util, 10CFR50.55a(5)(i). listed. · ,CATEGORY 3. REGULAT w'i XiVFORMATION DISTRIBUTIO dYSTEM (RIDS)...

,CATEGORY 3.

REGULAT w'i XiVFORMATION DISTRIBUTIO dYSTEM (RIDS)

ACCEE/ION 16R: 9907260092 DOC.DATE: 99/07/16 NOTARIZED: NO DOCKET 0FACIL:STN-'50-528 Palo Verde Nuclear Station, Unit .1, Arizona Publi 05000528

AUTH.NAME AUTHOR AFFILIATIONXDE,W.E. Arizona Public Service Co. (formerly Arizona Nuclear Power

RECIP.NAME RECIPIENT AFFILIATIONRecords Management Branch (Document Control Desk)

SUBJECT: Forwards rev 2 to "Inservice Insp, Program Summary Manual fo'PVNGS Unit 1," per requirements of 10CFR50.55a(5)(i). CCommitments made by util, listed.

ADISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:~ YTITLE: OR Submittal: Inservice/Testing/Relief from ASM Code T

NOTES: STANDARDIZED PLANT 05000528 E

RECIPIENTXD CODE/NAME

LPD4-2

COPIESLTTR ENCL

1 1

RECIPIENTID CODE/NAME

FIELDS,Ã

COPIESLTTR ENCL

1 jINTERNAL: ACRS

NUDOCS-ABSTRACTRES/DFT/ERAB

;. EXTERNAL: LITCO ANDERSONNRC PDR

1 11 1

FILE CENTER

RES/DET/MEB

NOAC

1 01 1

D

'E

L„ig L (jQ~) pic-Lu)IiU

NOTE TO ALL "RZDS" RECIPIENTS:PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTSOR REDUCE THE NUMBER OF COPIES RECEZVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROLDESK (DCD) ON EXTENSION '415-2083

TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10

i+i

1

CommlfmenL Innmetke. Fnerpy. 10CFR50.55a(g)

Palo Verde NuclearGenerating Station

WilliamE. IdeVice PresidentNuclear Engineering

TEL 602/393-6116FAX 602/393-6077

Mail StatIon 7605P.O. Box 52034Phoenix, AZ 65072-2034

102-04312-WEI/SAB/RKBJuly 16, 1999

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskMail Station P1-37Washington, DC 20555-0001

Dear Sirs:

Subject: Palo Verde Nuclear Generating Station (PVNGS)Unit1Docket No. STN 50-528Unit 1 First 10-Year Interval lnservice Inspection (ISI) Program—Revision 2

Pursuant to the requirements of 10 CFR 50.55a(5)(i), Arizona Public Service Company(APS) hereby submits Revision 2 to the first 10-year interval Inservice Inspection (ISI)Program for PVNGS Unit 1. The enclosed document reflects the final status of ISI

program requirements for the first 10-year interval. Included in this revision is anupdated record of program revisions, revised pages to the program (with change bars),and any new or revised relief requests. Relief Request number 7 was previouslyapproved for limited Class 2 and 3 components, and has been revised to includeadditional components. Relief Requests 9 and 10 were previously approved by theNRC Staff under separate requests subsequent to Revision 1 of the Unit 1 first interval.ISI program. Relief Requests 11 through 16 are new requests being submitted as partof Revision 2 to the ISI Program. Approval of relief request numbers 7, 11, 12, 13, 14,

15 and 16 is requested by July 17, 2000 pursuant to 10 CFR 50.55a(g)(5)(iv).

The following new commitments are being made to the NRC in this letter:

~ APS will perform the required first interval ISI program VT-2 systemleakage test and system pressure test examinations of the ASME Class1 and Class 2 reactor head vent system lines in the first Unit 1 refuelingoutage of the second 10-year ISI interval (U1R8). See Relief Request No.11 ~ p,oQ ~

9907260092 99O716PDR ADQCK 050005288 '' 'DR

t

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"U.S. Nuclear Regulatory CommissionATTN: Document Control DeskUnit 1 First 10-Year Interval Inservice Inspection (ISI) Program—Revision 2Page 2

Should you have any questions, please contact Scott A. Bauer at (623) 393-5978.

Sincerely,

WEI/SAB/RKB/

Enclosure:

cc: E. W. MerschoffN. KalyanamJ. H. Moorman

0 4l

4

INSERVICE INSPECTIONPROGRAM SUMMARYMAZUAL

PALO VERDENUCLEARGENERATING STATION

UNIT 1

ARIZONAPUBLIC SERVICE COMPANYP.O. Box 52034Phoenix, AZ 85072-2034

PVNGS5801 S. Wintersburg Road

Tonopah, AZ 85354

PREPARED BY:

REVIEWED

REVIEWED BY:

ANIICONCURRENCE:

APPROVALBYENGINEERINGDEPARTMENTLEADER:

DATE: 5DATE:

DATE: 7 /3DATE: ~-4-+t

6 7, S/a k UATE. ///Y/f5

COMMERCIALSERVICE DATE: 01/28/86

PROGRAM NO: ISI-1REVISION NO: 2DATE: 06-18-99

r

4

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RFCORD OF RFVISIONS

Cover .

REVISI N

I

ii thru iii.

1-1 and 1-2 .....

1-3 thru 1-5.

1-6 thru 1-7.....

4-1 thru 4-2

TABLES:1-1 and 1-2....................1-3 page 1 of2 ..............1-3 page2of21-41-5 page 1 of21-5 page 2 of2 ..............1-6 page 1 of3 .

1-6 page 2 of3.1-6 page 3 of3.1-7 page 1 of4.1-7 page 2 of4.1-7page3 and4of4.1-81-9 page 1 of5 .

1-9 page 2 thru 4 of5.1-9 page 5 of5 .

1-10.1-12 page 1 of21-12 page 2 of21-13 and 1-14.1-151-16 .....1-IWF page 1 of31-IWF page 2 of3

1-IWF page 3 of3

1-RCP..5-1 and 5-2

TABLES:2-1

2-2page1of22-2 page 2 of2

0

1

01

01

1

20201

20

1

0201

1

02

1

00

REV. 206-18-99

0'

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0

2-3 page 1 thru 3 of4....2-3 page 1 of4.2-3 page 2 thru 3 of4.

..... 1

..... 0..2

2-3 page 4 of4 .

2-4 ...2-52-6.2-7.

..... 0.0

1

2-IWF page 1 thru 3 of6 .

2-IWF page 4 thru 5 of6 .

2-IWF page 6of6 ........

6-1 and 6-2

TABLES:3-1 page 1 of23-1 page 2 of23-IWF ..........

7-1

TABLES:

I 2-AHE page 1 and 2 of3

2-AHE page 3 of3.

8-1

TABLES:2-CFR page 1 thru 3 of6 .

2-CFRpage3 thru4of6 .

2-CFR page 5 of6 .........

9-1

9-2

Relief Request 1 thru 8..

10-1

10-2

11-1 thru 11-4.

Zone Drawings

~ ~'

~ ~ ~ ~ .... 01

'0

..12

'

~ ~ ~ ~ ~ ot ~ 1

..0

(see Dwg.)

REV. 206-18-99

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3.3 ACCESSIBILITY

3.3.1 The preservice examinations were performed with examination techniques, both automated andmanual, similar to those planned for use during Inservice Inspections. The examinationlimitations noted during the preservice examinations were documented in requests for reliefsubmitted with the preservice examination program. There have been no additional codelimitations noted during the formulation ofthis program other than those contained in theRequest for Relief Section.

3.3.2 All items that are scheduled for examination willbe examined to the extent practical. Inaddition, any code limitations that are noted during the examinations willbe documented in thesummary reports that are prepared aAer each outage.

3.4 EXAMINATIONTECHNIQUES

3.4.1 The three types ofexaminations utilized to perform Inservice Inspections, along with the actualnondestructive examination technique, are identified in the legend below:

VT - Visual

VT - 1 (General Condition)VT- 2 (Leakage)VT - 3 (Structural Condition)VT- 4 (Operability)

S - Surface

PT- Liquid PenetrantMT - Magnetic ParticleET - Eddy Current

VOL- Volumetric

UT - UltrasonicRT - Radiography

3.4.2 Allthe above nondestructive examination techniques willbe performed using specifictechniques and procedures that are identified in ASME Section XI, or alternative examinationsthat are demonstrated to be equivalent or superior to those identified.

