ML19208A096: Difference between revisions

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{{#Wiki_filter:(7 77), LICENSEE EVENT REPORT CONTROL BLOCK: l lllll(PLEASE PRINT OR TYPE ALL REQUIRED INFORMhTION)
{{#Wiki_filter:(7 77)
*l0l1lNl Cl B ElPl2l@l0 0 l -l 0 l 0 l 0 l 0 l 0 l - l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l ll@7 8 9 LICENSEE CODE 14 15 LICENSE NUMSER 25 26 LICENSE TYPE JO
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E NURN IL hl0 l5 l0 l- l0 3 l2 4 7 8 60 il DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONS'dQUENCES h O 2 lWhile performing PT 8.2.4. RHRSW Operational Component Test. DFRSW numn 2D had a l 0 a l vibration of 12.5 mils. The maximum allowable value is I ,3.6 mils.
7       8 9                                     14   15                                                         25       26                   TYPE JO CON'T E
l 0141 l Technical Specifications 3.7.1.1, 6.9.1.9b I O s i I O 6 I QD.J l l O a llDE CO E S BC E COMPONE NT CODE SUSCOD'E DElS lB l@ Q@ l Bl@ l P lU l M l P l X l X l@ ]@ y @
7       8 NURN            IL hl0 l5 l0DOCKET      l- l0NUMBER  3 l2      4    @l690 l EVENT 8 l 0DATEl 8l 7 l 9 @l REPORT            0 9l0l6l7l9l@
O 9 F 8 9 to 11 12 13 18 19 20.SE QUE NTI AL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR R EPOR T NO.
60           il                                           68                                   74       75                 DATE         80 EVENT DESCRIPTION AND PROBABLE CONS'dQUENCES h O   2 lWhile performing PT 8.2.4. RHRSW Operational Component Test. DFRSW numn 2D had a                                                                                       l 0   a l vibration of 12.5 mils. The maximum allowable value is I ,3.6 mils.
CODE TYPE NO.@ REl7 9ll--jl0l7l1ly 10 l 3l Lll-ll 0lRT 21 22 23 24 26 27 28 29 30 31 32 N AC ON P NT M HOURS 22 S S IT E FOR B.SUPPLIE MANUFACTURER
l 0141 l Technical Specifications 3.7.1.1, 6.9.1.9b                                                                                                                               I O   s i                                                                                                                                                                       I O   6                                                                                                                                                                         I QD.J l                                                                                                                                                                           l O   a l                                                                                                                                                                      l DE            CO E       S BC E                     COMPONE NT CODE                 SUSCOD'E                 DE F
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lS lB l@ Q@ l Bl@ l P lU l M l P l X l X l@ ]@ y @
33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS a IAn investigation of the pump revealed a part of a spring lodged in the vane of the i i LLL'_J limpell er.
9         to         11             12               13                           18           19             20
This was removed, the pumn was insi,ected, tested, and returned to service. I IIt is believed that this partial spring came from a check valve disk assembly on the I i 2l discharge of the nuclear and/or conventional service water pumps.
                              .                                         SE QUE NTI AL                     OCCURRENCE             REPORT                       REVISION LER/RO     EVENT YEAR                               R EPOR T NO.                           CODE                 TYPE                           NO.
In the pas i these I i 3 g l valves have sustained damage apparent 1v by reverse pressure from the other (CON'T) l7 8 9 80 STA% POWER OTHER STATUS DISCO RY DISCOVERY QESCRIPTION
              @ RE        RT l7 9l 21        22 l--j 23 l0l7l1l 24               26 y
$ y@ l 0l 3 l 3 l@l NA lW @lNAl7 8 8 12 11 44 45 46 80 RELEASE @D OF RELEASE l NA lNAlAMOUNT OF ACTIVITY LOCATION OF RELEASE l Zl1 6'' *'PEnsONNEL ExPOSuAES
