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{{#Wiki_filter:Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555  
{{#Wiki_filter:o*ps~G-e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 21, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC               20555


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-31*1 *UNIT NO. 2 LICENSEE EVENT REPORT 91-021-00 January 21, 1992 This Licensee Event requirements of the 50. 73 (a} (2) (i} (B}. thirty (30) days of Report is being submitted pursuant to the Code of Federal Regulations lOCFR MJP:pc Distribution This report is required to be issued within event discovery.
 
Sincerely yours, C. A. Vondra General Manager -Salem Operations q1. . The Enerov Peonle *---*9201200109 920121 '"' '!"
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-31*1
* PDR ADOCK 05000311 C'! s PDR 95-2189 (10M) 12-89
          *UNIT NO. 2 LICENSEE EVENT REPORT 91-021-00 This Licensee Event               Report is being submitted pursuant to the requirements of the               Code of Federal Regulations lOCFR
-. NRCFORM366 U.S. NUCLEAR RE.GULATORY COMMISSION  
: 50. 73 (a} (2) (i} (B}.         This report is required to be issued within thirty (30) days of              event discovery.
.,*. , .. ,* APPROVED OMB NO. 3150-0104 , --*-:'. (6-89) -.  
Sincerely yours, C. A. Vondra General Manager -
!LERI REGARDING BURDEN ESTIMATE TO THE RECORDS .AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR .REGULATORY CoMMISSION, WASHINGTON,-DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT. (3150-0104), OFFICE _OF BUDGEJ, DC 20503. -FACILITY NAME m Salem Generating.Station Unit 2 TITLE (4) , * .. Tech.
Salem Operations MJP:pc Distribution q1.
Surveillance Overdue Due To Personnel Error *-.:.-EVENT DATE(&)
~ The Enerov               .
* L,ER NUMBER (6) REPORT DAT.E (7) * . -_!)THER FACILITIES INVOLVED.Ill)  
Peonle
*. MONTH DAY .
            *---*9201200109 920121
DAY YEAR. . ' .....
  '"' '!"
* fojAMES --.* * :;-:
* PDR   ADOCK 05000311                                                           95-2189 (10M) 12-89 C'!            s                      PDR
* DOCKET NUMB_ER(Sl  
 
