ML20136E210
| ML20136E210 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/20/1985 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 0200C, 200C, 50-366-1985-004, 50-366-1985-4, SL-133, NUDOCS 8601060465 | |
| Download: ML20136E210 (2) | |
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Georg a Power Comp. y 333 Piedmont Avenue Attarta. Ge< icia 30308
' Telephore 404 526 6526 Whng A1 Ness:
Post Ott ce Box 4545 At:ama. Gectg.a 30302 b
Georgia Power 4
L T. Gucws.
I'
/ " + " " e'*
'rt 3 s Manage:f N ctear Eng reer r.g rd CNet Nucear Eng neer SL-133 0200C December 20, 1985 U. S. Nuclear Regulatory Commission Document Control. Desk Washington, D. C.
20555 Attached is Special Report No. 50-366/1985-004.
This report meets the special reporting requirements of 10 CFR 73.71(c) and Unit 2 Technical Specifications Section 3.7.6.2, ACTION a.
I l
i Very truly yours, 4
c:8 f An e L. T. Gucwa CBS/lc Attachment c:
Mr. J. T. Beckham, Jr.
Mr. H. C. Nix, Jr.
NRC-Region II G0-NORMS tseuzueo%5 sslawu PDR S
. ADOCM 05000366 PDR u
p
e Special' Report 50-366/l'985-004 LICENSEE GEORGIA POWER COMPANY FACILITY NAME EDWIN I. HATCH UNIT 2 DOCKET NUMBER 50-366 This Special' Report is required by 10 CFR 73.73(c) ' and Technical Specifications Sections 3.'7.6.2,. Action a. and 6.9.2.
On 11/07/85 at approximately 1420 CST, Operations personnel received indication in the mais contrcl room that the reactor building drywell chiller room deiuge valve- (2T43-F017A) had automatically opened.
After_ determining-that no fire had occurred in that compartment those personnel isolated this valve and placed an administrative hold on its use to prevent it from being ranually reopened.
Those personnel also made a determinat. ion et that time that these actions did not render inoperable any of the sprinkler systems listed in Technical Specifications Section 3.7.6.2.
For this reason, the actions required by Technical.
Specifications Section 3.7.6.2, Action a.
were not performed at that. time.
On 12/09/85 at approximately 1100
- CST, fire protection personnel, while - reviewing completed Data Package 1
for the
" DELUGE / SPRINKLER SYSTEM SURVEILLANCE SAFETY RELATED AREAS" procedure (42SV-SUV-Oll-2),
determined that the surveillance requirements on the reactor building drywell chiller room deluge valve (2T43-F017A) could not be completed on 11/08/85 due to the administrative hold on the use of that valve.
Fire protection-personnel informed Operations personnel that this sprinkler system was referred to as the " Reactor. Building HVAC room" sprinkler system in Technical Specifications Section 3.7.6.2.
At that time, the requirements of Technical Specifications Section 3. 7.- 6. 2,
ACTION a.
were complied with.
Plant personnel reset the 2T43-F017A deluge valve (per.the vendor's manunl),
cleared the administrative hold on that component, and returned the reactor building chiller room sprinkler system to an operable status on 12/09/85 at approximately 1830 CST.
The-initial. determination as to whether the system w a s' covered by Technical Specifications and the resulting failure to comply with Technical Specifications Section 3.7.6.2, ACTION c. was the result of I
the' ambiguity of the phrase " Reactor Building HVAC room" in Section 3.7.6.2.
To plant personnel thi s mea,it another room in the building which contains no sprinkler system, and is not required to have one.
The room which the Techn.ical Specifications refer to is known on site as the reactor buiiding drywell chiller room.
To prevent recurrence, a letter will te written to, the operations department to inform responsible personnel what the. phrase " Reactor Building HVAC room"-in Technical Specifications means.-