NRD-SER-97-07

97 10 16

i

(Measurement Uncertainty Recapture Power Uprate)

97 2

NRC RIS 2002-03

7 1.69%

ii

.................................................................................................................................i ................................................................................................................................ii ............................................................................................................v 1 ..........................................................................................................................1 1.1 ................................................................................................................1 1.2 ................................................................................................2 1.3 1.69%......................................................................3 1.4 ............................................................................................4 1.5 ........................................................................................................5 1.6 ........................................................................................................6

2 ..............................................................................7 2.1 NSSS ...................................................................................7 2.1.1 .....................................................................................................7 2.1.2 ............................................................7 2.1.3 ............................................................................................7 2.1.4 ............................................................................................8

2.2 RCS .........................................................................................8 2.3 ........................................................................................................9

3 ................................................................................................................11 3.1 NSSS .............................................................................................11 3.1.1 ..................................................................................................11 3.1.2 ..................................................................................................11 3.1.3 ..................................................................................................14

3.2 ......................................................................................15 3.2.1 ..............................................................................15 3.2.2 ......................................................................................15 3.2.3 ..................................................................................................16

3.3 .......................................................................................................16 4 ................................................................................................17 4.1 ..........................................................17 4.1.1 ..................................................................17 4.1.2 NSSS .........................................................................17

4.2 /............................................18 4.3 ......................................................................................................22

5 ........................................................................................24

iii

5.1 ..............................................................................24 5.2 ..........................................................................24 5.3 ..........................................................................................26 5.4 ..................................................................27 5.5 ..........................................................................................28 5.6 ..............................................................................28 5.6.1 ..............................................................................28 5.6.2 ......................................................................29

5.7 ..................................................................................................30 5.7.1 ......................................................................................30 5.7.2 ..............................................................................30 5.7.3 ..........................................................31 5.7.4 ..........................................................................32 5.7.5 ..................................................................................32 5.7.6 U ...............................................................33 5.7.7 U ...........................................................................34 5.7.8 ..........................................................................................35

5.8 ..........................................................................................................35 5.9 ......................................................................................................36 5.10 ....................................................................................................36

6 ................................................................................38 6.1 ..........................................................................38 6.2 ..................................................................39 6.3 ..........................................................................39 6.4 ..................................................................57 6.4.1 ..............................................57 6.4.2 ..............................................58

6.5 ..........................................................58 6.5.1 ......................................58 6.5.2 .......................................59

6.6 (STGR)..............................................59 6.7 ......................................................................................................59 6.8 ......................................................................................................61 6.9 ......................................................................................................64

7 ................................................................................................................65 7.1 ..................................................................................65 7.2 ......................................................................................................67 7.3 ......................................................................................................67

iv

8 ........................................................................................68 8.1 ...................................................................68 8.2 ..................................................................................68 8.3 ..............................................................................................72 8.4 .......................................................................................73 8.5 .......................................................................................................77 8.6 .......................................................................................................80 8.7 ...............................................................................................81 8.8 ......................................................................................................82 8.9 ......................................................................................................82

9 ........................................................................85 9.1 .......................................................................85 9.2 ..........................................................85 9.3 ......................................................................................86 9.4 ..................................................................................87 9.5 ..............................................................................................88 9.6 ..............................................................................88

10 ..........................................................................................90