*. J s*j o I o I o I I I i I 2 i I 9 9 i 9
NRCFORM366                                                                 U.S. NUCLEAR RE.GULATORY COMMISSION (6-89)        -                                                                                                                    .,*. ,       ..,* APPROVED OMB NO. 3150-0104 , -- *-:'.
* 11 * -o I 2 11 o I o o I i 2 I o 9 I 2 o I 5 I 0 Io I 0.1 1 1 OPERATING MODE (Ill *D THIS REPORT IS SUBMITTED PURSUANT TO THE RloQUIREMENTS OF -10 CFR §: (Check on* or more 'of th* following}
UC~NSEE'Evlr REPO~T !LERI                                                                 .*~&:~o~u~~~~~;;~;:i~gf~;l0~i.~~~Ls~:;;f:wl~;g
1111 . . 20.405(cl 60.73(*112llivl
                                                                                                                                      ~~TS          REGARDING BURDEN ESTIMATE TO THE RECORDS
* eo.13<*i<211&#xa5;1  
                                                                                                                                    .AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR
* *.: , *. &0.731*112llviil
- . FACILITY NAME      m
&0.73l*ll2llv11111AI 73.71(b) 73.71(cl >----60.38(cll11
                                                                                                                                    .REGULATORY CoMMISSION, WASHINGTON,-DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT. (3150-0104), OFFICE
,_.__ -60.38(cll2l  
_OF MA~AGEMENT ~ND BUDGEJ, WASHIN~TO~, DC 20503.                           -
--x 60.73(*ll211il  
Salem Generating.Station                               Unit 2 TITLE (4)   ,                                                                                                             * ..
--60.73(*112l(iil  
Tech. Spec~ Surveillance Overdue Due To Personnel Error                                                                                 *-.:.-
--60.73(*ll2llilll LICENSEE CONTACT FOR THIS LER (121 NAME . &0.?3l*ll2llvlllllBI
EVENT DATE(&)
&0.731*ll2llxl
* L,ER NUMBER (6)                       REPORT DAT.E (7) *                           . - _!)THER FACILITIES INVOLVED.Ill) *.
*_ * * -. >----OTHER (Specify in Ab1t111ct IHlow *nd In Tut, NRC Form 366AJ TELEPHONE NUMBER . AREA CODE M. J. Pollack " LER Coordinator
MONTH       DAY     . Y~AR                                                            DAY   YEAR.
: f. In I a h I a(_ I ? In I? I? COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM _COMPONENT-I I I I I I I I MANUFAC* TUR ER I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 J YES (If yo1, compl*t* EXPECTED SUBMISSION DA TEI AllSTRACT (Limit to 1400 i.* .. *pproKim*r.ly fiftNn lines} (16) SYSTEM I I COMPONENT
                                                                                                          . ' .....
-I -I I I r ., MANUFAC-_ TUR ER I *1 *.I
* FACll,I!~ fojAMES --.*             * :;-:
* I -I I . -EXPECTED SUBMISSION DATE.1151 MONTH DAY YEAR I I I On 12/19/91, it was discovered that the Waste Gas Analyzer channel functional, Technical Specification had not been performed.-
* DOCKET NUMB_ER(Sl
This monthly surveillance was overdue as of 12/16/91.
                                                                                                                                                                        *. *~ J s*j o I o I o I       I     I i   I2 i I 9           9 i   9*11* - oI2 11               ~    o I o oI i           2 Io 9 I     2                                                                   o I 5 I 0 Io I 0.1       1 1 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RloQUIREMENTS OF -10 CFR               &sect;: (Check   on* or more 'of th* following} 1111         . .
The last time the test was successfully completed was on 11/9/91. The surveillance was originally scheduled for 12/9/91; however, the start date was shifted (by computer logic) to 12/19/91.
MODE (Ill        *D                                        >---
The PREMIS computer program for outage scheduling is structured tu control the start date for all work done during the outage, including Surveillances.
                                                                        ,_.__
When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements.
20.405(cl 60.38(cll11                        --      60.73(*112llivl
The root cause of this event is personnel error. Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report". The surveillance was successfully completed on 12/19/91.
* eo.13<*i<211&#xa5;1 **.:   , *.
Appropriate disciplinary action has been taken with those individuals involved in this event. This event has been reviewed with applicable Outage Planning Department personnel.
                                                                                                                                                                      - . >---
A Technical Specification Surveillance review will be conducted to identify those Surveillances required when the core is defueled.
73.71(b) 73.71(cl
A review of the applicable administrative procedures will be completed to ensure* scheduling responsibilities for surveillances, during outage vs. non outage time periods, are adequate.
                                                                        --x 60.38(cll2l 60.73(*ll211il 60.73(*112l(iil
NRC Form 366 (6-89)
                                                                                                                    -
..
                                                                                                                    -
* LICENsEAvENT REPORT CLER> TEXT *coaNUATI_oN  
                                                                                                                            &0.731*112llviil
-
                                                                                                                            &0.73l*ll2llv11111AI
*. __________
                                                                                                                          . &0.?3l*ll2llvlllllBI
:..__ ___ _ DOCKET NUMBER LER NUMBER PAGE Salem Generating Station Unit 2 ____ so_Q_Q.31!
                                                                                                                                                                          -     OTHER (Specify in Ab1t111ct IHlow *nd In Tut, NRC Form 366AJ
__  
                                                                          -    60.73(*ll2llilll
-. . .2 __
                                                                                                                    -      &0.731*ll2llxl *_ *
* LICENSEE CONTACT FOR THIS LER (121 NAME                                                                                                                                                                    TELEPHONE NUMBER
                                                                                                                                                    . AREA CODE M.     J. Pollack
                                          "
LER Coordinator                                                                                                   f. In I a ~ h I a(_ I               ? In I? I?
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC*                                                                                                MANUFAC- _
CAUSE   SYSTEM       _COMPONENT-                                                                     SYSTEM          COMPONENT                    TUR ER TUR ER I        I  I  I        I   I   I                                                         I         -I - I           I         I *1 *.I I        I I I            I   I   I                                                         I           I     r .,          *I -I            I SUPPLEMENTAL REPORT EXPECTED (141                                                                                                 MONTH      DAY      YEAR
                                                                                                                                                            . -EXPECTED SUBMISSION DATE.1151 J       YES (If yo1, compl*t* EXPECTED SUBMISSION DA TEI                                                                                                                               I      I          I AllSTRACT (Limit to 1400 1~cos, i.*.. *pproKim*r.ly fiftNn linglo-s~c* ty~writtan lines} (16)
On 12/19/91, it was discovered that the Waste Gas Analyzer channel functional, Technical Specification Stirveillancia~ had not been performed.- This monthly surveillance was overdue as of 12/16/91. The last time the test was successfully completed was on 11/9/91. The surveillance was originally scheduled for 12/9/91; however, the start date was shifted (by computer logic) to 12/19/91. The PREMIS computer program for outage scheduling is structured tu control the start date for all work done during the outage, including Surveillances. When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements. The root cause of this event is personnel error. Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report". The surveillance was successfully completed on 12/19/91. Appropriate disciplinary action has been taken with those individuals involved in this event. This event has been reviewed with applicable Outage Planning Department personnel. A Technical Specification Surveillance review will be conducted to identify those Surveillances required when the core is defueled. A review of the applicable administrative procedures will be completed to ensure* scheduling responsibilities for surveillances, during outage vs. non outage time periods, are adequate.
NRC Form 366 (6-89)
 
