Tennessee Valley Authority, Post Office Box 2000, Spring ... · C.' N3C-945, Procedure for...

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000

March 21, 2012

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001

Watts Bar Nuclear Plant, Unit 2NRC Docket No. 50-391

Subject: Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Pre-op TestInstructions

The following approved WBN Unit 2 Pre-op Test Instructions (PTIs) are enclosed:

PTI NUMBER Rev. TITLE

2-PTI-001-03 0 Main Steam Safety Valves

2-PTI-003A-02 0 Feedwater and Steam Generator Level

2-PTI-068-02 0 Reactor Coolant Flow Measurement

If you have any questions, please contact Pete Olson at (423) 365-3294.

Respectfully,

Raymond A. Hruby, Jr.General Manager, Technical ServicesWatts Bar Unit 2

Enclosures

,dejt

U.S. Nuclear Regulatory CommissionMarch 21, 2012

cc (Enclosures):

U. S. Nuclear Regulatory CommissionRegion IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257

NRC Resident Inspector Unit 2Watts Bar Nuclear Plant1260 Nuclear Plant RoadSpring City, Tennessee 37381

WATTS BAR NUCLEAR PLANT

UNIT 2 PREOPERATIONAL TEST

TITLE: MAIN STEAM SAFETY VALVES

Instruction No: 2-PTI-001-03

Revision No: 0000

PREPARED BY: J*Ls )ChCA / J,&a k--J DATE: 05/i S/,tPRINT NAME / SIGNATURE

REVIEWED BY: 14- i , /---- z-,./, . DATE: ___5_- _2-PRINT NAME I SIGNATURE

INSTRUCTION APPROVAL

JTG MEETINC. • -/ - 0V5

JTG CHAIRMArI. -- DATE:

PREOPEATiONAL STARTUP MANAGER DATEii1&4•

TEST RESULTS APPROVAL

JTG MEETING No:

JTG CHAIRMAN: DATE:

APPROVED BY: DATE:PREOPERATIONAL STARTUP MANAGER

SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010

Revision Log

Revision Affectedor Change Effective Page

Number Date Numbers Description of Revision/Change

0000 ALL Initial issue. This procedure was written usingUnit 1 PTI-001-03, Rev 0 as a guide.

Table of Contents

1.0 INTRODUCTION .................................................................................................. 4

1.1 Test Objectives ....................................................................................................... 4

1.2 Scope ............................................................................................................................ 4

2.0 REFERENCES ...................................................................................................... 5

2.1 Perform ance References .............................................. I .......................................... 5

2.2 Developmental References ...................................................................................... 5

3.0 PRECAUTIONS AND LIM ITATIO NS ........................................................................ 7

4.0 PREREQ UISITE ACTIO NS ....................................................................................... 8

4.1 Prelim inary Actions .................................................................................................. 84.2 Test Equipm ent .................................. ...................................................................... 10

4.3 Field Preparations ................................................................................................... 10

4.4 Approvals and Notifications .................................................................................... 10

5.0 ACCEPTANCE CRITERIA ..................................................................................... 11

6.0 PERFORMANCE ................................................................................................... 13

6.1 Main Steam Safety Valve Pressure Setpoint Testing ....................... ... 13

7.0 PO ST PERFORMANCE ACTIVITY ....................................................................... 16

8.0 RECO RDS .................................................................................................................. 17

8.1 QA Records ................................................................................................................ 178.2 Non-QA Records .................................................................................................... 17

Appendix A: TEST PROCEDURES/INSTRUCTIONS REFERENCE

REVIEW ................................................................................................. 18

Appendix B: TEM PORARY CONDITION LOG ........................................................... 19

Date

1.0 INTRODUCTION

1.1 Test Objectives

Demonstrate proper operation of the Main Steam Safety Valves (MSSVs).

1.2 Scope

Demonstrate (using a pressure assist device to measure the lifting pressure) thateach MSSV's setpoint meets its design requirement.

Demonstrate each MSSV properly reseats with absence of seat leakage followingsetpoint verification.

Date

2.0 REFERENCES

2.1 Performance References

A. SMP-9.0, Test Conduct

B. 2-S1-1-907, Testing and Setpoint Adjustment of Main Steam Safety ValvesUsing Trevitest Equipment.

C.' N3C-945, Procedure for Evaluation and Qualification of Piping SystemVibrations.

D. 2-PTI-068-01, HFT Heatup and Cooldown.

2.2 Developmental References

A. Final Safety Analysis Report (FSAR) Amendment 107

1. FSAR Table 14.2-1, Sheet 64 of 89, Steam Generator & AtmosphericRelief Valves Test Summary

2. FSAR Chapter 10.3 Main Steam Supply System

B. Drawings

1. Flow Diagrams

a. 2-47W801-1, Rev 3, FLOW DIAGRAM MAIN AND REHEAT STEAM.DRA 53949-201, Rev 0DRA 53949-202, Rev 0DRA 53949-203, Rev 0DRA 53949-204, Rev 0

2. Mechanical

a. 47W415-1 (AD), Rev 10, MECHANICAL MAIN STEAM RELIEF &SAFETY VALVE VENTSDRA 53949-100, Rev I

Date

2.2 Developmental References (continued)

C. Documents

1. NPG-SSD-WBN2-1-4002, Rev 3, Main Steam System.

2. 2-TSD-1-3, Rev 1, Main Steam Safety Valves Test.

3. 2-PTI-068-01, Draft, HFT Heatup and Cooldown.

4. 1-Si-1 -907, Rev 19 Testing and Setpoint Adjustment of Main Steam SafetyValves Using Trevitest Equipment.

To be verified against 2-SI-1-907 (Current Draft/Rev), Testing and SetpointAdjustment of Main Steam Safety Valves Using Trevitest Equipment, inAppendix A.

Date

3.0 PRECAUTIONS AND LIMITATIONS

A. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.

B. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a TDN in accordance with SMP-14.0 if theUNIDs match, exclusive of place-keeping zeros and train designators (e.g.2-HS-31-468 vs 2-HS-031-0468) and the noun description is sufficient toidentify the component. If the component label needs to be changed, a TagRequest (TR Card) should be processed in accordance with TI-12.14. Make anentry in the CTL and continue testing.

C. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.

D. Problems identified during the test shall be annotated on the Chronological TestLog (CTL) from SMP-9.0 including a description of the problem, the procedurestep when/where the problem was identified, corrective action steps taken toresolve the problem, and the number of the corrective action document, if onewas required.

E. Observe all Radiation Protection (RP) requirements when working in or nearradiological areas.

F. Ensure no adverse effects to the operation of Unit 1 structures, systems orcomponents result from test performance.

G. During performance of this test, system components will be hot. Test personnelshall exercise care in order to avoid contact with these surfaces.

H. Testing activities will occur in areas that will be physically demanding due tohigh temperatures. Heat stress of personnel could occur if safety precautionsare not followed.

1. A loud noise will occur anytime a Main Steam Safety Valve lift is achieved or if aSteam Generator Power Operated Valve is exercised for pressure control.Double hearing protection shall be used in the U2 Valve Vault Rooms duringperformance of this test.

J. Caution signs should be posted at the entrances to the Valve Vault rooms whiletesting is in progress to warn of heat stress and hearing risks.

WBN MAIN STEAM SAFETY VALVES 2-PTI-001 -03Unit 2 Rev. 0000

Page 8 of 19

Date

4.0 PREREQUISITE ACTIONS

NOTE

Prerequisite steps may be performed in any order unless otherwise stated and should becompleted as close in time as practicable to the start of Section 6.0

4.1 Preliminary Actions

[1] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision and, as needed,each test person assisting in this test has the current revisionincluding any change notices.

[2] OBTAIN copies of the applicable forms from the latest revisionof SMP-9.0, AND

ATTACH to this PTI for use during the performance of this PTI.

[3] ENSURE changes to the references listed on Appendix A havebeen reviewed and determined NOT to adversely affect thetest results.

[4] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, AND

ATTACH documentation of current drawing revision numbersand change paper that were reviewed to data package.

[5] EVALUATE open items for system 001 in Watts Bar IntegratedTask Equipment List (WITEL), AND

ENSURE that they will NOT adversely affect the testperformance and results.

[6] ENSURE required Component Testing has been completedprior to start of test.

Date

4.1 Preliminary Actions (continued)

[7] ENSURE outstanding Design Change Notices (DCN's),Engineering Design Change Requests (EDCR's) or TemporaryAlterations (TA's) do NOT adversely impact testing, AND

ATTACH documentation of DCNs, EDCRs and TAs that werereviewed to the data package.

[8] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance, AND

RECORD in Appendix B, Temporary Condition Log, ifrequired.

[9] VERIFY System cleanness, as required for the performance ofthis test, has been completed, in accordance with SMP-7.0and 2-CP-01-01.

[10] ENSURE components contained within the boundaries of thistest are under the jurisdictional control of PreoperationalStartup Engineering (PSE) and/or Plant Operations.

[11] ENSURE all piping supports required for testing are installedand adjusted, as required.

[12] VERIFY the U2 Reactor Coolant System is at the 5570FPlateau, in accordance with 2-PTI-068-01.

[13] PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact test performance.

[14] CONDUCT a pretest briefing with Test and Operationspersonnel, in accordance with SMP-9.0.

[15] ENSURE that communications are available for areas wheretesting is to be conducted.

[16] ENSURE Surveillance Instruction 2-SI-1-907 has beensubmitted to the JTG for concurrence that it adequatelysatisfies the requirements of this procedure.

JTG Meeting # 2-S1-1-907, Rev #

Date

4.2 Test Equipment

Measuring & Test Equipment utilized for this procedure will be specified in2-SI-1-907.

4.3 Field Preparations

None

4.4 Approvals and Notifications

[1] OBTAIN permission of the Preoperational Startup Manager tostart the test.

Preoperational Startup Manager DateSignature

[2] OBTAIN Unit 2 Supervisor (US/SRO) or Shift Manager (SM)authorization.

U2 US/SRO/SM Signature Date

Date

5.0 ACCEPTANCE CRITERIA

[1] Main Steam Safety Valves lift at the following pressures(determined using a pressure-assist device) (Step 6.1141):

Valve Setpoint (psig)

Steam Generator Loop I

2-SFV-1-522 1211.76-1236.24

2-SFV-1-523 1202.85-1227.15

2-SFV-1 -524 1192.95-1217.05

2-SFV-1 -525 1183.05-1206.95

2-SFV-1 -526 1173.15-1196.85

Steam Generator Loop 2

2-SFV-1 -517 1211.76-1236.24

2-SFV-1 -518 1202.85-1227.15

2-SFV-1 -519 1192.95-1217.05

2-SFV-1 -520 1183.05-1206.95

2-SFV-1 -521 1173.15-1196.85


2-SFV-1-512 1211.76-1236.24

2-SFV-1-513 1202.85-1227.15

2-SFV-1-514 1192.95-1217.05

2-SFV-1-515 1183.05-1206.95

2-SFV-1-516 1173.15-1196.85


2-SFV-1-527 1211.76-1236.24

2-SFV-1 -528 1202.85-1227.15

2-SFV-1 -529 1192.95-1217.05

2-SFV-1-530 1183.05-1206.95

2-SFV-1-531 1173.15-1196.85

Date

5.0 ACCEPTANCE CRITERIA (continued)

[2] Main Steam Safety Valves reseat with no audible or visibleseat leakage (Step 6.1[5]).

Valve

Steam Generator Loop I Steam Generator Loop 3

2-SFV-1-522 2-SFV-1 -512

2-SFV-1-523 2-SFV-1-513

2-SFV-1 -524 2-SFV-1-514

2-SFV-1 -525 2-SFV-1-515

2-SFV-1-526 2-SFV-1 -516

Steam Generator Loop 2 Steam Generator Loop 4

2-SFV-1-517 2-SFV-1 -527

2-SFV-1 -518 2-SFV-1 -528

2-SFV-1-519 2-SFV-1 -529

2-SFV-1-520 2-SFV-1 -530

2-SFV-1 -521 2-SFV-1 -531

Date

6.0

6.1

PERFORMANCE

Main Steam Safety Valve Pressure Setpoint Testing

[1] VERIFY that all Prerequisites Actions in Section 4.0 arecomplete.

NOTES

1) 2-SI-1-907 shall be performed (through Post Performance Activities) for all twentyMain Steam Safety Valves.

2) Steps 6.1[2] through 6.1[5] may be performed concurrently, on a component bycomponent basis.

[2] PERFORM 2-S1-1-907, Testing and Setpoint Adjustment ofMain Steam Safety Valves Using Trevitest Equipment.

NOTES

1) Piping vibration is to be visually monitored in accordance with N3C-945 (visualmethod), during transient conditions.

2) Walkdown should be performed on a loop by loop basis, where a given MSS loopwalkdown is performed during MSSV lift of a valve on that loop.

3) Post Test walkdown may be performed for areas/components inaccessible duringtesting to determine if damaging vibration occurred during the test.

4) If vibration is excessive, initiate a Test Deficiency Notice (TDN) and initial Step 6.1[3].

[3] WALKDOWN the portions of the Main Steam System locatedin the Valve Vault Rooms and U2 Containment, AND

VERIFY the transient piping and component vibration isacceptable.

Date

6.1 Main Steam Safety Valve Pressure Setpoint Testing (continued)

NOTES

1) 2-SI -1-907 will exercise each MSSV until two consecutive lift setpoints, withoutadjustment between lifts, are verified to be within acceptance criteria.

2) The "Last, As-Left Setpoint" is the final acceptable valve lift and the "Next to Last, AsLeft Setpoint" is the lift performed just prior to the "Last, As-Left Setpoint".

[41 RECORD as-left setpoint data from 2-SI-1-907 for each MainSteam Safety Valve, AND

VERIFY the setpoint data meets the listed acceptance criteria.(Acc Crit)

UNID Last, As-Left, Next to Last, As-Left, Acceptance Acceptance CriteriaSetpoint (PSIG) Setpoint (PSIG) Criteria (PSIG) Met

(INITIAL for Yes)2-SFV-1 -512 1211.76-1236.24

2-SFV-1 -513 1202.85-1227.15

2-SFV-1-514 1192.95-1217.05

2-SFV-1-515 1183.05-1206.95

2-SFV-1 -516 1173.15-1196.85

2-SFV-1-517 1211.76-1236.24

2-SFV-1-518 1202.85-1227.15

2-SFV-1-519 1192.95-1217.05

2-SFV-1-520 1183.05-1206.95

2-SFV-1-521 1173.15-1196.85

2-SFV-1-522 1211.76-1236.24

2-SFV-1-523 1202.85-1227.15

2-SFV-1-524 1192.95-1217.05

2-SFV-1-525 1183.05-1206.95

2-SFV-1 -526 1173.15-1196.85

2-SFV-1 -527 1211.76-1236.24

2-SFV-1-528 1202.85-1227.152-SFV-1-529 1192.95-1217.05

2-SFV-1-530 1183.05-1206.95

2-SFV-1-531 1173.15-1196.85

Date

6.1 Main Steam Safety Valve Pressure Setpoint Testing (continued)

[5] VERIFY no, as-left, seat leakage (audible/visible) was notedduring 2-SI-1 -907 performance, after final re-seat for each ofthe following valves: (Acc Crit)

UNID Acceptance Criteria Met

(INITIAL for Yes)

2-SFV-1-512

2-SFV-1 -513

2-SFV-1-514

2-SFV-1-515

2-SFV-1-516

2-SFV-1 -517

2-SFV-1-518

2-SFV-1 -519

2-SFV-1-520

2-SFV-1-521

2-SFV-1-522

2-SFV-1 -523

2-SFV-1 -524

2-SFV-1-525

2-SFV-1-526

2-SFV-1 -527

2-SFV-1-528

2-SFV-1 -529

2-SFV-1 -530

2-SFV-1-531

Date

7.0 POST PERFORMANCE ACTIVITY

[1] ENSURE that Post-test calibration of the M&TE used in2-S1-1 -907 to record quantitative acceptance criteria in thisprocedure has been satisfactorily performed, AND

ATTACH a copy of Post-test calibration results to this testpackage.

[2] ENSURE any temporary conditions recorded in Appendix B,Temporary Condition Log, are addressed for necessaryrestoration as applicable (N/A if no conditions recorded).

1 st

Cv

[3] ATTACH a copy of the 2-SI-1 -907 data record utilized inperformance of this procedure to this test package.

[4] NOTIFY the Unit 2 US/SRO/SM of the test completion andsystem alignment.

Date

8.0 RECORDS

8.1 QA Records

Completed Test Package

8.2 Non-QA Records

None

Appendix A(Page I of 1)

TEST PROCEDURES/INSTRUCTIONS REFERENCE REVIEW

Date

NOTES

1) Additional copies of this table may be made as necessary.

2) Initial and date indicates review has been completed for impact.

PROCEDURE/ INITIAL AND DATE.INSTRUCTION REVISIONICHANGES (NIA for no change)

U2 FSAR - Amendment 104

Section 10.3

Table 14.2-1 Sh 64 of 89

NPG-SSD-WBN2-1-4002,Rev 3

2-TSD-1-3, Rev 1

2-PTI-068-01, Draft

1-S1-1-9071, Rev 19

___________________________ I _____________________________ I ___________________

1 To be Reviewed against current, equivalent, U2 Procedure/Instruction for impact

Appendix B(Page 1 of 1)

TEMPORARY CONDITION LOG

Date

NOTE

These steps will be N/A'd if no temporary condition existed. Additional copies of this tablemay be made as necessary.