27 10 l 3                  l Ll          l-l          l 0l 28         29           30             31           32 N AC                 ON P NT           M                         HOURS 22       S S IT E           FOR       B.     SUPPLIE             MANUFACTURER
"''*NUMBER TYPE DESCRIPTION W l0 0 l0 l@W@l NA l'' ''PERtONNe'L INJU IES NUMBER DESCRIPTION (E' "l 0 l 0 l 0 l@l NA i a i'-<-7 8 9 11 12'80'm=E^c;;'^ "" @
              ]33X ]@[_X_J@
7909120 f.3 D W@=NA P1ll1 9 7 8 9 10 Si issue @loeSCRiPnON h NRC USE ONLY
34                l35Z l@           W@
, NA 2 0lllllllllllljj 7 8 9 10_68 69 80 %NAME OF PREPARER A. C. Tollison, Jr.
36 lG 0l0l0 31                    40 W@
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.s LER CONTINUATION -- RO# 2-79-071 Facility: BSEP Unit No. 2 Event Date:
44             47 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS i
8-8-79 pumps when a pump is deenergized. The check valves were inspected during the 1979 refueling outage and several were found damaged and repaired.
a IAn investigation of the pump revealed a part of a spring lodged in the vane of the                                                                                     i LLL'_J limpell er.                   This was removed, the pumn was insi,ected, tested, and returned to service. I i 2      IIt is believed that this partial spring came from a check valve disk assembly on the                                                                               I i   3    l discharge of the nuclear and/or conventional service water pumps.                                                               In the pas i these I g l valves have sustained damage apparent 1v by reverse pressure from the other (CON'T)                                                                                         l 7        8 9 80 STA               % POWER                       OTHER STATUS                 DISCO RY                             DISCOVERY QESCRIPTION
It is believed that this broken spring segment came from one of those valves. An Engineering Work Request has been written to correct this problem.
$ y@ l 0l 3 l 3 l@l NA 7        8   8 l    W    @l46    NA                                                                    l 12       11                             44     45                                                                             80 AMOUNT OF ACTIVITY                                                        LOCATION OF RELEASE 1 6 RELEASE         l Zl @D OF RELEASE l NA                                               l    NA                                                                      l
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'       ' *             '                                                        "            ''
PEnsONNEL ExPOSuAES
* NUMBER             TYPE         DESCRIPTION W l0
'        ' '
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                            '
NA                                                                                                                           l PERtONNe'L INJU     IES NUMBER             DESCRIPTION                                                                                                   ' "
(E i a 7        8 9 l 0 l 0 l 011l@l12NA                                                                                                                              <- - i' 80
            'm=E
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                                ^c;;'^ "" @
P1 7909120 f.3 D 7
1 9 8 9 W@=NA     l 10 l
Si NRC USE ONLY issueNA@loeSCRiPnON h
                                                                                                                                                                                    ,
2 0 7       8 9           10 l    lllll          lllllljj  _
68 69                           80 %
NAME OF PREPARER A. C. Tollison, Jr.                                                               PHONE:
                                                                                                                                                        ~
                                                                                                                                                                                    $
 