.                 LICENsEAvENT REPORT CLER> TEXT *coaNUATI_oN -
      -----------------~--------------
Salem Generating Station            DOCKET NUMBER
                                                                      *.
LER NUMBER
__________ :..__ ___
PAGE
_
* Unit 2                         _ _ _ _so_Q_Q.31! __----~1-:-_Q_21:-o_o - .     . .2 __0L_~--------
PLANT AND SYSTEM IDEN_'.l'I_FI_CATIQ_N:
PLANT AND SYSTEM IDEN_'.l'I_FI_CATIQ_N:
Westinghouse Water Reactor Energy Industry System-(EIIS) c6des are identified in the text as {xxJ IDENTIFICATION OF  
Westinghouse       Pr~ssurized    Water Reactor Energy Industry I~eritifidation System-(EIIS) c6des are identified in the text as {xxJ IDENTIFICATION OF   occg~~~NCE:      -
-. . Technical overdue due to personnel Event Date: 12/19/91 Report Date: 1/20/92
            .         .
* This report was initiated by .Incident Report No.
Technical ~pecification Su~v~illance overdue due to personnel ~rror Event Date:   12/19/91 Report Date:   1/20/92
* This report was initiated by .Incident Report No.           91-921~
CONDITIONS PRIOR TO OCCURRENCE:
CONDITIONS PRIOR TO OCCURRENCE:
Defueled:
Defueled:   Gth Refueling Outage in Progress On December 19, 1991, it was discovered that the Waste Gas Analyzer
Gth Refueling Outage in Progress On December 19, 1991, it was discovered that the Waste Gas Analyzer {WEI channel functional, Technical Specification 3/4.3.3.9 Table 4.3-13 Surveillance, had not been performed.
{WEI channel functional, Technical Specification 3/4.3.3.9 Table 4.3-13 Surveillance, had not been performed.             This monthly surveillance was overdue as of December 16, 1991. The last time the test was successfully completed was on November 9, 1991.
This monthly surveillance was overdue as of December 16, 1991. The last time the test was successfully completed was on November 9, 1991. The surveillance was originally scheduled for December 9, 1991; however, the start date was shifted (by computer logic) to December 19, 1991. The PREMIS computer program for outage scheduling is structured to control the start date for all work done during the outage, including Surveillances.
The surveillance was originally scheduled for December 9, 1991; however, the start date was shifted (by computer logic) to December 19, 1991. The PREMIS computer program for outage scheduling is structured to control the start date for all work done during the outage, including Surveillances. When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements.
When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements.
During non outage periods, the start date for all work (including Surveillances) is controlled by a different computer program (i.e.,
During non outage periods, the start date for all work (including Surveillances) is controlled by a different computer program (i.e., MMIS). The MMIS, for the subject surveillance, correctly identified the start, due and overdue dates. APPARENT CAUSE OF The root cause of this event is personnel error. Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report". Outage Planning Department personnel did not observe that the Surveillance would go overdue due to inattention to detail.
MMIS). The MMIS, for the subject surveillance, correctly identified the start, due and overdue dates.
".  
APPARENT CAUSE OF   oc~~R~~~~~=
---------------*  
The root cause of this event is personnel error.
.. _ '* -. ., . *  
Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report".         Outage Planning Department personnel did not observe that the Surveillance would go overdue due to inattention to detail.
&NT (LER)
 
