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{{#Wiki_filter:NRC FORM 366                                                                                                                            U. S. NUCLE AR REGULATOR) COMMISSION
{{#Wiki_filter:NRC FORM 366                                                                                                                            U. S. NUCLE AR REGULATOR) COMMISSION l.lCENSEE EVENT REPORT CONTROL BLOCK: l
* l.lCENSEE EVENT REPORT CONTROL BLOCK: l
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(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
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                                                                                                                                                                                        @
1      8 9            CICENSEE CODE              14    1S CON'T lolIl
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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
   #        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
   #        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
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)
[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
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
   /      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"
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li la 8l 9101010 l@l 7                                11      11 NA 80 l
li la 8l 9101010 l@l 7                                11      11 NA 80 l
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A. C. To111soa, Jr.                                                                        919-457-9521                            o N AME OF PnFPAF10 Ft                                                                                      PHONE                                                      S,
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.
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.
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}}
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

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(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

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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)

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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.

Y j

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