ML20072J868

Confirms Statements Re Compliance W/Reg Guide 1.62 Listed in Encl to NRC .No Seal Cooling Required for LPCI Pumps as Long as Sys Is Pumping from Suppression Pool & Temp Below 212 F.Rhr Valves Normally Aligned for LPCI Operation

ML20072J868
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	03/22/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.062, RTR-REGGD-1.062 SNRC-850, NUDOCS 8303300238
Download: ML20072J868 (5)

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j =_.,! LONG ISLAND LIGHTING COM PANY SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD + WADING RIVER. N.Y.11792 Direct Dial Number March 22, 1983 SNRC-850 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Compliance With R.G. 1.62 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

In enclosure four to NRC letter dated January 6, 1983 (A. Schwencer to M. S. Pollock), LILCO was requested to confirm the following statements:

1) As long as the LPCI system is pumping from the suppression pool and ghe suppression pool tem-perature is below 212 F, no seal cooling is required for the LPCI pumps. Also, normal secondary containment ventilation is sufficient to cool the LPCI pump areas until the Reactor Standby Ventilation System is actuated.

2) The Residual Heat Removal (RHR) non-essential flow path valves are normally aligned correctly (closed) for LPCI operation.

3) The RBCLCW system is not needed for the cooling of any safety functions other than the RHR shut-down cooling mode & spent fuel pool cooling.

4) The Service Water System is not needed for the first ten minutes following an accident (with the excep-tion of diesel generator cooling) and it can be aligned as two separate safety grade divisions by manipulating, from the control room five valves and starting a miximum of two pumps. For diesel generator cooling, the Service Water pumps start when the diesels start and five valves have to be manipulated fo; alignment into two separate safety grade divisions.

830330023e 83032g DR ADOCK 05000322 QQQf V

PDR FC-8935.1

March 22, 1983 SNRC-850 Page 2 ,

5) The Labeling for the system Level manual initiation switches (A and B) for the core spray system will be appropriately. changed to reflect the fact that other systems in addition to the core spray system-are actuated by the same switch. This change should be done in accordance with good Human Factors engineering principles. The Human Factors Branch (HFB) will review this change before fuel load.

LILCO does hereby confirm the above items to be correct with'the following clarifications provided relative to items (4) and (5).

As stated during our meeting with members of your staff on December 16, 1982, after any design basis event, area cooling to support residual heat removal (LPCI mode) pump operation would not be required prior to ten minutes. Area cooling is provided by unit coolers which are a subsystem of the reactor building standby ventilation system. During the detailed in-house engineering and QA review of item (4) above, it was noted that, during certain design basis events, the unit cooler subsystem would operate in conjunction with the RBSVS cooling coils to remove latent and sensible heat and thereby support RBSVS design function (i.e. maintain reactor building secondary containment negative pressure). The unit cooler subsystem and RBSVS cooling coils are supplied by the safety related chilled water system which utilizes the reactor building service water system as a heat sink. The safety related chilled water system is designed to operate during all normal, shutdown, and design basis accident conditions without loss of function.

In the unlikely event that service water flow should be interupted, the thermal inertia of the continously circulating chilled water in the safety related chilled water system would be sufficient to support RDSVS cooling coil and unit cooler subsystem requirements

. for 3 to 5 minutes without a significant increase in secondary containment pressure. Service water flow would be restored by performing the same operator actions as those required to provide diesel generator cooling requirements (i.e. manipulation of five valves and starting a maximum of two pumps) . However, cooling requirements for the diesel generators precede those of RBSVS, consequently the safety related chilled water system is assured of an adequate supply of cooling water and would therefore continue to meet the needs of the RBSVS cooling coils and unit cooler sub-system.

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o March 22, 1983 SNRC-850 Page 3 j Relative to item (5) above, after a preliminary review of the core spray manual initiation logic for those other systems (or portions of systems) which are actuated from the same pushbutton, the following proposed labeling changes (enclosu're 1) will'be submitted to LILCO's human factors consultant, General Physics Corporation, for evaluation of potential impact to the current control room configuration.

LILCO feels that these confirmations and related clarifications are sufficient to address NRC Staff concerns in this area. Should you have any further questions with regards to this issue, feel free to contact this office.

Very truly yours, J. L. Smith Manager, Special Projects Shoreham Nuclear Power Station DWD:bc Enclosure cc: J. Higgins All Parties Listed in Attachment 1

Enclosure 1 The following systems The followingqsyst( .s (or portions of systems) . (or portions of systems) are actuated by this switch ' are actuated by this switch Core Spray-A 4 Core. Spray B Diesel Generator,101 Diesel Generator 102 Diesel Generator 103 Diesel Generator 103 RBCLCW A Valves RBCLCW B Valves Reactor Building Service Water Reactor Builing Service Water System A Valves _ System B Valves

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.._i ATTACHMENT 1 Lawrence Brenner, Esq. Herbert H. Brown, Esq.

Administrative Judge Lawrence Coe Lanpher, Esq.

Atomic Safety and Licensing Karla J. Letsche, Esq.

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

Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge 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 Board Panel ' San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Stephen B. Latham, Esq.

Tuomey, 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 l Washington, D.C. 20555 l

Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.

l 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. ,

State of New York James Dougherty Department of Public Service 3045 Porter Street Three Empire State Plaza Washington, D.C. 20008 Albany, New York 12223 1

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