v

AAC Alternate AC Source

AC Alternating Current

AEC Atomic Energy Council

AFS Auxiliary Feedwater System

ALARA As Low As is Reasonably Achievable

AMSAC ATWS Mitigation System Actuation Circuitry ATWS

ANC Advanced Nodal Code

ANS American Nuclear Society

ANSI American National Standard Institute

AOR Analysis of Record

ART Adjusted Reference Temperature

ARV Atmospheric Relief Valve

ASD After Shutdown

ASME American Society of Mechanical Engineers

ASTM American Society for Testing and Materials

ATWS Anticipated Transient Without Scram

AVB anti-vibration bar

B&PV Boiler and Pressure Vessel

BEF Best-Estimated Flow

BHP Brake Horsepower

BIT Boron Injection Tank

BOP Balance-of-Plant

BTRS Boron Thermal Regeneration System

C&FS Condensate and Feedwater System

CCW Component Cooling Water

CDV Condenser Dump Valve

CF Chemistry Factor

CFR Code of Federal Regulations

CLTP Current Licensed Thermal Power

COPS Cold Overpressure Protection System

CRDM Control Rod Drive Mechanism

CSS Containment Spray System

CST Condensate Storage Tank

CVCS Chemical and Volume Control System

CW Circulating Water

DBA Design Basis Accident

DC Direct Current

DNBR Departure from Nucleate Boiling Ratio

DRLL Dropped Rod Limit Line

ECCS Emergency Core Cooling System

EDG Emergency Diesel Generator

EFPY Effective Full-Power Year

EHC Electro-hydraulic Control

vi

EOL End of Life

EPRI Electric Power Research Institute

EQ Environmental Qualification

ERG Emergency Response Guideline

ESDR Engineered Safeguards Design Rating

ESF Engineered Safety Feature

degree Fahrenheit

FAC Flow Accelerated Corrosion

FWLB Feedwater Line Break

FF Fluence Factor

FQ Peaking Factor

FSAR Final Safety Analysis Report

FH Enthalpy Rise Factor

GL Generic Letter

gpm gallons per minute /

HEI Heat Exchanger Institute

HELB High Energy Line Break

HFF Hydraulic Forcing Function

HFP Hot Full-Power

HI Hydraulics Institute

hp horsepower

HP High Pressure

HVAC Heating, Ventilating and Air Conditioning

HZP Hot Zero-Power

IASCC Irradiation Assisted Stress Corrosion Cracking

IEEE Institute of Electrical and Electronics Engineers

IFM Intermediate Flow Mixer

IN Information Notice

INER Institute of Nuclear Energy Research

IPBD Isolated Phase Bus Duct

lbm pound(s) mass -

LOCA Loss-of-Coolant Accident

LONF Loss of Normal Feedwater

LOOP Loss of Offsite Power

MCC Motor Control Center

MCO Moisture Carryover

MDF Mechanical Design Flow

MELB Moderate Energy Line Break

Mlbm Million pounds

MOV Motor-Operated Valve

MSIV Main Steam Isolation Valve

MSLB Main Steam Line Break

MSR Moisture Separator and Reheater

MSS Main Steam System

MTC Moderator Temperature Coefficient

MUR-PU Measurement Uncertainity Recapture Power Uprate ()

MVA Million Volt Amps

vii

MVAR Mega Volt Amps - Reactive

MWe Megawatts - electric

MWt Megawatts - thermal

NA Not Applicable (N/A)

NEMA National Electrical Manufacturers Association

NPSH Net Positive Suction Head

NRC Nuclear Regulatory Commission

NRS Narrow Range Span

NSSS Nuclear Steam Supply System

ODSCC Outside Diameter Stress Corrosion Cracking

OPT Overpower delta-T T

OTT Overtemperature delta-T T

PCWG Performance Capability Working Group

PEPSETM

Performance Evaluation of Power System Efficiencies

(Computer Program)

PORV Power-Operated Relief Valve

ppm part per million

PRT Pressurizer Relief Tank

Psteam Secondary Side Steam Pressure

psi pounds per square inch /

psia pounds per square inch absolute /()

psig pounds per square inch gauge /()

P-T Pressure-Temperature -

PTS Pressurized Thermal Shock

PU Power Uprate

PWR Pressurized Water Reactor

PWSCC Primary Water Stress Corrosion Cracking

RAOC Relaxed Axial Offset Control

RCCA Rod Cluster Control Assembly

RCL Reactor Coolant Loop

RCP Reactor Coolant Pump

RCS Reactor Coolant System

RHR Residual Heat Removal

RHRS Residual Heat Removal System

RIS Regulatory Issue Summary

rpm revolution(s) per minute

RPV Reactor Pressure Vessel

RSAC Reload Safety Analysis Checklist

RSE Reload Safety Evaluation

RTD Resistance Temperature Detector

RTDP Revised Thermal Design Procedure

RTNDT Reference Temperature (nil-ductility transition) ()

RTPTS Reference Temperature (pressurized thermal shock) ()

RTS Reactor Trip System

RTSR Reload Transition Safety Report

RWAP Rod Withdrawal at Power

RWST Refueling Water Storage Tank

viii

SAR Safety Analysis Report

SDS Steam Dump System

SER Safety Evaluation Report

SFP Spent Fuel Pool

SFPCCS Spent Fuel Pool Cooling and Cleanup System

SGBS Steam Generator Blowdown System

SGFP Steam Generator Feed Pump

SGTP Steam Generator Tube Plugging

SGTR Steam Generator Tube Rupture

SIS Safety Injection System

SLB Steam Line Break

SRP Standard Review Plan

SSCs Structures, Systems, and Components

SSE Safe Shutdown Earthquake

STDP Standard Thermal Design Procedure

T Temperature

Tavg average temperature

TBCCW Turbine Building Closed Cooling Water

Tcold Cold Leg Temperature

TDF Thermal Design Flow

TFW Feedwater Temperature

T/H Thermal-Hydraulic

Thot Hot Leg Temperature

Tsat saturation temperature

Tsteam Secondary Side Steam Temperature

UFM Ultrasonic Flow Meter

USE Upper-Shelf Energy

VCT Volume Control Tank

WCAP Westinghouse Commercial Atomic Power

RTNDT change in reference temperature (nil-ductility

transition)

1

1

1.1

(MUR-PU)

(LOCA)

(ECCS)102%

2%

(1-1)(1-2)

(UFM)2%

0.3 %UFM

101.7% (102 % - 0.3 % = 101.7 %)

2

1.7%

9710(USNRC)

400.4%1.7%

(96)

1.2

97219314MUR-PU

MS-MUR-SAR-00 0(NSSS)

(WCAP-16744-P Rev.1)(BOP)

(Evaluation No.2008-04562 Rev.0)

97318

7481

(Safety Evaluation Report, SER)

1.69%

3

1.3 1.69%

2775

MWt2822 MWt47 MWt1.69%

Cameron/CaldonLEFM CheckPlusTM

(LEFMTM)

LEFMTMAlden

(Commissioning Test)LEFMTM

9717

LEFMTM

0.31%(1-3)

1.69%

(2250 psia)

(621.5 )RCS

RCS

4

1.4

10 CFR 50 Appendix K (Emergency Core

Cooling System Evaluation Models) Regulatory Guide 1.49

(Power Levels of Nuclear Power Plants)ECCS

2%102%

102%

200010 CFR 50 Appendix K

(LOCA)2%

2%

Appendix K

LOCAECCS

(Design Change Request, DCR)

5

2002

RIS 2002-03Guidance on the Content of Measurement

Uncertainty Recapture Power Uprate Applications

1.5

9723

(2%)(1.7%)

LEFMTM

0.31%

1.69%

1.69%

1FSAR

2FSAR3

(4)2%1.7%

6

1.69%(5)

(6)

2,822

MWtDCR

FSAR

1.6

1-1 USNRC 10 CFR 50.46 "Acceptance criteria for ECCS for

light-water nuclear power reactor".

