ML20077B891

Provides Description of Mods to Portion of Reactor Vessel Water Level Measurement Sys & ECCS Initiation Logic,Based on Agreement Reached During ASLB Hearings

ML20077B891
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/19/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-934, NUDOCS 8307250477
Download: ML20077B891 (6)

Text

{{#Wiki_filter:t i LONG ISLAND LIGHTING COMPANY kNf SHOREHAM NUCLEAR POWER STATION r.,w - w#. - u m s F.O. BOX 610 NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 Direct Dial Number July 19, 1983 SNRC-934 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Shoreham Water Level Measurement System Shoreham Nuclear Dower Station - Unit 1 Docket No. 50-322

References:

1. Review of Shoreham Water Level Measurement System, SLI 8221, November 1982, Rev. 1. 2. Resolution of S.C. Contention 3/ SOC Contention 8 --- Reduction of Inadequate Core Cooling, December 8, 1982.

Dear Mr. Denton:

As a result of an agreement reached during the Shoreham ASLB hearings, LILCO has agreed to modify portions of the reactor vessel water level measurement system and ECCS initiation logic. These modifications are to assure that early operator action is not required in the event of an instrument line failure (leak or break) accompanied by a single additional component failure. See subparagraph II.B1, B2 and B3 of Ref. 2. The purpose of this submittal is to describe the proposed modification which will accomplish this objective. The Shoreham response to events of interest is reported in Section 5 of Reference 1. Reference 1 is a Shoreham specific study which evaluates the recommendations of the BWROG generic report SLI-8211, Review of BWR Reactor Water Level Measurement System. In summary, this analysis shows that early operator action would be required to initiate either HPCI or RCIC in the event of a loss of the reference leg connected to the level sensor which is controlling feedwater combined with a failure of a level sensor, control component or power supoly bus associated with the intact reference leg instruments. The specific level sensors are NO91, A, B, C, D l and the buses are 125VDC A and B. \\ 0 10 F307250477 830719 1 J PDR ADOCK 05000322 k \\\\ P PDR FC 8935.1 u

July 19, 1983 SNRC-934 Page 2 The modifications are illustrated by "before and after" Figures 1 and 2. Figure 1 shows the current complement of level instruments, instrument assignments, and IIPCI and RCIC initiation logic, as well as the associated utilization of DC buses. Figure 2 provides the same information'after the modification has been implemented. Briefly, the' modification consists of adding four level sensors, reassigning initiation and trip signals to the HPCI and RCIC control logic, and modifying DC power distribution to assure that all HPCI control is associated with DC bus B and all RCIC control is associated with DC bus A. The association of these systems with a single bus is acceptable because the turbine controls of each are associated with a single bus. The turbine controls of the HPCI and the RCIC are powered by DC bus B and A, respectively. This modification reassigns the level initiation and trip logic to the same bu.as as the turbine control of each. It can be shown through a failure analysis that the type of failures postulated in Section 5 of Reference 1 are entirely precluded by the proposed modification. As a result of this modification, there will be no known-reference' leg failure scenarios that, when coupled with a single failure which would disable both HPCI and RCIC, require early operator action. The physical modification entails the installation of four new transmitters on existing racks or adjacently located new racks. Instrument piping must be tapped and run to the transmitters and new cables will have to run from the racks in the secondary containment to the Analog Transmitter Trip System panels in the relay room of the Control Building. The existing relay logic for HPCI and RCIC will have to be modified so that it correlates to the new transmitter assignments, and a safety evaluation will be performed in accordance with 10 CFR 50.59. LILT 3 is planning to have this modifiamtion in place and functional prior to the return to service following the second refueling outage. The following is a proposed schedule, based on an August 1983 fuel load, outlining key dates for implementation of this modification:

Jul, ' 19, 198 3 SNRC-934 Page 3 Anticipated approval by NRC 12/83 Completion of conceptual engineering and design review and material procureinent documents 12/84 Equipment Delivery 12/86 Completion of Installation and Testing 8/87 The August, 1987 date is premised on an anticipated second refueling outage at that time. We trust the above is satisfactory. Should you have any questions, please contact this office. Very truly yours, 5 L' ata t.21 J. L. Smith Manager, Special Projects Shoreham Nuclear Power Station RWG:bc Attachment cc: J. Higgins All Parties Listed in Attachment 1 y- - <., ~

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, Lockhart, Hill U.S. Nuclear Regulatory Commission Christoper & 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. 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. David A. Repka, Esq. ~ New York, New York 10016 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ' Matthew J. Kelly, Esq. State of New York Department of Public Service James Dougherty Three Empire State Plaza 3045 Porter Street Albany, New York 12223 Washington, D.C. 20008 e --r- ,w, ..-.,-,-w

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