ML17252A155

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Summary of Meeting with Representatives of the Mark I Owners Group and GE to Discuss the Structural Acceptance Criteria for the Mark I Containment LTP
ML17252A155
Person / Time
Site: Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Fermi, Oyster Creek, Hope Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick
Issue date: 09/19/1977
From: Guibert J
Office of Nuclear Reactor Regulation
To:
References
Download: ML17252A155 (10)
v • d • e


Text

.-~-*,..-*--......

SEP 19 fJ77 DOCKETS NOS.:

50-219. 50-220. 50-237, 50-245,~ 50-254, 50-259.

50-260, 50-263, S0.:265, *so..:211, ~

50-278, 50-293, 50-296, 50-298, 50-321.- *50-324"~ 50-325, 50-331. 50-!33, 50-341, 50-354, 50-355, and 50'-366 LICENSEES:

Boston Edison Company, Carolina Power & light Company, Cou111011wealth Edisori'eomp&ny, 11etro1t Edison Company, Georgia Power Company, Iowa ETectr1c light I Power Com-pany, Jersey Central Power I. l'ight Company, Nebraska Public Power District, Niagara.. )lohawk Power Corporation, Northeast Nuclear Energy eompa*ny, Northern States Power Company, Philadelphia Electric.. Company, Power Authority of the State of New York, Pubffc Service Electric and Gas, Tennessee Valley Author19'~ Vermont Yankee Nuclear Power Corpora ti on FACILITIES:

Oyster Creek Nuclear Generat1n!J Station. Nine Mile Point Unit No. 1, Pilgr1m-Orift.. Jk).* T, Dresden Units N0s. 2 and 3, M111s,~ne Unit No. 1, Quad 1t1t1es Units Nos. 1 and 2, Monticello, Peach Bottom Un1ts" lfos. 2 and 3, Browns Ferry Units Nos. 1, 2 and 3, Vennont'-Yanl:ee, Hatch Units Nos. 1 and 2, Brunswick Units Nos. 1 *and 2,. Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fenn1 Unit No. 2, and Hope Creek Units Nos. 1 and 2~*

SUBJECT:

SUMMARY

OF MEmNG HELD OH JUNE 17, 1977.Willi REPRESEN-TATIVES OF THE MARK I.Ol4NER' S tROUP On June 17, 19n, a meeting was held in Bethesda, Maryland with represen-tatives of the Mark I Owner's Group *arn!"the 'General Electric Company (GE}.

The purpose of the meeting was io "d1Sct.iss **the -structural acceptance criteria for the Mark I Conta_fri.~~ :.~o*ri~ Jer~fProgram (LTP}. in particular service limfts for specific structural elements as a function of loading events. Enclosure 1 fs a list.. of "at'teridees: **Enclosure 2 fs a copy of the meeting agenda.

"* ~ *--~ * "** * *** *

  • ., *: o:.

e *'.... -...... r Sunvnary

l. J. Sobon, GE, stated that the development of a preliminary table (Enclosu-re 3) of loading event c'<mlb1ri"ciffons *and associated structural
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OFFICll.. I

~ I SURNAME.. ****------=: *::.. ~---***::::: :::::---~ *::::~~====:.: :::~:.

DATii......*--*---.. -.......... --......... ****----***.. -*-.................

NRC FORM 318 (9-76) NRCM 0240

  • u. s. OOVERNME:NT PRINTING OFP'ICE1 1878 -

e2e-eu service limits for the Mark I containment system structural elements

included consideration of 111 mecnarifstfca1'fy--,;ossib1e load caribina-1 tions.

He further stated that "not 'ilf of 'tnese 33 possible canb1na-.

