ML20071E491

Forwards Response to Generic Ltr 82-28 Re Inadequate Core Cooling Instrumentation Sys Per NUREG-0737,Item II.F.2 Requirements

ML20071E491
Person / Time
Site:	Sequoyah
Issue date:	03/08/1983
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GL-82-28, NUDOCS 8303140234
Download: ML20071E491 (2)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II March 8, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 12 ear Ms. Aden9am:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 50-328 Enclosed is our response to the December 10, 1982 letter (NRC Generic Letter 82-28) from D. G. Eisenhut to "All Licensees of Operating Westinghouse and CE PWRs" regarding inadequate core cooling instrumenta-tion system. As requested by the subject NRC letter, this information is being submitted pursuant to 10 CFR 50.54(f) of the Commission's regulations.

If you llave any questions concerning this matter, please get in touch with J. E. Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Sworn d subsc bed be ore me this day of 1983

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Notary Public O ~

My Commission Expires /

Enclosure cc: U.S. Nuclear Regulatory Commission (Enclosure)

Region II Attn: Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 gov, p gj.r SW palws/M 8303140234 830308 DR ADOCK 05000 An Equat opportunity tEmployer

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• ENCLOSURE RESPONSE TO NRC GENERIC LETTER 82-28 INADEQUATE CORE COOLING INSTRUMEMTATION SYSTEM SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 As. requested in the December 10, 1982 letter from D. G. Eisenhut, we have completed our review of TVA's previous responses related to NUREG-0737, II.F.2 requirements. The following is our response to each of the three items in the subject letter.

NRC Recuirement - Item 1 Within 90 days of the date of this letter, identify to the Director, Division of Licensing, the design for the reactor coolant inventory system selected and submit to the Director, Division of Licensing, detailed References schedules for its engineering, procurement, and installation.

to generic design descriptions and to previous submittals containing the required information, where applicable, are acceptable.

TVA Responses TVA plans to install the Westinghouse reactor vessel10, level instrumentation 1982 letter as system (RVLIS) which NRC has stated in the December

" acceptable for tracking reactor coolant system inventory."

Details of the design of the RVLIS are given in the proprietary version and-nonproprietary version of:

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Summary Report, Westinghouse Reactor Vessel Level Instrumentation System for Monitoring Inadequate Core Cooling '

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(UNI plant). ,

This sunmary report was submitted to the NRC on January 2, 1981 by letter As stated in my August 6 and fr5m L. M. Mills to A. Schwencer (NRC).

November 22, 1982 letters to you we plan to complete the installation NRC has of the RVLIS during the second refueling outage for each unit.

accepted this schedule for unit 1 by issuance of a revised license ,

condition, 2.C.(23)H.2 in License Amendment 23 to Facility Operating '

License, dated December 27, 1982.

i NRC Requirement - Item 2 Within 90 days of the date of this letter, review the status of conformance of all components of the ICC instrumentation system including subcooling margin monitors, core-exit thermocouples, and the reactor coolant inventory tracking system with KUREG-0737, item II.F.2 and submit a report on the l

i status of such conformance.

'i TVA Responge As stated in the Sequoyah Nuclear Plant Safety Evaluation Report (SER),

l NUREG-0011 (Supplements 1 and 2), NRC considers TVA's plans for using the subcooling meter with the plant computer as acceptable for full power operation.

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Tha chort-ttra NUREG-0737, itta II.F.2 requiremento for coro-trit - .

thIrmocouplca hava been met cs VIrificd by tha NRC onsit3 in pectors's report No. 50-327/82-03 and 50-328/82-03 which was transmitted to TVA by the March 5, 1982 letter from F. S. Cantrell ts H. G. Parris. The thermocouple system will be further upgraded stated in my September 4 and November 6, 1981 and March 15, 1982 letters to you regarding Regulatory Guide 1.97 Revision 2.

NRC Requirement - Item 3 The installation of the ICC instrumentation system shall be completed during the earliest refueling shutdown consistent with the existing status of the plant and practical design and procurement considerations. It has become apparent through discussions with owners' groups and individual licensees that schedules must adequately consider the integration of these requirements with other TMI-related activities. In recognition of this and the difficulty in implementing generic deadlines, the Commission has adopted a plan to establish realistic plant-specific schedules that take into account the unique aspects of the work at each plant. Each licensee is to develop and submit its own plant-specific schedule which will be reviewed by the assigned NRC project manager. The NRC project manager and licensee will reach an agreement on the final schedule and in this manner provide for prompt implementation of these important improvements while optimizing the use of utility and NRC resources.

TVA Response TVA plans to upgrade the core-exit thermocouple system in accordance with the response made on Regulatory Guide 1.97 revision 2 by my March 15, 1982 letter to you. This item will be completed as part of the TVA integrated plan to SECY-82-111B (NRC Generic Letter 82-33). Development of operating procedures is proceeding with the Westinghouse Owners Group. As stated in our response to Item 1, TVA plans to complete the installation of the RVLIS by the end of the second refueling outage for each unit.

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