LICENSEE: Arizona Pubfd S €8rkpany

Palo Verde Nuclear Generating Station, Unit 2

SUMMARY OF THE MAY 24,2000, MEETING TO DISCUSS STEAM GENERATOR REPLACEMENT AND POWER UPRATE ISSUES

On May 24, 2000, the U.S. Nuclear Regulatory Commission's (NRC's) staff, and the Palo Verde Nuclear Generating Station, Unit 2 licensee, Arizona Public Service Company, met in Rockville, Maryland, to discuss steam generator replacement and power uprate issues planned by the licensee for Palo Verde Unit 2. The licensee plans to replace both Unit 2 steam generators during the Fall 2003 refueling outage with generators being fabricated in Milan, Italy, by Ansaldo. The new steam generators have an improved steam dryer design, have 26 percent more heat transfer area, and use Inconel 690 steel for the tubes. Construction and quality assurance activities were discussed during the meeting, as well as the plans to transport the generators through Mexico to the site. A recent example of the licensee's activities in the quality assurance area was the rejection of almost 3000 steam generator tubes because they were manufactured 1.5 millimeters shorter than the specified length.

The licensee is planning to take advantage of the increased steam generator capacity by .requesting NRC approval of a power uprate for Unit 2. The licensing submittals associated with the power uprate proposal would revise the appropriate sections of Chapters 6 and 15 of the Updated Final Safety Analysis Report, and would revise the Technical Specifications. The staff noted that, when using generically approved computer codes to conduct the safety analyses, all conditions placed on the use of these codes should be specifically addressed in the licensee's submittals.

Enclosure 1 is the list of attendees for the meeting, and Enclosure.2 is a copy of the slides presented by the licensee.

It was agreed at the conclusion of the meeting that the staff and the licensee will meet in

approximately 6 months to discuss progress on these issues.

/RA/

Docket No. STN 50-529

Enclosures: 1. List of Meeting Attendees 2. Licensee's Meeting Slides

cc w/encls: See next page

Mel B. Fields, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

DISTRIBUTION: PUBLIC PDIV-2 Reading JZwolinski/SBlack (RidsNrrDIpm) SRichards (RidsNrrDIpmLpdiv) RidsNrrLACJamerson RidsNrrPMMFields RidsOgcRp RidsAcrsAcnwMailCenter KLandis RWessman CLiang Attard JTsao

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NAME M_____:lcc CJamerson f SDembeK

DAjTE •/es- 1..515 k1 DoZ .ŽJ DOCUMENT NAME: G-\PDIV-2\PaloVerde\MtsO5-24-OO.wpd

OFFICIAL RECORD COPY

FACILITY:

SUBJECT:

Aee��i6n N� MLOO�71Aceso Noww ML.. w... 371..

Palo Verde Generating Station, Units 1, 2, and 3

cc:

Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007

Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O. Box 800 Rosemead, CA 91770

Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 40 Buckeye, AZ 85326

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003

Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, AZ 85040

Ms. Angela K. Krainik, Director Regulatory Affairs Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034

Mr. John C. Horne Vice President, Power Generation El Paso Electric Company 2702 N. Third Street, Suite 3040 Phoenix, AZ 85004

Mr. David Summers Public Service Company of New Mexico 414 Silver SW, #1206 Albuquerque, NM 87102

Mr. Jarlath Curran Southern California Edison Company 5000 Pacific Coast Hwy Bldg DIN San Clemente, CA 92672

Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251

Terry Bassham, Esq. General Counsel El Paso Electric Company 123 W. Mills El Paso, TX 79901

Mr. John Schumann Los Angeles Department of Water & Power Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100

Mr. Gregg R. Overbeck Senior Vice President, Nuclear Arizona Public Service Company P. 0. Box 52034 Phoenix, AZ 85072-2034

August 18, 1999

LIST OF ATTENDEES

PALO VERDE NUCLEAR GENERATING STATION, UNIT 2

STEAM GENERATOR REPLACEMENT AND POWER UPRATE ISSUES

NRC/APS

MAY 24, 2000

ARIZONA PUBLIC SERVICE COMPANY

David Mauldin Carl Churchman Paul Clifford Richard Bernier Mohammad Karbassian Kevin Neese Ron Pontes Larry Joy Ted Erikson

WESTINGHOUSE

Bill Gardner Richard Bradshaw

BECHTEL

Eric Ocsterle Andrew Matyas

McGRAW HILL

Elaine Hiruo

NRC

Dick Wessman Mel Fields Chu-yu Liang Steve Dembek Anthony Attard John Tsao

Enclosure 1

Palo Verde Steam Generator Replacement

And Power Uprate Project

Presentation To The

Nuclear Regulatory Commission

May 24, 2000W1

........

