ML20211D636

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Responds to 821109 Memo Re NRR & Region V Views on Facility Design Verification Program.Concurs W/Recipient View That Expanded Phases I & II Program Will Assure That Deficiencies in Design Program of Util Will Be Identified
ML20211D636
Person / Time
Site: 05000000, Diablo Canyon
Issue date: 11/09/1982
From: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20209B155 List:
References
FOIA-86-151 NUDOCS 8610220242
Download: ML20211D636 (1)


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NUCLEAR REGULATORY COMMISSION

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WALNUT CRE E K, CALIFORNIA 94596

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NOV 09 F9%

MEMORANDUM'FOR:

H. R. Denton, Director, Office of Nuclear Reactor Regulation FROM:

R. H. Engelken,~ Regional Administrator

SUBJECT:

NRR AND RV VIEWS ON THE DIABLO CANYON DESIGN VERIFICATION PROGRAM

~

This is in reference to your memorandum of November 9, 1982, on this same subject. My memorandum of September 15, 1982 was, in part, intended to inform your office of QA findings by R. F. Reedy and PG&E, to provide early identification of possible implications of these findings.

I concur with your view that the expanded Phase I and Phase II program, as proposed in SECY 82-414 will assure that any broad programmatic deficiencies in the design program of PG&E and its contractors will be identified.

The other comments included in my memorandum relate to the administrative execution of the~ program and are being addressed by the IDVP contractor and the staff. The resolution of these comments will not affect our mutual view expressed in the SECY 82-414 paper.

R. H. Engelken Regional Administrator cc:

J. L. Crews j

T. W. Bishop D. G. Eisenhut

\\)C E. Schierling

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NUCLEAR REGULATORY COMMISSION E

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. GCLAETED wc s, v October 21, 1982

'82 00T 21 P3:3 E Ei Ti:.iM '

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To Participants in the Diablo Canyon Proceedings

.ERANCH

SUBJECT:

COMMENTS ON STAFF BRIEFING SEnv0 OCT 211982 The Commission held an open meeting on Wednesday, October 20, 1982 to receive the NRC staff's briefing on the proposed scope of Phase II of the Independent Design Verification Program (IDVP) for Diablo Canyon Nuclear Power Plant.

The NRC staff, Pacific Gas and Electric Company, and participants in the IDVP had met in Bethesda, Maryland on Tuesday, October 19, 1982 to discuss the same subject.

Copies of the transcripts of these two meetings and SECY-82-414, transmitting the staff recommendation presently before the Commission, are hereby provided for your information.

Parties have been notified by the Office of the General Counsel of the opportunity to address the C:= mission in a meeting tentatively scheduled for Wednesday, November 10, 1982 in response to the staff briefing.

We will inform you of the details regarding the upcoming meeting as socn as they are finalized.

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Sincerely, A>o'

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Samu 1 J. Chilk Sec tary of the Commiss.,,,,..

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Transcript of 10/20/82 Commission Meecing Transcript of 10/19/82 IDVP Meeting e

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SECY-82-414

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SERTICI LIST

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Philip A. Crane, Jn., Esq.

John F. Wolf, Esq.

Pacific Gas & Electric Co= piny

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77 Beale Street, Roon 3127 San Francisco, California 94106 o

Mr. Glenn O. Bright l

Ato=ic Safety and Licensing Board U.S. Nuclear Regulatory Co-4 ssion.

Washing:en, D.C.

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Janice E. Kerr, Esq.

Dr. Jerry R. Kline California Public Utilities Cc-4ssion kto ic Safe:v and Licensing Board 5246 State' Building San Francisco,' California 94102

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'W.S. Nuclear Regulatory Co==ission Washington, D.C.

20555 Mrs. Raye Fleming 1920 Mattie Road 76.cca s S'afety and L.c,ensing Appeal Board Moore, Esc.

Chairtsn Ato.ic S Shell Beach, California 93440 U.S. Nuclear Regulatofy Co=nissien Washingten. D.C.

20555 Mr. Frederick Eissler

. Scenic Shoreline Preservation Conference, Inc.

Dr. W. Reef Jchnsen 4623 More Mesa Drive Atenic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Co-4 ssion Santa Barbara, California i3105 Washington, D.C.

2055.5 Mrs. Sandra A. Silver 1760 Alisal Street nr. 1chn H. Buck San Luis Obispo, California 93401 Atc=ic Safety and Licensing Appeal. Board C. S. Nuclear Regulatory Cc-4 ssion Washing:cn, D.C.

20555 Mr. Gordon A. Silver 1760 Alisal Street Ccunsel for NRC Staff San Luis Obispo, California 93 Cffice of the Executive Legal Director U.S. Nuclear Regula cry Co=nission Washing:ca, D. C.

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John R; Phill'ps, Esq.

Td.rkpatrick, Lockhart, Eill, Cen:er for Law in the Public interest Christopher & Phillips

.10951 West Pico Boulevard, 3rd Floor 1900 F.. Street, N.W.

Los Angeles, California 90054 Washington, D.C.

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.gDavidF.Fleischaker,Esq.

P.O_._ 3'ex317 8 Oklaho=a City, Ok.

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'Fr. Carl Neiburger Snell & Wilmer San Luis Obispo Telegrzn-Tribune 3100 Valley Center P.O. Box 112 Phoenix,. ) icona 85073 San Luis Obispo, California 93406 F.r. James 0. Schuyler Fr. James Eanchett Euclear Projects Engineer Public Affairs Officer, Region V Pacific Gas & Electric Co=pany U.S. Nuclear Regulatory Co==ission 77 seale Street 1990 N. California Boulevard, Suite 20 San Francisco, California 94106 Walnut Creek, California 94596

' g' g3ruce Norton, Esq.

Dian Grueneich, Esq.

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3 3216 North Tnird Street, Suite 202 California Inergy Co H ssion Phoenix, Irizona 85012 1111 Howe Avenue, P.S 27 Sacramento, California 95825' ym. W. Andrev Baldein, Esq..

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124 Soear Legal Affairs Secretary to the Governe:

San Francisco, Calife:nia 94105 State Capitol. Building

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DESCRIPTI0N 0F EOI/0I 0VERLAP

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THERE ARE 33 OPEN ITEMS (0I) IDENTIFIED BY THE INTERNAL TECHNICAL PROGRAM (ITP) AND 14 CLASS A OR B ERROR /CPEN ITEMS (E0I) IDENTIFIED BY THE INDEPENDENT DESIGN VERIFICATION PROGRAM (IDVP).

HOWEVER. ONE CANNOT SIMPLY ADD THESE TWO NUMBERS TOGETHER TO COME UP WITH THE TOTAL NUMBER OF ERRORS SINCE THERE ARE E0Is AND OIs WHICH OVERLAP AND/0R ENVELOPE ONE ANOTHER.

SLICE 1 CEMONSTRATES HCW THESE E0Is AND OIs INTERRELATE WITH EACH OTHER.

THE BASIC REASONS FOR THESE OIs AND E0Is TO OVERLAP AND/0R ENVELOP ARE T-E 70LLOUING:

1.

CIs WERE IDENTIFIED BY THE ITP AS GENERIC PROBLEMS WHERE AS E0Is WERE IDENTIFIED BY THE IDVP AS SPECIFIC PROBLEMS.

LATER THE IDVP REDEFINED THE E0Is AS GENERIC PROBLEMS BY LUMPING SOME OF THE SPECIFIC E0Is INTO A SINGLE E0I.

E.

THE INDEPENDENT NATURE OF THE ITP AND THE IDVP HAS FURTHER A:CENTUATED THE OVERLAP IN IDENTIFIED E0Is AND OIs. SINCE THE ITF AND THE IDVP REVIEWS HAVE OCCURRED SEPARATELY AND WITH LIMITED INTERACTION.