3.5 INSPECTION INTERVALS

3.5.1 The Inservice Inspection Program was prepared in accordance with Program B ofASMESection XI. The initial 10-year inspection interval and corresponding inspection periods aredefined below:

I'irst Inspection Interval:Period One:Period Two:Period Three:

01/28/86 to 07/17/98 *01/28/86 to 11/17/9111/18/91 to 03/17/9503/18/95 to 07/17/98

1-3

REV. 206-18-99

These dates have been modified to a common interval start date for all three PVNGS units.This is in accordance with NRC letter dated October 21, 1987, from E. A. Licitra, NRC, toE. E. Van Brunt, Jr., ANPP, "Inservice Inspection Programs - Palo Verde, Units 1, 2, and 3"to allow the three units to be under the same ASME Section XIedition and addenda. Itshould be noted that the intervals/periods may change between units to allow for extendedoutage durations per IWA-2400 ofASME Section XI. For Unit 1, a 16-month extensionwas also added to the interval due to the length of the second refueling outage.

* The first inspection interval has been extended 1 year to 07/17/99 as allowed by IWA-2400(c).

3.6 EXAMINATIONCATEGORIES

3.6.1 The examination categories ofASME Section XIwere utilized to develop this program for allsystems, components, and supports. The Program summary tables contained in Sections 4.0and 5.0 are organized by examination category for ASME Class 1 and 2 systems, respectively.For each examination category, these tables identify the system, line number, nondestructiveexamination method, total number of items, required examination amount for each inspectionperiod, and running percentage. For ASME Class 3 systems, the examinations categories areidentified in Section 6.0.

3.7 EVALUATIONAND REPAIR

3.7.1 The evaluation ofall examination results willbe performed in accordance with ASME SectionXIArticles IWAand IWB-3000. In addition, all applicable repairs and replacements willbeperformed in accordance with ASME Section XIArticles IWA,IWB, IWC, IWD, and IWF-4000 and 7000. Pressure tests willbe performed only on welded repairs or replacements, inaccordance with IWA-4000 and 5000. Both the evaluations and repair or replacement willbeperformed in accordance with the 1980 Edition through and including the Winter 1981

Addenda ofASME Section XI, or later editions and addenda ofASME Section XI referencedin 10 CFR 50. Allrepairs and replacements willbe documented in accordance with the WorkControl program, and are maintained at Palo Verde for review.

3.8 SYSTEM PRESSURE TESTS

3.8.1 System pressure tests willbe performed in accordance with ASME Section XIand as identifiedin Sections 4.0, 5.0, and 6.0 for ASME Class 1, 2, and 3, respectively. These tables alsoidentify the type ofpressure test, and test frequency, any applicable requests for relief, andreferences the appropriate ASME Section XIArticle for each ofthe ASME Code Classes.

3.9 AUGMENTEDHIGHENERGY PIPING

3.9.1 Based on the PVNGS UFSAR, an augmented examination is required for protection againstpostulated pipe failures. This augmented examination program includes the followinghighenergy piping systems located between the containment penetration and the main steam

support structure wall:

Main SteamFeedwaterSteam Generator BlowdownDowncomer Feedwater

1-4

REV. 206-18-99

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3.10 EXEMPTIONS

3.10.1 The exemption criteria identified in the 1980 Edition through and including the Winter 1981Addenda ofASME Section XIwas utilized for all ASME Class 1, 2, and 3 components andsystems. This includes the PVNGS Safety Injection System (RHR, ECCS, and CHR systems)piping and components, even though 10 CFR 50.55a requires the 1974 Edition through andincluding the 1975 Summer Addenda be utilized. Itwas concluded after a detailed review thatthe exemption criteria identified in the Winter 1981 Addenda was more conservative in everycase than those identified in the Summer 1975 Addenda, and more examinations wouldtherefore be performed on safety injection systems piping and components.

3.10.2 A thorough review ofall the systems and components was performed in accordance with theabove exemptions and a complete set ofcolor coded Inservice Inspection Boundary drawingswas prepared. These drawings are maintained at the PVNGS site for review.

3.11 CODE CASES~ e

3.11.1 ASME Section XICode Case acceptability willbe based on Regulatory Guide 1.147.

3.11.1.1 In addition, Code Case N-416-1 was approved for use in an SER attached to NRC letteraddressed to Mr. W. L. Stewart, dated March 16, 1995.

3.11.1.2 Code Case N-498-1 was approved for use in Revision 12 to Regulatory Guide 1.147issued June 10, 1999.

REV. 206-18-99

1-5

1

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0'Q PALOVERDENUCU<ARGE<NERATINGSTATIONM 10YI<~INTERVAL-EXANIINATIONSUMMARYASME CLASS I TABLE 1-6

PAGE 2 OF 3

AShIEITEhINO. ZOiM~hlPOiIENTORSYSIEM IDENTIFICATIOi(

DESCRIPTIONLINENO., ORSERIALNO.

NDE TOTALMETIIOD ITEhfS

EXAMINATIONAMOUNT

INSPECTIONPERIOD

RUNNING REMARKS ANDRELIEF REQUESTS

NoaeNone

6110 NoneNone

61206130

NoneNone

6140 None

61506160

6170

6180

16-Reactor CoolantPump IA

17-Reactor CoolantPump IB

18-Reactor CoolantPump 2A

19-Reactor CoolantPump 2B

NoaeNone

None

Haage Studs

Hange Studs

Hange Studs

Haagc Studs

433" x32.87"

433" x32.87"

433" x32.87"

433" x32.87"

Vol'ol'ol'ol'616

16

16 53-6

OneTwo

31

62100

31

62100

31

62100

31

62100

'ASUPPLEMENTALVISUALEXAMWASPERFORMED EACHREFUELING OUTAGEINCONJUCIIONWITHEXAMCAT.B.P(SEE IEIN80-27)"SUPPLEMENTEDBYVISUAL(EACHREMOVAL)ANDSURFACE (ATS YR.INIERVALS)EXAMSWIIENREMOVED(SEE IEB 82412)

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PAGE 3 OF 3

ASMEITEhfNO. ZONE~hlPOi~ORSYSIKM IDENTIFICATION


NDE TOTALhKTHOD ITEhIS

EXAMINATIOiNAMOUNT

INSPECITOI<IPERIOD

RUNNING REhIARKS ANDRELIEF REQUESTS

6190

6200

16, 17, 18 an4 19-Reactor CoolantPumps IA, IB,2A 4 2B

~EESt 0


17-Reactor CoolantPump IB


19-Reactor Coolant "

Pump 2B

PiangeSurface

Nuts Ec

Clamping Ring

Nuts 4tQamping Ring

Nuts gc

Clamping Ring

Nuts 8tQamping Ring

CASING SNIA-1247IB -12492A - 12482B - 1250

4528" x7.283"

4328" x7283"

4328" x7283"

4.528" x7283"

VT-I

VT-I

VT-I

VT-I

VT-I

I perpump

16

16

16

16

OneTwoTillee

OneTwoThree

OneTwoThree

3162

100

3162

100

31

62100

.3162

100

a100% EXAMWHENDISASSEMBLED(THERE ARE NOBUSHINGS INTHEPUMP PLANGES)"THECLAMPINGRING WILLBEEXAMINEDiTHEREARE NO WASHERS)

6210 NoneNone

6230 None

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A D Q PALOVERDENUCLEARGENERATINGSI'ATIONL7 10 YFARINTERVAL-FXA1VHNATIONSUM1VJARY ASME CLASS I TABLE 1-7

PAGE I OF 4

ASMEITEhINO. ZOiiEKOhiPOiKNrORSYSIXhf IDENTIFICATIOiN

DESCRIPTIONLINENO„ORSERIALNO.