ITEM TEMPORARY CONDITION PERFORMED RETURNED TO NORMALNo. DESCRIPTION Step Performed By/Date Step Returned By/Date

No. CV By/Date No. CV By/Date



TITLE: Feedwater and Steam Generator Level

Instruction No: 2-PTI-003A-02

Revision No: 0000

PREPARED BY: 10$epis E.hJod-fe,.. DATE: ___________

PRINT NAME /iVIGNATURE

REPVIENWED BY: e 2-A RDATE:PRINT NAME / SIGNATURE


JTG MEETING No:

JTG CHAIRMAN:

APPROVED BY:

DATE: Un-

DATE: t


JTG MEETING No:

JTG CHAIRMAN:

APPROVED BY:

DATE:

DATE:PREOPERATIONAL STARTUP MANAGER

SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010

WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page 2 of 182

Revision Log

Revision Affectedor Change Effective PageNumber Date Numbers Description of RevisionlChange

0 ALL Original Issue


Page 3 of 182

Table of Contents

1.0 INTRODUCTION ................................................ 6

1.1 T est O bjectives ........ i .............................................................................................. 6

1 .2 S co pe ....................................................................................................... , ................. .. 6

2.0 REFERENCES ................................................. 6

2.1 Perform ance References ... 6......................................................................................... 6

2.2 Developm ental References ......................................................................................... 7

3.0 PRECAUTIONS AND LIMITATIONS ......................................................................... 12

4.0 PREREQUISITE ACTIONS . 14

4.1 Preliminary Actions ............................................ 14

4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ...................... 17

4.3 Field Preparations .............................................. 18

4.4 Approvals and Notifications ................................................................................... 22

5.0 ACCEPTANCE CRITERIA ............... . . .............................................. 23

6.0 PERFORMANCE ..................................................... 25

6.1 SG 1 Narrow Range Level Instrument Test ............................. 26


6.3 SG 3 Narrow Range Level Instrument Test ......................................................... 55


7.0 POST PERFORMANCE ACTIVITY ............................................................................ 83

8.0 R EC O R D S ................................................................... ............................................ 8 3

Appendix A: Test Procedureslinstructions Reference Review ................ 84

Appendix B: Temporary Condition Log ............. ..................................................... 86

Appendix C: Permanent Plant Instrumentation Log ............................................... 87

Table 1: Computer Point Verification Log ............................ 90

Table 2: Train A Plastic Screw Verification ...................................................... 91

Table 3: Train B Plastic Screw Verification ........................... 93

Data Sheet 1: SG I - Initial Level Verification Data ......................... 95


Page 4 of 182

Data Sheet 2:

Data Sheet 3:

Data Sheet 4:

Data Sheet 5:

Data Sheet 6: -

Data Sheet 7:

Data Sheet 8:

Data Sheet 9:

Data Sheet 10:

Data Sheet 11:

Data Sheet 12:

Data Sheet 13:

Data Sheet 14:

Data Sheet 15:

Data Sheet 16:

Data Sheet 17:

Data Sheet 18:

,Data Sheet 19:

Data Sheet 20:

Data Sheet 21:

Data Sheet 22:

Data Sheet 23:

Data Sheet 24:

Data Sheet 25:

Data Sheet 26:

Table of Contents (continued)

SG I - 50% Level Verification Data.............................. 97

SG I - 75% Level Verification Data ..................................................... 99

SG I - 100% Tap Verification Data .............................. ........................... 101

SG I - 100% Level Verification Data ..................................................... 102

SG I - 75% Level Verification Data ......................... 104

SG 1 - 50% Level Verification Data ........................................................ 106

SG I - 25% Level Verification Data ........................................................ 108

SG I - 0% Tap Verification Data ............................................................. 110

SG 1 - 0% Level Verification Data ........................... 1

SG I - 25% Level Verification Data ........................................................ 113

SG I - Final Level Verification Data ............................... 115

SG 2 - Initial Level Verification Data•..................................................... 117

SG 2 - 50% Level Verification Data ........ ................................................ 119

SG 2 - 75% Level Verification Data ......................... 121

SG 2 - 100% Tap Verification Data ........ ...................... I ................... 123,

SG 2 - 100% Level Verification Data ..................................................... 124



SG 2 - 25% Level Verification Data .................................................... 130

SG 2 - 0% Tap Verification Data ...................................................... 132

SG 2 -0% Level Verification Data ........................................................ 133


SG 2 - Final Level Verification Data ......................... 137

SG 3 - Initial Level Verification Date ..... ............................ ............... 139


I WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page5 of 182

Data Sheet 27:

Data Sheet 28:

Data Sheet 29:

Data Sheet 30:

Data Sheet 31:

Data Sheet 32:

Data Sheet 33:

Data Sheet 34:

Data Sheet 35:

Data Sheet 36:

Data Sheet 37:

Data Sheet 38:

Data Sheet 39:

Data Sheet 40:

Data Sheet 41:

Data Sheet 42:

Data Sheet 43:

Data Sheet 44:

Data Sheet 45:

Data Sheet 46:

Data Sheet 47:

Data Sheet 48:

Table of Contents (continued)

SG 3 - 75% Level Verification Data .................................. 143

SG 3 - 100% Tap Verification Data ...................................... ................ 145

SG 3 - 100% Level Verification Data ...................................................... 146


SG 3 - 50% Level Verification Data ....................................................... 150

SG 3 - 25% Level Verification Data ................................... 152

SG 3 -0% Tap Verification Data ............................................................. 154

SG 3 -0% Level Verification Data .......................... 155


SG 3 - Final Level Verification Data ...................................................... 159

SG 4 - Initial Level Verification Data ................................... ................... 161



SG 4 - 100% Tap Verification Data............................ 167


SG 4 - 75% Level Verification Data .............................. 170

SG 4 - 50% Level Verification Data ........... ...... I ...................................... 172


SG 4-0% Tap Verification Data ............... .............................................. 176

SG 4 - 0% Level Verification Data ...................................................... 177

SG 4 - 25% Level Verification Data .............. ........... 179

SG 4 - Final Level Verification Data ........ ........................... 1 81

WBN, Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page 6 of 182

1.0 INTRODUCTION

1.1 Test Objectives

This test will demonstrate the following test objectives:

A. Proper operation of the narrow range level indication over the full Narrow-Range (NR).

'B. NR instrumentation digital outputs to the Solid State Protection System (SSPS).

1.2 Scope

A. The NR level instrumentation shall agree between each loop.

1. The highest and lowest indication for the three NR level indicators for eachsteam generator shall be within 5% of each other.

2. The highest and lowest calculated level for the three NR level transmittersfor each steam generator shall be within 1.1% of each other.

B. The NR level instrumentation provides digital outputs to the Solid StateProtection System for the following conditions:

1. Hi-Hi level digital output from the NR level instrumentation to the SSPS.

2. Lo-Lo level digital output from the NR level instrumentation to the SSPS.

2.0 REFERENCES

2.1 Performance References

A. SMP-9.0, Conduct of Test

B. SMP-15.0, Status and Control of Isolation Devices

C. 2-SOI-2&3.01, Condensate and Feedwater System

D. 2-SOI-15.01, System Operating Instruction for Steam Generator Blowdown

E. 2-PTI-68-1, Hot Functional Testing


Page 7 of 182


A. Final Safety Analysis Report (FSAR), Amendment 107

1. Table 14.2.1, Integrated Hot Functional Tests Test Summary, Sheet 77



B. Drawings

1. Flow Diagrams

a. 2-47W801-2, Rev. 4, Flow Diagram Steam Generator BlowdownSystem, DRA-53177-2 and -3 Rev. 0, DRA-53223-1 Rev. 0, DRA-53949-205 through -208, -219 through -222, Rev. 0, DRA-54449-1,Rev. 0, DRA-52340-90, Rev. 0, DRA -53606-18, Rev. 0 DRA-54623-100, Rev. 0

b. 2-47W803-1, Rev. 5, Flow Diagram Feedwater, DRA-53128-110, Rev.0,- DRA-53276-22, Rev. 0, DRA-53380-1, -2, Rev. 0, DRA-53390-45, -46, Rev. 0, DRA-53391-35, Rev. 0, DRA-53525-1, Rev. 0, DRA-53876-1through -5,-320 Rev. 0, DRA-54039-75, Rev. 0, DRA-52310-12, Rev. 0, DRA-52317-304 through -308, Rev. 0, DRA-54145-111, -

112, Rev. 0, DRA-54263-96 through -99, Rev, 0

2. Electrical

a. 45N2676-1, Rev. E, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-1

b. 45N2676-2, Rev. E, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-2

c. 45N2676-4, Rev. AA, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-4, DRA 56336-114, Rev. 0, DRA 54706-166, Rev. 0

d. 45N2676-5, Rev. K, Wiring Diagram Solid State Protection Sys TrainA Connection Diagram Sh-5, DRA 56•336-115, Rev. 0

e. 45N2677-1, Rev. E, Wiring Diagram Solid State Protection Sys TrainB Conhection Diagram Sh-1

f. 2-45N2677-2, Rev. E, Wiring Diagram Solid State Protection SysTrain B Connection Diagram Sh-2


Page 8 of 182


g. 45N2677-4, Rev. AA, Wiring Diagram Solid State Protection Sys TrainB Connection Diagram Sh-4, DRA 56336-116, Rev. 0

h. 45N2677-5, Rev. L, Wiring Diagram Solid State Protection Sys Train BConnection Diagram Sh-5, DRA 56336-117, Rev. 0

3. Mechanical

None

4. Logic/Control

a. 2-47W610-3-1, Rev. 2, Electrical Control Diagram Main Aux FWSystem, DRA-52319-6, Rev. 0, DRA-53301-110, Rev. 0, DRA-55180-37, Rev. 0, DRA-55347-54, Rev. 0, DRA-52378-415, Rev. 2, DRA-52317-55, Rev. 0

b. 2-47W610-3-1A, Rev. 0, Electrical Control Diagram Main Aux FWSystem, DRA-52319-7, Rev. 0, DRA-53301-111 through -116, Rev. 0,DRA-55180-38, Rev. 0, DRA-52378-423, Rev. 0

c. 2-47W610-3-1B, Rev. 0, Electrical Control Diagram Main Aux FWSystem, DRA-52319-8, Rev.0, DRA-53600-7, Rev. 0, DRA-53873-311, Rev. 0, DRA-55347-55,-56, Rev. 0, DRA-52310-13, Rev. 0,52378-416, Rev. 2, DRA-54144-7,-322, Rev. 0

d. 2-47W610-3-IC, Rev. 1, Electrical Control Diagram Main Aux FWSystem, DRA-52319-9, Rev. 0, DRA-55180-40, Rev. 0, DRA-55347-47, Rev. 0, DRA-52378-539, Rev. 1, DRA-52675-3, Rev. 0

e. 2-47W610-3-1D, Rev. 2, Electrical Control Diagram Main Aux FWSystem, DRA-52319-10, Rev. 0, DRA-53600-8, Rev. 0, DRA-55180-41, Rev. 0, DRA-55347-58, -59, Rev. 0, 52378-417, Rev. 2, DRA-53217-56, Rev. 0, DRA-54144-233, Rev. 0

f. 2-47W610-3-2, Rev. 1, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-11, Rev. 0, DRA-55180-42, Rev. 0, DRA-55347-60, Rev. 0, DRA-52378-540, Rev. 1, DRA-52675-5, Rev. 0

g. 2-47W610-3-2A, Rev. 3, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-12, Rev. 0, DRA-53315-2,-3, Rev. 0, DRA-53559-157, Rev. 0, 53600-9, Rev. 0, 53876-301 ,-304, Rev. 0, DRA-'55180-43, Rev. 0, DRA-55347-61, -62, Rev. 0, DRA-52378-418, Rev.1, DRA-52378-419, Rev.2, DRA-53217-57, Rev. 0, DRA-51444-2341Rev. 0


Page 9 of 182


h. 2-47W610-3-2B, Rev. 1, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-13, Rev. 0, DRA-55180-44, rev. 0, DRA-55347-63, Rev. 0, DRA-52378-541, Rev. 1

i. 2-47W610-3-2C, Rev. 3, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-14, rev. 0, DRA-53600-10, Rev. 0, DRA-55180-45, Rev. 0, DRA-55347-64,-65, Rev. 0, DRA-52378-420, Rev. 1, DRA-53217-58, Rev. 0, DRA-54144-235, Rev. 0

j. 2-47W610-3-4, Rev. 2, Electrical Control Diagram Main & Aux FWSystem, DRA-52319-15, Rev. 0, DRA-53097-14, Rev. 0, DRA-53315-1, Rev. 0, DRA-53876-305, Rev. 1, DRA-53876-307, Rev. 0, DRA-52378-421, Rev. 0

k. 2-47W61.1-3-2, Rev. 5, Electrical Logic Diagram Feedwater System,DRA-53876-317, Rev. 0, 54144-237,-238, Rev. 0

1. 2-47W611-3-3, Rev. 2, Electrical Logic Diagram Auxiliary FeedwaterSystem, DRA-52376-7, Rev. 1, DRA-52343-34,-35, Rev. 0, DRA-54208-21, Rev. 0, DRA-52427-43, Rev. 0, DRA-53288-69,-70, Rev. 0,DRA-54145-7,-8, Rev. 0

m. 2-47W611-3-5, Rev. 2, Electrical Logic Diagram Feedwater System,DRA-53876-316, Rev. 0, DRA-52378-604, Rev. 1

n. 2-45B655-3C, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-3C, DRA-53301-132, Rev. 0, DRA-54449-12, Rev. 0,DRA-55180-3, Rev. 0, DRA-52343-230, Rev. 0, DRA-52378-222,-233,-252, Rev. 0, 54144-1, Rev. 0, DRA-54145-12, Rev. 0

o. 2-45B655-4C, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-4C, DRA-55180-7, Rev. 0, DRA-52408-10, Rev. 0, DRA-53439-10, Rev. 0, DRA-53939-329, Rev. 0

p. 2-45B655-4D, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-4D, DRA-55180-9, Rev. 0

q. 2-45B655-6B, Rev. 0, Main Control Room Annunciator Inputs WindowBox XA-55-6B, DRA-53301-135, Rev. 0, DRA-55180-14, Rev. 0

5. Vendor Drawings

a. 108D408-1, Rev. 43, Process Control Block Diagram

b. 108D408-17, Rev. 12, Process Control Block Diagram

c. 108D408-19, Rev. 10, Process Control Block Diagram


Page 10 of 182.


d. 108D408-20, Rev. 16, Process Control Block Diagram

e. 108D408-33, Rev. F, Process Control Block Diagram

f. 108D408-34, Rev. 9, Process Control Block Diagram

g. 108D408-41, Rev. D, Process Control Block Diagram

h. 108D408-49, Rev. 2, Process Control Block Diagram

i. 108D408-50, Rev. 2, Process Control Block Diagram

j. 108D408-54, Rev. 2, Process Control Block Diagram

k. 108D408-55, Rev. 3, Process Control Block Diagram

I. 108D408-56, Rev. 3, Process Control Block Diagram

m. 2-54114-1-7246D11-06, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-763, Rev. 0

n. 2-54114-1-7246Dl1-07, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-764, Rev. 0

o. 2-54114-1-7246Dl1-09, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-766, Rev. 0

p. 2-54114-1-7246311-11, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-768, Rev. 0

q. 2-54114-1-7246Dl1-12, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-769, Rev. 0

r. 2-54114-1-7246D11-20, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-777, Rev. 0, DRA-53352-96,Rev. 0

s. 2-54114-1-7246D11-21, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-778, Rev. 0

t. 2-54114-1-7246Dl1-22, Rev. 0, Solid State Protection SystemInterconnection Diagram, DRA-52328-779, Rev. 0

u. 2-54114-1-7246Dl1-24, Rev. K, Solid State Protection SystemInterconnection Diagram, DRA-52328-781, Rev. 0

v. 1082H70-27D, Rev. AE, Output Relays

2.2


Page 11 of 182

Developmental References (continued)

6. Other

a. 2-TSD-3A-2, Rev. 0, Feedwater and Steam Generator Level TestScoping Document

b. SSD-1-LPF-3-35, Rev. 11, Scaling & Setpoint Document LoopDrawing Steam Generator I Level Control To be verified against SSD-2-LPF-3-35 [Later] in Appendix A

c. SSD-1-LPF-3-48, Rev. 10, Scaling & Setpoint Document LoopDrawing Steam Generator 2 Level Control To be verified against SSD-2-LPF-3-48 [Later] in Appendix A

d. SSD-1-LPF-3-90, Rev. 10, Scaling & Setpoint Document LoopDrawing Steam Generator 3 Level Control To be verified against SSD-2-LPF-3-90 [Later] in Appendix A

e. SSD-1-LPF-3-103, Rev.10, Scaling & Setpoint Document LoopDrawing Steam Generator 4 Level Control To be verified against SSD-2-LPF-3-103 (Later] in Appendix A

C. Vendor Manuals

None

D. Documents

1. 2-L-3-38, Rev. 0, Setpoint and Scaling Document Steam Generator NRLevel







Page 2 of 182







12. 2-L-3-110, Rev. 0, Setpoint and Scaling Document Steam Generator NR

Level

13. 2-SOI-2&3.01, Rev. 0 [Draft], Condensate and Feedwater System

14. 2-SOI-15.01, Rev. 0 [Draft], Steam Generator Blowdown System


A. Standard precautions shall be followed for working around energized electricalequipment in accordance with TVA Safety Procedure 1021.

B. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.

C. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a Test Deficiency Notice, TDN, in.accordance with SMP-14.0, if the UNIDs match, exclusive of place-keepingzeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and thenoun description is sufficient to identify the component. If the component labelneeds to be changed,. a Tag Request Form (TR Card) should be processed inaccordance with TI-12.14. Make an entry in the CTL and continue testing.

D. All wires removed/lifted from a terminal shall be identified and taped or coveredwith an insulator to prevent personnel or equipment hazard and possiblespurious initiations. The wires should be labeled with the work implementing.document number that required them to be lifted if left unattended.

E. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.


Page 13 of 182

3.0 PRECAUTIONS AND LIMITATIONS (continued)

F. Problems identified during the test shall be annotated on the CTL from SMP-9.0including a description of the problem, the procedure step when/where theproblem was identified, corrective action steps taken to resolve the problem,and the number of the corrective action document, if one was required.

G. Observe all Radiation Protection (RP) requirements when working in or nearcontaminated areas.

H. Ensure there are no adverse effects to the operation of Unit 1 structures,systems, or components.

1. Test personnel will coordinate with Unit 1 Operations when manipulating Unit 1equipment if required.

J. System water chemistry is within system specifiable parameters especially forfluids supplied from external sources.

K. During Hot Functional Testing, feedwater additions should be controlled tominimize the thermal stress cycles of the feedwater nozzle. Feedwateradditions should be slow in order to minimize the possibility of water hammerand thermal shock to the steam generator internals.

