ML20111D101
| ML20111D101 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/01/1985 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| CON-#285-979 OL, NUDOCS 8503180072 | |
| Download: ML20111D101 (4) | |
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- PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 SHIELDS L DALTROFF SLs fasc o c tow March 1, 1905 Docket 1;o. 50-352 Mr..nichard W.
Starontecki Division of Reactor Projects U.S. Iluclear Regulatory Commiccion nogion I G31 Park Avenue King of Prussia, PA 19406
Dear !!r. Starontecki:
Your letter of February 1, 1985 forwarded Inspection Report !!o. 50-352/05-00 for Limerick Generating Station Unit 1 which addresscc one item which apparently van not in full compliance with the IIuclear Regulatory Commiscion requirements.
This item ic rectated below along with our recponce Technical Specification 3.6.3 requires that the containment isolation valvcc 11cted in Table 3.6.3-1 be maintained operable at all timec.
Ilowever, power operations may continue for up to four hourc with one or more containment isolation valves inoperable provided at least one containment isolation valve is maintained operabic for cach containment ponctration.
Contrary to the above, between 9:20 a.m. and 9:27 a.m.,
January 15, 1905, power operationc were in progrecc, but at least one containment icolation valve was not maintained operable for containment ponctration number 014 in that the power cupply feeder breakcrc to the operator for valves IIV44-1F001 and IIV44-lF004 were open.
Thic in a Scverity Level IV violation (Supplement I).
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!!r. Rich rd W. Stere tccki March 1, 1985 Page 2 Responce Thic event in discucced in your inspection report and in Limerick Generating Station Unit 1 Licensec Event Report No.85-006, cubmitted February 19, 1985.
An a recult of defects associated with the Riley Temperature cwitches causing spuriouc ESF actuations, the supervicorn, in an attempt to prevent unnecessary cyctem isolations directed
.that the electrical feed to the isolation valves be opened, one at a time.
Actions were promptly taken to correct the problem which resulted primarily from a lack of clear communication between the supervisor and the *cactor operator.
The individuals involved in thic event were interviewed and counseled regarding the need to properly communicato in a cicar unambiguous fashion.
A design change was developed and a modification was issued to allow the temperaturo monitoring cwitches to be operated without operating the containment valves.
Interim measures taken to prevent recurrence of this event were as follows:
1)
Issuance, on a daily basic of temporary procedure changcc (TPC) to the surveillance test, ST-G-107-590-1, " Daily Surveillance Log /OPCONS 1, 2, 3,"
to provide detailed operator inctructions for removing the feed to one isolation valve at a time.
2)
Posting of an operator aid on the appropriate panel in the auxiliary equipment room which directs the operators to render only one isolation valve at a time inoperable per Technical Specification 3.6.3.
3)
Iccuance of a memorandum to the operating chifts to review the requirements of Technical Specification 3.G.3.
The modification to the " READ" circuit of the Riley temperature switch, including curveillance tonting and calibration of the cwitches to correct the difficultice associated with the generation of cpurious icolation cignals van completed February 14, 1985.
Additional corrective action mcacurcs taken to prevent recurrence included:
1)
An additional 24 hourc of Limerick Generating Station specific Technical Specification training has been included in the rcqualification training cycle for reactor operators, conior operators, shift technical advicorn, and shift advicors to u.
' Mr. Richard W. Staromtecki March 1, 1985 Page 3 enhance the familiarity of the operators with the Limerick Generating Station Technical Specification requirements.
Additionally, each of the above individuals have been issued his own copy of the Technical Specifications.
2)
Control room log review requirements are being modified to provide clarification of control room log review by the shift superintendent, the shift supervisors, and the shift technical advisor.
These requirements are in proposed Revision 2 to Administrative Procedure A-7, which is anticipated to be PORC approved by March 22, 1985.
3)
The Daily Surveillance Logs for OPCONS 1, 2,-and 3 and for OPCONS 4 and 5 were reviewed to determine the adequacy of the procedural guidance incorporated within them.
It was determined that no procedural changes are required.
4)
An operational excellence program has been instituted.
Should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours,
/
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cca J. T. Wiggins, Site Inspector See Service List i
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cc:
Judge Helen F.'Hoyt Judge Jerry Harbour Judge Richard F. Cole Troy B. Conner, Jr., Esq.
~
Ann P. Hodgdon, Esq.
Mr. Frank R. Romano Mr. Robert L. Anthony Ms. Phyllis Zitzer Charles W. Elliott, Esq.
Zori G. Ferkin, Esq.
Mr. Thomas Gerusky-Director, Penna. Emergency Management Agency Angus Love, Esq.
David Wersan, Esq.
Robert J. Sugarman, Esq.
Martha W. Bush, Esq.
Spence W. - Perry, Esq.
Jay M. Gutierrez, Esq.
Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section.(3 Copies)
James Wiggins Timothy R.
S. Campbell I
o 1/16/85 4
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