NDEMETHOD

TOTALITEMS

EXAhIINATIONAhIOUNT

INSPECflONPERIOD

RUNNING REhlARKS ANDRELIEF REQUESTS

B 700

710 None

720

730

5- Pressurizer Manway

3- Steam Generator ICold Leg andHot Leg Mauways

Studs gs Nuts

Studs ge Nuts

18" x 14.5"

IS"x 143"

VT-I

VT-I

'0Pairs

'0Pairs

202020

404040

OncTwo

100

100100

100

100

100

CSTUDS ONLYARESUPPLEMENIEDBYVISUAL(EACHREMOVAL)ANDSURFACE (AT5 YLINTERVALS)EXAMSWHENREMOVED(SEE IEB 82412)

740

4- Stcam Generator'2Cold Leg andHot Leg Manways

Studs dt Nuts

None

I.S" x 143" VT-I a 40Pairs

404040

OncTwoIhfcc

100100

100

750

31-Pressurizer Safeties

37.Charging Line

HangcHangcHangeHang

RC 1-6"RC.3%"RC 54"RC-74"

CH-5-3"

VT-I

VT-I

~ 4

I00

OncTwoThfcc

2550

100

100

100

100

0

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Al3Q PALOVERDENUCLEARGENI<WATINGSI'ATIONk3 10 YEARINTERVAL-KGkMNATIONSUMMARY ASME CLASS 1

TABLE 1-8

PAGE 1 OF 1

AShiEITEMNO. ZONE~hIPONENTOR SYSIEM IDENTIFICATION


NDE TOTAI.hKTHOD ITEihIS

EXAhilNATIONAihIOUNT

INSPECTIONPERIOD

RUNNINGF

REhiARKS ANDRELIEF REQUESIS

B 800

810 None

820

hXQLQIhKKX

S- Pressurizer Support Skirt SN 78373 S, Vol 33%33%34%

3366

100

hXQKHhKHIX

3- Steam Generator 1

4- Steam Generator 2

Support Skirt

Support Skirt

SN 78273-1

SN 78273-2

S,Vol

S,Vol

33%

34%

33%

OneTwoThree

33'00'6

'ULTIPLEVESSELS,EXAMNATIONSTOTAL100%SUPPORTSYJRT WELD1N 1 EQUIVALENTSTEAMGENERATOR.

840 None

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PAGE 1 OF 5

AShKITEhINO. ZONE~hIPONENTOR~f IDEKTIFICATIOiN


NDE TOTALhKTHOD ITEhIS

EXAhIINATIONAhIOUNT

INSPECIIOiNPERIOD

RUNNING REhIARKS ANDRELIEF REQUESTS

B 900

910

911

912

6- RCS Primsry Piping

20-Pressurirer Surge Linc

21-Shutdown CoolingLoop I

22-Shutdown CoolingLoop 2

23-Safety Injection IA

HL IHL2CL IAto RCPCL IB to RCPCL2Ato RCPCL2BtoRCPCL IA to RPVCL IB to RPVCL2AtoRPVCI.2B to RPV

Butt Welds

Butt Welds

Butt Welds

Butt Welds

RC-3242" IDRG6342" IDRC-33-30" IDRC-30-30" IDRC.73-30" IDRC44-30" IDRC-34-30" IDRC-31-30" IDRC-7.9-30" IDRC.93-30" ID

RC 2&-12"

RC.S1-16"SI-240-16"

R(A8-16"SW93-16

SI-207-14"SI-203-12"

i

S, Vol

S, Vol

S, Vol

S, Vol

S, Vol

62

22

27

19

712

13

30-2

OncTwoTlncc

OneTwoThrcc

OneTwoTlircc

OneTwoTllrcc

ll31

$2

99

27

9Ig27

7Is26

16

16

26

'IIELESSEROF12" ORONEPIPE DIAMETERLENGTHFROMSCHEDULED CIRCWELD INTER-SECIION WILLBEEXAMNED

AUTOMATEDEXAMOF NOZZLETOEXTENSION ANDEXIENSIONTO PIPEWELDS

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PAGE I OF I

AShIEITEhINO. ZONE~hlPOi IEN1 ORSYSIEM IDENTIFICATION

DES CRIPTIOiNLINENO., OR NDE TOTALSERIALNO. METHOD ITEhIS

EXAhIINATIONAhIOUNT

INSPECIIONPERIOD

RUNNING REMARKSANDRELIEF REQUESTS

B 1000

1010

22-Shutdown Coo! ingLoop 2

244afety Injection IB

25-Safety Injection 2A

26-Safety Injection 2B

36.Letdown Line

Lugs

Stanchion

Stanchion

Stanchion

SI-193-16"

SI-223-14"

SI-160-14"

SI-179-14"

RG091-16"

Two

100

4080

ITEMB10.10COMBINEDFOR PERCENTAGE

VOIDEDPRIOR TOUNIT I SERVICEDATE

1020 None

'1030 None

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TABLE 1-13

PAGE I OF I

AShIEITEhINO. ZOiiE~hIPOiIll'ORSYSIEM IDENTIFICATION


NDEMETIIOD

TOTALITEMS

EXAhIINATIONAMOUNT

INSPECTIONPERIOD


II 1300

ZEHELJBB.

1310

I- Reactor Vessel Examine the areas aboveand below the reactor corethat arc made accessibleforexamination by removalofcomponents during normalrefueling outagcs.

VT-3 AccessibleAreas

33%33%34%

3366

100

'EXAMNEAT1st

REFUELING OUT-AGE, ANDSUB-SEQUENILYAT3-YEARINIERVALS

13201321

1322

I1330

1331

N/AN/A

None

Examine the accessiblewelds and thc surrounding

VT-3 AccessibleWclds

IOO% ~ e DYTHEENDOFTHE INTERVAL

1332 Examine the accessiblecore support sttuctufe

VT-3 Accessib! e

Surfaces100%

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A53 Q PALO VERDENUCUMRGl<.NFRATINGSI'ATIONL k7 10 YEARINTERVAL-F<WAMINATIONSUMMARY ASME CLASS 1

TABLE I-ISPAGE I OF I

AShIEITEMNO. ZOiIE~hIPOi IEO'OR~1 IDENTIFICATION


NDEhKTHOD

TOTALITEhIS

EXAMINATIONAihIOUNT

INSPECTIOi IPERIOD


B 1500

1510152015301540155015601570

Reactor VesselPressurizerSteam GeneratorsHeat ExchangersPipingPumpsValves

PressureRetaining

Boundary

VT-2 Entire Pressure

Retaining BounIWA-5000IWB-5000

'ACHREFUELINGOUTAGE

1511

1521

1531

1541

1551

1561

1571

Reactor VesselPressurizerStcam GeneratorsHeat ExchangersPipingPumpsValves

PrcssureRetainingBoundary

VT-2 Entire PressureRetaining BounIWA-5000IWB-5000

100 "BYTIIEENDOFTHE INTERVAL

"'ERFORMWALKDOWNATTHE BEGINNINGOFEACH REFUELINGOUTAGEFOR GEN-ERIC LEITER8845.INADDmON,WALKDOWNREQUIREMENTSSHALLBEEVALUATEDFORSHUTDOWNSFOLLOWINGOPERATIONLONGER THANAPPROXIMATH.Y6MONIHS INMODE IOR 2.

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PAGE I OF 3

AShIEITEMNO.

F 110

F „120F 130F 140

F 210F 220F 230F 240F 310F 320F 330F 340F 350

ZONE~hlPOi KN1'ORSYSIEhI

I- Reactor Vessel

IDENTIFICATIOil

SupportColumns

DES CRIFHOiiiLINENO„OR NDE TOTALSERIALNO. 'lETIIOD ITEMS

SN 78173

EXAhIINATIONAMOUNT

0 a ~ ~

04

INSPECTIONPERIOD

OncTwoThree

RUNNING

00

100

REhfARKS ANDRELIEF REQUESIS

REQUEST FOR RE-LIEF tt I df tt3

'NCLUDES EXAMITEMS IDENTIFIEDAS APPLICABLE.

"NDE METHODINCLUDES VT-IEXAMS,WHEREAPPLICABLE.

3- Steam Generator I

4- Steam Generator-2

5- Pressurizer

Support Skirt

Support Skirt

Support Skbt

SN 78273-1

SN 78273-2

SN 78373

VT-3

VT-3

VT-3

OncTwoThfcc

OneTwoThlcc

OneTwollifcc

100

100100

100

100

100


Vatical andLateral Supports

SN 1109-1 A 10 OneTwoThfcc

2060

100

cd goo<

17.Reactor CoolantPump IB


19-Reactor CoolantPump 2B




SN III6-IB

SN 1109-2A

SN 1109-2B

VT-3

VI'-3

VT-3

10

10

10 424

OneTwoThfcc

OncTwolllfcc

2060

100

4060

100

4060

100

h4

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M 10 YEARINTERVAL-K21NINATIONSUMIyIARY ASMKCLASS 1TABLE I-IWFPAGE 2 OF 3

ASMEITEMNO. ZONE~hIPOi%0'ORSYSIEM IDENTIFICATIOiN


NDE TOTALMETIIOD ITEhIS

EXAMINATIONAMOUNT

INSPECTIONPERIOD

RUNNING REMARKSANDRELIEF REQUESIS

F 110

F 120

F 130

F 140

F 210F 220F 230F 240F 310F 320F 330F 340F 350

20-Pressurizer Surge Line

214hutdowtt CoolingLoop I

22-Shutdown CoolingLoop 2

Supports

Supports

Supports(1-810.10)