tfons would be included 1n the
~~~s~~C.~u~aJ ::analyses and that
pre11m1nary judgement 1nd1eates that aPJ)rox1mately 7 1oad1ng comb1na-
tions would be required to ~~

~a.i:l~S,~1.b.1.9- ~comb1nat1ons..

  • Based on Mr. Sobon's*remarts. a d1scuss1on took place on the need to cons1der an SRV and OBA pool sweTl'loa'd*eonmf'riation 1n the LTP. The Mark I Owner's position on thfs. matter fi tna*t such a load eombinat1on is mechan1stica11y 1mposs1b1e arid stioUld not *t;e considered *. Further-more. the OWner's Group does not agree -that *a "postulated sfng~*e faflure 1nvo1v1ng the.ropen1ng of an SRV eonctirrent Wfth the OBA pool swell h an appropr1ate application of the.... s1rig1e failure criterion.

11 The NRC staff stated that ft would consider *sucti.argumentS::~m thetliet~ctrtw..:i::~

t1on of its pos1tton on th1s matter and -apressed a cormi1tment to advise the Mark I <Mner's GrQup of 1ts posft10ri.~s sc>on as poss1b1e.

W. Cooper. Teledyne, introduced the discussion on stn1ctural service 11m1ts w1th the following nmarks f *: ~-- ~. ~

~"...

1. It should be noted that th1s is a pre11m1nary effort. Some load comb1nat1ons may not require ~~~r,~~ :~~~tluent.
2. :*The structural acceptance criteria ~plication Guide w111 not

. contain lpads. but rather wfll-refer'to"itle load Def1ntttori Report.

..i -

~...,,

3. Seismic loads w111 be treated as they were treated tn the FSAR for each f aen 1 ty. 1.t., the )nost ~~'!ri'~ :~rf ~l.js'i s on the docket. --
4.

Cyclic events wfll be evaluated for fatigue cons1derat1ons for all fatigue-related loading "events; 'even ~i*f such treatment 1s not required by the Code.

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  • .* ",. ~'

,.,..,;;..,.................. *. f.*

S.

The Application Gutde 1s designed ~o establish generic service 11m1ts. Relief from these T 1m1ts would ~require NRC approval on a case by case bas1s.

~.....

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6. Only MC (metal containment) related elements w111blte discussed today.

'~.... -

W. Cooper proceeded to explain the table of proposed service ltmits for specific components under specific postulated loading comb1nat1ons.

Following a lengthy discussion, 'ttie lfRC *staff expressed the fo11<>Wing conments :

I I

I I

I I..

OFFICE~

SURNAME~................................................................................. _...................... -*-******-**************...................... -.......................................... --*-****

7

  • 1. The format of the Table (Enclosure 3) seems to be approprfate, but the specf ff c service 11mfts pr0J)Osed are not acceptable fn a 11 cases.
2. The general service levels described by the staff (1.e., "A" for basic loads I 118" for load fn c0njuriction 'with OBE. and acu for load 1n conjunction with *ssE) *re1ireserit -.. g.round-zero" for acceptab111ty.

Any dev1at1ons*-from-thf's. "ground zero" would require justification.

  • . ~..... *--****
3. Some general guidance wfth respect to deviations from aground zero" 1 s as fo 11 ows :

~ ".. ** * ' * *.. ** *

._ - ~*.. *:......... " *:

a. Impulsive Loads. For non-quasfstatic loads, we would accept deviations which are *basecf'on 'the *use Of impulSf Ve t@Chnf Q\\leS I such as are being 1nvestf g'ated 'for' **ttle NRC by Lawrence Liver-more taboratorfes (lll). "Along this -line, we would be w1111ng to arrange a meeting between tne* 'Mark I Owner's Group and our consultants at Lll to descrfbe' our '*program there.

-~............

b. local D.ynam1c Loads. Jet forces and associated piping reac-tions would be acceptable *for corislde'rat1on under this cat~gory. However, we are* not' *receptf ve to your categoriza-tion, as presented today, 'of perietraff.ons and local loads.
  • we would consider pool swe11 1mpact', 'safety-relfef valv~
\\

actuations, and steam chugging-loads as potentf ally fal lfng wfthfn thfS category, ff t'hey *c:*ari 'tie adequately justified to be sol

c. Changes in Service Levels es a Function of the Transient.

ff b

d. Level E Items. Only for non-safety related items and, even then, only if the consequeriees"of'their failure on safety related equipment fs consfden!d. * **,.

