ML20214G427

Summary of 761202 Meeting W/Mark II Owners & GE Re Mark II Containment Structural Design & Pool Dynamic Loads Supporting Program.Attendee List & Viewgraphs Encl

ML20214G427
Person / Time
Site:	Nine Mile Point, Susquehanna, Columbia, Brunswick, Limerick, LaSalle, 05000000, Shoreham, Bailly
Issue date:	12/29/1976
From:	Miner S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
CON-WNP-0005, CON-WNP-5 NUDOCS 8605220103
Download: ML20214G427 (12)

Text

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4 UNITED STATES j

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DEC 2 01976 Docket Nos: 50-322, 50-352 & 50-353, 50-358, 50-367 50-373 & 50-374, 50-387 & 50-388, 50 7 50-410 FACILITIES: Shoreham Nuclear Power Station Unit No.1, Limerick Generating Station Units No. I and No. 2, William H. Zininer Nuclear Power Station, Unit 1. Bailly Generatin Station Nuclear No.1. LaSalle County Station Units No. I and No. 2, Susquehanna Steam Electric Station Units No. I and No. 2, WPPSS Nuclear Project No. 2, Nine Mile Point Nuclear Station Unit No. 2.

APPLICANTS: Long Island Lighting Co., Philadelphia Electric Cincinnati Gas and Electric Co., Northern Indiana Public Service Co.,

Commonwealth Edison, Pennsylvania Power and Light Co.,

Washington Public Power Supply System and Niagara Mohawk Power Corporation

SUMMARY

OF MEETINGS HELD ON DECEMBER 2,1976 TO DISCUSS MARK II CONTAINMENT STRUCTURAL DESIGN AND POOL SYNAMIC LOADS SUPPORTING PROGRAM A meeting was held on December 2,1976 between representatives of the Mark II Owners, the General Electric Company and the NRC staff. The purpose of the meeting was to discuss with GE and the Mark !! Owners (1) the method for comgining dynamic loads for structural design and (2) the status of the Pool Dynamics Load Supporting Program. The attendee lists and copies of some of the slides given to the attendees are enclosed.

Copies of the remainder of the slides are available in my office. The major typics discussed are as follows:

A.

Dynamic Load / Response Combinations In Section 5.2.2 of the Dynamic Forcing Function Report (DFFR)

NED0-21061 it is stated that "the peak dynamic responses due to individual loads should be combined in the SRSS method." We indicated this is currently unacceptable.

The General Electric Company stated that they were not asking for blanket approval of the SRSS method but for selective application ofthemethod(figure 1). They further stated the SRSS method has been used for many years for combining rapidly varying dynamic loads / responses and that the method provides adequate margin in design (figure 2). If the absolute sum of the dynamic response method, which is acceptable to the staff, has to be used for all cases there is a high probability that existing plant hardware

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will have to be modified. This will result in delays to a number of Mark II plants. We indicated that the blanket statement as now provided in the DFFR on the use of the SRSS method gave no indication of its application or justification and therefore is unacceptable.

The Mark II owners suggested the following approach to resolve the issue. They will (1) establish a quantitative program to provide details on Dynamic Loads / Response combinations and justifications, (2) provide in January a description of the program, (3) meet with the staff to discuss the program and provide a schedule for its completion, and (4) revise the DFFR when the program is complete.

B.

Pool Dynamic loads Supportinq Program (1) SteamLoads(Chugging)Progran General Electric Company provided the current schedule for the Mark II Supporting Program (fig. 3). The pool swell model report is now scheduled to be completed on January 31, 1971.

l The program for defining the steam loads (chugging loads) l developed by the Mark II ownes consists of a parallel analytical and experimental approach, GE stated their analysis indicates that the single cell tests provide the bounding chugging load. Therefore, the objective of their chugging program will be to first confinn the conservatism of the single cell approach and then to develop a more realistic predictive methodforindividualplants(Fig.4).

The overall chugging program technical strategy (the analytical and experimental program) is shown on Fig.

4.

The analytical approach is to develop an analytical model from first principles and to compile and use all known experimental data to verify and refine the model. As a parallel effort GE is planning a multi vent test and has started the acquisition of equipment.

However, they expect that their analytical approach will resolve the chugging problem and they do not expect to have to run the multi vent tests. The decision on whether to proceed with the tests will be made in January. The analytical program is a Mark I and Mark II owners jointly funded program. The current status of the program is shown in Fig. 5.

s (2) SRI / PRI The SRI /EPRI tests were completed and the report will be available l

the end of February or the beginning of March. The report will be made available to the staff. The Mark II owners have not yet i

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_3, made the detennination whether the tests could be used to satisfy the staff request for air tests. If the tests are applicable they will be used to satisfy this requirement. EPRI has not decided whether to conduct the 1/13 scale single downcomer tests.

f Sydney Miner, Project Manager Light Water Reactors Branch No. 3 Division of Project Management i

Enclosures:

As stated j

CC: Pennsylvania Power and Light Company Comonwealth Edison Company ATTN: Mr. Norman W. Curtis ATIN: Mr. Byron Lee, Jr.