RC.28-12"

RC-51-16"81-240-16"

RG68-16"$1-193-16"

VT-3 22

OneTwolllfce

2957

100

3264

100

31

69100

23-Safety Injection IA

24-Safety Injection 18

25-Safety Injection 2A

26-Safety Injection 28

Supports

Supports(I-BIO.IO)

Supports(1-810.10)

Supports(1-810.10)

81-207-14"SI-203-12"

SI-223-14"81-221-12"

SI-160-14"81-156-12"

SI-179-14"81-175-12"

VT-3

VT-3

VT-3

OneTwothree

OneTwothree

17

50100

2550

100

2971

100

3875

100

27-Pressunzer SprayLoop IA

28-Pressurizer SprayLoop 18

29-Pressurizer SprayLoop IB andCornbhrcd

30-Aux Pressurizer Spray

Supports

Supports

Supports

Supports

RG62-3"RC-16-3"

RC-17-3"RC-18-3"RC-184"

RC IW"

CH.521-2"

VT-3

VT-3

VT-3

26

28 98ll

002

OneTwoThree

OneTwoThree

3569

100

3261

IN

67IN100

100

I

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C k3 10YEARINTERVAL-FWANIINATlONSUMMARY ASMKCLASS 2TABLE 2-2

FAGE~GF~

ASMEITEIIINO. ZOiVE~illPOi~ORSYSIEM IDENTIFICATION

DESCRIPTIOi <

LINENO., ORSERIALNO.

NDE TOTALMETHOD ITEMS

EXAbfINATIONAMOUNT

INSPECrIONPERIOD

RUNNING REMARKS ANDRELIEF REQUESIS

210 None

220

221

222

41-Steam Gcncrator I

42-Steam Generator 2

84-SD Cooling HeatExchanger Room A

87-SD Cooling HeatExchanger B

Nozzle toVessel Welds

Nozrle toVessel Welds

Nozzle toShell Wclds

Nonce toShell Welds

SN-78273-1

SN-78273-2

SN-18341

'N-1

&342

S, Vol

S, Vol

S, Vol

S, Vol

I03

OneTwolhfcc

OneTwoThree

OneTwoThree

OneTwoThree

29

100

$7

30

100

INSIDE RA-DIUS ON PIP-ING ONLYGREATERTHAN 12"D~MULTIPLEVESSELS:PERCENTAGE COM-BINED

MULTIPLEVESSELSPERCENTAGECOMBINED

Chgoo<

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l3U PALO VERDENUCUtARGENERATINGSTATIONM 10 YEA.RINTERVAL-IUMiVHNATIONSUMMARY ASMKCLASS 2

TABLE 2-3

FAGE~GF~

ASihIEITEhfNO. ZOiK~hIPOiiPORSYSIEM IDENTIFICATIOiN

DESCRIPTIONLINENO., OR NDE TOTALSERIALNO. hIETIIOD ITEhIS

EXAhIINATIOiNAhIOUNT

INSPECITONPERIOD


320

54.Feedwata SG No. Ihside Containment

55-Pm!water SG No. 2Inside Containment

62-AuxiliaryFeedwata SG I

64.Blow~ SG IInside Containment

65-Blowdown SG 2Inside Containment

11.LPSI Pump Room ADischarge

Attachments SG405

AF418

SG-39SG-53

SG48SG.52

SI-81

OneTwoTllrec

On)

OneTwollircc

OneTwoThree

100

5050

100

100

100

4351

100

2563

100

SI SYSTEM%'S COMBINED

76-Containment Spray Pump RoomASuction

77-Contaimnent Spray Pump RoomADischarge

80-Containment Spray Pmnp RoomB Discharge

82-Shutdown Cooling Heat ExchangerRoom A

83-Shutdown Cooling Heat ExchangerRoom A

864hutdown Cooling Heat ExchangerRoom B

88-East Wrap

89.East Wrap

Attachments

Attachments

SI-9

SI-79

81-119

SI-78

$1-70

S147SI-90

SI-72

SI-72

SI-194

TwoThree

1

I

'g>4

t

I y

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l3Q PALO VERDENUCUDRGENERATINGSI'ATIONM 10 YFA.RINTERVAL-KKMINATIONSU1VPrIARY ASMK CLASS 2

TABLE 2-3

PAGE~GF~

ASMEITEMNO. ZOi4E~IIPONENPORSYSIEAI IDENTIFICATION

DES CRIPTIOiNLINENO., ORSERIALNO.

NDE TOTALWETIIOD ITEMS

EXAMINATIONAMOUNT

INSPECTIONPERIOD

RUNNING REMARKSANDRELIEF REQUESIS

320

91-West Wrap

92-West Wrap

93-West Wrap

94-A Train Misc. Pipe Chases th88'ipe

Tunnel

9S-B Train Misc. Pipe Chases gc88'ipe

Tunnel

96.Containment LPSI Header to Loop IA

99~ntainmcnt LPSI Header to Loop 2B

100Coatainment LPSI Train ASuction

101-Containment LPSI Train B Suction

Total Safety Injection

Attachn eats

Attachments

Attachments

Attachments

Attachn cuts

Attachments

SI-70

SI.239SI-241

SI49

S1-70

SI-194

SI-202

S1-174

SI-7SI-369

SI-30

30 109Il

TMi'0

Two

OneTwoIhfcc

3363

100

330

72-LPSI Pump A AttachmentLugs

SN 0876-36 OneTooThfcc

66100

100

7S-LPSI Pump B

78-Containment Spray Pump A

AttachmentLugs

AttachmentLugs

SN 0876-37

SN 0876-38

OneTwoT1ircc

33100

66100

100

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0l3 'Q PALO VERDENUCLEARGENEBATINGSTATION

k3 10 YEARINTERVAL-EXANIINATIONSUMMARY ASME CLASS 2TABLE 2-IWF

PAGE~GF~

ASMEITEMNO. ZO IE~iiIPONENrOR SYSIXM IDENTIFICATIOi1

DES CRIPTIOi ILINENO., ORSERIALNPO.

NDEiaaf ETIIOD

TOTALrrEMS

EXAMINATIONAMOUNT

INSPECI'IONPERIOD

RUNNING REMARKSANDRELKFREQUESTS

F110F120F130F140F210F220F230F240F310H20H30H40HSO

7S-LPSI Pump B

76~tainment SprayPump ASuctioa

77~tainmcnt SprayPump A Discharge

Supports

Supports

SN4876-31

81-9SIW7SI-78

SI-79SI-82

VT-3

VT-3

VT-3

3A ~

10 OneTwoThfCc

E'3 PVMP SVPPORTS

78~tainmeat SprayPump A

79~!ainmcat SprayPump B Suctioa

80~tainment SprayPump B Discharge

Supports

SN4876-38

SI-33SI-34

SI-I1981.141

VT-3

VT-3

3FE

10

OacTwo

OneTwoTlircc

gl~tainmcat SprayPump B

82$ hutdown Cooling A

83$ hutdown Cooling A

8S$ hutdown Cooling B

Supports

Supports

Supports

SN4816-39

Sl-79SI-78

SI-70SI-87SI-90SI-89Sl-82

SI-119SI-123

VT-3

VT-3

VT-3

VT-3

3 '

19

10

4312

OneTwoThree

gl goo<

86$ hutdown Cooling B Supports SI-72SI-I34SI-147SI-I3SSI-129

VT-3 2S 3

7

IS

OneTwoTllfCC

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l3Q PALO VERDENUCIS~ GEM<2AATINGSTATIONk3 10 Y1ÃRIKIXRVAL-EXAMINATIONSUMMARY ASME CLASS 2

TABLE 2-IWF

PAGE~OF~

AShIEITEMNO. ZOND'E~hIPOl IENrORSYSIXM

C

IDENTIFICATION


NDE TOTALMETIIoD rrEMS

EXAhIINATIONAMOUNT

INSPECTIONPERIOD

RUNNING REMARKS ANDRELIEF REQUESIS

FIIOF120F130F140F210F220F230F240HI0H20H30H40HSO

MHIIEIE12

88.East Wrap

89.East Wrap

90.East Wrap

91-West Wrap

Supports

Supports

Supports

Supports

SI-72SI-73

SI-173SI-194

81-134

SI-7081-71

VT-3

VT-3

VT-3

14

10

Oae1hrec

T'lVO

92-West Wrap ~

93-West Wrap Supports

SI-2SI-239SI-241

SI49 VT-3

12 OncTlVO

ThfCC

94-A Train Misc. Pipe Chases dt88'ipe

TunnelSupports SI-70

SI49SI-241

OacTwoThree

95-B Traia hiisc. Pipe Chases th88'ipe

TunnelSupports Si-72

SI.134SI.194

VT-3 19 610

3

OneT'lvoThfcC

9&Containmeat LPSI Header to Loop IA Supports Sl-202 VT-3 18

esl g

97~tainment LPSI Header to Loop IB Supports

98Matainmeat LPSI Header to Loop 2A Supports

99~tainmeat LPSI Header to Loop 2B Supports

81-220

SI-155

SI-174i

VT-3

VT-3

27

10

10710

23

OncTwothree

T'lvo

three

I

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)~ 4'f'/

I]I >

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A 'Q PALO VERDENUCLEARGENERATlNGSI'ATIONM 10Yl<~INTl<2VVAL-KKMlNATlONSUMMARYASMKCLASS 2