* TEXT cow9a.ATibN Sa1em Generating Unit 2 * * .... *. D.OCKET NUMBER LER NUMBER PAGE 5000311 91..;..021-'-00 . . 3 of 4 * ----* **------
  --'-'-'-'----------'--~,_.:....-'--'------        - - - ------------*
*:-*--*:-*.-*-
          ..
--*--*-----*-**---** . .: -. . APPARENT CAUSE OF . . .The Technical: .Specification Administrator acts as a backup to .Qutage Planning Department' personnel to. help ensure .*s*urveillances*
LICE~sE~          ,R~PokT
are not missed.* He observed.that.
              '* - ..,
the Surveillance would go overdue, but since the Unit*2.was defueled.he concluded that the equipment was not reqqfred to be operable .. In.addition his database showed the surveillance as being applicable in Modes .1 through 6. At the time of the event the plant wa*s* in an undefined Mode of operation Ci. e., the reactor vessel was defueled).
".          _            .
Technical Specification Table 3. 3-13 specifies that the "Oxygen Monitor" is applicable  
                              *           &NT                 (LER)
''during waste gas holdup The Waste Gas System was in service during the time period in question.
* TEXT cow9a.ATibN Sa1em Generating                 ~tation        D.OCKET NUMBER                LER NUMBER                      PAGE Unit 2 * *               .... *.                   5000311                     91..;..021-'-00         .   . 3 of 4 *
                                    ----*           **---- -- *.-~--------~--------**--** *:-*--*:-*.-*- --*--*-----*-**---**
    .                 .:   - . .
APPARENT CAUSE OF                 OC~UR~EN~E_:_~*<_c_o_nt'gl
                  .                         .
        .The Technical: .Specification Administrator acts as a backup to .Qutage Planning Department' personnel to. help ensure .*s*urveillances* are not missed.* He observed.that. the Surveillance would go overdue, but since the Unit*2.was defueled.he concluded that the equipment was not reqqfred to be operable .. In.addition his database showed the surveillance as being applicable in Modes .1 through 6. At the time of the event the plant wa*s* in an undefined Mode of operation Ci. e.,
the reactor vessel was defueled). Technical Specification Table
: 3. 3-13 specifies that the "Oxygen Monitor" is applicable ''during waste gas holdup operation"~ The Waste Gas System was in service during the time period in question.
ANALYSIS OF OCCURRENCE:
ANALYSIS OF OCCURRENCE:
As discussed in the Description of section, Technical Specifications require periodic surveillance of the Waste Gas Analyzer for continued reliable operation.
As discussed in the Description of Oc~urrence section, Technical Specifications require periodic surveillance of the Waste Gas Analyzer for continued reliable operation. TQe Waste Gas Analyzer monitors oxygen concentration in the Waste Gas Holdup System, used to provide controlled handling and disposal of radioactive gaseous wastes generated during routine plant operation as required by the Code of Federal Regulations.
TQe Waste Gas Analyzer monitors oxygen concentration in the Waste Gas Holdup System, used to provide controlled handling and disposal of radioactive gaseous wastes generated during routine plant operation as required by the Code of Federal Regulations.
* The concern for oxygen within the Waste Gas-Holdup System is due to the presence* of hydrogen gas within the system. In sufficient
* The concern for oxygen within the Waste Gas-Holdup System is due to the presence*
      *quantities, hydrogen in the presence of oxygen can be explosive. The Technical Specification level of not greater than 2% oxygen is conservatively low, ensuring that an explosive hazard is not present.
of hydrogen gas within the system. In sufficient  
Monitoring the oxygen concentration, in accordance with Technical Specifications, ensures that if the oxygen concentration increases above the 2% limitation expeditious corrective action can be taken to lower the level to below 2%. As discussed previously, the.Waste Gas Analyzer surveillance was not completed within the required time.
*quantities, hydrogen in the presence of oxygen can be explosive.
However, since the analyzer did successfully pass subsequent functional testing this event did not affect the health or safety of the public. This event is reportable to the Nuclear Regulatory Commission, in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B), since.the Technical Specifications were not fully compli*ed with.
The Technical Specification level of not greater than 2% oxygen is conservatively low, ensuring that an explosive hazard is not present. Monitoring the oxygen concentration, in accordance with Technical Specifications, ensures that if the oxygen concentration increases above the 2% limitation expeditious corrective action can be taken to lower the level to below 2%. As discussed previously, the.Waste Gas Analyzer surveillance was not completed within the required time. However, since the analyzer did successfully pass subsequent functional testing this event did not affect the health or safety of the public. This event is reportable to the Nuclear Regulatory Commission, in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B), since.the Technical Specifications were not fully compli*ed with. CORRECTIVE ACTION: Technical Specification Surveillance Waste Gas Analyzer functional testing was successfully completed on December 19, 1991. Appropriate disciplinary action has been taken with those individuals involved in this event. This event has been reviewed with applicable Outage Planning Department personnel.
CORRECTIVE ACTION:
The need to maintain attention to detail and to ensure that decisions associated with the deferral of scheduled work are valid was emphasized.
Technical Specification Surveillance Waste Gas Analyzer functional testing was successfully completed on December 19, 1991.
Appropriate disciplinary action has been taken with those individuals involved in this event.
This event has been reviewed with applicable Outage Planning Department personnel. The need to maintain attention to detail and to ensure that decisions associated with the deferral of scheduled work are valid was emphasized.