L. Primary to secondary differential pressure should not exceed 1600 psid duringnormal plant operations.

M. At Operations discretion, steam generator blowdown may be initiated orincreased during level decreases to allow some feedwater flow to bemaintained. It is preferable that blowdown be kept to a minimum during levelincreases to avoid lowering Reactor Coolant System (RCS) temperature due toexcessive feedwater flowrates.

N. The Steam Generator Hi Level Alarms and Low Pwr Lo Level Alarmsassociated with 2-L-148, 2-L-156, 2-L-164, 2-L-171, 2-L-172, 2-L-173, 2-L-174,and 2-L-175 should operate at approximately 74% and 25%. If this does notoccur, appropriate work documents should be generated and an entry made inthe CTL.

WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000.

Page 14 of 182

Date

4.0 PREREQUISITE ACTIONS

NOTE

Prerequisite steps may be performed in any order unless otherwise stated and should be completedas close in time as practicable to the start of the instruction subsection to which they apply.




[2] ENSURE changes to the references listed on Appendix A,have been reviewed, and determined NOT to adversely affectthe test performance.

[3] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, and

ATTACH documentation of current drawing revision numbersand change paper that were reviewed to the data package.

[4] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision including any changenotices and as needed, each test person assisting in this testhas the current revision including any change notices.

[5] EVALUATE open items in Watts Bar Integrated TaskEquipment-List (WITEL), ANDENSURE that they will NOT adversely affect the test

performance results.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4 _

[6] ENSURE required Component Testing has been completedprior to start of test


Page 15 of 182

Date


[7] ENSURE outstanding Design Change Notices (DCN's),Engineering Document Construction Releases (EDCR's) orTemporary Alterations (TA's) do NOT adversely impact testing,AND

ATTACH documentation of DCN's, EDCR's and TA's thatwere reviewed to the data package.

[8] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance. If required, items will be recorded in AppendixB, Temporary Condition Log.

[9] ENSURE all piping supports required for testing are installedand adjusted as required.

[10] VERIFY System cleanness as required for the performance ofthis test has been completed in accordance with SMP-7.0.

[11] VERIFY plant instruments required for test performance, listed onAppendix C, Permanent Plant Instrumentation Log, have been filled,

vented; (as required) placed in service and are within their calibrationinterval.

A. Subsection 6.1

B. Subsection .6.2

C. Subsection 6.3

D. Subsection. 6.4

[12] VERIFY Measuring and Test Equipment (M&TE) required for testperformance has been (as required) filled, vented , placed inservice and recorded on Measuring and Test Equipment Log(Appendix F of SMP-9.0)

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4


Page 16 of 182

Date


[13] VERIFY M&TE calibration due dates will support the completionof this test performance.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

[14] ENSURE System 55, Annunciator and Sequential EventsRecording System applicable TBK switches are ON, the applicableMaster Switches are ON, and window software input (s) are

ENABLED for the following'Annunciator windows:

A. 2-XA-55-3C/60-B (SubSection 6.1)

B. 2-XA-55-3C/60-D (SubSection 6.1)

C. 2-XA-55-3C/61-B (SubSection 6.2)

D. 2-XA-55-3C/61-D (SubSection 6.2)

E. 2-XA-55-3C/62-B (SubSection 6.3)

F. 2-XA-55-3C/62-D (SubSection 6.3)

G. 2-XA-55-3C/63-B (SubSection 6.4)

H. 2-XA-55-3C/63-D (SubSection 6.4)

I. 2-XA-55-3C/63-F (SubSections 6.1, 6.2, 6.3, and 6.4)

J. 2-XA-55-6B/116-B (SubSection 6.1)

K. 2-XA-55-6B/1 17-B (SubSection 6.2)

L. 2-XA-55-6B/1 18-B (SubSection 6.3)

M. 2-XA-55-6B/1 19-B (SubSection 6.4)

N. 2-XA-55-6B/1 16-D (SubSection 6.1)

0. 2-XA-55-6B/1 17-D (SubSection 6.2)

P. 2-XA-55-6B/1 18-D (SubSection 6.3).


Page 17 of 182

Date


Q. 2-XA-55-6B/1 19-D (SubSection 6.4)

R. 2-XA-55-6B/1 16-E (SubSection 6.1)

S. 2-XA-55-6B/11 17-E (SubSection 6.2)

T. 2-XA-55-6B/118-E (SubSection 6.3)

U. 2-XA-55-6B/1 19-E (SubSection 6.4)


[16] PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact test performance.

[17] CONDUCT a pretest briefing with Test and Operationspersonnel in accordance with SMP-9.0.

[18] ESTABLISH communications in areas where testing is to beconducted.

[191 REVIEW preventive maintenance for system/componentscovered by this test, AND

VERIFY no conditions exist that will impact test performance.

4.2 Special Tools, Measuring and Test Equipment, Parts, andSupplies

[11 ENSURE eighteen (18) digital multimeters (0-1.5 VDC +0.02%) are available. Twelve will be installed in Step 4.3[3]and six will be installed and used consecutively in Sections6.1, 6.2, 6.3, and 6.4


Page 18 of 182

Date


[1] ENSURE the Plant Computer is available and the ComputerPoints listed on Table 1 are active and the description andstatus for each computer point has been verified.

[2] ENSURE the following systems are operational and have been

placed in service to the extent necessary to perform this test:

A. System 032, Control Air - Provide control air to all AOVs.

B. System 003A, Main Feedwater - Has the SteamGenerator Level controls.

C. System 003B, Auxiliary Feedwater - Provide feedwater toraise Steam Generator levels.

D. System 015, Steam Generator Blowdown - Provideblowdown to lower Steam generator levels.

E. System 002, Condensate - provide a source of water tothe Main Feedwater System and condenser vacuum.

F. System 99, Reactor Protection System - inputs to and.from the Steam Generator level control system.

G. System 98, Foxboro I/A (DCS) - inputs to and from theSteam Generator Level Control.


Page 19 of 182

Date

4.3 Field Preparations (continued)

NOTE

The test points are located on the front of each of the cabinets listed in 4.3[3]. If there arenot enough multi-meters available to install all of them for all Subsections, the test mayproceed with installation of those necessary to perform each subsection.

[3] ENSURE voltmeters are installed and labeled at the followinglocations:

A.: Panel 2-R-12, SG 1 Level trip, Test Point 2LP/517B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C10P)

Cv

B. Panel 2-R-11, SG 1 Level trip, Test Point 2LP/518B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C9P)

Cv

C. Panel 2-R-5, SG 1 Level trip, Test Point 2LP1519B(Subsection 6.1) (Control Building Auxiliary InstrumentRoom 708/C9Q)

Cv

D. Panel 2-R-12, SG 2 Level trip, Test Point 2LP/527B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/CI0P)

CV

E. Panel 2-R-1 1, SG 2 Level trip, Test Point 2LP/528B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/C9P)

Cv

F. Panel 2-R-5, SG 2 Level trip, Test Point 2LP/529B(Subsection 6.2) (Control Building Auxiliary InstrumentRoom 708/C9Q)

CV

WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev.0000

Page 20 of 182

Date


G. Panel 2-R-12, SG 3 Level trip, Test Point 2LP/537B(Subsection 6.3) (Control Building Auxiliary InstrumentRoom 708/C10P)

CV

H.: Panel 2-R-1 1, SG 3 Level trip, Test Point 2LP/538B(Subsection 6.3)(Control Building Auxiliary InstrumentRoom 708/C9P)

CV

I. Panel 2-R-5, SG 3 Level trip, Test Point 2LP/539B(Subsection 6.3) (Control Building Auxiliary InstrumentRoom 708/C9Q)

CV

J. Panel 2-R-12, SG 4 Level trip, Test Point 2LP/547B(Subsection 6.4)(Control Building Auxiliary InstrumentRoom 708/C10P)

CV

K. Panel 2-R-1 1, SG 4 Level trip, Test Point 2LP/548B(Subsection 6.4) (Control Building Auxiliary InstrumentRoom 708/C9P)

CV

L. Panel 2-R-5, SG 4 Level trip, Test Point 2LP/549B(Subsection 6.4) (Control Building Auxiliary InstrumentRoom 708/C9Q)

CV

[4] VERIFY Steam Generator I level is stable at 38%(programmed level) as indicated on 2-FR-3-35, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.1).

[5] VERIFY Steam Generator 2 level is stable at 38%(programmed level) as indicated on 2-FR-3-48, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.2).


Page 21 of 182

Date


[6] VERIFY Steam Generator 3 level is stable at 38%(programmed level) as indicated on 2-FR-3-90, STM-FWFLOW & NR LEVEL on panel 2-M4 (SubSection 6.3).

[7] VERIFY Steam Generator 4 level is stable at 38%-(programmed level) as indicated on 2-FR-3-103, STM-FWFLOW & NR LEVEL on panel 2-M-4 (SubSection 6.4).

[8] VERIFY that Hot Functional Testing is in progress at the 5570 Fplateau per 2-PTI-68-1.

[9] VERIFY that SG 1 LEVEL CONTROL is in Manual.(SubSection 6.1)




,[13] ENSURE that the field side wiring is landed with plastic screwsin 2-R-48 at the terminals listed on Table 2 in accordance withSMP-15.0. These will isolate the trips and Feedwater isolationsignals.

[14] ENSURE that the field side wiring is landed with plastic screwsin 2-R-51 at the terminals listed on Table 3 in accordance withSMP-15.0. These will isolate the trips and Feedwater isolationsignals.


Page 22 of 182

Date


[1] Prior to start of the test; OBTAIN permission of thePreoperational Startup Manager to start the test.

Preoperational Startup ManagerSignature

Date

[21 Prior to start of the test; OBTAIN the Unit 2 Supervisor's(US/SRO) or Shift Manager's (SM) authorization.

US/SRO/SM Signature Date


Page 23 of 182


A. Paragraph/sentences/tables/steps which determine acceptance criteria shall bedesignated by [ACC CRIT]

B. The NR level instrumentation shall agree between each loop

1. The highest and lowest indication for the three NR level indicators for eachsteam generator shall be within 5% of each other.

a. Steam Generator 1 (Step 6.1[461)

b. Steam Generator 2 (Step 6.2[46])

c. Steam Generator 3 (Step 6.3[46])

d. Steam Generator 4 (Step 6.4[46])

2. The highest and lowest calculated level for the three NR level transmittersfor each steam generator shall be within 1.1% of each other.

a. Steam Generator 1 (Step 6.1(46])

b. Steam Generator 2 (Step 6.2[46])



C. The NR level instrumentation provides digital outputs to the solid stateprotection system for the following conditions.

1. Hi-Hi Level 82.4% (79.9% - 84.9%)

a. Steam Generator 1 (Step 6.1(11])

b. Steam Generator 2 (Step 6.2111])

c. Steam Generator 3 (Step 6.3(11])



Page 24 of 182

5.0 ACCEPTANCE CRITERIA (continued)

2. Lo-Lo Level 17% (14.5% - 19.5%)

a. Steam Generator I (Step 6.1[311)

b. Steam Generator 2 (Step 6.2131])




Page 25 of 182

6.0 PERFORMANCE ~NOTES

1) Subsections 6.1, 6.2, 6.3, and 6.4 may be performed in any order, but cannot beperformed concurrently.

Table 6.0-1 Comparison of Narrow Range and Wide Range Indications

Narrow Range Wide Range Elevation

100% 100% 773.833

90% 95.8% 771.891

80% 91.6% 769.950

70% 87.4% 768.008

60% 83.2% 766.066

50% 79.0% 764.125

40% 74.8% 762.183

30% 70.6% 760.241

20% 66.4% 758.300

10% 62.1% 756.358

0% 58.0% 754.420

These numbers were calculated from the elevations given for the wide and narrowranges from the Scaling and Setpoint Documents (SSD).


Page 26 of 182

Date

6.1 SG I Narrow Range Level Instrument TestNOTES

1) At the Operators discretion, Steam Generator Blowdown may be initiated or increased.during level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.

2) The levels in the Steam Generator are adjusted by regulation of feedwater flow(2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SOI-15.01). Operation of the equipment required to perform these actions is not a part ofthis test and therefore, will not be specifically detailed in this test.

[11 VERIFY prerequisites listed in Section 4.0 for Subsection 6.1

have been completed.

[2] COMPLETE Data Sheet 1.

[3] VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.

[4] VERIFY Unit 2 Events Display Legend indicates 63-F, SG 1LEVEL HI is CLEAR.

[5) SLOWLY INCREASE the level in SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.

A. VERIFY Unit 2 Events Display.Legend indicates 63-F SG1 LEVEL HI (LS-3-42D) is in ALARM (Red).

B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE), at 2-M-4.

2-FR-3-35, STM FW FLOW & NR LEVEL* %

C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.115)B.[Programmed level +5% (_>2%, <8%)]

- 38% =

[6] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 50% is indicated on 2-LI-3-38, SG 1 LEVEL at2-M-4.


Date

6.1 SG I Narrow Range Level Instrument Test (continued)

NOTE

Annunciator Window 2-XA-55-3C, 60-B, SG1 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.




Page 28 of 182

Date


[10] INSTALL and LABEL digital multimeters AND

VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 7081C8P)

A. TB 403-5 and TB 403-6 in Panel 2-R-46(Dwg 45N2676-2)

Cv

B. TB 403-5 and TB 403-6 in Panel 2-R-49.(Dwg 45N2677-2)

Cv

C. TB 304-1 and TB 304-2 in Panel 2-R-46(Dwg 45N2676-2)

Cv

D. TB 304-1 and TB 304-2 in Panel 2-R-49(Dwg 45N2677-2)

Cv

E. TB 205-9 and TB 205-10 in Panel 2-R-46(Dwg 45N2676-1)

F. TB 205-9 and TB 205-10 in Panel 2-R-49(Dwg 45N2677-1)

Cv

Cv


Page 29 of 182

Date

6.1 SG 1 Narrow Range Level Instrument Test (continued)

NOTE

Annunciator Window 2-XA-55-6B, 116-B, SG 1 LEVEL HI-HI, will alarm at approximately82% level. The alarm may be acknowledged and silenced. No other action is required.

NOTE

Steps 6.1 [11]A, B, and C may be signed off as they occur

[11] SLOWLY INCREASE the level in Steam Generator 1 AND

A. WHEN TB 403-5 and TB 403-6 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),

RECORD the SG 1 Level on 2-LI-3-42, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]

B. WHEN TB 304-1 and TB 304-2 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),

RECORD the SG I Level on 2-LI-3-39, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.0C.1 [82.4% (79.9% - 84.9%)]

C. WHEN TB 205-9 and TB 205-10 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),

RECORD the SG 1 Level on 2-LI-3-38, SG 1 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]


Page 30 of 182

Date


NOTE

The following two steps will raise the SG 1 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.

[12] SLOWLY INCREASE the level in the SG 1 until the meterslabeled SG 1 installed in 2-R-5, 2-R-1 1, and 2-R-12 no longerindicate increasing voltage which indicates the water level hasreached the upper tap:

A. 2-R-5, SG 1 Level

B. 2-R-11, SG 1 Level

C. 2-R-12, SG 1 Level

[13] COMPLETE Data Sheet 4

[14] SLOWLY DECREASE the level in SG I until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:

A. 2-LI-3-42, SG 1 LEVEL

B. 2-LI-3-39, SG 1 LEVEL

C. 2-LI-3-38, SG 1 LEVEL



Page 31 of 182

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NOTE

Steps 6.1[16]A through 6.1[16]C may be signed off as they occur.

NOTE

Annunciator Window 2-XA-55-6B, 116-B, SG 1 LEVEL HI-HI, will clear at approximately81% level. The alarm may be acknowledged and silenced. No other action is required.

[16] SLOWLY DECREASE the level in SG 1 AND

A. WHEN TB 403-5 and TB 403-6 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),

RECORD the SG 1 Level on 2-LI-3-42, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]

B. WHEN TB 304-1 and TB 304-2 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),

RECORD the SG 1 Level on 2-LI-3-39, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]

C. WHEN TB 205-9 and TB 205-10 in Panels 2-R-46 and 2-R-49 indicate trip signals are OFF (voltage indicated),

RECORD the SG 1 Level on 2-L1-3-38, SG 1 LEVEL, at2-M-4, indication. [81.4% (78.9% - 83.9%)]


Page 32 of 182

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[171 REMOVE Digital Multimeters installed in at the followinglocations:

A. TB 403-5 and TB 403-6 in Panel 2-R-46

B. TB 403-5 and TB 403-6 in Panel 2-R-49

CV

CV

C. TB 304-1 and TB 304-2 in Panel 2-R-46

CV

D. TB 304-1 and TB 304-2 in Panel 2-R-49

E. TB 205-9 and TB 205-10 in Panel 2-R-46

CV

CV

CV

F. TB 205-9 and TB 205-10 in Panel 2-R-49

NOTE

Annunciator Window 2-XA-55-3C, 60-B, SG 1 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required. j

[18] SLOWLY DECREASE the level in SG 1 until approximately75% is indicated on 2-LI-3-38, SG 1 LEVEL.


.[20] SLOWLY DECREASE the level in SG 1 until approximately50% is indicated on 2-LI-3-38, SG 1 LEVEL.



Page 33 of 182

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[22] SLOWLY DECREASE the level in SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.

A., VERIFY Unit 2 Events Display Legend indicates 63-F SG1 LEVEL HI (LS-3-42D) is NORMAL (Blue)

B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE)

C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.1[22]B.[Programmed level +4% (>1 %, :7%)]

% - 38% =%

[23] SLOWLY DECREASE the level in-SG 1 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.

A. VERIFY Unit 2 Events Display Legend. indicates 63-F SG1 LEVEL LO (LS-3-42E) is in ALARM (Red)


C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.1[23]B from 38%.[Programmed level -5% (>2%,-<8%)]

% - 38% =

NOTE

Annunciator Window 2-XA-55-3C, 60-D, SG 1 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.

[24] SLOWLY DECREASE the level in SG 1 until approximately25% is indicated on 2-LI-3-38, SG ILEVEL.



Page 34 of 182

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[26] INSTALL and LABEL Digital Multimeters AND

VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)


(Dwg 45N2676-2)

CV

B. TB 404-5 and TB 404-6 in Panel 2-R-49(Dwg 45N2677-2)

CV


CV


CV


CV


CV

[27] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SG 1LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.

