ML20215E551

Summary of 860822 Meeting W/Util in Bethesda,Md to Discuss Containment Process Piping Penetrations for Isolation Condenser.Viewgraphs Encl

ML20215E551
Person / Time
Site:	Oyster Creek
Issue date:	10/01/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8610150370
Download: ML20215E551 (21)

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%'c, UNITED STATES

• *~ NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 October 1,1986

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Occket No. 50-219 LICENSEES: GPil Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station AIIGUST 22, 1986, PEETING WITH GPU NUCLEAR CORPORATION (GPUN1 SUPJECT:

ON THE CONTAINMENT PROCESS PIPING PENETRATIONS FOR CONDENSEP On Friday, August 22, 1986, a meeting was held at NRP. headquarters, Bethesda, Maryland, with GPUN, the licenree, on the design marginsThese in thepenetrations pipinP 4

penetrations for the two emerg ncy isolation condensers.

are for the steam lines to the condensers and the condensate return lines from the condensers to the reactor vessel. The licensee had reauested th meeting to discuss the loading on the 15 process piping penetrations in the primary containment or drywell during a double-ended rupture of the pipe in the penetration. The licensee concluded under 10 CFR 50.59 that 11 of the 15 penet-ations were acceptable and 4 were not.

Attachment Attachment 1 is the l'st of individuals who attended the meeting. The markups 2 is the riaterial for the meetino handed out by the licensee.

The following is a summary of the were done by me durino the meetina. The significar.t items discussed and the actions, if any, taken The discussion on the drywell piping penetrations follows the material in Attachment 2. The licensee stated that its 10 CFP 50.50 reviews of the 11 penetrations will be included in the Updated Final Safety Analysis Report (FSAR1 for Oyster Creek. This material will be submitted in the earliest available update of the FSAR.

The only piping penetrations that do not have acceptable design maroins are the four penetrations for the two condensate return lines and the two ste

' lines for the Isolation Condensers.

' outside the drywell above the reactor vessel to allow natural circulation throuch the condensers and reactor core to cool the reactor core.

The licensee explained it is considering the the following pipes, (?) 3 potential restrict flow fixes for through the A piping penetrations: (1) anch-the break and (31 replace the penetrations. The last fix could not be done in the current Cycle 11 Refueling (Cycle 11R1 outage without significantly Anchoring the pipe would recuire a re-analysis of the extending the outape. stresses in the piping becau w the anchors might cause th 1 The licensee stated that the second l penetrations under other conditions.fix was possibly the best solution

or not such a redesign of the 4 sing penetration could be implernted without significantly impacting the current outage in the use of resources or in extending the outage. gg g PDH ADOCK 05000219 P PDR l

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[ The licensee discussed the safety significance of the 4 penetrations. The

< licensee explained in its presentation its application of leak before break j in its evaluation of the condenser piping. A slide on this is in Attachment

-2. The licensee stated that the pipe will leak before breaking and the leakage detection systems at Oyster Creek will assure the licensee will shut down Oyster Creek before a double ended rupture of the pipes. The penetrations

can acceptably take the loads from smaller or less severe breaks.

The staff requested that the licensee complete its design of the fix for-j the 4 piping penetrations and evaluate its ability to implement the fix during the current outage. The results would be submitted before the restart for Operating Cycle 11. The fix would return the existing design margins in the piping penetrations to that in the FSAR when the plant was licensed. If the licensee concludes that the work cannot be done in this current outage, it must request the approval of the staff to implement the fix in the Cycle 12R outage. This outage should be in 1988. The staff requested, and the licensee agreed, that the licensee's submittal will be made at least one i month before its planned restart of Oyster Creek from the current Cycle 11R i _ outage and will explain the impact of the work on the outage. The staff stated that it will address this issue as part of the restart of Oyster Creek l from the Cycle 11R outage.

i 1

I

/ k N. Donoh Jr., Project Manager i NBWRProjectDirectorate#1 Division of BWR Licensing i

Attachments:

1. List of Attendees

, 2. Licensee's handout i cc: R. Bernero l R. Houston G. Lainas

,'- G. Hulman i M. Srinivasan l B. D. Liaw i

D Y DBL:BWD1 DBL:BWD1

+

CJamerso [' DBL JD t)w$ijg JZwolinski q /pB6 /86 go / $ /86 l

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Oyster Creek Nuclear Mr. P. B. Fiedler Generating Station Oyster Creek Nuclear Generating Station cc: Resident Inspector Mr. Ernest L. Blake, Jr.

Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Forked River, New Jersey 08731 Washington, D.C. 20037 J.B. Liberman, Esquire Comissioner New Jersey Department of Energy Bishop, Liberman, Cook, et al.

101 Comerce Street 1155 Avenue of the Americas Newark, New Jersey 072 New York, New York 10036 Mr. David M. Scott, Acting Chief Bureau of Nuclear Engineerir Regional Administrator, Region I Department of Environmental Protection U.S. Nuclear Regulatory Commission CN 411 631 Park Avenue Trenton, New Jersey 08625 r.ing of Prussia, Pennsylvania 19406 BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN ll?