1-2 USNRC 10CFR 50, Appendix K "ECCS evaluation models".

1-3 Caldon Ultrasonics, Engineering Report: ER-672 Rev.0,

Uncertainty Analysis for Thermal Power Determination at

Maanshan NPS Unit 2 Using the LEFM CheckPlus, June 2008.

7

2 NSSS

(45)

NSSS

2.1 NSSS

2.1.1

NSSSPerformance

Capability Working GroupPCWG

2.1.2

NSSSNSSSPlus

First Principles

2.1.3

NSSS

NSSS

8

2.1.4

MUR101.7102PCWG

MS-MUR-SAR-001.112

010WCAP-16744-P Rev 12.1-1

MS-MUR-SAR-001.112

2

PCWG

(12)

6.3

2.2 RCS

MUR2RCS

Best-Estimated Flow, BEFThermal Design

Flow, TDFMechanical Design Flow, MDF

20

9

10Thermal Design Flow

NSSSPlus

MS-MUR-SAR-00 2.510

0

RCS

92,600

gpm/MUR292,600 gpm/

106,900 gpm/MUR

2106,900 gpm/

MUR2TDFMDF

2.3

NSSSRCS

10

101.7

101.69 WCAP-16744-P

Rev 1.12.1-2101.69PCWG

WCAP-16744-P Rev 1.1

MS-MUR-SAR-01

11

3

3.1 NSSS

3.1.1

NSSS2787 MWt

RCS588.5440

10

1.7

MS-MUR-SAR-00

3.1WCAP-16744-P Rev. 13.1-151

(normal conditions)2(upset conditions)

3(emergency conditions) 4(faulted

conditions)5(test conditions)

3.1.2

RCS

ThotTcoldTsteamPsteam

TFW1.7

1.7

12

1314

Vantage+

MUR2.0

WCAP-16744-P Rev. 13.1-2

MUR2.0

10

0

WCAP-16744-P Rev. 13.1-2MUR2.0

:

(1)MUR2.0Thot

1.6

MUR2.0Thot

(2)MUR2.0Tcold1.4

2.9(1)MUR2.0

Tcold

(3)MUR2.0TsteamPsteam1.9

13

15 psi5.644 psiTsteamPsteam

----

Tsteam5.6

Tsteam

NSSSWCAP-16744-P Rev. 1Figures

3.1-13.1-33.1-53.1-73.1-93.1-113.1-133.1-15

3.1-16

(4)MUR2.0NSSS

56 MWtRCS56 MWtNSSS

(5)MUR2.0RCS

5,000 gpmMUR2.0RCS

5,000 gpmRCSTsteam

Psteam

(1)-(4)

(6)MUR2.0

2.63TFW2.6

TFW

WCAP-16744-P Rev. 1Figures 3.1-23.1-43.1-6

14

3.1-83.1-103.1-123.1-143.1-173.1-183.1-19

3

NSSSRCS

MURMUR

40

WCAP-16744-P Rev. 1 3.1-1Reactor

Coolant System Cold Over-pressurizationMUR

FSARFSAR

FSAR

1989MUR

FSAR

3.1.3

3.1.2 MUR 2

Tsteam TFW

5 NSSS

15

3.2

RCS Class 1 NSSS

40

3.2.1

MUR

102 PCWG

PCWG

3.2.2

Tcold

RCS

MUR

Tcold 560 102

RCS 554.1 MUR

2

MUR 2

16

3.2.3

RCS Tcold

MUR 2

MUR 2 MUR

1.7

3.3

(1)MUR 2 Tsteam TFW

5

NSSS

(2)RCS

Tcold MUR 2

MUR 2

MUR 1.7

(3) FSAR Reactor Coolant System

Cold Over-pressurization

(4) 101.7

101.69

WCAP-16744-P Rev 1.1 MS-MUR-SAR-01

17

4

4.1

4.1.1

RCS

(AOR)92,600 gpmRCS

960 gpm700 gpm

MUR1.7%

(BEF100,000 gpm)960 gpmMUR1.7%

RCS

MUR1.7%

4.1.2 NSSS

NSSS

MUR1.7%RCSpsi

(CVCS)(2165 psi)

