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{{#Wiki_filter:19-831 . LICENSEE EVENT REPORT ILER) U.I. NUCLEAR REGULATORY CCltlW!talON  
{{#Wiki_filter:,*r.N~A~C~Fot-111~311~-----------i                                                                                                          U.I. NUCLEAR REGULATORY CCltlW!talON 19-831        .
*l'PAOVED DMI NO. 311!11-411Mi EXPIRES: 8/311115 F*CILITY NAME C1J Sa1em Generatinq Station -Unit 1 !DOCKET NUM8EA CZI I ,.,..,,. 131 o 15 Io Io Io I 21 712 1 loF 0*14 TITLE l'J T. S. Survei11ance Not Performed Historica11y Due To Inad. Admin. Contro1s EVENT DATI! IBJ LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIEI INVOLVED Ill MONTH QAY .YEAR YEAR F*CILITY N*MES DOCKET NUMBERISJ Sa1em -Unit 2 O I 5 I O I O I O I 3 11 11 OPERATING MODE Ill 1 THll REPORT 11 IUIMITTED PUAIUANT TO THE AEQUIAEMENTI OF 10 CFR §: (Ch..:lt an* 01 man of th* fol/awinf}
                                                                                                                                                    *l'PAOVED DMI NO. 311!11-411Mi EXPIRES: 8/311115 LICENSEE EVENT REPORT ILER)
1111 20.<<l21bl zo.-Ccl ---zo.-11111 JOI ll0.31!Call11  
F*CILITY NAME C1J                                                                                                                 DOCKET NUM8EA CZI                               I     ,.,..,,. 131 Sa1em Generatinq Station - Unit 1 TITLE l'J
---73.7111*1 73.711cl POWER I _. LEVEL -1101 11 O 10 zo.-1111111111 20.-11111111111 20.4GIC.111111*1 20.-11111 IM -x ll0.3111*1121  
                                                                                                                                  !o 15 Io Io Io I 21 712                           1 loF 0*14 T. S. Survei11ance Not Performed Historica11y Due To Inad. Admin. Contro1s EVENT DATI! IBJ                     LEA NUMBER Ill                     REPORT DATE 171                           OTHER FACILITIEI INVOLVED Ill MONTH     QAY     .YEAR       YEAR                                                                             F*CILITY N*MES                         DOCKET NUMBERISJ Sa1em - Unit 2                                         O I 5 I O I O I O I 3 11 11 THll REPORT 11 IUIMITTED PUAIUANT TO THE AEQUIAEMENTI OF 10 CFR         &sect;: (Ch..:lt an* 01 man of th* fol/awinf} 1111
-ll0.73111121111 ll0,73C.llZlllYJ ll0.73C.llZIM ll0.73C.ll21Cvlll ll0.73C1112llw11111AI ll0.73C.ll211wtllllll
                                                                                                                                                        --
!ICl.73C*ll211*1 OTHER ($p<<Jfv in .Ab-r i---/>>low *ntl In T1xr, NRC Form 366.AI --I0.73C111211PI --I0.73C.llZllllll LICENSEE CONTACT FOR THll LEA 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Po1lack .LER Coordinator 6 I 0 1 9 3 1 3 1 9 I -1 4 I 0 I 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAIHD IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC. TUR ER CAUSE SYSTEM COMPONENT MANUFAC. TUR EA I I I *I I I I I I I I I I I I I I I I I I I I I . I I I I EXPECTED IUl'PLEMENTAL REPORT EXPECTED 11'1 MONTH DAY YiiAR SUBMISSION  
OPERATING MODE Ill          1        20.<<l21bl                                                                 ll0,73C.llZlllYJ                                73.7111*1 I _.                                                -    zo.-Ccl
--, YES (If vn. complete.
                                                                                                      -
EXl'ECTEO SUBMISSION OA TEI DATE 1151 I I On January 20, 1989, during the course of the Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as required.
POWER LEVEL                    -
The surveillance requires functional testing of the Reactor Coolant Pump (RCP) (AB} breaker position trip every refueling (every 18 months). This requirement is identical in both, Salem Unit 1 and Salem Unit 2. The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated.
zo.-11111 JOI
A procedure, "Reactor Coolant Pump Status Indication Test" has been issued for both Salem Units. The MMIS (Managed Maintenance Information System), a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame. PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance.
                                                                  -    ll0.31!Call11
The Technical  
                                                                                                      -       ll0.73C.llZIM                                  73.711cl 1101       11 O 10           zo.-1111111111
*Specification Surveillance audit project is 9ontinuing its review. ' l I . . --I LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE 8_9_-Q_Q_4_::-_Q_0
                                                                  -x   ll0.3111*1121
____ __ 9!_1 ____ _ PLAfIJ__l.ND SYSTEM _IDENTJ:FICATION:_;_
                                                                                                      -       ll0.73C.ll21Cvlll                               OTHER ($p<<Jfv in .Ab-r
Westinghouse  
                                                                                                      --
-Pressurized Water Reactor .Energy Industry Identification System {EIIS) codes are identified in the text as [xxl IDENTIFICATION OF OCCURRENCE:
i---   />>low *ntl In T1xr, NRC Form ll0.73111121111                        ll0.73C1112llw11111AI                          366.AI
Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip'' not performed historically Discovery Date: 1/20/89 Report Date: 2/16/89 This report was initiated by Incident Report Nos. 89-038 and 89-039. CONDITIONS PRIOR TO Unit 1: Unit 2: Mode 1 Mode 1 Reactor Power 100% Reactor Power 100% On January 20, 1989, during the course of the Technical Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as The surveillance requires functional testing of the Reactor Coolant Pump (RCP) f AB} breaker position trip every refueling
                                                                  -
{every 18 months). This requirement is identical in both, Salem Unit 1 and Salem Unit 2. APP_h-_BENT CAUS_E OF OCCURR:l;:_I:li_:E:
20.-11111111111 20.4GIC.111111*1
                                                                  -    I0.73C111211PI                         ll0.73C.ll211wtllllll 20.-11111 IM                        I0.73C.llZllllll                       !ICl.73C*ll211*1 LICENSEE CONTACT FOR THll LEA 1121 NAME                                                                                                                                                   TELEPHONE NUMBER AREA CODE M. J. Po1lack .LER Coordinator                                                                                                       6 I 0 19            3 13 19 I - 14 I 0 I 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAIHD IN THll REPORT 1131 CAUSE SYSTEM         COMPONENT           MANUFAC.                                                                                  MANUFAC.
TUR ER                                       CAUSE SYSTEM         COMPONENT             TUR EA I         I   I *I           I   I   I                                             I             I   I     I       I   I     I I         I I       I         I   I   I                                             I             I   I .I           I   I     I IUl'PLEMENTAL REPORT EXPECTED 11'1                                                                               MONTH           DAY         YiiAR EXPECTED SUBMISSION DATE 1151
- - , YES (If vn. complete. EXl'ECTEO SUBMISSION OA TEI I         I            I On January 20, 1989, during the course of the Techni~al Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as required.                                                                                               The surveillance requires functional testing of the Reactor Coolant Pump (RCP) (AB} breaker position trip every refueling (every 18 months).
This requirement is identical in both, Salem Unit 1 and Salem Unit 2.
The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated. A procedure, "Reactor Coolant Pump Status Indication Test" has been issued for both Salem Units. The MMIS (Managed Maintenance Information System), a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame.                                                   PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance. The Technical *Specification Surveillance audit project is 9ontinuing its review.
                                                                                                          ' l     I
                                                                                                                                                      *-=~-  .       *-~~ .   =~* --
 
LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station                             DOCKET NUMBER             LER NUMBER               PAGE U~n_i_t~1~~~~~~~~~~~~~~~5_0Q02~7_2~--~-                                        8_9_-Q_Q_4_::-_Q_0_ _ _ _~__9!_1____ _
PLAfIJ__l.ND SYSTEM _IDENTJ:FICATION:_;_
Westinghouse                 - Pressurized Water Reactor
                                .Energy Industry Identification System {EIIS) codes are identified in the text as [xxl IDENTIFICATION OF OCCURRENCE:
Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip'' not performed historically Discovery Date:                 1/20/89 Report Date:                 2/16/89 This report was initiated by Incident Report Nos. 89-038 and 89-039.
CONDITIONS PRIOR TO                       OCCV~RE~C~~
Unit 1:                 Mode 1   Reactor Power 100%
Unit 2:                Mode 1  Reactor Power 100%
On January 20, 1989, during the course of the Technical Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as ~equired. The surveillance requires functional testing of the Reactor Coolant Pump (RCP) f AB} breaker position trip every refueling {every 18 months).
This requirement is identical in both, Salem Unit 1 and Salem Unit 2.
APP_h-_BENT CAUS_E OF OCCURR:l;:_I:li_:E:
The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated.
The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated.
ANALYSIS OF OCCURRENCE:
ANALYSIS OF OCCURRENCE:
1* -***.** .. *.*.-***:**
The Reactor Coolant Pump {RCP) breaker position trip is functionally tested by using the control room overhead and status panel indications. The surveillance is done to ensure continued reliable operation.
.* *: The Reactor Coolant Pump {RCP) breaker position trip is functionally tested by using the control room overhead and status panel indications.
Upon identification of the potential of not having completed the surveillance, a review was initiated to determine if the surveillance requirement was met within the last 18 months for both Salem Units.
The surveillance is done to ensure continued reliable operation.
The initial Unit 1 review did not identify if the surveillance was met. Therefore, at 1135 hours on January 20, 1989 Technical Specification Action Statement 3.0.3 was entered since Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 did not apply .
Upon identification of the potential of not having completed the surveillance, a review was initiated to determine if the surveillance requirement was met within the last 18 months for both Salem Units. The initial Unit 1 review did not identify if the surveillance was met. Therefore, at 1135 hours on January 20, 1989 Technical Specification Action Statement 3.0.3 was entered since Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 did not apply . .... ,_ ..... ,. .... ". :*-... _ ... -*' ...
-***.** .. *.*.-***:**.* *: .... ,_ ..... ,. .... ". :*-                           ..._ ... - *' ...
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER LER NUMBER PAGE 5 o o o 212 ______ 8_9_-_o o 4_:-_9_0 ______ :J_g_:t_3
 
__ Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 states: "With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours or reduce THERMAL POWER to below P-8 within the next 2 hours. Operation below P-8 may continue pursuant to ACTION 11." Technical Specification Action Statement  
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER           LER NUMBER                   PAGE Unit 1                          5 oo o212_ _ _ _ _ _8_9_-_o o4_:-_9_0______:J_g_:t_3_ _
Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 states:
          "With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours or reduce THERMAL POWER to below P-8 within the next 2 hours. Operation below P-8 may continue pursuant to ACTION 11."
Technical Specification Action Statement 3.0.3 states:
          "When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
: 1. At least HOT STANDBY within the next 6 hours,
: 2. At least HOT SHUTDOWN within the following 6 hours, and
: 3. At least COLD SHUTDOWN within the subsequent 24 hours.
Where corrective measures are completed that permit operation unde~ the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measur~d from the time of failure to meet the Limiting Condition of Operation.
Exceptions to these-requirements are stated in the individual specifications."
Completion of the Unit 1 shutdown was not required.                      Subsequent review revealed the surveillance was satisfied by conduction of Maintenance Department procedure lIC-2.6.024, "lPT-505 First Stage Turbine Impulse Pressure - Channel I". This procedure requires that the reactor protection status panel lights for all reactor trips are off .. If they are not off, a comment is made in the procedure. This procedure. was last completed on January 12, 1988. The "RCP Breaker Open" lights were identified as being on. When the unit was returned to power, subsequent use of this procedure (done monthly) indicated the lights were off thereby indicating proper response of the open/close positioning of the RCP breakers. Technical Specification Action Statement 3.0.3 was exited at 1455 hours the same day.
The Salem Unit 2 review revealed that the surveillance was satisfied as indicated in Operator Log entries and Sequence of Event computer printouts which show the Solid State Protection System (SSPS) [JGl received the appropriate change of state inputs for the RCP breaker.
Although, it has been shown that the surveillance has been completed within the last eighteen months, it has not been determined if the surveillance requirement has been met historically for either Salem unit. Therefore, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B).
CORRECTIVE ACTION:
A procedure, "Reactor Coolant Pump Status Indication Test", addressing the functional surveillance requirement, has been issued for both
                                                    .. ---~- -*.., -*' *....


