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{{#Wiki_filter:NRC FORM 36G U. S. NUCLE AR REGULATORY COMMISSION f7 77)
{{#Wiki_filter:NRC FORM 36G U. S. NUCLE AR REGULATORY COMMISSION f7 77)
                        .
                                   ,-                                            LICENSEE EVENT REPORT
                                   ,-                                            LICENSEE EVENT REPORT
                 ~ CONTROL ULOCK: l                      l    l      l    l    l    l                  (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) dd 8l'0l 7              9 ul Dl B Sl1l@l0 LICEr. Sic CODE                14    15 0    -l 0 l 0 NlPlF LICENSE NUMBEH
                 ~ CONTROL ULOCK: l                      l    l      l    l    l    l                  (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) dd 8l'0l 7              9 ul Dl B Sl1l@l0 LICEr. Sic CODE                14    15 0    -l 0 l 0 NlPlF LICENSE NUMBEH Ol3 @l4lll1l1l1l@l 23        26      LICENSE TYPE JJ        57 CATSS l@
                                                                                                              -
Ol3 @l4lll1l1l1l@l 23        26      LICENSE TYPE JJ        57 CATSS l@
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the health and safety of the public or unit personnel.                                                          (NP-33-79-03)                                    [
the health and safety of the public or unit personnel.                                                          (NP-33-79-03)                                    [
SYSTEM              CAUSE          CAUSE                                                      C O9 P.        VALVE CODE                CCCE        SUBOODE                CO'.PONENT CODE                      SUBCODE          SUBCODE o    o                              lc l uj@                      xl@ l Z jg lV l A lL lV E l X l@ {Q                                                    Dl@
SYSTEM              CAUSE          CAUSE                                                      C O9 P.        VALVE CODE                CCCE        SUBOODE                CO'.PONENT CODE                      SUBCODE          SUBCODE o    o                              lc l uj@                      xl@ l Z jg lV l A lL lV E l X l@ {Q                                                    Dl@
zu 7          8                          9          to          11            12            i3                            td            19 OCCU R R E N CE        REPORT                      REVISION
zu 7          8                          9          to          11            12            i3                            td            19 OCCU R R E N CE        REPORT                      REVISION SEQUE NTI AL REPOHT NO.                            CODE                  TYPE                        N O.
_
SEQUE NTI AL REPOHT NO.                            CODE                  TYPE                        N O.
LE R 'RO      EVENT YE AR
LE R 'RO      EVENT YE AR
                   @ nEeoRT                [7l9                    _
                   @ nEeoRT                [7l9                    _
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-03 DATE OF OCCURRENCE: January 2,1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feed Pump 1-1 Inoperable Conditions Prior to Occurrence:      The unit was in Mode 1, with Power (MWT) = 2331,    e and Load (Gross MWE) = 785.
TOLEDO EDISON COMPANY
          '
DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-03 DATE OF OCCURRENCE: January 2,1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feed Pump 1-1 Inoperable Conditions Prior to Occurrence:      The unit was in Mode 1, with Power (MWT) = 2331,    e and Load (Gross MWE) = 785.
Description of Occurrence: At 0610 hours on January 2,1979 while perf orming Surveil-lance Test ST 5071.01, " Auxiliary Feedwater System Monthly Test", valves Main Steam (MS) 106 and 106A, which supply steam to Auxiliary Feed Pump 1-1, f ailed to operate properly on initial operation.                                                          ,
Description of Occurrence: At 0610 hours on January 2,1979 while perf orming Surveil-lance Test ST 5071.01, " Auxiliary Feedwater System Monthly Test", valves Main Steam (MS) 106 and 106A, which supply steam to Auxiliary Feed Pump 1-1, f ailed to operate properly on initial operation.                                                          ,
This placed the unit in the Action Statement of Technical Specification 3.7.1.2 which requires that with one pump inoperable, the inoperable pump be repaired within 72 hours or be in Hot Shutdown within the next 12 hours. The Technical Specification requires operability of both Auxiliary Feed Pumps (AFP) while in Modes 1, 2, and 3.
This placed the unit in the Action Statement of Technical Specification 3.7.1.2 which requires that with one pump inoperable, the inoperable pump be repaired within 72 hours or be in Hot Shutdown within the next 12 hours. The Technical Specification requires operability of both Auxiliary Feed Pumps (AFP) while in Modes 1, 2, and 3.
                                                                                            !
Designation of Apparent Cause of Occurrence: The cause of the occurrence is attri-buted to a buildup of dirt on the stem of the valves. This caused the valves to stick and hangup. The dirt buildup was caused by construction activities associated with the installation of a new security system.
Designation of Apparent Cause of Occurrence: The cause of the occurrence is attri-buted to a buildup of dirt on the stem of the valves. This caused the valves to stick and hangup. The dirt buildup was caused by construction activities associated with the installation of a new security system.
Analysis of Occurrence:    There was no danger to the health and safety of the public or to unit personnel. Auxiliary Feed Pump 1-2 was operable during the inoperability of AFP l-1.
Analysis of Occurrence:    There was no danger to the health and safety of the public or to unit personnel. Auxiliary Feed Pump 1-2 was operable during the inoperability of AFP l-1.
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LER #79-002
LER #79-002


