ML20235D923

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/87-24

ML20235D923
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/18/1987
From:	Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
References
NUDOCS 8709250409
Download: ML20235D923 (1)

See also: IR 05000344/1987024

Text

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Docket No. 50-344

SEP 181987

M1 SEP 25 A 9 39

Purtland General Electric Company

121 S. W. Salmon Street

Portland, Oregon 97204

. Attention:

Mr. David W. Cockfield

Vice President, Nuclear

Gentlemen:

.Thank you for your letter dated September 11, 1987, in response to our Notice

of Violation and Inspection Report No. 50-344/87-24, dated August 10, 1987,

informing us of the steps you have taken to correct the items which we

brought to your attention.

Your corrective actions will be verified during a

future inspection.

Your cooperation with us is appreciated.

Sincerely,

.

.

.

.

R. P/ Zimmerma , Chief

Reactor Projects Branch

cc w/cy ltr dtd 9/11/87:

W. Dixon, DOE

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RSB/ Document Control Desk (RIDS) (IE01)

Project Inspector

Resident Inspector

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David W. Cockfield Vice President, Nuclear

1981 SEP 1ti A O 23

September 11, 1987

Trojan Nucicar Plant

Docket 50-344

License NPF-1

U. S. Nucicar Regulatory Commission

Attention: Document Control Desk

Washington DC 20555

Dear Sir:

TROJIS NUCLEAR PLANT

Reply to a Notice of Violation

Your letter of August 10, 1987, transmitted a Notice of Violation based

upon NRC Inspection Report 50-344/87-24. Attached to this letter is our

response to that Notice of Violation. This letter and response is being

submitted two days late due to personnel error.

Sincerely,

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Attachment

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Mr. John B. Martin

Regional Administrator, Region V

U. S. Nuc1 car Regulatory Commission

Mr. David Kish, Director

State of Oregon

Department of Energy

Mr. R. C. Barr

NRC Resident Inspector

Trojan Nuc1 car Plant

Subscribed and sworn to before mo this cloventh day of September 1987.

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Docket 50-344

September 11, 1987

Licence NPF-1

Attachment

PCE REPLY TO NOTICE OF VIOLATION

Violation

10 CFR 50.72(b)(2)(ii) requires that the licensco shall notify the

NRC as soon as practical and in all cases, within four hours of he

occurrence of any event or condition that results in manual or auto-

matic actuation of any Enginecred Safety Feature, including the

Reactor Protection System.

Contrary to the above, an automatic actuation of the Reactor Protec-

tion System occurred at 9:02 p.m. on June 29, 1987, resulting in the

opening of reactor trip breakers RTA and RTB and bypass breaker BYB,

but this event was not reported to the NRC until 7:05 p.m. on June 30,

1987.

This is a severity Level V violation (Supplement I).

PGE Response

PGE acknowledges that the automatic actuation of the Reactor Protoc-

tion System (RPS) Which occurred at 9:02 p.m. on June 29, 1987, was

not reported to the NRC until 7:05 p.m. on June 30, 1987.

This is in

violation of 10 CFR 50.72(b)(2)(li) which requires this event to be

reported within four hours. The reason for the violation was person-

nel error.

At the time of the RPS actuation, the plant was in Mode 5 (cold shut-

down) with the Reactor Coolant System at about 110*F.

The control

rods were inserted and the control rod drive mechanisms (CRDM) were

deenergized with both CRDM generators shut down. The Plant operators

were conducting a simulated loss of offsite power test which involved

reactor trip breaker manipulations.

Under these conditions, the

operators failed to initially recognize roccipt of an unexpected re-

actor trip signal as immediately reportable and, therefore, did not

meet the four-hour reporting requirement.

In addition to discussing the event with operational staff, written

instructions worc issued to operators emphasizing the immediato re-

porting requirements for RPS actuations. Since that time, there have

been no similar occurrences. Since a telephone notification was made

on June 30, 1987, with a followup 30-day report submitted July 16,

1987 (LER 87-16), correctivo action addressing the operator error is

complete and full compliance has been determined to be achieved.

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