ML19274E472: Difference between revisions

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26 l1LICENSE l1 l1TYPE              l l1 JJl@l51 CATSd    l@
26 l1LICENSE l1 l1TYPE              l l1 JJl@l51 CATSd    l@
7          8 9          LICENSEE CODE CON'T                                                                                                          ~
7          8 9          LICENSEE CODE CON'T                                                                                                          ~
                      * "
3g[gC          l L @] 0 l 5 l 0 l - [ 0 l 3 l 4 l 6 @l                          0 lEVENT 2 l DATE 2 l 0 l 7 14l 9 l@l          0REPORT l 3 lDATE 1l9l7 o    i                                                                                                                              75                        80 l 9 @
3g[gC          l L @] 0 l 5 l 0 l - [ 0 l 3 l 4 l 6 @l                          0 lEVENT 2 l DATE 2 l 0 l 7 14l 9 l@l          0REPORT l 3 lDATE 1l9l7 o    i                                                                                                                              75                        80 l 9 @
61            COCKET NL*.'5 ER              Ed    63 7          8                      00 EVENT DESCRIPTION AND PROB ABLE CONSECUENCES h i
61            COCKET NL*.'5 ER              Ed    63 7          8                      00 EVENT DESCRIPTION AND PROB ABLE CONSECUENCES h i
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l o l 7 l l health and saf ety of the oublic or unit personnel. AFW Systen 1-2 was available to I
l o l 7 l l health and saf ety of the oublic or unit personnel. AFW Systen 1-2 was available to I
o    a l feed the affected steam generator.                                        (NP-33-79-33)
o    a l feed the affected steam generator.                                        (NP-33-79-33)
CAUSE                                                    COYP.          VALVE SYSTEN1          CAUSE                                                                                  SUSCODE
CAUSE                                                    COYP.          VALVE SYSTEN1          CAUSE                                                                                  SUSCODE CODE              CODE        SUSCODE                  COhiPONENT CODE                SUBCODE 7
                                                                                                                                                                                    *
                                                                                                                                                                                      -
CODE              CODE        SUSCODE                  COhiPONENT CODE                SUBCODE 7
o 9 8
o 9 8
lC l Hl@ l El@ l Al@ l V] Al Ll Vl 0l P h W@ lD l@
lC l Hl@ l El@ l Al@ l V] Al Ll Vl 0l P h W@ lD l@
9        10        11            12              13                          18          19            20 REVISION SE QUE NTI AL                      OCCURRENCE          REPORT
9        10        11            12              13                          18          19            20 REVISION SE QUE NTI AL                      OCCURRENCE          REPORT CODE              TYPE                      N o.
_
CODE              TYPE                      N o.
EVENT YE AR                            REPORT NO.
EVENT YE AR                            REPORT NO.
LER RO h REPOhT l7l9                            l-l            l 01 3l 0l              l/l          l0l3l                  Ll          l-l        10l 21          28      29          30            31          32
LER RO h REPOhT l7l9                            l-l            l 01 3l 0l              l/l          l0l3l                  Ll          l-l        10l 21          28      29          30            31          32
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       ,    4      l Action Statement of Technical Specification 3.7.1.2. _                                                                                                  80 7          8 9
       ,    4      l Action Statement of Technical Specification 3.7.1.2. _                                                                                                  80 7          8 9
                                     % POV.ER                    OTHER STATUS                DISCOV RY                          DISCOVERY DESCRIPTION ST    S l
                                     % POV.ER                    OTHER STATUS                DISCOV RY                          DISCOVERY DESCRIPTION ST    S l
li j s j y@ l 0l 8 l 7 l@l                                NA                          l    l B l@l Surveillance Test ST 5071.01 ACTIVITY      CONTENT AYOUNT CF ACTIVITY                                                      LOCATION OF RELEASE RELEASED OF RELE ASE (TI6] y @ l Z l@l NA                                                                    l          l NA                                                                  80 10                                                      44          45 7        8 9                            11 PERSGNNEL EXPOSURES NUYBER              TYPE      CESCRIPTION NA                                                                                                                    l i    7 l 0 l 0 l 0 lhl Z hl
li j s j y@ l 0l 8 l 7 l@l                                NA                          l    l B l@l Surveillance Test ST 5071.01 ACTIVITY      CONTENT AYOUNT CF ACTIVITY                                                      LOCATION OF RELEASE RELEASED OF RELE ASE (TI6] y @ l Z l@l NA                                                                    l          l NA                                                                  80 10                                                      44          45 7        8 9                            11 PERSGNNEL EXPOSURES NUYBER              TYPE      CESCRIPTION NA                                                                                                                    l i    7 l 0 l 0 l 0 lhl Z hl PERSONN E L IN )b RIES
  '          *
* PERSONN E L IN )b RIES
* NUY9ER              DESCRIPTION l
* NUY9ER              DESCRIPTION l
7 1 R 8 9 l0l0l0l@l      11    12 NA 80 LOSS OF OR D AY AGE TO F ACILITY TYPE      DESCRIPTION "A                                                                                                                                          I L'hJ8 Lz 7            9 J@l    to 80 PUBLICITY                                                                                                                          NRC USE ONLY              ~
7 1 R 8 9 l0l0l0l@l      11    12 NA 80 LOSS OF OR D AY AGE TO F ACILITY TYPE      DESCRIPTION "A                                                                                                                                          I L'hJ8 Lz 7            9 J@l    to 80 PUBLICITY                                                                                                                          NRC USE ONLY              ~
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-33
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-33 DATE OF EVENT: February 20, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feedwater (AFW) Systen valve torque switch failed Conditions Prior to Occurrence: The unit was in Mode 1, with Power (!C(I) = 2422, and Load (Gross MWE) = 818.
                                                      .
DATE OF EVENT: February 20, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feedwater (AFW) Systen valve torque switch failed Conditions Prior to Occurrence: The unit was in Mode 1, with Power (!C(I) = 2422, and Load (Gross MWE) = 818.
Description of Occurrence: On February 20, 1979 at 1300 hours while performing Surveillance rest ST 5071.01, " Auxiliary Feedwater System Monthly Test", AFW System Valve AF3869 could not be closed by the motor operator, but could be opened by the    ..
Description of Occurrence: On February 20, 1979 at 1300 hours while performing Surveillance rest ST 5071.01, " Auxiliary Feedwater System Monthly Test", AFW System Valve AF3869 could not be closed by the motor operator, but could be opened by the    ..
motor operator. This rendered AFW System 1-1 inoperable and placed the unit in the Action Statement of Technical Specification 3.7.1.2, which requires two independent steam generator auxiliary feedwater pumps and flowpaths be operable. The Action Statement requires the inoperable system be returned to operable status within 72 hours or be in Hot Shutdown within the next 12 hours.
motor operator. This rendered AFW System 1-1 inoperable and placed the unit in the Action Statement of Technical Specification 3.7.1.2, which requires two independent steam generator auxiliary feedwater pumps and flowpaths be operable. The Action Statement requires the inoperable system be returned to operable status within 72 hours or be in Hot Shutdown within the next 12 hours.
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Corrective Action: A new torque switch was installed under Maintenance Work Order 79-1558. This torque switch supplied on the vendor's same part number, is of a heavier duty design. At 1915 hours on February 20, 1979, Surveillance Test ST 5071.01 was performed and AFW System 1-1 was declared operable, removing the unit from the Action Statement of Technical Specification 3.7.1.2.
Corrective Action: A new torque switch was installed under Maintenance Work Order 79-1558. This torque switch supplied on the vendor's same part number, is of a heavier duty design. At 1915 hours on February 20, 1979, Surveillance Test ST 5071.01 was performed and AFW System 1-1 was declared operable, removing the unit from the Action Statement of Technical Specification 3.7.1.2.
Failure Data: One previously reported failure of AFW System motor operator torque switches had been reported under Licensee Event Report NP-33-77-83.
Failure Data: One previously reported failure of AFW System motor operator torque switches had been reported under Licensee Event Report NP-33-77-83.
                                                          .
LER #79-030}}
LER #79-030}}