I
I T01$DO EDISON CO:FANY DAVIS-0 ESSE NUCLEAR POWER STATION U' LIT ONE PAGE 2 SUPPLDIENTAL INFORMATION FOP. LER NP-33-79-03 Failure Data: This is not a repetitive occurrence. No previous failures of this type have been reported.
    .. .  *-
      ,
.
  '
T01$DO EDISON CO:FANY DAVIS-0 ESSE NUCLEAR POWER STATION U' LIT ONE PAGE 2 SUPPLDIENTAL INFORMATION FOP. LER NP-33-79-03 Failure Data: This is not a repetitive occurrence. No previous failures of this type have been reported.
LER //79-002
LER //79-002
                                                                         .}}
                                                                         .}}

Revision as of 19:02, 1 February 2020

LER 79-002/03L-0 on 790102:main Steam Valves 106 & 106A Failed to Open Due to Buildup of Dirt on Valve Stems.Dirt Buildup Result of Recent Const Activities.Valve Stems Cleaned & Valve MS106 Greased
ML19273A985
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/29/1979
From: Oneill J
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19273A981 List:
References
LER-79-002-03L, LER-79-2-3L, NP-33-79-03, NP-33-79-3, NUDOCS 7902010172
Download: ML19273A985 (3)


Text

NRC FORM 36G U. S. NUCLE AR REGULATORY COMMISSION f7 77)

,- LICENSEE EVENT REPORT

~ CONTROL ULOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) dd 8l'0l 7 9 ul Dl B Sl1l@l0 LICEr. Sic CODE 14 15 0 -l 0 l 0 NlPlF LICENSE NUMBEH Ol3 @l4lll1l1l1l@l 23 26 LICENSE TYPE JJ 57 CATSS l@

cov r 7

0 1 8

E ,"CE l Ll@ Ol 5l 0l -l 0] 3l 4 6 @l0 f.,3 61 DOCK ET NU'.'3 E R 66 63 l1 EVENT l0 l2DATEl 7 l 9 @l 0 l 1 REPORT 14 75 l2l9 l 7 l 980 l@

DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h j o l 2 ] l On 1/2/79, during surveillance testing, valves Main Steam (MS) 106 and 106A failed to l o 3 l open. At 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />, Auxiliary Feed Pump (AFP) 1-1 was declared inoperable. The unit]

was placed in the Action Statement of Technical Specification (TS) 3.7.1.2. This re-

[o ja l o 5 l quires the one inoperable pump be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown with1 o o [ in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The valves were repaired and AFP l-1 was declared operable. l There was no danger tol l o l 7 ] l The unit was removed f rom the Action Statement of TS 3.7.1.2.

0 8 )

the health and safety of the public or unit personnel. (NP-33-79-03) [

SYSTEM CAUSE CAUSE C O9 P. VALVE CODE CCCE SUBOODE CO'.PONENT CODE SUBCODE SUBCODE o o lc l uj@ xl@ l Z jg lV l A lL lV E l X l@ {Q Dl@

zu 7 8 9 to 11 12 i3 td 19 OCCU R R E N CE REPORT REVISION SEQUE NTI AL REPOHT NO. CODE TYPE N O.