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Pila 3[ LJI)VP l HkORS NIAl Akl LLA131FlBLA QPdl F

SECTION Ill ITP PilASE I ptir1BER DESCRIPIION CLASSIFICATION EJJLAL REPORl FCI #D!,2 IIPWARD VER1ICAl RESTRAlilT RE0'D FOR SllPPORT 585-23R A

2.2.3

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EDI #9819 REVISE RIGIDITY OF f1AIN ANNUNCIATOR CABINET A OR B 2.3 FOI #9G3 EVALUATE ACCEPTABILITY OF'0APS FOR SUPPORT 595-32R B

2.2.3 E0I #983 RACEWAY SUPPORT REEVALUATION (INCLUDES FILES 910 AND 930)

A 2. 4. 11.

E01 #1002 TilREE SUPPLY FANS QUALIFIED WITil INCORRECT SPECTRA B

NONE E0I #1003 HVAC DUCT SUPPORT SEISMIC REVIEW (INCLUDES FILE 1077)

A OR B 2.5 E0I #1013 TEST SPECTRA FAILED TO ENVELOP OUALIFACTION SPECTRA FOR ONE B

NONE GROUP 0F ELEC. EQUIP.

E0I #10181 CONTAINMENT SEISMIC REVIEW A CR B 2.1.1-(INCLUDES FILES 977 AND 1009)

E0I #1022 INTAKE STRUCTURE SEISMIC REVIEW A OR B 2.1.5 INCLUDES FILES 967 AND 988)

E0I #1026 TURBINE BUILDINO SEISMIC REVIEW A OR B 2.1.4 (INCLUDES FILES 982, 984. 989, 1010, 1025)

E0I #1069 TWO VALVES WERE UNSUPPORTED A

2.2.1 E0I #1092 FUEL HANLING BUILDING SEISMIC REEVALUATION A

2.1.3 (INCLUDES 990, 991, 1027, 1079 AND 1091)

E01 #1097 AUXILIARY BUILDING SEISMIC REEVALUATION A OR 8 2.1.2 (INCLUDES FILES 920, 986, 1029, 1070, 1093)

E0I #1098 PIPING SEISMIC REEVALUATION A OR B 2.2 (INCLUDES FILES 961, 1021, 1058, 1059, 1060, 110t!)

PAGE 1 0F 1

PilASI J Par CPI N liiflu IMAI Al:1 LLAASTF1ED_A OftB SECTION IN ITP PilASE I JM1B[R DESf I'IPI 1ci!

CLASSJf_ICATION EllAL REE0BI 01 til SD: val Vf S flGuil l D Il1 CORRECTLY A

2.2.1 2.2.2-OI fl2 AUXILIARY BillLDIliG SPECTRA FRROR

'A 2.1.2 OI l!3 CACLWAY UEIGilTS IJUDERESTIf1ATFD A OR B 2.4 OI #81 FOURTY Sf1ALL BORE SUPPORTS RE0'D VERTICAL RESTRAINTS A

2.2.4 OI fl5 CNE ACTIVE VALVE LIST NOT REVIEWED A OR B 2.2.1 OI #6 OVER SPAN IN SMALL BORE PIPINE A

2.2.2 2.2.4 OI #7 TWO TilERt1AL PIPING CALCS l10 DELED SUPPORTS INCORRECTLY A OR 8 2.2.1 J

2.2.2 OI #8 USE OF CONTAINMENT SPECTRA FOR SOME PIPING AND RACEWAYS A OR B 2.2.1 i

f1AY BE INAPPLICABLE.

2.2.2 l

OI #9 ONE PIPE SUPPORT WITH FEWER LUGS thall REQUIRED.

A 2.2.3 2.2.4 OI #10 INAPPROPRIATE SPECTRA USED FOR SEVEN PIPING ANALYSIS A

2.2.1' i

01 #11 DYNAMIC PROPERTIES REVISED FOR PLANT VENT B

NONE l

OI #12 ESTIt1ATED MASSES IN CONTAINMENT INTERIOR DYNAMIC MODEL B

2.1.1 l

OI #13 DISCREPAllCIES BETWEEN ASBUILT PIPING CONFIGURATION AND A

2.2.1 IS0 METRICS 2.2.2 i

GI #15 LACK OF DOCUt1EllTATION FOR SOME Sf1ALL BORE PIPING A OR B 2.2.4 CI #16 ERROR IN SEISMIC COEFFICIENT USED FOR PIPE SUPPORT DESIGN A OR B 2.2.4 PAGE 1 0F 2

PilASf _. I PGf4 LPil: lll f a; 111/,1 Al;L CLASSiflED A !)R B SECTI0fl Ill

'ITP PilASE I fill!1l1LR P6081['l10D C_LASSIFICATION f_INAL REPORT 0] #17 CEISillC AliCl!CR 11CVLf1Efii I Ff fCTS NOI Al)DRESULD FOR SOME L ARGE A'OR B-2.2.1 BORE PIPIllG I

DI #18 REVIEW CF SPLCTRA USED TO CUALIFY AllXII.IARY CALTUATER SYSTEM A

2.2.1 ECUIPMEllT 2.3 2.4 i

2.5 OI #19 PCLAR CRAtlE 2D NCN-LINEAR Af!ALYSIS MAY l10T DE CONSERVATIVE A OR B SECTION TO DE ADDED OI #20 DOME SERVICE CRAllE ANALYSIS USED POLAR CRANE 3D NON-LINEAR A OR B SECTION ANALYSIS TO BE i

ADDED l

OI #21 INCORRECT SPECTRA USED FOR QUALIFICATION OF SOME HVAC A OR B 2.5.3 DUCT SUPPORTS OI #22 TWO ITEMS OF EQUIPMENT MODELED AS RIGID FOR PIPING A

2.2.1 ANALYSIS 2.2.2 0I #29 EFFECT OF INSULATION NOT CONSIDERED FOR PIPE SUPPORT A OR B 2.2.1 SPACING TABLES 2.2.2 OI #31 REVIEW 0F WELDED PIPE ATTACHMENTS FOR MAIN STEAM AND A OR B 2.2.3 j

FEEDWATER ANCHORS OI #32 FUEL HAflDLING BUILDING SEISMIC REANALYSIS A

2.1. 3' OI #33 GENERIC HVAC DUCT SUPPORT DOES NOT SATISFY APPLICABLE A OR B 2.5.4 CRITERIA PAGE 2 0F 2 w

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E011003 E011013 HVAC DUCT SUPPORT E01949 SHAKE TESTED l

E011002 l

SEISMIC REVIEW MAIN EQUIPMENT SUPPLY l ANNUNCIATOR I

SPECTRA i

FANS OVERLAP BETWEEP CABINET RIGIDITY SPECTRA PHASE I

/oI 0133 EOIS AND OIS THAL f

s c SUPPORT ARE CLASSIFIED i l DUCT I

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SUPPORT GENERIC A OR B 1

SPECTRA DESIGN E011097 AUXlLfARY BUILDING SEISMIC REEVALUATION FROM E011014 INDICATES SEISMIC INPUT E011026 TURBINE BUILDING (SPECTRA)

SEISMIC REVIEW l

E011092 FUEL HANDLING BLOG SEISMIC REEVALUATION 0132 E011098 FUEL PIPING SEISMIC HANDLING REEVALUATION BLOG SEISMIC REANALYSIS 01 E01 E01983 CON 0Ulf 1,2,4,5, R ACEWAY SUPPORT

& PIPING ll 932 l

I 6,7,9,10.