18

RCS

1.7%RCSTcold

CVCSMUR

RHRCOOL5

2%RHRNSCW

90(32.2 )RHR2%

MUR1.7%

32.2

4.2 /

BOP

NSSS/BOP

MS-MUR-SAR-00MUR1.7%

10%923 psia

84.0%85%

19

0%943

psia85.8%

MS-MUR-SAR-004.3MUR1.7%

4.3

4.3MUR

563.4 psig560.5 psig0.5

NPSH ratio10.4810.02ANSI/HI

2.0

Low suction pressure alarm 145 psig

MS-MUR-SAR-00MUR

HEIHEI

MUR

HEI

10 ft/secRecommendation

RegulationMUR

2%

20

NDE

NDE

NDE

(List of Commitments)

MS-MUR-SAR-00

NPSH

MUR

NPSH Ratio10.510.0HEI2.0Required

Pump SpeedBHP84%49%

99%101%

MURTR2.7G

Evaluation of the Power Train Pumps Non-Safety Related Client

Comment IssueSee Task Report 12A

and 12B for Technical Specification impacts associated with the

Condensate and Feedwater Systems.See Task Report 12A and

12B for FSAR impacts associated with the Condensate and

Feedwater Systems.Technical SpecificationFSAR

Task Report 12A and 12BTR2.7MTR2.7E

21

Technical SpecificationFSAR

923 psia

WCAP-16744-P Rev.1920psia

WCAP-16744-P Rev.1102%

10%964 psia920

psia101.7%

10%964 psia923 psia

MUR1.7%/

(1)

(2) HEI

NDE

(3)Technical SpecificationFSAR

22

4.3

NSSS

P-8

(1)MS-MUR-SAR-00 102%

OTT RTS

OTT K1 1.45 1.49

WCAP-16744-P K1 Sargent & Lundy K1

K6

MUR-PU Core Thermal

Limit OTT OPT

Core Thermal Limit(k1k3k4k6

) Non-LOCA

Condition II OTT

(a)Uncontrolled RCCA bank Withdrawal at

Power (b)Loss of External Load/Turbine Trip (c)RCS

Depressurization OPTRupture of

Main Steam Line at Power

(2)P-8MUR1.7%

23

31.9% WCAP-16744-P

31.2%

16 6

10 964 psia 12.3

Mlbm/hr 89.4 33.9%

MUR 1.7 10

923 psia 12.53 Mlbm/hr

33.9%923/96412.3/12.53=31.9%

WCAP-16744-P 31.2% 2%

31.6% MS-MUR-SAR-00 WCAP-16744-P Rev.1

MS-MUR-SAR-01 WCAP-16744-P Rev.1.1

MUR 1.7%

24

5

5.1

RPV

LOCA

RCS MUR

ASME B&PV

1

MUR 1.7MS-MUR-SAR-00 5.1

Instrumentation Tubes

ASME

1.7% MUR

ASME BPV

5.2

MUR

(1)

25

10CFR 50 Appendix H (Beltline)

(2) RG 1.99

(P-T Curve) (3) 10CFR 50.61 RTPTS

(4)EOL

Upper Shelf Energy, USERTNDT

(5) ASTM E900

32 (Effective Full Power

Year, EFPY)

P-T CurveERG PTS USE

36 EFPY

(Capacity Factor) 0.9

36 EFPY

36 EFPY MUR 2

ERG

36 EFPY ARTRTPTSUSE

36 EFPY -

26

-

MUR 2 MUR 1.7

5.3

1

2

Flow-induced Vibration3

4 MUR

MUR

RIPD

MUR 1.7

MUR1.7

MUR 1.7

27

0.3

MUR 1.7

5.4

MUR

Reactor Coolant Loop, RCL

(1) RCL (2)Nozzle(3)

(4)(5)RCL

(6)Class I MUR

1.7

ASME

BPV

MSLB

FWLB LOCA

MUR

(flow accelerated corrosion, FAC)

