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| issue date = 05/10/1996
| issue date = 05/10/1996
| title = LER 95-018-01:on 950720,improper Range Gauges Used for Ist. Caused by Inadequate IST Program & Lack of IST Program Maint & Implementation Processes & Associated Controls.Issued Stop Work Order by QA 950731.W/960509 Ltr
| title = LER 95-018-01:on 950720,improper Range Gauges Used for Ist. Caused by Inadequate IST Program & Lack of IST Program Maint & Implementation Processes & Associated Controls.Issued Stop Work Order by QA 950731.W/960509 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 M1\Y 0 9 1996 LR-N96119 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
{{#Wiki_filter:e 0.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit M1\Y 0 9 1996 LR-N96119 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LER 272/95-018-01 SALEM GENERATING STATION -UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Improper Range For Inservice Testing" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B). Attachment SORC Mtg. 96-057 DVH/tcp C Distribution LER File 3.7 1*"_,,. __ 960514-0388 ADOCK PDR The pO\\er is in yDur hands. Sincerely, Clay Warren General Manager -Salem Operations 95-2168 REV. 6/94 e Document Control Desk LR-N96119 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 (272/95-018-01).
LER 272/95-018-01 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report               ~upplement      entitled "Improper Range             q~uges For Inservice Testing" 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. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing. The stop work order specified that no testing shall be conducted without prior review and approval by the IST (o...,gineer.
Sincerely,
The stop work order was on December 12, 1995 with interim work controls in place. The interim controls will remain in place until the procedure revisions stated in Item 4 below are completed.
                                              ~(i:t.-fa Clay Warren General Manager -
: 2. The IST Manual will be revised prior to restart. 3. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart. 4. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit. This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028. ----------------------------------------------
Salem Operations Attachment SORC Mtg. 96-057 DVH/tcp C     Distribution LER File 3.7 1*"_,,. __
960514-0388         6~85bg72
    ~DR      ADOCK             PDR The pO\\er is in yDur hands.
95-2168 REV. 6/94


NRCFORM 366 U.S.N CLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS . MANDATORY INFORMATION COLLECTION REQUEST: 60.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
Document Control Desk e
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T F33J, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20 55-0001, AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT (315M104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (1) I uvvftc NUMBER (2) PAGE (3) SALEM GENERATING STATION, UNIT 1 05000272 1 OF3 TITLE (4) ,:;:.., IMPROPER RANGE GAUGES USED FOR INSERVICE TESTING EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER SALEM, UNIT 2 05000311 07 20 95 95 018 01 05 10 96 FACILITY tl!AME DOCKET NUMBER --05000 OPERATING 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)  
LR-N96119 Attachment A The following item represents commitments that Public Service Electric
: 50. 73(a l(2)(viii)
& Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/95-018-01). The commitments are as follows:
POWER 20.2203(a)(1) 20.2203(a)(3)(i)  
: 1. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing. The stop work order specified that no testing shall be conducted without prior review and approval by the IST (o...,gineer.
: 50. 73(a)(2)(ii) 50.73(a)(2)(x)  
The stop work order was ~ifted on December 12, 1995 with interim work controls in place. The interim controls will remain in place until the procedure revisions stated in Item 4 below are completed.
(10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii)  
: 2. The IST Manual will be revised prior to restart.
: 50. 73(a)(2)(iii) 73.71 -20.2203(a)(2)(ii) 20.2203(a)(4)  
: 3. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart.
: 50. 73(a)(2)(iv)
                                                                                ~.\
OTHER 20.2203(a)(2)(iii) 50.36(c)(1)  
: 4. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit.
: 50. 73(a)(2)(v)
This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028.
Abstnict below . .!--_
 