Revision as of 17:38, 1 February 2020

LER 79-030/03L-0 on 790220:auxiliary Feedwater Valve Could Not Be Closed,Rendering Auxiliary Feedwater Sys 1-1 Inoperable.Caused by Faulty Torque Switch.Heavier Duty Unit Installed & Sys Declared Operable
ML19274E472
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/19/1979
From: Naylor R
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19274E468 List:
References
LER-79-030-03L, LER-79-30-3L, NP-33-79-33, NUDOCS 7903260227
Download: ML19274E472 (2)


Text

U.S. NUCLE AR REGULATORY COMMISSION NRC FORM 366 (7 77) '

LICENSEE EVENT REPORT CONTROL BLOCK:

1 l l l l l 6

lh (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) 0 1 l0lH D l B l S l 114l@l150 l 0 - l 0 lLICENSE 0 lNNvYSER l P I F l- l01325 l@l4 _

26 l1LICENSE l1 l1TYPE l l1 JJl@l51 CATSd l@

7 8 9 LICENSEE CODE CON'T ~

3g[gC l L @] 0 l 5 l 0 l - [ 0 l 3 l 4 l 6 @l 0 lEVENT 2 l DATE 2 l 0 l 7 14l 9 l@l 0REPORT l 3 lDATE 1l9l7 o i 75 80 l 9 @

61 COCKET NL*.'5 ER Ed 63 7 8 00 EVENT DESCRIPTION AND PROB ABLE CONSECUENCES h i

l o l 2 l l On 2/20/79 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> while perf orming surveillance testing, Auxiliary Feedwater This rendered AFW Sys- l o a I (AFW) Valve AF3869 could not be closed by the notor operator.