28

MS1EOC-17

MS2EOC-16 MUR

FAC FAC

MUR1.7

5.5

MUR

40

MUR 1.7

5.6

5.6.1

(RCL) Model 93A-1

7000 hp

RCP

ASME B&PV

29

MUR 1.7

2250 psia RCS

555.0RCP

1.0

MUR

1.7

5.6.2

NSSS 102 %

1hot-loop

2cold-loop3

4

7176 bhp 9370 bhp

7000 hp 8750

hp 2.5 7.1

MUR 1.7

30

5.7

5.7.1

Model F MUR

1.7

MUR 1.7

5.7.2

MUR 2 U

0 10

31

chamber head

0.070

MUR 2

MUR 1.7

MUR 2MUR

1.7

5.7.3

MUR

ASME B&PV Code

0 10

10 MUR 2

1,480 psi

1,730 psi ASME B&PV

1,600 psi 1,760 psi

MUR 2

ASME B&PV MUR 2

32

MUR 1.7

5.7.4

Ribbed Rolled

Collar-cable

Stabilizer

ASME

B&PV MUR

MUR 1.7

5.7.5

33

MUR

5.7.6 U

U

fluid-elastic stabilityturbulence

MURU

MUR 2U

0.500 0.523

0.521 1.0 U

0.3 mils 2 mils

MUR 2 U

9.2 8.6

NSSS

WCAP-16744-P

U MUR 2

2 U

MUR 1.7 U

MUR 2 MUR 1.7

34

U

5.7.7 U

MUR U

Model F U Alloy 600 TT

Alloy 600 MAmill-annealed

AVB EOC-16

U

U

PWSCC ODSCCAVB

MUR

U

U MUR 1.7

35

5.7.8

EPRI

Guidelines

MUR

MUR 1.7

5.8

RCSRCS

ThotTcold

12

NSSS

3

MUR NSSS

36

/

MUR 1.7 ASME

MUR 1.7

5.9

MUR

ASME

MUR 1.7

MUR

MUR 1.7

5.10

1.7 Vantage+

123

45

37

MUR 2

2MUR

2MUR 1.7

38

6 MUR NSSS 1LOCA

2LOCA 3 LOCA 4

5LOCA 6

7

6.1

LOCA

LOCA

LOCA

MUR Tcold LOCA

TcoldLOCA

LOCA

LOCA

LOCALOCA

MUR 1.7

LOCA RCS LOCA

LOCA LOCA MUR 1.7

39

6.2

Vantage+

2

MUR

2

MUR 1.7

6.3

MUR

(Safety

Limits)FSAR

Non-LOCA

MUR 2

2,843MWt MUR 2( 1.7)

Non-LOCA

(DNBR) Non-LOCA (1)

40

RTDP WRB-2 (2) WRB-2

STDP W-3

RTDP RTDP

DNBDNBRDNBR

DNBR Condition I

Condition II 95 95

Non-LOCA THINC-IV WRB-2 DNB

DNBR Vantage+ DNBR

1.23 1.22 MUR

VIPRE-W THINC-IV WRB-2 DNB

DNBR 6-1

MUR DNBR

DNB Non-LOCA

DNBR

DNBR 1.32

MUR 2

MUR2Non-LOCAMS-MUR-SAR-00

6.4

41

MUR Non-LOCA

6.4 RTDP

RTDP DNBR RTDP

0.3 MUR

1.7 RCS 430 psi

DNB

FH MUR 2

FHRTDP FH RTDP 1.62 1.68

DNBR 1.55 chopped

cosine OTT

RCP chopped

cosine

DNB

FQRCCA

FQ 2.42 RCP 2.50

42

Non-LOCA

MS-MUR-SAR-00 6.4

RCCA

2.4

Non-LOCA

Non-LOCA

MS-MUR-SAR 6.5 OTT OPT

MUR

OTT OPT

Non-LOCAOTT

1 RCCA

43

2

3RCS

OPT

1

(1)WCAP-16744-P Rev.1 6.3

MS-MUR-SAR-00 6.3

( BWR )

WCAP-16744-P BWR

MS-MUR-SAR-00

MS-MUR-SAR-00 6.3.29 WCAP-16744-P

6.6

(2) Non-LOCA

THINC-IV WRB-2 DNB DNBR MUR

VIPRE-W THINC-IV WRB-2 DNB

DNBR 6-1

(3) WCAP-16744-P 2.1-1 6.3-4

0% 10%

44

(4)

6.3

MUR(WCAP-16744-P)

(a) 2% 2,775 MWt

2,831 MWt(b)(Thot)

(Tcold) 555.5 554.1(Tavg)

588.5 587.8(c) 440 442.6

12.29 Mlbm/hr 12.57 Mlbm/hr

45

935 psia 920 psia (PCWG )(d) DNBR

(SAL DNBR=1.32) MURPU PCWG Core Limit

Lines(e) FH 1.65 1.62 (2% reduction)(f)OT

T OPT (g)

(h)Feedwater System Malfunction

SG Common Mode Failure (i)

( LOOPLONF FWLB)

MURPU FSAR

(ITS)

Core Thermal Power =2,822 MWt

FH =1.62

Core Limits and OTT/OPT Setpoints

36 EFPY P-T Curves

LTOPS/COMS PORVs Setpoint

ATWS MTC Reload Design Criteria

Motor Driven AFW Flow (FSAR Table 10.4-14)

(a)(LOOP):380 GPM

3

(b)(LONF):500 gpm 3

46

(c)(FWLB):330 gpm 2

Applicable Power for Inoperable SGSVs

Design Basis for RHR Cooldown (FSAR 5.4.7.1)

No Re-insertion of OFA Fuel

FSAR Chapter 15

(5) MUR-PU Non-LOCA

WCAP-16744-P Table 6.3-5 MUR-PU

Reload Transition Safety Report (RTSR) for use of

Vantage+ at Maanshan Units 1 and 2 (pre-MUR-PU) Table 7.3.0-3

MUR-PU

(a)Steam System Piping Failure:

Hot Zero Power MUR-PU

WCAP-16744-P Hot Zero Power

47

Feedwater

Malfunction Hot Zero Power

SG Common Mode Failure

(b)Loss of Load/Turbine Trip: RTSR(pre-MUR-PU)

pressure case DNB case moderator

temperature coefficient(MTC)pressure case MTC

+7 pcm/F DNB case MTC 0 pcm/F

MTC 0 pcm/F 50%

+7 pcm/F RTSR pressure case

+7 pcm/F WCAP-16744-P

pressure case DNB case MTC

0 pcm/F

part power

part power MTC

Loss of Load/Turbine Trip

MTC 0 pcm/F part power

48

MTC

(c) (Locked Rotor): RTSR

(pre-MUR-PU)pressure case DNB case

WCAP-16744-P

pressure case

(2%)