&NT REPORT (LER) TEXT Salem Generating Station Unit 2-, ... CORRECTIVE ACTIO_N: (cont'd) *------------**-*  
                      *L~CEN.SEE &NT REPORT (LER) TEXT           coN&uATI~N
----------*-*
___
___ ,,_.:,____.__
                                              * - - - - - - - - - - - - * * - *----------*-* ,,_.:,____.__
DOCKET NUMBER LER NUMBER $_Q_Q_Q_311=_  
PAGE.-
.. _____
Salem Generating Station            DOCKET NUMBER               LER NUMBER Unit 2-, . . .                                      .. _____91_-Q_~J- ~Q_Q. ----=4~.PL~--
* .. A. Technical.
                                          $_Q_Q_Q_311=_
Specification.
CORRECTIVE ACTIO_N:        (cont'd)
Surveill_ance will be conducted to identify (by computer)
    *.. A. Technical. Specification. Surveill_ance revie~ will be conducted to identify (by computer) *tho~e Surveillances required-when the core is*
Surveillances required-when the core is* defueled ... currently, only 1 through 6 *applicability is identified.  
defueled ... currently, only ~ode 1 through 6 *applicability is identified.                     *       *       *   *
* * * *
* A review .of _the applicable ~dministrative procedures will be
* A review .of _the applicable procedures will be .completed"to ensure scheduling responsibilities for.surveillances, during *ou'tage *vs. non outage time. periods, are adequate.  
      .completed"to ensure scheduling responsibilities for.surveillances, during *ou'tage *vs. non outage time. periods, are adequate.
-, _-.. * ..
                    - , _- ..
* *General Manager -. Salem MJP:pc* . S9RC Mtg. 92-=-*oos}}
                                          *. **d&#xa3;/~
                                                *   *General Manager -
Salem Ope~ations
                                                                                    .
MJP:pc*
. S9RC Mtg. 92-=-*oos}}