963 13.15,16,17, REEVALUATION SPECTRA 1069 22,29,31 E011022 INTAKE STRUCTU RE 01 3 SEISMIC REVIEW I

RACEWAY I

f E011014 CONTAINMENT SEISMIC REVIEW l

01 21 & 0133 ESTIMATED I

MASSES 01 18 AUX SALT Ol 19 WATE R SYS I

POLAR EQUIPMENT I

CRANE I

SPECTRA ANALYSIS i

VENT OYNAMIC 0120 R0PERTIES DOME I

SERVICE CRANE ANALYSIS

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Tuferim Tu.kktca.l Reperf 5 ku3Lb 2.&A kap. k w

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INTERIM TECHNICAL REPORTS (ITR)

ITRs ARE ISSUED BY IDVP ON PROGRAMMATIC ASPECTS COMPLETED TECHNICAL ACTIVITIES REVIEW 0F PG&E CORRECTIVE ACTIONS ITRs ISSUED AS OF OCTOBER 5. 1982 1.

ADDITIONAL VERIFICATION AND SAMPLING 2.

EVALUATION OF QA PROGRAM AND IMPLEMENTATION REVIEWS 3.

TANKS 4.

SHAKE TABLE TESTING 5.

DESIGN CHAIN

6. ' AUXILIARY BUILDING 7.

ELECTRICAL-RACEWAY SUPPORTS 8.

VERIFICATION PROGRAM FOR PG&E CORRECTIVE ACTION APPROXIMATELY 25 ADDITIONAL ITR's TO BE ISSUED FOR PHASE I 1

STAFF PERFORMS SELECTIVE AUDIT OF ITR's AT IDVP 0FFICES (10/20/82 ENCL 1)

BACKUP SLIDE 1

IDVP - PHASE I Cf. DESIGN REVIEW (RFR)

PHASE I RESULTS REPORTED IN ITR-2:

DEFICIENCIES IN QA CONTROLS FOR CERTAIN DESIGN ACTIVITIES NO ADDITIONAL SAMPLING AND VERIFICATION BEYOND ITR-1 RECOMMENDATIONS l

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I (10/20/82 ENCL. 6)

BACKUP SLIDE 2

'JDVP - PHASE II DA DESIGN REVIEW (RFR)

PHASE II DESIGN QA AUDIT APPROACH:

IF SATISFACTORY QA PROGRAM EVIDENT THEN ROUTINE QA ~ AUDIT IF SAllSFACTORY.0A PROGRAM NOT EVIDENT THEN AUDIT OFlla PRACTICES AGAINST IDVP CRITERIA PHASE II QA AUDIT OF PG8E AND'4 SERVICE CONTRACTORS (PRELIMINARY RUSULTS)

SATISFACTORY DESIGN QA PROGRAM 2

QA DEFICIENCIES IN DESIGN INPUTS, DESIGN 1 (PGSE)

ANALYSES AND CHANGE CONTROL NO ESTABLISHED DESIGN QA PROGRAfi, ADEQUATE 1-DESIGN CONTROL PRACTICES LACK OF EVIDENCE OF QA PROGRAM AND QA 1

PRACTICES REGION V COMMENTS:

SCOPE AND APPROACH WITH REFERENCE TO NRR LETTER (10/20/82 ENCL. 6)

BACKUP SLIDE 3

PGRE LOOK BACK OF 0A PROGRAMS PHASE I PHASE II CONTRACTORS REVIEWED 6

17 SATISFACTORY QA PROGRAMS 2

7 0A PROGRAM IMPLEMENTATION 2

4 i

DEFICIENCIES NO FORMAL QA PROGRAM 2

6 REGION V PERFORMED AUDIT OF RESULTS OF "LOOK BACK":

RECOMMENDS THAT IDVP USE RESULTS FOR DECISION ON ADDITIONAL VERIFICATION (10/20/82 ENCL, 5)

BACKUP SLIDE 4 f

-___.,-,____.______,_.__.,._,__,,..,_,,-y__,._,,..,

4 BNL ANALYSIS STAFF REQUESTED BNL INDEPENDENT ANALYSIS OF CONTAINMENT ANNULUS STRUCTURE AND SELECTED PIPING SYSTEMS (FALL 1981)

BNL USED PG&E INFORMATION FOR INPUT BNL EMPLOYED DIFFERENT SEISMIC ANALYSIS MODEL BNL REPORT COMPLETED JUNE 1982 STAFF IDENTIFIED SEVERAL ITEf1S FOR FURTHER EXPLORATION AND ASSESSMENT AS TO GENERIC IMPLICATIONS STAFF REQUESTED IDVP TO CONSIDER BNL REPORT IN THEIR DECISI0il MAKING PROCESS AND TO PROVIDE THEIR VEIWS, BNL REPORT DISCUSSED AT MEETING Oli 27 JULY (10/20/82 ENCL. 2)

BACKUP SLIDE 5 4

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_,.. _-. _ _ _ _.. _, _ _, - _. - -. - _ ~ _ _ _ _ _ _ _ _., - - - -. _ _... - -, -......, -..,,. - - -

BNL ANALYSIS (STAFF COMMENTS)

ITEMS IDENTIFIED BY STAFF IN BNL REPORT FOR FURTHER EXPLORATION AND ASSESSMENT AS TO GENERIC IMPLICATIONS DISTRIBUTION OF MASSES ASSUMPTION FOR BEAM TO COLUMN JOINT CONSISTENCY OF STRUCTURAL CONNECTIONS IN HOSGRI REPORT AND IN ORIGINAL ANALYSIS RESPONSE SPECTRUM SM0OTHING TECHNIQUES DESIGN VERSUS AS-BUILT DIMENSIONS MODELING OF BENDS IN PIPING ANALYSIS COMPUTATION OF PIPING SUPPORT FORCES (10/20/82 ENCL. 2) i BACKUP SLIDE 6 i

_. ~. _ _ _ _ _. _ _, _ _. _ _. _ _ _ _. _ _...

l m

PGRE CORRECTIVE ACTION PROGRAM (CAP)

PG&E INTERNAL TECHNICAL PROGRAM (ITP) INCLUDES RECENTLY (AUGUST) INITIATED CAP CAP INCLUDES COMPLETE REVIEW 0F ALL MAJOR SAFETY-RELATED STRUCTURES

- ALL LARGE BORE SAFETY-RELATED PIPING 4

SMALL BORE PIPING SYSTEMS AS NECESSARY IDVP WILL REVIEW RESULTS WITH RESPECT TO ITS NEED FOR ADDITIONAL VERIFICATION AND SAMPLING (ITR-1)

(10/20/82 ENCL. 7)

BACKUP SLIDE 7 1

4 i

I I

I

NRC INSPECTIONS AND AUDITS REGION V/NRR/IE AUDIT ITP AND IDVP ACTIVITIES AT PG&E AND IDVP 0FFICES l

REGION V INSPECTS MODIFICATIONS AT SITE AUDITS IDENTIFIED ISSUES IN SEISMIC ANALYSIS OF AUXILIARY BUILDING, INTAKE STRUCTURE, CERTAIN PIPING EQUIPMENT AND COMPONENTS.

ISSUES INCORPORATED IN AND TO BE RESOLVED BY IDVP AND ITP 1

l (10/20/82 ENCL. 3) l BACKUP SLIDE 8 I

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SEISMIC ASSUMPTIONS HYPOTHETICAL EARTHQUAKES FOR DIABLO CANYON SEISMIC DESIGN:

(A)

DESIGN EARTHQUAKE (DE):

g2bPN (B)

DOUBLE DESIGN EARTHQUAKE (DDE):

g4bPMG (C)

HOSGRI EARTHQUAKE:

{GGDE. 1.60 ANALYSES RESULT IN DIFFERENCES IN DESIGN SPECTRA, ACCELERATION TIME HISTORIES, DAMPING VALUES, MODELS, ACCEPTANCE CRITERIA.