DNB case

WCAP-16744-P

2%

2843MWt

2843MWt DNB case

pressure case DNB case

(d)(Inadvertent

Opening of a Pressurizer Safety or Relief Valve):

MTC 0

Inadvertent Opening of a Pressurizer Safety or Relief Valve

MTC 0

pcm/F part power MTC

49

MTC part

power

(e)(Rod Withdrawal at Power): MTC

part power MTC

MTC

(6) minimum DNBR

1.35 DNBR safety analysis limit 1.32

MUR-PU

RTSR Relaxed Axial Offset

Control (RAOC)

minimum DNBR

RTSR RAOC MUR-PU

Minimum DNBR 1.64 1.45 1.357

LOFTRAN RW3

RTSR RW3

50

DNBR safety analysis limitRTSR

Minimum DNBR RAOC

MUR-PU RAOC MUR-PU DNBR safety

analysis limit 1.32 MUR-PU PCWG

Core Limit Lines MUR-PU RW3 RAOC

MUR-PU RW3 OPTOAX

OPTOAXDNB core limit linesOTT trip

line OTT trip line OPT trip line RW3

RW3 core limit

RW3PLO RW3PLL

RW3PLO RW3PLL

DNBR RAOC

MUR-PU

MUR-PU Minimum DNBR

MUR-PU Minimum DNBR

RAOC

MUR-PU MUR-PU

MUR-PUMinimum DNBR RAOC

51

RAOC MUR-PU

LOFTRAN RW3 Minimum DNBR

(7)

loss of non-emergency AC power to the

plant auxiliariesloss of normal feedwater flow

4 Loss of Normal Feedwater Event Loss of

Non-Emergency AC Power to the Plant Auxiliaries

/

Loss of Normal Feedwater

52

Event Condition IV

WCAP-16744-P Rev.1

WCAP-16744-P Rev.1.1

(8) Loss of Non-Emergency AC Power to the Plant

Auxiliaries Loss of Normal Feedwater Event

WCAP-16744-P Rev.1.1

WCAP-16744-P Rev.1

WCAP-16744-P Rev.1.1 WCAP-16744-P Rev.1.1

(9) RSAC Rod Withdrawal Event DNB

limit MUR-PU Pre-MUR-PU

DNBR marginrod bow penalty MUR-PU

Pre-MUR-PU

53

(10)Automatic Rod Control System

Tavg lead/lag 80 /10

40 /10 OTT OPT lead/lag

OTT OPT

RCS Tavg

OTT OPT

OPT OTT

Non-LOCA

(11) OTT OPT

3

OTT OPT 3

Non-LOCA

3To OPTOAX K1

3 OTT OPT

54

(12)

...

Thermal Design Flow

Minimum Measured Flow

Thermal Design Flow Minimum Measured Flow

(13)MS-MRU-SAR-006.3.7

(14) WCAP-16744-P 6.3.8-1

1,318 psia 6.3.8.1

55

110% 1,318.5 psia

0.5 psia

0.5 psia

NSSS

(Thermal Design Flow)

MSSV

MSSV tolerance

WCAP-16744-P 6.3.8-1

(15) MS-MUR-SAR-00 6.3.30

56

(a) ATWS MTC -8

pcm/ MTC -5 pcm/

RCS 330 psi

RCS MTC

technical basis RCS MTC

(b)ATWS

Doppler Coefficient Main steam safety valve and

PORV response and capacity ATWS

ATWS

(c)MS-MUR-SAR-00 6.3.30 10%

10%

10%

ATWS

(SGTP)

Loss of Load Loss of Normal Feedwater ATWS

SGTPL 0%

57

(16) Locked Rotor

WCAP-16744-P 3,200 psig

RCS

pressure < 110% design pressure

General Design Criterion 31 SRP

faulted

condition

RCS pressure < 110% design pressure4

RCS pressure < 110% design

3 2 RCS pressure <

110% design pressure

faulted condition

6.4

6.4.1

2

MUR

2

MURFSAR6

58

6.4.2

FSAR

6.5

6.5.1

WCAP-8264-P-A Rev.1FSAR

NSSS2,968

MWt2,775 MWtRCP(10

MWt)4.5%(ESDR)

2%MUR-PU 1.7%PCWGRCP

12 MWtNSSS2,971 MWt2,971 MWt

2,968 MWt3 MWt (0.1%)Long-Term LOCA

Mass and Energy Release Analysis

MUR-PU 1.7%Tcold/Thot(AOR)(MUR-PU

554.1F/621.5F vs. AOR 558.8F/627.2F)

MUR

59

6.5.2

Cavity

65.7 in2100 in

2150 in

2

10

FSAR

MUR

6.6 (STGR)

Vantage+

RTSR2MUR

1.7

6.7

FSAR15:

60

2,900 MWt

2,775 MWtMUR1.72,822 MWt

MUR1.7

MUR

MUR

MUR1.7

61

6.8

(1) LOCA RCS LOCA

LOCA LOCA MUR 1.7

(2)

MUR 1.7

(3)WCAP-16744-P Rev1 Non-LOCA (6.3 )

MS-MUR-SAR-00 6.3

(4) MUR VIPRE-W THINC-IV

WRB-2 DNB DNBR

(5)

