ML20246J284
| ML20246J284 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/28/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1-89-002, 1-89-2, HL-714, NUDOCS 8909050108 | |
| Download: ML20246J284 (5) | |
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. Georpa Powet Company '
~ 333 Pkomont Auenue 3
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Atlanta Georpa 3030B
-Teephone 404 $2&3195 -
. Mailing Addrectc
~ 40 inverress Ceet Pekway
,y Por;t Ottice f3ox 1295 Birndngham. Alabama 35201 Telephore 205 068 5581 reaut%m eu: rec sprem W. G. Hairstort, in Senior Vice President Nuclear Orerations.-
0272V August 28, 1989-U. S. Nuclear. Regulatory Commission ATTN: Document Control Desk Hashington, D. C. -20555 PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 SPECIAL REPORT l-89-002 BATTERY POWERED EMERGENCY LIGHTING UNITS INOPERABLE FOR A PERIOD GREATER THAN 72 HOURS Gentlemen:
In accordance with_ the requirements of the Plant Hatch Unit 1 Technical Specifications Section 6.9.2, and the Fire Hazards Analysis (FHA) Appendix B,
Georgia Power _ Company is submitting the enclosed Special Report' (SR) concerning an event where battery powered emergency lighting' units were inoperable longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This event. occurred at Plant Hatch - Unit 1.
Sincerely, sY. $ k f H. G. Hairston, III LSJB/eb
Enclosure:
SR 50-321/1989-002 c:- (See next page.)
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U.S. Nuclear Regulatory Commission
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August 26s-1989 Page Two ci. Georaia Power Company 3
Mr.: N. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager. Engineering and Licensing._- Hatch GO-NORMS U.S. Nuclear Reaulatory Commission.'Washinoton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch
'U.S. Nuclear Regulatory Commission; Reaion II
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Mr. S. D. Ebneter, Regional Administrator-Mr. J. E. Menning, Senior Resident Inspector - Hatch 0272V
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ENCLOSURE PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 I*
SPECIAL REPORT 1-89-002 BATTERY POWERED EMERGENCY LIGHTING UNITS INOPERABLE FOR A PERIOD GREATER THAN 72 HOURS.
A.
REQUIREMENT FOR REPORT This report is required by Unit 1 Technical Specifications section 6.9.2.
This section of the Technical Specifications
.l states that Special Reports for fire protection equipment operating and surveillance requirements shall be submitted as required by the Fire Hazards Analysis (FHA) and its Appendix B requirements.
l Appendix B, section 1.9.1 of the FHA states that emergency lighting equipment must be operable at all times.
The Action i
Statement states that in the event a battery powered emergency lighting unit is inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, a i
Special Report must be prepared and submitted to the Commission within 30 days.
In the event described in this report, several battery powered emergency lighting units were inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> due to planned plant modification activities.
B.
UNIT STATUS AT. TIME OF EVENT On 08/03/89, Unit I was in the Run mode at an approximate
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power level of 2433 MHt (approximately 100% of rated thermal power).
C.
DESCRIPTION OF EVENT On 07/31/89, preplanned work began on a plant modification involving structural members in the southeast diagonal of.the Unit 1 Reactor Building.
Most of the equipment located in this diagonal is related to the 'A' loop of the Residual Heat Removal (RHR) system and the
'A' loop of the Core Spray system.
The work involved disconnection and relocation of several pieces of wiring conduit.
Some of these conduits contained cables supplying charging power to battery powered l
emergency lighting units. When the conduits were disconnected, i
l the power cables to the battery powered emergency lighting units were disconnected.
To prevent unnecessary discharge of the batteries, the lighting units were electrically disabled and the ur,its were declared inoperable.
As of 08/03/89, the power cables had not been reconnected.
It is estimated that j
the lights will be restored to operable status by 09/05/89.
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0272V HL-714 E-1 1
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l D.
CAUSE OF EVENT
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The cause of this event was planned plant modification activity -
which resulted in several. battery powered ~ emergency lighting units being rendered inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
E.
' ANALYSIS OF EVENT The battery powered emergency lighting enits are designed to provide illumination of certain pieces of equipment in the event of a fire concurrent with a loss of off-site power (LOSP).
During a LOSP the automatic load shedding function of the emergency diesel generators will disconnect power to the reactor building interior lighting, thereby triggering the emergency l
lights.
Below is a tabulation of the inoperable emergency lights and a list of equipment the lights were intended to illuminate:
i
- Inoperable Emergency Component Number or J.
Licht Number Area to be Illuminated
)
1R42-E087 Valve 1E11-F006C Valve 1E11-F006C Valve IP41-F0039A Heat Exchanger 1T41-B002A Valve 1E11-F006A i
1R42-E017 Stairway 107' to 097' Elevations:
1R42-E054 Stairway 118' to 107' Elevations:
1R42-E091 Stairway 097' to 087' Elevations:
1R42-E108 RHR Pump Area Valve 1E11-F018A 1R42-E119 Valve 1E11-F026A 1R42-E117 Valve 1E21-F010A 0272V HL-714 E-2
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,.;y In the event the reactor building' lights are ' extinguished. plant operators can use: : flashlights for any required. emergency operations in the diagonal.
Procedure 34G0-OPS-030-1S, Inside Daily Rounds,. requires. plant equipment operators to carry flashlights. with them during' ' their - daily rounds.
.Also, flashlights are available continually 'in the'. Maintenance' Tool-Storage Area for use'during emergencies.
Based on': the above analysis it is concluded that _ this event has no adverse. impact on nuclear ~ safety.
F.
CORRECTIVE ACTIONS The battery powered emergency lighting units will' be restored to operable status.upon completion of the plant modification activity.
It is estimated that this action will be cmpleted by 09/05/89.
0272V HL-714 E-3
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