HOSGRI EARTHQUAKE NOT LIMITING FOR ALL ANALYSES OF STRUCTURES, SYSTEMS AND COMPONENTS IDVP PHASE I WITH RESPECT TO HOSGRI EARTHQUAKE PGaE PERFORMED (THROUGH URS/BLUME) REVIEW 0F HOSGRI-RELATED CIVIL-STRUCUTRAL ANALYSIS WITH RESPECT TO HOSGRI CRITERIA (BIR REPORT)

PG&E EFFORI IN ITP INCLUDES DE AND DDE CONSIDERATIONS IDVP PHASE 11 WILL INCLUDE NON-HOSGRI ANALYSES (10/20/82)

BACK!)P SLIDE 9 f

o BRIEFING ON PROPOSED PHASE II DESIGN VERIFICATION PROGRAM DIABLO CANYON UNIT 1 EISENHUT X27672 10/20/82

J OUTLINE PURPOSE COMMISSION REQUEST RE:

PHASE II APPROVAL 3ACKGROUND 11/19/81 ORDER (PHASE I) 11/19/81 LETTER (PHASE II)

DESCRIPTION OF PROGRAM NOW UNDERWAY RESULTS TO DATE PHASE-I PHASE II CONSTRUCTION QA MODIFICATION TO DATE FACTORS INFLUENCING STAFF RECOMMENDATION i

PGE PROPOSED PHASE II PROGRAM PLAN CONTRACTORS CONCLUSIONS STAFF PROPOSAL RECOMMENDATION RE:

PHASE 11 10/20/82 SLIDE 1

BACKGROUND NOVEMBER 19. 1981 NRC REQUIREMENTS PHASE I COMMISSION ORDER SUSPENDED FUEL LOADING AND LOW POWER TESTING LICENSE REQUIRED 1.

RESULTS OF AN IDVP' FOR ALL SEISMIC SERVICE-RELATED.

CONTRACTS PRIOR TO JUNE 1978 PHASE II STAFF LETTER ACTIVITIES REQUIRED PRIOR TO DECISION REGARDING POWER LEVELS AB0VE 5%

2.

IDVP FOR NON-SEISMIC SERVICE RELAlED CONTRACTS PRIOR TO JUNE 1978 3.

IDVP FOR PGE INTERNAL QA 4.

IDVP FOR ALL SERVICE RELATED CONTRACTS POST JANUARY 1978 NOTE:

BOTH PHASE I AND PHASE II WERE DEFINED AS NECESSARY, BUT NOT NECESSARILY SUFFICIENT, FOR THE APPROPRIATE APPROVALS.

  • IDVP = INDEPENDENT DESIGN VERIFICATION PROGRAM i

10/20/82 SLIDE 2

IDVP/,PGAE ACilVIT_lL5 I

f I't.%I inistinq PilASE_,1 (solid lines) friteria 4

Analysis 1.

IDVP for all SSER prior Design to June 78 k

1r IDVP PIIASI I t

A TES + RLCA

  • irR

- Sampling

- Check Calc.

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- Indep. Calc.

l 1

- As-Builts i

1r 1r I

l E0!'s RESULTS i

1

- ITR's i

- E01 Resolution

- Basis Cause For each of above 1

co s-

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[2, E2

~

'"*"IC* I*DI' C3 b0 a.

Basic Cause Report i

I"E2 Final Report b.

PG4E Effectiveness LN oo i

22 na y

T Conclusion l

c.

Schedule for PGAE NRC j

Modifications Iffectiveness Report j

tt..! i e i,.. t i nn L tici fie l e-i

i IDVP/PGLE AETIVlTILS i

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l'r, ', i I.istin.

1 PHASE I (solid lines) ieiterla Desiern 4

Analysis 1.

IDVP for all SSER prior to June 78 1r' I'llA5[ 11 (dotted lines)

IDVP PHA*I I

    • Ni A' I II*

7.

IllVP for NS$R prior to A

TES + RLCA + l.FR

  • + sWI L e

3.

IDVP for PG&E internal QA

- Sampling 4

IUVP for all SR post

- Check Calc.

~ Indep. Calc.

- As-Builts 1r 1r E0l's RESULTS

- ITR's

- E01 Resolution

- Basis Cause For each of above pg ennic. Impi, s.

Basic Cause Report

-N$y Final Report b.

PG8E Effectiveness x

U u co T

Conclusion CD N O

c.

Schedule for Pr.AE NRC Modifications Effectiveness Report it.,,l i f i,,, t i,in t, he,f o 1 os

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IDVP for all SSER prior Desiesn to June 78 U'

U ntAst 11 (dotted lines) q IDVP PHAsi i

  • ' hiASE !!' CONSTRUCTION:

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- Sampling 4.

IDVP for all SR post

- Check Calc.

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OTHER (dashed lines)

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E0!'s RESULTS

- ITR's i

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- E01 Resolution

- Basis Cause for each of above i

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- Final Report m

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PG&E Effectiveness Q

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Conclusion e

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PRELIf11 NARY RESULTS PHASE I (HOSGRI SEISMIC; PRE 1978)

ASSOCIATED EFFORT NEARLY COMPLETE THOROUGH PROGRAM EXPECl IDVP TO IDENTIFY PROBLEMS EXPECT PROBLEMS TO BE RESOLVED (T0 IDVP SATISFACTION)

IDVP:

FINDINGS ARE BROAD IN APPLICABILIlY: NARROW IN SCOPE GOOD UNDERSTAllDING OF ERRORS ABOUT 200 E0lS: 13 ARE "A/B" EFFORT HAS DONE JOB 0F IDENTIFYING ERRORS SCHEDULE FOR IDVP (PHASE I)

TECHillCAL REPORTS COMPLETED (11/17)

COMPLETE ADDITIONAL VERIFICATION (12/15)

FINAL REPORT (1/25/83)

PRELIMINARY'RESULTS (CONTINUED)

-PHASE II UNDERTAKEN PRIOR TO NRC APPROVAL PRINCIPALLY. CHECKS 3 SYSTEMS AND 2-3 ANALYTICAL CHECKS 39 TECHNICAL CONCERNS (ANTICIPATED 55-60)

TO DATE, 5 "A/B"; 7 POTENTIAL "A/B" FEWERS E0IS THAN PHASE I; BUT FRACTION SIGNIFICANT IS LARGER SIGNIFICANT PROGRESS TO DATE IDVP:

NO COMMON TRENDS OF ERRORS TO DATE MANY INDIVIDUAL QUESTIONS SCHEDULE-MOST IDVP TECHNICAL REPORTS TO BE ISSUED NOVEMBER - DECEMBER, 1982 FINAL PHASE 11 REPORT - 1/25/83 CONSTRUCTION QA VOLUNTERRED BY PGSE NO EXPLICIT FINDINGS TO DICTATE NEED IMPLICIT 00ESTIONS RE:

OVERALL 0A IDVP SCHEDULE INTERIM REPORT 11/22 FINAL REPORT 12/15 10/20/82 SLIDE 4B

MODIFICATIONS TO DATE DESCRIPTION PIPE SUPPORTS 257 OTHER SUPPORTS 43 ANNULUS STRUCTURE 38 OTHER-6 ADDITIONAL MODS ARE EXPECTED CHARACTERIZATION OF MODIFICATIONS (SEE SLIDES 6A, 6B, AND 6C)

P f;

10/20/82 SLIDE 5

IATERAL RACEMAY. SUPPORTS i

i Raceway Supports 1

This slide shows modifications to a raceway support type S102. The vertical braces did not meet the acceptance criteria (allowable stress) for revised seismic loads. The angle braces (S-6) were insta.lled to stiffen the vertical members. They can be shown to have sufficient capability, through inelastic analysis, to perform their function and pose no threat to safety. However, it is very time consuning to demonstrate this by analysis, therefore modifications l

were carried out. 16 supports have been revised as shown in item 7 Table 1, Attachment 1 of PG8E's September 15, 1982 submittal.