1 Vice President - Engineering Vice President and Construction P. O. Box 767 2 North Ninth Street Chicago, Illinois 60690 Allentown, Pennsylvania 18101 Richard E. Powell, Esq.

Gerald Charnoff, Esq.

Isham, Lincoln & Beale Shaw, Pittman, Potts, One First National Plaza, Suite 2400 Trowbridge & Madden Chicago, Illinois 60670 Barr Building i

hing o 5b06 Mr. William E. Barberich Licensing Engineer Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Robert J. Shovlin, Project Manager Susquehanna Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 i

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ATTENDEES LIST DECEMBER 2, 1976 DYNAMIC LOADS MEETING Burns & Roe NRC P. Hsueh S. Miner C. Anderson J. Kudrick WPPSS G. Lainas G. Gelhaus CFE/EBASC0_

CECO Y. Oktay B. Shelton PP&L Co.

Sargent & Lundy E. Mead R. Crawford Stone & Webster _

Nuclear Services Corp.

R. Klause W. Hennessy F. Schraub S. Chow LILCO PEPC0 H. Chau R. Logue J, Novarro BECHTEL CGE Co.

E. McFarland H. Brinkmann N!PSCO GE J. Dunn

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P. Marriott L. Frauenholz A. Smith

ATTENDEES LIST DECEMBER 2. 1976 STRUCTURAL MEETING CGE U3.C,

5. Miner H. Brinkmann P. Kuo F. Schauer D. Jeng LILCO S. Hou W. Paulson H. Chau J. Novarro GE

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Stone & Webster L. Frauenhciz P. Marriott S. Chow D. Ditmore W. Hennessy A. Smith R. Klause PECO '

Nuclear Services R. Logue F. Schraub S&L PP&LCO B. Erler E. Mead R. Crawford CFE/EBASCO WPPSS Y. Oktay G. Gelhaus BECHTEL Burns & Roe E. McFarland P. Hsuch flIPSCO CECO J. Dunn B. Shelton i

PERSPECTIVE Oil PROBLEM o f'OT PRESSING FOR BLANKET APPROVAL OF SRSS

- BOTH ABS & SRSS ARE EMPLOYED o SRSS APPLICATION IS SELECTIVE

- ACTUAL LOAD NOT EXPECTED TO EXCEED SRSS

- MINIMAL IMPACT IF SRSS EXCEEDED o BLA!!KET REQUIRENENT FOR ABS ll0T APPROPRIATE

- NOT flECESSARY TO ASSURE DESIGN ADEQUACY

- DESIGN IMPACT IS SIGillFICA!!T l

o SRSS IS TECliNICALLY JUSTIFIED Ifl SPECIFIC APPLICATI0flS l

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OUALITATIVE FACTORS Fig. 2 I!!FLUENCIflG SRSS APPLICATI0il e

ACTUAL LOAD UNLIKELY TO EXCEED SRSS

- LOAD EVEtlTS TIME OVERLAP UNLIKELY l

- RESPONSES RANDOM AMPLITilDE AND PHASE

- RESPONSES VARY RAPIDLY AtlD SHORT DURATI0il

- RESP 0flSE FREQUEf!CIES COMPARABLE S0

- MAX, PEAKS UNLIKELY TO C0lllCIDE

- STRESS / STRAIN RISE AND DECAY RAPIDLY CONSEQUENCES OF EXCEEDIflG STRSS MINIMA'L e

- DYNAMIC LOADS AtlD MODELS CONSERVATIVE

- CODE RULES PROVIDE LARGE DESIGN MARGIN s

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Fig. 3 MARK II SUPPORTING PROGRAM A.

LOCA RELATED ACTIVITIES 1.

4T POOL SWELL TESTS PHASE 11 & III TEST REPORT 12/3V76 PHASE 11 s Ill APPLICATIONS MEMORANDUM V31/77 2

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POOL SWELL MODEL REPORT V31/77 3.

IMPACT TESTS COMPLETE 4.

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MARK 11 SUPPORTING PROGRAM B.

S/RV RELATED ACTIVITIES 1.

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S/RV TESTS PRELIMINARY TEST REPORT 12/31/76 FINAL TEST REPORT 4/30/77 4.

CONSECUTIVE ACTUATION ANALYSIS 6/77 5.

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TEST PLAN 1/2/77 FINAL REPORT

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A Fig. 4 CH u GG I N G-PRcG RA M OVERALL TE C H NI CA L STRATEGY OTHER TESTS g

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