ML20083D018

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Intervenor Exhibit I-MOSBA-24,consisting of to NRC Re Confirmation of Action Ltr
ML20083D018
Person / Time
Site: Vogtle  Southern Nuclear icon.png
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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ELV-01516.

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:

V0GTLE ELECTRIC GENERATING PLANT i

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 23, 1990 the event, GPC received a Confirmation of Action Letter dated March 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  :

provides justification for this request. i 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 emergency.  ;

The event review team has presented the results of it's review to 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 and Comunicators (see; attached letter from George Bockhold to Emergency Directors generator control) systems; temporary barricades to prevent u  ;

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 i recomendations which require additional management review and evaluation.

' These include the se mid-loop operations;quencing of outage activities; plant conditions during notification system upgrades; changing diesel generator logic; contropost-main and re-evaluating the duties and responsibilities of the Emergency Director.

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U. S. Nuclear Region II Regulatory Comission ELY-01516 )

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The most significant occurrence during the event ,1990, of March 20 invoh i failureGeorgia cooling. of Diesel Generator Power Company (DG) 1A to remain running own to' has investigated the DG failure,and has determined th a.

' During bench testing, all three jacket water temperature wert

- found to be set high during the DG maintenance ins 1990 (by approximately 6-10 degrees F above the setpointt that previous 1y used. adjusted downward using All three a ca b.

Switch TS 19110 was found to have a setpo est found to have a setpoint of 199Switch as the original setting. degrees TS 19111 186 degrees setting F which and was readjusted. was approximately 17 degr was judged to be acceptable to support diagnostic reinstalled. as.

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c. j During the subsequent test run of the DG on March 30 (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

e. the manufacturer's assistance to ensure a o9 a cons technic Subsequent testing indicated that the diesel annunicator f.

March 20, 1990 is reproduced on a high jacket water r p. tem on of. ,

A test }

starts wasofconducted.

the Jacket water system temperature transient g ne jacket water temperature at the switch locations i na normal rolling the standby engine tolineup, replicate and thethen followed starts of Marchby20.a series of i

that jacket water temperature at the switch location The test showed e

decrea rom a standby remained temperature of 163 degrees F to approximately steady.

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U. S. Nuclear Region II Regulatory Commission t

ELV-01516 Paoe Three 9 Since March 20, 1990, (including jacket water temperaturesGPC has performed numerou ns pneumatic conditions. leak testing, and multiple)e,ngine starts a IB DG has Sincestarted been March19 20, the 1A DG has been started 18r times times.

ou during any of these starts.

' In addition, an undervoltage sta without air. roll was conducted on April 6,1990 and uthe loaded properly.

Based on the above facts temperature switches were, the most probable 1990.

on March 20, cause 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 temperature trip.that an emergency reset will override e that the they hig Alarm response emergency reset functions procedures will be revised to addre prior to April 30, 1990.

2.

The the undervoltage non-ess provided to start feature of the Unit 1 DGs tial engine trips are bypassed.

has bee e such that t will be implemented on Unit 2 prior to Aprilaform 30, 1990 )

(This change the o

3. .

Specification change to delete therecal essential engine trip. jacket trip as an w

4.

GPC has reviewed air quality of the D ,

control and has concluded that air qu/G air system including dewpoint ality is satisfactory. Initial reports of higher than expected dewpoints were later instrumention. attributed t receiver on April 6,1990, the periodic replaceme '

filters last done in March,1990 which showed no indication o r 5.

daily air receiver blowdowns with no significant e. water disc orrosion and Based on discussions with the NRC in Atlanta on April 9 1990, GPC will transmit a summary and schedule of NRC by May 15, 1990. andthe en to the will ac vehicles in the perimeter area will also be revised by

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U. S. Nuclear Regulatory Commission Region II ,

ELV-01516 I 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 i 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" W

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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

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92 PROJECT c57746

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