ML19329F328

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Summary of 780913 W/Util,Bechtel Corp & B&W in Bethesda,Md Re NRC 771111,780224 & 0830 Requsts for Addl Info on Main Steam & Process Steam Piping,Reactor Coolant Pump Cooling & Fuel Cask Drop
ML19329F328
Person / Time
Site: Midland
Issue date: 10/23/1978
From: Hood D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8006250417
Download: ML19329F328 (4)


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NUCLEAR REGULATORY COMMISSION lT. '

E WASHINGTON, D. C. 20555 k...../

October 23, 1978 Docket Nos.

APPLICANT:

Consumers Power Company FACILITY:

Midland Plant, Units 1 & 2

SUBJECT:

SUMMARY

OF SEPTEMBER 13, 1978 MEETING ON INFORMATION REQUESTED BY THE AUXILIARY SYSTEMS BRANCH On September 13, 1978, the NRC staff met in Bethesda, Maryland with Consumers Power Company (CPCO), Bechtel Associates, and the Babcock &

Wilcox (B&W) Company. Attendees are listed in Enclosure 1.

The purpose of the meeting was to discuss three matters in the requests for additional information by the staff's Auxiliary Systems Branch, contained in letters dated August 30, 1978; February 24,1978; and November 11, 1977.

Main Steam and Process Steam Piping In request 010.43, the staff noted that the design of the main steam and process steam piping over the auxiliary building roof is based upon specific break locations for the non-seismic portions of the steam piping..

which includes about 1800 feet of piping. The staff position was that the Midland piping be designed to seismic Category I requirements, or that the applicant demonstrate that cold shutdown would not be precluded in the event of a pipe break postulated anywhere in the non-seismic portion of the main steam and process steam lines.

CPC0 stated that break locations in this piping were based upon the stress criteria of Branch Technical Position MEB 3-1.

These criteria are applicable to seismic Category I piping. The stress analyses for this piping and its supports included OBE and SSE loadings. CPC0 stated that the only at2as where this piping did not meet the more stringent seismic Category I requirements were those portions imposing Appendix B,10 CFR Part 50.

The staff indicated that the CPC0 response to this request should also identify

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all safety-related equipment near this piping, and describe how such equip-ment is protected from the effects of a rupture. CPC0 stated that the items of concern were (1) the chases for the heating, ventilation and air conditioning systems, (2) the control room, and (3) the cable spreading rooms. CPC0 will also submit information on an assumed process steam line break above the spent fuel pool. CPC0 described how each of these areas is protected by concrete walls and described additional restraints that had been added adjacent to the control room.

THIS DCCUMENT CONTAINS j

P00R QUAUTY PAGES

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Reactor Coolant Pump Cooling This discussion was based upon staff requests 010.12, 010.26, and 010.48 which address the ability of the reactor coolant pump to operate without component cooling water. The staff stated the concerns were loss of pump seals and possible pump seizure. The staff also stated that these matters had been appealed in early September 1978 by another applicant, Public Service Electric & Gas Company on Salem Unit 2, and referred CPC0 to the results of that meeting.

A related request,10.S0,, was discussed which regards the potential damage to pump seals following a loss of offsite power in conjunction with the assumption of operator action to inadvertently close a valve in the seal injection line. CPC0 will also submit a report by General Electric Company on the test results of seal leakage.

Fuel Cask Drop Relative to request 010.46, CPC0 described various measures under con-sideration to prevent the fuel cask crane from dropping a cask (e.g.,

additional rigging) and from precluding a cask from tipping into the spent fuel pool. The measure to be implemented will be identified in the response to this request.

The staff referred CPC0 to the SER for North Anna for an example of the

.information needed in regard to the new liigh-density fuel rack design which is being considered for Midland.

CPC0 stated that responses to each of the above requests will be submitted October 20, 1978 by Revision 14 to the FSAR.

J - s H e: D Darl Hood, Project fianager Light Water Reactors Branch 4 Division of Project Management l

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ENCLOSURE List of Attendees, September 13, 1978 NRC Darl Hood Phil Matthews Bill LeFave Randy Stephens Vic Benaroya Scott Newberry Jerry Mazetis i

R. J. Kiessel Consumers Power Comoany Jim Zabritski Mike Solerno Bechtel Jerry Clements Dale Messing David Tooker Mike Pratt Babcock & Wilcox Roland Reed Jim Agar 4

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consumers Power Campany ces:

Michael I. Miller, Esq.

Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Judd L. Bacon, Esq.

Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 o

Mr. Paul A. Perry Secretary Consumers Power Ccmpany 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.

One IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Drive Midland, Michigan 48640 Frank J. Kelley, Esq.

Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Windell Marshall Route 10 Midland, Michigan 48640 Mr. S. H. Howell Vice President Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201

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