ML20057F342

Special Rept 93-20:on 930927,LCO 3.7.11.1 Entered When Portion of Auxiliary Bldg Fire Header Isolated & Fire Pumps 2A & 2B Removed from Svc in Order to Perform Surveillance Test on Fire Pumps 1A & 1B.Test Completed & LCO Exited

ML20057F342
Person / Time
Site:	Sequoyah
Issue date:	10/08/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-20, NUDOCS 9310150163
Download: ML20057F342 (3)

Text

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i Tenressee Valley Authonty, Post Offee Scx 2000. Soddy-Daisy. Tennessee 37379-2000 Robert .A. Fenech Vice Prescent, Sequoyah Nuclear Plant October 8, 1993

-U.S. Nuclear Regulatory Commission

~ ATTN: Document Control Desk

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Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-328 Tennessee Valley Authority; )

SEQUOYAH NUCLEAR-PLANT.(SQN) - UNITS 1 AND 2 - FACILITY OPERATING LICENSES DPR-77 AND DPR SPECIAL REPORT 93-20 l The enclosed special report provides details concerning the'inoperability ,

of'the fire suppression water system in the auxiliary building as initially reported by telephone at 1730 Eastern daylight time (EDT) on i September 27, 1993, end confirmed by facsimile on September 28, 1993, as required by Technical Specification (TS) Action Statement 3.7.11.1(b)(2)(a)  !

and'(b),Lrespectively. j l

Details are provided in the enclosure. -This condition, which involves both  !

Units 1 and 2, is being reported in accordance with TS Action Statement 3.7.11.1(b)(2)(c).

I If you have any questions concerning this submittal, please telephone K. E. Meado at (615) 843-7766. 1 i

Sincerely, 1

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l ' Robert A. Fenech  !

i-i Enclosure

! cc: See page 2 l'

12'.147 931'0150163 93100s=

PDR g If l ADOCK^05000328 a[p -l S .PDR Q _ 4. .

,a U.S.. Nuclear Regulatory' Commission Page 2-October 8, 1993 cc'(Enclosure):

fir. D. E. LaBarge, Project' Manager U.S. Nuclear ~ Regulatory Commission One White Flint, North l'

11555 Rockville Pike Rockville, Maryland 20852-2739 NRU Resident Inspector Sequoyah Nuclear Plant 2600:Igou Ferry Road Soddy-Daisy,. Tennessee 37379-3624 l Regional: Administrator l- U.S. Nuclear Regulatory Commission l ' Region II.

101 Marietta Street, NW, Suite 2900

~ Atlanta, Georgia 30323-2711 l-

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ENCLOSURE SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 14-DAY FOLLOW-UP REPORT

'SPECIAL REPORT 93-20

' SQN Technical Specification (TS) Limiting. Condition for. Operation

.(LCO)'3.7.11.1 requires that the fire suppression water system be

. operable through the last valve ahead of the water pressure alarm device on each sprinkler or hose standpipe and through the.last. valve ahead of

' the deluge valve: on each deluge or ' spray system in the auxiliary building.

Description of Conditinn On. September 27,1993, at 1237 Eastern ' daylight time (EDT), with Unit 1 in Mode 5;in a refueling outage and Unit 2 in Mode 5 in a forced outage, LCO 3.7.11.1 was entered. . A portion of the~ auxiliary building fire header was isolated, and the 2A and 2B fire pumps were; removed from service in order to perform a surveillance teht (i.e., flow test) on'the 1A and 1B fire pumps. The test was completed, and the;LCO was exited at 1825'EDT on September 27, 1993.

Corrective Actions Appropriate compensatory action was taken.to comply with Action Statement 3.7.11.1(b).

This event is being reported.in accordance with the requirements of TS Action Statement 3.7.11.1(b)(2)(c).

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