ML19225C506

Fire Protection in Operating Nuclear Power Stations,Prairie Island Station SER Review, Interim Rept

ML19225C506
Person / Time
Site:	Prairie Island
Issue date:	06/21/1979
From:	Randy Hall, Macdougall E BROOKHAVEN NATIONAL LABORATORY
To:	Ferguson R Office of Nuclear Reactor Regulation
References
CON-FIN-A-3107 NUDOCS 7907310175
Download: ML19225C506 (4)

Text

IIITERIM REPoli

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Contract Program or Project

Title:

Fire Protection in Operating Nuclear Power Stations Subject of this Document: Prairie Island 1 and 2 Safety Evaluation Report Review Type of Document: Letter Report Author (s): R.E. Hall and E.A. MacDougall Date of Document: June 21, 1979 Respoasible !!?C Individual Mr. R.L. Fergus and t!RC Of fice or Division: I; ant Systems Branch U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1his document was prepared primarily for prelininary or internal use. It has not received full review and approval. Since there nay be substantive changes, this document should not be considered final.

Brookhaven !!ational Laboratory Upton, fly 11973 Associated Universities, Inc.

for the U.S. Department of Energy Prepared for 448 357 U.S. I!uclear P.egulatory Co.mnission Washington, D. C. 20555

.L_ Under Interagency Agreement EY-76-C-02-0016 u !aC FIl! I:o. A-3107 l

79073@om5 It1TERIM REPORT

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x :~r  :- . : e~ %, y e 2.:5 2144 June 21, 1979 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Robert L. Ferguson Plant Systems Branch

Subject:

Fire Protection in Ooerating Nuclear Power Stations

, Prairie Island 1 anc 2 Safety Evaluation Recort Review The Safety Evaluation Report, as develcped jointly by the NRC staff and Brookhaven National Laboratory, (ENL), adequately reflects the concerns and recanmendations of the consultants. Throughout 'he reevaluation of Prairie Island 1 anc 2 there has been general agreement betwc an the NRC staff and the BNL consultants. Based on present data, the proposed fire protection, as set forth in the SER, will give reasonable assurance that the health and safety of the public is not endangered. The following exception represents a differing engineering point of view that should be evaluated by the NRC staff.

alve Sucervision - DSER Sc ..un 4.3.1.3 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves. The present proposal of admini-strative controls or locks is unacceptable. See Letter dated July 13, 1977 to Mr. R.L. Ferguson fran Mr. R.E. Hall .

Portable Gas Cyiinders - DSER Section 5.12.6 We recommend that tne 2 large flammable liquified gas cylinders located at elevation 715 feet in the Auxiliary Building be relocated out of the building.

We recanmend that pressure regulators be installed and the gas piped into the lacoratory in accordance with applicable NFPA Standards, including No. 58.

The preceding statements are based on a detailed reevaluation of the fire protection progran as implemented by the Northern States Power Company at the Prairle Island 1 and 2 Nuclear Power Station. The analysis covered a review of the fire prevention, detection and suppression capabilities of the plant as interf aced with the nuclear systens requirements. This was acccmplished by utilizing a review team conce?t with members fran Brockhaven National Lab o ra-tory (BNL) and tne Nuclear Regulatory C.cgpission Division of Operating Re-actors stat t. .7 44u 330 t ,

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R. L. Ferguson June 21,1979

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The fire protection evaluation for the Prairie Island 1 and 2 plant is based on an analysis of documents submitted by the Northera States Power Con-pany to the Nuclear Regulatory Commission and a site visit. The site visit was conducted by Mr. E. Sylvester and V. Panciera of the NRC; Mr. I. Asp of Gage-Babcock and Associates, Inc. under contract to Brookhaven National Laboratory; and Mr. J. Riopelle consultant to BNL. Mr. Riopelle was under contract to BNL to review the manual fire fighting capabilities of the station along with administrative controls.

The Prairie Island 1 and 2 review has been conducted under the direction af Mr. E. A. MacDougall and myself of Reactor Engineering Analysis Group at BNL.

We have reviewed the analyses submitted by the licensee and have visited the facility to examine the relationship of safety-related components, systems and structures with b'*h conbustibles and the associated fire detection and suppression systems. Our review has been limited to the aspects cf fire pro-tection related to the protection of the public fran the standpoint of radio-logical health and safety. We have not considered aspects of fire protection associated with life safety of onsite personnel and with property protection, unless they impact the health and safety of the public due to the release of radioactive material . The proposed modifications represent a significant increase in the level of protection against serious fire associated hazards.

Sincerely yours, '

/

h obert E. Hall , Group Leader C

Reactor Engineering Analysis REH:EAM:sd

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by

DISTRIBUTION M. Antonetti 1

1. Asp 1 V. Benaroya 1 E. Blackwood 1 W. Butler 1 R. Cerbone 1 D. Eisenhut 1 R. Feit 1 R. Ferguson 5 R. Hall 1 S. Hanauer 1 E. Imbro 1 W. Kato 1 J. Klevan 1 G. Lainas 1 C. Long 1 E. MacDougall 1 J. Riopelle 1 V. Stello 1

1. Telford 1 H. Todosow 2

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J. Townley Jg 1 NRC - Division of Technical Irformation and Control 2