IR 05000219/1986040

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Meeting Rept 50-219/86-40 on 860401.Major Areas Discussed: Status of Current Piping Reverification Program.Viewgraphs & List of Meeting Attendees Encl
ML20203Q184
Person / Time
Site: Oyster Creek
Issue date: 05/01/1986
From: Durr J, Kamal Manoly, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20203Q178 List:
References
50-219-86-40-MM, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8605090094
Download: ML20203Q184 (23)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Meeting Report N /86-040 Docket N License N DPR-16 Priority --

Category C Licensee: GPU Nuclear Corporation P. O. Box 388 Forked River, Facility Name: Oyster Creek Nuclear Generating Station Meeting At: NRC - Region I Office King of Prussia, Pennsylvania Meeting Conducted: April 1, 1986 NRC Personnel: 2I (7 J(/ T. Wiggins() CUtef, Materials and date Processes Section, EB, DRS

,L W / 4 4 yhsh6 K. A. Manoly, Lead Reactar Engineer date P4P , DRS Approved by: i Pb ,,jgJ SI,[T C,

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J.P.Durr, Chief,EngineeringBranch,DRS Meeting Summary: Meeting on April 1, 1986 (Meeting Report Number 50-219/86-040)

A meeting was held on April 1, 1986 in King of Prussia, Pennsylvania, between representatives of GPU Nuclear and the NRC staff to discuss the status of the current piping reverification program.

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[ 8605090094 860502 PDR

G ADOCK 05000219 l pyg i

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Details 1. Persons Contacted .

The attendance list for the April 1, 1986 meeting is shown in Attachment . Meeting Summary A meeting was held on April 1, 1986 in King of Prussia, PA., between representatives of GPU Nuclear and the NRC staff (Attachment 1) to discuss the status of the current piping reverification program. The activity was undertaken by GPUN in response to findings identified during the NRC -

Region I inspection for closeout of IEB 79-02 and 79-14 (Report N /85-14) and subsequent meeting in Parsippany with the NRC staff on June 25, 1985. Further commitments made by GPUN during a meeting with the NRC staff on November 13, 1985, were contained in inspection report 219/85-3 In the meetino of April 1, 1986, GpVN presented the revised schedule for the engineering evaluations and field inspection and modifications asso-ciated with the reverification program. Details of the above activities were provided by GPUN during the meeting and are enclosed with this meeting report (Attachment 2). Other related items and schedular commit-ments which were discussed during the meeting included:

I.IEB 79-14

  • Completion of the piping and pipe support evaluations is planned during the 11R outag * Scoping of piping nozzle loads is intended during the 11R outag * Operability of safety related piping systems and supports will be verified before the restart from the 11R outag II. IEB 79-02
  • Verification of anchor bolts (engineering and field) is intended to be performed during the 11R outage, cycle 11 and 12R outag * At the startup from 11R outage, supports required for system opera-bility will meet at least a factor of safety of two (2) for wedge and shell type anchor . Conclusion

- GPUN will submit a letter, within three weeks, to document certain clarifications to its schedular commitments for completion of activ-ities related to IEB 79-02 and 79-14, and other engineering issues raised during this meetin . The licensee will re-evaluate its JC0 to ensure the acceptability of its restart from the 11R outage with IEB 79-02 and 79-14 incomplete.

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, GPUN will re-evaluate its plans for the design verification asso-ciated with IEB 79-14 pending the outcome of field verifications related to IEB 79-0 . The NRC - Region I staff will follow-up on the following:

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review of GPUN criteria for inspection and testing related to IEB 79-02

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the disposition cf nozzle loads

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The status of the licensee's JC0 for 11R restart

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update NRR-SEP group of results from the piping and pipe support verification effort l

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Attachment 1 NRC/GPUN Meeting Participants l l

Name Title Drg j i

J. T. Wiggins Chief, Materials and Processes Section RI K. A. Manoly Lead Reactor Engineer, MPS RI S. D. Ebneter Director, Division of Reactor Safety RI I

J. P. Durr Chief, Engineer Branch RI

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A. R. Blough Chief, Rx Projects Sec. IA RI  ;

k i W. Baunack Proj. Engr., RPS IA RI

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l J. F. Wechselberger Resident RI [

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R. J. Blouch Sup., Supplier Evaluation GPUN  !

i M. Laggart Mgr. BWR Licensing GPUN i e

D. K. Croneberger Director, Engineering & Design GPUN  !

R. F. Wilson Director, Tech. Functions GPUN ,

G. R. Capodanno Fluid Systems Director GPUN N. C. Kazanas Director, Quality Assurance GPUN J. Rogers Licensing Engineer GPUN  !

