ML20235C735

Rept to ACRS in Matter of Preliminary Aspects of Lilco Application for CP for Proposed Shoreham Nuclear Power Station,Unit 1

ML20235C735
Person / Time
Site:	05000000, Shoreham
Issue date:	07/05/1968
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML20235B311	List: IA-87-111, Submits Rept on Plant,As Discussed in ACRS 150th Meeting on 721012-14.Listed Items Can Be Resolved During Const & Facility Can Be Constructed W/Reasonable Assurance for Operation W/O Undue Risk to Public Safety IR 05000254/1972009 IR 05000358/1972003 IR 05000358/1973001 IR 05000358/1973002 IR 05000358/1973003 IR 05000358/1973005 IR 05000358/1973006 IR 05000358/1973007 IR 05000358/1974001 IR 05000358/1974002 IR 05000358/1974003 IR 05000358/1975004 ML20235B308 ML20235B364 ML20235B401 ML20235B405 ML20235B424 ML20235B456 ML20235B461 ML20235B465 ML20235B477 ML20235B488 ML20235B507 ML20235B552 ML20235B582 ML20235B585 ML20235B588 ML20235B605 ML20235B618 ML20235B623 ML20235B649 ML20235B656 ML20235B662 ML20235B670 ML20235B679 ML20235B683 ML20235B687 ML20235B702 ML20235B708 ML20235B713 ML20235B714 ML20235B718 ML20235B720 ML20235B730 ML20235B734 ML20235B748 ML20235B754 ML20235B762 ML20235B764 ... further results
References
FOIA-87-111 NUDOCS 8709240556
Download: ML20235C735 (3)

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-JFFHCHAL USE4NL M5 1968 U. S. ATOMIC ENERGY COMMISSION DIVISION OF REACTOR LICENSING REPORT TO ADVISORY COMMITTEE ON REACTOR SAFEGUARDS IN THE MATTER OF PRELIMINARY ASPECTS OF LONG ISLAND LIGHTING COMPANY'S APPLICATION FOR A CONSTRUCTION PERMIT FOR ITS PROPOSED SHOREHAM NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-322 8709240556 070721 PDR FOIA MENZB7-111 PDR Note by the Director, Division of Reactor Licensing The attached report has been prepared by the Division of Reactor Licensing for the use of the Advisory Committee on Reactor Safeguards.

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%. E E uvud"aua v was %v&M I. INTRODUCTION The Long Island Lighting Company (LILCO) has submitted an application, filed May'15, 1968, for a construction permit and operating license for a nuclear electric generating plant to be called the Shoreham Nuclear Power Station, Unit 1. The plant will initially consist of a single BWR unit and is to be located on a 450 acre site on the north shore of Long Island, adjacent to the Brookhaven National Laboratory. The unit is initially to be operated at a power level of 1593 Mwt, but the applicant anticipates that it will be capable of operation at powers up to 1665 Mwt.

The nuclear steam supply system will be provided by GE and Stone and Wcoster Engineering Corporation will design the balance of the station and act ar construction managers. Construction work will be subcontracted.

LILCO has essentially no experience in the nuclear field other than that as a member of APDA, PRDC and ESADA.

II. HICHLIGHTS OF THE APPLICATION The Shoreham plant will use a boiling water reactor very similar in general design and power level to the Vermont Yankee Nuclear Power Station, Unit 1. The major difference is that the primary containment-vapor suppres-sion system will consist of a steel-lined, reinforced concrete structure rather than the usual light bulb and torus steci vessels. In addition, the  !

radioactive waste gas system will provide for a longer holdup period (8 hrs, to 3 days) than the 30 minutes generally provided in BWR plants and there will

. be no stack so that gases will be released from a vent on the reactor building 1

roof. The effects of not having an elevated stack release in the event of an

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accident will have to be considered in relation to the relatively small exclu-sion distance of 1000 f t. (305 meters) provided by the proposed site to assure that' potential doses are acceptable.

Another unusual feature of the proposed facility is that one of the redun-cant sources of "offsite" power (Criterion 39) is to be provided by a 55 Mw ^'

gas turbine-driven generator located on the site. Redundant sources of "onsite"  !

electric power will be provided by two stand-by diesel generators.

1 The proposed site has an unusual feature in that a Nike missile base is 'i located within the general bounds of the site, 4000 f t. from the proposed i s i reactor location. The potential interaction of these facilities will be con-sidered in the review.

At the applicant's request, a meeting has already been held to discuss the performance requirements and the proposed design of the flexible seal-joint at the juncture of the walls of the concrete primary containment and the base slab of the plant. Additional analysis and possibly some test work relative to this design detail is indicated.

III. CONCLUSION On the basis of our preliminary review of' the application, the only major potential problem area identified is the unique reinforced concrete primary containment, and we expect that this can be resolved satisfactorily.

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