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O.S. NUCLE AR REGULi TORY COMMISSION NRC FORM 363 87 77)                                                                                                                                                                  -
O.S. NUCLE AR REGULi TORY COMMISSION NRC FORM 363 87 77)                                                                                                                                                                  -
LICENSEE EVENT REPORT CONTROL BLOCK: l 1
LICENSEE EVENT REPORT CONTROL BLOCK: l 1
l      l      l    l  l    jh 6
l      l      l    l  l    jh 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI fit 110l            HI      DI      sl  SI      11@l              el  el    ol  el      el LICEN5E NUMBER el  el  el  el  ol 26    ol@k 26            it LICENSE    i  ilililGI TYPE  JG I
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI fit 110l            HI      DI      sl  SI      11@l              el  el    ol  el      el LICEN5E NUMBER el  el  el  el  ol 26    ol@k 26            it LICENSE    i  ilililGI TYPE  JG I
SF JAT be le 7      8 9          LtCENSEE CODE                14      1S
SF JAT be le 7      8 9          LtCENSEE CODE                14      1S CON'T
                                                                                                                                                                                  .
CON'T
[OITl              l'0"],    lL ]@l0 l 5 l 0 l - l 0 l 3 l 4 l 66d@l1ta l1 l2                                18 l8 10 @l 175l 2 lREPORT EVENT DATE            F4 2 l 6D ATE l 8 l 9_j@  80 i        8                      60            61                DOCKET NUMBER EVENT OESCRIPTION AND PROSABLE CONSEQUENCES h lOl2l l (NP-33-E0-110) On 11/28/80 at approximately 1500 hours while performine surveillance 1 i
[OITl              l'0"],    lL ]@l0 l 5 l 0 l - l 0 l 3 l 4 l 66d@l1ta l1 l2                                18 l8 10 @l 175l 2 lREPORT EVENT DATE            F4 2 l 6D ATE l 8 l 9_j@  80 i        8                      60            61                DOCKET NUMBER EVENT OESCRIPTION AND PROSABLE CONSEQUENCES h lOl2l l (NP-33-E0-110) On 11/28/80 at approximately 1500 hours while performine surveillance 1 i
l0l3l l testing, operations personnel noted that PSL107D would not reset after actuating on ITT71 I low steam pressure. With this pressure switch inoperable. Auxiliary Feedwater SystemI lO t si I 1-2 was declared inoperable. This placed the unit in the action statement of Technt-1                                                                                    ,
l0l3l l testing, operations personnel noted that PSL107D would not reset after actuating on ITT71 I low steam pressure. With this pressure switch inoperable. Auxiliary Feedwater SystemI lO t si I 1-2 was declared inoperable. This placed the unit in the action statement of Technt-1                                                                                    ,
I cls l l cal Specification 3.7.1.2.                                      There was no danger to the health and safety of the oublic!
I cls l l cal Specification 3.7.1.2.                                      There was no danger to the health and safety of the oublic!
[ o i 7 l l or to station personnel. Auxiliary Feedwater (AW) Train 1-1 was still operable.                                                                                            I I
[ o i 7 l l or to station personnel. Auxiliary Feedwater (AW) Train 1-1 was still operable.                                                                                            I I
Ioiel l                                                                                                                                                                              80 E                COOE        Stec E                  COYPONENT CODE                  SUB DE            S        E
Ioiel l                                                                                                                                                                              80 E                COOE        Stec E                  COYPONENT CODE                  SUB DE            S        E ICl9l                              lC lH lh Wh l F l@ l I l N l S l T l R l U lh (S_jh (_Z_j                          18          ts                20 h
* ICl9l                              lC lH lh Wh l F l@ l I l N l S l T l R l U lh (S_jh (_Z_j                          18          ts                20 h
8                        9          to            11            12              13 7
8                        9          to            11            12              13 7
OCCURRENCE          RE* ORT                          RE .'ISION SE QU E NTI AL
OCCURRENCE          RE* ORT                          RE .'ISION SE QU E NTI AL REPORT NO.                            CODE                T**E                              NO.
                                ,_
REPORT NO.                            CODE                T**E                              NO.
EVENT VEAR LE R RO
EVENT VEAR LE R RO
               @ ay,La;              1810l 21        22 l-l 2J 1018 l 4 l 24              26
               @ ay,La;              1810l 21        22 l-l 2J 1018 l 4 l 24              26
Line 53: Line 47:
             'ST    s            % POWEFt l
             'ST    s            % POWEFt l
W (_C_jh l 0l 9111@l                                            NA                        l  l Blhl Surveillance Test ST 5071. 04 ACTivlTV CO TENT                                                                                                      LOCATION OF RELEASE F4ELEASEO OF RELEASE                          AMOUNT OF ACTivtTY l
W (_C_jh l 0l 9111@l                                            NA                        l  l Blhl Surveillance Test ST 5071. 04 ACTivlTV CO TENT                                                                                                      LOCATION OF RELEASE F4ELEASEO OF RELEASE                          AMOUNT OF ACTivtTY l
7 1 6 8 9 hl2    10 l NA 11
7 1 6 8 9 hl2    10 l NA 11 44 l        l 45 NA 80 PERSONNEL EXPOSVRES NUMBER                TYPE          OESCRIPTION I
                                                                                      .
44 l        l 45 NA 80 PERSONNEL EXPOSVRES NUMBER                TYPE          OESCRIPTION I
U_LJ l el e I ol@LZJ@l NA                                                                                                *                ~
U_LJ l el e I ol@LZJ@l NA                                                                                                *                ~
                                                                                                                                                                                      *
PERSONNE L iN;SES D**D                    D    9            M Nuv8ER                OESCniPTiONh                                                        **            *          ]' }(g  "          ''
  '      ' '                  ''
PERSONNE L iN;SES
                                                      ''
D**D                    D    9            M Nuv8ER                OESCniPTiONh                                                        **            *          ]' }(g  "          ''
l 7
l 7
i a 8 9 i oI eI el@l    11      12 NA 80 .
i a 8 9 i oI eI el@l    11      12 NA 80 .
LOSS OF OR DA'LtAGE TO FACILITY TYPE        OtSCRIPTION N^                                                                                                                                                    l I'HILz_J@l 8 9              10 60 7
LOSS OF OR DA'LtAGE TO FACILITY TYPE        OtSCRIPTION N^                                                                                                                                                    l I'HILz_J@l 8 9              10 60 7
                                                                                                                                                               "acuse o~'v 2 O
                                                                                                                                                               "acuse o~'v 2 O
                  '"""''''
               ,sSuE@OESCn.PTiO~@
               ,sSuE@OESCn.PTiO~@
l        na 8012a1033f                                                                    I    I i I I I I I I I I I I I :2 LxJ        10 68 69                                  80 5 7      8 9
l        na 8012a1033f                                                                    I    I i I I I I I I I I I I I :2 LxJ        10 68 69                                  80 5 7      8 9
                                                                                                                                                                 ~
                                                                                                                                                                 ~
* DVR 80-197                NAME OF PREPARMH.
DVR 80-197                NAME OF PREPARMH.
Dan haumm                                                PHONE:
Dan haumm                                                PHONE:
                                                                                                                                                                          '


