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| issue date = 04/24/1996
| issue date = 04/24/1996
| title = LER 96-005-00:on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip initiated.W/960423 Ltr
| title = LER 96-005-00:on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip initiated.W/960423 Ltr
| author name = HASSLER D V, WARREN C
| author name = Hassler D, Warren C
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 2 2 1996 LR-N96098 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
{{#Wiki_filter:e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 2 2 1996 LR-N96098 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LER 272/96-005-00 SALEM GENERATING STATION -UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report Supplement entitled "Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B). Attachment SORC Mtg. 96-047 DVH/tcp C LER File 3.7 9604290116 960424 PDR ADOCK 05000272 S PDR The power is in yDur hands. Sincerely, &d Ou___ Clay2arren General Manager -Salem Operations bocument Control Desk :*I LR-N96098 Attachment A The following item represents commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-005-00).
LER 272/96-005-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report Supplement entitled "Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).
The commitments are as follows: 1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart. 2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00.
Sincerely,
The TSSIP review is expected to be completed by December 31, 1997.
                                              &d Ou___
NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES U/30198 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS -MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
Clay2arren General Manager -
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC , AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, 20503. FACILITY NAllE (1) DOCKET NUMBER (2) PAOE(3) SALEM GENERATING STATION, UNIT 1 05000272 1 OF3 TITLE (4) Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL  
Salem Operations Attachment SORC Mtg. 96-047 DVH/tcp C     D~stribution LER File 3.7 9604290116 960424 PDR     ADOCK 05000272 S                         PDR The power is in yDur hands.
'REVISION MONTH DAY YEAR NUMBER NUMBER SALEM -UNIT 2 05000311 03 25 96 96 005 00 04 24 96 FACILITY NAME DOCKET NUMBER --05000 OPERATING N THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) MODE(9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i)  
 
: 50. 73(a)(2)(viii) 0 20.2203(a)(1) 20.2203(a)(3)(i)  
bocument Control Desk
: 50. 73(a)(2)(ii)  
:*I LR-N96098 Attachment A The following item represents commitments that Public Service Electric
: 50. 73(a)(2)(x)
    & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-005-00). The commitments are as follows:
LEVEL(10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii)  
: 1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart.
: 50. 73(a)(2)(iii) 73.71 -20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv)
: 2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.
OTHER J 20.2203(a)(2)(iii) 50.36(c)(1)  
 