====3.0.3 states====
  -----*----------1-----
"When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: 1. At least HOT STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as from the time of failure to meet the Limiting Condition of Operation.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
Exceptions to these-requirements are stated in the individual specifications." Completion of the Unit 1 shutdown was not required.
'                                                                    ------- - - - - * --------------**-*--------*
Subsequent review revealed the surveillance was satisfied by conduction of Maintenance Department procedure lIC-2.6.024, "lPT-505 First Stage Turbine Impulse Pressure -Channel I". This procedure requires that the reactor protection status panel lights for all reactor trips are off .. If they are not off, a comment is made in the procedure.
Salem Generating Station                               DOCKET NUMBER       LER NUMBER                         PAGE u__n_i_t__1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _5_Q_Q_02_7__2_ _ _ _ _ _              89-0_Q_4-=-Q_0_____ 4_2__L_4_____
This procedure.
CORRECTIVE ACTION:                             (cont'd)
was last completed on January 12, 1988. The "RCP Breaker Open" lights were identified as being on. When the unit was returned to power, subsequent use of this procedure (done monthly) indicated the lights were off thereby indicating proper response of the open/close positioning of the RCP breakers.
Salem Units.
Technical Specification Action Statement 3.0.3 was exited at 1455 hours the same day. The Salem Unit 2 review revealed that the surveillance was satisfied as indicated in Operator Log entries and Sequence of Event computer printouts which show the Solid State Protection System (SSPS) [JGl received the appropriate change of state inputs for the RCP breaker. Although, it has been shown that the surveillance has been completed within the last eighteen months, it has not been determined if the surveillance requirement has been met historically for either Salem unit. Therefore, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). CORRECTIVE ACTION: A procedure, "Reactor Coolant Pump Status Indication Test", addressing the functional surveillance requirement, has been issued for both ..
The MMIS (Managed Maintenance Information System) , a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame.
-* .. , -*' * .... 
PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance.
' -----*----------1-----
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION  
-----------* --------------**-*--------*
Salem Generating Station DOCKET NUMBER LER NUMBER PAGE u __ n_i_t __ 1 _______________
5_Q_Q_02_7__2
______ 89-0_Q_4-=-Q_0
_____ 4_2__L_4 ____ _ CORRECTIVE ACTION: (cont'd) Salem Units. The MMIS (Managed Maintenance Information System) , a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame. PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance.
The Technical Specification Surveillance audit project is continuing its review to ensure full compliance with the requirements of the Unit 1 and Unit 2 Technical Specification Surveillances.
The Technical Specification Surveillance audit project is continuing its review to ensure full compliance with the requirements of the Unit 1 and Unit 2 Technical Specification Surveillances.
MJP:pc SORC Mtg. 89-011 : ' ' -. *. .  
_LVJM~~
.. * .. '
General Manager -
General Manager -Salem Operations . -. .. ** .. *. :-**:* -*
Salem Operations MJP:pc SORC Mtg. 89-011
Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555  
                                                                                                .. ** .. *. :- **:*
:' ' - . *. . *.:-~*.. '.~ * .. '                  . - . ---                  -*
 
Public Service Electric and Gas Company                                     P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 16, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC                                   20555


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-004-00 February 16, 1989 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of discovery.
 
