ML20037C656
| ML20037C656 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/16/1981 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20037C654 | List: |
| References | |
| NUDOCS 8102190206 | |
| Download: ML20037C656 (3) | |
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January 16, 1981 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. R. H. Encelken, Director 3.
acicar Reculatory Commission
- -'evion V Suite 202. Ualnut Creek i>1aza 1990.. California Blvd.
Ualnut Creex, CA 94596 Daar Mr. E.ngeiken:
Your letter of Dececoer 44, i > 00 f o rwa rc ea results of an inspection co ntiuc teu hoveauer.2-i6, iRU ano a notice or violation. Pursuant to the provisions of 10 GJ. 2.201, attacneu is our reply to this notice of violation uescriolug (ij cae corrective steps wnicn have been taken and th reau16e mealc. cu,
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Attachment 2ESPONSE TO "0TICE OF VIOLATION I
Notice of Violation Facility Operatinq License NPF-1 states:
Section 2.C.(7) ".
all activities to which a cuality assurance nrogram is applicable shall, after the date or issue of the license. be conducted in accordance with the Quality Assurance Program for Operatfon." Quality Assurance Pro-cedure QAP-5, " Procedures, Instructions and Drawings", requires, in part, that " activities af fecting quality shall be accomplished in accordance with current Plant orocedures or instructions includine but not limited to approvea Plant ocerating manual procecures..
Plant Operating Manual rroceaure Au-3-14, " Safety Related Equipment Outages", ensures, in part, tne proper testing or equipment upon re-turning it to service.
Contrary to tne aoove, following the reconnection of lifted leads wnich had disabled tne automatic start or cne auxiliary reeuwater pumps on a low steam generator level signal on July 9, 1980, no testing to ensure the proper funccioning or culs automatte start signal was performed.
On Octooer u, 1300 it was uiscovereu coac cne lifted leads had been connected iupropetij waea cae failure of cne auxiliary feedwater pumps to stacc va ius sceaa genecacor leveis auring a Plant trip on October 3, 1980, uas evaluascu.
.cc:ug cae perlou July 9, 1930 througn October 6, 1980, :ne iucility iiad v eecacca la uoaes I, II and III during wnich this sarety-reluccu mucamacic omarcing Zeacure of the auxiliary feedwater punps was coauued ta au t uactioaal ua described in the f acility's Final Safety Analyaia naport.
This is a 3everity - /el l'.
violation (Gupplement 1).
Response
Upon identification af the probic, taa leads to the slave relays for the automatic start of the auxiliary feedwa ter pumps due to low-low steam generator water level were properly reconnected and the circuits were tested.
The auxiliary feedwater pumps were determined to be capable of starting automatically from a low-low steam generator water level signal.
Plant Operating 'hnual Procedure Administrative Order A0-6-2, "llypass of Safety Functions", will be revised to require supervisor review and approval of lifted leads and identification of subsequent test-ing or independent verification of their restoration. Supe rviso ry review of lif ted leads prior to their being lifted ensures that sub-sequent testing and verification is performed af ter their restoration.
Attachaent to Crochi Ictter v '7C Jaau.ry 15, 1901 Pn;,e t '.J o r er 50-6-?
ill nro"ide anidance and direction to the d
Administrat!"a o supervisors #or the " ecific enses far "htch testing or independent verification by, car. cad nercon is necessarv.
It is estinated that Adainistrative Order A0-6-2 vill he revised and laplemented hv March 1, 1981.
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