[28] SLOWLY DECREASE the level in Steam Generator 1.


Page 35 of 182

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NOTE

Steps 6.1[31]A through 6.1[31]F may be signed off as they occur.

NOTE

Annunciator Window 2-XA-55-6B, 116-E, SG 1 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.

[29] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SGI LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).

[30] VERIFY the following Event Display Legends are in alarm.Stop decreasing Steam Generator level when all three are in.

A. 116-D SG I LOLO LEVEL TTD INITIATED (ILY/519H).

B. 116-D SG 1 LOLO LEVEL TTD INITIATED (ILY/518H).

C. 116-D SG 1 LOLO LEVEL TTD INITIATED (ILY/517H).

NOTE

After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in.

[31] RECORD the level from the specified indicators AND

VERIFY status of associated computer points as the followingtrip signals come ON as indicated by absence of voltage at thefollowing locations:

A. TB 404-5 and TB 404-6 in Panel 2-R-46 and 2-R-49, SG 1Level indication on 2-L-3-42, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.0C.2 [17% (14.5 %- 19.5%)]

B. Computer Point L0405D indicates TRIP.(ACC CRIT) 5.OC.2


Page 36 of 182

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C. TB 305-1 and TB 305-2 in: Panel 2-R-46 and 2-R-49, SG 1Level indication on, 2-LI-3-39, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5 %- 19.5%)]

D. VERIFY Computer Point L0404D indicates TRIP.(ACC CRIT) 5.OC.2

E. TB 206-3 and TB 206-4 in Panel 2-R-46 and 2-R-49, SG ILevel indication on 2-LI-3-38, SG 1 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5 %- 19.5%)]

F. Computer Point L0403D indicates TRIP. (ACC CRIT).5.OC.2

NOTE

The following two steps will decrease the Steam Generator Level to the lower NR tap. Datacollection should be completed as rapidly as possible.

[32] SLOWLY DECREASE the level in SG 1 until the meterslabeled SG 1 installed in 2-R-5, 2-R-11, and 2-R-12 no longerindicate decreasing voltage which indicates the water level hasreached the lower tap.

A. 2-R-5, SG 1 Level trip

B. 2-R-1 1, SG 1 Level trip

C. 2-R-12, SG I Level trip



Page 37 of 182

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[34] SLOWLY INCREASE the level in SG 1 until level change isindicated on the following instruments which indicates thewater level has risen above the lower tap:




[35] COMPLETE Data Sheet 10.~NOTE

Steps 6.1 (36]A through 6.1 [36]F may be signed off as they occur.

INOTE

Annunciator Window 2-XA-55-6B, 11 6-E, SG 1 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.

[36] SLOWLY INCREASE the level in SG 1 AND

RECORD the level from the specified indicators AND

VERIFY status of associated computer points as the followingtrip signals CLEAR as indicated by presence of voltage at thefollowing locations:

A. TB 404-5 and TB 404-6 in Panel 2-R-46 and 2-R-49,2-LI-3-42, SG 1 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]

B. Computer Point L0405D indicates NOT TR.

C. TB 305-1 and TB 305-2 in Panel 2-R-46 and 2-R-49,2-LI-3-39, SG 1 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]

D. Computer Point L0404D indicates NOT TR.


Page 38 of 182

Date


E. TB 206-3 and TB 206-4 in Panel 2-R-46 and 2-R-49,2-LI-3-38, SG 1 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]

F. Computer Point L0403D indicates NOT TR.

[37] REMOVE Digital Multimeters installed at the followinglocations:


CV


CV


CV


CV


CV


CV

[38] VERIFY Annunciator Window 2-XA-55-6B, 116-D, SG 1LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.

[39] VERIFY Unit 2 Events Display Legend indicates 116-D, SG 1LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).


Page 39 of 182

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NOTE

Annunciator Window 2-XA-55-3C, 60-D, SG 1 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.

[40] SLOWLY INCREASE the level in Steam Generator 1 untilapproximately 25% is indicated on 2-LI-3-38, SG 1 LEVEL.


[42] SLOWLY INCREASE the level in SG 1 until AnnunciatorWindow 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG1 LEVEL LO (LS-3-42E) is in CLEAR (Blue).

B. RECORD the level indication from 2-FR-3-35, STM-FWFLOW & NR LEVEL, (PEN 3-BLUE).

C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.1[42]B from 38%.[Programmed level -4% (>1%, :7%)]

- 38% %/



[45] REMOVE the meters from the following test points:

A. Panel 2-R-5, SG 1 Level, Test Point 2LP/519B

B. Panel 2-R-1 1, SG 1 Level, Test Point 2LP/518B

C. Panel 2-R-12, SG 1 Level, Test Point 2LP/517B

CV

CV

CV


Page 40 of 182

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6.1 SG I

[46]

Narrow Range Level Instrument Test (continued)

VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0B.1 and 5.0B.2 as specified on thefollowing Data Sheets. (ACC CRIT)

A. Data Sheet 1

B. Data Sheet 2

C. Data Sheet 3

D.. Data Sheet 5

E. Data Sheet 6

F. Data Sheet 7

G. Data Sheet 8

H. Data Sheet 10

I. Data Sheet 11

J. Data Sheet 12


Page 41 of 182

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6.2 SG 2 Narrow Range Level Instrument TestNOTES

1) At the Operators'discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.

2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SOl-15.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.

[1] VERIFY prerequisites listed in Section 4.0 for Subsection 6.2



[3) VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.

[4] VERIFY Unit 2 Events Display Legend indicates 63-F SG 2LEVEL HI is CLEAR.

[5] SLOWLY INCREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, alarms.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL HI (2-LS-3-55D) is in ALARM (Red).


2-FR-3-48, STM FW FLOW & NR LEVEL %

C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.2[5]B.[Programmed level +5% (>2%, -8%)]

% - 38% %




Page 42 of 182

Date


NOTE

Annunciator Window 2-XA-55-3C, 61-B, SG 2 LEVEL HI, will alarm at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.


[91 COMPLETE Data Sheet 15.



A. TB 207-11 AND TB 207-12 in Panel 2-R-46.(Dwg 45N2676-1)

CV

B. TB 207-11 AND TB 207-12 in Panel 2-R-49.(Dwg 45N2677-1)

CV

C. TB 304-3 AND TB 304-4 in Panel 2-R-46.(Dwg 45N2676-2)

CV

D. TB 304-3 AND TB 304-4 in Panel 2-R-49.(Dwg 45N2677-2)

CV

E. TB 403-7 AND TB 403-8 in Panel 2-R-46.(Dwg 45N2676-2)

CV


Page 43 of 182

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F. TB 403-7 AND TB 403-8 in Panel 2-R-49.(Dwg 45N2677-2)

CV

NOTE


NOTE

Steps 6.2[1 ]A, B, and C may be signed off as they occur



RECORD the SG 2 LEVEL on 2-LI-3-55, SG 2 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9%- 84.9%)]






Page 44 of 182

-Date


NOTE

The following two steeps will raise the SG 2 level to the upper NR tap. Data collection shouldbe completed as rapidly as possible.

[12] SLOWLY INCREASE the level in the SG 2 until the meterslabeled SG 2 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:





[14] SLOWLY DECREASE the level in SG 2 until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:






Page 45 of 182

Date


NOTE


NOTE



A. WHEN TB 403-7 and TB 403-8 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),

RECORD SG 2 Level on 2-L-3-55, SG 2 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]

B. WHEN TB 304-3 and TB 304-4 in Panels 2-R-46 and,2-R-49 indicate the trip is OFF (voltage indicated),

RECORD SG 2 Level on 2-LI-3-52, SG 2 LEVEL, at2-M-4. [81.4% (78.9 - 83.9)]

C. WHEN TB 205-1land TB 205-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),

RECORD SG 2 Level on 2-LI-3-51, SG 2 LEVEL, at2-M-4. [81.4% (78.9 - 83.9)]


Page 46 of 182

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[17] REMOVE Digital Multimeters installed in at the followinglocations:


CV


CV


CV


CV


CV


CV

NOTE

Although not within the scope of this test, Annunciator Window 2-XA-55-3C, 61-B, SG 2LEVEL HI, will clear at approximately 74% level. The alarm may be acknowledged andsilenced. No other action is required.

[18] SLOWLY DECREASE the level in SG 2 until approximately

75% is indicated on 2-LI-3-51, SG 2 LEVEL.


[20] SLOWLY DECREASE the level in SG 2 until approximately50% is indicated on 2-LI-3-51, SG 2 LEVEL.•


Date


[22] SLOWLY DECREASE the level in SG 2 until Annunciator 2-XA-55-3C, Window 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL HI (LS-3-55D) is NORMAL (Blue).


C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.2[22]B.[Programmed level +4% (--1%, <7%)]

% - 38% %

[23] SLOWLY DECREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, ALARMS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL LO (LS-3-55E) is in ALARM (Red).


C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.2[23]B from 38%.[Programmed level -5% (>2%, <8%)]

% - 38% = %

NOTE





Page 48 of 182

Date



VERIFY trip signals are OFF as indicated by presence ofvoltage.at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)



CV

CV

CV




CV

CV

CV





Page 49 of 182

Date


NOTE


NOTE

Annunciator Window 2-XA-55-6B, 11 7-E, SG 2 LEVEL LO-LO, will alarm at approximately17% level. The alarm may be acknowledged and silenced. No other action is required.

[29] VERIFY Annunciator Window 2-XA-55-6B, 117-D, SG2 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).

[30] VERIFY the following Event Display Legends are in alarm.

Stop decreasing Steam Generator level when all three are in.

A. 117-D SG 2 LOLO LEVEL TTD INITIATED (ILY/529H).



NOTE

After the time delay (TTD) has finished (approximately 8 minutes), all three trip channelsshould come in. ]



A. TB 404-7 and TB 404-8 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-55, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]



Page 50 of 182

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C. TB 305-3 and TB 305-4 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-52, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]

D. Computer Point L0424D indicates TRIP.(ACC CRIT) 5.OC.2

E. TB 210-1 and TB 210-2 in Panel 2-R-46 and 2-R-49, SG 2Level indication on 2-LI-3-51, SG 2 LEVEL, at 2-M-4.(ACC CRIT) 5.0C.2 [17% (14.5% - 19.5%)]

F. Computer Point L0423D indicates TRIP.(ACC CRIT) 5.OC.2

NOTE


[32] SLOWLY DECREASE the level in SG 2 until the meterslabeled SG 2 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.






Page 51 of 182

Date

6.2 o SG 2 Narrow Range Level Instrument Test (continued)


A. 2-L-3-55, SG 2 LEVEL


C. 2-L-3-51, SG 2 LEVEL


[ NOTE


NOTE

Annunciator Window 2-XA-55-6B, 11 7-E, SG 2 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other-action is required.



VERIFY status of associated computer points as the following*trip signals CLEAR as indicated by. presence of voltage at thefollowing locations:

A. TB 404-7 and TB 404-8 in Panel 2-R-46 and 2-R-49,2-L-3-55, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]


C. TB 305-3 and TB 305-4 in Panel 2-R-46 and 2-R-49,2-LI-3-52, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]


E. TB 210-1 and TB 210-2 in Panel 2-R-46 and 2-R-49,2-LI-3-51, SG 2 LEVEL, at 2-M-4. [18% (15.5% - 20.5%)]


Page 52 of 182

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(371 REMOVE Digital Multimeters installed at the followinglocations:



.C. TB 305-3 and TB 305-4 in Panel 2-R-46

CV

CV

CV

CV

CV

CV




[38] VERIFY Annunciator Window 2-XA-55-6B, 117-D, SG 2LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.

[39] VERIFY Unit 2 Events Display Legend indicates 11 7-D, SG 2LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).


Page 53 of 182

Date


NOTE

Annunciator Window 2-XA-55-3C,. 61-D, SG 2 LEVEL LO, will clear at approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.



[42] SLOWLY INCREASE the level in SG 2 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG2 LEVEL LO (LS-3-55E) is CLEAR (Blue).



% 38% %




Page 54 of 182

Date




Cv


Cv

C. Panel 2-R-12, SG 2 Level, Test Point 2LP/527B1

Cv

[46] VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)

A. Data Sheet 13.

B. Data Sheet 14.

C. Data Sheet 15.

D. Data Sheet 17.

E. Data Sheet 18.

F. Data Sheet 19.

G. Data Sheet 20.

H. Data Sheet 22.

I. Data Sheet 23.

J. Data Sheet 24.


Page 55 of 182

Date

6.3 SG 3 Narrow Range Level Instrument Test

NOTES

1) At the Operators discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator. It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.

2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.01), into the generator, and blowdown flow from the generator (2-SO1-15.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.




[3] VERIFY.Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.



A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL HI (LS-3-97D) is in ALARM (Red)..


2-FR-3-90, STM FW FLOW & NR LEVEL __ -%

C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.3[5]B.[Programmed level +5% (>-2%, <8%)]

% - 38% =%

[6] SLOWLY INCREASE the level in Steam Generator 3 untilapproximately 50% is indicated on 2-LI-3-93, SG 3 LEVEL at2-M4.



Page 56 of 182

Date


NOTE


[8] SLOWLY INCREASE the level in Steam Generator 3.untilapproximately 75% is indicated on 2-LI-3-93, SG 3 LEVEL at2-M-4.



VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary. Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 708/C8P)


CV



CV

CV



CV

CV

WBN Feedwater & Steam Generator Level 2 PTI-003A-02Unit2 Rev.0000

Page 57 of 182

Date



CV

NOTE


NOTE

Steps 6.3[1 ]A, B, and C may be signed off as they occur



RECORD SG 3 Level on 2-LI-3-97, SG 3 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]



C. WHEN TTB 210-9 and TB 210-10 in Panels 2-R-46 and2-R-49 indicate TRIP (no voltage),

RECORD SG 3 Level on 2-LI-3-93, SG 3 LEVEL, at2-M-4. (ACC CRIT) 5.0C.1 [82.4% (79.9% - 84.9%)]

0/


Page 58 of 182

Date


NOTE


[12] SLOWLY INCREASE the level in the SG 3 until the meterslabeled SG 3 Level installed in 2-R-5, 2-R-1 1, and 2-R-1 2 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:





[14] SLOWLY DECREASE the level in SG 3 until level change isindicated on the following instruments which indicates thewater level has fallen below the lower tap:






Page 59 of 182

Date.



NOTE



A. WHEN TB 403-9 and TB 403-10 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),

RECORD SG 3 Level on 2-LI-3-97, SG 3 LEVEL, at2-M-4. [81.4% (78.9% - 83.9%)]

B. WHEN TB 304-5 and TB 304-6 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),


C. WHEN TB 210-9 and TB 210-10 in Panels 2-R-46 and2-R-49 indicate the trip is off (voltage indicated),



Page 60 of 182

Date



-A. TB 403-9 and TB 403-10 in Panel 2-R-46



CV

CV

CV

CV




CV

CV

NOTE

Annunciator Window 2-XA-55-3C, 62-B, SG 3 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required. I






Page 61 of 182

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[22] SLOWLY DECREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL HI (LS-3-97D) is NORMAL (Blue)


C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.3[22]B.[Programmed level +4% (21%, 57%)]

% - 38% %


A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL LO (LS-3-97E) is in ALARM (Red)



%/ 38% = %/

NOTE

Annunciator Window 2-XA-55-3C 62-D, SG 3 LEVEL LO, will alarm approximately 25%level. The alarm may be acknowledged and silenced. No other action is required.




Page 62 of 182

Date


[261 INSTALL and LABEL Digital Multimeters AND

VERIFY trip signals are OFF as indicated by presence ofvoltage at the following locations: (2-R-46 - Control BuildingAuxiliary Instrument Room 708/C8P, 2-R-49 - Control BuildingAuxiliary Instrument Room 7081C8P)







(271 VERIFY Annunciator Window 2-XA-55-6B, 118-D, SG 3LO-LO LEVEL TTD INITIATED, at 2-M-6 is CLEAR.

CV

CV

CV

CV

CV

CV



Page 63 of 182

Date


NOTE


NOTE


[29] VERIFY Annunciator Window 2-XA-55-6B, 11 8-D, SG3 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the Steam.Generator level reaches 17%.(14.5 %- 19.5%).

[30] VERIFY the following Event Display Legends are in alarm.Stop decreasing Steam Generator level when all three are in.




NOTE




A. TB 404-9 and TB 404-10 in Panel 2-R-46 and 2-R-49, SG3 Level indication on 2-LI-3-97, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]

B. Computer Point L0445D indicates TRIP.(ACC CRIT) 5.0C.2

WBNu Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page 64 of 182

Date


C. TB 305-5 and TB 305-6 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-94, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5%- 19.5%)]

D. Computer Point L0444D indicates TRIP.(ACC CRIT) 5.OC.2

E. TB 210-3 and TB 210-4 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-93, SG 3 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]


NOTE


[32] SLOWLY DECREASE the level in SG 3 until the meterslabeled SG 3 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.

A. 2-R-5, SG 3 LEVEL

B. 2-R-11, SG 3 LEVEL

C. 2-R-12, SG 3 LEVEL



Page 65 of 182

Date





C. 2-L-3-93, SG 3 LEVEL

.[35] COMPLETE Data Sheet 34.

NOTE


NOTE

Annunciator Window 2-XA-55-6B, I I8-E, SG 3 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.




A. TB 404-9 and TB 404-10 in Panel 2-R-46 and 2-R-49, SG3 Level indication on 2-LI-3-97, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]


C. TB 305-5 and TB 305-6 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-94, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]



Page 66 of 182

Date


E. TB 210-3 and TB 210-4 in Panel 2-R-46 and 2-R-49, SG 3Level indication on 2-LI-3-93, SG 3 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]


[37] REMOVE Digital Multimeters installed at the following

locations:


CV


CV


CV


CV


CV


CV

[38] VERIFY Annunciator Window 2-XA-55-6B, 11 8-D, SG 3LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.

[39] VERIFY Unit 2 Events Display Legend indicates 11 8-D, SG 3LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).


Page 67 of 182

Date


NOTE


[401 SLOWLY INCREASE the level in Steam Generator 3 untilapproximately 25% is indicated on 2-L-3-93, SG 3 LEVEL.