TABLE 2-AIIE

PAGE I OF

ASMEITEhINO. ZONE~hIPOiVTTORSYSIEM IDENTIFICATION

DESCRIPTIONLINENO., OR NDE TOTALSERIALNO. METHOD ITEMS

EXAMINATIONAMOUNT

INSPECIIONPERIOD

RUNNING REhfARKS ANDRELIEF REQUESTS

(')IDENTI-FIES TIIENUMBEROFWELDS THATARE NOT ASMECLASSIFIED

510

511512

520

MQII(IKUPIHSIZELDA51-Atmospheric Dump No. I

Bypass UV-180

52-Atmospheric Dump No. 2Bypass UV-171

5Mtmn to AuxFeedwatcr

Butt Welds4"x 337"

Butt Welds4"x 337"

Butt WcMs6"x.432"

SG.954"

SG-1054"

SG-814"SG-834"

S, Vol

S, Vol

S, VolS, Vol

(2I)

(21)

14

14

021

0

0021

10

99

100

100

100

3568

100

"NONE

521

522

47-Main Steam SG I West270'SSS

48-Main Stcam SG I East90'SSS

49-Main Steam SG 2 East270«MSSS

Butt Welds

Butt Welds

Butt Wclds

SG.206-28"SG.206.12"SG 2064"

SG-207-28"SG-207-12"SG-2074"

SG-208-28"SG-208-12"SG-2084"

S, VolS, VolS, Vol

S, VolS, VolS, Vol

S, VolS, VolS, Vol

5(1)25

5(I)25

5(I)25

13

00

013

0

00

13'ncTunThrcc

OneTwuThree

OneT'l%0

Thrcc

100

100

100

IN100

100

«100/«OF ALLINTERSECTINGLONGITUDINALWELDS WEREBE EXAMINED

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A MU PALO VERDENUCU<.ARGI«tERATINGSTATIONX k3 1071<~INIKRVAL-EXAIMINATIONSUMMARY ASME CLASS 2

TABLE 2-AnEPAGE 2 OF

ASMEITEihINO. ZONE~hlPONENFORSYSIKII IDENTIFICATION

DESCRIPTIONLhVENO., ORSERIALNO.

NDEhIETIIOD

TOTALITEMS

EXAMINATIONAMOUNT

INSPECITONPERIOD

RUNNING REhfARKS ANDRELIEF REQUESPs

521522

GQHIIHUE12

50-hiain Steam SG 2 West90'SSS

S I-Atmospheric Dump No. I

52-Atmospheric Dump No. 2

Butt Welds

Butt Wclds12" x .844"

Butt Welds12" x .844"

SG-209-28"SG-209-12"SG-2094"

SG.59-12"SG-70-12"

SG-84-1 2"SG-103-12"

S, VolS, VolS, Vol

S, VolS, Vol

S, VolS, Vol

5(I)25

13

14

16

13

0013

13

14

0

0029

OneTwoThfCC

OneTwollifCC

100

46100

100

100

56.Feedwater SG No. IMSSS

57-Feelwater SG No. 2MSSS

60-Downcomer Feedwater SG IMSSS

61-Downcoma Feedwata SG 2MSSS

66.B!owdown SG IMSSS

67-Biowdown SG 2MSSS

Butt Welds

Butt WeMs

Butt Welds8"x.719"

Butt Wclds8"x.719"

Butt WcMs

Butt Welds

SG-201-24"SG.202-24"SG-224-24"

SG-204-24"SG-205-24"SG-225-24"

SG-2004"SG-84"

SG-2034"SG-114"

SG.394"

8&484"

S, VolS, VolS, Vol

S, VolS, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, Vol

S, Vol

23

(2)

23

(2)

2(8)4

2(8)4

3(12)

3(9)

OncTwoThree

OneTwoThfCc

OneTwoThfCC

OneTwoThfCc

OneTwoThree

63

100100

100

64100100

36100

69100100

50100

530

531532

Mgoo(

47-Main Steam SG I West270'SSS

S<j<cepolcts SG-206-28" S, Vol 700

100

100

100

'SCIIEDULEDUNDER C$21ANDC$22

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A PALO VERDENUCLEARGENERATINGSTATION10 YEARXNTERVAL-'FWANIINATIONSUMMARY ASMKCLASS 2(RHR, ECCS, and CHR SYSTEMS)

TABLE 2-CPR

PAGE 3 OF 6

ASMEITEihfNO. ZOi4EWOhfPOi IENfOR~f IDENTIFICATION


TOTALMETHOD ITEMS 40 YR. 10 YR.

EXAMAMOUNTINSPECITOi I

PERIOD

(40 YR.)10 YK REhfARKS AND

RELIEF REQUESPI

511

512

88-East Wrap, 91-West WrapSl

89-East Wrap,92-West WrapShutdown Cooling Suction

20" x 0500"

Butt Welds10" x 036$ "

12" x 0375"

20" x 0500"

Butt Welds10" x 0250""10"x 0365"

12" x 0250"

16" x 0312"

18" x 0312"

SI-70SI-72

SI-172SI-71

81-72SI-73SI-70SI-71

SI-72SI-70

SI-173SI-239

SI-38SI-2

SI-I94SI-241Sl-173

SI-I94SI-241

S, VolS, Vol

S, VolS, Vol

S, VolS, VolS, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, VolS, Vol

S, VolS, Vol

14

12

(52)42

15

6ll8

(63)ll10

410

810

2

(16)2I

(33)65

OneTwoThfee

OneTwoTlffee

"Oue Weld perline

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A PALO VERDENUCUBLRGENE<BATINGSI'ATION10 Y1<~INTERVAL-Fi&ANIINATIONSUMMARY psME CZ,pSS g(RIBS, ECCS, nnd CHR SYSIEMS)

TABLE 2~PAGE 4 OF 6

ASMEITEMNO. ZONE~hIPOi60'OR SYSIEM

DESCRIPTIONLINENO., OR

IDENTIFICATIOiN = SERIALNO.NDE TOTAL

METHOD ITEMS 40 YR. 10 YR.

EXAMAMOUNTINSPECTION

PERIOD

(40 YR.)10 YIL REMARKSAM)

RELIEF REQUESTS

511

512

90-Bast Wrap, 93-West WrapSI

94.A Train Misc. Pipe Chases 4h

88'ipe Tunnel,95-B Train Misc. Pipe Chases th

88'ipe TunnelSl

IOSContaiamcnt LPSI Train ASuction,101 ~tainmcnt LPSI Train B Suction

Inside Containment

Category C510 SystemsTotal

Butt Weldr8"x 0322"

10" x 0365"

24" x 0375"

Butt Welds10" x 0365"

18" x 0312"

20" x 0.500"

Butt Wclds10" x 0250""6"x 0280"

16" x 0312"

24" x 0375"

SI-134SI-89

SI-I34SI-89

SI-30SI-7

SI-89SI-134

SI-194SI-241

SI-70SI-72

SI-369SI-368

SI-241SI-194

SI-1SI-30

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

S, VolS, Vol

(24)22

5ll

(67)IO

9

IS15

10

5

(43)10

11

(627)

(12)II

(34)55

(22)5

9

(310)292829

OneTwoThree

OneTwoThree

OneTwo'IllfCC

(100)IO19

28

"One Weld per line.

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RELIEF REQUEST INDEX

Number ~Descri tion

Hydraulic and Mechanical Snubbers will be tested in accordance with PVNGSTechnical Specifications.

Withdrawn

Insulation will not be removed for visual examinations of welded or mechanicalattachments.

Level III Personnel will be recertified by examination every 5 years.

