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 lllllh (PLEASE PRINT OR TYPE AL. REQUIRED INFORMATION)

\t>l0l1lly lC B E p 12 l@l0l0 l010 0l0j 01- Ol01@l d 1 1l1l1 l@ll@1 8 9 CICENSEE CODE 14 1S LICENS" NUWr H 25/t>LICLNSE T)PE JU St CAT $8 CON'T@l 0l 5 l 0 l - l 0 l 3 l 2 l 4 l@l 0 8l3 0l7l9l@l 0g9l2 5l7l9 g lolIl 3[g" , 'L"#8 bo 61 DOCKE T NUVBEH 68 63 EVENT DATE I4 75 HEPORT D ATE Su 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 l0 6 lsnall steam leak. The heat load on the RBCCW system was high due ~; high service lo 7 Iwater iniection temperature. RWC U.reiectinn to the hotwell, and supplying the 20 gpm lO 8 Iconcentrator in radwaste.

Technical Specification 3.6.1.6, 6.9.1.9b l90 7 8 9 SYSTEM CAUSE C AUSE C O'? P.VALVE CODE CODE SU8 CODE COMPONENT CODE SU6 CODE SUBCODElh (g_j@ [Bj h l V A l L !V l E l X l@ [CJ@ l Al @

O 9 IS A 7 8 9 10 11 11 IJ 18 l'8 10_SE QUENTI AL OCCUR R E NCE HEFOHT REVISION LE k HO EVENT YE AH HEPOHT NO.

CODE TYPE NO.@ sjg 17l9ll-ll0l8l01 yl 01 3lLll-0lR_ 21 21 23 24 26 2/28 2')30 31 31 ACTION FUTUHE EFFECT SHUTDOWN ATT ACHYE NT NPHD 4 PHIVE cnvP.

COMPONENT TAKEN ACTION ON PL ANT METHOD HOJHS SU8VITTED FORY dUlt SUPP LI F H MANUFAC'UHER lx l@l z l@

lzl@Izl@01010101 LY,j g[Nj @lA glAl3l9 3]g 33 34 35 Ju 3/40 41 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 lil3lDuring the recent outage, it was discovered that the King pin cover en the feedwater lg [ check valve B21-F010B was leaking and had a steam cut.

This leak was repaired and l7 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@

NAll A l@l Operator Surveillance l7 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 Iz I @ l zj@l NA ll NAli o/H 9 10 tt 44 45 80 PE RSONNE L E MPOSUMES NUYBE R TYPE DESCHlPTION L'_LU 1010 lo l@l z l@l NAl'"*'" 'Pt H SON NJ'IN>UJ,E S naCni,nON@

NuveE n li la l 101010 l@l NAl7 8 9 11 11 80 L OSS OF OR DAYAGE TO F ACILITY TYPE DESCHIPTION

'l u^790928o 4 i Lz_J@l i a F 8 9 10 3 80 l Ldal LUv[ @l ESCHIPTION

• iss NAlllllllllllllj i 8 9 10 68 fi 9 80 T.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., Y j