: 50. 73(a)(2)(v)
NRCFORM366                                                                   U.S. NUCLEAR REGULATORY COMMISSION                                                     APPROVED BY OMB NO. 3150-0104 (4-95)                                                                                                                                                                         EXPIRES U/30198 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS
Abstract below 20.2203(a)(2)(iv) 50.36(c)(2)  
                                      -                   ~                                                                                                            MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.
: 50. 73(a)(2)(vii) or In C Form 386A LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) ;,:.: ... ::.-: .. :-***": CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS .
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER)                                                                                              LICENSING PROCESS AND FED BACK TO INDUSTRY.               FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T~ i;:Js~ NUCLEAR (See reverse for required number of                                                                             REGULATORY COMMISSION, WASHINGTON, DC                     , AND TO THE PAPERWORK REDUCTION PROJECT ~150-0104), OFFICE OF digits/characters for each block)                                                                           MANAGEMENT AND BUDGET, WASHINGTON,             20503.
SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR 'YES XINO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE(15) ABSTRACT (Limitto 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16) On March 25 ,. 1996, the Technical Specification Surveillc..nce Improvement Project Team identified a potential Technical Specification violation regarding Channel Checks required by Technical Specification 4.3.2.1.1.
FACILITY NAllE (1)                                                                                                                                     DOCKET NUMBER (2)                                   PAOE(3)
Items 1.f and 4.d of Table 4.3-2 require that Channel Checks be performed on the Steam Line Flow, Steam Line Pressure, and Reactor Coolant Average Temperature (Tavg) instrumentation at least once per shift in modes 1, 2 and 3. A further review determined that Tavg instruments are not Channel Checked as required by Specification 4.3.2.1.1.
SALEM GENERATING STATION, UNIT 1                                                                                                               05000272                             1 OF3 TITLE (4)
A review of historical documentation indicates that both Salem Units 1 and 2 have not performed the Channel Check of Tavg instruments in modes 1, 2 and 3, potent-ially since initial plant startup. The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specifications surveillance procedures.
Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications EVENT DATE (5)                                                 LER NUMBER (6)                                 REPORT DATE (7)                                   OTHER FACILITIES INVOLVED (8)
This weakness was previously identified in LER 311/95-008-00.
MONTH             DAY             YEAR               YEAR          I          SEQUENTIAL NUMBER
                                                                                                                      'REVISION NUMBER MONTH           DAY         YEAR FACILITY NAME SALEM       -   UNIT 2 DOCKET NUMBER 05000311 03             25               96                 96             -          005           -        00       04             24           96 FACILITY NAME                             DOCKET NUMBER 05000 OPERATING                           N             THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
MODE(9)                                                   20.2201(b)                                         20.2203(a)(2)(v)                           x 50. 73(a)(2)(i)                         50. 73(a)(2)(viii)
                  ~POWER 0                     20.2203(a)(1)                                       20.2203(a)(3)(i)                               50. 73(a)(2)(ii)                     50. 73(a)(2)(x)
LEVEL(10)                                                 20.2203(a)(2)(i)                                     20.2203(a)(3)(ii)                             50. 73(a)(2)(iii)                     73.71 20.2203(a)(2)(ii)                                   20.2203(a)(4)                                 50.73(a)(2)(iv)                       OTHER 20.2203(a)(2)(iii)                                   50.36(c)(1)                                   50. 73(a)(2)(v)                 SJ>!!C~ln  Abstract below or In    C Form 386A J              20.2203(a)(2)(iv)                                   50.36(c)(2)                                   50. 73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME                                                                                                                                                         TELEPHONE NUMBER (Include Area Code)
Dennis                 v.         Hassler, LER Coordinator                                                                                                                         609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE                 SYSTEM                   COMPONENT                       MANUFACTURER             REPORTABLE                           CAUSE       SYSTEM     COMPONENT     MANUFACTURER         REPORTABLE TONPRDS                                                                                         TONPRDS t~rn=~n~~~~i
::::~**              .
                                                                                                                                          ~~M~~~~~~i SUPPLEMENTAL REPORT EXPECTED (14)                                                                                         EXPECTED             MONTH           DAY       YEAR SUBMISSION
                  'YES (If yes, complete EXPECTED SUBMISSION DATE).                                                                             XINO                                  DATE(15)
ABSTRACT (Limitto 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16)
On March 25 ,. 1996, the Technical Specification Surveillc..nce Improvement Project Team identified a potential Technical Specification violation regarding Channel Checks required by Technical Specification 4.3.2.1.1.                                                                                                                   Items 1.f and 4.d of Table 4.3-2 require that Channel Checks be performed on the Steam Line Flow, Steam Line Pressure, and Reactor Coolant Average Temperature (Tavg) instrumentation at least once per shift in modes 1, 2 and 3. A further review determined that Tavg instruments are not Channel Checked as required by Specification 4.3.2.1.1.
A review of historical documentation indicates that both Salem Units 1 and 2 have not performed the Channel Check of Tavg instruments in modes 1, 2 and 3, potent-ially since initial plant startup. The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specifications surveillance procedures. This weakness was previously identified in LER 311/95-008-00.
This event is reportable in accordance with 10 CFR 73 (a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
This event is reportable in accordance with 10 CFR 73 (a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
NRC FORM 384S (4-95) .. __ .,.. -*.o,--*  
NRC FORM 384S (4-95)
.. * .. #**"-<-*.***-.*-
.. __.,.. -*.o,--* **~-- .. * . . #**"-<-*.***-.*- "".!*~  ,. ,..,.,. --..,._. *** * * - , - - *.* '"*** *,.. * * .._ *
,. ,..,.,. --..,._. *** ** -,--*.* '"*** *,.. ** .._
 