* 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 I CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR IYES x INO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) In July 1995, while conducting a routine biennial Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that testing of certain components was not performed in accordance with ASME Section XI requirements.
NRCFORM 366                           U.S.N CLEAR REGULATORY COMMISSION                               APPROVED BY OMB NO. 3150-0104 (4-95)                                                                                                           EXPIRES 04/30/98
The deficiency involved the failure to use the proper gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) pumps, 12 and 22 Boric Acid Transfer (BAT) pumps and 12 Residual Heat Removal (RHR) pump. This issue is reportable under 10 CFR 50.73(a) (2) (i) (B)' any condition prohibited by the plant's Technical Specifications.
                        .                                                                  ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 60.0 HRS.
This LER supplement provides an overview of the assessments of the IST program which were performed as one of the corrective actions in LER 95-018-00.
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~ F33J, U.S. NUCLEAR (See reverse for required number of                                REGULATORY COMMISSION, WASHINGTON, DC 20 55-0001, AND TO THE PAPERWORK REDUCTION PROJECT (315M104), OFFICE OF digits/characters for each block)                                MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
These assessments identified deficiencies within the IST Program. However, these deficiencies did not result in reportable conditions.
FACILITY NAME (1)                                                                       I uvvftc NUMBER (2)                                     PAGE (3)
SALEM GENERATING STATION, UNIT 1                                                         05000272                                 1 OF3 TITLE (4)                                                                                                                               ,:;:..,
IMPROPER RANGE GAUGES USED FOR INSERVICE TESTING EVENT DATE (5)                 LER NUMBER (6)                 REPORT DATE (7)                       OTHER FACILITIES INVOLVED (8)
MONTH       DAY     YEAR    YEAR I  SEQUENTIAL NUMBER IREVISION NUMBER MONTH     DAY   YEAR FACILITY NAME SALEM, UNIT 2 DOCKET NUMBER 05000311 07       20       95     95   -    018       -    01       05       10     96 FACILITY tl!AME                           DOCKET NUMBER 05000 OPERATING                 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 l(2)(viii)
POWER                       20.2203(a)(1)                   20.2203(a)(3)(i)                   50. 73(a)(2)(ii)                       50.73(a)(2)(x)
(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)                 Speci~ln Abstnict below o::-~n..!--_ CFo~m.J66A
* 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 TO NPRDS                                                                               TO NPRDS IYES SUPPLEMENTAL REPORT EXPECTED (14)
(If yes, complete EXPECTED SUBMISSION DATE).
I x INO EXPECTED SUBMISSION DATE (15)
MONTH              DAY        YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
In July 1995, while conducting a routine biennial Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that ~he testing of certain components was not performed in accordance with ASME Section XI requirements.               The deficiency involved the failure to use the proper gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) pumps, 12 and 22 Boric Acid Transfer (BAT) pumps and 12 Residual Heat Removal (RHR) pump.                                                         This issue is reportable under 10 CFR 50.73(a) (2) (i) (B)' any condition prohibited by the plant's Technical Specifications.
This LER supplement provides an overview of the assessments of the IST program which were performed as one of the corrective actions in LER 95-018-00.                                                                 These assessments identified deficiencies within the IST Program.                                                     However, these deficiencies did not result in reportable conditions.
Corrective actions for the identified IST deficiencies include procedure revisions, an upgrade to the IST manual, and a new programmatic IST standard.
Corrective actions for the identified IST deficiencies include procedure revisions, an upgrade to the IST manual, and a new programmatic IST standard.
NRC FORM 366 (4-95)
NRC FORM 366 (4-95)
* NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) LICENSEE EVENT REPORT (LfR) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER 6) PAGE (3) 05000272 YEAR I SEQUENTIAL REVISION NUMBER NUMBER 2 OF 3 SALEM GENERATING STATION, UNIT 1 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT and SYSTEM IDENTIFICATION:
 