'ithdrawn

Withdrawn

Class 2 and 3 Systems Pressure Test (revised)

e,'ithdrawnSteam Generator Handhole Pressure Test

10. Deferral of First Interval Reactor Vessel Examinations

Reactor Head Vent System

12. Main Steam Nozzle Volumetric Examination

13. Reactor Vessel Head and Closure Head Weld Coverage

14. Class 1 Pressure Test Boundary

15. Miscellaneous Code Limited Examinations

16. Restricted Access Under Reactor Vessel For VT-2 Examination

Rev. 206-18-99

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Relief Request No. 7

Class 2 and 3 Systems Pressure Test (revised)

Code Class 2 and 3

Code Reference

Component Description Containment Penetrations

PVNGS Units 1

ASME Section XI, Division 1, 1980 Edition, Winter 1981Addenda, and IWC-2500, Table IWC-2500-1.

Examination Category C-H

Item Numbers C7.30 and C7.40

Requirement The System Pressure Test and System Hydrostatic Test requirementsof the 1980 Edition, Winter 1981 Addenda, IWC-2500, Table IWC-2500-1, Category C-H, All Pressure Retaining Components includeessentially all ASME Class 2 piping.

Alternate Utilize 10CFR50, Appendix J, Leak Rate Testing requirements andresults to satisfy the above ASME Section XI requirements for pipingsystems that pass through the containment wall. This would apply tothe following mechanical/piping penetrations:

P i & &. ~&t Ii N. &&ION. ~&t &I679

21222324

25A/828293031

32A333435363839

42A42842C

DWFPRDSlSlSlSIHCSlGAGAIA

HCNCNCHPHPHPHPssssss

055096259088130007030008149009002069007135137001002003004004007007

DWP-002FPP-006RDP-001SIP-002SIP-002SIP-001SIP-001HCP-001SIP-001

GAP-001GAP-001IAP-003HCP-001NCP-003NCP-003HPP-001HPP-001HPP-001HPP-001SSP-001SSP-001SSP-001

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J,i,

I

43444550515253

54A55A565758596061

62A62B62C67777879

CH 122CH 283CH 275PC 073PC 072GR 001Fuel Transfer TubeHC 006HC 004CP 005CP 007CL 001IA 080

WC 039WC 042HC 005CL 009CL 008SI 114SI 106CP 006CP 008

CHP-002CHP-003CHP-003PCP-001PCP-001GRP-001PCP-001HCP-001HCP-001CPP-001CPP-001CLP-001IAP-002

WCP-001WCP-001HCP-001CLP-001CLP-001SIP-002SIP-002CPP-001CPP-001

* = Non ASME

Basis ForRelief

The applicable containment piping penetrations are subjected to 10CFR 50, Appendix J, testing. This request for relief (without ASMEClass 2 lines) was originally accepted for the First Ten Year InspectionInterval in USNRC letter dated April 12, 1996, from W. H. Bateman toW. L. Stewart, "Evaluation of the First Ten Year Interval InspectionProgram Plan, Revision 1, and Associated Request for Relief for PaloVerde Nuclear Generating Station, Units 1, 2, and 3". This request forrelief has been revised to include ASME Class 2 piping systems andCode Case N-498-1 for the System Hydrostatic Test requirements. Inaddition, the alternatives of Code Case N-522, Pressure Testing ofContainment Penetration Piping, are being applied for those systemsnot classified ASME outside the containment isolation valves.

For all the listed penetrations, the proposed 10 CFR 50, Appendix J,Leak Rate Testing was conducted at peak calculated containmentpressure, utilizing procedures that willdetect the source and location ofthrough-wall leakage.

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Additional Code Case N-498 is listed as an acceptable case in Regulatory GuideInformation 1.147, Revision 11, and Code Case N-498-1 and Code Case N-522

are listed as acceptable cases in Regulatory Guide 1.147, Revision 12.

On October 28, 1998, Condition Report/Disposition Request (CRDR)number 9-8-1412 was written to address the additional conditionsimposed by NRC Safety Evaluation Report Docket Nos. STN-50-528,STN-50-529 and STN-50-530. It was determined that the condition toperform testing at the peak calculated containment pressure wassatisfied in procedure 73ST-9CL01, Containment Leakage Type "B"

and "C" Testing.

Also it was determined in the evaluation that the additional conditionimposed to perform Appendix J testing using test procedures that willdetect through-wall leakage's in the pipe segments being tested wasalso satisfied. In addition, clarification was added to procedure 73ST-9CL01 for how suspected pressure boundary leakage would beaddressed during performance of Appendix J testing.

Approval In accordance with 10 CFR 50.55a(a)(3)(i), relief is requested from thecode requirements on the basis that the proposed alternative wouldprovide an acceptable level of quality and safety.

1. ASME Section XI, Division 1,1980 Edition, Winter 1981 Addenda.2. ASME Code Case N-498.3. ASME Code Case N-498-1.4. ASME Code Case N-522.

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Steam Generator Handhole Pressure Test

Code Class

Code Reference

Component Description Steam Generators

PVNGS Units 1

ASME Section XI, Division 1, 1980 Edition, Winter 1981Addenda, IWA-5200 and IWC-5222.

Examination Category N/A

Item Numbers N/A

Status Approved

Requirement ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda, IWA-5200 and IWC-5220 require the performance of a Hydrostatic PressureTest (1.25 times the system design pressure) after repairs by welding.

AlternateTesting

In lieu of the Hydrostatic Pressure Test required by IWC- 5220, aSystem Inservice Pressure Test (normal operating pressure) per IWC-5221, will be performed.

Basis ForRelief

A detailed basis was provided under separate cover. The following is abrief summary:

~ The hydrostatic pressure test must be performed with the vesseldefueled due to testing prerequisites.

~ This would require an additional reactor reassembly.~ The reactor coolant pumps would be used to raise and maintain

temperatures in a precore type configuration at their upper designlimit, which would put additional stress on the RCPs.

~ All main steam safety valves and atmospheric dump valves wouldrequire removal and replacement with blind flanges.

~ Additional supports would be required due to filing the steam lineswith water.

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I

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f

Approval Approval granted in NRC letter dated April 8, 1993, from T. R. Quay toW. F. Conway, "Request for Relief from the ASME Code, Section XI,Hydrostatic Pressure Test Requirements".

References 1. ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda.

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Deferral of First Interval Reactor Vessel Examinations

Code Class

Code Reference

Component Description Reactor Vessel

PVNGS Units 1

ASME Section XI, Division 1, 1980 Edition, Winter 1981Addenda, IWA-2400, IWB-2410 and IWB-2500.

Examination Category B-A, B-D, B-N-1, B-N-2 and B-N-3

Item Numbers All

Status

Requirement

Approved

The required volumetric and visual examinations of the Reactor Vesselwelds and internals shall be completed during each successiveinspection interval in accordance with ASME Section XI, Division 1,1980 Edition, Winter 1981 Addenda, IWB-2410 and IWB-2500, TableIWB-2412-1. The Inspection Period specified may be decreased orextended by as much as 1 year to enable an inspection to coincide witha plant outage, within the limits of IWA-2400 (c).

AlternateTesting

Reactor Vessel Exams will be performed during the U1R8 Outage.

Basis ForRelief

Delay the First Ten Year Interval Reactor Vessel Exams scheduled forthe 7~ Refueling Outage to the 8~ Refueling Outage in Unit 1.

Reasons for this relief include:

~ The One Year Period Extension for Unit 1 ends 07/17/99 and theU1R8 Outage is scheduled from 10/02/99 to 11/08/99. This willdelaythe exams approximately 114 days at outage completion.

~ This delay would facilitate the Reactor Coolant Pump Shaftreplacements planned for U1R7.

~ The raising of the refuel pool water level for the vessel exams wouldadd approximately 8 days to the 7~ Refueling Outage.

~ There will be fewer critical maintenance activities during U1R8.~ This situation only impacts Unit 1 and does not effect the ISI

Program Plan for Units 2 and 3.

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AdditionalInformation

None

Approval Approval granted in NRC letter dated October 16, 1997 from W. H.Bateman to J. M. Levine, "Evaluation of Request for Deferral of theReactor Vessel Examinations First Ten-Year Inservice InspectionInterval (Relief Request No. 10) for the Palo Verde Nuclear GeneratingStation, Unit 1, TAC No. M99104".


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Reactor Head Vent System

Code Class

Code Reference

Examination Category

Item Numbers

1and2ASME Section XI, Division 1, 1980 Edition, 1981 Addenda,IWA-5200, IWB-5200 and IWC-5200.