* it !fN'Rc FORM 366A U.S. NUCLEAR REGULATORY COMMISSIOtll FACILITY NAME (1) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) SALEM GENERATING STATION, UNIT 1 05000272 YEAR I SE.fil'rirJhAL I 2 OF 3 96 -005 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION Westinghouse  
  !fN'Rc FORM 366A                                                                                                                     U.S. NUCLEAR REGULATORY COMMISSIOtll it 11(~95, LICENSEE EVENT REPORT (LER)
-Pressurized Water Reactor Tavg Instrumentation  
TEXT CONTINUATION FACILITY NAME (1)                            DOCKET NUMBER (2)                                                     LER NUMBER (6)                                             PAGE (3) 05000272                                           YEAR   I SE.fil'rirJhAL I~=                                      2           OF               3 SALEM GENERATING STATION, UNIT 1 96 -           005         -                     00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
{RCP) {AB/-}*
PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Tavg Instrumentation {RCP) {AB/-}*
* Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as (SS/CCC) CONDITIONS PRIOR TO OCCURRENCE i At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
* Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as (SS/CCC)
Technical Specification surveillance Mode applicability is 1, 2 and 3 for the Tavg Channel Check. DESCRIPTION OF OCCURRENCE As a Corrective Action from LER 311/95-006 a Technical Specification Surveillance Improvement Project (TSSIP) has been initiated.
CONDITIONS PRIOR TO OCCURRENCE i
Additional deficiencies found during the TSSIP will be documented in supplements to this LER. On March 25, 1996 during a review of the implementation of Technical Specification Surveillance Requirement 4.3.2.1.1, the TSSIP Team identified a potential Technical Specification violation regarding Channel Checks. Surveillance Requirement 4.3.2.1.1 requires a Channel Check on the instrument channels listed in Table 4.3-2. Items 1.f and 4.d of Table 4.3-2 list Engineered Safety Feature Actuations which occur on Steam Flow in Two Steam Lines--HIGH coincident with Tavg--LOW-LOW or Steam Line Pressure--LOW.
At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
The Channel Check requirements apply such that a comparison of the Steam Line Flow {SB/-} indications is to be made once per shift in modes 1, 2 and 3, as are comparisons of the Tavg instruments, and the Steam Line Pressure instruments.
Technical Specification surveillance Mode applicability is 1, 2 and 3 for the Tavg Channel Check.
A further review determined that Channel Checks were being performed on the Steam Line Flow and Pressure instruments, but not on the Tavg instruments.
DESCRIPTION OF OCCURRENCE As a Corrective Action from LER 311/95-006 a Technical Specification Surveillance Improvement Project (TSSIP) has been initiated. Additional deficiencies found during the TSSIP will be documented in supplements to this LER.
A review indicated the Channel Checks for Tavg have been required once per shift in Modes 1, 2 and 3 since the original issue of Technical Specifications for both Units 1 and 2. A historical review of the station operating log revisions since November 23, 1979 indicated that Channel Checks were not recorded for Tavg instruments in Modes 1, 2 and 3. CAUSE OF OCCURRENCE The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.
On March 25, 1996 during a review of the implementation of Technical Specification Surveillance Requirement 4.3.2.1.1, the TSSIP Team identified a potential Technical Specification violation regarding Channel Checks.
Surveillance Requirement 4.3.2.1.1 requires a Channel Check on the instrument channels listed in Table 4.3-2.                           Items 1.f and 4.d of Table 4.3-2 list Engineered Safety Feature Actuations which occur on Steam Flow in Two Steam Lines--HIGH coincident with Tavg--LOW-LOW or Steam Line Pressure--LOW. The Channel Check requirements apply such that a comparison of the Steam Line Flow {SB/-}
indications is to be made once per shift in modes 1, 2 and 3, as are comparisons of the Tavg instruments, and the Steam Line Pressure instruments. A further review determined that Channel Checks were being performed on the Steam Line Flow and Pressure instruments, but not on the Tavg instruments.
A review indicated the Channel Checks for Tavg have been required once per shift in Modes 1, 2 and 3 since the original issue of Technical Specifications for both Units 1 and 2.
A historical review of the station operating log revisions since November 23, 1979 indicated that Channel Checks were not recorded for Tavg instruments in Modes 1, 2 and 3.
CAUSE OF OCCURRENCE The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.
This weakness was previously identified in LER 311/95-008.
This weakness was previously identified in LER 311/95-008.
NRC FORM 366A (4-95) **'-----*. *---*** .,.,. ** , ** ------"<. --
NRC FORM 366A (4-95)
*----. ** .., ...... .-..
                                                                        **'- --- -*. *- --*** . , . , . ** , * * ------ "<. - - ~- -~*--*- ~.-*---* ~----*-.--.--- * - - - - . ** .., ...... ,.~,*.-. ~  .- .. ~.--,.,r.** ~;-:--** _, .* -, '':".**::-.- * *..
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NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER SALEM GENERATING STATION, UNIT 1 96 -005 -00 TEXT (If more apace is required, use additional copies of NRC Form 366A) (17) PRIOR SIMILAR OCCURRENCES PAGE(3) 3 OF A review of LERs for Salem Units 1 and 2 identified three LERs in the last two years related to missed Technical Specification Surveillances due to a procedural deficiency:
3 LER 272/96-004 "Technical 4.6.1.1 Incomplete Containment Isolation Valve Position Verification Surveillance" identified an occurrence where Containment Isolation valves were omitted from monthly position verification surveillances due to inadequate implementation of Technical Specification surveillance requirements into procedures.
LER 272/94-008 "Quarterly Channel Functional Testing of Position Indication For Power Operated Relief Valves Missed On Both Units" identified an occurrence where a procedure was revised in response to Generic Letter 90-06 without a revision to Technical Specifications which resulted in missed surveillance testing of Power Operated Relief Valves while in Modes 1 and 2. LER 311/95-008, "Technical Specification