Westinghouse  
NRC FORM 366A                                                                                                                                               U.S. NUCLEAR REGULATORY COMMISSION (4-95)
-Pressurized Water Reactor Component Cooling Pumps {CC/P}* Boric Acid Transfer Pumps {CB/P} Residual Heat Removal Pump {BP/P} 95 -018 -01
* LICENSEE EVENT REPORT (LfR)
* Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as {SS/CC}. CONDITIONS PRIOR TO OCCURRENCE:
TEXT CONTINUATION FACILITY NAME (1)                                                                    DOCKET NUMBER (2)     LER NUMBER 6)                                 PAGE (3) 05000272   YEAR I   SEQUENTIAL NUMBER REVISION NUMBER         2         OF         3 SALEM GENERATING STATION, UNIT 1 95 -        018          -      01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT and SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Component Cooling Pumps {CC/P}*
Boric Acid Transfer Pumps {CB/P}
Residual Heat Removal Pump {BP/P}
* Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as {SS/CC}.
CONDITIONS PRIOR TO OCCURRENCE:
At the time of identification, Salem Units 1 and 2 were in a self-imposed extended shutdown.
At the time of identification, Salem Units 1 and 2 were in a self-imposed extended shutdown.
Mode: 5 Reactor Power: % Unit Load: MWe DESCRIPTION OF OCCURRENCE:
Mode: 5                                                       Reactor Power: %                                                                   Unit Load: MWe DESCRIPTION OF OCCURRENCE:
In July 1995, while conducting a routine bienni al Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable programmatic deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that the testing of certain components was not performed in accordance with ASME Section XI requirements.
In July 1995, while conducting a routine bienni al Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable programmatic deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that the testing of certain components was not performed in accordance with ASME Section XI requirements.
The deficiency involved the failure to use the proper range gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) {CC/P} pumps, 12 and 22 Boric Acid Transfer (BAT) {CB/P} pumps and 12 Residual Heat Removal (RHR) {BP/P} pump. ASME Section XI, subsection IWP 4120 requires that, "the full scale range of each instrument be three times the reference value or less." The IST audit concluded that the range of the gauges used for testing in accordance with Technical Specification section 4.0.5 exceeded three times the reference value. This LER supplement provides an overview of the assessment of the IST program which was performed as one of the corrective actions in LER 95-018-00.
The deficiency involved the failure to use the proper range gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) {CC/P} pumps, 12 and 22 Boric Acid Transfer (BAT) {CB/P} pumps and 12 Residual Heat Removal (RHR) {BP/P} pump.
An assessment of the IST program was performed as one of the corrective actions stated in LER 95-018-00. The assessment identified deficiencies within the IST Program; however, it was determined that the deficiencies did not result in any additional Technical Specification systems being declared inoperable.
ASME Section XI, subsection IWP 4120 requires that, "the full scale range of each instrument be three times the reference value or less." The IST audit concluded that the range of the gauges used for testing in accordance with Technical Specification section 4.0.5 exceeded three times the reference value.
Therefore, these deficiencies did not constitute reportable conditions.
This LER supplement provides an overview of the assessment of the IST program which was performed as one of the corrective actions in LER 95-018-00. An assessment of the IST program was performed as one of the corrective actions stated in LER 95-018-00. The assessment identified deficiencies within the IST Program; however, it was determined that the deficiencies did not result in any additional Technical Specification systems being declared inoperable. Therefore, these deficiencies did not constitute reportable conditions.
CAUSE OF OCCURRENCE The causes for the IST Program deficiencies, including the use of improper gauges, were an inadequate IST Program, and a lack of adequate IST program maintenance and implementation processes and associated controls.
CAUSE OF OCCURRENCE The causes for the IST Program deficiencies, including the use of improper gauges, were an inadequate IST Program, and a lack of adequate IST program maintenance and implementation processes and associated controls.
NRC FORM 366A (4-95) ----.,,., ___ ,_ ,_._..s_,,._  
NRC FORM 366A (4-95)
*---. -* . ,,.. ..... .,. -.--* **------------"'  
---- .,,., ___ ,_ ,_._..s_,,._ *-- - . -* . ,,.. ..... .,. - .--* **- -----------"' ---*****--*' -* ~-*'-- *-**-~------- p - -~ --- --- , **** -- - - -                   . - -** - ..... - .. *--------------- --------.. ~- --- ,_,_, '"",*'-'*:**- . l
---*****--*'  
 