Revision as of 11:24, 21 October 2019

LER 91-021-00:on 911219,monthly Surveillance of Wg Analyzer for Reliable Operation Overdue.Caused by Personnel Error. Event Reviewed W/Applicable Personnel & Discplinary Action taken.W/920121 Ltr
ML18096A453
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/21/1992
From: Pollack M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-021-01, LER-91-21-1, NUDOCS 9201280109
Download: ML18096A453 (5)
v • d • e


Text

o*ps~G-e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 21, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-31*1

  • UNIT NO. 2 LICENSEE EVENT REPORT 91-021-00 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 to be issued within thirty (30) days of event discovery.

Sincerely yours, C. A. Vondra General Manager -

Salem Operations MJP:pc Distribution q1.

~ The Enerov .

Peonle

  • ---*9201200109 920121

'"' '!"

  • PDR ADOCK 05000311 95-2189 (10M) 12-89 C'! s PDR

NRCFORM366 U.S. NUCLEAR RE.GULATORY COMMISSION (6-89) - .,*. , ..,* APPROVED OMB NO. 3150-0104 , -- *-:'.

UC~NSEE'Evlr REPO~T !LERI .*~&:~o~u~~~~~;;~;:i~gf~;l0~i.~~~Ls~:;;f:wl~;g

~~TS REGARDING BURDEN ESTIMATE TO THE RECORDS

.AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR

- . FACILITY NAME m

.REGULATORY CoMMISSION, WASHINGTON,-DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT. (3150-0104), OFFICE

_OF MA~AGEMENT ~ND BUDGEJ, WASHIN~TO~, DC 20503. -

Salem Generating.Station Unit 2 TITLE (4) , * ..

Tech. Spec~ Surveillance Overdue Due To Personnel Error *-.:.-

EVENT DATE(&)

  • L,ER NUMBER (6) REPORT DAT.E (7) * . - _!)THER FACILITIES INVOLVED.Ill) *.

MONTH DAY . Y~AR DAY YEAR.

. ' .....

  • FACll,I!~ fojAMES --.* * :;-:
  • DOCKET NUMB_ER(Sl
  • . *~ J s*j o I o I o I I I i I2 i I 9 9 i 9*11* - oI2 11 ~ o I o oI i 2 Io 9 I 2 o I 5 I 0 Io I 0.1 1 1 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RloQUIREMENTS OF -10 CFR §: (Check on* or more 'of th* following} 1111 . .

MODE (Ill *D >---

,_.__

20.405(cl 60.38(cll11 -- 60.73(*112llivl

  • eo.13<*i<211¥1 **.: , *.