[42] SLOWLY INCREASE the level in SG 3 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG3 LEVEL LO (LS-3-97E) is CLEAR (Blue).


C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.3[42]B from 38%.[Programmed level -4% (51%, <7%)]

38% %/




Page 68 of 182

Date,






Cv

Cv

Cv

[46] VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)

A. Data Sheet 25.

B. Data Sheet 26.

C. Data Sheet 27.

D. Data Sheet 29.

E. Data Sheet 30.

F. Data Sheet 31.

G. Data Sheet 32.

H. Data Sheet 34.

I. Data Sheet 35.

J. Data Sheet 36.


Page 69 of 182

Date

6.4 SG 4 Narrow Range Level Instrument TestNOTES

1) At the Operators discretion, Steam Generator Blowdown may be initiated or increasedduring level decreases to allow some feedwater flow to the generator, It is preferablethat blowdown flow be maintained as low as possible to avoid decreasing primarytemperature due to excessive feedwater flow.

2) The levels in the Steam Generator are adjusted by regulation of feedwater flow (2-SOI-2&3.011), into the generator, and blowdown flow from the generator (2-SOl-1 5.01).Operation of the equipment required to perform these actions is not a part of this testand therefore, will not be specifically detailed in this test.




[3] VERIFY Annunciator Window 2-XA-55-3C, 63-F, SG LEVELDEVIATION, at 2-M-3 is CLEAR.



A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL HI (LS-3-1 10D) is in ALARM (Red).


2-FR-3-103, STM FW FLOW & NR LEVEL %

C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.4[5]B.[Programmed level +5% (-2%, <8%)]

% 38% %

[6] SLOWLY INCREASE the level in Steam Generator 4 until.approximately 50% is indicated on 2-LI-3-106, SG 4 LEVEL at2,M-4.



Page 70 of 182

Date


NOTE







CV


CV


CV


CV

E. TB 205-11 and TB 205-12 in Panel 2-R-46(Dwg 45N2676-1) _

CV

WBN Feedwater & Steam Generator Level 2 PTI-003A-02Unit2 Rev.0000

Page 71 of 182

Date


F. TB 205-11 and TB 205-12 in Panel 2-R-49(Dwg 45N2677-10

CV

NOTE


NOTE

Steps 6.4[l 1]A, B, and C may be signed off as they occur



RECORD SG 4 Level on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.OC.1 [82.4% (79.9% - 84.9%)]






~Page 72 of 182

Date


NOTE


[12] SLOWLY increase the level in the SG 4 until the meterslabeled SG 4 Level installed in 2-R-5, 2-R-11, and 2-R-12 nolonger indicate increasing voltage which indicates the waterlevel has reached the upper tap:




(13] COMPLETE Data Sheet 40.

[14] SLOWLY DECREASE the level in SG 4 until level change isindicated on the following instruments which indicates thewater level has fallen below the upper tap:






Page 73 of 182

Date


NOTE

Steps 6.4116]A through 6.4[16]C may be signed off as they occur.

NOTE



A. WHEN TB 403-11 and TB 403-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),

RECORD SG 4 Level indication on 2-LI-3-1 10, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]

B. WHEN TB 304-7 and TB 304-8 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),

RECORD SG 4 Level indication on 2-LI-3-107, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]

C. WHEN TB 205-1 land TB 205-12 in Panels 2-R-46 and 2-R-49 indicate the trip is OFF (voltage indicated),

.RECORD SG 4 Level indication on 2-LI-3-106, SG 4LEVEL, at 2-M-4. [81.4% (78.9% - 83.9%)]

%I


Page 74 of 182

Date





CV

CV




CV

CV

,CV

CV


NOTE

Annunciator Window 2-XA-55-3C, 63-B, SG 4 LEVEL HI, will clear at approximately 74%level. The alarm may be acknowledged and silenced. No other action is required.






Page 75 of 182

Date


[22] SLOWLY DECREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C, 63-F, SG LEVEL DEVIATION., CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL HI (LS-3-11OD) is NORMAL (Blue)


C. DETERMINE the percent deviation by subtracting 38%from the indication recorded in Step 6.4[22]B.[Programmed level +4% (>1%, <7%)]

% - 38% =


A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL LO (LS-3-1 10 E) is in ALARM (Red)


C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.4[23]B from 38%.[Programmed level -5% (>2%, -8%)]

% - 38% %

NOTE





Page 76 of 182

Date





CV


CV


CV


CV


CV


CV




Page 77 of 182

Date


NOTE


NOTE


[29] VERIFY Annunciator Window 2-XA-55-6B, 11 9-D, SG4 LO-LOLEVEL TTD INITIATED, at 2-M-6, ALARMS as the SteamGenerator level reaches 17% (14.5 %- 19.5%).

[30] VERIFY the following Event Display Legends are in alarm.

Stop decreasing Steam Generator level when all three are in.




NOTE




A. TB 404-11 and TB 404-12 in Panel 2-R-46 and 2-R-49,SG 4 Level indication on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. (ACC CRIT) 5.0C.2 [17% (14.5% - 19.5%)]



Page 78 of 182

Date


C. TB 305-7 and TB 305-8 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-107, SG 4 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]

D. Computer Point L0464D indicates TRIP.(ACC CRIT) 5.0C.2

E. TB 206-5 and TB 206-6 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-106, SG 4 LEVEL, at 2-M-4.(ACC CRIT) 5.OC.2 [17% (14.5% - 19.5%)]


NOTE


[32] SLOWLY DECREASE the level in SG 4 until the meterslabeled SG 4 Level installed in 2-R-5, 2-R-1 1, and 2-R-12 nolonger indicate decreasing voltage which indicates the waterlevel has reached the lower tap.


B. 2-R-!1, SG4 Level




A. 2-LI-3-110, SG4 LEVEL




Page 79 of 182

Date

6.4 SG4 Narrow Range Level Instrument Test (continued)

.[35] COMPLETE Data Sheet 46.

NOTE


NOTE

Annunciator Window 2-XA-55-6B, 11 9-E, SG 4 LEVEL LO-LO, will clear at approximately18% level. The alarm may be acknowledged and silenced. No other action is required.




A. TB 404-11 and TB 404-12 in Panel 2-R-46 and 2-R-49,SG 4 Level indication on 2-LI-3-1 10, SG 4 LEVEL, at2-M-4. [18% (15.5% - 20.5%)]


C. TB 305-7 and TB 305-8 in Panel 2-R-46 and 2-R-49, SG 4.Level indication on 2-LI-3-107, SG 4 LEVEL, at 2-M-4.[18% (15.5% - 20.5%)]


E. TB 206-5 and TB 206-6 in Panel 2-R-46 and 2-R-49, SG 4Level indication on 2-LI-3-106, SG 4 LEVEL, at 2-M-4.(18% (15.5% - 20.5%)]

%/


Page 80 of 182

Date



[37] REMOVE Digital Multimeters installed at the followinglocations:




CV

CV

CV

CV

CV

CV




[38] VERIFY Annunciator Window 2-XA-55-6B, 11 9-D, SG 4LO-LO LEVEL TTD INITIATED, CLEARS when all trip signalsare cleared.

[39] VERIFY Unit 2 Events Display Legend indicates 119-D, SG 4LO-LO LEVEL TTD INITIATED is in CLEAR (Blue).

NOTE





Page 81 of 182

Date


[42] SLOWLY INCREASE the level in SG 4 until AnnunciatorWindow 2-XA-55-3C 63-F, SG LEVEL DEVIATION, CLEARS.

A. VERIFY Unit 2 Events Display Legend indicates 63-F SG4 LEVEL LO (LS-3-1 10E) is CLEAR (Blue).


C. DETERMINE the percent deviation by subtracting theindication recorded in Step 6.4[42]B from 38%.[Programmed level -4% (-1 %, <7%)],

% - 38% =

[43] SLOWLY INCREASE the level in Steam Generator 4 until

approximately 38% is indicated on 2-LI-3-106, SG 4 LEVEL.




CV

B. Panel 2-R-11,ZSG 4 Level, Test Point 2LP/548B

CV


CV


Page 82 of 182

Date


[461 VERIFY that level indications and calculated levels satisfyAcceptance Criteria 5.0 B.land 5.0 B.2 as specified on thefollowing Data Sheets. (ACC CRIT)

A. Data Sheet 37.

-B. Data Sheet 38.

C. Data Sheet 39.

D. Data Sheet 41.

E.. Data Sheet42.

F. Data Sheet 43.

.G. Data Sheet 44.

H. Data Sheet 46.

I. Data Sheet 47.

J. Data Sheet48.

WBN Feedwater & Steam Generator Level 2-PTI-003A-02•Unit 2 Rev. 0000

Page 83 of 182


[1] NOTIFY the Unit 2 US/SRO of the test completion and systemalignment.

[2] VERIFY that Post-test calibration of the M&TE used to recordquantitative acceptance criteria has been satisfactorily performed,

AND

RECORD the results on M&TE Log.

[3] VERIFY that Post-test calibration of permanent plant instrumentsused to record quantitative acceptance criteria has beensatisfactorily performed,

AND

RECORD the results on Appendix C, Permanent PlantInstrumentation Log.

8.0 RECORDS

A. QA Records

Completed Test Package

B. Non-QA Records

None


Page 84 of 182

Appendix A(Page 1 of 2)

Test Proceduresllnstructions Reference Review

NOTES



PROCEDURE/INSTRUCTION REVISIONICHANGES

Unit 2 FSAR - Amendment 107

Table 14.2.1 Sheet 77



2-SOI-2&3.01

2-SO1-15.01

2-TSD-3A-2

SSD-2-LPF-3-35

(review against SSD-1-LPF-3-35)

SSD-2-LPF-3-48


SSD-2-LPF-3-90


SSD-2-LPF-3-103


2-L-3-38

2-L-3-39

2-L-3-42

2-L-3-51

2-L-3-52

IMPACT

Yes/NoINITIAL AND DATE.(N/A for no change)


Page 85 of 182

Appendix A(Page 2 of 2)

Test Proceduresllnstructions Reference Review

PROCEDURE/ IMPACT INITIAL AND DATE.INSTRUCTION REVISIONICHANGESYes/No (N/A for no change)

2-L-3-55

2-L-3-93

2-L-3-97

2-L-3-106

2-L-3-107

2-L-3-1 10


Page 86 of 182


Temporary Condition Log

Date

NOTE

These steps will be marked NIA if no temporary condition existed. Additional copies of thistable may be made as necessary.

TEMPORARY PERFORMED RETURNED TO NORMALITEM CONDITION Step Perf. By/Date Step Returned By/Date

NUMBER DESCRIPTION Number CV/Date Number CV/Date

.WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page 87 of 182

Appendix C(Page 1 of 3)

Permanent Plant Instrumentation Log

Date

POST-TEST

FILLED AND PLACED IN CALIBRATION

INSTRUMENT OR VENTED(1) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLE

INSTRUMENT POST-TEST CALLOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INIT/DATE

2-L-3-38

2-L-3-39

2-L-3-42

2-L-3-51

2-L-3-52

2-L-3-55

2-L-3-93

2-mL-3-94

2-L-3-97

2-L-3-106

2-L-3-107

2-L-3-1 10


Page 88 of 182



Date

POST-TESTFILLED AND PLACED IN CALIBRATION

INSTRUMENT OR VENTED(I) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLEINSTRUMENT POST-TEST CAL

LOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INITIDATE

2-L-3-35

2-L-3-48

2-L-3-90

2-L-3-103

2-L-3-231

2-L-3-232

2-L-3-233

2-L-3-234

2-L-3-43

2-L-3-56

2-L-3-98

2-L-3-1 11


Page 89 of 182

Appendix C(Page 3 of 3).


Date

POST-TEST

FILLED AND PLACED iN CALIBRATIONINSTRUMENT OR VENTED(1) SERVICE(1) USED FOR QUANTITATIVE ACC CRIT ACCEPTABLE

INSTRUMENT POST-TEST CALLOOP CAL DUE DATE INITIDATE INITIDATE YES NO DATE(2) INIT/DATE

2-L-3-148

2-L-3-156

2-L-3-164

2-L-3-171

2-L-3-172

2-L-3-173

2-L-3-174

2-L-3-175

(1) These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and ventedmay be identified as Not Applicable (NA).

(2) May be identified as NA if instrument was not used to verify/record quantitative acceptance criteria data.


Page 90 of 182

Table 1

(Page 1 of 1)

Computer Point Verification Log

Date

Computer Point Description Status Initials

Set Reset

L0403D STM GEN 1 LO-LO TRIP NOT TRLI PART RE

L0404D STM GEN 1 LO-LO TRIP NOT TRL2 PART RE


L0423D. STM GEN 2 LO-LO TRIP NOT TRL1 PART RE






L0463D STM GEN 4 LO-LO TRIP NOT TRLi PART RE




Page 91 of 182

Table 2(Page 1 of 2)

Train A Plastic Screw Verification

.Date

Panel TB Drawing Point Initials

2-R-48 634 2-45N2676-5 1

2-R-48 634 2-45N2676-5 2

2-R-48 634 2-45N2676-5 3

2-R-48 634 2-45N2676-5 4

2-R-48 634 2-45N2676-5 5

2-R-48 634 2-45N2676-5 6

2-R-48 634 2-45N2676-5 7

2-R-48 634 2-45N2676-5 8

2-R-48 634 2-45N2676-5 11

2-R-48 634 2-45N2676-5 12

2-R-48 635 2-45N2676-5 I

2-R-48 635 2-45N2676-5 2

2-R-48 632 2-45N2676-5 1

2-R-48 632 2-45N2676-5 .2

2-R-48 630 2-45N2676-5 9

2-R-48 630 2-45N2676-5 10

2-R-48 631 2-45N2676-5 5

2-R-48 631 2-45N2676-5 6

2-R-48 631 2-45N2676-5 7

2-R-48 631 2-45N2676-5 8

2-R-48 648 2-45N2676-5 1

2-R-48 648 2-45N2676-5 2

2-R-48 648 2-45N2676-5 3


Page 92 of 182


Train A Plastic Screw Verification

Date


2-R-48 648 2-45N2676-5 4

2-R-48 649 2-45N2676-5 1

2-R-48 649 2-45N2676-5 2

2-R-48 649 2-45N2676-5 3

2-R-48 649 2-45N2676-5 4

2-R-48 621 2-45N2676-4 9

2-R-48 621 2-45N2676-4 10

2-R-48 621 2-45N2676-4 11

2-R-48 621 2-45N2676-4 12

2-R-48 622 2-45N2676-4 1

2-R48 622 2-45N2676-4 2

2-R-48 622 2-45N2676-4 5

2-R-48 622 2-45N2676-4 6

2-R-48, 622 2-45N2676-4 7

2-R-48 622 2-45N2676-4 8

2-R-48 622 2-45N2676-4 9

2-R-48 622 2-45N2676-4 10


Train B Plastic Screw Verification

Date


2-RW51 634 2-45N2677-5 1

2.,R-5 634 2-45N2677-5 2

2-*R-51 634 2-45N2677-5 3

2-R-51 634 2-45N2677-5 4

* 2-R-51 634 2-45N2677-5 5

2-R-51 634 2-45N2677-5 6

2-R-51 634 2-45N2677-5 7

2-R-51. 634 2-45N2677-5 8

2-R-51 634 2-45N2677-5 1i

2-R-51 . 634 2-45N2677-5 12

2-R-51 635 2-45N2677-5 1

2-R-51 635 2-45N2677-5 2

2-R-51 632 2-45N2677-5 1

2-R-51 632 2-45N2677-5 2

2-R-51 630 2-45N2677-5 9

2-R-51 630 2-45N2677-5 10

2-PýR5.1 631 2-45N2677-5 5

2-R-51 631 2-45N2677-5 6

2-R-51 631 2-45N2677-5 7

2-R-51 631 2-45N2677-5 8

2-R-51. 648 2-45N2677-5 1

2-R-51 648 2-45N2677-5 2

2-R-51 648 2-45N2677-5 3

WBN Feedwater & Steam Generator Level 2-PTI-003A-02Unit 2- Rev. 0000

Page 94 of 182


Train B Plastic Screw Verification

Date


2-R-51 648 2z.45N2677-5 4

2-R-51 649 2-45N2677-5 1

2-R-51 649 2-45N2677-5 2

2-R-51 649 2-45N2677-5 3

2-R-51 649 2-45N2677-5 4

2-R-51 621 2-45N2677-4 9

2-R-51 621 2-45N2677-4 10

2-R-51 621 2-45N2677-4 11

2-R-51 621 2-45N2677-4 12

2-R-51 622 2-45N2677-4 1

2-R-51 622 2-45N2677-4 .2

2-R-51 622 2-45N2677-4 5.