Trenton, New Jersey 08625 Mayor lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P. O. Box 388 Forked River, New Jersey 08731 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731

ATTACHMENT 1 MEETINr- VITH GPil NUCLEAR CORPOPt. TION (GPUn')

TO DISCUSS FIRE PROTECTION June 23, 1986 ORGAFIZATI0f:

Nf"I NRC/NRP/0P.L J. Donohew NPC/NRR/ DBL J. Iwolinski GPUN P. Crayr GPUN N. Shah GPUN M. Sanfero GPUN A. Pochino GPU?!

D. Croneberger

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ATTACHMENT 2 PRESENTATION ON ANALYSIS FOR HELB IN THE DRYWELL PENETPATION PIPING

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9 I. BACKGROUND II. PENETRATIONS AffECTED III. ORIGINAL DESIGN CRITERIA VS. NEW DESIGN CRITERI IV. NEW ANALYSIS AND RESULTS V. HELB IN THE EMERGENCY CONDENSER STEAM SUPPLY AND PIPING VI. CONCLUSION l

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. 1 I. BACKGR M D A. NINE MILE POINT 1 ANALYSIS o Original analysis did not consider flow reversal effects oSeveralpenetrationsfoundtohaveexcessiveloads B. GPUK ]YSTER CREEK ANALYSIS o Original analysis similar to NMP 1 0 GPUN performed re-analysis i

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II. PENET MTIONS AFFECTED A. TYPICAL PENETMTION CONFIGUMTIONS - SKETCHES B. LIST OF PENET MTIONS AffECTED

CDuTAI4'*EHT walt. (14TERioR) bRYWELL.,9eELL TO PE6JE TR A1 TON- -

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II B. LIST OF PENETRATIONS AffECTED PIPE PENETRATION N0. TYPE SIZE 10" Emerg.Cond. Steam 2 DoublefluedHead X-3A,B Emerg.Cond.Cond. 2 DoublefluedHead 10" X-SA,B Main Steam 2 Doublefluedvl 24" X-2A,B bellows Feedwater 2 Doublefluedvl 18" X-4A,B bellows CleanupLetdown i SinglefluedHead 6"

X-9 CleanupReturn i SinglefluedFead 6"

X-10 CoreSpray 2 SinglefluedHead 8"

X-128,X-70 ShutdownCooling 2 SinglefluedHead 14" X-7-8 i SinglefluedHead 3" CR0 Return X-61

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III. ORIGINAL DESIGN CRITERIA VS. REVISEl

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REVISEDDESIGN CRITERIAi 0RIGINALDESIGN(PERfSAR) 1.PipeRuptureDesign PipeAssumedToRupture,At RupturelocationsSelected Random,OnEitherSideOfThe PerGiambussoletterCritera Condition Drywell Jetforceloadingfrom JetforcePlusMomentum 2.LoadOnPenetration Guillotine-TypePipeBreak EffectsDueToFow ReversalWithinGuardPipe f =1xP x A F = :(P+lV')A) e 9 9

+[(P+lV')A) a Where,P= Pressure A= Area V= Velocity Z= Density e=Processpipeconditionitthebreak a=Annularregionexitcondition ASMESect.III,1983

3. Allowible Stresses 0.9S fig.NE3221-3i.e.The Greaterof1.5Sor y

l.Sb mC Where, S = Yield Stress S = Allowable Stress Intensity

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6 IV. NEW ANALYSIS AND RESULTS A. CALCULATIONAL NETHOD B. SU R RY Of PENETRATIONS EVALUATED t

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IV A. CALCULATION Of THRUST LOAD DAYWELL STEEL SHELL IdiiDE OuTSIDE

" GUAR.D PIPE n PEoCEss ESPE

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f=((p+2v')A: +[(p+zv')A) a e

fluidpressures, densities,andvelocitiescalculatedconsiderin

• Womogeneous, Steady flow and transient Analysis

• Multi-Node Computer Solution or fanno line Calculation

• Upstream Losses Accounted for -ihm hm, . ,,g

• Separation of Pipe Ends Exceeds Dl4

• flowfromBothDirections,ContainmentIncludej(whenAppro

. i IV 3. EVALUATION OF 0.0. PEETRATIONS Mhm gle m(re: p Mconc ,

for HIGH EERGY LIE BER (HELB)

FinalResults 4 ,

NORMAL CONDITIONS i

PRESS TEMP. ANALYSIS PIPE 'T EQUIRED REMARS -

TYPE PSIC.

PEETRATION N0.

SIZE Yes dingisacceptable 1020 Sat.

Emerg,Cond. Steam 2 Doublefluedhead 10" in stand-by node; Ili X-3A,B applies when initiatec Yet leakBeforeBreak 1020 Subcooled Emerg.Cond.Cond. 2 Doublefluedhead 10" Water applies in stand-by ani ,

X-5A,B operatingmodes Yes Icading is acceptable 1020 Sat.

