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,

J.P.Durr, Chief,EngineeringBranch,DRS

' date

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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:

-

review of GPUN criteria for inspection and testing related to

IEB 79-02

-

the disposition cf nozzle loads

-

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

-

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

Name

Title

Drg

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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

A. R. Blough

Chief, Rx Projects Sec. IA

RI

k

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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

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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

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AGENDA

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1.

INTRODUCTION

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79-14 STATUS

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79-02 STATUS

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FUTUREWORK

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SUMARY/ CONCLUSIONS

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79-14 STATUS

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C0itETENT

STATUS

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FIELD INTECTIONS ON ALL SYSTEMS

(ItPLETED AS SCHmJ m

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(EX&PT f0RTIONS OF RECIRCULATION SYSTEN)

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R&RINING RECIRCULATION SYSTEM INTECTIONS

CLERENT SCEDULE SATISFIES

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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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(IPPLETED AS SCHEDULE

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79-14SCOPEOFREVIEW

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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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AS OF MARCH 28,1986

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1986

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24 MAR 86

CLEAN-UP DEMINERALIZER

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DATA

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1986

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6DEC85

CORE SPRAY-114

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13JAN86

EMERG SERVICE WATER-75

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27JAN86

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14JAN86

12 MAR 86

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EMERG SER WTR INTAKE-11

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ZONE 22 - INSIDE DRYELL - SUPPORT ANALYSIS

28JAN86

20FEB86

FEEDWATER-26

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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

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PIPESUPPORTUPGRADES

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(AsofMARCH28,1986)

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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

.

SUPPORTREMOVAL

3

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Total

Concrete

CONCRETE

CASI-IN

79-80

OTHER

Anchors

ANCHORS

INSERIS

EFFORI

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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

0

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225 CRD/SDV

82

69

93

0

36

241 CONI. SPRAY

123

91

132

20

63

411 MAIN SIE.8

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422 FEEDWATER

28

2

4

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532 ESW

78

77

132

32

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698

465

681

132

157

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324BASEPLATES

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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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ANCHORBOLTVERIFICATIONSTATUS

'

(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 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.

o

ELRilNATES FEED Fm TEST RIG WiICH CAN BE DIFFICULT

-

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

TEST RIG IS A POTENTIAL HAZNO AR0lf0

-

SENSITIVE EWIRfNT #0 SYSTENS.

BCLT INSTALLATION REWIRES LESS SCAFFOLDING.

-

O

BOLT INSTALLATION VERIFICATION IS MWE EOMCAL THAN BOLT

TESTING.

.

o

BCLT INSTAL'.ATION VERIFICATION CItPLIES WITH BLLLETIN.

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FUTUREWORK

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079-14 ANALYSIS

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079-02 ANALYSIS

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oSUPPORTUPGRADES

.

FIELD:

.

079-14 INSPECTIONS

079-02INSTALLATIONVERIFICATIONS/ REPAIRS (asreg'd)

0SUPPORTUPGRADES

-STRUCTURALTODESIGNCRITERIA

-ANCHORBOLTSTOREQUIREDSAFETYFACTORS

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0UPGRADEANCHORBOLTSTOREQUIREDSAFETYFACTORS

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llROUTAGE

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12R OUTAGE

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3

I

3

5

I

i7

I

5

1

4

M J J A S O N D J FM A M J J A S O N D J F M A M J

1986

1987

1988

L

-- -- ---

_

..

-

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.

_

ML20203Q184

Text

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