0% 10%

62

(6) FSAR

Chapter 15

(7) Non-LOCA

WCAP-16744-P Table 6.3-5

MUR-PUReload Transition

Safety Report (RTSR) for use of Vantage+ at Maanshan Units 1

and 2 (pre-MUR-PU) Table 7.3.0-3

(8) minimum DNBR

1.35 DNBR safety analysis limit 1.32

LOFTRAN

RW3 Minimum DNBR

(9)

63

(10)Automatic Rod Control System

Non-LOCA

(11) OTT OPT

(12) 1,318 psia

1,318.5 psia. 0.5 psia

0.5 psia

(13)

MUR

(14) FSAR

MUR

64

(15) MUR 1.7

(16)

MUR 1.7

(17)

WCAP-16744-P Rev.1

WCAP-16744-P Rev.1.1

(18) 101.7

101.69

WCAP-16744-P Rev.1.1

MS-MUR-SAR-01

6.9

6-1 NRD-SER-97-03,

65

7

7.1

MS-MUR-SRA 7.1 7.1

The data presented in WCAP-9620 are based on a set of

assumptions and calculation tools that are nearly 30 years old.

Although the following list does not summarize all of the key

assumptions that were made to support the WCAP-9620

documentation, several important changes have occurred that

are highlighted below.

Fuel Product Line Changes

Axial blankets regions with annular pellets

Longer fuel cycle lengths

shorter bottom and top nozzle designs

Transition from out-in to low leakage loading patterns

(L3P)

Plant Modifications

66

Upratings

Other programs that reflect changing PCWG parameters for

a plant

Methodology Updates

Current nuclear cross-section data

P5 versus P1 expansion of the scattering cross-sections

S16 versus S8 angular quadrature

No gap assumed between the fuel rod and bottom nozzle

From this list of differences, the change from out-in to L3P

is the most significant. The out-in fuel management strategy

that was assumed in WCAP-9620 places fresh fuel on the periphery

and these assemblies are moved towards the center of the core

during subsequent reload fuel cycles. However, L3P reload

designs intentionally place fresh fuel in the center of the core

burned fuel assemblies on the core periphery. Out-in core

loading patterns have relatively high peripheral power and

correspondingly low power in the central region of the core.

In contrast, L3P designs have low power on the core periphery

and high power in the center of the core. Hence, transitioning

67

from out-in to L3P core designs makes the WCAP-9620 results

conservative for the baffle and core barrel regions, but

non-conservative for the core plate structures since more power

is now being produced in the central portion of the core

7.2

2008

MUR 1.7%

7.3

MUR 1.7%MS-MUR-SAR-00

68

8 8.1

MUR

MUR 1.7%

8.2

(1) MUR 1.7%

BOP

()

18%

ABB

5% MUR

R2.7AEvaluation of the Turbine

Generator for MUR Power Uprate Non-Safety Related Client

69

Comment Issue R2.7A FSAR

Sections 3.5, 10.1, and 10.2 were reviewed. In Section 10.2,

Fig. 10.1-1 should be replaced with a heat balance which

reflects MUR-PU. Section 10.2.2.2.7 should be revised to

reflect the differences between the Unit 1 and Unit 2 generator

operating hydrogen pressures.

FSAR

R2.7A

(2) MUR

1.7%

MUR

1.7% 6.26109Btu/hr

6.38109Btu/hr steam dump 32%

8.82109Btu/hr

6.267109 BTU/hr/shell (FSAR Table 10.4-1)2shell

12.5109Btu/hr

(3) 100% 1.7%MUR

70

()

MUR NPSH Ratio (~1.15) HEI1.1

TR2.7GEvaluation

of the Power Train Pumps Non-Safety Related Client Comment

Issue 4.2 (4)

(4)

8.2.2

(

4 25%)

MUR 0.3

TR2.7B

Main Condenser Non-Safety Related Client Comment Issue

TR2.7C Evaluation of the Circulating Water and Condenser

Evacuation System Non-Safety Related Client Comment Issue

TR2.7C FSAR The current text of

UFSAR Section 10.4 was reviewed and changes are required in the

text related to the main condensers full load conditions which

will increase after MUR uprate. The total turbine exhaust steam,

71

total condensate outflow, and the total condenser duty need to

be updated to reflect the MUR uprate conditions.TR2.7B

7.1.2 The severity factor (tube vibration) could not

be calculated because the tube exhaust flange area and tube

support span information is not available. See Open items 9.1

and 9.2. FSAR

tube exhaust flange

area and tube support span informationS&L

Open items 9.1 and 9.2 TR2.7B

TR2.7C

MUR 1.7%

(1) FSAR

(2) R2.7ATR2.7B TR2.7C

72

8.3

(1)

T

hAT(h A )

