ML20205S891
| ML20205S891 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/04/1988 |
| From: | White S TENNESSEE VALLEY AUTHORITY |
| To: | Partlow J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8811140027 | |
| Download: ML20205S891 (4) | |
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1 TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 6N 38A Lookout Place November 4, 1988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk uashington, D.C.
20555 Attention:
Mr. James G. Partlow Centlemen:
In the Matter of
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Docket No. 50-327 Tennessee Valley Authority
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SEQUOYAH NUCLEAR PLANT (SQN) UNIT 1 - PLANS FOR POWER ESCALATION OF UNIT 1 As requestad in a telephone conversation on November 2, 1988, batween TVA and NRC, this letter is provided to detail TVA's plans for power escalation for SQN unit 1.
This plan includes power operation at various power levels to provide reasonable assurance that the majority of equipment deficiencies will be identified and corrected as required during the subsequent shutdown. The period of pover operation shall not exceed a maximum of 21 days. Previously established NRC holdpoints will, of course, remain in effect throughout the power escalation. Of consideration are the five following existing plant conditions:
1.
Reactor vessel flange 0-ring seal scepage (condition adverse to quality report (CAQR) SQP880546) 2.
Emergency diesel generator with failed load sensor card (CAQR SQP880548) 3.
Pressurizer safety valve seepage (CAQR SQP880551) 4.
Steam generator main steam safety valve scopage (CAQR SQP880536) 5.
Main steam system steam dump valve scepage (temporary alteration change form 1-88-19-01)
The above-referenced documents provide TVA's technical evaluation of these issues to support power escalation. These issues were discussed with NRC in the telephone conversation of November 2, 1988, and the referenced documents and applicabic safety evaluations are available oneite at SQN for NRC review.
TVA's plan to address items 3 through 5 above is dependent upon the pressurizer safety valve seepage (item 3) acceptability for power operation.
Acceptability of pressurizer sa'ety valve scepage is based upon evaluation of hh g0 L
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s U.S. Neclear Regulatory Commission November 4, 1988 1
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various factors. Results of ongoing evaluations will be discussed with the NRC resident inspectors.
In all cases, SQN will compiv with technical specificatior requirements.
Item 1 (reactor vessel flange 0-ring seal seepage) haa been evaluated and determined to be acceptable for long-term operation. Currently, TVA is developing a method to quantify the reactor vessel flange scepage and will continue to monitor this seepage during this, power escalation.
Item 2 has been evaluated, and repairs will be made during the upcoming diesel generator outage scheduled for the week of November 28, 1988.
TVA in currently eva4uating the pressurizer safety valve scepage (item 3);
and, if it is determined that this seepage is acceptable for short-term operation TVA plans to conduct power escalation as previously described.
Upon completion of this activity, if conditions described in items 3 through 5 have not improved, SQN will be shut down to effect repairs on those items.
If for some reason the pressurizer safety valve scepage should stop and depending on overall plant condition. TVA may desire to discuss continued power operation with tha NRC.
Summary statements of commitments contained in this submittal are provided in the enclosure.
If you have any questions, please telephone M. A. Cooper at (615) 870-6549.
Very truly yours.
TENNESSEE VALLEY AUTHORITY kQ.
S. A. White, Senior Vice President, Nuclear Power Enclosure cc: See page 3
U.S. Nuclear Regulatory Commission November 4, 1988 cc (Enclosure):
Ms. S. C. Black, Assistant Director i
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 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy. Tennessee 37379 i
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I
e Enclosure List of Commitments A.
Currently, TVA is developing a method to quantify the reactor vessel flange seepage and will continue to monitor this seepage during this power escalation.
B.
Item 2 (emergency diesel generator with failed load sensor card (CAQR SQP880548]) has been evaluated and will be repaired during the upcoming diesel generator outage scheduled for the week of November 28, 1988.
C.
In the event the pressurizer safety valve seepage is determined to be unacceptable, SQN will proceed with repair of items 3 through 5 before power operation.
D.
In the event unit 1 is returned to mode 5 during power ascension, items 3 through 5 will be repaired before resuming power operation.
E.
After operating in mode i for 21 days, if conditions described in items 3 through 5 have not improved, SQN will be shut down to effect repairs on those items.
In the event the material condition of those items has improved, further discussion of TVA's plan with NRC will be required.
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