ML20141E788: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[BSEP-85-2183, Special Rept 2-SR-85-9:on 851214,time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 203 Being Out of Svc to Prevent Wear & Damage to Locking Seals & Interlocks.Fire Watches Maintained]]
| number = ML20141E788
| issue date = 12/31/1985
| title = Special Rept 2-SR-85-9:on 851214,time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 203 Being Out of Svc to Prevent Wear & Damage to Locking Seals & Interlocks.Fire Watches Maintained
| author name = Dietz C
| author affiliation = CAROLINA POWER & LIGHT CO.
| addressee name = Grace J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000324
| license number =
| contact person =
| document report number = 2-SR-85-9, BSEP-85-2183, NUDOCS 8601080324
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 1
}}
 
=Text=
{{#Wiki_filter:.
09&L Carolina Power & Light Company us2m.um:mrmmmm:rwas BrunswickSteamg1 9 trig P P. O. Bo'$ 1 4'29        t N2 Southport, NC 28461-0429 December 31, 1985 FILE: B09-13510C SERIAL: BSEP/85-2183 r    J. Nelson Grace, Administrator D. Nuclear Regulatory Commission Suite 2900 101 Marietta Street hV Atlanta, GA 30323 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 DOCKET NO. 50-324 LICENSE NO. DPR-62 SPECIAL REPORT PER TECHNICAL SPECIFICATION 3.7.8 AND PURSUANT TO TECHNICAL SPECIFICATION 6.9.2 (2-SR-85-9)
 
==Dear Dr. Grace:==
 
During the Unit 2 1985 refueling / maintenance outage, a Unit    2 fire barrier LCO was initiated on December 7, 1985, for fire door No. 203 in      the unit Reactor Building. Door No. 203 is. located 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 possible damage to its locking seals and interlocks, resulting from outage-related traffic. On December 14, 1985, the specified 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 2 refueling / maintenance 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 addi-
    ' tional outage-related traffic:        fire door Nos. 301 and 303 (located on the 50-foot elevation) and fire door No. 211 (located on the 20-foot elevation).
This report is intended to meet the reporting requirements for fire door No. 203 as well as any of the above-listed Unit 2 Reactor Building fire doors, which may require 30-day reporting in accordance with Technical Specification 3.7.8.
0601080324 es123j                qy' PDR                                        Very truly yours, S      ADOCK 05000324 PDR                          g C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/
Enclosure cc: NRC Document Control Desk                                                        cf l                                                                                            W}}

Latest revision as of 12:00, 12 December 2021