ML20064H484
| ML20064H484 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/15/1994 |
| From: | Powers K TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9403180021 | |
| Download: ML20064H484 (3) | |
Text
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u,1, i sm March 15, 1994 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAll NUCLEAR PLANT (SQN) - NRC INSPECTION REPORT NOS. 50-327, 328/93 REPLY TO INSPECTOR FOLLOW-lip ITEM (IF ) 50-327, '?P/93-02-05 This letter is TVA's reply to Albert F. Gibson's letter to Mark O. Medford dated February 14, 1994, which requested TVA's resolution of the subject IFI relative to the need for procedural guidance for system realignment to isolate nonessential heat loads. The IF'. addressed heat removal capability of the essential raw cooling water (FLCW) system for mitigation of an accident in one unit coincident with.efueling in the other unit.
After reviewing the ERCW system in a design-basis event (i.e., assumed single failure), it was determined that identifying nonessential heat loads to operators may be of benefit in the unlikely event that system realignment is required.
Therefore, the appropriate procedures will be revised by June 17, 1994, to identify nonessential heat loads that could be isolated in the event that system realignment is required.
The previous response to the subject IFT provided heat-removal capability information to a most severe, non-design-basis plant event with assumptions resulting in a scenario that is not credible (multiple failures were assumed to achieve the worst-case condition).
Because the scenario was not credible and the event was outside the design basis, no procedure revisions will be made relative to the previous heat-load evaluation.
The enclosure contains any commitments associated with this letter 1 Spu on 9403180021 940315 DR ADOCK 0500 7
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U.S. Nuclear Regulatory Convulssion Page 2 March 15, 1994 If you have any questions concerning this submittal, please telephone J. Bajranzewski at (615) 843-7749.
Sincerel-
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j Ken Powers Site Vice Prealdent Enclosure cc (Enclosure):
Mr.
D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Filnt, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Conunission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711
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ENCLOSURE ComnLi.tmettt The appropriate procedures will be revised by June 17, 1994, to identify nonessential heat loads that 'ould be isolated in the event that system realignment is required.
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