MUR

Qmur/Q=Tmur/T

1.7Tmur/T=1.017Tmur-To=1.017(T-To) To

Tmur=1.017T-0.017To1.017T=1.017103 =104.7

105

103MUR 1.7

105

(2)MUR 1.7%

TBCCW 8.3%

TBCCW

73

( Generator Stator CoolerAir Compressor Aftercooler

Main Turbine Lube Oil Cooler 15 ) 68.5106 BTU/hr

TBCCW 76.32106 BTU/hr 10%

MUR ( Air Compressor

Aftercooler) 1.7%

8.3%

(3) MUR

1.7% SFP

0.4 0.8

Scenario 1 MUR 123.34122.91

= 0.4Scenario 3 MUR

146.4145.59 = 0.8

MUR 1.7%

8.4

Engineered Safety Feature, ESF

74

ESF Containment

Containment Heat Removal System

Containment Isolation System

Containment Combustible Gas Control System

Fission Product Removal and Control System

Habitability SystemEmergency Core

Cooling System, ECCSAuxiliary Feedwater

System MUR 1.7% ESF

MS-MUR-SAR-00 4.2.3.4

MUR 1.7

MUR

ASME B&PV Code

Section III Articles NC-2l60 NC-3l20

FSAR

(Mass and Energy Release Analyses For Postulated

75

Loss-of-Coolant Accidents)MUR

MS-MUR-SAR-00LOCA

NSSS2,971 MWt

1NSSS

2,968 MWt1LOCA

NSSS2843 MWtNRC 10 CFR

50 Appendix K0.31%

2,968 MWt1

TcoldThot (AOR)

MUR 1.7FSAR

MUR

MURFSAR

MUR

1.7 MUR

MUR

MUR1.7

76

1.69 MUR

MUR

LOCAMUR

MUR

LOCAECCS10 CFR 50 Appendix K

2MUR1.7

MURLOCA

MUR

MURLOCA

102MUR1.7

MUR

1.7 MUR

LOCA

77

1.7 MURMUR

1.7% MUR

8.5

FSAR

(Reactor Trip System, RTS)

Engineering Safety Feature Actuation System,

ESFAS

(Safety-Related Display Instrumentation)

FSAR

(ATWS (Anticipated Transient Without Scram) Mitigation

System Actuation Circuitry, AMSAC)

RTS

MUR 1.7

MUR OTT OP

78

T OTT OP

T

OTT OPT

Non-LOCA

DNB 1.7

FSAR

LOCA ECCS

102 CLTP MUR

1.7 ESFAS

ESF ESFAS MUR 1.7

MUR 1.7

MUR 1.7

MUR

MUR 1.7

RHR

79

MUR

1.7PORV

--

MUR LTOP PORV

MUR

Automatic Rod Control System

TavgLead/Lag

Tavg

Tavg

MUR

2

90MUR

1.7(Cv1,250

gpm/psi)MUR1.72

(Cv 935 gpm/psi)

AMSAC MUR

1.7 AMSAC

80

1.7% MUR

8.6

345 kV 161 kV

MUR 1.7

MUR 1.7

MUR 1.7

MUR

1.7

81

EDG ESF

ESF 102 CLTPMUR

1.7 ESF

EDG MUR 1.7

UFM

MUR 1.7

1.7% MUR

8.7

IPBD

MUR 1.7

1.69

IPBD

IPBD IPBD IPBD

MUR

82

1.7% MUR

8.8

MS-MUR-SAR-00 MUR 1.7%

FAC

MUR 1.7%

8.9

EQ-

EQ Radiation Dose

FSAR Table 3.11-5 b 40 years operation (0.8

plant capacity factor assumed for drywell Zones 1 and 2

doses) FSAR Table 3.11-2 a Includes

40-year normal operation radiation exposure. 0.8 plant

capacity factor Tables

Containment Building DBA Integrated Dose 1.0108 rad

5.0106NEQ EQ

FSAR (Equipment Qualification Report, Rev.

83

3 , Dec. 1988)

EQ 10 CFR50.49 (Environmental Qualification of

Electric Equipment Important to Safety for Nuclear Power Plants)

IEEE 323 (IEEE Standard for Qualifying Class IE Equipment

for Nuclear Power Generating Station, 1983) 10CFR50.49

IEEE 323

10% USNRC IEEE 323

FSAR Table3.11-2Includes

40-year normal operation radiation exposure.

0.8( FSAR Table 3.11-5) Containment

Building DBA Integrated Dose 1.0 ~ 2.0108 rad

( 5.0106

rad) FSAR

( 0.8 0.85)NEQ EQ

FSAR (Equipment Qualification

Report, Rev.3 , Dec.1988)

0.3

84

94 0.3

TR2.7C PEPSETM BOP Heat Balance

MUR

MUR 1.7%

85

9

9.1

2 SCFM 0.1-0.3 SCFM 10 1.7%

0.102-0.306 SCFM

9.2

1.7 2,822MWt

(LRS)

30 (101,127 3,347 )

7 (26,250 /3,347 /)

12%

LRS LRS

25

86

87

91 82

985 96 211 4.67

200 93 30,000

99MUR 1.7

9.3

MUR

105

MUR

1.7%

1.7%

2,775 MWt 1.7%

87

1.7% 5

5 Sv/hr 1.7%

5

MUR 1.7

9.4

MUR

1.7 2

2,775 MWt 1.7%

1.7%

MUR 1.7

88

9.5

1.7% 1.7%

105%

105%

102%101.7%+ 0.3%

FSAR

9.6

89

0.01 1.7%

FSAR 12.212.312.4 1.7%

90

10

(1) FSAR Reactor Coolant System

Cold Over-pressurization

(2) 10%

(3) HEI

NDE

(4) Technical Specification FSAR

(5)

(6) WCAP-16744-P Rev.1.1

(7) FSAR

91

(8) R2.7ATR2.7B TR2.7C

(9)