Text

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: ML20203Q177; ML20203Q184;
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 No. 50-219/86-040

Docket No. 50-219

License No. DPR-16 Priority --

Category C

Licensee: GPU Nuclear Corporation

P. O. Box 388

Forked River, N.J. 08731

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,

' date

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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

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Details

1. Persons Contacted .

The attendance list for the April 1, 1986 meeting is shown in Attachment 1.

2. 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 No.

219/85-14) 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 219/85-37.

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 outage.

Scoping of piping nozzle loads is intended during the 11R outage.

Operability of safety related piping systems and supports will be

verified before the restart from the 11R outage.

II. IEB 79-02

Verification of anchor bolts (engineering and field) is intended to

be performed during the 11R outage, cycle 11 and 12R outage.

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 anchors.

3. Conclusion

-1. 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 meeting.

2. 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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3. 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 79-02.

4. 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

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Attachment 1

NRC/GPUN Meeting Participants l

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Name Title Drg j

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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

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J. P. Durr Chief, Engineer Branch RI

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

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W. Baunack Proj. Engr., RPS IA RI

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J. F. Wechselberger Resident RI [

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

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M. Laggart Mgr. BWR Licensing GPUN i

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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

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IEBULLETINS79-14AND79-02 i

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AGENDA

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1. INTRODUCTION i

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2, 79-14 STATUS :

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3. 79-02 STATUS

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4. FUTUREWORK l

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5. SUMARY/ CONCLUSIONS !

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, 79-14 STATUS

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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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R&RINING RECIRCULATION SYSTEM INTECTIONS CLERENT SCEDULE SATISFIES -

! DURING 11R QMUENT ,

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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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StfMTTED T0 fER ,

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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

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, 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

inspectedforanalyticalpurposes.

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'? N G AN'A_YS S STA~~US

AS OF MARCH 28,1986

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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

~ 333 %

OPDtABLE -

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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

0

IJUL85 2C ' . 35 SHUTDOWN COOLING

0

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

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210CT8k 3JAN86 CONTAINMENT SPRAY

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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

0

18NOV85 23DEC85 ISO CONDENSER

0

10DEC85 2JAN86 CRD

18DECSO 20JAN86 FEEDWATER

2_O , _ eme_ C_e p

3JAN8 24JAN86 MAIN STEAM

6JAN8 16JAN86 LICuw .DISON l

0

6FEB86 SMAR86 CONTAINMENT SPRAY ,

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3 MAR 8 24 MAR 86 CLEAN-UP DEMINERALIZER

28JUL86 25SEP86 RECIRCULATION I I

DATA

DATE

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1985 1986 <

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RD S O N D J F M

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ZONE 12 - OUTSIDE DRYWELL - SUPPORT ANALYSIS

0

9SEP85 20SEP85 LIQUID POISON-23

0

16SEP85 20CT85 SHUTDOW C00 LING-29

0

23SEP85 6DEC85 CORE SPRAY-114 ,

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O I WWIS

26NOV85 13JAN86 EMERG SERVICE WATER-75 _

0

9DEC85 27JAN86 ISO CONDENSER-59

0 ! ! ! -- =

14JAN86 12 MAR 86 CRD-95 -

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14JAN86 24FEB86 CONTAINMENT SPRAY-98 _

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20JAN8 SFEB86 FEEDWATER & MAINSTEAM-4

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21FEB86 10 MAR 86 EMERG SER WTR INTAKE-11

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1986 ,

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 *

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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

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8APR86 9WAY86 MAIN STEAM-29

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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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79-14PIPINGREANALYSIS.

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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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SCOPEOf79-02 PROGRAM

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FIELDWORK

SUPPORIS PLAIES Pl.AIESWEICHCANBE

SYSIEM With WIIH OMIIIEDFROMPROGR.6

Total Concrete CONCRETE CASI-IN 79-80 OTHER

Anchors ANCHORS INSERIS EFFORI

u)

211 150 C0N. 73 54 77 37 7

212 CORE SPRAY 137 112 156 22 47

213 LIQUID POIS0N 30 19 30 4 19 3*

214 SHUIDOWN COOL. 38 29 41 9 11 *

215 CLE N P DEMIN. 19 6 10 6

223 RECIRC. 55 5 5 0

M

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225 CRD/SDV 82 69 93 0 36

241 CONI. SPRAY 123 91 132 20 63

411 MAIN SIE.8 35 1 1 0

422 FEEDWATER 28 2 4 2

532 ESW 78 77 132 32 21 18'"

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698 465 681 132 157 *68

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324BASEPLATES

"'