The l o 4 l ten 1-1 inoperable and placed the unit in the Action Statement of T.S. 3.7.1.2.

lolsl l Action Statement requires the inoperable systen be returned to operable status within l 0 6 ]72 hours 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 />. There was no danger to the I I

l o l 7 l l health and saf ety of the oublic or unit personnel. AFW Systen 1-2 was available to I

o a l feed the affected steam generator. (NP-33-79-33)

CAUSE COYP. VALVE SYSTEN1 CAUSE SUSCODE CODE CODE SUSCODE COhiPONENT CODE SUBCODE 7

o 9 8

lC l Hl@ l El@ l Al@ l V] Al Ll Vl 0l P h W@ lD l@

9 10 11 12 13 18 19 20 REVISION SE QUE NTI AL OCCURRENCE REPORT CODE TYPE N o.

EVENT YE AR REPORT NO.

LER RO h REPOhT l7l9 l-l l 01 3l 0l l/l l0l3l Ll l-l 10l 21 28 29 30 31 32

_ 21 22 23 24 26 HOURS S BN IT D FO 15 8. SL PLIE MA F TUPER T KE A O C PL T E l33A lgl34Xlg Z lg l36Z l@ l 0l 0l 0l 0l40 31 lYg 41 lY [g W@

42 43 44 L l 2 ] 0 l 047l@

35 CAUSE DESCRIPTION AND CORRECTIVE ACTICNS h i o IThe cause of the occurrence was due to a f aulty torque switch in the notor operator fori g , ; , ; ) AFW Valve AF3869. A replacement torque switch, of heavier duty design supplied on

, ., lthe vendor's sa=c part number, was installed. At 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on 2/20/79, ST 5071.01 l from the ,

l , l 3 g l was perforned and AFW Systen 1-1 was declared operable, removing the unit

, 4 l Action Statement of Technical Specification 3.7.1.2. _ 80 7 8 9

% POV.ER OTHER STATUS DISCOV RY DISCOVERY DESCRIPTION ST S l

li j s j y@ l 0l 8 l 7 l@l NA l l B l@l Surveillance Test ST 5071.01 ACTIVITY CONTENT AYOUNT CF ACTIVITY LOCATION OF RELEASE RELEASED OF RELE ASE (TI6] y @ l Z l@l NA l l NA 80 10 44 45 7 8 9 11 PERSGNNEL EXPOSURES NUYBER TYPE CESCRIPTION NA l i 7 l 0 l 0 l 0 lhl Z hl PERSONN E L IN )b RIES

  • NUY9ER DESCRIPTION l

7 1 R 8 9 l0l0l0l@l 11 12 NA 80 LOSS OF OR D AY AGE TO F ACILITY TYPE DESCRIPTION "A I L'hJ8 Lz 7 9 J@l to 80 PUBLICITY NRC USE ONLY ~

@ 7 9 0 3 2 6 0 2a7 llllllll l lll7 2 o ISSUED lN l @lDESCn>

NA prion bJ .;;

68 69 8 9 la 7

mhad Nayh umb%M, M. 2M DVR 79-039 NAME OF PREPAREn pggyg;

~

^

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-33 DATE OF EVENT: February 20, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Auxiliary Feedwater (AFW) Systen valve torque switch failed Conditions Prior to Occurrence: The unit was in Mode 1, with Power (!C(I) = 2422, and Load (Gross MWE) = 818.

Description of Occurrence: On February 20, 1979 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> while performing Surveillance rest ST 5071.01, " Auxiliary Feedwater System Monthly Test", AFW System Valve AF3869 could not be closed by the motor operator, but could be opened by the ..

motor operator. This rendered AFW System 1-1 inoperable and placed the unit in the Action Statement of Technical Specification 3.7.1.2, which requires two independent steam generator auxiliary feedwater pumps and flowpaths be operable. The Action Statement requires the inoperable system be returned to operable status 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 />.

Designation of Apparent Cause of Occurrence: The apparent cause of the occurrence was due to a f aulty torque switch in the mocar operator for AFW Valve AF3869. The closing torque switch would actuate and prevent the valve from closing with the motor operator. The valve could be operated manually.

Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. In the event of an occurrence which required the AFW System, AFW System 1-2 would have fed the af fected steam generator.

Corrective Action: A new torque switch was installed under Maintenance Work Order 79-1558. This torque switch supplied on the vendor's same part number, is of a heavier duty design. At 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on February 20, 1979, Surveillance Test ST 5071.01 was performed and AFW System 1-1 was declared operable, removing the unit from the Action Statement of Technical Specification 3.7.1.2.

Failure Data: One previously reported failure of AFW System motor operator torque switches had been reported under Licensee Event Report NP-33-77-83.

LER #79-030