- . >---

73.71(b) 73.71(cl

--x 60.38(cll2l 60.73(*ll211il 60.73(*112l(iil

-

-

&0.731*112llviil

&0.73l*ll2llv11111AI

. &0.?3l*ll2llvlllllBI

- OTHER (Specify in Ab1t111ct IHlow *nd In Tut, NRC Form 366AJ

- 60.73(*ll2llilll

- &0.731*ll2llxl *_ *

  • LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER

. AREA CODE M. J. Pollack

"

LER Coordinator f. In I a ~ h I a(_ I  ? In I? I?

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC* MANUFAC- _

CAUSE SYSTEM _COMPONENT- SYSTEM COMPONENT TUR ER TUR ER I I I I I I I I -I - I I I *1 *.I I I I I I I I I I r ., *I -I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR

. -EXPECTED SUBMISSION DATE.1151 J YES (If yo1, compl*t* EXPECTED SUBMISSION DA TEI I I I AllSTRACT (Limit to 1400 1~cos, i.*.. *pproKim*r.ly fiftNn linglo-s~c* ty~writtan lines} (16)

On 12/19/91, it was discovered that the Waste Gas Analyzer channel functional, Technical Specification Stirveillancia~ had not been performed.- This monthly surveillance was overdue as of 12/16/91. The last time the test was successfully completed was on 11/9/91. The surveillance was originally scheduled for 12/9/91; however, the start date was shifted (by computer logic) to 12/19/91. The PREMIS computer program for outage scheduling is structured tu control the start date for all work done during the outage, including Surveillances. When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements. The root cause of this event is personnel error. Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report". The surveillance was successfully completed on 12/19/91. Appropriate disciplinary action has been taken with those individuals involved in this event. This event has been reviewed with applicable Outage Planning Department personnel. A Technical Specification Surveillance review will be conducted to identify those Surveillances required when the core is defueled. A review of the applicable administrative procedures will be completed to ensure* scheduling responsibilities for surveillances, during outage vs. non outage time periods, are adequate.

NRC Form 366 (6-89)

. LICENsEAvENT REPORT CLER> TEXT *coaNUATI_oN -

~--------------

Salem Generating Station DOCKET NUMBER

  • .

LER NUMBER

__________ :..__ ___

PAGE

_

  • Unit 2 _ _ _ _so_Q_Q.31! __----~1-:-_Q_21:-o_o - . . .2 __0L_~--------

PLANT AND SYSTEM IDEN_'.l'I_FI_CATIQ_N:

Westinghouse Pr~ssurized Water Reactor Energy Industry I~eritifidation System-(EIIS) c6des are identified in the text as {xxJ IDENTIFICATION OF occg~~~NCE: -

. .

Technical ~pecification Su~v~illance overdue due to personnel ~rror Event Date: 12/19/91 Report Date: 1/20/92

  • This report was initiated by .Incident Report No. 91-921~

CONDITIONS PRIOR TO OCCURRENCE:

Defueled: Gth Refueling Outage in Progress On December 19, 1991, it was discovered that the Waste Gas Analyzer

{WEI channel functional, Technical Specification 3/4.3.3.9 Table 4.3-13 Surveillance, had not been performed. This monthly surveillance was overdue as of December 16, 1991. The last time the test was successfully completed was on November 9, 1991.

The surveillance was originally scheduled for December 9, 1991; however, the start date was shifted (by computer logic) to December 19, 1991. The PREMIS computer program for outage scheduling is structured to control the start date for all work done during the outage, including Surveillances. When a job is delayed, the computer automatically reschedules the start date for jobs dependent on the delayed job, independent of Technical Specification or other commitment requirements.

During non outage periods, the start date for all work (including Surveillances) is controlled by a different computer program (i.e.,

MMIS). The MMIS, for the subject surveillance, correctly identified the start, due and overdue dates.

APPARENT CAUSE OF oc~~R~~~~~=

The root cause of this event is personnel error.

Neither Outage Planning Department personnel nor the Technical Specification Surveillance Administrator observed the shift in the surveillance start date upon review of the "Technical Specification Overdue Surveillance Report". Outage Planning Department personnel did not observe that the Surveillance would go overdue due to inattention to detail.

