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{{#Wiki_filter:C FORM 366                                                                                                            U.BCEELCAO GnBILA9%R7 N ~~
{{#Wiki_filter:C FORM 366                                                                                                            U.BCEELCAO GnBILA9%R7 N ~~
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* LICENSEE EVENT REPORT
* LICENSEE EVENT REPORT
       ,        Control sLoCK:                  l    l      l    l  l      l@                (PLEASE PRINT C3 TYPE ALL RE*Uf RE3 INFORMATION) l@
       ,        Control sLoCK:                  l    l      l    l  l      l@                (PLEASE PRINT C3 TYPE ALL RE*Uf RE3 INFORMATION) l@
          -
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l                                                                                                                                                                I TTil8 101  9 nLICENSEE l D i CODE  B l S l ll@l15 e l e l e l oLICENSE 14 l e l eNuveEH l 01 o f o I e 23l o l@l        26    4LICENSE l i l i TYPE l i l J011@l 57 CAT 68 CON'T o i            "'',$
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       , , i      Further investigation found that the size of the dump solenoid orifice was too small                                                                          l g ito allow adequate bleedoff flow. The solenoid will be changed.                                                                                                          l l
       , , i      Further investigation found that the size of the dump solenoid orifice was too small                                                                          l g ito allow adequate bleedoff flow. The solenoid will be changed.                                                                                                          l l
i 4      l 80 7      8 9 STA S              % POWER                      oTHER STATUS              IS O HY                              DISCOVERY DESCRIPTION is        l E l@ l 0l 5 l 4 l@l NA                                              l    lBl@lSurveillanceTestST 5099.08                                                ]
i 4      l 80 7      8 9 STA S              % POWER                      oTHER STATUS              IS O HY                              DISCOVERY DESCRIPTION is        l E l@ l 0l 5 l 4 l@l NA                                              l    lBl@lSurveillanceTestST 5099.08                                                ]
A TIVITY CO TENT CELE ASED OF RELEASE                      AMOUNT OF ACTIVITY                                                    LOCATION OF RELEASE l NA                                                        NA                                                                      l i 6      [_Zj @                                                                l          l
A TIVITY CO TENT CELE ASED OF RELEASE                      AMOUNT OF ACTIVITY                                                    LOCATION OF RELEASE l NA                                                        NA                                                                      l i 6      [_Zj @                                                                l          l PERSONNEt ExPOSSES NUM                TYPE        DESCRIPTION l
                                                                                                                                                                              "
    '      ' *              '                                                    "
* PERSONNEt ExPOSSES NUM                TYPE        DESCRIPTION l
i 7      10lEERI 0 l@l Zl@l NA PERSONNEL INJU IES
i 7      10lEERI 0 l@l Zl@l NA PERSONNEL INJU IES
                     ~                                ~e                                              T1AD DDIElklAl                                                            i 7
                     ~                                ~e                                              T1AD DDIElklAl                                                            i 7
       , R 8 9 i orsTei@r"h"rl 11      12
       , R 8 9 i orsTei@r"h"rl 11      12
                                                                                                    '
                                                                                                         < J UE I Wll%Ell1flLa                                                  80 LOSS OF OR DAMAGE TO FACILITY TiPE      DESCmP flON l
                                                                                                         < J UE I Wll%Ell1flLa                                                  80 LOSS OF OR DAMAGE TO FACILITY TiPE      DESCmP flON l
7 i 9 8 9 W @l10NA                                                                                                                                                      80 PUBLICITY                                                                                                                            NRC USE ONL Y