~

T

4. External and internal pressure boundaries should, in general. be treated the same.
  • .. * * -.. * * ~ *
  • At the conclusfon of the meeting, arrangementwswere 1n1tfated for a meeting between the representatives *of *the t.;a*nc I Owner's Group and our consultants at LLL.
  • * * ** * * ~ * * ' * * '

. -... *' -. )-~ i John C. Guibert

  • Techn1ca1 Assistant Division of Operating Reactor~

Distribution:

  • Docket Fi 1 es' E. G. Case V. Stel 1 o
  • J. Reece K. R. Goller

.T. J. Carter

  • D. Eisenhut A. Schwencer D. Ziemann G. Lear R. Reid
  • W. Butler D. Davis
  • L. Shao
  • OELD
  • OI&E (3).
  • NRC Participants
  • ACRS (16)

W. Paulson P. O'Connor.. **

    • . D. Jaffe R. Snai der.

T. Wambach C. Trammell M. Fletcher P. Riehm L. Kintner

  • G. Lainas
  • I. Sihwei 1
  • J. Knight
  • R. Tedesco
  • R. Stuart J. Siegel
  • R. Bevan S. Nowicki D. Verrelli G. Vissing
  • wits.enclosure

.. i

UNITED STATES NUCLEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 SEP 14 1977 DOCKETS NOS.:

50-219, 50-220, 50-237, 50-245, 50-249, 50-254, 50-259, 50-260, 50-263, 50-265, 50-271, 50-277, 50-278, 50-293, 50-296, 50-298, 50-321, 50-324, 50-325, 50-331, 50-333, 50-341, 50-354, 50-355, and 50-366 LICENSEES:

Boston Edison Company, Carolina Power & Light Company, Commonwealth Edison Company, Detroit Edison Company, Georgia Power Company, Iowa Electric Light & Power Com-pany, Jersey Central Power &-Light Company, Nebraska Public Power District, Niagara Mohawk Power Corporation, Northeast Nuclear Energy Company, Northern States Power Company, Philadelphia Electric Company, Power Authority of the State of New York, Public Service Electric a~d Gas, Tennessee Valley Authority, Vermont Yankee Nuclear Power Corporation FACILITIES:

Oyster Creek Nuclear Generating Station, Nine Mil~ Point.

Unit No. 1, Pilgrim Unit No. l, Dresden Units Nos. 2 and 3, Millstone Unit No. 1, Quad Cities Units Nos. l and 2, Monticello, Peach Bottom Units Nos. 2 and 3, Browns Ferry Units Nos. 1, 2 and 3, Vermont Yankee, Hatch Units Nos. l and 2, Brunswick Units Nos. l and 2, Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fermi Unit No. 2, and Hope Creek Units Nos. *1 and 2.

SUBJECT:

SUMMARY

OF MEETING HELD ON JUNE 17, 1977 WITH REPRESEN-TATIVES OF THE MARK I OWNER'S GROUP On June 17, 1977, a meeting was held in Bethesda, Maryland with represen-tatives of the Mark I Owner's Group and the General Electric Company (GE).

The purpose of the meeting was to discuss the structural acceptance*

criteria for the Mark I Containment Long Term Program (LTP), in particular seivice limits for specific structurai elements as a function of loadihg events.

Enclosure l is a list of attendees.

Enclosure *2 is a copy of the meeting agenda.

Summary L. J. Sobon, GE, stated that the development of a preliminary table (Enclosure 3) of loading event combinations and associated structural

-c

i: service limits for the Mark I containment syst~m structura) elements.

included consideration of all mechanistically possible load combina-tions.

He further stated that not all of these 33possible combina-tions would be included in the LTP structural analyses and that

  • preliminary judgement indicates that approximately 7 loading co111bina-tions would be required to bound all possible combinations.

Based on Mr. Sobon's remarks, a discussion took place on the need to..

consider an SRV and OBA pool swell load combination in the LTP.

The Mark I Owner's position on this matter is that such a load combination is mechanistically impossible and should not be considered.

Further-more, the Owner's Group does not agree that a postulated single failure involving the opening of an SRV concurrent with the OBA pool swell is ah appropriate application of the "single.failure criterion." The NRC staff stated that it would consider such arguments in the determina-tion of its position on this matter and expressed a connnitment to advise the Mark I Owner's Group of its position as soon as possible.

W. Cooper, Teledyne, introduced the discussion on structural service limits with the following remarks:

1. It should be noted that this is a preliminary effort. Some load combinations may not require separate treatment.
2.

The ~tructural acceptance criteria Application Guide will not contain loads, but rather will refer to the Load Definition Report.

3.

Seismic loads will be treated as they were treated in the FSAR for each facility, i. e., the most recent analysis on the docket.

4.

Cyclic events will be evaluated for fatigue considerations for all fatigue-related loading events, even if such treatment is riot required by the Code.

5.

The Application Guide is designed to establish generic service limits. Relief from these limits would require NRC approval on a case by case basis.

6, Only MC (metal conta1nment) related elements will be discussed

  • today.

W. Cooper proceeded to exp)ain the table of proposed service limits f6r specific components under specific postul!ited loading combinations.

Fdllowing a lengthy di~cussion, the NRC staff expressed the following connnents:

'I

  • l. Tlie format of the Table (Enclosure 3) seems to be appropriate, but the specific service limits proposed are not acceptable in all cases.

2:

The general service levels described by the staff (i.e.,

11A 11 for basic loads, 118 11 for ioad in conjunction with OBE, and 11C 11 for load in conjunction with SSE) represent "ground-zero" for acceptability.

Any deviations from this "ground zero" would require justification.

3.

Some general guidance with respect to deviations from "ground zero" is as follows:

.a.

Impulsive Loads.

For non-quasistatic loads, we would accept deviations which are based on the use of impulsive techniques, such as are being investigated for the NRC by Lawrence Liver-more Laboratories (LLL).

Along this line, we would be willing to arrange a meeting between the Mark I Owner's Group and our consultants at LLL to describe our program there.

b.

Local Dynamic Loads. Jet forces and associated piping reac-tions would be acceptable for consideration under this category.

However, we are not receptive to your categoriza-tion, as presented today, of penetrations and local loads.

We would consider pool swell.impact, safety-relief valve actuations, and steam chugging loads as potentially falling within this category, if they can be adequately justified to be so.

c. Changes in Service Levels as a Function of the Transient.
d.

Level E Items.

Only for non-safety related items and, even then, only if the consequences of their failure on Safety related equipment is considered.

4.

External and internal pressure boundaries should, in general, be treated the same.

At the conclusion of the meeting, arrangements were initiated for a meeting between the representatives of the Mark I Owner's Group and our consultants at LLL.

Enclosures:

As stated

,/71~

--1-,4~',,

1 John C. Guibert Technical Assistant Di~ision of Operating Reactors

  • Name J. Guibert R. H. B._uchholz L. D. Steinert W. E. Cooper N. W. Edwards L. V. Sobon C.. I. Grimes
  • Randy Broman E. Mangrum T. J. Mulford C. H. Hofmayer L. C. Shao R. J. Stuart A. Hafiz.

Keith Wichman Bill Bauer C. W. Churchman Kulin D. Desai B. D. Liaw

.Pei-Ying Chen R. L. Cudlin D. Whitt R. Klause

.R. E. Shewmaker G. Bagchi J. Kudrick R. E. Shaffstall I. Sihwiel

  • C; Anderson
  • Enclosure l MEETING.- JUNE 17~ 1977 Organization NRC/OOR GE
  • GE Tdy. Eng. Services NUTE CH GE NRC/DOR Bechtel GE GE

.NRC/DOR/EB NRC/DOR/EB NRC/DOR/EB NRC/SEB NRC/SD/DOR PSE&G PSE&G NRC/DSS/MEB NRC/DOR/EB NRC/MEB NRC/DOR CBI Storie & Webster

  • NRC/IE:HQ NRC/DOR/EB NRC/DSS/CSB GE-Bethesda NRC/DSS/SEB

.. NRC/DSS/CSB I

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0900 0915 1200 1300 1400

  • . 1445 1500 1530 T J Mulford 6/14/77 Ai l

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AGENDA MARK* I LONG TERM PROGRAM.

STRUCTURAL ACCEPTANCE CRITERIA MEETING WITH THE NRC JUNE 17, 1977

  • I INTRODUCTION t

DISCUSSION OF REVISION B OF PLANT UNIQUE ANALYSIS APPLICATION GUIDE Lurich CONTINUATION DISCUSSION OF INCREASED ALLOWABLE STRESSES FOR CLASS MC VESSELS STATUS REPORT ON COLUMN BUCKLING TEST-PHASE II CLOSURE Adjournment MULFORD/SOBON COOPER COOPER COOPER MANGRUM SOBON

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