1 Singlefluedhead 6" Cleanupletdown Water X-9 Sat. No Giambussoletter 1020 2 Doublefluedw/ criteriapredictsno 24" MainSteam Steam X-2A,B bellows HElBatthislocation

- - No CheckvalveintheDW 2 Doublefluedv/

18" Feedwater X-4A,B bellows

- - No CheckvalveintheEs 6" CleanupReturn i Singlefluedhead

-- - No CheckvalveintheDU 2 Singlefluedhead 8" CoreSpray .

X-12B,X-70

- - No CheckvalveintheB 1 Single flued head 3" CRDReturn X-61 linedepressurized

- No 2 Singlefluedhead 14" ShddownCooling X-7-8

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V. HELB IN THE EMERGENCY CONDENSER STEAN SU AND CONDENSATE RETURN PIPING-ANALYSIS RESU

1. STEAN SUPPLY LINE

. Leak Before Break Precludes Double Ended Rupture

. Double Ended Rupt;te is Tolerable in " Stand-Bf Node

. In Operating Mode, Double Ended Rupture vill Exc

2. CONDENSATE RETURN LINE

. Leak Before Break Precludes Doubles Ended Rupture

. Doub1e Ended Rupture Would Initiate Emergency Co and Exceed Allowables '

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Va. LEAK BEFORE BREAK (LBB)

• ConceptofLBBpreviouslyacceptedbyNRC

- Guidence by NCR for SEP topic for the Palisades Plant

. LBB accepted on,PWR'S to eliminate RCS pipe wh

- GDC 4 revision in April, 1986 i

LBBisconsideredvalid,inGDC4revisioncurrentlyindraft

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X Vb. APPLICATION 0FLBBTOEMERGENCYCONDE

" PALISADES"CRITERIAREQUIREMENT EMERGENCYCONDENSERPIPINGEVALU i TwoindependentQuantitativeLeakage DetectabilityRequirements monitoringsystemsinoperation i

Indirect indications available e i Specifiedconditionsusedfor IntegrityRequirements evaluation Level D Loads

. CrackStabilityexists .oubm3hh Extreme Conditions

- Material Properties

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. Tendencyforthetracktodevelop SubcriticalCrackGrowth wasshown.

' Analysis made for time vs. crack growthandleakrate Augmented 151 s

. EmergencyCondenser #k QN

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Piping (sublectedtoISIshowedrc IGSCC.

< J ' PenetrationWeld wasnotinspectedduetc inaccessibility.

VI. CONCLUSION

. 4penetrationsoutof15requiringNRCapprovalforunrevie question.

Remarks Penetration Loadingisacceptableinstandbymode; Emerg.Cond. Steam >

LBBApplieswheninitiated LBBappliesinstandbyandoperating Emerg.Cond. Condensate mode e 11 penetrations out of 15 found acceptable by 10 CF Remarks Penetration loadingisacceptable Clean-upLetdown PerGiambussolettercriterianoWEL MainSteam atthislocation Feedwater Check valve in DW,Loggg Check valve in DW, Clean-upReturn CheckvalveinDW,

CoreSpray CheckvalveinDW, CRDReturn Lineisdepressurized, ShutdownCooling

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The The licensee discussed the safety significance of the 4 penetrations.

licensee explained in its presentation its application of leak before break in its evaluation of the condenser piping. A slide on this is in Attachment

2. The licensee stated that the pipe will leak before breaHng and the leakage detection systems at Oyster Creek will assure the licensee will shut The penetrations down Oyster Creek before a double ended rupture of the pipes.

can acceptably take the loads from smaller or less severe breaks.

The sta#f requested that the licensee complete its desion of the fix for the 4 piping penetrations and evaluate its ability to implement the fix The results would be submitted before the restart durine the current for Operatino Cycleoutage.The

11. fix would return the existing design margins in If the piping penetrations to that in the FSAR when the plant was licensed.

the licensee concludes that the work cannot be done in this current outage, it must request the approval of the staff to implement the fix ir. the Cycle 129 outage. This outage should be in 1988. The sta'f reauested, and the licensee agreed, that the licensee's submittal will be made at least one month before its planned restart of Oyster Creek from the currentThe Cycle staff11R outage and will explain the impact of the work on the outaae. stated t from the Cycle 11R outage.

C.%

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Jack N. Donohew, Jr. I Pro.iect Manaaer BWR Project Directorate #1 Division of BWR Licensing Attachments:

1. List of Attendees

2. Licensee's handout cc: R. Bernero P. Houston G. Lainas G. Hulman j

- M. Srinivasan B. D. Liaw i

I l

October 1, 1986 Distribution for Meetinc Sumary Dated:

Facility: Oyster Creek Nuclear Generating Station

• E kbC F11F(50;216"??? "

N RC ~ PDR '"" ~~'~""'~

Local PDF.

BWD1 Reading J. Iwolinski J. Donohew C. Jamerson OGC-BETH (For ir.fo only)

E. Jorcan B. Grimes ACRS (10)

R. Bernero R. Houstor G. Laines B. D. Liaw G. Hulman M. Srinivasan W. Hodges DC File

• Copies sent to persons on facility service list l'

I r

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