1
1 I
          '
l TOLEDO EDISON COMPANY
I
       .                    DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-110                        j DATE OF EVENT: November 28, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATICM 01 OCCURRENCE: Auxiliary Feed Pump Turbine (AFPT) 1-2 Suction Line Pressure Switch PSL 107D Failed to Reset Conditions Prior to Occurrence: The unit was in Mode 1 with Power (MRI) = 2525 and Load (Gross MWE) = 853.
. .
l
                                                                                                '
TOLEDO EDISON COMPANY
       .                    DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-110                        j
                                                                          -
                                                                                              .
                                  .
DATE OF EVENT: November 28, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATICM 01 OCCURRENCE: Auxiliary Feed Pump Turbine (AFPT) 1-2 Suction Line Pressure Switch PSL 107D Failed to Reset Conditions Prior to Occurrence: The unit was in Mode 1 with Power (MRI) = 2525 and Load (Gross MWE) = 853.
Description of Occurrence: On November 28, 1980 at approximately 1500 hours during the performance of ST 5071.04, Auxiliary Feedwater Channel Functional Test, it was noted by operations personnel that PSL 107D would not reset after actuating on low steam pressure. PSL 107D is one of four pressure switches located between the AFPT trip throt-tle valve and the AFFT steam isolation valve on each main steam line. The purpose of these pressure suitches is to close the AFPT main steam isolation valves should a main steam line break occur between the AFP room and the islation valves in the auxiliary building. The control logic requires actuation of both PSL 107A and PSL 107C or PSL 107B and PSL 107D to cause steam isolation to the AFPT. With this pressure switch inoperable h mfifary Feedwater System 1-2 was declared inocerable.
Description of Occurrence: On November 28, 1980 at approximately 1500 hours during the performance of ST 5071.04, Auxiliary Feedwater Channel Functional Test, it was noted by operations personnel that PSL 107D would not reset after actuating on low steam pressure. PSL 107D is one of four pressure switches located between the AFPT trip throt-tle valve and the AFFT steam isolation valve on each main steam line. The purpose of these pressure suitches is to close the AFPT main steam isolation valves should a main steam line break occur between the AFP room and the islation valves in the auxiliary building. The control logic requires actuation of both PSL 107A and PSL 107C or PSL 107B and PSL 107D to cause steam isolation to the AFPT. With this pressure switch inoperable h mfifary Feedwater System 1-2 was declared inocerable.
This placed the unit in the action statement of Technical Spec'ification 3.7.1.2 which states that with one Auxiliary Feedwater System inoperable, restore the inoperable system to operable stetus within 72 hours or be in hot shutdown with.in the next 12 hours.
This placed the unit in the action statement of Technical Spec'ification 3.7.1.2 which states that with one Auxiliary Feedwater System inoperable, restore the inoperable system to operable stetus within 72 hours or be in hot shutdown with.in the next 12 hours.
_
Designation of Apparent Cause of Occurrence: The apparent cause of the occurrence was determined to be a defective actuation switch and actuator in PSL 107D. The actuating stem in the microswitch was worn.
Designation of Apparent Cause of Occurrence: The apparent cause of the occurrence was determined to be a defective actuation switch and actuator in PSL 107D. The actuating stem in the microswitch was worn.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. Auxiliary Feedwater Train 1-1 Vas still operable.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. Auxiliary Feedwater Train 1-1 Vas still operable.
                                                        .
Corrective Action: Maintenance Work Order IC-802-80 was issued to perform maintenance on PSL 107D. PSL 107D was removed, the defective parts replaced and the repaired switch installed. Multiple checks were made on the pressure switch calibration, both out' of sys-tem and in the system and results proved satisfactory. The applicable portion of ST 5071.04 was re-performed satisfactorily, and Auxiliary Feedwater Train 1-2 was declared operable at 2250 hours on November 28, 1980. Further investigation into the cause of the worn part will be undertaken.
Corrective Action: Maintenance Work Order IC-802-80 was issued to perform maintenance on PSL 107D. PSL 107D was removed, the defective parts replaced and the repaired switch installed. Multiple checks were made on the pressure switch calibration, both out' of sys-tem and in the system and results proved satisfactory. The applicable portion of ST 5071.04 was re-performed satisfactorily, and Auxiliary Feedwater Train 1-2 was declared operable at 2250 hours on November 28, 1980. Further investigation into the cause of the worn part will be undertaken.
Failure Data: There have been no previous similar occurrences of worn parts causing a pressure switch failure.
Failure Data: There have been no previous similar occurrences of worn parts causing a pressure switch failure.
LER #80-084
LER #80-084
                                 .}}
                                 .}}

