ML20155E171

Forwards List of Commitments Made Resulting from Discussion at 880913 Mgt Meeting Re post-trip Cooldown

ML20155E171
Person / Time
Site:	Sequoyah
Issue date:	10/05/1988
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
IEB-88-005, IEB-88-5, NUDOCS 8810120152
Download: ML20155E171 (4)

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place 08T 051988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - COMMITMENTS MADE DURING THE SEPTEMBER 13, 1988 MANAGEMENT MEETING The subject meeting was held at SQN between NRC 0.fice of Special Projects and TVA management to discuss the posttrip cooldown experienced on SQN units 1 and 2 and its effect on shutdown margin, unit I status for restart, and Inspection and Enforcement (IE) Bulletin 88-05. As a result of that discussion, several commitments were made by TVA. A listing of those commitments, as TVA understands them, is enclosed.

If you have any questions, please telephone M. A. Cooper at (615) 870-6549.

Very truly yours, TENNESSEE VALLEY AUTHORITY R. Gridley, nager Nuclear Lice sing and Regulatory Affairs Enclosure cc: See page 2

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U.S. Nuclear Regulatory Commission 08T 051988 cc (Enclosure):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Harletta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379

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• Enclosure Commitments

1. Emergency Operating Procedure (E0P) ES-0.1, "Reactor Trip Response," will be revised to require manual control of auxiliary feedwater (AFH) posttrip and manual boration if reactor coolant system average temperature (Tavg) cannot be maintained within acceptable limits. The revised procedure will be implemented before unit I restart.

2. Reactor operators will be trained on manual AFH control before unit I restart. This training will consist of a training letter to all Ilcensed operators describing the revision to E0P ES-0.1 requiring manual AFH control.

In addition, all licensed operators will receive training (postrestart unit 1) on AFH manual control during operator requalification training week 6. This training will be completed by December 31, 1988.

3. SQN Administrative Instruction 18, file package 18, Part B "Reactor Trip Report," will be revised to provide further guidance on performing a posttrip review. The revised procedure will be implemented before Unit I restart.

4. The unit I cycle 4 core reload package unreviewed safety question determination will be reverified using an interdiscipline review before unit I restart.

5. TVA will provide NRC with a status of the investigation results and plan for resolution of the cooldown/ shutdown margin concern by October 14, 1988.

6. TVA stated that the steam dump control system will be modified to operate in the steam pressure mode following a reactor trip. On the basis of continuing evaluation, TVA has determined that a viable alternative for resolution may include an optimized Tavg mode of steam dump control on a reactor trip. Resolution through either method will be done after restart of unit 1. Details on the approach and schedule for resolution implementation will be given in TVA's October 14, 1988 submittal.

7. A scenario will be run on the SQN simulator to determine the need for the addition of a reactor operator to the shift manning requirements.

This scenario was run on September 15, 1988, and witnessed by personnel from the resident inspector's office.

8. The Browns Ferry Nuclear Plant (BFN) reload package will be verified using an interdiscipline review process before restart of BFN.

9. TVA w111 Investigate the possibility of making the Westinghouse Electric Corporation document, "Precautions, Limitations and Setpoints for Nuclear Steam Supply Systems," a controlled document for SQN. This investigation will be complete by October 31, 1988.

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10. TVA will provide NRC with an update for IE Bulletin 88-05 by September 30, 1988.

This item was completed in a TVA submittal to NRC dated September 26, 1988.

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