2-R-51 622 2-45N2677-4 6

2-R-51 622 2-45N2677-4 7

2-R:51 622 2745N2677-4 8

2-R-51 622 2-45N2677-4 9

2-R-51 622 2-45N2677-4 10


Page 95 of 182

Data Sheet I(Page 1 of 2)

SG I - Initial Level Verification Data

Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage 0)(3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-1 1 - 2LP/518B

2-LI-3-42 2) 2-R-12 - 2LP/517B

2-FR-3-35 N/A N/A N/A N/A(Pen 3 Blue)

2-LI-3-43A N/A N/A N/A N/A

2-LI-3-43B N/A N/A N/A N/A

2-LR-3-43 N/A N/A N/A N/A(Pen. 1 Red)

2-LI-3-164 N/A N/A N/A N/A

2-LI-3-164C N/A N/A N/A N/A

2-LI-3-174 N/A N/A N/A N/A

(2) Maximum and Minimum indicated levels are within 5%

(3) Maximum and Minimum calculated levels are within 1.1%


Page 96 of 182

Data Sheet I(Page 2 of 2)

SG I - Initial Level Verification Data

Date

(1) Calculations

2LP/51 9B Calculated Level = (Indicated Voltage - 0. 19829)x 100%

0.79315100%

Calculated Level = ( -0.19829) x 0.7931%5)

Calculation Performed By: Verified By:

2LP/518B 100%Calculated Level = (Indicated Voltage - 0.19829) x

0.79315100%

Calculated Level= ( -- 0.19829)x 0 15%)•0.79315


2LP/51 7B Calculated Level = (Indicated Voltage - 0. 19829) x 100%0.79315

100%Calculated Level= ( -0.19829)x 0.7931%)



Page 97 of 182

Data Sheet 2(Page I of 2)

SG I - 50% Level Verification Data

Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials

Location Voltage ()3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-11 - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B




2-LR-3-43 N/A N/A N/A N/A(Pen 1 Red)

2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 98 of 182

Data Sheet 2(Page 2 of 2)

SG 1 - 50% Level Verification Data

Date

(1) Calculations

2L-P/519B 100%Calculated Level = (Indicated Voltage- 0. 19829)x

0.79315

Calculated Level =( -0.19829)x 100%0.79315


2LP/51 8B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.91

0.79315

Calculated Level= -0.19829)x 0%5 - ( %)


2LP/517B Calculated Level = (Indicated Voltage- 0. 19829) x 100%

0.79315100% _

Calculated Level = ( -0.19829)x 0.79315 %)0.79315

rCalculation Performed By: jVerified B .y:


Page 99 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1)(3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-11 - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B





2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 100 of 182


SG 1 -75% Level Verification Data

Date

(1) Calculations

2LP/51 9B Calculated Level = (Indicated Voltage- 0. 19829)x 100%

0.79315

Calculated Level= ( -0.19829)x 0 .7 %)0 .79315


2LP/51 8B Calculated Level = (Indicated Voltage - 0. 19829) x

0.79315100%

Calculated Level ( - 0.19829)x- 0.9)1


2LP/517B Calculated Level = (Indicated Voltage - 0. 19829)x 0.3

Calculated Level:= ( -0.19829)x 100% =( %0.793150


WBN Feedwater & St eam Generator Level 2-PTI-003A-02Unit 2 Rev. 0000

Page 101 of 182


SG 1 - 100% Tap Verification Data

Date

DVM Test Point Location Indicated Voltage M&TE No. Initials

2-R-52LP/519B

2-R-112LP/518B

.2-R-:122LP/517B


Page 102 of 182

Data Sheet 5

(Page 1 of 2)


Date


Location Voltage (1X3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-11 - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B





2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 103 of 182

Data Sheet 5

(Page 2 of 2)


Date

(1) Calculations

2LP/51 9B 10Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315

Calculated Level = ( -0.19829)x 100% =( %)0.79315


.2LP/518B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%

Calculated Level = ( -0.19829)x 100%%)/ 0.79315


2LP/517B 1 000/Calculated Level = (Indicated Voltage- 0.19829)x

0.79315

Calculated Level= ( -0.19829)x 100% =%)0.79315



Page 104 of 182



Date


2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-1I - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B

2-FR-3-35 N/A N/A NIA N/A(Pen 3 Blue)

2-LI-3-43A N/A N/A. N/A N/A


2-LR-3-43 N/A -N/A N/A N/A(Pen 1 Red)

2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174. N/A N/A N/A N/A




Page 105 of 182



Date

(1) Calculations

2LP/519B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 0.79315

Calculated Level = ( -0.19829)x 10.7 %)


2LP/518B Calculated Level = (Indicated Voltage - 0.19829) x 100%0.793 15

Calculated Level = -0.9829 100% ( %)0.79315


2LP/517B 100%Calculated Level = (Indicated Voltage - 0. 19829) x

0.79315

Calculated Level =( -0.19829)x 7100% %0.79315n o Be y

rCalculatio~n Performed• By: Verified By:

WBNUnit 2

Feedwater & Steam Generator Level 2-PTI-003A-02Rev. 00.00Page 106 of 182

Data Sheet 7

(Page 1 of 2)


Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1X3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-11 - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B





2-LI-3-164 N/A N/A N/A N/A

2-LI-3-164C N/A N/A N/A •N/A

2-LI-3-174 I N/A. N/A N/A N/A




Page 107 of 182



Date

(1) Calculations

2LP/51 9B 10Calculated Level = (Indicated Voltage -0.19829)× 100%0.79315

Calculated Level= ( -0.19829)x 0.79315 %)


2LP/518B , - • 10Calculated Level = (Indicated Voltage - 0.19829) 100%0.79315

100%Calculated Level= (. -0.19829)x 0791 %)


2LP/517B , 100%Calculated Level = (Indicated Voltage- 0.19829) xVoltge '0.79315

100%Calculated Level= ( -0.19829)x 0915



Page 108 of 182Data Sheet 8

(Page 1 of 2)


Date

Instrument Indication % DVM Test Point. M&TE No. Indicated Calculated Level InitialsLocation Voltage (IX3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-1 I - 2LP/518B.

2-LI-3-42 .(2) 2-R-12 - 2LP/517B





2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 109 of 182



Date

(1) Calculations

2LP1519B : Calculated Level = (Indicated'Voltage -0.19829)x 100%

0.79315

Calculated Level=( -0.19829)x 100% 5 %)0.79315


2LP/518B 192~x100%Calculated Level = (Indicated Voltage-0. 019829)x 150.79315

CalculatedLevel=( -0.19829)x 100% 6(0.79315


2LP/51 7B Calculated Level = (Indicated Voltage- 0. 19829) x 100%

Calculated Level = ( -0.19829)x 100%

0 .79315

Calculation Performed By: FVerified By:


Page 110 of 182



Date


2-R-5

2LP/519B

2-R-112LP/518B

2-R-122LP/517B


Page 111 of 182


SG 1 -0% Level Verification Data

Date


2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-1 1 - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B




2-LR-3-43 N/A N/A N/A N/A(Pen I Red)

2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 112 of 182


SG,1 - 0% Level Verification Data

Date

(1) Calculations

2LP/519B 100%2 Calculated Level = (Indicated Voltage - 0. 19829) x 100%

0.79315

Calculated Level = ( -0.19829)x 0.79315)

Calculation Performed By: Vedfied By:

2LP/51 8B Calculated Level = (Indicated Voltage - 0. 19829) x 100%

0.79315100%

Calculated Level= ( -0.19829)x 0.79315 ( %)


2LP/517B Calculated Level = (IndicatedVoltage - 0. 19829) x 100%

0.79315

Calculated Level = ( - O.19829)x 710%



Page 113 of 182



Date


2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-11 - 2LP/51 8B

2-LI-3-42 (2) 2-R-12 - 2LP/517B




2-LR-3-43 N/A N/A N/A N/A(Pen I Red)

2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 114 of 182


SG 1,, 25% Level Verification Data

Date

(1) Calculations

2LP/519B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100

0.79315- Calculated Levei= ( -O. 19829) 0.79315%)


2LP/518B Calculated Level = (Indicated Voltage- -. 19829) x 100%

g0.79315100%Calculated Level = ( -0.19829)x 079 15%)0.79315

Calculation Performed By: Verified By:2LP/517B 100%

Calculated Level = (Indicated Voltage- 0.19829)x 100.79315

Calculated Level -0.19829)x 100% %

0.79315



Page 115 of 182


SG I - Final Level Verification Data

Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1X3)

2-LI-3-38 (2) 2-R-5 - 2LP/519B

2-LI-3-39 (2) 2-R-1 I - 2LP/518B

2-LI-3-42 (2) 2-R-12 - 2LP/517B





2-LI-3-164 N/A N/A N/A N/A


2-LI-3-174 N/A N/A N/A N/A




Page 116 of 182


SG 1 - Final Level Verification Data

Date

(1) Calculations

2LP/519B 100%Calculated Level = (Indicated Voltage- 0. 19829) x

0.79315

Calculated Level = ( -0.19829)x 100% %)0.79315


2L-P/51 8B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.79315

Calculated Level = ( -0.19829)x 100% %0.793150


2LP/517B 100%Calculated Level = (Indicated Voltage- 0. 19829)x

0.79315

Calculated Level = ( -0.19829)x 0791 %)C.om31B

[Calculation Performed By: Verified By:


Page 117 of 182


SG 2 - Initial Level Verification Data

Date


Location Voltage (1)(3)

2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 I - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B



2-LI-3-56B N/A N/A N/A NIA

2-LR-3-43 N/A N/A N/A N/A(Pen 2 Green)

2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A




Page 118 of 182



Date

(1) Calculations

2LP/529B 100%Calculated Level = (indicated Voltage - 0. 19829) x 100%Vlae 0.79315

Calculated Level=( -0.19829) x 100% . %)0.79315


2LP/528B (Indicated . 100%Calculated Level = Voltage- 0. 19829) x

100%_Calculated Level = ( -0.19829)x 0.79315 %)


Calculated Level =(Indicated Voltage - 0. 19829) x0.79315

100%Calculated Level= ( -0.19829)x 015 %)



Page 119 of 182



Date

Instrument Indication % DVM Test Point

Location

2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B

2-FR-3-48 N/A(Pen 3 Blue)

2-LI-3-56A N/A

2-LI-3-56B N/A

2-LR-3-43 N/A(Pen 2 Green)

2-LI-3-156 N/A

2-LI-3-156C N/A

2-LI-3-173 N/A



-1


Page 120 of 182



Date

(1) Calculations

2L-P/529B Calculated Level = (Indicated Voltage- 0. 19829) x 100%

0.793 15100%

Calculated Level= ( -0.19829)x 715)0.79315 -(


2/ Calculated Level = (Indicated Voltage- 0. 19829)x 0.3'•. 0.79315

100%Calculated Level= ( -0.19829)x 07 %)::: 0.79315


2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.79315

100%Calculated Level= ( -0.19829)x 0.79315 %)



Page 121 of 182



Date


2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A




Page 122 of 182



Date

(1) Calculations

2LP/S29B 100%Calculated Level = (Indicated Voltage - 0. 19829) x

0.79315

Calculated Level= ( -0.19829)x 100.9%3 %)0.79315


S2LP/528B 100%Calculated Level = (Indicated Voltage- 0. 19829) x

0.79315

CalculatedLevel=( -0.19829)x 100.73 ( %)6.79315


2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315

Calculated Level=( -0.19829)x 1700% 5 %)0.79315

Calculation Performed By: T _Verified By:


Page 123 of 182



Date


2-R-52LP/529B

2-R-112LP/528B

2-R-122LP/527B


Page 124 of 182



Date


2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 I - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A




Page 125 of 182



Date

(1) Calculations

2LP/529B IOCalculated Level = (Indicated Voltage- 0.19829)x 100%

0.79315100%

Calculated Level = ( -0.19829)x 0.73 ( %)0.79315


2LP/528B Calculated Level = (Indicated Voltage - 0. 19829) x 100%

0.79315

Calculated Level = ( -0.19829)x 0.79315%


2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829) x0.79315

Calculated Level = ( -0.19829) x 100% . %)0.79315

Caclation Performed By: . Vedlfied By:


Page 126 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (XH3)

2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A



WBN Feedwater & Steam Generator Level 2-I e-003A-02Unit 2 Rev.0000

Page 127 of 182



Date

(1) Calculations

2LP/529B Calculated Level = (Indicated Voltage - 0.19829) x 100%0.79315

100%Calculated Level= ( -0.19829)x 100931%)0.79315


2LP/528B Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315

100%/Calculated Level= ( -0.19829)x 0.79315 %)


2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 1

0.79315100%_

Calculated Level- ( -0.19829)x 0.7931%)0.79315



Page 128 of 182



Date


2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 I - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A) MI


(3) Maximum and Minimum calculated levels are within 1.1 %


Page 129 of 182



Date

(1) Calculations

2LPi529B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.30.79315

100%Calculated Level= ( -0.19829)x 0.793 15 %)


2LP/528B 100%Calculated Level = (Indicated Voltage - 0.19829) x 0.79315

Calculated Level=( -0.19829)x 100% .3 %0.79315


2LP/527B 100%Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315

Calculated Level = ( -0.19829)x( %)0.79315



Page 130 of 182



DateInstrument Indication % DVM Test Point

Location

2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B


2-LI-3-56A N/A

2-LI-3-56B N/A

2-LR-3-43 N/A(Pen 2 Green)

2-LI-3-156 N/A

2-LI-3-156C N/A

2-LI-3-173 N/A




Page 131 of 182



Date

(1) Calculations

,2L-P/529B 1 00%Calculated Level = (Indicated Voltage- 0. 19829)x 100%

0.79315


2LP/528B 10l0%-Calculated Level = (Indicated Voltage- 0. 19829) x010

Calculated Level = ( --0.1982+) 100__% %)0.79315

Calculation Performed By: Verified By:2LP/527B (Idctd-. 100%

Calculated Level = (Indicated Voltage- 0. 19829) x0.3

Calculated Level = ( -0.19829)x 100. - ( %)0.79315

Calculation Performed By: T erifiedByFcBy:


Page 132 of 182

Data Sheet 21(Page l of 1)


Date


2-R-52LP/529B

2-R-112LP/528B

2-R-122LP/527B


Page 133 of 182



Date


2-LI-3-51 (2) 2-R-5 - 2LP1529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A




Page 134 of 182



Date

(1) Calculations


0.79315

Calculated Level = ( -0.1 9829)x 7100% %)0.79315=

Calculation Performed By: Verified By:2LP/528B "100%

Calculated Level (Indicated Voltage - 0. 19829) x 10.70./79315

100%/Calculated Level=( -0.19829)x 0.91 =%0.79315


2LP/527B 100%Calculated Level = (Indicated Voltage- 0.19829)x0• 0.79315

100%_Calculated Level= ( -0.19829)x 0.79315 %)


WBN Feedwater & Steam Generator Level 2-RTI-003A-02Unit 2 Rev.0000

Page 135 of 182



Date


2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 NIA N/A N/A N/A




Page 136 of 182



Date

(1) Calculations2LP/529B 100%

Calculated Level = (Indicated Voltage - Oý. 19829)x

0.79315



2LP/528B 100%2LP/528B Calculated Level = (Indicated Voltage- 0. 19829)x 0.30.79315

Calculated Level= ( -0.19829)x 10.9 %)

Calculation Performed By: * Verified By:


0.79315

Calculated Level= ( -0.19829)x 100% .1%)0.79315



Page 137 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1 X3)

2-LI-3-51 (2) 2-R-5 - 2LP/529B

2-LI-3-52 (2) 2-R-1 1 - 2LP/528B

2-LI-3-55 (2) 2-R-12 - 2LP/527B





2-LI-3-156 N/A N/A N/A N/A


2-LI-3-173 N/A N/A N/A N/A




Page 138 of 182



Date

(1) Calculations

2LP/529B Calculated Level = (Indicated Voltage - O. 19829)x 100%

0.79315

Calculated Level=( -0.19829)x 100% %)0.79315


2LP/528B 100%Calculated Level = (Indicated Voltage -0. 19829)×x 100

0.79315

Calculated Level = ( - 0.19829) x 0.7935%)


2LP/527B Calculated Level = (Indicated Voltage - O..19829)x 100%

0.79315




Page 139 of 182


SG 3 - Initial Level Verification Date

Date

Instrument Indication % DVM Test Point

Location

2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP1538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B


2-LI-3-98A N/A

2-LI-3-98B N/A

2-LR-3-98 N/A(Pen 1 Red)

2-LI-3-148 N/A

2-LI-3-148C N/A

2-LI-3-172 N/A




Page 140 of 182


SG 3 - Initial Level Verification Date

Date

(1) Calculations


0.79315



2LP/538B Calculated Level = (Indicated Voltage- 0. 19829)x 100%

0.79315

Calculated Level=( -0.19829)x 100% .1%)0.79315


2LP/537B Calculated Level = (Indicated Voltage - 0.19829) x 100%

0.79315

Calculated Level: ( -0.19829)x 10.9 %)0.7Cm15

Calculation Performed By: Verifie d By:


Page 141 of 182



Date



2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 I - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 142 of 182



Date

(1) Calculations


0.79315,100%



.2LP/538B 100%Calculated Level (Indicated Voltage- 0. 19829) x 100%

Calculated Level=( -0.19829)x 100% %)0.79315 -

Calculation Performed By: - Verified By:


0.79315

Calculated Level= ( -0.19829)x 100% 1 ( %)0.79315


WBN' Feedwater & Steam Generator Level 2,PTI-003A-02Unit 2 Rev. 0000

Page 143 of 182



Date


2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 144 of 182



Date

(1) Calculations

2LP/539B Calculated Level = (Indicated Voltage - 0. 19829)x 100%

0.79315



2LP/538B Calculated Level = (Indicated Voltage- 0.19829) x 100%

0.79315Calculated Level=( -0.19829)x 100% =( %)

0.79315


2LP/537B Calculated Level = (Indicated Voltage- -. 19829)x 100%

0.79315100%

Calculated Level=( -0.19829)x 100% . %)0.79315



Page 145 of 182



Date


2-R-52LP/539B

2-R-112LP/538B

2-R-122LP/537B


Page 146 of 182



Date


2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 I - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 147 of 182



Date

(1) Calculations

2L-P/539B 100%Calculated Level = (Indicated Voltage- 0. 19829) x 0.79315

.100%Calculated Level-- ( -0.19829)x 00%-3 ( %)


2LPI538B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%0.79315

Calculated Level =( -0.19829)x 100 %)0.793 15


2LP/537B 100%Calculated Level = (Indicated Voltage- 0. 19829)x 10.30.79315

Calculated Level=( -0.19829)x 100% ( %)0.79315



Page 148 of 182



Date


2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 I - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A


(3) Maximum and Minimum calculated levels are within 1.1%.