J. R. Thorpe Director, Licensing & Reg. Affairs GPdN

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Attachment 2 f:

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l; IEBULLETINS79-14AND79-02 i L  !'

l AGENDA l

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1. INTRODUCTION i

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l 2, 79-14 STATUS  :

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i 3. 79-02 STATUS i

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4. FUTUREWORK l t

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5. SUMARY/ CONCLUSIONS  !

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, 79-14 STATUS i

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, C0itETENT STATUS

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i FIELD INTECTIONS ON ALL SYSTEMS (ItPLETED AS SCHmJ m i (EX&PT f0RTIONS OF RECIRCULATION SYSTEN)

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I R&RINING RECIRCULATION SYSTEM INTECTIONS CLERENT SCEDULE SATISFIES -

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! ANALYSIS TO BE (IPPLETED PRIOR TO CLERENT SOiEDULE SATISFIES .

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RESTART FR&1 11R OMOENT ,

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I?F0ff% TION REGARDING SEP TCPICS (IPPLETED AS SCHEDULE ;

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.. 79-14SCOPEOFREVIEW SYSTEMSDESCRIPTION SUPPORTS PIPINGMODELS CLEANUPDEMINERALIZER 19 4 CONTAINMENTSPRAY 123 7 CONTROLR0DDRIVE 82 4 CORESPRAY 137 5 ISOLATIONCONDENSER 73 8 EMERGENCYSERVICEWATER 78 6 FEEDWATER 28 1 LIQUIDPOIS0N 30 4 MAINSTEAM 35 2 i

, REACTORRECIRCULATION 55 5 SHUTDOWNCOOLING 38 4 TOTAL 698 50 NOTE:Theprevioussupporttotalof816wasbasedinpartupon countingindividualsupportcomponents.(i.e. snubbers, spring cans, etc.). The support total of 698 is based uponthenumberofsupportdrawings(i.e., support locations). In fact, the 698 tbtal reflects an increase inscopesinceadditionalconnectingpiperunshavebeen inspectedforanalyticalpurpose ._ - . - .

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'? N G AN'A_YS S STA~~US AS OF MARCH 28,1986

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! I 45 OF 50 P!PNG MODELS HAVE BEEN ANALYZED (90%)

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' 3E SP30F S X US AS OF MARCH.28,1986

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234

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374 OF 698 SUPPORTS HAVE BEEN ANALYZED (54%)

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1985 1986 J A S O N D J F e,

[D FD ZONE 11 - OUTSIDE DRY % ELL - PIPING ANALYSIS

IJUL85 2C ' . 35 SHUTDOWN COOLING

1JUL85 19JUL85 LIQUID POISON O N 22JUL85 22NOV85 COI Y

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29JUL85 15NOV85 ISO CONDENSER -

SAUG80 22NOV85 EMERG SERVICE WATER 12AUG80 7NOV85 CRD/SDV l l 210CT8k 3JAN86 CONTAINMENT SPRAY

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o l I I 8NOV85 21NOV85 FEEDWATER 0 i !

22NOV85 9DEC85 MAIN STEAM 0 l I I I 15JAN86 5FEB86 EMERGENCY SW INTAKE

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1985 1986 ,

N D J F M A M J J A S 00 FD ZONE 21 - INSIDE DRYWELL - PIPING ANALYSIS 0 M 11NOV85 11FEB86 CORE SPRAY

18NOV85 23DEC85 ISO CONDENSER

10DEC85 2JAN86 CRD 18DECSO 20JAN86 FEEDWATER 2_O , _ eme_ C_e p 3JAN8 24JAN86 MAIN STEAM 6JAN8 16JAN86 LICuw .DISON l

6FEB86 SMAR86 CONTAINMENT SPRAY ,

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I I 3 MAR 8 24 MAR 86 CLEAN-UP DEMINERALIZER 28JUL86 25SEP86 RECIRCULATION I I DATA DATE

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1985 1986 <

l RD S O N D J F M 7g ZONE 12 - OUTSIDE DRYWELL - SUPPORT ANALYSIS

9SEP85 20SEP85 LIQUID POISON-23

16SEP85 20CT85 SHUTDOW C00 LING-29

23SEP85 6DEC85 CORE SPRAY-114 ,

I O I WWIS 26NOV85 13JAN86 EMERG SERVICE WATER-75 _

9DEC85 27JAN86 ISO CONDENSER-59 0  ! ! ! -- =

14JAN86 12 MAR 86 CRD-95 -

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Eiiiiii 14JAN86 24FEB86 CONTAINMENT SPRAY-98 _

