ML20057D610

Special Rept 93-18:on 930916,LCOs 3.7.11.1,3.7.11.2 & 3.7.11.4 Entered When Fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities for Repair & Replacement of Leaking Lines.Repairs Completed on 930919

ML20057D610
Person / Time
Site:	Sequoyah
Issue date:	09/28/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-18, NUDOCS 9310050049
Download: ML20057D610 (3)

Text

. ~ , . . .~. - - . . -

sc

. 3

'm  ;

=e. .

~

1 1

1 Tenneswe Va! ley Awhonty. Fest Office Oca 2000. $oady-Daisy, Tennessee 37379EJD0 i

Robert A. Fenech _ f Vee Premdent, %qmyah rbclear Pbot  ;

i September 28, 1993 ,

i U.S. Nuclear Regulatory Commission '

ATTN: Document Control Desk j Washington, D.C. 20555  ;

Gentlemen: .

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR' PLANT (SQN) - UNIT 1 - FACILITY OPERATING LICENSES DPR-77 ,

AND DPR TECHNICAL SPECIFICATION (TS) 3.7.11.1 SPECIAL REPORT 93-18 The enclosed special follow-up report provides details.concerning the .f inoperability of the fire suppression water system in the. auxiliary i building as initially reported by telephone at 1622 Eastern daylight time  !

on September 16, 1993, in accordance with Technica1' Specification  ;

(TS) 3.7.11.1 Action Statement (b)(2)(a) and confirmed by a facsimile on  !

September 17, 1993. This-condition involves only a portion of the auxiliary building.

i Details are provided in the enclosure. This report is being submitted in accordance with TS 3.7.11.1 Action Statement (b)(2)(c). .

1 i

If you have any questions concerning this submittal, please telephone  !

C. H. Whittemore at (615) 843-7210.  !

Sincerely,  ;

hh,4(cu-J' d? L-*- ^~~

i Robert A. Fenech Enclosure i ec: See page 2 l

g 34 ' 3 ? ') 13 ADOCK 05000327-h 9310050049 930928 _

j  ;

PDR **k .

.g PDR l

i

. i l

.l U.S. Nuclear Regulatory Commission Page 2 i September 28, 1993 cc (Enclosure):

Mr. D. E. LaBarge, Project Manager 1 U.S. Nuclear Regulatory Commission One White Flint, 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 Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711

ENCLOSURE l

14-DAY FOLLOW-UP REPORT l SPECIAL REPORT 93-18 Sequoyah Nuclear Plant Technical Specification (TS) Limiting Condition  !

for Operation (LCO) 3.7.11.1 requires that the fire suppression water system be operable with a flow path capatie of taking suction from the ,

forebay and transferring the water through distribution piping with operable sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water pressure alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be operable according to  ;

Specifications 3.7.11.2 and 3.7.11.4.

l Desctintion_sf_Cendition  ;

On September 16, 1993, at 1245 Eastern daylight time (EDT), with Unit 1 I in Mode 5 coming out of a refueling outage and Unit 2 in Mode 5 for a maintenance outage, LCOs 3.7.11.1, 3.7.11.2, and 3.7.11.4 were entered.

A fire header in the auxiliary building was removed from service as a l result of maintenance activities in the process of repairing and replacing leaking lines. The removal of the header from service isolated a portion of the fire protection sprinklers and standpipes in the area.

Carles11Xa_Attion Appropriate compensatory measures in the form of fire watches and a backup fire suppression water system were established before the initiation of the clearance to comply with TS Action Statements 3.7.11.1, 3.7.11.2, and 3.7.11.4. The maintenance activity was completed, and the LCOs were exited at 0150 EDT on September 19, 1993.

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

l l

l l

__ _