ML19208D484

LER 79-080/03L-0:on 790830,primary Containment Ambient Temp Exceeded Tech Spec Limits,Causing Small Steam Leak.Caused by Leakage & Steam Cut of King Pin Cover on Feedwater Check Valve B21-F010B.Leak Repaired & Leakage Decreased

ML19208D484
Person / Time
Site:	Brunswick
Issue date:	09/25/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19208D481	List: ML19208D480 ML19208D484
References
LER-79-080-03L, LER-79-80-3L, NUDOCS 7909280475
Download: ML19208D484 (2)

Text

NRC FORM 366 U. S. NUCLE AR REGULATOR) COMMISSION l.lCENSEE EVENT REPORT CONTROL BLOCK: l

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1. 8 bo EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121 IDurinn normal plant operation, the primary containment ambient temperature exceeded j o 3 l135 F (135.176 F). The temperatures over the previous several days had been 133-134 F l 1014 l lwith all available dryvell coolers > operating. Drvwell leakage had increased to approx-l 0 s limately 2 epm and airborne particulate activit:. wac higher than normal, indicating a l 0 6 lsnall steam leak. The heat load on the RBCCW system was high due ~; high service l o 7 Iwater iniection temperature. RWC U.reiectinn to the hotwell, and supplying the 20 gpm l O 8 Iconcentrator in radwaste. Technical Specification 3.6.1.6, 6.9.1.9b 90 l

7 8 9 SYSTEM CAUSE C AUSE C O'? P. VALVE CODE CODE SU8 CODE COMPONENT CODE SU6 CODE SUBCODE O 9 IS 9

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[Nj @ lA g lAl3l9 3]g 33 34 35 Ju 3/ 40 42 43 44 4; CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 1 o lRWCU reject to the hotwell was decreased from 130 gpm to 100 rpm and service water flow 1 Ii Ii l lto the RBCCW heat exchangers was increased. This lowered the RBCCW outlet temperature l lil2l [from 99 F to 89 F and drvvell ambient temperature was lowered from 135.176 F to 1340F,l lil3l During the recent outage, it was discovered that the King pin cover en the feedwater l g [ check valve B21-F010B was leaking and had a steam cut. This leak was repaired and l 7 8 9 (CON '1)so ST S N POW E H OTHER ST ATUS b V FY DISCOVE HY DESCHiPTION li ls j lE l@ l 0l 9 l 4l@ NA l l A l@l Operator Surveillance l 7 8 9 to 12 11 44 4 ', 46 80 AC TIVI T Y CONTENT J d)

RELEASED OF HELE AGF AVOUN T OF ACTIVITV LOC ATION OF HELE ASE i o Iz I @ l zj@l NA l l NA l

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A. C. To111soa, Jr. 919-457-9521 o N AME OF PnFPAF10 Ft PHONE S,

LER CONTINUATIOff -- RO# 2-79-080 Facility: BSEP Unit No. 2 Event Date: 8-30-79 during subsequent power operation, drywell leakage had decreased to agprox-imately 0.2 gpa and the containment temperature was averaging 120-125 F.

The surveillance that detected this event is a daily computer check of dry-well temperatures. This surveillance has been increased to a frequency of once per shift to better detect rising temperatures, and to provide for an earlier initiation of methods for temperature reduction before c::ceeding any limits. This is considered an isolated event and no further action is required.

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