-*
NRC FORM 366A                                                                           U.S. NUCLEAR REGULATORY COMMISSION (4-95)
p -------, **** -----. --** -..... -.. *---------------
'                                              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 95 -     018     -     01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
.. l
PRIOR SIMILAR OCCURRENCE A review of LERs for Salem Units 1 and 2 in the past two years identified two problem areas similar to the IST Program deficiencies. LER 272/95-028-00 addressed a Technical Specifications required program, leakage monitoring of primary coolant outside containment, not being controlled as an integrated program. In this case the elements of the program were being implemented separately. A leakage monitoring program that will meet the Technical Specifications will be implemented prior to entering Mode 4.
' NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (6) 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER SALEM GENERATING STATION, UNIT 1 95 -018 -01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PRIOR SIMILAR OCCURRENCE PAGE (3) 3 OF 3 A review of LERs for Salem Units 1 and 2 in the past two years identified two problem areas similar to the IST Program deficiencies.
The second similar area was a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures. This concern was addressed in LERs 272/96-005-01, 272/96-005-00, 272/96-004-00, 272/94-008-00, and 311/95-008-00. A Technical Specification surveillance Improvement Prog"'?ain:.has been initiated to ensure that surveillances are adequately proceduralized.
LER 272/95-028-00 addressed a Technical Specifications required program, leakage monitoring of primary coolant outside containment, not being controlled as an integrated program. In this case the elements of the program were being implemented separately.
SAFETY CONSEQUENCES AND IMPLICATIONS The IST Program deficiencies did not result in a failure to identify degradation of the affected components nor were any components identified which would have failed to perform their intended safety function.                                 Therefore the health and safety of the* public was not affected.
A leakage monitoring program that will meet the Technical Specifications will be implemented prior to entering Mode 4. The second similar area was a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.
CORRECTIVE ACTIONS
This concern was addressed in LERs 272/96-005-01, 272/96-005-00, 272/96-004-00, 272/94-008-00, and 311/95-008-00.
: 1. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing.       The stop work order specified that no testing shall be conducted without prior review and approval by the IST engineer.                                 The stop work order was lifted on December 12, 1995 with interim work co;trols in place. The interim controls will remain in place until the *procedure revisions stated in Item 5 below are completed.
A Technical Specification surveillance Improvement Prog"'?ain:.has been initiated to ensure that surveillances are adequately proceduralized.
SAFETY CONSEQUENCES AND IMPLICATIONS The IST Program deficiencies did not result in a failure to identify degradation of the affected components nor were any components identified which would have failed to perform their intended safety function.
Therefore the health and safety of the* public was not affected.
CORRECTIVE ACTIONS 1. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing. The stop work order specified that no testing shall be conducted without prior review and approval by the IST engineer.
The stop work order was lifted on December 12, 1995 with interim work co;trols in place. The interim controls will remain in place until the *procedure revisions stated in Item 5 below are completed.  
: 2. An assessment of the IST program was performed to ensure that programmatic.:.
: 2. An assessment of the IST program was performed to ensure that programmatic.:.
and procedure deficiencies within the IST program were identified and corrective actions initiated.  
and procedure deficiencies within the IST program were identified and corrective actions initiated.
: 3. The IST Manual will be revised prior to restart. 4. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart. 5. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit. This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028.
: 3. The IST Manual will be revised prior to restart.
: 4. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart.
: 5. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit. This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028.
NRC FORM 366A (4-95)}}
NRC FORM 366A (4-95)}}

Latest revision as of 05:34, 3 February 2020

LER 95-018-01:on 950720,improper Range Gauges Used for Ist. Caused by Inadequate IST Program & Lack of IST Program Maint & Implementation Processes & Associated Controls.Issued Stop Work Order by QA 950731.W/960509 Ltr
ML18101B351
Person / Time
Site: Salem PSEG icon.png
Issue date: 05/10/1996
From: Hassler D, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-95-018, LER-95-18, LR-N96119, NUDOCS 9605140388
Download: ML18101B351 (5)
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e 0.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit M1\Y 0 9 1996 LR-N96119 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/95-018-01 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report ~upplement entitled "Improper Range q~uges For Inservice Testing" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).

Sincerely,

~(i:t.-fa Clay Warren General Manager -

Salem Operations Attachment SORC Mtg.96-057 DVH/tcp C Distribution LER File 3.7 1*"_,,. __

960514-0388 6~85bg72

~DR ADOCK PDR The pO\\er is in yDur hands.

95-2168 REV. 6/94

Document Control Desk e

LR-N96119 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 (272/95-018-01). The commitments are as follows:

1. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing. The stop work order specified that no testing shall be conducted without prior review and approval by the IST (o...,gineer.

The stop work order was ~ifted on December 12, 1995 with interim work controls in place. The interim controls will remain in place until the procedure revisions stated in Item 4 below are completed.

2. The IST Manual will be revised prior to restart.
3. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart.

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4. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit.

This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028.

  • ~*=

NRCFORM 366 U.S.N CLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30/98

. ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 60.0 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~ F33J, U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20 55-0001, AND TO THE PAPERWORK REDUCTION PROJECT (315M104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) I uvvftc NUMBER (2) PAGE (3)

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

IMPROPER RANGE GAUGES USED FOR INSERVICE TESTING EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME SALEM, UNIT 2 DOCKET NUMBER 05000311 07 20 95 95 - 018 - 01 05 10 96 FACILITY tl!AME DOCKET NUMBER 05000 OPERATING 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 l(2)(viii)

POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x)

(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) Speci~ln Abstnict below o::-~n..!--_ CFo~m.J66A

  • 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 TO NPRDS TO NPRDS IYES SUPPLEMENTAL REPORT EXPECTED (14)

(If yes, complete EXPECTED SUBMISSION DATE).

I x INO EXPECTED SUBMISSION DATE (15)

MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

In July 1995, while conducting a routine biennial Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that ~he testing of certain components was not performed in accordance with ASME Section XI requirements. The deficiency involved the failure to use the proper gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) pumps, 12 and 22 Boric Acid Transfer (BAT) pumps and 12 Residual Heat Removal (RHR) pump. This issue is reportable under 10 CFR 50.73(a) (2) (i) (B)' any condition prohibited by the plant's Technical Specifications.

