ML20141N347

Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl

ML20141N347
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, 05000000, 05000355
Issue date:	05/20/1977
From:	Guibert J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20141N278	List: ML20141N277 ML20141N301 ML20141N318 ML20141N347 ML20141N358
References
FOIA-85-782 NUDOCS 8603060237
Download: ML20141N347 (4)

Text

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i 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, i 50-296, 50-293, 50-321, 50-324, 50-325, 50-331, 50-333, j 50-341, 50-354, 50-355, ana 50-366.

LICENSEES: Boston Edison Company, Carolina Power & Light Company, ,

, Commonwealth Edison Company, Detroit Edison Company,  :

i Georgia Power Company, Iowa Electric Light & Power Com- .

t pany, Jersey Central Power & Light Company, Nebraska' I l Public Power District, Niagara Mohawk Power Corpdration, Northeast Nuclear Energy Company, Northern States Power Company, Philadelphia Electric Company, Power Authority l

of the S*. ate of New York, Public Service Electric and Gas, Tennessee Valley Authority, Vemont Yankee Nuclear i Power Corporation FACILITIES: Oyster Creek Nuclear Generating Station, Nine Mile Point t Unit No.1, . Pilgrim Unit No.1, Dresden Units Nos. 2 and I  ; 3, Millstone Unit No.1. Quad Cities Units Nos. I and 2, Monticello, Peach Bottom Units Nos. 2 and 3 Browns Ferry i

Units Nos. 1, 2 and 3. Vermont Yankee, Hatch Units Nos. 1 and 2, Brunswick Units Nos. I and 2, Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fenni Unit No. 2, and Hope Creek Units Nos. I and 2.

SUMMARY

OF MEETING HELD ON APRIL 11, 1977 WITH REPRESENTA-

. TIVES OF THE PARK I OWNER'S GROUP i

On April ll,1977, a meeting was held in Bethesda, Maryland with represen-i .

tatives of the Mark I Owner's Group and the General Electric Company. The i purpose of the meeting was to discuss the stri ural ac.ceptance criteria i

, for the Mark I Containment Long Term Program. aclosure 1 is a list of ,

the meeting attendees.

• Summa ry It was emphasized, at the outset, that this meeting was the first of several anticipated working sessions between the NRC staff and the representatives

, of the Mark I Owner's Group leading to the establishment of NRC-approved structural acceptance criteria for application in the Long Term Program ,

Plant Unique Analyses.

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W. Cooper, Teledyne, reviewed the infomation presented in two preliminary reports, TR-2278(b) and TR-2278(c), which had been transmitted to the NRC

! on behalf of the Mark I Owner's Group by GE on April 4,1977. Copies of i these reports may be obtained from J. Guibert (X28256).

I

! In general, the approach proposed by the Mark I Owner's Group is to evaluate

, all structural elements in the Mark I containment system utilizing the structural design criteria of the latest ASME Section III Code Addenda.

When complete application of these criteria result in hardships or unusual difficulties without a compensating increase in the level of quality and safety, other structural acceptance criteria may be considered, on a case basis and subject to NRC approval.

l The Owner's, Group has proposed to establish a distinction betweeri external pressure boundary components, internal pressure boundary components, and internal structures. As stated, the major purpose of this distinction between the two types of pressure boundary components is to permit the I

e consideration of different load combinations or service limits when such i

considerations can be justified technically. Differing load combinations

,  ; and service limits may be applied, as a . function of time, depending upon the subsequent service requirements ^on the sfriIctrraTTo'#ponent following

, , the loading event.

! In addition to the Design and Service Level Limits currently specified in

, the proposed ASME Code' revision, the Owner's Group has proposed a new service level limit designated as Level E. As proposed, this special limit i inay be used in situations where failure of an element under a particular I loading event is acceptable in that its failure would not impair contain-I ment function and integrity. Representatives of the Owner's Group stated that this

• service level limit may be useful for those instances where i failure of the element does not impair containment function, and when replacement of an element after a postulated LOCA event is a more acceptable alternative than modifications to preclude damage. It should be noted that this concept is not specified within the ASME Code, since the Code does not provide rules which pemit an item to fail.

I The NRC staff made the.following coments and observations on the proposed program:

a. The acceptability of the concept of changing service level limits for a particular structural elements .as a function of time during a postulated accident event will require further~di'5FussToii both within i the NRC staff and with the Mark I Owner's Group. Essentially, two areas need to be explored further: (1) whether this approach is philosophically a departure from the Code, and (2) how such an approach would be applied to a particular structural evaluation. The NRC staff requested that the Owner's Group provide, at the earliest time practicable, tables which would indicate load combinations and the e.

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associated proposed service . level limits (as a function of time) for each major structural element in the Mark I containment system.

1 l b. The acceptability of the proposed service Level E limit and the I f proposed approach of distinguishing between internal and external pressure boundary components will require further internal staff

...t discussion. .

! c. The table of load combinations presented in Technical Report TR-2278(c) l does not include a combination of DBA loads and SRV loads. Further documented justification for the omission of this load combination will be required.

I A brief discussion of the preliminary results of the Mark I Owner's Group's testing program to investigate column buckling was held. The Owner's Group agreed to submit the results of this program to the NRC staff when they become g

available.

u Y

, Jo n Guibert, Technical Assistant to the Assistant Director for i Operational Technology Division of Operating Reactors i

Enclosure:

Attendance List i

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NRC/ MARK I OWNERS GROUP MEETING ON LTP STRUCTURAL ACCEPTANCE CRITERIA APRIL 11, 1977 Name Organization J. Guibert DOR /NRC R.-J. Stuart '

EB/ DOR /NRC H.' L. Bramer MEB/ DSS /NRC S. Klein EB/ DOR /NRC J. Strosnider EB/ DOR /NRC l R. Gamble EB/ DOR /,tiRC ,

i B. D. Liaw ,EB/ DOR /flRC

. G. Bagchi EB/ DOR /NRC -

,C. Hofma g ES/ DOR /NRC f L. V. Sobon GE T. J. Mulford GE E. Mangrum GE -

f R. Broman Bechtel l N. W. Edwards NUTECH W. E. Cooper TES

, i ,-

I. Sihweil. .

SEB/ DSS /NRC i D d Jen3 _ SE)/ DSS /NRC j

R. E. Shewma_kers IE:HQ/NRC A. Hafiz SEB/ DSS /NRC

! L. Shao- EB/ g NRC

! C. Grimes PSB/ DOR /,NRC J. Kudrick CSB/ DSS /NRC

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