Latest revision as of 09:35, 31 January 2020

LER 80-084/03L-0:on 801128,switch PSL107D Would Not Reset After Actuating on Low Steam Pressure & Auxiliary Feedwater Sys Declared Inoperable.Caused by Defective Actuation Switch & Actuator in PSL107D.Parts Replaced
ML19340D598
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/26/1980
From: Trautman D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19340D581 List:
References
LER-80-084-03L, LER-80-84-3L, NUDOCS 8012310337
Download: ML19340D598 (2)


Text

_

O.S. NUCLE AR REGULi TORY COMMISSION NRC FORM 363 87 77) -

LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l jh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI fit 110l HI DI sl SI 11@l el el ol el el LICEN5E NUMBER el el el el ol 26 ol@k 26 it LICENSE i ilililGI TYPE JG I

SF JAT be le 7 8 9 LtCENSEE CODE 14 1S CON'T

[OITl l'0"], lL ]@l0 l 5 l 0 l - l 0 l 3 l 4 l 66d@l1ta l1 l2 18 l8 10 @l 175l 2 lREPORT EVENT DATE F4 2 l 6D ATE l 8 l 9_j@ 80 i 8 60 61 DOCKET NUMBER EVENT OESCRIPTION AND PROSABLE CONSEQUENCES h lOl2l l (NP-33-E0-110) On 11/28/80 at approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> while performine surveillance 1 i

l0l3l l testing, operations personnel noted that PSL107D would not reset after actuating on ITT71 I low steam pressure. With this pressure switch inoperable. Auxiliary Feedwater SystemI lO t si I 1-2 was declared inoperable. This placed the unit in the action statement of Technt-1 ,

I cls l l cal Specification 3.7.1.2. There was no danger to the health and safety of the oublic!