====4.9.9 Missed====
NRC FORM 366A                                                                          U.S. NUCLEAR REGULATORY COMMISSION (4-95)
Isolation Initiation Testing," identified an occurrence where Containment Purge and Pressure-Vacuum Relief system isolation logic was not fully tested prior to and during Core Alterations due to inadequate implementation of Technical Specification surveillance requirements into procedures.
LICENSEE EVENT REPORT (LER)
SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences for this occurrence since plant operators monitor Tavg readings for each loop every eight (8) hours in Modes 1 and 2, and every 30 minutes if the reactor is critical and Tavg is below 551 degrees F with the Tavg-Tref in alarm. In addition, the RC Loops Tavg Deviation alarm provides a continuous monitor of the deviation between all Tavg channels -alarming at a preset value. While not a Technical Specification required function, this alarm would readily alert operators to any significant deviation between Tavg indications.
TEXT CONTINUATION FACILITY NAME (1)                            DOCKET NUMBER (2)      LER NUMBER (6)            PAGE(3) 05000272      YEAR I  SEQUENTIAL NUMBER IREVISION NUMBER  3  OF    3 SALEM GENERATING STATION, UNIT 1                                                      96 -      005    -    00 TEXT (If more apace is required, use additional copies of NRC Form 366A) (17)
The alarm response requires monitoring Tavg readings and initiating repairs to restore faulty instrumentation.
PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 identified three LERs in the last two years related to missed Technical Specification Surveillances due to a procedural deficiency:
Based on the above, the health and safety of the public were not affected.
LER 272/96-004 "Technical Specif~~ation 4.6.1.1 Incomplete Containment Isolation Valve Position Verification Surveillance" identified an occurrence where Containment Isolation valves were omitted from monthly position verification surveillances due to inadequate implementation of Technical Specification surveillance requirements into procedures.
CORRECTIVE ACTIONS 1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart. 2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00.
LER 272/94-008 "Quarterly Channel Functional Testing of Position Indication For Power Operated Relief Valves Missed On Both Units" identified an occurrence where a procedure was revised in response to Generic Letter 90-06 without a revision to Technical Specifications which resulted in missed surveillance testing of Power Operated Relief Valves while in Modes 1 and 2.
The TSSIP review is expected to be completed by December 31, 1997. NRC FORM 366A (4-95)}}
LER 311/95-008, "Technical Specification 4.9.9 Missed Isolation Initiation Testing," identified an occurrence where Containment Purge and Pressure-Vacuum Relief system isolation logic was not fully tested prior to and during Core Alterations due to inadequate implementation of Technical Specification surveillance requirements into procedures.
SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences for this occurrence since plant operators monitor Tavg readings for each loop every eight (8) hours in Modes 1 and 2, and every 30 minutes if the reactor is critical and Tavg is below 551 degrees F with the Tavg-Tref in alarm.                   In addition, the RC Loops Tavg Deviation alarm provides a continuous monitor of the deviation between all Tavg channels - alarming at a preset value. While not a Technical Specification required function, this alarm would readily alert operators to any significant deviation between Tavg indications. The alarm response requires monitoring Tavg readings and initiating repairs to restore faulty instrumentation. Based on the above, the health and safety of the public were not affected.
CORRECTIVE ACTIONS
: 1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart.
: 2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.
NRC FORM 366A (4-95)}}