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i SMALL BORE PIPE SUPPORTS CONTADHDIT ANNUIUS t

2155-23 Small bore support 2155-23, located in the Containment annulus, i

supports lines J 013 and 3143. Line 1013, a non-safety related line, i

is the primary water supply to the Reactor Coolant Pump 1-1 seal I

stand pipe. Line 3143, is the check valve leak test header for the Reactor Coolant System Hot Leg Safety Injection lines. This is a typical example of a support that was modified to provide sway struts in place of rod hangers in order to provide a bidirectional seismic restraint.

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Support 12-45SL is a mechanical snubber located in the annulus area f

of the Containment Building. It restrains line 1357, the Component j

i Cooling Water Return Header from the Reacter Coolant Pump Thermal r

Barrier Labyrinth Seals. The review for the reoriented-revised l

l Hosgri spectra showed that the diagonal brace, which was a structural j

l angle, did not meet stress criteria. The angle was replaced by the j

tube steel shown in the slide.

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FACTORS IflFLUEllCIf!G STAFF RECOMMENDATI0fS

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PHASE I RESULTS TO DATE INTERIM TECHNICAL REPORT FINDINGS l

J BNL lilDEPENDENT ANALYSIS STAFF AUDITS / INSPECTIONS PHASE II RESULTS TO DATE

.PRELll11 NARY RFR RESULTS IDVP ASSESSMENT OF PG8E IflTERilAL QA PGEE ACTIONS-PGEE CORRECTIVE ACTION PROGRAI1 BIR REPORT PGEE "LOOK BACK" REPORT PRE 1978'VERSUS POST 1978 IDVP AUDIT OF CONSTRUCTION QA AS BUILT VERIFICATI0il i

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10/20/82 SLIJE 7 l

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O PROPOSED IDVP PHASE II PROGRAM PLAN RESPONSE TO NOVEMBER 19, 1981 STAFF LETTER PROPOSED IDVP PHASE II PLAN INCLUDES:

SYSTEM SAMPLE 1.

AFW SYSTEM 2.

CONTROL ROOM VENTILATION AND PRESSURIZATION SYSTEM 3.

SAFETY RELATED PORTION OF 4160 V ELECTRIC DISTRIBUTION SYSTEM DESIGN CHAINS QA AUDITS (PROGRAMS AND IMPLEMENTATION)

ADDITIONAL SAMPLING VERIFICATION. IF REQUIRED STAFF FINDINGS THE PROPOSED PHASE II PROGRAM PROVIDES ADEQUATE IDENTIFICATION AilD EVALUATION OF SIGNIFICANT DESIGN ERRORS IN THE SELECTED SAMPLE AND AN ADEQUATE UNDERSTANDING OF THE ROOT CAUSE.

10/20/82 SLIDE 8

IDVP PHASE II CONTRACTORS PROPOSED TELEDYNE ENGINEERING SERVICES (TES) - PROGRAM MANAGER R. L. CLOUD ASSOCIATES (RLCA)

- SEISMIC, MECHANICAL, STRUCTURAL STONE & WEBSTER ENGINEERING CORP.

- SAFETY SYSTEMS

- CONSTRUCTION QA R. F. REEDY INC. (RFR)

- QA AND DESIGN CONTROL IECHNICAL QUALIFICATIONS:

SWEC FOUND FULLY QUALIFIED FOR PHASE II OTHER EVALUATED FOR PHASE I AND FOUND ACCEPTABLE INDEPENDENCE OF CONTRACTOR ORGANIZATIONS:

FROM PG&E:

DETERMINED DURING PHASE I, INCLUDING S't.'EC FROM BECHTEL:

NO OWNERSHIP BY IDVP CONTRACTORS, VERY LIMITED BUSINESS CONNECTIONS INDEPENDENCE OF INDIVIDUALS:

EVALUATED PER OTTINGER LETTER CRITERIA ONE CONCERN - REEDY ASSOCIATES ARE EX-BECHTEL N0 OTHER CONFLICTS 10/20/82 SLIDE 9

CONCLUSIONS MAJOR, THOROUGH PROGRAM UNDERWAY PG8E INTERNAL EFFORTS G0 WELL BEYOND NOVEMBER 19 REQUIREMENTS PROGRAM SHOULD FIND ERRORS AND RESOLVE ANY ISSUES ERRORS FOUND TO DATE NOT MAJOR FROM SAFETY STANDPOINT-MANY MODIFICATIONS, BUT GENERALLY MINOR PHASE II PROGRAM CLOSELY LINKED WITH PHASE I SCOPE OF VERIFICATION REQUIRED BEFORE FL DECISION HAS EXPANDED f

e 10/20/82 SLIDE 10 1

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PHASE I (COMMISSION ORDER)

1. IDgP,fF g g PRIOR TO B.

PHASE 11 (NRR 1ETTER)

2. IDVP FOR NSSR PRIOR TO 6/78 1R
3. IDVP FOR PG&E INTERNAL QA IR
4. IDVP FOR ALL SR POST 1/78 IR C.

DIllER

5. QA PROGRAM FOR ITP IR

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6. CONSTRUCTION QA IR

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7. AS-BUILT WALK-DOWN IR

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8. MODS. AS NECESSARY

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9. PG&E/W INTERFACE EVAL.
10. VE.RIFY HOSGRI SPECTRA L SSR (NON-IR

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11. IDVP FOR A'fl0R TO 6/78)

HOSGRI, P NOMERCLATURE:

O:

AS ORIGINALLY REQUIRED, NOVEMBER 19, 1981 ACTIVITY COMPLETE SSR:

SEISMIC SERVICE-RELATED CONTRACTS NSSR:

NON-SEISillC SERVICE RELATED CONTRACTS SR:

SERVICE-RELATED CONTRACTS IR:

INTERIM REPORT, DEMONSTRATING EFFORT SUBSTANTIALLY COMPLETE 10/20/82 l

SLIDE 11

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i RECOMMENDATION l

0 APPROVE PHASE 11 PROGRAM-0 APPROVE REDIRECTION OF PHASE l/

PHASE 11 INTERFACE t

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10/20/82 SLIDE 12 i

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The Comissioners Fro":

l!illiam J. Dircks, Executive Director for Operations 1.. JECT:

DI A3LC CMiYO!! DESIGV VERIFICATI0'! PROGRR4 -

Prt/SE II recon"D,0ATIO! S P"P U :

In accerc:nce with the Corr.ission's re::uest (C9!UA-92 r,)

cf July 27, IM.2, this r. aper provides the staff recomendations re? arcing Phase II of the Diatlo Canyon Independent Design Verification Progren (ID\\D) and its relationship to the ongoing Phase I program.

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ria tec Septerter 2.4, 1932, we orovided you uith a Stotus.encrt of oncoing activities associated c

with tbc verification of the seismic design of Diablo Car. yon Unit 1.

Te re' crardu'-noted that fincings fron Phase I of the ITVP anc ctber recent developrents my influence tree staff's cccclusions with regard to the Phasc II Program

  • >lan which was suhritted to the hhC for correval on June H, IC42. ile have continued to pursue those natters ar.c

%ve develo::cr. our recc.rmenoations with regard to the P ro.r ra- :'l an. The steff findines and recomencations are viscussed telow.

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"e have su 'rarized in Figure 1 the elenents of the Orcar

?M letter of I:everter 19, 1981. The original requirerents nea.;ed to suuport a fuel-loao/lcu-oc.er (FL/LP) decision t6ve recene known as Phase I whereas iters originally rer.eiriry co'cletion before a cecision regarcing perer levcir creater than M vere definec as Phase II.