[ o i 7 l l or to station personnel. Auxiliary Feedwater (AW) Train 1-1 was still operable. I I

Ioiel l 80 E COOE Stec E COYPONENT CODE SUB DE S E ICl9l lC lH lh Wh l F l@ l I l N l S l T l R l U lh (S_jh (_Z_j 18 ts 20 h

8 9 to 11 12 13 7

OCCURRENCE RE* ORT RE .'ISION SE QU E NTI AL REPORT NO. CODE T**E NO.

EVENT VEAR LE R RO

@ ay,La; 1810l 21 22 l-l 2J 1018 l 4 l 24 26

[ _j 27 le 13 l 28 29

[ tl Ju l-l 31 W

32 HOURS $8 IT FOR S. SLPP E MANUFACYbRER A E 4 G oN PLANT  ? 7 lAj@lZl@ lZ l@

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43 l44.S l 3 l 8 l 247 l@'

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lijollThe cause was a defective actuation switch and actuator in PSL107D. The actuating i g istem in the microswitch was worn. Under Maintenance Work OrderIC-802-80. the defec- l

,,,,,ltive parts were replaced. The applicable portion of ST 5071.04 was re-performed sa t f <:1-g l factorily, and Auxiliary Feedwater Train 1-2 was declared operable at 2205' hours on I

~

l pi p-] l 11/28/80. 80 7 8 9 OTHER STATUS DSO Y DISCOVERY DESCRIPTION

'ST s  % POWEFt l

W (_C_jh l 0l 9111@l NA l l Blhl Surveillance Test ST 5071. 04 ACTivlTV CO TENT LOCATION OF RELEASE F4ELEASEO OF RELEASE AMOUNT OF ACTivtTY l

7 1 6 8 9 hl2 10 l NA 11 44 l l 45 NA 80 PERSONNEL EXPOSVRES NUMBER TYPE OESCRIPTION I

U_LJ l el e I ol@LZJ@l NA * ~

PERSONNE L iN;SES D**D D 9 M Nuv8ER OESCniPTiONh ** * ]' }(g "

l 7

i a 8 9 i oI eI el@l 11 12 NA 80 .

LOSS OF OR DA'LtAGE TO FACILITY TYPE OtSCRIPTION N^ l I'HILz_J@l 8 9 10 60 7

"acuse o~'v 2 O

,sSuE@OESCn.PTiO~@

l na 8012a1033f I I i I I I I I I I I I I I :2 LxJ 10 68 69 80 5 7 8 9

~

DVR 80-197 NAME OF PREPARMH.

Dan haumm PHONE:

1 I

l TOLEDO EDISON COMPANY

. DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-110 j DATE OF EVENT: November 28, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATICM 01 OCCURRENCE: Auxiliary Feed Pump Turbine (AFPT) 1-2 Suction Line Pressure Switch PSL 107D Failed to Reset Conditions Prior to Occurrence: The unit was in Mode 1 with Power (MRI) = 2525 and Load (Gross MWE) = 853.

Description of Occurrence: On November 28, 1980 at approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> during the performance of ST 5071.04, Auxiliary Feedwater Channel Functional Test, it was noted by operations personnel that PSL 107D would not reset after actuating on low steam pressure. PSL 107D is one of four pressure switches located between the AFPT trip throt-tle valve and the AFFT steam isolation valve on each main steam line. The purpose of these pressure suitches is to close the AFPT main steam isolation valves should a main steam line break occur between the AFP room and the islation valves in the auxiliary building. The control logic requires actuation of both PSL 107A and PSL 107C or PSL 107B and PSL 107D to cause steam isolation to the AFPT. With this pressure switch inoperable h mfifary Feedwater System 1-2 was declared inocerable.

This placed the unit in the action statement of Technical Spec'ification 3.7.1.2 which states that with one Auxiliary Feedwater System inoperable, restore the inoperable system to operable stetus 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 with.in 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 determined to be a defective actuation switch and actuator in PSL 107D. The actuating stem in the microswitch was worn.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. Auxiliary Feedwater Train 1-1 Vas still operable.

Corrective Action: Maintenance Work Order IC-802-80 was issued to perform maintenance on PSL 107D. PSL 107D was removed, the defective parts replaced and the repaired switch installed. Multiple checks were made on the pressure switch calibration, both out' of sys-tem and in the system and results proved satisfactory. The applicable portion of ST 5071.04 was re-performed satisfactorily, and Auxiliary Feedwater Train 1-2 was declared operable at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> on November 28, 1980. Further investigation into the cause of the worn part will be undertaken.

Failure Data: There have been no previous similar occurrences of worn parts causing a pressure switch failure.

LER #80-084

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