ML20086R623
| ML20086R623 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/20/1991 |
| From: | Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-18, NUDOCS 9201020144 | |
| Download: ML20086R623 (3) | |
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December 20, 1991 U.S. Nuclea. Regulator" L.cmission
-ATTN 1 Document ~Cc.atrol Der 2
- 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
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SEQUOYAH NUCLEAR ELANT (5QN) - TECHNICAL SPECIFICATION (TS) 3.7.11.1 -
SPECIAL REPORT 91-18J The enclosed special report provides details concerning the inoperability of the high pressure fire protection system in accordance with TS Action S tatement 3. 7.11.1(b )( 2 )( c ).
The event was origina11) reported by telephone notification at 2109 Eastern standard time on December 7. 1991, and confirmed by facsimile on December 9, 1991, in accordance with TS Action Statement 3.7.11.1(b)(2).
If you have any questions concerning this submittal, please telephone i
M. A. Cooper at (615) 843-8924 Sincerely,
$1 "
J L. Wilson Enclosure cca See page 2 oO c,;' Y' '. J:
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9201020144 911220
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ENCLOSURE 14-DAY F01. LOW-UP REPORT SEQUOYAH Nt' CLEAR PLANT (SQN)
SPECIAL REPORT 91-18 DESCRIPTION OF CONDITION SQN Teennical Specification (TS) Limiting Condition for Operation (LC01 3.7.11.3 requires the fire suppression water system to be demonstrated operable at least once every three years by performing a flow test of the system.
SQN implements the requirement annually for the auxiliary building fire protcetion system by performance,f a system hydraulic varification.
This test was performed on April 11, 1991. However, on May 6 1991, the fire protection system engineer reviewed the data and declared the system inoperaole. This event was reported in Licensee Event Report 50-127/91009.
To restore the system to operable service, a temporary alteration was made to the system.
The system pressure was raised from its normal value of 135 rounds per square inch gauge (psig).co 147 psig.
Raising the system pressura allowed the system hydraull: test, which verifles !S operability, to be successfully performed.
5qN has operated since May 1991 with the elevated operating pressure, i.e.. 147 psig, on the high pressure fire protection system.
Since May. SQN has conducted investigations into the cause of the-system's reduced performance, and appropriate corr 4ctive actions have been taken to improve that performance and restore The system-tc the
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original configuration.
The last action to fully restore the system to its original configuration to remove the temporary alteration reduce the operating pressure was back to its.riginally designated value of 13$ psig, and perform the system _ operability test.-
LCO 3. 7.11.1 was entered-at 040S Eastern-standard time (EST) on December 7,1991, because the system was considered administrative 1y inoper ble while the system operabillt"y test-was being conducted. During the test, plant personnel were available and dedicated to return the system to its pretest condition, i.e.
147 psig, in the event a fire situation occurred.
The system operability test has-been completed, and calculations are being verified. After completing the field portions of the test, the pressure control valve was reset:to 1! 7 reig in accordance with the requirements of the test procedure at apprcximately 1000 EST on December 9. 1991. Operations exited 100 3.7.11.1.b~ at approximately.1058 EST on December 9, 1991. When'all--
the acceptance criteria'are met, the calculations are verified, and the test procedure is signed off, the temporary alteration will be removed, i.e., the pressure control' valve will-be reset to 135 psig.
The system is expected to be returned to operable status in its original configuration by December 23. 1991.
PLO90204/1573
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U.S. Nuclear Regulatory Commission i
Page 2 December 20, 1991 i
t cc (4nclosure):
Mr. 9. E. LaBarge. Project Manager U.S. Nuclear Regulatory Commission One White Flint. North 1155$ Rcckville Pike Rockville, Maryland 20857 i
NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379 Mr. B. A. Wilson. Project Chief U.S. Nuc'sar Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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