It is irc.ortant to nnte that although they were cefined as such at t'ie tim, bcth the Phase I Orcer and toc Phase II Ictter ecr.nowled.?ed that an ex;'ansion of either or bcth efforts ay be necessary. 'In this context, the staff exarined t5c overall fincings to date and a number of recent develeprents to determine if any occificaticns to the cricinally cefined scope of Phase I and Phase II need be race.

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.- Overall Findincs to Date As of Septenber 24, 1982, the IDVP had identified 199 technical concerns requiring resolution. A number of these have subsequently been resolved and 13 have been classified as "A/B" errors. These are errors in which design criteria or operating limits of safety-related equipnent could have been exceeded and physical redifications, changes in onerating procedures, eore realistic calculations, or retesting are required to bring the plant into conformance with the original design. These technical concerns can be summarized as follows:

Fully resolved:

147 Errors:

3 (3 A/B errors)

No design criteria or operating limits exceeded:

144.

Revicw. continuing:

52 by PG&E:

2E (9 A/P errors) by IDVP:

24 (1 A/B errors)

Total 199 (13 A/B errors)

Furthernore, PG&E has identified 33 concerns within their Internal Technical Progran (ITP). Six have been reselved and 27 concerns have been classified as A/P errors.

These errors are not directly additive because there exists scre overlep between the ICVP and ITP errors.

As cf Septerber 15,1992, PG4E had corpleted 344 rodifica-tinns as follo.es:

"o'.i f i ca ti on s Pine supports 257 Other supecrts a3 i,nnulus structure 39 Otner 6

Total 344 It should be noted that not all A/B errors will necessiate r:odifications and that a single error may result in a nurber of modifications. In addition so.Te of these rodifications, nade to cate, were a result of the errors f ro.m either, or both, the IDVP and ITP and soce were rcdifications undertal:en by PC&E even though they believe the error could have been shown acceptable by detailed calculations, omer p sva=wr >

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3-During a meeting on Septenber 1,1982 the staff discussed the modifications made to that date with PG&E. With respect to those codifications, PG8E stated that:

1.

!'ost nodifications flow from their Internal Technical Program and not the IDYP.

2.

All modifications are to restore margins or to neet design criteria.

3.

Nothing has been found which would have prevented a systen, structure or component from perfonaing its e

intended safety function in the event of the postulated Hosgri earthquake.

The staff has exanined nodifications ccroleted to cate and has concluded that they are generally minor in nature; while we have not done a detailed evaluation of each, we believe that had the nodifications not been made, the facility would likely have withstood an earthcuake without unacceptable conseocences.

Staff Evaluation of Recent Develoonents During recent nonths, a number of siqnificant developments and findings have occurred which influenced our recommendations regarcing the scope of the Phase II Program. Plan as proposed.

For your reference, we have graphically summarized in Figure 2 the functioning of Phase I of the IDVP, the functioning of Phase If of the IDVP, and various activities undertaken by PGSE and their relationship to the IDVP. The cevelopments exanined by the staff were briefly discussed in our Septenber 24, 15C2 r;ercrandun to you ano are further discussed in enclosures to this nenorandun. The de'.elopnents include:

1.

IOVP Phase I Results:

a.

The identification of a larger tnan originally expected nutber of errors or cpen itens (E0Is) from both the IDVP and the PGe.E ITP as discusseo above. A list of these errors and open itens were previced to you as attachnents to the September 24, 1932 recorandur.

b.

The issuance of eight Interim Tecnnical Reports (ITR),

as of October 5,1982, including ITR 1, which suggested that the sample for the reverification program cust be -

expanced, and ITR 2, which identified deficiencies in Qt, contrels for certain design e.ctivities. The staff evaluations of ITP.s 1 through 5 are provided in Enclosure 1.

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.- c.

The results froo an indepencent analysis nerforced by the staff's contractor, Brookhaven National Laboratory, raised a number of seismic concerns regarding PG&E original seisnic analysis of the containment annulus structure. BKL developed a three dimensional vertical nodel and identified concerns regarding the distributed masses, nodeling of joints, as-built dimension variations, spectra-smoothing techniques, modeling of piping bends and calculated piping support forces used in PGLE's original analysis. These concerns were forwarded to TES for consideration of their generic implications by the IDVP. PGAE has indicated that a majority of these concerns had been separately icentified by the IDVP and/nr PGAE. The staff will audit the IDVP resolution of these concerns. Enclosure 2 provides additional discussion.

d.

Region V inspection of the ongoing activities identified a nunber of open inspection issues. These issues include verificatinn that the seis-ic analysis model adequately characteri:es the seisnte responses of the Auxiliary Duilding, Intake Structure and various ecuipment and components. Sone of these issues had been previously icentified by the IDVP.

These issues are being closed out by both Pegion Y and fiRR personnel via their consideration in the in the ITP and IDVP. A suonary of these issues is provided in Enclosure 3.

e.

The original Phase I IDVP proposed, and the NRC acceoted, to include a reevaluation of the Hosgri analyses only. The remaining seismic analyses will be examined by the IDVP in the Phase II progran.

The staff discussion of this action is provided in Enclosure 4.

2.

19VP Phase II P.esults:

a.

Preliminary results from the R. F. Reecy Phase II QA audit indicated that there exist deficiencies in the QA controls of the PG&E design progran and of certain of their contractors.

b.

The results from the PGLE initiated QA audits of tneir in-house design activities and their safety-related service contractors are summarized in Enclosure 5.

The PG8E findings are consistent with the creliminary results fron the P. F. P.cedy Phase II CA audit (discussed in a. above). Region V attended the u-..,.q,

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-s-i the Region's concents on both of these activities is provided as Enclosure 6.

The staff has also forwarded these comments to TES for their consideration in the IDVP, in particular with respect to the scope of the audit as compared to the scope delineated in the NP.R letter of November 19, 1981.

3.

PGLE Acticns:

a.

The establishment by the PG&E/Bechtel Project Tean of a corrective action program that includes a seismic reevaluation enconpassing all safety-related structures, systems, and components. The scope of the effort is discussed in nore detail in Enclosure 7.

The IDVP will audit and consider the results of tre corrective action progran.

b.

The completion of todifications, as necessary, to restore the "as-built" plant to the "as-designed" condition. A listing of nodifications made to date, and a listing of anticipated additional rodifications, are included in Enclosure 8.

c.

The undertaking of a review, to deterrine the adecuacy of the seismic evaluation originally done by Blune, called the Blume Internal Report (DIR). Speci fically, the EIR includes an internal technical review, conducted by Blume, of civil / structural work perforned with particular attention to the work for the Hesrei evaluation in the 1977-1978 time frame. The esults of this review have been cocumented by Blune in a report and subnitted to the staff in early October 1982.

d.

The recognition by PG&E that there is probably no step-uise distinction between pre-1978 and post-1978 activities as was assumed in the isseance of the Concission Orcer and the URR Letter of hevenber 19, 1981.

e.

The decision by PGLE to uncertake a reevaluation cf construction QA proposed as part the IDVP.

While PG6E has stated that they have no reason to cuestion the quality of construction, they also stated that such a progran is neeced to renove any doubts. The IDVP has recently submitted a progran plan fer review of these activities. Region V has reviewed this croposed progran and found it to l

be satisfactory and consistent with previous Region y recommendations.

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The decision by PG&E to undertake a walkdown of as-built safety-related structures, systems, and components to increase confidence that cs-built conditions are identified and evaluated.

g.

The PG8E proposal for staged licensing is discussed in Enclosure 9.

This proposal is to complete, prior to fuel loading, the review, analysis, and modifications for those systems required for fuel load. The remainder of the systers will be examined subsequently. The staff has reviewed the PGLE proposal and concurs in their identification -

of systens with sone additions to the " supportive" list of equipnent.