LE R 'RO EVENT YE AR

@ nEeoRT [7l9 _

0l 0l 2l l/l 10 3l lL l l-l l0 l 23 24 2ts 27 28 29 JO 31 J2

_ 21 22 O PLA T t TH HOURS S E IT D F B. SUP Li MAN FA T PER TA Et A TO lXlQ Zl@ ZlQ W@ l0l0 0l0l [Y @

46 ly l@ lA]@

43 l44V l 0 l 8 l 547 l@

33 34 33 3o 31 40 42 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l Failure of valves MS106 and MS106A to operate was attributed to a buildup of dirt on l g,j,,lthe valve stems. The dirt buildup was a result of construction activities associated i g  ; with the installation of a new security system. The valve stems were cleaned and valve ST 5071.01 was completed

, 3 lMS106 was greased. The valves were tested satisfactorily.

,,ja; gand AFP l-1 was declared operable at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on 1/2/79. 80

7 8 9

' POWER OTHE R STA TUS ISCOV FY OtSCOVERY DESCHlPTION ST S l

i s EjQ l 0 l 8 l 3 @l NA l l B l@l Surveillance Test A Tf Vli / CON TE N T A'.10UNT OF ACTIVITY LOCATION OF RE LEASE RELEASED OF RELEME i G Zl l NA l l NA 80 l

7 8 9 10 11 44 43 PERSONNEL E XPOSURES NUMBE R TYPE CESCRIPTION i 7 1010 Oj@l Z @t NA I PE R$uN'.E L INJURIES NUYPF H CESCRIPTION FF18 Lo 010181 x^ l 80 7 9 1i 12 LOSS OF OR O.W AGE To F ACILITY ..

TYFE Di SC HIP D ON N^

l' l o 8l 9L zJ@l10 80 1

PUBLICITY NRC USE ONLY 2 "

Im % mmn,c, I NI61m NA 7902010/7A -

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i t, M m 0%N W 1 MFmaM, M.

JVR 79-003 naveoppngpanen pggyL.

.. s.

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-03 DATE OF OCCURRENCE: January 2,1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feed Pump 1-1 Inoperable Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) = 2331, e and Load (Gross MWE) = 785.

Description of Occurrence: At 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> on January 2,1979 while perf orming Surveil-lance Test ST 5071.01, " Auxiliary Feedwater System Monthly Test", valves Main Steam (MS) 106 and 106A, which supply steam to Auxiliary Feed Pump 1-1, f ailed to operate properly on initial operation. ,

This placed the unit in the Action Statement of Technical Specification 3.7.1.2 which requires that with one pump inoperable, the inoperable pump be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The Technical Specification requires operability of both Auxiliary Feed Pumps (AFP) while in Modes 1, 2, and 3.

Designation of Apparent Cause of Occurrence: The cause of the occurrence is attri-buted to a buildup of dirt on the stem of the valves. This caused the valves to stick and hangup. The dirt buildup was caused by construction activities associated with the installation of a new security system.

Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. Auxiliary Feed Pump 1-2 was operable during the inoperability of AFP l-1.

Corrective Action: The valve MS106A stroked properly when it was attempted a Thesecond time and no excessive dirt buildup was observed on the stem after stroking.

valve was successfully stroked several additional times and returned to operability.

The valve stem of MS106A was cleaned under Maintenance Work Order 79-1377, prior to the plant returning to operation.

The valve MS106 was stroked while being observed by maintenance personnel. Abnormal noise and dirt buildup on the stem was observed. Under Maintenance Work Order 79-1190 the valve was then cycled six times resulting in satisfactory operation. Su rveillance Test ST 5071.01, was completed at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on January 2, 1979, and Auxiliary Feed Pump 1-1 uas declared operable. The unit was then removed from the Action Statement of Technical Specification 3.7.1.2. Normal activities performed in the room should not cause a dirt buildup on the valve stems as was caused by the construction activi-ties associated with the installation of the new security system. Other equipment in the room was laspected and no dirt buildup was observed.

LER #79-002

I T01$DO EDISON CO:FANY DAVIS-0 ESSE NUCLEAR POWER STATION U' LIT ONE PAGE 2 SUPPLDIENTAL INFORMATION FOP. LER NP-33-79-03 Failure Data: This is not a repetitive occurrence. No previous failures of this type have been reported.

LER //79-002

.