ML20246K664

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Forwards Implementation Rept Re Inadequate Core Cooling Monitoring Sys in Conformance w/NUREG-0737,Item II.F.2,per NRC Request
ML20246K664
Person / Time
Site: Seabrook 
Issue date: 05/12/1989
From: George Thomas
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NYN-89061, NUDOCS 8905180116
Download: ML20246K664 (4)


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New Hampshire e-oe s.momas Vbe President Nuclear Production NYN 89061 May 12, 1989 United States Nuclear Regulatory Conunission Washington, DC 20555 Attention: Document Control Desk

References:

a) Facility Operating License NPF-56, Docket No. 50-443 b) Safety Evaluation Report Related to the Operation of Seabrook Station, Units 1 and 2; NUREG-0896, Supplement No. 5, dated July 1986

Subject:

' Inadequate Core Cooling (ICC) Monitoring System, NUREG-0737, Item II.F.2 Implementation Gentlemen In Reference (b), (Section 4.4.5.4), the NRC concluded that the "Seabrook Station ICC instrumentation system is in conformance with NUREG-0737, Item II.F.2" and stated that an implementation report was required "to complete the staff's review for implementation approval of the installed ICC system and must be provided before 5% power operation is exceeded."

The implementation information required by the NRC is provided in the Enclosure.

Should you require further information on this matter, please contact Mr. Robert E. Sweeney in our Bethesda Licensing Office at (301) 656-6100.

Very truly yours,

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.'Oorge[. Thomas Enclosure 8905180116 890512

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i New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300 = Seabrook, NH 03874 = Telephone (603) 474-9521

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United States Nuclear Regulatory Commission May 12, 1989

" Attention: Document Control Desk Page 2 cc Mr. William T. Russell'

. Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia. PA 19406 L

Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555-NRC Senior Resident Inspector P.O. Box 1149 Seabrook Station, NH 03874

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ENCLOSURE TO NYN-89061 NUREG-0896, Safety Evaluation Report related to the operation of Seabrook Station, Supplement No. 5, required that the following information be L

provided to allow the Staff to complete its review of New Hampshire Yankee's l'

actions on NUREG-0737. Item II.F.2:

Item'fa) notification that the system installation, functional testing, and calibration are complete and test results are available for inspection Responses y

The Inadequate Core Cooling Monitoring (ICCM) system L

installation, functional testing, and calibration has been completed and test results are available for NRC inspection.

Item (b) summary of applicant conclusions based on test results, e.g.,

o performance of the system in accordance with design expectations and within design error tolerances, or o description of deviations from design performance specifications and basis for concluding that the deviations are acceptable

Response

The ICCM system performed in accordance with design requirements. Minor firmware conditions requiring system enhancements were identified during testing. These system enhancements will be implemented prior to exceeding SZ power.

Item (c) description of any deviations of the as-built system from previous design descriptions with any appropriate explanation

Response

The ICCM system was deceribed in SBN-952 dated February 24, 1986.

The ar-built system contains no deviations from that described in SBN-952; however the following two clarifications are provided: i

Item (c) (Continued) o The B train plasma display located at the Shift Technical Advisor's console is powered by a 120 VAC power source. backed by an emergency diesel generator.

It should be noted that NHY does not take credit for the B train plasma display in meeting our commitment for providing Accident Monitoring Instrumentation as required by USNRC RG 1.97.

O The RVLIS page 3 display is used by the operators for obtaining numerical values of the RVLIS parameters on an as-needed basi;.

Item (d) confirmation that the emergency operating procedures (EOPs) used for operator training are complete and conform to the technical content of NRC-approved E0P guidelines (generic or plant specific)

Response

The Emergency Operating Procedures (EOP's) used for operator training are Seabrook Station specific adaptations of the generic Westinghouse Owners Group (WOG) Emergency Response Guidelines which were approved by the NRC in Generic Letter 83-22.

The operator training program utilizes the most.recent revision of these' Emergency Operating Procedures which are complete in all respects and are identical to the procedures used in the plant.

The current revision to these procedures is WOG Rev. lA (Station 1

Revision 6) which has an effective date of December, 1988.

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