This LER supplement provides an overview of the assessments of the IST program which were performed as one of the corrective actions in LER 95-018-00. These assessments identified deficiencies within the IST Program. However, these deficiencies did not result in reportable conditions.

Corrective actions for the identified IST deficiencies include procedure revisions, an upgrade to the IST manual, and a new programmatic IST standard.

NRC FORM 366 (4-95)

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

  • LICENSEE EVENT REPORT (LfR)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER 6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER REVISION NUMBER 2 OF 3 SALEM GENERATING STATION, UNIT 1 95 - 018 - 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT and SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Component Cooling Pumps {CC/P}*

Boric Acid Transfer Pumps {CB/P}

Residual Heat Removal Pump {BP/P}

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

CONDITIONS PRIOR TO OCCURRENCE:

At the time of identification, Salem Units 1 and 2 were in a self-imposed extended shutdown.

Mode: 5 Reactor Power: % Unit Load: MWe DESCRIPTION OF OCCURRENCE:

In July 1995, while conducting a routine bienni al Quality Assurance (QA) audit of the Salem Inservice Testing (IST) Program, a reportable programmatic deficiency was identified concerning the failure to use gauges with a proper range for pump testing. This deficiency constitutes a violation of Technical Specification 4.0.5 in that the testing of certain components was not performed in accordance with ASME Section XI requirements.

The deficiency involved the failure to use the proper range gauges for the testing of 11, 12, 13, 21, 22, and 23 Component Cooling (CC) {CC/P} pumps, 12 and 22 Boric Acid Transfer (BAT) {CB/P} pumps and 12 Residual Heat Removal (RHR) {BP/P} pump.

ASME Section XI, subsection IWP 4120 requires that, "the full scale range of each instrument be three times the reference value or less." The IST audit concluded that the range of the gauges used for testing in accordance with Technical Specification section 4.0.5 exceeded three times the reference value.

This LER supplement provides an overview of the assessment of the IST program which was performed as one of the corrective actions in LER 95-018-00. An assessment of the IST program was performed as one of the corrective actions stated in LER 95-018-00. The assessment identified deficiencies within the IST Program; however, it was determined that the deficiencies did not result in any additional Technical Specification systems being declared inoperable. Therefore, these deficiencies did not constitute reportable conditions.

CAUSE OF OCCURRENCE The causes for the IST Program deficiencies, including the use of improper gauges, were an inadequate IST Program, and a lack of adequate IST program maintenance and implementation processes and associated controls.

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 95 - 018 - 01 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PRIOR SIMILAR OCCURRENCE A review of LERs for Salem Units 1 and 2 in the past two years identified two problem areas similar to the IST Program deficiencies. LER 272/95-028-00 addressed a Technical Specifications required program, leakage monitoring of primary coolant outside containment, not being controlled as an integrated program. In this case the elements of the program were being implemented separately. A leakage monitoring program that will meet the Technical Specifications will be implemented prior to entering Mode 4.

The second similar area was a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures. This concern was addressed in LERs 272/96-005-01, 272/96-005-00, 272/96-004-00, 272/94-008-00, and 311/95-008-00. A Technical Specification surveillance Improvement Prog"'?ain:.has been initiated to ensure that surveillances are adequately proceduralized.

SAFETY CONSEQUENCES AND IMPLICATIONS The IST Program deficiencies did not result in a failure to identify degradation of the affected components nor were any components identified which would have failed to perform their intended safety function. Therefore the health and safety of the* public was not affected.

CORRECTIVE ACTIONS

1. A stop work order was issued by QA on July 31, 1995 for all IST surveillance testing. The stop work order specified that no testing shall be conducted without prior review and approval by the IST engineer. The stop work order was lifted on December 12, 1995 with interim work co;trols in place. The interim controls will remain in place until the *procedure revisions stated in Item 5 below are completed.
2. An assessment of the IST program was performed to ensure that programmatic.:.

and procedure deficiencies within the IST program were identified and corrective actions initiated.

3. The IST Manual will be revised prior to restart.
4. A programmatic Standard describing conduct of the Salem IST program will be developed and issued prior to restart.
5. Procedure revisions to ensure adequate IST program maintenance and implementation will be completed prior to restart of each Salem unit. This includes Operations procedures implementing Technical Specification 4.0.5, procedures NC.NA-AP.ZZ-0001, NC.NA-AP.ZZ-0070 and SC.TE-TI.ZZ-0028.

NRC FORM 366A (4-95)

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