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| {{Adams
| | #REDIRECT [[IR 05000344/1987024]] |
| | number = ML20235D923
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| | issue date = 09/18/1987
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| | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/87-24
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| | author name = Zimmerman R
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| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
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| | addressee name = Cockfield D
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| | addressee affiliation = PORTLAND GENERAL ELECTRIC CO.
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| | docket = 05000344
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| | license number =
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| | contact person =
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| | document report number = NUDOCS 8709250409
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| | title reference date = 09-11-1987
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| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
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| | page count = 1
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| }}
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| See also: [[see also::IR 05000344/1987024]]
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| | |
| =Text=
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| {{#Wiki_filter:. - _ _ _ - _ - _ _
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| :c - o . - . . .
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| tJSNRC-DS
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| Docket No. 50-344 SEP 181987
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| M1 SEP 25 A 9 39
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| Purtland General Electric Company
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| 121 S. W. Salmon Street
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| Portland, Oregon 97204
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| . Attention: Mr. David W. Cockfield
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| Vice President, Nuclear
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| Gentlemen:
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| .Thank you for your letter dated September 11, 1987, in response to our Notice
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| of Violation and Inspection Report No. 50-344/87-24, dated August 10, 1987,
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| informing us of the steps you have taken to correct the items which we
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| brought to your attention. Your corrective actions will be verified during a
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| future inspection.
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| Your cooperation with us is appreciated.
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| Sincerely,
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| . . . .
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| R. P/ Zimmerma , Chief
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| Reactor Projects Branch
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| cc w/cy ltr dtd 9/11/87:
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| W. Dixon, DOE
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| bec w/cy ltr dtd 9/11/87:
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| RSB/ Document Control Desk (RIDS) (IE01)
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| Project Inspector
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| Resident Inspector
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| B. Faulkenberry
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| J. Martin
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| 'J. Zo111 coffer {
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| .l'
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| bcc w/o cy of ltr dtd 9/11/87:
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| M. Smith
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| Regiong
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| ](YES /] NO
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| _ - - - - - _ - - _ _ _ _ _
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| .
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| *- , . ,
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| ,;- . .. .
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| - REcgigED
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| b'WV RE 10H V
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| David W. Cockfield Vice President, Nuclear 1981 SEP 1ti A O 23
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| September 11, 1987
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| Trojan Nucicar Plant
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| Docket 50-344
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| License NPF-1
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| U. S. Nucicar Regulatory Commission
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| Attention: Document Control Desk
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| Washington DC 20555
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| Dear Sir:
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| TROJIS NUCLEAR PLANT
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| Reply to a Notice of Violation
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| Your letter of August 10, 1987, transmitted a Notice of Violation based
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| upon NRC Inspection Report 50-344/87-24. Attached to this letter is our
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| response to that Notice of Violation. This letter and response is being
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| submitted two days late due to personnel error.
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| Sincerely,
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| /
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| r
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| Attachment
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| c: Mr. John B. Martin
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| Regional Administrator, Region V
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| U. S. Nuc1 car Regulatory Commission
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| Mr. David Kish, Director
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| State of Oregon
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| Department of Energy
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| Mr. R. C. Barr
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| NRC Resident Inspector
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| Trojan Nuc1 car Plant
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| Subscribed and sworn to before mo this cloventh day of September 1987. ;
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| 9
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| M dit LLU
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| Nota 6y Public of Oregon
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| My Commission Expires: (
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| n . . ~ -~ n
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| N [ *
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| | |
| -- _ _
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| -.
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| .
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| . . .
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| ~ ~
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| . Trojan Nuclear Plant Document Control Desk
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| *
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| e Docket 50-344 September 11, 1987
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| Licence NPF-1 Attachment
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| PCE REPLY TO NOTICE OF VIOLATION
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| Violation
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| 10 CFR 50.72(b)(2)(ii) requires that the licensco shall notify the
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| NRC as soon as practical and in all cases, within four hours of he
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| occurrence of any event or condition that results in manual or auto-
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| matic actuation of any Enginecred Safety Feature, including the
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| Reactor Protection System.
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| Contrary to the above, an automatic actuation of the Reactor Protec-
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| tion System occurred at 9:02 p.m. on June 29, 1987, resulting in the
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| opening of reactor trip breakers RTA and RTB and bypass breaker BYB,
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| but this event was not reported to the NRC until 7:05 p.m. on June 30,
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| 1987.
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| This is a severity Level V violation (Supplement I).
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| PGE Response
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| PGE acknowledges that the automatic actuation of the Reactor Protoc-
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| tion System (RPS) Which occurred at 9:02 p.m. on June 29, 1987, was
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| not reported to the NRC until 7:05 p.m. on June 30, 1987. This is in
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| violation of 10 CFR 50.72(b)(2)(li) which requires this event to be
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| reported within four hours. The reason for the violation was person-
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| nel error.
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| At the time of the RPS actuation, the plant was in Mode 5 (cold shut-
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| down) with the Reactor Coolant System at about 110*F. The control
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| rods were inserted and the control rod drive mechanisms (CRDM) were
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| deenergized with both CRDM generators shut down. The Plant operators
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| were conducting a simulated loss of offsite power test which involved
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| reactor trip breaker manipulations. Under these conditions, the
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| operators failed to initially recognize roccipt of an unexpected re-
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| actor trip signal as immediately reportable and, therefore, did not
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| meet the four-hour reporting requirement.
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| In addition to discussing the event with operational staff, written
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| instructions worc issued to operators emphasizing the immediato re-
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| porting requirements for RPS actuations. Since that time, there have
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| been no similar occurrences. Since a telephone notification was made
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| on June 30, 1987, with a followup 30-day report submitted July 16,
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| 1987 (LER 87-16), correctivo action addressing the operator error is
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| complete and full compliance has been determined to be achieved.
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| }}
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