Page 149 of 182



Date

(1) Calculations2LP/539B 100%

• Calculated Level= (Indicated Voltage -0.19829) x 0.3

Calculated Level= ( -0.19829)x 100%7915%)0,79315


2L-P/538B Calculated Level = (Indicated Voltage - 0.19829)x 100%0.79315

Calculated Level=( -0.19829)x 100731 %)0.79315


2LP/537B. (indictedO-0 100%Calculated Level = (Indicated Voltage- 0.19829)x 0.7

Calculated Level = ( - 0.19829)X 100%73 %)0.79315

•[Calculation Performed By: . Verified By:


Page 150 of 182



Date

Instrument Indication % DVM Test Point M&TE No.. Indicated Calculated Level InitialsLocation Voltage (1)(3)

2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 151 of 182



Date

(1) Calculations


0.79315

Calculated Level=( -0.19829)x 100%. =( %)'0.79315

Calculationý Performed By: Verified By:

2LP/538B Calculated Level = (Indicated Voltage- 0. 19829) x 100%0.79315




0.79315

Calculated Level=( -0.19829)x 100% _( %0.793 15



Page 152 of 182



Date


2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 153 of 182



Date

(1) Calculations

2LP/539B Calculated Level = (Indicated Voltage- 0.1 9829) x 100%

0.79315100%

Calculated Level -0.19829)x 007931 ( %)0.79315



0.79315


Calculation Performed By: Verified By:2LP/537B . acltdLvl=100%

BCalculated Level = (Indicated Voltage- 0. 19829) x

0.79315

Calculated Level =( -0.19829)x 100% %)0.79315

Calculation Performed By: Verified By:Fy


Page 154 of 182



Date


2-R-52LP/539B

2-R-112LP/538B

2-R-122LP/537B


Page 155 of 182



Date


2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 156 of 182



Date

(1) Calculations

2LP/539B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 1V0.79315

100%CalculatedLevel=( -0.19829)x 0.79315 %)


2LP/538B 100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%

Calculated Level = ( -0. 19829)x 100% ( %)0.79315


2LP/537B .100%Calculated Level = (Indicated Voltage- 0. 19829)x 0.3

Calculated Level = ( -0.19829)x 100% =%)0.79315



Page 157 of 182



Date



2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 1 - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 158 of 182



Date

(1) Calculations





0.79315100%Calculated Level = ( -0.19829)x 07 = ( %)


2LP/537B _100%Calculated Level = (Indicated Voltage - 0. 19829) x

0.79315

Calculated Level = ( -0. 19829)x 0 = ( %)0.793 15


W BN Feedwater & Steam Generator Level 2- TI-003A-02Unit 2 Rev. 0000

Page 159 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials(2) Location Voltage (1X3)

2-LI-3-93 (2) 2-R-5 - 2LP/539B

2-LI-3-94 (2) 2-R-1 I - 2LP/538B

2-LI-3-97 (2) 2-R-12 - 2LP/537B





2-LI-3-148 N/A N/A N/A N/A


2-LI-3-172 N/A N/A N/A N/A




Page 160 of 182



Date

(1.) Calculations

2LP/539B Calculated Level = (Indicated Voltage - 0. 19829) x 100%

g0.79315

Calculated Level = ( -0.19829)x 100 ( %0.79315


2LP/538B 100%Calculated Level = (Indicated Voltage - 0.19829)x

0.79315100%

Calculated Level=( -0.19829)x 109% ()~0.79315


2LP/537B 100%Calculated Level = (Indicated Voltage - 0. 19829)x: 0.79315

Calculated Level= ( - 0.19829)x' %)Ccanerd)r .By:



Page 161 of 182



Date


Location Voltage (1 X3)

2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 1 - 2LP/548B

2-LI-3-110 (2) 2-R-12 - 2LP/547B



2-LI-3-111B N/A NIA N/A N/A


2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171C N/A NIA N/A N/A

2-LI-3-175 N/A N/A N/A N/A




Page 162 of 182



Date

(1) Calculations

2LP/549BCalculated Level = (Indicated Voltage- 0.19829) 100%.

0.79315

Calculated Level=( -0.19829)x 100% %)0.79315


Calculated Level = (Indicated Voltage- 0.19829)x 0.3

0.79315.100%Calculated Level =( - 0.19829)x • 0.731 %)



0.79315

Calculated Level= ( -0. 19829)x 00%3 ( %)



Page 163 of 182



Date


2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 1 - 2LP/548B

2-LI-3-110 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A


2-LI-3-175 N/A N/A N/A N/A




Page 164 of 182



Date

K

(1) Calculations

2LP/549B 1000%Calculated Level = (Indicated Voltage - 0. 19829) x 100%Voltge /0.79315

Calculated Level=( -0.19829)x 100% =%)0.79315


Calculated Level = (Indicated Voltage- 0.19829) x 100%g'0.79315

Calculated Level=( -0.19829)x 100% =%)

0.79315


* 2LP/547B Calculated Level = (Indicated Voltage -10.%19829) x 005

0.79315

Calculated Level = P0B.V19829)xr B: %)

Calculation Performed By: Verified By--


Page 165 of 182



Date


2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 I - 2LP/548B

2-LI-3-1 10 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A


•2-LI-3-175 N/A N/A N/A N/A




Page 166 of 182



Date

(1) Calculations

2LP/549B •.100%Calculated Level = (Indicated Voltage - 0. 19829) x 100%

Calculated Level =( -0.19829)x 100% -0.79315-( %


2LP/548B Calculated Level = (Indicated Voltage -0.19829) x 100%

0.79315

Calculated Level = ( - 0.19829)x- 100% %)



0.79315

Calculated Level = ( -0.19829)x 100% % %)

0.79315,



Page 167 of 182



Date


2-R-52LP/549B

2-R-112LP/548B

2-R-122LP/547B


Page 168 of 182



Date


Location Voltage (1)3)

2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-11 - 2LP/548B

2-LI-3-110 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171C N/A N/A NiA N/A

2-LI-3-175 N/A N/A N/A N/A




Page 169 of 182



Date

(1) Calculations

2LP/549B 100%Calculated Level = (Indicated Voltage- 0.19829)x 0.79315

Calculated Level = ( -0. 19829)x 100% =%)

0.79315


2LP/5 .48B Calculated Level (Indicated Voltage- 0. 19829)x 100%0.79315

Calculated Level=( -0.19829)x 100%0.79315



Calculated Level = ( -0.19829)x =7 ( %)



Page 170 of 182



Date


2-1-k3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1I - 2LP/548B

2-LI-3-1 10 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171 C N/A N/A N/A N/A

2-LI-3-175 N/A N/A N/A N/A




Page 171 of 182



Date

(1) Calculations


1 0.79315100%

Calculated Level = ( - 0.19829)x 0.793 15 %)


2LP1548B Calculated Level = (Indicated Voltage- 0.19829) x D1.0

100%Calculated Level ( -- 0.19829)x 0.9 %)


2LP/547B Calculated Level = (Indicated Voltage- 0.19829) x 073

Calculated Level: ( -0.19829)x 0•%73 %)



Page 172 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (1 X3)

2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 1 - 2LP1548B

2-LI-3-1 10 (2) 2-R-12 - 2LP/547B


2-LI-3-1IIA N/A N/A N/A N/A

2-LI-3-1IIB N/A N/A N/A N/A


2-LI-3-171 N/A N/A N/A N/A-


2-LI-3-175 N/A N/A N/A N/A




Page 173 of 182


SG4 - 50% Level Verification Data

Date

(1) Calculations

2LP/549B Calculated Level = (Indicated Voltage- 0.19829)x 100%

0.79315

Calculated Level = ( -0.19829)x 10% %)


2LP/548B 100%Calculated Level = (Indicated Voltage- 019829) 0

0.79315

Calculated Level= ( -0.19829)x 0.7931%)


2LP1547B 100%Calculated Level = (Indicated Voltage -0.19829) x 0.9• 0.79315

100%Calculated Level= ( -. 0.19829)x 0.731 %)



Page 174 of 182



Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level InitialsLocation Voltage (OX3)

2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 I - 2LP/548B

2-LI-3-110 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171C N/A NIA N/A N/A

2-LI-3-175 N/A N/A N/A N/A

•(2) Maximum and Minimum indicated levels are within 5%



Page 175 of 182



Date

(1) Calculations

2LP/549B Calculated Level = (Indicated Voltage- 0. 19829)x 100%0.79315

100%/Calculated Level= ( -0.19829)×x 0.7935 %)


2LP/548B 10Calculated Level = (Indicated Voltage - 0. 19829)x 100%

0.79315

Calculated Level= ( -0.19829)x 100% %0.79315=( %


2LP/547B 100%Calculated Level = (Indicated Voltage - 0.19829)x 0.79315

100%CalculatedLevel=( -0.19829)x 0.79315 %)

0.79315

[Calculation Performed By: Verifie~d 7By:

WBN Feedwater & Steam Generator Level 2-RTe-003A-02Unit 2 Rev.0000

Page 176 of 182



Date


2-R-52LP/549B

2-R-112LP/548B

2-R-122LP/547B


Page 177 of 182



Date


2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-11 - 2LP/548B

2-LI-3-1 10 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171C. N/A N/A N/A N/A

I2-LI-3A175 N/A N/A N/A N/A




Page 178 of 182



Date

(1) Calculations

•2LP/549B 1.00%Calculated Level = (Indicated Voltage - 0. 19829) x

0.79315

Calculated Level = ( -0.19829)x 1 %)0.79315-


2LP/548B 100%Calculated Level (Indicated Voltage - 0. 19829) x

0.79315100%

Calculated Level= ( -0.19829)x 0910


2LP/547B -. " 100%Calculated Level = (Indicated Voltage- 0.19829)x 100%0.79315

100%_CalculatedLevel=( -0.19829)x 0.79315 %)



Page 179 of 182



Date


2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 1 - 2LP/548B

2-LI-3-1 10 (2) 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171 C N/A N/A N/A N/A

2-LI-3-175 N/A N/A N/A N/A




Page 180 of 182



Date

(1) Calculations• 2LPi549B 100%

Calculated Level= (Indicated Voltage-0.19829)x

0.79315100%1

Calculated Level= ( -0.19829)x 0.79315. = %)

Calculation Performed By: Verified By: .

2LP/548B Calculated Level = (IndicatedVoltage- -. 19829) x 100%

' 0.79315

Calculated Level=( -0.19829)x 100%%)0.79315



Voltge '0.79315

Calculated Level = ( -0. 19829)x 0091 =%)0.79315

rCalculation Performed .By: [Verified By:


Page 181 of 182


SG 4 - Final Level Verification' Data

Date

Instrument Indication % DVM Test Point M&TE No. Indicated Calculated Level Initials( 2) Location Voltage (1)(3)

2-LI-3-106 (2) 2-R-5 - 2LP/549B

2-LI-3-107 (2) 2-R-1 1 - 2LP/548B

2-LI-3-1 10 (2)- 2-R-12 - 2LP/547B





2-LI-3-171 N/A N/A N/A N/A

2-LI-3-171C N/A N/A -N/A N/A

2-LI-3-175 N/A N/A N/A N/A




Page 182 of 182



Date

(1) Calculations

2LP/549B 10Calculated Level= (Indicated Voltage -0.. 19829)x

0.79315

Calculated Level = ( -0. 19829)1x 0% %)0.79315


2LP/548B Calculated Level = (Indicated Voltage -0.19829) x 100%0.79315

Calculated Level= ( -0.19829)x = ( %)0.793/15


2LP/547B Calculated Level = (Indicated Voltage- 0. 19829) x 100%: 0.79315

Calculated Level= ( -0.19829)x 100% %)0.79315




TITLE: •;•eio•"- C..oo•oi•+ Flow MewA.reintn

Instruction No: Z-P-Th- 8- OZ.

Revision No: 0000

PREPARED BY: ])an e.i b. Ore /Q c - 10m-, DATE: (.-21-11PRINT NAME I SIGNATURE

REVI EWE D BY: kc" 5' 0-Th DATE: (,2 Z01 IPRINT NAME /SIG(A•LiRE- - /•


JTG MEETINPTo: 9,- t2 -- oat!A=

JTG CHAI RMA • ) DATEN••I'1••

APPROVED BY: DATE:PREOPE RAt6AL STARTUP MANAGER


JTG MEETING No:

JTG CHAIRMAN: DATE:

APPROVED BY: DATE:PREOPERATIONAL STARTUP MANAGER

SMP-8.0 R7 Administration of Preoperational Test instructions, Appendix B

WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev. 0000

Page 2 of 33

Revision Log

Revision Affectedor Change Effective Page

Number Date Numbers Description of RevisionlChange

0000 3/f .. ALL Initial Issue based on Unit 1 PTI-068-002 Rev. 0CN 3

Table of Contents

1.0 INTRODUCTION .......................................................................................................... 51.1 T est O bjectives ......................................................................... ..................................... 5

1.2 S co pe ........................................... 5................................................................................ 5

2.0 REFERENCES ..................................................................................................... 62.1 Performance References .......................................................................................... 6

2.2 Developmental References ......................................................................................... 6

3.0 PRECAUTIONS AND LIMITATIONS ........................................................................ 8

4.0 PREREQUISITE ACTIONS ................................................................................... 10

4.1 Preliminary Actions ................................................................................................. 10

4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ............ 144.3 Field Preparations................................................................................................. 144.4 Approvals and Notifications ..................................................................................... 15

5.0 ACCEPTANCE CRITERIA .................................................................................... 16

6.0 PERFORMANCE .................................................................................................... 17

6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 17

6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and (RCS)Low Flow Alarm Verification ........................................ 20

6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 23

6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and (RCS)Low Flow Alarm Verification ................................................................................... 26

7.0 POST PERFORMANCE ACTIVITY ........................................................................ 29

8.0 RECORDS .................................................................................................................. 29

Appendix A: TEST PROCEDURESIINSTRUCTIONS REFERENCEREVIEW .......................... ...................... 30

Appendix B: TEMPORARY CONDITION LOG ........................................................... 31


Page 4 of 33

Appendix C: PERMANENT PLANT INSTRUMENTATION LOG ................................ 32


Page 5 of 33

1.0 INTRODUCTION

1.1 Test Objectives

This test will demonstrate the operability of the Reactor Coolant Flow MeasurementSystem and Reactor Coolant Low flow alarm signals.

1.2 Scope

A. Demonstrate proper operations of the Reactor Coolant System Loop FlowMeasurements.

B. This test is being performed to satisfy a temporary condition during HotFunctional Test (HFT) simulating the core being in place by adjusting ReactorCoolant flow instrumentation to indicate 110% (106-110) flow with all RCPs inservice.

WBN Reactor Coolant Flow Measurement 2-PTI-068-02.Unit 2 Rev. 0000

Page 6 of 33

2.0 REFERENCES

2.1 Performance. References

A. 2-SOI-68.02, System Operating Instruction, Reactor Coolant Pumps

B. SMP-9.0, Conduct of Test

C. 2-PTI-068-01, Hot Functional Test (HFT), Heatup & Cooldown

D. 2-SI-68-25 Recalibration of Channel I Reactor Coolant System Flow Loops

E. 2-SI-68-26 Recalibration of Channel II Reactor Coolant System Flow Loops

F. 2-SI-68-27 Recalibration of Channel III Reactor Coolant System Flow Loops


A. Unit 2 Final Safety Analysis Report - Amendment 107

1. Table 14.2-1 Sheet 77, 78 and 79 of 89 Integrated Hot Functional Test-Summary

2. Section 5.0 Reactor Coolant System

B. Drawings

1. Flow Drawings

a. 2-47W813-1, Rev 5, Flow Diagram Reactor Coolant System

2. Electrical

a. 2-45B655-E6B, Rev 0, Electrical Annunciator Window Box XA-55-6BEngraving

b. 2-47B601-55-71, Rev 1, Electrical Instrument Tabulation

3. Mechanical

None

4. Logic/Control


Page 7 of 33


a. 2-47W610-68-1, Rev 1, Electrical Control Diagram, Reactor CoolantSystem

b. 2-47W610-68-2, Rev 1, Electrical Control Diagram, Reactor CoolantSystem

c. 2-47W610-68-3, Rev 2, Electrical Control Diagram, Reactor CoolantSystem

d. 2-47W610-68-4, Rev 1, Electrical Control Diagram, Reactor CoolantSystem

5. Vendor Drawings

a. 108D408 Sh 2, Rev 6, Westinghouse, Process Control Block Diagram

b. 108D408 Sh 3, Rev 4, Westinghouse, Process Control Block Diagram

c. 108D408 Sh 4, Rev 4, Westinghouse, Process Control Block Diagram

d. 108D408 Sh 5, Rev 16, Westinghouse, Process Control BlockDiagram

C. Vendor Manuals

1. WBN-VTD-Wl20-0670, Rev 21, Westinghouse Instruction Book forReactor Coolant Pumps

D. Documents

1. 2-TSD-68-2A, Reactor Coolant System (RCS) Flow Measurements For HotFunctional Testing, Rev 1


A. Standard precautions shall be followed for working around energized electricalequipment in accordance with TVA Safety Procedure 1021.

B. Steps may be repeated if all components cannot be tested in a step. However,if the test has been exited, prerequisite steps must be re-verified and aChronological Test Log (CTL) entry made.

C. Discrepancies between component ID tags and the description in aprocedure/instruction do not require a Test Deficiency Notice, TDN, inaccordance with SMP-14.0, if the UNIDs match, exclusive of place-keepingzeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and thenoun description is sufficient to identify the component. If the component labelneeds to be changed, a Tag Request Form (TR Card) should be processed inaccordance with TI-12.14. Make an entry in the CTL and continue testing.

D. All wires removed/lifted from a terminal shall be identified and taped or coveredwith an insulator to prevent personnel or equipment hazard and possiblespurious initiations. The wires should be grouped together and labeled with thework implementing document number that required them to be lifted if leftunattended.

E. All open problems are to be tracked by a corrective action document andentered on the appropriate system punchlist.

F. Problems identified during the test shall be annotated on the Chronological TestLog (CTL) from SMP-9.0 including a description of the problem, the procedurestep when/where the problem was identified, corrective action steps taken toresolve the problem, and the number of the corrective action document, if onewas required.

G. Observe all Radiation Protection (RP) requirements when working in or nearradiological areas.

H. Ensure there are no adverse effects to the operation of Unit 1 structures,systems, or components.

I. During the performance of this procedure visual observation of piping andcomponents is required. This includes steady state and transient operationswith visual confirmation that vibration is not excessive.

J. If the vibration is determined to be excessive the Test Engineer shall initiate aTest Deficiency Notice (TDN).


Page 9 of 33

3.0 PRECAUTIONS AND LIMITATIONS (continued)

K. The following Reactor Coolant Pump (RCP) maximum starting duty limitsshould be observed: (2-SOI-68-02)

1. After any period of running or after an attempted start, restart should not bemade until the motor has been idle for at least 30 minutes.

2. The number of RCP start attempts should be limited to three in anytwo hour period, with RCP idle at least 30 minutes prior to each startattempt. A fourth start should not be made until RCP motor has been idlefor at least I hour.

NOTE

Coordinate with the on duty Hot Functional Test Director prior to commencement ofeach test section.

