BSEP-88-0094, Special Rept 1-SR-88-002:on 880126,limiting Condition for Operation (LCO) Initiated for Fire Door 203 in Reactor Bldg to Permit Opening Door to Help Prevent Wear & Possible Damage to Locking Seals & Interlocks.Lco Exceeded on 880202

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Special Rept 1-SR-88-002:on 880126,limiting Condition for Operation (LCO) Initiated for Fire Door 203 in Reactor Bldg to Permit Opening Door to Help Prevent Wear & Possible Damage to Locking Seals & Interlocks.Lco Exceeded on 880202
ML20149G489
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/10/1988
From: Dietz C
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
1-SR-88-002, 1-SR-88-2, BSEP-88-0094, BSEP-88-94, NUDOCS 8802180280
Download: ML20149G489 (2)


Text

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CML Carolina Power & Light Company r - un Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 Feb rua ry 10, 1988 FILE: B09-13510C SERIAL: BSEP/88-0094 U.S. Nuclear Regulatory Commission A'ITN : Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 SPECIAL REPORT PER TECHNICAL SPECIFICATION 3.7.8 AND PURSUANT TO TECHNICAL SPECIFICATION 6.9.2 (1-SR-88-002)

Gentlemen:

During the scheduled Unit 1 1988 oucage, a Unit 1 fire barrier LCO was initiated on January 26, 1988, for fire door No. 203 in the unit Reactcr Building. Door No. 203 is located at fire barrier penetration seal No. R1-2-017 on the 20-foot elevation of the building and provides personnel access to the building from the unit Turbine Building hallway. The subject LCO was initiated to permit opening the door to help prevent wear and possibic damage to its locking seals and interlocks resulting from outage-related traffic. On February 2, 1988, the specified aeven-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, the following Reactor Building fire doors, in addition to door No. 203, will be appropriately placed under LCO at various times to provide for additional outage-related traffic: fire door Nos. 301 and 303 (located on the 50-foot elevation) and fire door No. 209 (located on the 20-foot elevation).

F 8802180280 880210 1 PDR S

ADOCK 05000325 DCD f

U.S. Nuclear Regulatory Commission This report is intended to meet *the reporting requirements for fire door No. 203 as well es any of the above-Iisted Unit 1 Reactor Building fire doors, which may require 30-day reporting in accordance with Technical Specification 3.7.8.

Very truly yours,

/ ~ l )h/

C. R. D etz, Gene al Manager Brunswick Steam Electric Plant MJP/byc Enclosure cc: Dr. J. N. Grace Mr. E. D. Sylvester BSEP NRC Resident Office l

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