m C,

0

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Palo Verde Steam Generator Replacement And Power Uprate. Project

"Project Update

Carl Churchman SGR Project Director

Objectives

* Provide status of SG replacement and power uprate project

+ Discuss oversight activities

* Provide details of project management

+ Discuss recently identified modifications

+ Discuss results of safety analyses

Objectives

* Review installation plan

+ Provide update on licensing activities

* Provide an overview of upcoming activities

* Discuss integrated schedule

Agenda

Introduction Project status & oversight ABBICE transition Safety Analyses Configuration

management

Modifications Installation plan Licensing activities Future activities

Carl Churchman Carl Churchman Rick Bradshaw Paul Clifford Mo Karbassian

Mo Karbassian Ron Pontes Dick Bernier Carl Churchman

RSG Fabrication Status

* Tubing e Fabrication in progress

• Delivery to be in July and September 2000

* Tubesheet#1 e Drilling in progress

- > 75 percent complete

RSG Fabrication Status

* Tubesheet#2 • Stub barrel welded to tubesheet

• Drilling to start mid-June 2000

* Lower and intermediate shells • Fabrication in progress for both SGs

* Eggcrate supports • Fabrication of templates in progress

4-

RSG Fabrication Status

+ Economizer flow distribution plate #1 • Drilling in progress

* Primary channel heads * Support skirts attached • Stainless steel cladding in progress

* Primary nozzles "• Cold leg: stainless steel cladding in progress "* Hot leg: Safe ends attached

RSG Transportation

+ Status of transportation plan

+ Status of permits

* Status of infrastructure improvements

Oversight Activities

* Audited ABB Chattanooga in May 1999 • Seven findings

- Software control, design control, internal audit program, corrective action program

* Source verification performed in February 2000 "* ABB resolved all identified issues and

implemented appropriate corrective actions

"* Audit findings are closed

Oversight Activities

* Audited ABB Windsor in August 1999 Eight findings - Software control/design control - Weakness QA audits/auditor training - Corrective actions

* APS has accepted corrective actions proposed by ABB

+ Implementation of corrective actions was verified during week of May 15, 2000

Oversight Activities

* Audited Ansaldo Milan in June 1999 Wisconsin Public Service Corp. participated

Six findings "o Weak and ineffective corrective action • ~/,

"o Non-compliance ANSI Standard "o Procurement control

"o Compliance with cleaning spec (WPSC) "o Documentation of witness points

Oversight Activities

* Audited Ansaido Genoa in June 1999 Wisconsin Public Service Corp. participated

Two findings "o Procurement control "o Corrective action program

Oversight Activities

+ APS and WPSC have accepted corrective actions proposed by Ansaldo

* Ansaldo implementing corrective actions. to audit findings

+ Ansaldo has appointed a new QA director * Implementation of corrective actions to be

verified in June 2000

Sandvik Oversight Activities

* Ansaldo audited Sandvik in March 2000 with APS in an oversight capacity * Results generally satisfactory with two minor

findings - Document control - Records storage temperature controls

* APS/Ansaldo quality team review scheduled for July/August 2000

Sandvik Oversight Activities

* Short tubes * 2895 tubes fabricated 1.5mm short * Error related to use of incorrect drawing * Tubes to be replaced by Sandvik to meet

specifications

BNFL Acquisition of ABB Nuclear *BNFL/Westinghouse announced the acquisition of ABB's Nuclear Businesses Worldwide on May 2, 2000.

*ABB Nuclear Companies will be integrated into and operated as part of Westinghouse.

* In USA: Westinghouse Electric Company

CE Nuclear Power LLC.

* No changes to the PVNGS RSG Project Team, QA, Technology, or Schedule are anticipated.

*BNFL

Safety Analyses

SUFSAR Chapter 15 Transient Analysis "* CENTS code "• Analytical limits "* Methodology changes "* Sample from uprate submittal

Safety Analyses

*CENTS will replace CESEC-III as the primary tool for Chapter 15 non-LOCA transient analysis.

SCENTS will be used to predict global changes in RCS pressure during the CEA ejection event. STRIKIN-II will continue to be used to predict local conditions (i.e., fuel enthalpy and DNBR).