4 IDVP/ITP Interface:

The IDVP has preserted plans to incluce the results of the expanded PG&E activities as inputs to the IDVP progran. This proposal is included in the Figure 2 flow chart.

Procosed Phase 11 Procram With regard to the contractors for Phase II of the IDVP, PGSE has proposed to retain Telecyne Engineering Services (TES) as the IDVP progran nanager. The principal subcontractors to TES are Robert L. Cloud Associates (RLCA), R. F. Peedy, l

Inc. (P.FR), and Stone A Uebster Engineering Company (SWEC).

The staff has examined the financial independence of the Phase II contractors fro.m both PG3E and Bechtel in addition l

to the independence of individual enployees assigned to the IDVP. The criteria used by the staff in its evaluation are the sane as those used in the Phase I evaluation. The staff also has reviewed the technical cualifications of the IDVP contractors. Erclosure 10 surrarizes the staff review l

and our findings, detemining that the contractors are l

technically cualified and are indepenuent.

The adecuacy of the Phase II Progran Plan was reviewed l

by the staff against the requirenents of our Hovember 19, l

1981 letter. Enclosure 11 describes the proposed progran and presents the staff findings on that progran.

00!:CLUSIONS:

Based on cur review of the proposed Diablo Canyon Phase II IDVP, the status and results.o,f other ongoing activities, as discussed above, and consideration of comments of the intervening parties to this proceeding, we have reached the following conclusions:

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i 1.

With respect to the anount of reevaluation activities required prior to any decision regarding fuel-load / low-power, we have concluded that, in addition to the require-ments of the November 19, 1981 Order. review and evaluation efforts for Phase II activities should be sufficiently complete to provide confidence that no major deficiencies exist. We therefore require that an interin report on Phase II, summarizing the IDVP conclusions and results to date, be sub:sitted prior to the FL/LP decision.

He recognize that certain plant modifications will likely not be needed prior to fuel loaoing, and accordingly we conclude that selected modifications could be ceferred until af ter fuel load. Similarly, we recocnize that coroletion of the Phase II program and other activities proposed by the IOVP and PG&E to provice additional assurance that the plant is built in accordance with the application, need not be completed prior to a fuel-loac/ low-power decision. Figure 3 summarizes the staff's proposal.

2. %'ith respect to the competence of the contractors proposed by PG&E project to carry out the Independent Design Verification Program, we conclude that the necessary experience and technical skills are being provided.

3.

Uith respect to the independence of the contractors proposed we conclude that the independence of the IDVP individuals are acceptable in view of those independence criteria provided in the Comnission's FeDruary 1,1982 responses to Congressmen Dingell and Ottinger.

4 In recognition of the expanded DGLE Program, we believe it is appropriate that the ongoing IDVP alter its approach to incluce a saraling of all of PGSE's efforts to gain overall conficence in that reverification effort.

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.- REC 0;"'E!$ AT10"S: That the Cc:nission:

1.

Accrove the Phase II Program Plan and contractors as nocified by the staff conclusions in Enclosure 11.

2.

Acorove the redirection of the Phase I/ Phase II division to require that the Phase II review / evaluation efforts be sufficiently conpleted, as identified in Figure 3, prior to a fuel-load / low-power decision.

P1111am J. Dircks Executive Director for Operations

Enclosures:

  • s stated "TE: Co.r-ission ccments should be provided directly to the' Off-f ce of the Secretary by c.o.b.

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. ggCU0ATI0!is: That the Comission:

1.

Approve the Phase II Program Plan and contractors as roodified by the staff conclusions in Enclosure 11.

2.

Ap_ prove the redirection of the Phase I/ Phase II division to require that the Phase II review / evaluation efforts be sufficiently completed, as identified in Figure 3 prior to a fuel-load / low-power dec1sion.

i Hilliam J. Dircks Fxecutive Director for Operations N!vsere>:

A, st.ited

'.C E: Ccmission corrents should be provided directly to tho Office of the Secretary by c.o.b.

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IDVP for all SSER prior Design to June 78 I f' IDVP PHASE I J L TES + RLCA + I;fR

- Sampling

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i

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E0l's RESULTS

- ITR's

- E01 Resolution

- Basis Cause for each of above

- Generic. Imp 1.

a.

Basic Cause Report

- final Report b.

PG&E Effectiveness 1 r T

Conclusion c.

Schedule for PG&E NRC Modifications Effectiveness Report Modification Schedules 4

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Fan Cooler Weld 3

This poor photo shows modifications to the support welds on fan cooler No.1-3.

Originally, the base plate was anchored by welds on two sides. For the modification, the two welds were increased in size and a weld was added on the 3rd side.

(The 4th side is inaccessible). This modification involved only one of 19 supports on fan cooler No.1-3.

The modification was due to small installation variations of welds between a column foot and its corresponding embedded plate not being identical for all five fan coolers.

(PG&E September 15, 1982 Submittal,, Table 1, item 2.)

1 073?A/00:0A

hsfraw zut Tabw3 Supperi Tube Support 7

This slide shows a support for instrument tubing associated with a test flow orifice (FE 980) in the safety injection line to RCS Loop 3 hot leg and a test flow orifice (FE 926) for a boron injection line. Thc support is located in the center of the l

slide and is constructed of "Superstrut" which is a trade name i

for stock structural steel shapes, connectors, and brackets, which are routinely used for supporting such items and instrument tubing and electrical conduits and cable trays. The modification consisted of replacing one type of "Superstrut" angle brace with another, stronger connection to meet seismic acceptance criteria. Neither of these supports affected tubing associated with safety related instrumentation. However, they have been modified for consistency reasons only. These modifications are typical of other tubing support modifications which may be required due to spectra revisions.

(PG&E Septeober 15, 1982 subaittal, Attachment 1, Table 1, item 4. )

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i J739A/033JA t

'a 1-12-45SL Support 12-45SL is a mechanical snubber located in the annulus area of the Containaent Building.

It restrains line 1357, the Component Cooling Water Return Header from the Reactor Coolant Pump Tneraal Barrier Labyrinth Seals. The review for the reoriented-revised Hosgri spectra snowed that the diagonal Drace, which was a structural angle, did not meet stress c ri teri a.

The angle was replaced by the tube steel shown in the slide.

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No, i Ot ABLO C ANYON P G & E CO.

ORAWIN3 NUMBER P E v.

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6. n e c 0493iO3B
g... _.,12-105SL Support 12-105SL is a snubber restraining line 404, the letdown froa the regenerative heat exchanger to the letdown heat exchanger.

It is located inside the Containment.

There are two slides of this support. Slide l shows a closeup of three 3

snubbers, the rear-aost one being 12-105SL. The second slide shows an overall view of the frame to which 12-105SL and several other snubbers and l

spring supports are attached.

L When the DE piping analysis was revised due to a previous mistake in spectra selection, the load on this snubber increased, exceeding the allowaole load. Also, when the frame was analyzed, the restrained t

direction movements due to the DE loads were greater than our criteria allowed.

Tne snubber a PSA-1/4 pre-NF, was replaced with an PSA-l/4 NF and some frame members were reinforced.

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12-1395L Support 12-159SL !.s a mechanical snubber located in the Containment annulus. It seismically restrains line 1043, the Steam Generator 1-4 Blowdown Tane, header. When the seismic piping analysis for line 1043 was performed with the reoriented-revised Hosgri spectra, it was decided to add this snubber to reduce the Hosgri movements of the pipe to meet internal criteria by limiting the pipe deflections, even though the piping was not seismically overstressed and did meet code requirements.

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12-1595L Support 12-1595L is a mechanical snubber located in the Containment annulus.

It seismically restrains line 1043, the Steam Generator 1-4 Blowdown Tank header. When the seismic piping analysis for line 1043 was performed with the reoriented-revised Hosgri spectra, it was decided to add this snubber to reduce the Hosgri movements of the pipe to meet internal criteria, even though the piping was not seismically overstressed.