B-P, C-H

B15.51 and C7.40

Component Description Pressure Retaining Components

PVNGS Units 1

Requirement ASME Section XI, Division 1, 1980 Edition, 1981 Addenda, IWA-5200,IWB-5200 and IWC-5200, Table IWB-2500-1, Table IWC-2500-1 andCode Case N-498, require the performance of a VT-2 Systems LeakageTest (Class 1) and a System Pressure Test (Class 2) at or near the endof the first inspection interval.

AlternateTesting

Defer the performance of the VT-2 System Leakage Test and SystemPressure Test Examinations of the ASME Class 1 and Class 2 ReactorHead Vent System lines to the first refueling outage of the second 10-year interval. In accordance with IWB-2412, the one-year periodextension for Unit 1 ends 07/17/99 and the U1R8 outage is scheduled

.from 10/02/99 to 11/08/99. This will delay the exams approximately 114days beyond the ASME Section XI allowable extension. The deferral ofthese exams will not be credited toward exams for the second interval.The affected portions of the vent lines are as follows:

RC RC-1448

RC-146

ASME Class System Line No.

1 RC RC-179

Line Size P&ID No. Valve No.

RCP-001 HV108to

HV109RCP-001 HV101,

HV102,HV103,HV105HV106

andHV109

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e Basis ForRelief

Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested from the coderequirements stated above on the basis that the proposed alternativewould provide an acceptable level of quality and safety.

PVNGS believes that deferring this examination provides an acceptablelevel of quality and safety for the following reasons.

Containment entries are made on no less than a quarterly basis forother plant maintenance. A general inspection for leakage is performedduring those entries per PVNG's procedure 40DP-9ZZ01, ContainmentEntry in Modes 1 Through 4. Furthermore, RCS pressure boundaryleakage is monitored by the control room staff in several additionalways.

1. Containment atmosphere particulate radioactivity monitoring.2. Containment atmosphere gaseous radioactivity monitoring.3. Containment relative humidity monitoring.4. Containment sump level rates of change and discharge monitoring.5. RCS water inventory balance measurements.

Technical Specification 3.4.14, RCS Operation Leakage, allows for only1 gpm unidentified leakage and no pressure boundary leakage. The firstthree methods provide continuous monitoring with alarms. Sump levelsare monitored every hour and the RCS water inventory balance isperformed every three days. Ifgreater than 1 gpm leakage is detected,the leakage must be reduced to within limits within four hours or be inMode 5 within 36 hours.

PVNGS believes that the system pressure monitoring and the severalmethods for detecting RCS leakage provide an adequate level of safetyto justify deferring the pressure test for 114 days. Additionally, theserequired examinations were successfully completed in Units 2 and 3without any abnormal indications noted.


PVNGS is asking for relief to defer the first interval examinations to thefirst refueling outage of the second interval. Due to a long refuelingoutage in Unit 1, Unit 2 has become the lead Unit for implementing theISI Program Plan. Prior to the end of Interval 1 for Unit 2, it wasdetermined that it would require plant evolutions outside of normaloperating practice to perform the required pressure test on the ReactorHead Vent System, so at that time, Relief Request No. 15 was writtenfor Unit 2.

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Subsequent re-evaluation indicated the examination could beaccomplished and the test was performed in Unit 3 during normal plantshutdown. Also, the test has been performed in Unit 2 during the 8~

Refueling and the required test for Unit 1 will be performed during the 8~

Refueling Outage. No remaining scheduled plant shut downs within thefirst inspection interval are scheduled for Unit 1.

Approval In accordance with 10 CFR 50.55a(a)(3)(i), relief is requested from thecode requirements on the basis that the proposed alternative wouldprovide an acceptable level of quality and safety.

References 1. ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda.2. ASME Code Case N-498.

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Code Class

Code Reference

Main Steam Nozzle Volumetric Examination

ASME Section XI, Division 1, 1980 Edition, 1981 Addenda,and IWC-2500.


Item Numbers

Component Description

PVNGS Units

C-B

C2.22

Steam Generator

All

Requirement ASME Section XI, Division 1, 1980 Edition, 1981 Addenda, IWC-2500and Table IWC-2500-1 require a volumetric examination of the nozzleinside radius area.

e AlternateTesting

Basis ForRelief

In lieu of the volumetric examination, a surface examination will beperformed on the nozzle inner radius selected for examination.

Due to the design of the PVNGS Steam Generator Main Steam Nozzlesthe volumetric examination is not possible.


The nozzles have a protrusion into the steam generator that makes itimpossible to examine volumetrically. A copy of the nozzle drawing isattached that illustrates these geometric conditions.

Approval In accordance with 10 CFR 50.55a(g)(5)(iv), PVNGS is requesting relieffrom conformance with the above code requirements which have beendetermined to be impractical.


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RELIEF REQUEST NO. 12 Cont'd

37.5"

4.25" ""

16"

Main Steam Nozzle Cross Section

(Typical)

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Reactor Vessel Head and Closure Head Weld Coverage

Code Class

Code Reference


Item Numbers


PVNGS Units

ASME Section XI, Division 1, 1980 Edition, Winter 1981Addenda, and IWB-2500.

B-A

B1.22

Reactor Vessel/ Closure Head

Requirement ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda, IWB-2500, Table IWB-2500-1, Category B-A requires the Meridional HeadWelds to be volumetrically examined for the accessible (Note 2) lengthof all welds.Notes: (2) Includes essentially 100% of the weld length.

AlternateTesting

The volumetric examinations of both the Closure Head and BottomHead Meridional welds will be examined to the extent possible. A sketchshowing scan limitations is attached for both areas. The total coverageis estimated to be 31% for the Closure Head welds and 20% for theBottom Head welds based upon past examinations.

Basis ForRelief

These examinations are both limited by physical constraints and currenttechnology. Previous exams performed in Unit 2 and Unit 3 confirm thecoverage listed above and the sketches attached attempt to depict eachlimitation.


The examinations of the Bottom Head Meridional welds are included inthe first ten-year interval Reactor Vessel exams and will be performedduring the 8" Refueling Outage in Unit 1. Deferral of these exams hasbeen approved in relief request number 10.

Approval In accordance with 10 CFR 50.55a(g)(5)(iv), PVNGS is requesting relieffrom conformance with the above code requirements which have beendetermined to be impractical, due to design and geometry limitations.


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Accessible Portion ofMERIDIONALWELD

0 0 00 0 0 000000000000

0 0 0crd0 0 0 0 0cro000 ~ ddt000060000t000 O 000odoeodoo r

0 0 r0000000 /0 0000000 0 0 0 00000000 0 0 0

0 0 0


CEDM Penetrations (97)

CLOSURE HEADTOP VIEW

.';. Suppoit

Skirt'ccessible

Portion ofMERIDIONALWELD


HEAD

Mgoo<

CLOSURE HEADSIDE VIEW

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LOWER VESSELASSEMBLY

SIDE VIEW

Accessible Portions ofMERIDIONALWELD

Flow Skirt~

ICI Penetrations (61) Typ.


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0 0 000 00 r0 0 0pr0 0 0 rppp rp p

rpp 000 0 00 0 0 0

Flow Skirt

ICI Penetrations

INSIDE VIEWLOOKINGDOWN

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Class 1 Pressure Test Boundary

Code Class

Code Reference


Item Numbers


PVNGS Units

ASME Section XI, Division 1, 1980 Edition, 1981 WinterAddenda, IWB-2500 and IWB-5200.

B-P

B15.11, B15.21, B15.31, B15.41, B15.51, B15.61, 8 B15.71.

ASME Class 1 ISI Program Items and Components

1

Requirement

Testing

ASME Section XI, Division 1, 1980 Edition, 1981 Winter Addenda, IWB-2500, IWB-5200, Table IWB-2500-1 and Code Case N-498 require theboundary for the end of interval pressure test be extended to all Class 1

boundaries. This includes the small portion of pipe between two Class 1

isolation valves or between a valve and blind flange.

