ML20239A495
| ML20239A495 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/11/1987 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709170376 | |
| Download: ML20239A495 (2) | |
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. David W. Cockfield Vice President, Nuclear September 11, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555
Dear Sir:
TROJAN 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 responso to that Notice of Violation. This letter and responso is being submitted two days lato due to personnel error.
i Sincerely,
,/
Attachment c:
Mr. John B. Martin Regional Administrator, Region V U. S. Nuclear Regulatory Commission Mr. David Kish, Director State of Oregon Department of Energy Mr. R. C. Bare NRC Resident Inspector Trojan Nucicar Plant Subscribed and cworn to before me this eleventh day of September 1987.
Mka td Nota F Public of Oregon I
My Commission Expires:
B709170376 870911 DR ADOCK O 4
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g Trojcn Nuclser Plant Docum:nt Control Desk Docket 50-344 September 11, 1987 License NPF-1 Attachment PGE REPLY TO NOTICE OF VIOLATION Violation 10 CFR 50.72(b)(2)(ii) requires that the licensee shall notify the NRC as soon as practical and in all cases, within four hours of the occurrence of any event or condition that results in manual or auto-matic actuation of any Engineered 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 Protec-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)(ii) 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 receipt 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 were issued to operators emphasizing the immediate re-porting requirements for RPS actuations. Since that time, there have been no similar occurrences.
Since a celephone notification was made on June 30, 1987, with a followup 30-day report submitted July 16, 1987 (LER 87-16), corrective action addressing the operator error is complete and full compliance has been determined to be achieved.
DLN/rc 1670P l
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