  .
s LER CONTINUATION -- RO# 2-79-071 Facility:   BSEP Unit No. 2                             Event Date:   8-8-79 pumps when a pump is deenergized. The check valves were inspected during the 1979 refueling outage and several were found damaged and repaired. It is believed that this broken spring segment came from one of those valves. An Engineering Work Request has been written to correct this problem.
                                                                          ,,   n .,
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Revision as of 15:28, 19 October 2019

LER 79-071/03L-0:on 790808,RHR Sys Pump 2D Vibrated at Level Higher than Allowable Limit During RHR Sys Operational Component Test.Caused by Spring Part Lodged in Vane of Impeller.Part Removed,Pump Inspected & Tested
ML19208A096
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 09/06/1979
From: Tollison A
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19208A085 List:
References
LER-79-071-03L, LER-79-71-3L, NUDOCS 7909120530
Download: ML19208A096 (2)


Text

(7 77)

, LICENSEE EVENT REPORT

  • CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMhTION) l0l1l Nl LICENSEE Cl B CODE ElPl2l@l0 0 l -l 0 lLICENSE 0 l 0 NUMSER l 0 l 0 l - l 0 l 0 l@l 4 l 1LICENSE l1l1 l 1 l@l$ 7 CAl T $8l@

7 8 9 14 15 25 26 TYPE JO CON'T E

7 8 NURN IL hl0 l5 l0DOCKET l- l0NUMBER 3 l2 4 @l690 l EVENT 8 l 0DATEl 8l 7 l 9 @l REPORT 0 9l0l6l7l9l@

60 il 68 74 75 DATE 80 EVENT DESCRIPTION AND PROBABLE CONS'dQUENCES h O 2 lWhile performing PT 8.2.4. RHRSW Operational Component Test. DFRSW numn 2D had a l 0 a l vibration of 12.5 mils. The maximum allowable value is I ,3.6 mils.

l 0141 l Technical Specifications 3.7.1.1, 6.9.1.9b I O s i I O 6 I QD.J l l O a l l DE CO E S BC E COMPONE NT CODE SUSCOD'E DE F

O 9 8

lS lB l@ Q@ l Bl@ l P lU l M l P l X l X l@ ]@ y @

9 to 11 12 13 18 19 20

. SE QUE NTI AL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR R EPOR T NO. CODE TYPE NO.

@ RE RT l7 9l 21 22 l--j 23 l0l7l1l 24 26 y

27 10 l 3 l Ll l-l l 0l 28 29 30 31 32 N AC ON P NT M HOURS 22 S S IT E FOR B. SUPPLIE MANUFACTURER

]33X ]@[_X_J@

34 l35Z l@ W@

36 lG 0l0l0 31 40 W@

41 l N lg 42 43 Al@ lI Ol7l5l@

44 47 CAUSE DESCRIPTION AND CCRRECTIVE ACTIONS i

a IAn investigation of the pump revealed a part of a spring lodged in the vane of the i LLL'_J limpell er. This was removed, the pumn was insi,ected, tested, and returned to service. I i 2 IIt is believed that this partial spring came from a check valve disk assembly on the I i 3 l discharge of the nuclear and/or conventional service water pumps. In the pas i these I g l valves have sustained damage apparent 1v by reverse pressure from the other (CON'T) l 7 8 9 80 STA  % POWER OTHER STATUS DISCO RY DISCOVERY QESCRIPTION

$ y@ l 0l 3 l 3 l@l NA 7 8 8 l W @l46 NA l 12 11 44 45 80 AMOUNT OF ACTIVITY LOCATION OF RELEASE 1 6 RELEASE l Zl @D OF RELEASE l NA l NA l

' ' * ' "

PEnsONNEL ExPOSuAES

  • NUMBER TYPE DESCRIPTION W l0

' ' '

0 l0 l@W@l

'

NA l PERtONNe'L INJU IES NUMBER DESCRIPTION ' "

(E i a 7 8 9 l 0 l 0 l 011l@l12NA <- - i' 80

'm=E

'

^c;;'^ "" @

P1 7909120 f.3 D 7

1 9 8 9 W@=NA l 10 l

Si NRC USE ONLY issueNA@loeSCRiPnON h

,

2 0 7 8 9 10 l lllll lllllljj _

68 69 80 %

NAME OF PREPARER A. C. Tollison, Jr. PHONE:

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.

s LER CONTINUATION -- RO# 2-79-071 Facility: BSEP Unit No. 2 Event Date: 8-8-79 pumps when a pump is deenergized. The check valves were inspected during the 1979 refueling outage and several were found damaged and repaired. It is believed that this broken spring segment came from one of those valves. An Engineering Work Request has been written to correct this problem.

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