Safety Analyses

Initial conditions at full power Values Include appropriate uncertainties

Power

Inlet temperature Pressurizer pressure

RCS mass flow rate ?ressurizer level SG level Axial power distribution

MTC Primary to secondary leakage

= 4070 MWt = 548 to 566TF = 2100 to 2325 psia = 95% to 116% of design = 24% to 59% = 4% to 92% NR = -0.20 to +0.20 ASI = -0.20 to -4.0 E-4 delta-rhoIPF = 720 gpd I SG

Safety Analyses SMethodology changes

e The following methodslassumptions changes will be applied to both the current plant configuration (Units 113) and Unit 2 RSG/uprate

- Dose calculations will assume a decontamination factor of 100 (partition factor of 0.01) forthe intact SG /

- Post-trip MSLB will employ a more detailed reactivity calculation, including moderator density feedback in the hot channel

- More realistic IOSGADV+LOP event analyzed separately from limiting AOO with SF (i.e., LOF from SAFDL)

Safety Analyses

SMethodology changes (cont.) - Single RCP sheared shaft with LOP will

assume that, at 60 minutes, the operator either closes the stuck open ADV or reestablishes level in the affected SG

- SGTR+LOP will credit EOP-based isolation of affected SG

- SGTR+LOP+SF will employ calculated flashing (based on local conditions) for leakage into affected SG

Safety Analyses

0 Sample from uprate. submittal • Outline and contents of the safety analysis

portion of the submittal is based on a composite of the PVNGS UFSAR and the Farley uprate submittal

• Inadvertent opening of a SGADV - Identification of causes and event

description - Acceptance criteria

Safety Analyses

SSample from uprate submittal (cont.) • Inadvertent opening of a SGADV (cont.)

- Description of analysis - Input parameters, initial conditions, and

assumptions

- Results - Conclusions

Safety Analyses

Table 7.3.1.4.5.A: Sequence of Events for IOSGADV+LOP Event

Time (sec) Event Value

3876 3990 3876 3990 MVIt M"t MWt MWt

0.00 0.00 Inadvertent opening of SG#1 ADV -- -

0.00 0.00 Core Power (% RTP) 100 100

0.00 0.00 Hot Channel Minimum DNBR 1.72 1.72

147.9 176.5 SG pressure reaches MSIS/Trip setpoint (psia) 850 915

149.1 177.7 Reactor/Turbine trip

Loss of Offsite Power

149.7 178.3 Scram CEAs begin falling _ _ -_

151.2 179.7 Minimum DNBR > SAFDL > SAFDL

153.5 182.1 MSIVs Closed -_ _ _

352.7 329.3 SG#2 MSSV Bank I Open (psia) 1303 1303

Begin Oscillating

463.9 428.3 RCS pressure reaches SIAS setpoint (psia) 1750 1750

919 1005 SG#1 Empties -_

1800 1800 Operators manually close SG#1 ADV .

1800 1800 Operators initiate cooldown (min) 30 30

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Major Activities

SU2R10 (spring 2002) • Remove interfering commodities from

bioshield wall • Polar crane preparations (based on U2R9

inspection) • SG2 auxiliary crane supports • Modify second containment spray pump

impeller

Major Activities

SU2CII (summer 2002 - fall 2003) "• Craft access facility "• Outside lift system

"• Haul route

"* RSG preparations

* U2R11 (fall 2003) "o Bioshield wall modifications "• Replace steam generators

PVNGS - 2Rl I Steam Generator Replacement Outage Summary Schedule

Sep'03 Oct'03 Nov'03 Dec'03 A1262 282931 2 3 4 5 51 I 8 19 7 18l9111121131141151161171181191201211221231241251261271281291301311 1 2 1 3 1 4 1 516 1 7 a8 1911011 2134151617892 21 23124125126127128129130 1 12 3 2 4 51 8 17 9

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STEAM GENERATOR REPLACEMENT LEGEND

5 SIG REPLACEMENT CONTRACTOR PROCESSING, OFFICE & BREAK AREA FACILITY (EXISTING) SIG REPLACEMENT CONTRACTOR WAREHOUSE FACILITY (EXISTING)

Q REPLACEMENT SIG OFFLOADISTORAGE LOCATION

CONTAINMENT ACCESS, CRAFT ASSEMBLY AREA & POD/OUTAGE MANAGEMENT FACILITY

S OLD SIG STORAGE LOCATION

SIG CONTRACTOR SECURITY ACCESS V FACILITY

SEMERGENCY PERSONNEL HATCH) 100

® FAB SHOP, WELD TEST SHOP & MOCK-UP FACILITY (EXISTING)

4 LAYDOWN AREA

@CONTRACTOR PARKING AREA

DECONTAMINATION FACILITY / Im '00

NOTES:

1. SECURITY GATE TO BE REWORKED TO FACILITATE SG MOVEMENT INTO PROTECTED AREA.

2. CONTRACTOR TRUCK/SMALL EQUIPMENT ACCESS TO PROTECTED AREA

May 9,2000

STEAM GENERATOR REPLACEMENT

SITE FACILITIES

STEAM GENERATOR REPLACE ENT LEGEND

EQUIP. HATCHY TRAILER. SADDLES. & SG '

AKPRUNWAYO f I., 2'-7 3/8m !.JACK POD. TYP.

