ML20071A934

Responds to 830106 Request for Addl Info Re Low Pressure Coolant Injection,Core Spray & Rev to FSAR Reflecting Unmonitored Release Points for Turbine Bldg Atmosphere

ML20071A934
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	02/18/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-840, NUDOCS 8302250236
Download: ML20071A934 (3)

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5 LONG ISLAND LIGHTING COMPANY I IFUDP

• SHOREHAM NUCLEAR POWER STATION g

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f P.O. BOX 618, NORTH COUNTRY ROAD e WADIN3 RIVER, N.Y.11792 Direct D!al Number February 18, 1983 SNRC-840 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC Staff Positions and Requests For Additional Information Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Reference:

A. Schwencer letter to M. S. Pollock, dated January 6, 1983, "Shoreham Nuclear Power Station, Unit 1 - Staff Position and Requests for Further Information."

Dear Mr. Denton:

Enclosures (2) and (3) of the above referenced document presented staff positions on Core Spray Injection Valve Logic and indication /

annunciation of LPCI Injection Valve permissive relays, respectively.

As required by the NRC staff, LILCO commits to the following:

Low Pressure Coolant Injection LPCI low pressure permissive relay will be annunciated at panel lHil*PNL601, on annunciator boards A-1 (system A) and A-2 (system B). These annunciators have been located in accordance with good human engineering practices and will be installed prior to fuel load.

Core Spray i Prior to startup after the first refueling outage, LILCO will modify the core spray system injection valve low pressure permissive interlock so as to preclude overpressurization of downstream piping which could occur coincident with a failure of the core spray loop injection check valve. A conceptual design will be furnished to the NRC prior to implementation of modifications.

D i 8302250236 830218 PDR ADOCK 05000322 i

S PDR l F C-8935.1

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C February 18, 1983 '

Mr. Harold R. Denton

-Page 2 After initial startup and until such time as these modifica-tions are complete,.LILCO will (in addition to normal surveillance requirements) demonstrate operability of core spray system check valve lE21-FOO6.(A&B) by verifying that-leakage is within allowable limits;

1) whenever the unit has been'in cold shutdown, after the last check valve-disturbance (i.e. check valve changes-position) prigr to reactor coolant system temperature exceeding 200 F.

2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following check valve disturbance except when in cold' shutdown.

Enclosure (5) of the. referenced document requires that LILCO revise the FSAR to reflect the existence of potentially unmonitored release points for turbine building atmosphere. Accordingly, the following information will be incorporated into a future ammendment to the FSAR.

1) A description of those lines identified in the referenced document

2) Expected and maximum flow rates through those lines,

3) Justification for concluding that contamination levels in those lines will not be more significant than the radio-activity contamination level in the monitored turbine building exhaust, and

4) Dcsign improvements recently completed for one of those lines (i.e. installation of a seal plug on the RFPT head tank vent).

LILCO believes these commitments to be-in compliance with NRC Staff requirements and that these issues are resolved. Should you require further information, please feel free to contact this office.

Very truly yours,

.k

. L. Smith Manager, Special Project Shoreham Nuclear Power Station DWD:bc cc: J. Higgins All Parties Listed in Attachment 1

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ATTACHMENT 1 ,

Lawrence Brenner, Esq. Herbert H. Brown, Esq.

Administrative. Judge Lawrence Coe Lanpher, Esq.

Atomic Safety and Licensin9 Karla J. Letsche, Esq.

Board Panel ' Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Commission Christopher & Phillips Washington, D.C. 20555 8th Floor 1900 M Street, N.W.

-Washington, D.C.- 26336---- -- --

Dr. Peter A. Morris Administrative Judge l Atomic Safety and Licensing Mr.. Marc W. Goldsmith

! Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 Waltham, Massachusetts 02154 Dr. James H. Carpenter MHB Technical Associates ,

Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K l

Board Panel San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

, Stephen B. Latham, Esq.

i Twomey, Latham & Shea Daniel F. Brown, Esq. 33 West Second Street Attorney P.O. Box.398

( Atomic Safety and Licensing Riverhead, New York 11901 Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 -

Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.

• 9 East 40th Street Bernard M. Bordenick, Esq. New York, New York 10016 David A. Repka, Esq.

U.S. Nuclear Regulatory Commission Washington- D.C. 20555 ,

Matthew J. Kelly, Esq.

l State of New York i

Department of Public Service l Three Empire State Plaza

Albany, New York 12223 I

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