--'-'-'-'----------'--~,_.:....-'--'------ - - - ------------*

..

LICE~sE~ ,R~PokT

'* - ..,

". _ .

  • &NT (LER)
  • TEXT cow9a.ATibN Sa1em Generating ~tation D.OCKET NUMBER LER NUMBER PAGE Unit 2 * * .... *. 5000311 91..;..021-'-00 . . 3 of 4 *

* **---- -- *.-~--------~--------**--** *:-*--*:-*.-*- --*--*-----*-**---**

. .: - . .

APPARENT CAUSE OF OC~UR~EN~E_:_~*<_c_o_nt'gl

. .

.The Technical: .Specification Administrator acts as a backup to .Qutage Planning Department' personnel to. help ensure .*s*urveillances* are not missed.* He observed.that. the Surveillance would go overdue, but since the Unit*2.was defueled.he concluded that the equipment was not reqqfred to be operable .. In.addition his database showed the surveillance as being applicable in Modes .1 through 6. At the time of the event the plant wa*s* in an undefined Mode of operation Ci. e.,

the reactor vessel was defueled). Technical Specification Table

3. 3-13 specifies that the "Oxygen Monitor" is applicable during waste gas holdup operation"~ The Waste Gas System was in service during the time period in question.

ANALYSIS OF OCCURRENCE:

As discussed in the Description of Oc~urrence section, Technical Specifications require periodic surveillance of the Waste Gas Analyzer for continued reliable operation. TQe Waste Gas Analyzer monitors oxygen concentration in the Waste Gas Holdup System, used to provide controlled handling and disposal of radioactive gaseous wastes generated during routine plant operation as required by the Code of Federal Regulations.

  • The concern for oxygen within the Waste Gas-Holdup System is due to the presence* of hydrogen gas within the system. In sufficient
  • quantities, hydrogen in the presence of oxygen can be explosive. The Technical Specification level of not greater than 2% oxygen is conservatively low, ensuring that an explosive hazard is not present.

Monitoring the oxygen concentration, in accordance with Technical Specifications, ensures that if the oxygen concentration increases above the 2% limitation expeditious corrective action can be taken to lower the level to below 2%. As discussed previously, the.Waste Gas Analyzer surveillance was not completed within the required time.

However, since the analyzer did successfully pass subsequent functional testing this event did not affect the health or safety of the public. This event is reportable to the Nuclear Regulatory Commission, in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B), since.the Technical Specifications were not fully compli*ed with.

CORRECTIVE ACTION:

Technical Specification Surveillance Waste Gas Analyzer functional testing was successfully completed on December 19, 1991.

Appropriate disciplinary action has been taken with those individuals involved in this event.

This event has been reviewed with applicable Outage Planning Department personnel. The need to maintain attention to detail and to ensure that decisions associated with the deferral of scheduled work are valid was emphasized.

  • L~CEN.SEE &NT REPORT (LER) TEXT coN&uATI~N

___

  • - - - - - - - - - - - - * * - *----------*-* ,,_.:,____.__

PAGE.-

Salem Generating Station DOCKET NUMBER LER NUMBER Unit 2-, . . . .. _____91_-Q_~J- ~Q_Q. ----=4~.PL~--

$_Q_Q_Q_311=_

CORRECTIVE ACTIO_N: (cont'd)

  • .. A. Technical. Specification. Surveill_ance revie~ will be conducted to identify (by computer) *tho~e Surveillances required-when the core is*

defueled ... currently, only ~ode 1 through 6 *applicability is identified. * * * *

  • A review .of _the applicable ~dministrative procedures will be

.completed"to ensure scheduling responsibilities for.surveillances, during *ou'tage *vs. non outage time. periods, are adequate.

- , _- ..

  • . **d£/~
  • *General Manager -

Salem Ope~ations

.

MJP:pc*

. S9RC Mtg. 92-=-*oos

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