Latest revision as of 09:01, 23 February 2020

LER 96-005-00:on 960325,channel Checks for Average Temp Not Performed as Required by Ts.Caused by Inadequate Controls for Development & Maint of TS Surveillance Procedures.Tssip initiated.W/960423 Ltr
ML18101B333
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/24/1996
From: Hassler D, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-005-01, LER-96-5-1, LR-N96098, NUDOCS 9604290116
Download: ML18101B333 (5)
v • d • e


Text

e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 2 2 1996 LR-N96098 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/96-005-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report Supplement entitled "Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).

Sincerely,

&d Ou___

Clay2arren General Manager -

Salem Operations Attachment SORC Mtg.96-047 DVH/tcp C D~stribution LER File 3.7 9604290116 960424 PDR ADOCK 05000272 S PDR The power is in yDur hands.

bocument Control Desk

  • I LR-N96098 Attachment A The following item represents commitments that Public Service Electric

& Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-005-00). The commitments are as follows:

1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart.
2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.

NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES U/30198 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS

- ~ MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.

REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T~ i;:Js~ NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC , AND TO THE PAPERWORK REDUCTION PROJECT ~150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, 20503.

FACILITY NAllE (1) DOCKET NUMBER (2) PAOE(3)

SALEM GENERATING STATION, UNIT 1 05000272 1 OF3 TITLE (4)

Failure to Perform Channel Checks for Tavg as Required by the Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER

'REVISION NUMBER MONTH DAY YEAR FACILITY NAME SALEM - UNIT 2 DOCKET NUMBER 05000311 03 25 96 96 - 005 - 00 04 24 96 FACILITY NAME DOCKET NUMBER 05000 OPERATING N THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

MODE(9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)

~POWER 0 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(x)

LEVEL(10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) SJ>!!C~ln Abstract below or In C Form 386A J 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS t~rn=~n~~~~i

~** .

~~M~~~~~~i SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION

'YES (If yes, complete EXPECTED SUBMISSION DATE). XINO DATE(15)

ABSTRACT (Limitto 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16)

On March 25 ,. 1996, the Technical Specification Surveillc..nce Improvement Project Team identified a potential Technical Specification violation regarding Channel Checks required by Technical Specification 4.3.2.1.1. Items 1.f and 4.d of Table 4.3-2 require that Channel Checks be performed on the Steam Line Flow, Steam Line Pressure, and Reactor Coolant Average Temperature (Tavg) instrumentation at least once per shift in modes 1, 2 and 3. A further review determined that Tavg instruments are not Channel Checked as required by Specification 4.3.2.1.1.

A review of historical documentation indicates that both Salem Units 1 and 2 have not performed the Channel Check of Tavg instruments in modes 1, 2 and 3, potent-ially since initial plant startup. The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specifications surveillance procedures. This weakness was previously identified in LER 311/95-008-00.

This event is reportable in accordance with 10 CFR 73 (a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.

