ML20083D018
| ML20083D018 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/17/1995 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | |
| References | |
| CAL, OLA-3-I-MOS-024, OLA-3-I-MOS-24, NUDOCS 9505230290 | |
| Download: ML20083D018 (4) | |
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Docket No.
50-424 U. S.' Nuclear Regulatory Comission-Region II t
101 Marietta Street, N. W.
I Atlanta, GA 30323 ATTN: Mr. S. D. Ebneter
Dear Mr. Ebneter:
i V0GTLE ELECTRIC GENERATING PLANT CONFIRMATION OF ACTION LETTER On March 20, 1990, a site area emergency was declared due to a loss of offsite-power concurrent with a loss of onsite emergency diesel generator capability.
Following the event, GPC received a Confirmation of Action Letter dated March 23, 1990 concerning certain actions we were taking. ide have reviewed the O,.
March 20th event and the appropriate corrective actions necessary for entry into-Mode 2 have been accomplished. Therefore, we are requesting. approval to return Unit.1 to Mode 2 and subsequent power operation. The following discussion i
provides justification for this request.
1 In accordance with Vogtle Electric Generating Plant procedures, an event review team has investigated the events leading up to and following the site area The event review team has presented the results of it's review to emergency.
management and those recomendations considered important for continued safe plant operation have been implemented.
These include establishment of a management policy on control and operation of vehicles (see attached letter from George Bockhold to site personnel); upgrading of emergency notification network comunications (see attached letter from George Bockhold to Emergency Directors and Comunicators ;
generator control) systems; temporary barricades to prevent into low voltage switchyard areas; and comunications of imediate corrective actions related to operations to licensed operators.
In addition, the event review team report also contains a number of longer-term recomendations which require additional management review and evaluation.
i These include the se mid-loop operations;quencing of outage activities; plant conditions during notification system upgrades; changing diesel generator contropost-mai logic; and re-evaluating the duties and responsibilities of the Emergency Director.
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GeorpaPoneru ExhibitM,page 2,0f '
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U. S. Nuclear Regulatory Comission Region II ELY-01516
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Pace Two The most significant occurrence during the event of March 20\\
failure of Diesel Generator (DG) 1A to remain running to
,1990, invoh i cooling. Georgia Power Company has investigated the DG failure,and has determined th own a.
During bench testing, all three jacket water temperature found to be set high during the DG maintenance ins wert 1990 (by approximately 6-10 degrees F above the setpoint that previous 1y used. adjusted downward using a ca t
All three b.
Switch TS 19110 was found to have a setpo est found to have a setpoint of 199 degrees Switch TS 19111 as the original setting.
186 degrees F which was approximately 17 degr setting and was readjusted.
was judged to be acceptable to support diagnostic e reinstalled.
as.
j During the subsequent test run of the DG on March 30 c.
(TS 19111) tripped and would not reset.
one of the switch.
leaking switchintermittent failure because it subsequently reset.T testing has been(TS 19112) were replaced with new switches.This. switch a conducted with no additional problems.
All subsequi d.
The Unit 1 Jacket water temperature switches have b the manufacturer's assistance to ensure a cons a o9 technic Subsequent testing indicated that the diesel annunicator e.
March 20, 1990 is reproduced on a high jacket water tem on of.
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A test of the Jacket water system temperature transient}
starts was conducted.
jacket water temperature at the switch locations g ne i
normal standby lineup, and then followed by a series of na i
rolling the engine to replicate the starts of March 20.
that jacket water temperature at the switch location decrea The test showed standby temperature of 163 degrees F to approximately e
rom a remained steady.
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Georgia Power n$
(3 ExhibitE,pagedofI C#
U. S. Nuclear Regulatory Commission Region II ELV-01516 t
Paoe Three 9
Since March 20, 1990, (including jacket water temperaturesGPC has performed numerou pneumatic leak testing, and multiple)e,ngine starts a ns conditions.
Since March 20, the 1A DG has been started 18 times IB DG has been started 19 times.
r ou In addition, an undervoltage sta during any of these starts.
without air. roll was conducted on April 6,1990 and the loaded properly.
u Based on the above facts temperature switches were, the most probable cause 1990.
on March 20, a high state of diesel reliability.In addition, the followin o ensurt 1.
Operators are being trained prior to their next shift to ensur understand that an emergency reset will override the hig e that they temperature trip.
Alarm response procedures will be revised to addre emergency reset functions prior to April 30, 1990.
2.
The undervoltage start feature of the Unit 1 DGs has bee the non-ess tial engine trips are bypassed.
e such that provided to t
will be implemented on Unit 2 prior to Aprilaform the o 30, 1990 )
(This change 3.
Specification change to delete the jacket w cal essential engine trip.
re trip as an 4.
GPC has reviewed air quality of the D control and has concluded that air qu/G air system including dewpoint of higher than expected dewpoints were later attributed t ality is satisfactory.
Initial reports instrumention.
receiver on April 6,1990, the periodic replaceme filters last done in March,1990 which showed no indication o daily air receiver blowdowns with no significant water disc r
orrosion and 5.
e.
Based on discussions with the NRC in Atlanta on April 9 transmit a summary and schedule of the ac 1990, GPC will and will NRC by May 15, 1990.
vehicles in the perimeter area will also be revised by en to the
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Georgia Power A Exhibit V
U. S. Nuclear Regulatory Commission Region II ELV-01516 Paae Four 6.
GPC will continue to work with the IIT and an independent lab to evaluate the instruments currently under quarantine. Upon completion of the the lab test, calibration procedures will be revised as necessary to ensure consistent performance.
Completion of these investigations, reviews, tests and corrective actions justify GPC's determination that the DG's are operable. GPC will continue to work with the Transamerica DeLaval Incor) orated Owners Group to improve DG l
reliability. GPC will also review possi)le improvements to protective instrumentation and controls.
Based on the above discussion, we have completed the appropriate corrective actions necessary to safely operate the unit. We request NRC approval to allow i
Unit 1 to return to operation.
Should you have any questions, please inquire.
Sincerel" p),
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W O,
W. G. Hairston, III WGH,III/NJS/gm Attachment xc: Georoia Power Comoany Mr. C. K. McCoy Mr. G. Bockhold, Jr.
Mr. R. M. Odom Mr. P. D. Rushton NORMS U. S. Nuclear Reaulatory Comission Document Control Desk Mr. T. A. Reed, Licensing Project Manager, NRR Mr. R. F. Aiello, Senior Resident Inspector, Vogtle l
O 92 PROJECT c57746
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