MJP:pc Distribution The Energy People .. *: * .. .. --. -
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-004-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of discovery.
*,*. . . *.*-::-**:  
Sincerely yours, u<mJL/ff; L. K. Miller General Manager-s al em Operations MJP:pc Distribution The Energy People 95-2189 (11 Mi 12-84
-**-
.. *: *.. . --. -
* .. -'.-. *--** ***** Sincerely yours, u<mJL/ff; L. K. Miller General s al em Operations 95-2189 (11 Mi 12-84 --}}
          ~      '*:.:**::~*:*-~;. ~-*<-:*~:! ~.;""::~ *,*. . . *.*-::-**: - **- ~--~- *..-'.-. *--** ***** ~
                                                                                    --          ~~~__:_~--"-~~~~~___;_~~~~~......;.......;_~~~~....;..~~~~~~~-}}

Revision as of 12:21, 21 October 2019

LER 89-004-00:on 890120,Tech Spec Surveillance Table 4.3-1, Number 20, Reactor Coolant Pump Breaker Position Trip Not Performed as Required.Caused by Inadequate Administrative Controls.Procedure Reactor Coolant... issued.W/890216 Ltr
ML18093B465
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/16/1989
From: Miller L, Pollack M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-004, LER-89-4, NUDOCS 8903020619
Download: ML18093B465 (5)
v • d • e


Text

,*r.N~A~C~Fot-111~311~-----------i U.I. NUCLEAR REGULATORY CCltlW!talON 19-831 .

  • l'PAOVED DMI NO. 311!11-411Mi EXPIRES: 8/311115 LICENSEE EVENT REPORT ILER)

F*CILITY NAME C1J DOCKET NUM8EA CZI I ,.,..,,. 131 Sa1em Generatinq Station - Unit 1 TITLE l'J

!o 15 Io Io Io I 21 712 1 loF 0*14 T. S. Survei11ance Not Performed Historica11y Due To Inad. Admin. Contro1s EVENT DATI! IBJ LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIEI INVOLVED Ill MONTH QAY .YEAR YEAR F*CILITY N*MES DOCKET NUMBERISJ Sa1em - Unit 2 O I 5 I O I O I O I 3 11 11 THll REPORT 11 IUIMITTED PUAIUANT TO THE AEQUIAEMENTI OF 10 CFR §: (Ch..:lt an* 01 man of th* fol/awinf} 1111

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OPERATING MODE Ill 1 20.<<l21bl ll0,73C.llZlllYJ 73.7111*1 I _. - zo.-Ccl

-

POWER LEVEL -

zo.-11111 JOI

- ll0.31!Call11

- ll0.73C.llZIM 73.711cl 1101 11 O 10 zo.-1111111111

-x ll0.3111*1121

- ll0.73C.ll21Cvlll OTHER ($p<<Jfv in .Ab-r

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- I0.73C111211PI ll0.73C.ll211wtllllll 20.-11111 IM I0.73C.llZllllll !ICl.73C*ll211*1 LICENSEE CONTACT FOR THll LEA 1121 NAME TELEPHONE NUMBER AREA CODE M. J. Po1lack .LER Coordinator 6 I 0 19 3 13 19 I - 14 I 0 I 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAIHD IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC. MANUFAC.

TUR ER CAUSE SYSTEM COMPONENT TUR EA I I I *I I I I I I I I I I I I I I I I I I I I I .I I I I IUl'PLEMENTAL REPORT EXPECTED 11'1 MONTH DAY YiiAR EXPECTED SUBMISSION DATE 1151

- - , YES (If vn. complete. EXl'ECTEO SUBMISSION OA TEI I I I On January 20, 1989, during the course of the Techni~al Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as required. The surveillance requires functional testing of the Reactor Coolant Pump (RCP) (AB} breaker position trip every refueling (every 18 months).

This requirement is identical in both, Salem Unit 1 and Salem Unit 2.

The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated. A procedure, "Reactor Coolant Pump Status Indication Test" has been issued for both Salem Units. The MMIS (Managed Maintenance Information System), a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame. PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance. The Technical *Specification Surveillance audit project is 9ontinuing its review.

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LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE U~n_i_t~1~~~~~~~~~~~~~~~5_0Q02~7_2~--~- 8_9_-Q_Q_4_::-_Q_0_ _ _ _~__9!_1____ _

PLAfIJ__l.ND SYSTEM _IDENTJ:FICATION:_;_

Westinghouse - Pressurized Water Reactor

.Energy Industry Identification System {EIIS) codes are identified in the text as [xxl IDENTIFICATION OF OCCURRENCE:

Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip not performed historically Discovery Date: 1/20/89 Report Date: 2/16/89 This report was initiated by Incident Report Nos.89-038 and 89-039.

