ML20246L626

From kanterella
Jump to navigation Jump to search
Identifies Actions Being Undertaken by Util to Address Event Analysis & Corrective Actions for Facility 890826 Scram. Summary List of Actions Provided,Including Lab Insp
ML20246L626
Person / Time
Site: LaSalle 
Issue date: 08/30/1989
From: Galle D
COMMONWEALTH EDISON CO.
To: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8909070009
Download: ML20246L626 (2)


Text

_ _

f ~

Commonwealth Edison -

  1. 0.Y

[

/-

,f 72 West Adims Street Chicago, lilinois' Address R: ply to: Post OTEe BM67~ -

PRTORITY ROUTING

'k(_

"Q

,b

/ Chicago, Illinois 60690 0767 '

See md rat Q

7

' August 30, 1989 (12GNt '[ p o

pass

.x_

DYM M

~

FILE

'Mr..A.~Bert Davis-Regional Administrator-U.S.' Nuclear Regulatory Commission

-Region III'

799 Roosevelt Road

-Glen:Ellyn, IL 60137-

Subject:

. LaSalle County: Station Unit 2 August 26,:1989 Unit Scram-

-NRC Docket No. 50-374

Dear Mr.' Davis;

'This letter identifies the actions Commonwealth Edison'is undertaking to address the event analysis and corrective actions for the subject Unit 2 Scram and the concerns identified with the' response of the reactor protection

. system.

These actions will provide Commonwealth Edison and the NRC with assurance that the same problem is unlikely to occur agcin.

Following is a

. summary list of our actions:

1.

Determine the-cause of the reactor protection system (RPS) observed response.

2.

Conduct _an event-analysis to show that the cause determined in Item 1 above is the only likely cause that describes the observed RPS response.

3.

. Perform a laboratory-inspection of the K14E contactor.

4 '.

Provide the following information for the RPS K14 contactor:

a.

The expected service life, and b.

The recommended preventive maintenance / inspection requirements.

' Identify the actions taken prior to startup consistent with these requirements.

Further, indicate the maintenance program in place prior-to the event for these contactors.

8909070009 890830 PDR ADOCK 05000374 P

PDC l

n(

0269T:1

-ggg3ylggg Ek

e

f. j:.

.A.B. Davis

. -August 30,,1989'

15. Determine-the~cause of'the two of the four:first. stage pressure sensors' settings being-above the Technical Specification ~. limit'and identify corrective actians.

6, Determine'the cause of-the indication problems of the turbine stop valves and identify corrective actions.

7.

Determine the cause of the Hathaway computer inability to collect event

?

' data and actions to be taken to maximize Hathaway availability.

~8.

-Determine,the conditions that resulted in the turbine first stage.

pressure' chart; recorder being without ink and the programs which are in place to assure the availability of this;and other control room chart recorder.

9.

Submit.aformalreporttoNRCRegionIIIbkOctober1,1989,detailingthe findings and conclusions.

-The startup of. Unit 2 will.not occur without.the concurrence of the' Regional Administrator or his designee. He expect to have responses to items

'1 through 8 above for discussion with your staff prior to the startup.

If there are any further questions regarding this matter, please contact this office.

Very truly yours, Lv M S ' h 30f6}

D. P. Galle Vice President BHR Operations l

psk/Im-cc: _ Region III Inspector - LSCS P.C. Shemanski - Project Manager, NRR

.0269T:2

- - _ - -. - - _ _. _ - - - - - - - _ _ _. _