Visual examinations performed during System Leakage Tests will beextended to include the small portion of pipe and downstream valve orblind flange. The first valve will not be opened. A list of these areas areas follows:

SystemCHCHCHCHCHCHCHRCRCRCRCRCRCRCRC

Line No.CH026CH024CH022CH020CH026CH520CH001RC091RC091RC089RC096RC062RC017RC099RC005

P8 ID No.CHP001CHP001CHP001CHP001CHP001CHP001CHP001CHP001CHP001RCP001RCP001RCP001RCP001RCP001CHP001

Valve Description1PCHNV8481PCHNV8491PCHNV8591PCHNV8601PRCNV7521CHEVM411PCHEV8531PRCEV0611PRCEV0631PRCEV3321PRCEV3331PRCEV0011PRCEV0621P RCEV0571PCHEV939

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RCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCRCSISISISISISISlSISISISISISISlSISISISISI

RC005RC005RC098RC069RC070RC060RC018RC179RC058RC020RC202RC201RC200RC203RC024RC024RC022RC112RC106RC118RC124SI207SI217SI223SI240SI248SI248SI248SI156SI156SI179SI175SI193SI225SI203SI199SI248SI221SI199SI240

CHP001CHP001RCP001RCP001RCP001RCP001RCP001RCP001RCP001RCP002RCP002RCP002RCP002RCP002RCP002RCP002RCP002RCP002RCP002RCP002RCP002SIP002SIP002SIP002SIP002SIP002SIP002SIP002SIP002SIP 002SIP002SIP002SIP 002SIP002SIP 002SIP 002SIP 002SIP002SIP 002SIP002

1PCHEVM421PCHEV0961PRCEV0561PRCEV2141PRCEV2151PRCEV3341PRCEV0581PRCEV3921PRCEV3351P RCNV7551PRCNV9021PRCNV9011PRCNV9001PRCNV9031PRCNVR301PRCNV7531PRCNV7541PRCNV8691PRCNV8681PRCNV8711PRCNV8701PSIEV8821PSIEV9741PSIEV8831PSIAV8921PSIAV9021PSIAV0551PSIAV9061PSIAV8801PSIAV8041PSIEV8811PSIEV8031PSI BV8791PSIEV9751PSIEV0641PSIBV0571PSIAV0561PSIEV0631PSIBV9071PSIAV801

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Basis ForRelief

The normal reactor pressure boundary is examined during eachrefueling outage and no pressure boundary leakage has been noted.Currently these valves are independently verified closed prior to plantstart-up and are not manipulated during any procedure guided plantevolutions while at power.


PVNGS does not cycle these valves at NOP/NOT because it increasesthe opportunity to experience an incident where a valve will not reseat.This can be due to several mechanisms; foreign material moving intothe seating surface; stem failure while opening or closing; packingshifting; or valve binding. The opportunity for a packing leak could alsopresent itself, with the added challenge of normal RCS pressure behindit. Cycling of these valves and the resulting compensatory actions dueto a leak can easily result in leakage and a forced unit shutdown orcooldown. Current operating procedures require these valves to remainclosed with no exceptions. Valves that need to be operated arespecifically identified to be manipulated only in mode 5 (to prevent RCPseal damage).

The subject piping segments represent vent or drain piping,instrumentation, etc. and are 1" or less in diameter; generally less than12" in length. These piping segments have no active safety function andhave no effect on the operational readiness of the plant.




Miscellaneous Code Limited Examinations

Code Class 183Code Reference ASME Section XI, Division 1, 1980 Edition, Winter 1981

Addenda, IWB-2500 and IWF-2500.

Examination Category B-H, F-A, F-B 8 F-C

Item Numbers B8.20, F1.XX, F2.XX and F3.XX.

Component Description 1. Pressurizer Skirt Weld (Item P5-1)

2. Spray Pond Piping Supports

PVNGS Units

Requirement 1. ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda,IWB-2500, Table IWB-2500-1 requires 100 percent surfaceexamination of items unless otherwise noted in the code.

AlternateTesting

2. ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda,IWF-2500, Table IWF-2500-1 requires 100 percent visualexamination of items unless otherwise noted in the code.

1. A volumetric examination was performed to augment the surfaceexamination, however it was also limited to scans from the skirt sideof the weld only. Both examination techniques were applied to theweld from the outside surface of the pressurizer skirt.

2. The examination of the Spray Pond (Ultimate Heat Sink) pipingsupports was performed underwater, utilizing visually trained andcertified SCUBA divers. This was done in lieu of draining the pondsand cleaning the algae layer off all the welds.

Basis ForRelief

1. Limitations were noted for the Pressurizer Skirt weld due mainly tothe design. The inside surface area of the Pressurizer Skirt isconsidered inaccessible due to the pressurizer heaters,drain/instrumentation lines, and insulation.

2. Due to the environment in the spray ponds, a deposited layer coversa majority of the examination area. A random sampling of weldswere cleaned to reveal any abnormal conditions.

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1. The attached sketch identifies the limitations for both volumetric andsurface exams. It should be noted that the ASME Code requireseither volumetric or surface examinations be performed asapplicable.

2. Cleaning of all the welds was impractical, because this would cloudthe water, making the visual inspection impossible. Ifduring theexaminations, any abnormal indications such as bent, missing orbroken components were discovered, the support would be cleanedto enable a detailed examination of the welds.



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PRESSURIZERLOWER VESSEL ASSEMBLY

Skirt to Vessel Welds

12 Holes 6.00" Dia.

Support Skirt

Pressurizer Heaters (36) Typ.

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Restricted Access Under Reactor Vessel For VT-2 Examination

Code Class

Code Reference


Item Numbers


PVNGS Units

ASME Section XI, Division 1, 1980 Edition, Winter 1981Addenda, IWB-5210 and IWB-2500.

B-P

B15.50 and B15.51

Reactor Vessel

Requirement ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda, IWB-5210 and IWB-2500, Table IWB-2500-1, require that Category B-Pcomponents be VT-2 examined at a test pressure not less than thenominal operation pressure associated with 100 percent rated reactorpower.

AlternateTesting

PVNGS will conduct a VT-2 examination on all portions of the reactorvessel, which are accessible during Mode 3, without endangeringpersonnel from undue heat or radiation exposure.

However, in lieu of performing VT-2 exams in areas that are hazardousto personnel, PVNGS will monitor for reactor vessel leakage by the useof leakage detection methods provided in the design and operation ofthe plant.

Basis ForRelief

Pursuant to 10 CFR 50.55a (g)(5)(iv) relief is requested on the basisthat conformance with the code requirement is impractical. Specifically,relief is requested from the requirement to visually inspect the entirereactor vessel while pressurized to the pressure associated with 100percent rated reactor power as required by IWB-5210.

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The requirement to perform a VT-2 examination of the reactor vessel isto detect leakage of the vessel. Because the walls of the ReactorVessel are essentially vertical, the code allows the examination to belimited to the lowest elevation where leakage will accumulate [IWA-5242(a)]. In addition, the code requires that the surrounding areas includingfloor areas be inspected for evidence of leakage [IWA-5242 (b)].

PVNGS cannot comply with this code requirement to perform thisinspection at Mode 3 because of extreme temperature and very highradiation areas.

Temperatures under the vessel during Mode 3 reach approximately 500degrees Fahrenheit. In addition, the exams require personnel to accessareas under the vessel where radiation fields are between 2 to 12 Remper hour.

Accessing the bottom of the reactor vessel while it is depressurized toassess leakage which has accumulated is possible, but the reactorvessel at PVNGS is constructed in such a way that leakage which wouldaccumulate at the bottom of the insulation around the vessel or on thefloor cannot be distinguished from leakage from other sources such asleakage from the pool seals.

While direct visual examination may detect gross leakage, moresensitive methods of detecting leakage from the reactor vessel areavailable, as discussed bellow, which do not endanger plant personnel.


Reactor coolant system (RCS) pressure boundary leakage is monitoredby the control room staff in several different ways:

1. Monitoring of the space between the double 0-ring seal on thereactor vessel closure.

2. Containment atmosphere particulate radioactivity monitoring.3. Containment atmosphere gaseous radioactivity monitoring.4. Containment relative humidity monitoring.5. Containment sump level rates of change and discharge monitoring.6. RCS water inventory balance measurements.

Technical Specification 3.4.14, RCS Operation Leakage, allows for only1 gpm unidentified leakage and no pressure boundary leakage. The firstfour methods provide continuous monitoring with alarms. Sump levelsare monitored every hour and the RCS water inventory balance isPerformed every three days. Ifgreater than 1 gpm leakage is detected,the leakage must be reduced to within limits within four hours or be inMode 5 within 36 hours.

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PVNGS believes that the RCS leakage monitoring performed by thecontrol room staff satisfies the requirement for detection of RCSpressure boundary leakage from the reactor vessel. Performing a VT-2exam on the bottom of the reactor vessel would not provide betterinformation than is possible by other means and does not warrant therisk of injury to plant personnel from extreme heat and very highradiation areas.

Approval Relief is requested in accordance with 10 CFR 50.55a(g)(5)(iv). Thisexamination is impractical due to extreme temperatures and very highradiation in certain areas requiring personnel occupancy in order tocomplete this exam.

References ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda.

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