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?,:tacnnent 1, Table 2 Type 3 J7 3 ?.V J 03]'

l 39-24A l

Support 39-24A is located inside the Containment Building. It supports lines 2319 and 3289. These are the Component Cocling Water Return from Reactor Vessel Support Cooler 1-2 and the Component Cooling Water Supply to Reactor Vessel Support Coolers 1-1 'and 1-2, respectively.

During the review for the revised-reoriented Hosgri annulus spectra, it c

l was found that for the piping anchor on line 2319 a structural weld did not meet criteria for the corrected Hosgri loads. Additional plates and welds were added, to the lower pipe shown in the slide, to qualify this support.

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PGZ Septender 15, 1902 Subaittal Attachaent I, Taole 2 Type 1 l

JI334003GA i

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l 39-24A Support 39-24A is located inside the Containment Building. It supports lines 2319 and 3289. These are the Component Cooling Water Return from Reactor. Vessel Support Cooler 1-2 and the Component i

Cooling Water Supply to Reactor Vessel Support Coolers 1-1 and 1-2, respectively.

i During the review for the reoriented-revised Hosgri annulus spectra, I

it was found that for the piping anchor on line 2319 a structural weld did not meet stress criteria for the corrected Hosgri loads, since the we.ld was made to withstand a lesser load. Additional plates and welds were added to the piping in the region of this weld (the lower pipe shown in the slide) to qualify this support.

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PJ52 September 15, 1982 Submittal l, Table 2

[

Type 1 i

L t

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39-24A 1

i Support 39-24A is ated inside the Containment Building.

It supports lines These are the Component Cooling Water Return from React Vesse Support Cooler 1-2 &nd the Component Cooling Water Supply to Reactor Vessel Support Ccolers

'-l and 1-2, respectively.

During the review for the i t' was f at the pip did-for the and a

, to the lower pipe shown in e si e, to qua is support.

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p(A PG&E September 15, 1982 Suomittal Attachment ', Table 2 Type 1 l

0739A/0030A

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'0-55R Support 40-55R, which is located inside the Containment Building is a rigid restraint supporting lines 3289 and 3290, the Component Cooling Water supply and return lines from the reactor vessel support coolers l-1 and 1-2 respectively. When this support was reviewed for the reoriented-revised Hosdri spectra, it was found that the anchor bolts l

were overloaded due to possible lever prying effect at the base plate, and did not meet stress criteria. For line 3290, at the right side of the slide, it was found that an inadequate gap existed in one i

horizontal direction (N-S) and an excessive gap in the other norizontal direction (E-W).

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baseplate anchor bolts, a shim plate to reduce the excessive gap and a flange of structural member was cut to create an adequate gap for the pipe movements in the unrestrained direction.

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reoriented-revised Hosgri spectra, it was found that the anchor bolts were overloaded per criteria. For line 329C, at the right side of the slide, it was found that an inadequate gap existed in one horizontal direction and an excessive gap in the other horizontal direction. The modification consisted of adding stiffners to the base plate at the top of the slide, a shio plate to reduce the excessive gap and a flange of structural member 1

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42-12R Support 42-12R originally supported 6 lines: 316, 317, 318, 321, 322 and 323. These lines are the component cooling water supply and return to the Containment Fan Coolers 1-1,1-2 and 1-3.

The top four lines were supported vertically only and the bottom 2 lines were i

supported axially along the line using lugs as well as supported i

vertically.

i The support did not meet natural frequency criteria in the restrained axial direction, so that its ability to withstand the DE and DDE cannot be assured. Also, the structural member used to support the 2 lower lines was overstressed per criteria for the DE and DDE loads.

The modification consisted of breaking the existing frame into two separate supports. The new support,42-82R, as seen in the lower i

portion of the slide now supports the lower 2 lines.

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The top four lines were and the bottom 2 lines were supported The modification consisted of breaking the existing frame into two separate supports. The new support,42-82R, as seen in the lower portion of the slide now supports the lower 2 lines, i

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l 42 12R I

Support 42-12R originally supportt:d 6 lines: 316, 317, 318, 321, 322 and j

323. These lines are the component cooling water supply and return to the Containment Fan Coolers 1-1.1-2 and 1-3.

The top four lines were supported vertically only and the botton 2 lines were supported axially as well as vertically.

1 The support did not meet natural frequency criteria in the restrained j

di rec ti on. Also, lhe structural member used to support the 2 lower lines i

was overstressed per criteria for the DE and DDE loads.

i Tne uodification consisted of creaking the existing frame into two l

separate supports.

The new support,42-82R, as seen in the lower portion of the slide now supports the lower 2 lines.

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36S-12V This support, 36S-12V, is ou line 118 and is located in the Auxiliary Building. Line 118 is the outlet dfrom Residual Heat Exchanger 1-1.

'inen the seismic piping analysis for line 118 was performed with the valve modeling corrected, the new seismic movement exceeded the range i

of the spring can, so that a spring can which can tolerate the new movement had to be added. Further, because the new lateral loads exceeded anchor bolt allowables, the baseplate had to have stiffeners added. The new spring can is shown at the very top center of the I

slide and the modified baseplate is shown behind valve HCV-638 near the bottom of the slide.

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56S-12V This support, 565-12V, is on line 118 and is located in the Auxiliary Building. Line 118 is the outlet from Residual Heat Exchanger 1-1.

When, the seismic piping analysis for line 118 was performed with the valve eli corrected, and Th is shown at the very top center of -

the slide and the modi ase s shown behind valve HCV-638 near the bottom of the slide.

"--fT

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PG&E September 15, 1982 Submittal. Table 2 Type 1 & 2 1

0739A/0030A

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When the seismic piping analysis for line 118 was performed with the valve nodeling corrected, the new seismic movecent exceeded the range of the spring can and the base plate had to have stiffeners added because of the new lateral loads. The new spring can is shown at the very top center of the slide and the modified base plate is shown behind valve HCV-638 near the botton of the slide.

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5 565-37A Support 565-37A, located in the Auxiliary building is an anchor on line 3849 which is the recirculation path to the Reactor Coolant System Cold Legs from Safety Injection Pump 1-1.

When a previous mistake in spectra selection was corrected, the Hosgri loads on this support increased. This increase caused the anchor bolt loads to exceed allowables on the base plates for the two braces. The base plate shown in the slide was reworked by adding the bolt shown between the stiffener plates and *enoving the 4 I

l small bolts near the attachment point of the brace. The other base plate, not shown, required the addition of stiffener plates only.

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>8S-27V Support 38S-27V is a variable spring support located in the Auxiliary Building. It serves as a deadload support on line 265, the discharge line from Containment Spray Pump 1-2.

This spring can, shown at the center of the slide, had its preload adjusted to reduce the piping deadload stress, so that internal criteria for minimizing stress are met.

The analysis which was performed previously for the stress did not consider all fluid conditions and underestimated possible stress.

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It serves as a deadload support on line 265, the discharge line froa Containment Spray Pump 1-2.

This spring can, shown at the center of the slide, had its preload adjusted to reduce the piping deadload stress to meet internal criteria.

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C+*f & 3-4GY 40-55R t 40-55R which is located inside the Containment Building is a supporting lines 3289 and 3290, the Component Cooling upp return lines froa the reactor vessel support coolers 1-1 and 1-2 re ectivel When this upport was reviewed for it was found that the a 3290, at the ri ht side o it was found tha and an consist ep ea

. top of the slide,-a 6to reduce the excessive gap and a flenge of structural member was cut to create an adequate gap for the pipe movecents in the unrestrained direction.

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l PG&E September 15, 1982 Submittal, Table 2 i

Type 2 & 5 i

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