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{{#Wiki_filter:NRC FORM 366 U. S. NUCLE AR REGULATOR) COMMISSION l.lCENSEE EVENT REPORT
{{#Wiki_filter:NRC FORM 366                                                                                                                           U. S. NUCLE AR REGULATOR) COMMISSION l.lCENSEE EVENT REPORT CONTROL BLOCK: l
*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).
l            l      l  l      lh t>
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.
(PLEASE PRINT OR TYPE AL. REQUIRED INFORMATION) l0l1lly lC                   B     E   p 12 l@l0l0                         l010       0l0j 01- Ol01@l d 1LICLNSE1l1l1 LICENS" NUWr H                       25       /t>                     T)PE JU l@lSt CAT l
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 @
                                                                                                                                                                                    $8 1      8 9            CICENSEE CODE              14    1S CON'T lolIl 3[g" , '        L  @l 610l 5 l 0DOCKE      l - l T0NUVBEH l 3 l 2 l 4 68l@l630              8l3 0l7l9l@l 0g9l2 5l7l9 g EVENT DATE                 I4         75       HEPORT D ATE         Su
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.
  #        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
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.
7       8 9 SYSTEM             CAUSE           C AUSE                                                             C O'? P.           VALVE CODE               CODE         SU8 CODE                   COMPONENT CODE                       SU6 CODE           SUBCODE O  9                            IS 9
COMPONENT TAKEN ACTION ON PL ANT METHOD HOJHS SU8VITTED FORY dUlt SUPP LI F H MANUFAC'UHER lx l@l z l@
A 10 lh (g_j@ [Bj h l V         11              IJ A l L !V l E l X l@ [CJ@ l Al @
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.
18             l'8                 10 7        8                                                11
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@
_                                          SE QUENTI AL                         OCCUR R E NCE             HEFOHT                       REVISION LE k HO     EVENT YE AH                               HEPOHT NO.                               CODE                     TYPE                         NO.
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@
              @ sjg _ 2117l9l R
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-l              l0l8l01                    y            l 01 3l                        Ll            l-         0l 31 21         23             24             26           2/           28         2')             30                 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 41
'l u^790928o 4 i Lz_J@l i a F 8 9 10 3 80 l Ldal LUv[ @l ESCHIPTION
[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)
*iss NAlllllllllllllj i 8 9 10 68 fi 9 80 T.A. C. To111soa, Jr.
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
919-457-9521 o N AME OF PnFPAF10 Ft PHONE S,  
  /       H 9                   10         tt                                           44             45                                                                               80 PE RSONNE L E MPOSUMES NUYBE R             TYPE         DESCHlPTION NA L'_LU 1010 lo l@l' z l@l"
*.LER CONTINUATIOff -- RO# 2-79-080 Facility: BSEP Unit No. 2 Event Date:
* l Pt H SON NJ'IN>UJ,E S NuveE n              naCni,nON@
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.
li la 8l 9101010 l@l 7                                11     11 NA 80 l
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}}
L OSS OF OR DAYAGE TO F ACILITY TYPE         DESCHIPTION                                                                                                                                           'l i a Lz_J@l                                                                u^                                                           790928o                       4         i F       8 9               10                                                                                                     3                                                       80 iss                                                                                                                                    l
* Ldal LUv[ @l                     ESCHIPTION                                         NA                                                                  l      lllll        lllllllj 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}}

Latest revision as of 06:46, 2 February 2020

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 Duke Energy icon.png
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:
References
LER-79-080-03L, LER-79-80-3L, NUDOCS 7909280475
Download: ML19208D484 (2)
v • d • e


Text

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

\

l l l l lh t>

(PLEASE PRINT OR TYPE AL. REQUIRED INFORMATION) l0l1lly lC B E p 12 l@l0l0 l010 0l0j 01- Ol01@l d 1LICLNSE1l1l1 LICENS" NUWr H 25 /t> T)PE JU l@lSt CAT l

$8 1 8 9 CICENSEE CODE 14 1S CON'T lolIl 3[g" , ' L @l 610l 5 l 0DOCKE l - l T0NUVBEH l 3 l 2 l 4 68l@l630 8l3 0l7l9l@l 0g9l2 5l7l9 g EVENT DATE I4 75 HEPORT D ATE Su

  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

A 10 lh (g_j@ [Bj h l V 11 IJ A l L !V l E l X l@ [CJ@ l Al @

18 l'8 10 7 8 11

_ SE QUENTI AL OCCUR R E NCE HEFOHT REVISION LE k HO EVENT YE AH HEPOHT NO. CODE TYPE NO.

@ sjg _ 2117l9l R

l-l l0l8l01 y l 01 3l Ll l- 0l 31 21 23 24 26 2/ 28 2') 30 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 41

[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

/ H 9 10 tt 44 45 80 PE RSONNE L E MPOSUMES NUYBE R TYPE DESCHlPTION NA L'_LU 1010 lo l@l' z l@l"

  • l Pt H SON NJ'IN>UJ,E S NuveE n naCni,nON@

li la 8l 9101010 l@l 7 11 11 NA 80 l

L OSS OF OR DAYAGE TO F ACILITY TYPE DESCHIPTION 'l i a Lz_J@l u^ 790928o 4 i F 8 9 10 3 80 iss l

  • Ldal LUv[ @l ESCHIPTION NA l lllll lllllllj 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

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