NRC FORM 384S (4-95)

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!fN'Rc FORM 366A U.S. NUCLEAR REGULATORY COMMISSIOtll it 11(~95, LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SE.fil'rirJhAL I~= 2 OF 3 SALEM GENERATING STATION, UNIT 1 96 - 005 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Tavg Instrumentation {RCP) {AB/-}*

  • Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as (SS/CCC)

CONDITIONS PRIOR TO OCCURRENCE i

At the time of identification, Salem Units 1 and 2 were shutdown and defueled.

Technical Specification surveillance Mode applicability is 1, 2 and 3 for the Tavg Channel Check.

DESCRIPTION OF OCCURRENCE As a Corrective Action from LER 311/95-006 a Technical Specification Surveillance Improvement Project (TSSIP) has been initiated. Additional deficiencies found during the TSSIP will be documented in supplements to this LER.

On March 25, 1996 during a review of the implementation of Technical Specification Surveillance Requirement 4.3.2.1.1, the TSSIP Team identified a potential Technical Specification violation regarding Channel Checks.

Surveillance Requirement 4.3.2.1.1 requires a Channel Check on the instrument channels listed in Table 4.3-2. Items 1.f and 4.d of Table 4.3-2 list Engineered Safety Feature Actuations which occur on Steam Flow in Two Steam Lines--HIGH coincident with Tavg--LOW-LOW or Steam Line Pressure--LOW. The Channel Check requirements apply such that a comparison of the Steam Line Flow {SB/-}

indications is to be made once per shift in modes 1, 2 and 3, as are comparisons of the Tavg instruments, and the Steam Line Pressure instruments. A further review determined that Channel Checks were being performed on the Steam Line Flow and Pressure instruments, but not on the Tavg instruments.

A review indicated the Channel Checks for Tavg have been required once per shift in Modes 1, 2 and 3 since the original issue of Technical Specifications for both Units 1 and 2.

A historical review of the station operating log revisions since November 23, 1979 indicated that Channel Checks were not recorded for Tavg instruments in Modes 1, 2 and 3.

CAUSE OF OCCURRENCE The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.

This weakness was previously identified in LER 311/95-008.

NRC FORM 366A (4-95)

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3) 05000272 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 3 SALEM GENERATING STATION, UNIT 1 96 - 005 - 00 TEXT (If more apace is required, use additional copies of NRC Form 366A) (17)

PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 identified three LERs in the last two years related to missed Technical Specification Surveillances due to a procedural deficiency:

LER 272/96-004 "Technical Specif~~ation 4.6.1.1 Incomplete Containment Isolation Valve Position Verification Surveillance" identified an occurrence where Containment Isolation valves were omitted from monthly position verification surveillances due to inadequate implementation of Technical Specification surveillance requirements into procedures.

LER 272/94-008 "Quarterly Channel Functional Testing of Position Indication For Power Operated Relief Valves Missed On Both Units" identified an occurrence where a procedure was revised in response to Generic Letter 90-06 without a revision to Technical Specifications which resulted in missed surveillance testing of Power Operated Relief Valves while in Modes 1 and 2.

LER 311/95-008, "Technical Specification 4.9.9 Missed Isolation Initiation Testing," identified an occurrence where Containment Purge and Pressure-Vacuum Relief system isolation logic was not fully tested prior to and during Core Alterations due to inadequate implementation of Technical Specification surveillance requirements into procedures.

SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences for this occurrence since plant operators monitor Tavg readings for each loop every eight (8) hours in Modes 1 and 2, and every 30 minutes if the reactor is critical and Tavg is below 551 degrees F with the Tavg-Tref in alarm. In addition, the RC Loops Tavg Deviation alarm provides a continuous monitor of the deviation between all Tavg channels - alarming at a preset value. While not a Technical Specification required function, this alarm would readily alert operators to any significant deviation between Tavg indications. The alarm response requires monitoring Tavg readings and initiating repairs to restore faulty instrumentation. Based on the above, the health and safety of the public were not affected.

CORRECTIVE ACTIONS

1. Channel Checks of Tavg instruments will be incorporated into the operating logs for Modes 1 through 4 prior to each Unit restart.
2. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.

NRC FORM 366A (4-95)

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