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l l I 20JAN8 SFEB86 FEEDWATER & MAINSTEAM-4 o i I I I 21FEB86 10 MAR 86 EMERG SER WTR INTAKE-11

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SD FD J F M A M J J A S O

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ZONE 22 - INSIDE DRYELL - SUPPORT ANALYSIS 28JAN86 20FEB86 FEEDWATER-26 11FEB86 5 MAR 86 CRD-15 24FEB86 4 WAR 86 SHUTDOM COOLING-10 D 28FEB86 19 WARS 6 CORE SPRAY-12 S *

I 4 WAR 86 15APR86 CONTAINENT SPRAY-72 6 MAR 86 17 WAR 86 CLEAN-UP DEWINERALI-11 D 25 MAR 86 11APR86 LIQUID POISON-9

f 8APR86 9WAY86 MAIN STEAM-29

. e s s 18JUL86 IS COND-15(OWITTED) C I I I I I I I 3SEP86 200CT86 RECIRCULATION-105 I I ,

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PIPESUPPORTUPGRADES

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(AsofMARCH28,1986)

140 SUPPORTSREQUIREUPGRADES 85 ARESTRUCTURALONLYupgrades 43 AREANCHORBOLTONLYUPGRADES*

12 AREANCHORBOLTANDSTRUCTURALUPGRADES*

140 NOTE:THESEUPGRADESAREINADDITIONTOTHE21ESWSUPPORTS WHICHWERESHIMMEDDURING10MOUTAGE(November 1985).

APORTIONOFTHEANCHORBOLTUPGRADESREFLECT79-02 BASE PLATECONSIDERATIONSRATHERTHANLOADINCREASESDUETO

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BREAKDOWNOFSUPPORTUPGRADES (ASOFMARCH28,1986)

TYPEOFUPGRADE '50FTOTALSUPPORTS NUMBEROFSUPPORTS DESIGNCHANGEREQUIREMENT 20's 74 ANCHORBOLTUPGRADE 11'5 43 U-BOLT /LATERALRESTRAINT 3'5 11 WELDUPGRADE 3'5 11 ADDITIONALBRACING 0,3'5 1 37,3'5 140 SATISFACTORYASFOUND 62,7'5 234 100'5 374

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SUPPORTREMOVAL 3

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FIELDWORK SUPPORIS PLAIES Pl.AIESWEICHCANBE SYSIEM With WIIH OMIIIEDFROMPROG Total Concrete CONCRETE CASI-IN 79-80 OTHER Anchors ANCHORS INSERIS EFFORI u)

211 150 C0 CORE SPRAY 137 112 156 22 47 213 LIQUID POIS0N 30 19 30 4 19 3*

214 SHUIDOWN COO *

215 CLE N P DEMI RECIR M

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225 CRD/SDV 82 69 93 0 36 241 CONI. SPRAY 123 91 132 20 63 411 MAIN SI FEEDWATER 28 2 4 2 532 ESW 78 77 132 32 21 18'"

i 698 465 681 132 157 *68

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+357 (1) QC DAIA AVAIMBLE (2)FACIOR0?SAFEIYGiEAIERIEAN20 (3)CERRENIESIIB.IE-EECII0INCREASEASAVAIIABLE DAIA 15 RECEED (4)OUISIDESCOPEOF79-02 PROGRAM

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(ASOFMARCH28,1986)

ANALYSISRESULTS oAPPR0XIMATELY1150ANCHORBOLTSHAVEBEENEVALUATED o851(74%)MEETDESIGNCRITERIA o225(20%)HAVEAFACTOROFSAFETYBETWEEN2AND5 074(6%)HAVEAFACTOROFSAFETYLESSTHAN2(SYSTEMS HAVEBEENDETERMINEDTOBEOPERATIONALWITHTHESUPPORT INQUESTIONREMOVEDFROMTHEPIPINGCALCULATION)

FIELDVERIFICATIONRESULTS oORIGINAL79-80SUPPORTVERIFICATION(157)PLATESIS VALIDANDBASEDONLOWFAILURERATEEXPERIENCEDGIVESA DEGREEOFCONFIDENCEINTHEORIGINALINSTALLATION o54BASEPLATESHAVEVALIDINSTALLATIONDOCUMENTATION o 14 BASE PLATES HAVE BEEN IDENTIFIED WHICH HAVE HIGH FACTORSOFSAFETY o324BASEPLATESREQUIREFIELDVERIFICATION

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BOLT PHYSICAL VERIFICATION 7E-02 VERIFICATION APFROACH

ORIGDML PETRD: FULL TESTS WRRENT PETRD: DEVEL(P INSTALLATION DOCitENTATION FOR BOLTS WiIOi ARE NOT N)EQUATELY DOCitENTED m TESTE REASON Fm CP# SE:

PETRD:

o BCLT INSTALLATION VERIFICATICN PROVIDES MORE CIPPLETE CG/ERAGE THAN TESTIN o BQ.T INSTALLATION REWIRES LESS STAY TPE AT EA01 SLPPORT TKREBY REDl;CD6 MEKER RADIATION EXPOSUR i o ELRilNATES FEED Fm TEST RIG WiICH CAN BE DIFFICULT -

TO PMDLE Fm W4.L #0 0/EREAD LOCATIONS

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TEST RIG IS A POTENTIAL HAZNO AR0lf0 SENSITIVE EWIRfNT #0 SYSTEN BCLT INSTALLATION REWIRES LESS SCAFFOLDIN O BOLT INSTALLATION VERIFICATION IS MWE EOMCAL THAN BOLT TESTIN .

o BCLT INSTAL'.ATION VERIFICATION CItPLIES WITH BLLLETI . .. . . . - -. - - - . _ _ - .

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FUTUREWORK ENGINEERING:

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FIELD: .

079-14 INSPECTIONS

079-02INSTALLATIONVERIFICATIONS/ REPAIRS (asreg'd)

0SUPPORTUPGRADES

-STRUCTURALTODESIGNCRITERIA-ANCHORBOLTSTOREQUIREDSAFETYFACTORS

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0INSPECTIONOFRECIRCSUPPORTS

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OINSTALLATIONVERIFICATION/REPAIROFANCHORBOLTS 0UPGRADESUPPORTSTODESIGNCRITERIA 0UPGRADEANCHORBOLTSTOREQUIREDSAFETYFACTORS BASISFORFIELDWORK:

l 0ENSUREOPERABILITYOFSAFETYRELATEDSYSTEMS i

i oMINIMIZEIMPORTONllROUTAGEWORKLOAD

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oVISITSUPPORTSONLYONCE(i.e.,MinimizeALARAand EquipmentOut-of-ServiceTime,MaximizeEfficiency)

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INACCESSIBLESUPPORTS:

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l 0RECIRCSUPPORTINSPECTIONS llROUTAGE

! oINSTALLATIONVERIFICATION/REPAIROF ANCHORBOLTS llROUTAGE oUPGRADEANCHORBOLTSTOREQUIREDSAFETY FACTORS (NotCoincidentw/StructuralUpgrade) llROUTAGE oINSTALLATIONVERIFICATION/REPAIROF

! ANCHOR BOLTS (Coincident w/ Structural Upgrades) 12R OUTAGE ACCESSIBLESUPPORTS:

SCOPE COMPLETION 0INSTALLATIONVERIFICATION/REPAIROF ANCHORBOLTS OPRCYCLE11 oUPGRADESUPPORTSTODESIGNCRITERIA OPRCYCLE11 oUPGRADEANCHORBOLTSTOREQUIRED SAFETYFACTORS OPRCYCLE11

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3 I I I I I I I I I 3 5 5 I I I I I I i7 I 5 ~i 1 4 ~1 M J J A S O N D J FM A M J J A S O N D J F M1988 AMJ 1986 1987 L

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OVERALLCONCLUSIONS 79-14 o ALL ANALYSES TO DATE SHOW SYSTEMS CURRENTLY EET OPERABILITYCRITERI O INSPECTIONSANDREANALYSISWILLBECOMPLETEDDURING llR AND WILL EET OPERABILITY CRITERI o BYEXTRAPOLATION(45to50 total) UPGRADING SUPPORTS IS EXPECTED TO ALLOW ALL SYSTEMS TO EET DESIGNCRITERI NUMBER OF SUPPORT UPGRADES REQUIRED TO EET DESIGN CRITERIAISGREATERTHANORIGINALLYEXPECTED(37'5).

79-02 0 APPROACHFORCOMPLETIONOFWORKWILLCOMPLYWITH THEBULLETI o ALL PLANT PIPING DOCUENTATION WILL BE ENHANCE o THEORIGINAL1979 EFFORT,ALTHOUGHNOTCOMPLETE, ESTABLISHESAHIGHLEVELOFCONFIDENCEINTHE ORIGINALBOLTINSTALLATIO o THESCOPEOFANCHORBOLTUPGRADESHASINCREASED BASED ON TE 79-14 ANALYSIS FINDING O FIELDWORKFOR79-14UPGRADESAND79-02 VERIFICATIONEFFORTWILLBEINTEGRATEDAND COMPLETEDBYTHEENDOF12 _