+357

(1) QC DAIA AVAIMBLE

(2)FACIOR0?SAFEIYGiEAIERIEAN20

(3)CERRENIESIIB.IE-EECII0INCREASEASAVAIIABLE

DAIA 15 RECEED

(4)OUISIDESCOPEOF79-02 PROGRAM

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ANCHORBOLTVERIFICATIONSTATUS

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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

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ORIGDML PETRD: FULL TESTS

WRRENT PETRD: DEVEL(P INSTALLATION DOCitENTATION FOR BOLTS WiIOi ARE NOT

N)EQUATELY DOCitENTED m TESTED.

REASON Fm CP# SE:

PETRD:

o BCLT INSTALLATION VERIFICATICN PROVIDES MORE CIPPLETE

CG/ERAGE THAN TESTING.

o BQ.T INSTALLATION REWIRES LESS STAY TPE AT EA01

SLPPORT TKREBY REDl;CD6 MEKER RADIATION EXPOSURE.

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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 SYSTENS.

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BCLT INSTALLATION REWIRES LESS SCAFFOLDING.

O BOLT INSTALLATION VERIFICATION IS MWE EOMCAL THAN BOLT

TESTING.

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o BCLT INSTAL'.ATION VERIFICATION CItPLIES WITH BLLLETIN.

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FUTUREWORK

ENGINEERING:

, 079-14 ANALYSIS

079-02 ANALYSIS

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oSUPPORTUPGRADES

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FIELD: .

079-14 INSPECTIONS

079-02INSTALLATIONVERIFICATIONS/ REPAIRS (asreg'd)

0SUPPORTUPGRADES

-STRUCTURALTODESIGNCRITERIA

-ANCHORBOLTSTOREQUIREDSAFETYFACTORS

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SCOPE:

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0INSPECTIONOFRECIRCSUPPORTS

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OINSTALLATIONVERIFICATION/REPAIROFANCHORBOLTS

0UPGRADESUPPORTSTODESIGNCRITERIA

0UPGRADEANCHORBOLTSTOREQUIREDSAFETYFACTORS

BASISFORFIELDWORK:

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0ENSUREOPERABILITYOFSAFETYRELATEDSYSTEMS

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i oMINIMIZEIMPORTONllROUTAGEWORKLOAD

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oVISITSUPPORTSONLYONCE(i.e.,MinimizeALARAand

EquipmentOut-of-ServiceTime,MaximizeEfficiency)

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INACCESSIBLESUPPORTS:

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l SCOPE COMPLETION .

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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

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OVERALLCONCLUSIONS

79-14

o ALL ANALYSES TO DATE SHOW SYSTEMS CURRENTLY EET

OPERABILITYCRITERIA.

O INSPECTIONSANDREANALYSISWILLBECOMPLETEDDURING

llR AND WILL EET OPERABILITY CRITERIA.

o BYEXTRAPOLATION(45to50 total) UPGRADING

SUPPORTS IS EXPECTED TO ALLOW ALL SYSTEMS TO EET

DESIGNCRITERIA.

0 NUMBER OF SUPPORT UPGRADES REQUIRED TO EET DESIGN

CRITERIAISGREATERTHANORIGINALLYEXPECTED(37'5).

79-02

0 APPROACHFORCOMPLETIONOFWORKWILLCOMPLYWITH

THEBULLETIN.

o ALL PLANT PIPING DOCUENTATION WILL BE ENHANCED.

o THEORIGINAL1979 EFFORT,ALTHOUGHNOTCOMPLETE,

ESTABLISHESAHIGHLEVELOFCONFIDENCEINTHE

ORIGINALBOLTINSTALLATION.

o THESCOPEOFANCHORBOLTUPGRADESHASINCREASED

BASED ON TE 79-14 ANALYSIS FINDINGS.

O FIELDWORKFOR79-14UPGRADESAND79-02

VERIFICATIONEFFORTWILLBEINTEGRATEDAND

COMPLETEDBYTHEENDOF12R.

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ML20203Q184

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