1-- /2.-- I/. -'-7 1/___*L.-8-7-1/2;,

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JBUC SERVICE COMPANY GENERAL ANGSMENT HANDLI]NG SGs % o

NERATOR REPLACEMENT OUTSIDE CONTAINMENT __98_90 ______ VERDE NUCLEAR 2. SKETCH 05.04-4 |___ __ __ ___

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Licensing Activities

+ APS had planned a two phase submittal in August 2000 and February 2001

* APS will combine into one submittal in June 2001

* Request approval in June 2002 * U2C12 fuel design to commence in

September 2002 based on SER from NRC

Potential Technical Specification Changes

+ Definition of rated thermal power

* Low SG pressure reactor trip setpoint

+ Low SG pressure MSIS setpoint

* Peak containment pressure,

* Operating range for cold leg temperature at 100 percent power

Test Program

* Review UFSAR Chapter 14 for applicable testing

* Use existing Surveillance Test Procedures as applicable

* Test program and results to be described in start-up test report in accordance with the PVNGS TRM

PVNGS Unit 2 SGRP I Integrated Level One Schedule for RSG & Power Uprate 1997 1998 1999 2000 2001 1 2002: 2003 1:20041

U2i0

Design & Document Phase

U2RU

Fabrication of RSGs9Ansaldo Energla $.p.a. In Milan. Italy

U2RMO

12W07 I102

Uprate Scoping

4*08

Award Eng. Contract I Obtain Infrastructure Permits Transport to

nalize Trnsportaion Route Intervention Modification Transport

Study Complete, 'wC RSGs II Engineering=%,

APS & CE RSG I Uprate Engineering Analysis Analysis R IDSI20o *1e01

NRC Evaluation /Approval of Uprate Submittal &01

RSG & Power Uprate Modification Engineering & Installation W2

Venice

to PVNGS

Arrive At PVNGS *9)02

1109 110

Signed Installation Phase I Contract With Bechtel

Spray Pond Temp Transmitter Uprate Eng SP Temp Trans Uprate Installation .11013 W01 , 3102MSIo"

Main Transformer Cooling Eng. Main Transformer Cooling Installation

Cooling Tower Wnd Vane Eng.

"Cooling Tower Wind Vane Installation ED Control Valve Eng. ED Control Valve Insllatklo 1i02~~5102 12I 22I

Containment Spray Pump impeler Modilfication Engineering

Containment Spray Pump Modliled Impeller Installation SOte P12W 0Iaa 20n . Site Preparations for Installation

309 III i mosU2R8 - Laser Piping Templating U2R9 - Design Verification Wlldowne U2R 10. elo-shield VAll Mods logo/Iraqi W • •2ems0MS

Prepare/Issue U2RIO DCP*s Prepare/Issue U2RIOV1P's SG Level Transmitter Installation

SO Level Transmitter Design Eng SG Level Transmitter Installation P 5001 3002000502

PreparelIssue Const. Proc. Prepare/Issue U2Ri I Vi's3I01 Pe Ae Ae-01

Insalal Protected Ares Access. Nort

U2R11, Replace SGO

s52 Tm

Prepare/Issue U2R1 I DCPas

"Design/Consruct OSG Storage/NSG Storage Facilities

North Annex Remodeling Install Downcomer Slowdown Electlcal Modification S..I ,

Avarded To Awalkdo

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Safety Analyses

* Sample from uprate submittal (cont.) Conclusion

For the IOSGADV+LOP event, all of the acceptance criteria are met. The peak primary and secondary pressures remain below 110 percent of design at all times, thus ensuring the integrity of the RCS and main steam systems. The minimum hot channel DNBR remains above the SAFDL, thus ensuring fuel cladding integrity. Offsite radiological consequences remain within a small fraction of 10 CFR 100 guidelines.