7 i 9 8 9 W @l10NA                                                                                                                                                      80 PUBLICITY                                                                                                                            NRC USE ONL Y 8101220 4 40                                                                              3,iiii;iiii,lj !
                                        ' "
8101220 4 40                                                                              3,iiii;iiii,lj !
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                                                                                                                                               ;
68 ?3                            80 5  l
68 ?3                            80 5  l DVR 80-210                NAME or anEPAHEn                                                                                  PHONE:
                                                                                                                                                                  *
* DVR 80-210                NAME or anEPAHEn                                                                                  PHONE:
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e                  _    _
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r
r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-117 DATE OF EVENT: December 19, 1980                              ,
:
          *
        .
* TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-117
                                                                        .
  !
DATE OF EVENT: December 19, 1980                              ,
                                                  '
                                                  .
FACILITY: Davis-Besse Unit 1                ,
FACILITY: Davis-Besse Unit 1                ,
                                                                      -
IDENTIFICATION OF OCCURRENCE: Demineralized Water Containment Isolation Valve DW6831B did not meet required stroke time Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) - 1496 and Load (Gross MWE) = 490.
IDENTIFICATION OF OCCURRENCE: Demineralized Water Containment Isolation Valve DW6831B did not meet required stroke time Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) - 1496 and Load (Gross MWE) = 490.
Description of Occurrence: On December 19, 1980 at 0515 hours during performance of ST 5099.08, Miscellaneous Valves Quarterly Test, operations personnel discovered that demineralized water containment isolation valve DW6831 did not meet its required stroke time of 10 seconds. It closed in 11.4 seconds. DW6831B provides standpipe flush flow for reactor coolant pump standpipes. This event placed the unit in the Action State-ment of Technical Specification 3.6.3.1, which requires this valve to be operable in Mbdes 1, 2, 3, and 4. The action statement "b" required the valve to be returned to operable status within four hours or be secured in its safety position. The require-ments were met.
Description of Occurrence: On December 19, 1980 at 0515 hours during performance of ST 5099.08, Miscellaneous Valves Quarterly Test, operations personnel discovered that demineralized water containment isolation valve DW6831 did not meet its required stroke time of 10 seconds. It closed in 11.4 seconds. DW6831B provides standpipe flush flow for reactor coolant pump standpipes. This event placed the unit in the Action State-ment of Technical Specification 3.6.3.1, which requires this valve to be operable in Mbdes 1, 2, 3, and 4. The action statement "b" required the valve to be returned to operable status within four hours or be secured in its safety position. The require-ments were met.
Line 82: Line 62:
   '          orifice was not large enough to allow adequate bleedoff flow.
   '          orifice was not large enough to allow adequate bleedoff flow.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel.      DW6831A which is the inner containment isolation valve was operable at the time of the occurrence.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel.      DW6831A which is the inner containment isolation valve was operable at the time of the occurrence.
    ,
Corrective Action: Under Maintenance Work order IC-837-80, the air supply to DW6831B was readjusted and DU6831B was successfully stroked. DW6831B was declared operable at 0630 hours on December 19, 1980 within the action statement "b" deadline of Technical i        Specification 3.6.3.1. A facility change reuqest has been prepared to change the sole-noid size.
Corrective Action: Under Maintenance Work order IC-837-80, the air supply to DW6831B was readjusted and DU6831B was successfully stroked. DW6831B was declared operable at 0630 hours on December 19, 1980 within the action statement "b" deadline of Technical i        Specification 3.6.3.1. A facility change reuqest has been prepared to change the sole-
                                                                              -
noid size.
1 Failure Data: There have been no previous similar occurrences.
1 Failure Data: There have been no previous similar occurrences.
I LER #80-093 1
I LER #80-093 1
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Revision as of 10:03, 31 January 2020

