ML20125C571

Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks

ML20125C571
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, 05000355
Issue date:	09/09/1976
From:	Guibert J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9212110237
Download: ML20125C571 (4)

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% UNITt3 STATES s t NUCLEAR REOULATORY COMMIS$10N o WASHINGTON, D. C. 20048 5  !

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,/ September 9, 1976 DOCKETS NOS.: 20, 50-237, 50-245, 50-249, 50-254, 50-259, 50-219, 50-260, 50J263, M- 50-265, 50-271, 50-277, 50-278, 50-293, 50-296, 50-298, 50-321, 50-324, 50-325, 50-331, 50-333, 4 50-341, 50-354, 50-355, and 50-366.

LICENSEES: Boston Edison Company, Carolina Power & Light Company, Commonwealth Ediron Company, Detroit Edison Company, Georgia Power Company Iowa Electric Light & Power Company, 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 and Gas,. Tennessee Valley Authority, Vemont Yankee Nuclear Power Corporation.

FACILITIES: Oyster Creek Nuclear Generating Station, Nine Mile Point Unit 1. Pilgrim 1. Dresden Units 2 and 3, Millstone Unit 1, Quad Cities Units 1 and 2. Monticello, Peach Bottom-Units 2 and 3 Browns Terry Unit 1, 2 and 3. Vermont Yankee, Hatch Units i and 2, Brunswick Units 1 and 2, Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Femi Unit 2, and Hope Creek Units 1 and 2.

SUiHARY OF MEETING HELD ON AUGUST ~12, 1976 WITH REPRESENTATIVES OF THE MARK I OWNER'S GROUP On August 12, 1976, a meeting was held in San Jose, California with representatives of the Mark I Owner's Group, General Electric Company (GE),

EPRI. and their technical consultants. The purpose of the meeting was to discuss the following Long Tem Program tasks: (1) the 1/12 Scale Three-Dimensional Pool Swell Testing program, (2) the Pool Swell Analytical Model Development program, (3) the Flexible Cylinder Testing program, and (4) condensation loads and the 4T High Temperature Testing program. Enclosure 1 is a list of meeting attendees. Enclosure 2 contains the meeting agenda.

SUMMARY

C. Sullivan, EPRI, provided an overview of the Long Term Program tasks which EPRI is conducting on behalf of the Mark I Ownt.c's Group. The slides used in this presentation are contained in Enclosure 3.

B. Liang and K. Blahnik, Stanford Research Institute (SRI), described the 1/12 Scale Three-Dimensional Pool-Swell Testing program which SRI is performing for EPRI. The slides used in this presentation are contained in Enclosure 4. The NRC staff expressed the; following concerns related to 9212110237 760909 PDR ADOCK 05000219 P PDR

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this testing program:

1. Adequate justification for the selection of a 1/12 scale facility has not been provided.

2. Adequate justification for the selection of a nraight torus sector has not been provided.

I 3. The fourteen instrumentation channels associated with the test j

facility do not appear to be adequate.

4. An instrumentation error analysis should be performed prior to.

commencement of testing.

5. Adequate justification for the isothermal assumption used in the test facility scaling has not been provided.

! P. Nakayama and B. Chan, JAYCOR, described the program for development of an analytical model for the post-LOCA hydrodynamic response of the Mark I pressure suppression pool which JAYCOR is perfonning for EPRI. Representatives of the Mark I Owner's Group stated that it was their intention to utilize

! the resulting computer code model, as validated by 20 and 3D test results, to predict plant-unique hydrodynamic pool swell loads for the Long Term Program. Enclosures 5 and 6 contain the slides used in this presentation.

! G. Sliter and J. Carey, EPRI, described the analytical and testing programs which EPRI is conducting to assess load mitigation from fluid / structural

. interaction on the ring header. Enclosure 7 contains the slides used in their presentation. The NRC staff expressed the following concerns related to this testing program:

l 1. Use of fixed end supports to restrict beam rotation during the water impact-tests would assure conservatism in the test results and would 4 be more representative of the true end conditions than pinned end supports.

2. Fluid / structural interaction should be investigated for othe;' structures (i.e., the torus shell) as well as the ring header.

Bf Sobon, GE, reviewed the bases for the Mark I Owner's Group position that boundary-loads from steam condensation need not be considered in the

Short Term Program. He stated that (1) the magnitude of the steam condensation boundary loads is no higher than that of the safety / relief valve loads, and (2) the characterization of the effects of boundary loads resulting from steam condensation is similar to that of the safety / relief _ valve loads (i.e.,

a fatique concern).

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At the request of the Mark I-Owner's Group, the NRC- staff provided information on the status of the containment-related research programs being conducted

by Lawrence Livermore Laboraties (LLL) for the NRC. Representatives of the Mark I Owner's Group suggested that a mutual exchange of information between their consultants and LLL related to the development of pool swell analytical models would be desirable. The NRC staff stated that any contact

between the Owner's Group and LLL should be arranged through J. Guibert. NRC.

4 R. Petrokas, NUTECH, reviewed the status of load mitigation testing efforts i currently in progress. Enclosure 3 contains the slides used in his-

presentation. He stated _that initial testing has identified several devices which are very promising and that, after addional open-tank testing, a more rigorout testing program will commence.

John'C. Guibert

Operating Reactors Branch #3 l Division of Operating Reactors

Enclosures:

1. Attendance List

2. NRC Long Term Program Review 1 3. EPRI Long Term Program Tasks

4. Scale 3-D Mark I Model

. 5. JAYCOR program Definition and Objectives j 6. Hydrodynamic Response of Mark I Suppression Pools

7. EPRI - Water Impact Tests

8. Mark I Loads Mitigation Screening

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• B. C. Rusche *0 ELD

• E. G. Case *0I4E (3)

• V. Stello C. Parrish

• K. R. Go11er NRC Participants d

D. Eisenhut *ACRS (16)

T. J.-Carter T.-B. Abernathy

. J. Reece J. R. Buchanan

• D. L. Ziemann - D. Thompson

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