Configuration Management

CENP Analysis

S&L Analysis

Palo Verde Modification Packages

lAW 81 DP-OEE1 0

4-

Bechtel Analysis

Bechtel Installation Standards

PVNGS Impact Process 81 DP-OCC26

RSG Design Specification

02MN-725

Ansaldo Design & Analysis

u ,, !

Configuration Management

I

Mod Pkg #1

Mod Pkg #3

Mod Pkg #2

Mod Pkg #4

Mod Pkg #1

Mod Pkg #3

Mod .Pkg #2

Mod Pkg #4

N,

Master Mod Pkg

Power Uprate Mod

I

SGR Mod

. II I

Control Of Design Inputs

41Analysis

Bechtel Analysis

Containment Spray Modification

* Increase in calculated containment peak pressure has decreased pump head margin

* Pumps would be marginally acceptable * Approximately 8 PSID margin is desired at

test flow rate

Containment Spray Modification

*Alternate flow rate instrument with less uncertainty will be used to regain ~4 PSID

* Modifying pump impeller profile will regain the remaining desired margin • Vendor guidance will be used

* One pump to be done in 2R9 * One pump to be done in 2R10

Bechtel Engineering Schedule Palo Verde Unit 2 SGRP

Page 1 of 1 5111/00

1999 2000 2001 2002 2003

soJF A JJAso NID JJIFI AJIJAIAIsAINDJFMAM JIJIA1sloINIDJIFI+II JIJIAISoNID N-2 :: iN1 { ;SGRO

Walkdown Plans 3/ $/2t./ 101"!6

POWER UPRATE ENGINEERING... J 1 0 .. Primary Systems Analysis 1/3 !! - 8/1 Jun 19.'00: Prelim Branch Line Reaction Loads ~~~~~~~ ....... P m a y S s m .A n l s s ..................... ...... .. ..I.............. ..... ....... Ba c ..n .e ~ .o d .. .... "... . . .. ...

Secondary Systems Analysis 1 1,/21 July 31, '00: Prelim RSG Nozzle Reaction Loads

Containment Structural Analysis 3/10.- 10/,. 4

N-1 MOD PACKAGES i K. Prepare 30% Packages6 5. *"- .......15 Prepare 70% Packages 2.8 6----44/16: "Prepare 100% Packages 5/220--07-17: I S5/22 I•! 7117! Sept 4,'01: N-1 +

Issue Final Packages ....... 8/7. 8/28 Sackagep .. N i e . ..................... ........ .. .. ........... .. .. ...

PRE-OUTAGE MOD PACKAGES .. ... .......... ........... .. ..i .... .. ........ . .... ........ ....... .. .... .. .. • • • P r e p a r e.7.%.P.ck a g e s.......................................................... . ..... .............. . . ................ .. ............ . . ......................... ............... . Prepare 30% Packages ' 3 .... 7/./ i

Issue...Final..Packages. .Aug 16,'02: Pre-Outage-+

.Issue Final Packages .. 150" Packages Complete ... .. ..... ....... .. ......... ...... ...... ... ... ........ ................... ........ .... ...... .. .. .................. .... .......... .......... ................. ........ .i .. .... .... ... . .. ..... .............. .... ... ......... SGRO MOD PACKAGESj

Prepare 30% Packages . .7/13 Prepare 70% Packages 5/7 3f2 I P ......... 00%.... ......Packag es .... -.. J.2 , 0:.R.............. . ...... ... ....... ... .. .... . .... .... ..... .. F e .. a r... e- .1 0 0.%..o. .......... ..Pa c k....... ........ .... ...... ......" ........................ ........ .... +....... .... .. ... , ... .... ..... .... 1.7 ... ......... ... .. .. ... .... .......... .O e c 2 0 , '0 2 : S G R O ,

Issue Final Packages .1 . Packages Complete

POST-OUTAGE MOD PACKAGES I .

Prepare 30% Packages . . .. .. .. ... 22 Prepare 70% Packages 7/22 *-19/13 Prepare 100% Packages 7... ! 10/7 1- 18 ... . ... . ........ + . ... .... .... . . ..... ........ • .. . .... .. .D e c 2 0 , '0 2 : P o s tIssue Final Packages 12/2 l2/13 DcOutagePosC Outage Pkgs Cmplt

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SGR Implementation Phase -Functional Organization -

5/18/00

Major Activities

* U2R9 (fall 2000) • Laser templating of piping in containment • Design walkdowns in containment • Polar crane inspections

* Modify one containment spray pump impeller

* U2C10 (winter 2000 - spring 2002) • Personnel access and north side sally port

Art •