L. The Sis referenced in this pre-op will be used as a guide by the I&C work planwriter, steps that are not required to accomplish the temporary settings may bedisregarded at the discretion of the work plan writer.

M. This pre-op is being performed to satisfy a temporary condition during HotFunctional Test (HFT) simulating the core being in place by adjusting ReactorCoolant flow instrumentation to indicate 110% (106-110) flow.


Page 10 of 33

Date

4.0 PREREQUISITE ACTIONSNOTE

Prerequisite steps may be performed in any order unless otherwise stated and should becompleted as close in time as practicable to the start of the instruction subsection to whichthey apply.


[1] INFORM Preoperational Startup engineering personnel ofrequirement to monitor vibration data on rotating equipmentand piping during periods of testing.

[2) EVALUATE open items in Watts Bar Integrated TaskEquipment List (WITEL), AND

ENSURE they will NOT adversely affect the test performance

and results.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

[3] ENSURE changes to the references listed on Appendix A,have been reviewed and determined NOT to adversely affectthe test performance.

[4] VERIFY current revisions and change paper for referenceddrawings has been reviewed and determined NOT toadversely affect the test performance, AND

ATTACH documentation of current drawing revision numbersand change paper that were reviewed to the data package.

[5] VERIFY the test/performance copy of this Preoperational TestInstruction (PTI) is the current revision and as needed, eachtest person assisting in this test has the current revision.


Page 11 of 33

Date


[6] ENSURE outstanding Design Change Notices (DCN's),Engineering Document Construction Release (EDCR's) orTemporary Alterations (TA's) do NOT adversely impact testing,AND

ATTACH documentation of DCN's, EDCR's and TA's that

were reviewed to the data package.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

[7] ENSURE required Component Testing has been completedprior to start of test.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

[8] ENSURE the following Surveillance Procedures have beencompleted prior to the performance of this test:

A. 2-SI-68-12, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL I,LOOP 2-LPF-68-6A

B. 2-SI-68-13, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL IILOOP 2-LPF-68-6B

C. 2-SI-68-14, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 1 CHANNEL Ill,LOOP 2-LPF-68-6D

D. 2-SI-68-15, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL I,LOOP 2-LPF-68-29A


Page 12 of 33

Date


E. 2-SI-68-16, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL II,LOOP 2-LPF-68-29B

F. 2-SI-68-17, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 2 CHANNEL Ill,LOOP 2-LPF-68-29D

G. 2-SI-68-18, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL I LOOP2-LPF-68-48A

H. 2-SI-68-19, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL II,LOOP 2-LPF-68-48B

I. 2-SI-68-20, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 3 CHANNEL IIILOOP 2-LPF-68-48D

J. 2-SI-68-21, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL I LOOP2-LPF-68-71A

K. 2-SI-68-22, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL IILOOP 2-LPF-68-71B

L. 2-SI-68-23, 18 MONTH CHANNEL CALIBRATIONREACTOR COOLANT FLOW LOOP 4 CHANNEL Ill,LOOP 2-LPF-68-71D

[9] ENSURE all piping supports required for Hot FunctionalTesting are installed and adjusted as required.

[10] CONDUCT a pretest briefing with Test and Operationspersonnel in accordance with SMP-9.0

Date


NOTE

Final calibration of plant instruments listed in Appendix C will be performed for PowerAscension Testing.

[11] VERIFY plant instruments, listed on Appendix C, PermanentPlant Instrumentation Log, are placed in service and are withintheir calibration interval.

NOTE

Any Annunciator points associated with 2-MUX-55-12 and 2-MUX-55-13 ONLY havemaster switches at the bottom of each terminal strip.

All points associated with 2-TBK-55-25, 2-TBK-55-26, 2-TBK-55-27, and 2-TBK-55-28 willnot have individual switches or a master switch.

[12] VERIFY System 55, Annunciator and Sequential EventsRecording System, FTA switches (in Panel 2-M-21) associatedwith the following annunciator window inputs have beenverified to be in the ON position.

A. 2-XA-55-6B/120-B

B. 2-XA-55-6B/121-B

C. 2-XA-55-6B/122-B

D. 2-XA-55-6B/123-B


[14] ENSURE a review of outstanding Clearances has beencoordinated with Operations for impact to the testperformance, AND

RECORD in Appendix B, Temporary Condition Log if required.

WBN Reactor Coolant Flow Measurement 2-PTI-068-02Unit 2 Rev.0000

Page 14 of 33

Date




[161 PERFORM a pretest walkdown on equipment to be tested toensure no conditions exist that will impact-test performance.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

[17] REVIEW preventive maintenance for system/componentscovered by this test, AND

VERIFY no conditions exist that will impact test performance.

A. Subsection 6.1

B. Subsection 6.2

C. Subsection 6.3

D. Subsection 6.4

4.2 Special Tools, Measuring and Test Equipment, Parts, and

Supplies

None


[1] VERIFY that there is an I&C Maintenance work order in placeto calibrate RCS Flow Loops 1 thru 4. The setting will requireall RCS Flow instrument loops to be adjusted to a flow of110% (106-110) with all four Reactor Coolant Pumps running,this adjustment is to simulate the Core being in place AND

RECORD WO#


Page 15 of 33

Date


[1] OBTAIN permission of the Preoperational Startup Manager tostart the test.

Preoperational Startup ManagerSignature

Date

[2] OBTAIN the Unit 2 Supervisor's (US/SRO) or Shift Manager's(SM) authorization.

U2 US/SRO/SM Signature Date


Page 16 of 33


[1] RCS flow loops instrumentation are indicating 110% (106-110) flow. (Steps6.1[5], 6.2[5], 6.3[5], 6.4[5])


Page 17 of 33

Date

6.0 PERFORMANCE

NOTES

1) Plant Maintenance I&C Department will recalibrate the RCS Flow InstrumentationLoops 1 thru 4, to indicate 110% (106-110) flow. Completion of all prerequisiteSection 4.0 will satisfy initial conditions for test Sections 6.1 thru 6.4, which may beperformed in any order.

2) RCP pump starts and stops shall be coordinated with the sequencing events of2-PTI-068-01, Hot Functional Test Procedure for checking Low Flow Alarms forSections 6.1 through 6.4

3) IF, THEN steps in the performance section can be NA'd if conditions are met.

6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification.

[1] ENSURE Vibration Test Personnel are in place to monitorvibration of piping and equipment in support of this section.



[31 ENSURE all 4 RCPs are running.

[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF plateau has been reached,AND

VERIFY RCP 2-MTR-68-8 is running.


Page 18 of 33

Date

6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)

[5] VERIFY the following (RCS) Loop 1 Flow indicators are reading 110% (106 to110) Flow, AND

RECORD:

A. 2-FI-68-6A, RCS LOOP I COOLANT FLOW, located at2-M-5 panel in Main Control Room.

% Flow (ACC CRIT)

B. 2-FI-68-6B, RCS LOOP 1 COOLANT FLOW, located at2-M-5 panel in Main Control Room.

% Flow (ACC CRIT)

C. 2-FI-68-6D, RCS LOOP 1 COOLANT FLOW, located at2-M-5 panel in Main Control Room.

% Flow (ACC CRIT)

[6] IF flow indicators do not read 110% (106-110), THEN

PERFORM WO to recalibrate loop flowinstrumentation AND

Repeat step 6.1[5].

[7] VERIFY Annunciator Window 120B, RCS LOOP 1 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.

[8] STOP Reactor Coolant Pump 2-PMP-68-8 using handswitch2-HS-68-8AA at panel 2-M-5.

[9] VERIFY Annunciator 120B, RCS LOOP 1 FLOW LO,ALARMS.

[10] VERIFY Trip Status Light Box 4, Loop I FLOW LO FS-68-6Aat 2-M-6, 2-XX-55-6A is lit.


Page 19 of 33

Date

6.1 Reactor Coolant System (RCS) Loop No. I Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)

[11] VERIFY Trip Status Light Box 24, Loop I FLOW LO FS-68-6Bat 2-M-6, 2-XX-55-6A is lit.

[12] VERIFY Trip Status Light Box 44, Loop I FLOW LO FS-68-6D

at 2-M-6, 2-XX-55-6A is lit.

[13] RECORD the following (RCS) Loop 1 Flow indications:

A. 2-FI-68-6A, RCS LOOP 1 COOLANT FLOW

% Flow

B. 2-FI-68-6B, RCS LOOP 1 COOLANT FLOW

% Flow

C. 2-FI-68-6D, RCS LOOP 1 COOLANT FLOW

% Flow

CAUTION

After any period of running or after an attempted start, restart should not be made until themotor has been idle for at least 30 minutes.

[14] START Reactor Coolant Pump 2-PMP-68-8 in accordancewith 2-SOI-68.02 Section 5.0 Startup.

[15] VERIFY Annunciator Window 120B, RCS LOOP 1 FLOW LO,is CLEAR.

[16] VERIFY Trip Status Light Box 4, Loop 1 FLOW LO FS-68-6Aat 2-M-6, 2-XX-55-6A is NOT lit.

[17] VERIFY Trip Status Light Box 24, Loop 1 FLOW LO FS-68-6Bat 2-M-6, 2-XX-55-6A is NOT lit.

[18] VERIFY Trip Status Light Box 44, Loop 1 FLOW LO FS-68-6Dat 2-M-6, 2-XX-55-6A is NOT lit.


Page 20 of 33

Date

6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and(RCS) Low Flow Alarm Verification.




[3] ENSURE all 4 RCPs are running.



[5] VERIFY the following (RCS) Loop 2 Flow indicators are reading 110% (106 to110) flow, AND

RECORD:

A. 2-FI-68-29A, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room

% Flow (ACC CRIT)

B. 2-FI-68-29B, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room

% Flow (ACC CRIT)

C. 2-FI-68-29D, RCS LOOP 2 COOLANT FLOW, located at2-M-5 panel in Main Control Room

% Flow (ACC CRIT)


Page 21 of 33

Date

6.2 Reactor Coolant System (RCS) Loop No. 2 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)



Repeat step 6.2[5].

[7] VERIFY Annunciator Window 121 B, RCS LOOP 2 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.


[9] VERIFY Annunciator Window 121B, RCS LOOP 2 FLOW LO,ALARMS.

[10] VERIFY Trip Status Light Box 5, Loop 2 FLOW LO FS-68-29Aat 2-M-6, 2-XX-55-6A is lit.

[11] VERIFY Trip Status Light Box 25, Loop 2 FLOW LOFS-68-29B at 2-M-6, 2-XX-55-6A is lit.

[12] VERIFY Trip Status Light Box 45, Loop 2 FLOW LOFS-68-29D at 2-M-6, 2-XX-55-6A is lit.

[13] RECORD the following (RCS) Loop 2 Flow indications.


% Flow


% Flow


Page 22 of 33

Date



% Flow

CAUTION


[14] START Reactor Coolant Pump 2-PMP-68-31 in accordancewith 2-SOI-68.02, Section 5.0 Startup.



[17] VERIFY Trip Status Light Box 25, Loop 2 FLOW LOFS-68-29B at 2-M-6, 2-XX-55-6A is NOT lit.

[181 VERIFY Trip Status Light Box 45, Loop 2 FLOW LOFS-68-29D at 2-M-6, 2-XX-55-6A is NOT lit.


Page 23 of 33

Date

6.3 Reactor Coolant System (RCS) Loop No. 3 Flow Adjustment and(RCS) Low Flow Alarm Verification.





[4] COORDINATE with the on duty Hot Functional Test Director tocommence testing after the 557 OF Plateau has been reached,AND



RECORD:


% Flow (ACC CRIT)


% Flow (ACC CRIT)

C. 2-FI-68-48D, RCS LOOP 3 COOLANT FLOW, located at2-M-5 panel in Main Control Room

% Flow (ACC CRIT)

Date




Repeat step 6.3[5].

[71 VERIFY Annunciator Window 122B, RCS LOOP 3 FLOW LO,at 2-M-6, 2-XA-55-6B is CLEAR.

[8] STOP Reactor Coolant Pump, 2-PMP-68-50 using handswitch2-HS-68-50AA at panel 2-M-5.



[11] VERIFY Trip Status Light Box 26, Loop 3 FLOW LOFS-68-48B at 2-M-6, 2-XX-55-6A is lit.

[12] VERIFY Trip Status Light Box 46, Loop 3 FLOW LO

FS-68-48D at 2-M-6, 2-XX-55-6A is lit.



% Flow


% Flow


% Flow


Page 25 of 33

Date


CAUTION


[14] START Reactor Coolant Pump 2-PMP-68-50 in accordancewith 2-SOI-68.02, Section 5.0 Startup.

[15] VERIFY Annunciator Window 122B, RCS LOOP 3 Flow LO, isCLEAR.


[17] VERIFY Trip Status Light Box 26, Loop 3 FLOW LOFS-68-48B at 2-M-6, 2-XX-55-6A is NOT lit.

[18] VERIFY Trip Status Light Box 46, Loop 3 FLOW LOFS-68-48D at 2-M-6, 2-XX-55-6A is NOT lit.

Date

6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification.



have completed.





RECORD:


% Flow (ACC CRIT)


% Flow (ACC CRIT)

C. 2-FI-68-71D, RCS LOOP 4 COOLANT FLOW, located at

2-M-5 panel in Main Control Room

% Flow (ACC CRIT)


Page 27 of 33

Date

6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)



Repeat step 6.4[5].

[7] VERIFY Annunciator Window 123B, RCS LOOP 4 FLOW LO,at 2-M-6, 2-XA-55-6B, is CLEAR.




[11] VERIFY Trip Status Light Box 27, Loop 4 FLOW LOFS-68-71 B at 2-M-6, 2-XX-55-6A is lit.

[12] VERIFY Trip Status Light Box 47, Loop 4 FLOW LOFS-68-71 D at 2-M-6, 2-XX-55-6A is lit. _



% Flow


% Flow

C. 2-FI-68-71 D, RCS LOOP 4 COOLANT FLOW

% Flow

Date

6.4 Reactor Coolant System (RCS) Loop 4 Flow Adjustment and(RCS) Low Flow Alarm Verification. (continued)

CAUTION


[141 START Reactor Coolant Pump 2-PMP-68-73 in accordancewith 2-SOI-68.02 Section 5.0 Startup.


116] VERIFY Trip Status Light Box 7, Loop 4 FLOW LO FS-68-71Aat 2-M-6, 2-XX-55-6A is NOT lit.

[17] VERIFY Trip Status Light Box 27, Loop 4 FLOW LOFS-68-71 B at 2-M-6, 2-XX-55-6A is NOT lit.

[18] VERIFY Trip Status Light Box 47, Loop 4 FLOW LOFS-68-71 D at 2-M-6, 2-XX-55-6A is NOT lit.


Page 29 of 33

Date


[1] NOTIFY the Unit 2 US/SRO of the test completion and systemalignment.

(2] VERIFY that Post-test calibration of permanent plantinstruments used to record quantitative acceptance criteria hasbeen satisfactorily performed, AND

RECORD the results on Appendix C, Permanent PlantInstrumentation Log.

[3] NOTIFY the I&C Maintenance Department that RCS Loops 1thru 4 flow transmitters may be left as-is in preparation forperformance of 2-SI-68-25, 2-SI-68-26, and 2-SI-68-27,which will establish baseline adjustments for Fuel Load.

[4] NOTIFY the on duty Hot Functional Test Director of the testcompletion.

8.0 RECORDS

A. QA Records

Completed Test Package (PTI)

B. Non-QA Records

None


Page 30 of 33

Appendix A(Page I of 1)

TEST PROCEDURESIINSTRUCTIONS REFERENCE REVIEW

NOTES



PROCEDURE/ REVISION/CHANGES IMPACT INITIAL ANDINSTRUCTION YDATE. (NIA for no

CYes/No change)

Unit 2 FSAR -Amendment 107Section 5.0Chapter 14 Table 14.2-1Sheets 77-70 of 89

2-PTI-068-01 HFT Heatup& Cooldown

2-SI-68-25 Recalibrationof Channel I ReactorCoolant System, FlowLoops

2-S1-68-26 Recalibrationof Channel II ReactorCoolant System, FlowLoops

2-SI-68-27 Recalibrationof Channel III ReactorCoolant System, FlowLoops

2-TSD-68-2A, ReactorCoolant System (RCS)Flow Measurements ForHot Functional Testing


Page 31 of 33


TEMPORARY CONDITION LOG

Date

NOTE

These steps will be N/A'd if no temporary condition existed. Additional copies of this tablemay be made as necessary.

ITEM TEMPORARY CONDITION PERFORMED RETURNED TO NORMALNo. DESCRIPTION

Step Performed. By/Date Step Returned By/DateNo. CV By/Date No. CV By/Date

/ /

/ /

/ /

/ /

I /

/ /

/ I

/ /

/ /

/ /

/ /

/ /

/ /

I /

/ /

I /


Page 32 of 33


PERMANENT PLANT INSTRUMENTATION LOG

Date

INSTRUMENT PRELIM FILLED PLACED IN USED FOR POST-TEST POST-TESTOR CAL DUE AND SERVICE (1) QUANTITATIVE CAL DATE (2) CALIBRATIONINSTRUMENT DATE VENTED () ACC CRIT . ACCEPTABLE (2)

LOOP #INTDTINIT/DATE INIT/DATE YES NO INIT/DATE

2-FI-68-6A I I /

2-FI-68-6B I / /

2-FI-68-6D / / /

2-FI-68-29A / / I

2-FI-68-29B I / I

2-FI-68-29D / / /

2-FI-68-48A / / /

2-FI-68-48B /

2-FI-68-48D I I I

2-FI-68-71A I I


Page 33 of 33


PERMANENT PLANT INSTRUMENTATION LOG

Date

INSTRUMENT PRELIM FILLED PLACED IN USED FOR POST-TEST POST-TESTOR CAL DUE AND SERVICE (1) QUANTITATIVE CAL DATE (2) CALIBRATIONINSTRUMENT DATE VENTED (1) ACC CRIT ACCEPTABLE (2)

LOOP # INIT/DATEINIT/DATE INIT/DATE YES NO

2-FI-68-71B / / B

2-FI-68-71D / / D

/ / I

/ //

/ / I

These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filledand vented may be identified as Not Applicable (NIA)

(2) May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitive acceptance

criteria data.

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