LER 80-093/03L-0:on 801219,demineralized Water Containment Isolation Valve DW6831B Did Not Close in Required Time. Caused by Dump Solenoid Orifice Too Small to Allow Adequate Bleedoff Flow.Solenoid to Be Replaced
ML19341A248
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/16/1981
From: Trautman D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19341A247 List:
References
LER-80-093-03L, LER-80-93-3L, NUDOCS 8101220440
Download: ML19341A248 (2)


Text

C FORM 366 U.BCEELCAO GnBILA9%R7 N ~~

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  • LICENSEE EVENT REPORT

, Control sLoCK: l l l l l l@ (PLEASE PRINT C3 TYPE ALL RE*Uf RE3 INFORMATION) l@

l I TTil8 101 9 nLICENSEE l D i CODE B l S l ll@l15 e l e l e l oLICENSE 14 l e l eNuveEH l 01 o f o I e 23l o l@l 26 4LICENSE l i l i TYPE l i l J011@l 57 CAT 68 CON'T o i ",$

g Ql el 5 l a l - l e l 3 l 4 l 6 ]@l 1 l 2 l 1 l 9 l 8 l o j@l o l 1 l 1 l 6 l 8 l 180l@

6d 69 EVENT DATE 14 15 REPOR T DATE I 8 60 61 DOCKET NuYBER EVENT DESCRIPTION AND PROBABLE CON; .dUENCES h o 2 l (NP-33-80-117) On 12/19/80 at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> during the performance of ST 5099.08, Miscel-l 0 3 l laneous Valves Quarterly Test, operations personnel observed that demineralized water l g l containment isolation valve DW6831B did not meet its required stroke time. It closed l fiiTs1 l in 11.4 seconds and is supposed to close in 10 seconds. This placed the unit in the l There was no danger to the health and safety of thel

@ l action statement of T.S. 3.6.3.1.

l"OTil l public or station personnel. The inner containment isolation valve was operable and i I

g lcould have closed in the required time.

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SOI[E COoE Su8C$ct COMPONENT CODE S8 D'E S E Q l Sl Dl@ y@ l A l@ l Vl Al LlV l0 lP l@ ]@ { @

12 13 18 19 20 7 8 9 to 11 OCCURRENCE REPORT REVISION SEQUENTIAL EVENT YE AR REPORT NO. CODE TYPE N O.

OaEg LER/Ro su 18 !o l [__.] lol9l3l g qle l3 l lL l g y

_ 21 22 23 24 26 27 28 a 30 31 32 K A O O PL NT M HOURS S 8 IT FOR* 8. SUPPLIE MAN FACTURER

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35 l36Zl@ l ole lolol J/ 40 (Y_l@

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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lil0llUnder Maintenance Work Order IC-837-80, the air supply was readjusted and DW6831B was l i i asuccessfully stroked. It was declared operable at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on December 19, 1980. I

, , i Further investigation found that the size of the dump solenoid orifice was too small l g ito allow adequate bleedoff flow. The solenoid will be changed. l l

i 4 l 80 7 8 9 STA S  % POWER oTHER STATUS IS O HY DISCOVERY DESCRIPTION is l E l@ l 0l 5 l 4 l@l NA l lBl@lSurveillanceTestST 5099.08 ]

A TIVITY CO TENT CELE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l NA NA l i 6 [_Zj @ l l PERSONNEt ExPOSSES NUM TYPE DESCRIPTION l

i 7 10lEERI 0 l@l Zl@l NA PERSONNEL INJU IES

~ ~e T1AD DDIElklAl i 7

, R 8 9 i orsTei@r"h"rl 11 12

< J UE I Wll%Ell1flLa 80 LOSS OF OR DAMAGE TO FACILITY TiPE DESCmP flON l

7 i 9 8 9 W @l10NA 80 PUBLICITY NRC USE ONL Y 8101220 4 40 3,iiii;iiii,lj !

7 2 o 8 9 h 10 A

68 ?3 80 5 l DVR 80-210 NAME or anEPAHEn PHONE:

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r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-117 DATE OF EVENT: December 19, 1980 ,

FACILITY: Davis-Besse Unit 1 ,

IDENTIFICATION OF OCCURRENCE: Demineralized Water Containment Isolation Valve DW6831B did not meet required stroke time Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MWT) - 1496 and Load (Gross MWE) = 490.

Description of Occurrence: On December 19, 1980 at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> during performance of ST 5099.08, Miscellaneous Valves Quarterly Test, operations personnel discovered that demineralized water containment isolation valve DW6831 did not meet its required stroke time of 10 seconds. It closed in 11.4 seconds. DW6831B provides standpipe flush flow for reactor coolant pump standpipes. This event placed the unit in the Action State-ment of Technical Specification 3.6.3.1, which requires this valve to be operable in Mbdes 1, 2, 3, and 4. The action statement "b" required the valve to be returned to operable status within four hours or be secured in its safety position. The require-ments were met.

Designation of Apparent Cause of Occurrence: The cause was that the dump solenoid

' orifice was not large enough to allow adequate bleedoff flow.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. DW6831A which is the inner containment isolation valve was operable at the time of the occurrence.

Corrective Action: Under Maintenance Work order IC-837-80, the air supply to DW6831B was readjusted and DU6831B was successfully stroked. DW6831B was declared operable at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on December 19, 1980 within the action statement "b" deadline of Technical i Specification 3.6.3.1. A facility change reuqest has been prepared to change the sole-noid size.

1 Failure Data: There have been no previous similar occurrences.

I LER #80-093 1

1 1

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