BSEP-88-1228, Special Rept 1-SR-88-003:on 881120,7-day Time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 211 Being out-of-svc to Prevent Wear & Possible Damage to Locking Seals & Interlocks

Special Rept 1-SR-88-003:on 881120,7-day Time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 211 Being out-of-svc to Prevent Wear & Possible Damage to Locking Seals & Interlocks

ML20195K441
Person / Time
Site:	Brunswick
Issue date:	11/28/1988
From:	Harness J CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
1-SR-88-003, 1-SR-88-3, BSEP-88-1228, NUDOCS 8812050219
Download: ML20195K441 (2)

Text

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s Cp&L Carolina Power & Ligh6 Company summmausumuuammun numannum

, Brunswick Steam Electric Plant

. P.' Box 10429

.. Southport, NC 28461-0419 l November 28, 1988 FILE: B09-13510C 10CFR50.73 SERIAL: BSEP/88-1228 U.S. Nuclear Hegulatory Commission ATTN: Document Control P,sk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 DOCKET NO. 50-325 LICENSE NG. DPR-71 SPECI AL REPORT PER TECHNICAL SPECIFICATION 3.7.8 AND PURSUANT TO TECHNICAL SPECIFICATION 6.9.2 (1-SR-88-003)

Gentlemen:

During the Unit 1 1988-1989 refueling / maintenance outage, a Unit 1 fire barrier limiting condition for operation (LCO) was initiated on November 13, 1968, for fire door No. 211 in the unit Reactor Building. Door No. 211 is located at fire barrier penetration seal No. R1-2-032 on the 20-foot elevation of the building and provides railroad access to the building. The subject LCO was initiated to permit opening the door to help prevent wear and possible damage to its locking seals and interlocks resulting from outage-related traffic. On November 20, 1988, the specificd seven day time frame of the LCO was exceeded. Until return of the door to service and cancellation of the involved LCO, appropriately stationed fire watches will be maintained.

It is expected that during the remainder of the Unit 1 outage, scheduled for completion by February 3, 1989, the following Reactor Building fire doors, in addition to door No. 211, will be appropriately placed under LCO at various times to provide for additional outage-rei.ated traffic: fire door Nos. 301 and 303 (located on the 50-foot elevation) and fire door No. 203 (located on the 20-foot elevation).

I \

1 8912050219 Geltre POR S

ADOCK 05000325 PDC

T A

,o U.S. Nuclear Regulatory Commission This report is intended to meet the reporting requirements for fire door No. 211 as well as any of the above-listed Unit 1 Reactor Building fire doors, which may require 30-day reporting in accordance with Technical Specification 3.7.8 during the unit 1988-1989 refueling / maintenance outage.

Very truly yours, I

J. L. Harness, General Manager Brunswick Steam Electric Plant MJP/mcg Enclosure cc: Mr. B. C. Buckley Mr. M. L. Ernst BSEP NRC Resident Office

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