CONDITIONS PRIOR TO OCCV~RE~C~~

Unit 1: Mode 1 Reactor Power 100%

Unit 2: Mode 1 Reactor Power 100%

On January 20, 1989, during the course of the Technical Specification Surveillance audit project, it was discovered that Technical Specification Surveillance Table 4.3-1 No. 20, "Reactor Coolant Pump Breaker Position Trip" has not been performed as ~equired. The surveillance requires functional testing of the Reactor Coolant Pump (RCP) f AB} breaker position trip every refueling {every 18 months).

This requirement is identical in both, Salem Unit 1 and Salem Unit 2.

APP_h-_BENT CAUS_E OF OCCURR:l;:_I:li_:E:

The apparent cause of this event has been attributed to inadequate administrative controls of the Technical Specification surveillance testing program when the program was first initiated.

ANALYSIS OF OCCURRENCE:

The Reactor Coolant Pump {RCP) breaker position trip is functionally tested by using the control room overhead and status panel indications. The surveillance is done to ensure continued reliable operation.

Upon identification of the potential of not having completed the surveillance, a review was initiated to determine if the surveillance requirement was met within the last 18 months for both Salem Units.

The initial Unit 1 review did not identify if the surveillance was met. Therefore, at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> on January 20, 1989 Technical Specification Action Statement 3.0.3 was entered since Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 did not apply .

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5 oo o212_ _ _ _ _ _8_9_-_o o4_:-_9_0______:J_g_:t_3_ _

Technical Specification 3.3.1.1 Table 3.3-1 Action Statement 10 states:

"With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Operation below P-8 may continue pursuant to ACTION 11."

Technical Specification Action Statement 3.0.3 states:

"When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation unde~ the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measur~d from the time of failure to meet the Limiting Condition of Operation.

Exceptions to these-requirements are stated in the individual specifications."

Completion of the Unit 1 shutdown was not required. Subsequent review revealed the surveillance was satisfied by conduction of Maintenance Department procedure lIC-2.6.024, "lPT-505 First Stage Turbine Impulse Pressure - Channel I". This procedure requires that the reactor protection status panel lights for all reactor trips are off .. If they are not off, a comment is made in the procedure. This procedure. was last completed on January 12, 1988. The "RCP Breaker Open" lights were identified as being on. When the unit was returned to power, subsequent use of this procedure (done monthly) indicated the lights were off thereby indicating proper response of the open/close positioning of the RCP breakers. Technical Specification Action Statement 3.0.3 was exited at 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br /> the same day.

The Salem Unit 2 review revealed that the surveillance was satisfied as indicated in Operator Log entries and Sequence of Event computer printouts which show the Solid State Protection System (SSPS) [JGl received the appropriate change of state inputs for the RCP breaker.

Although, it has been shown that the surveillance has been completed within the last eighteen months, it has not been determined if the surveillance requirement has been met historically for either Salem unit. Therefore, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B).

CORRECTIVE ACTION:

A procedure, "Reactor Coolant Pump Status Indication Test", addressing the functional surveillance requirement, has been issued for both

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

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Salem Generating Station DOCKET NUMBER LER NUMBER PAGE u__n_i_t__1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _5_Q_Q_02_7__2_ _ _ _ _ _ 89-0_Q_4-=-Q_0_____ 4_2__L_4_____

CORRECTIVE ACTION: (cont'd)

Salem Units.

The MMIS (Managed Maintenance Information System) , a computerized work tracking system, has been updated to include a recurring task which will ensure the completion of the surveillance within the required time frame.

PSE&G System Engineering will complete an Engineering Evaluation addressing the missed surveillance.

The Technical Specification Surveillance audit project is continuing its review to ensure full compliance with the requirements of the Unit 1 and Unit 2 Technical Specification Surveillances.

_LVJM~~

General Manager -

Salem Operations MJP:pc SORC Mtg.89-011

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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station February 16, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-004-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of discovery.

Sincerely yours, u<mJL/ff; L. K. Miller General Manager-s al em Operations MJP:pc Distribution The Energy People 95-2189 (11 Mi 12-84

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