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{{#Wiki_filter:1...1 e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 0 81996 LR-N96094 U. S. Nuclear Regulatory Commission Document Control Desk
{{#Wiki_filter:e OPS~G 1...1 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 0 81996 LR-N96094 U. S. Nuclear Regulatory Commission Document Control Desk
* Washington, DC 20005  
* Washington, DC               20005


==Dear Sir:==
==Dear Sir:==
** *LER 272/96-004-00 SALEM GENERATING STATION -UNIT 1 LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Containment Isolation Valve Missed Technical Specification Surveillance" is being submitted pursuant to the requirements of the Code of Federal Regulations, 10CFR50.73 (a) (2) (i) (B). Attachment SORC Mtg. 96-041 DWD/ C: Distribution LER File 3.7 12nn11-1 PDR PDR s *The power is in your hands.
 
* General Manager -Salem Operations 95-2168 REV. 6/94
      ** *LER 272/96-004-00 SALEM GENERATING STATION - UNIT 1 LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Containment Isolation Valve Missed Technical Specification Surveillance" is being submitted pursuant to the requirements of the Code of Federal Regulations, 10CFR50.73 (a) (2) (i) (B).
' ' NRC FORM 366 U.S. NUCLEAR 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: 50.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS ANO FED BACK TO INDUSTRY.
s;nx~!Juu_
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of ANO RECORDS MANAGEMENT BRANCH (T-e F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, ANO TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, DC 20503. FACILITY NAllE (1) DOCKET NUllBER (2) PAGE (3) Salem Generating Station -Unit No. 1 05000272 1 OF 4 TITLE (4) Containment Isolation Valve Missed Technical Specification Surveillance EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL  
C~rren General Manager -
'REVISION MONTH DAY YEAR NUMBER NUMBER SALEM -UNIT 2 05000311 03 07 96 96 004 00 04 08 96 FACILITY NAME DOCKET NUMBER --.. OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) MODE (9) N/A 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i)
Salem Operations Attachment SORC Mtg.         96-041 DWD/
: 50. 73(a)(2)(viii)
C:     Distribution LER File 3.7 12nn11-1 960412000~ 6~868~72 PDR     ADOC~            PDR s
POWER 20.2203(a)(1) 20.2203(a)(3)(i)
        *The power is in your hands.
: 50. 73(a)(2)(ii)
* 95-2168 REV. 6/94
: 50. 73(a)(2)(x)
 
LEVEL (10) 0 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)
NRC FORM 366                       U.S. NUCLEAR 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: 50.0 HRS.
Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2)
REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER)                                            LICENSING PROCESS ANO FED BACK TO INDUSTRY.               FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH (T-e F33), U.S. NUCLEAR (See reverse for required number of                              REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF digits/characters for each block)                              MANAGEMENT ANO BUDGET, WASHINGTON, DC 20503.
: 50. 73(a)(2)(vii)
FACILITY NAllE (1)                                                                     DOCKET NUllBER (2)                                   PAGE (3)
LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Dave Dodson, Station Licensing Engineer 609-339-1282 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 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR 'YES X 'NO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On March 7, 1996, it was identified that the requirements of Technical Specification 4.6.1.1 were not fully implemented at Units 1 and 2 . Specifically, the monthly surveillance procedure that has been used to implement Technical Specification 4.6.1.1 did not direct position verification of the Refueling Canal Supply and Discharge Containment Isolation Valves.' This condition has existed since at least 1986. The apparent cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.
Salem Generating Station - Unit No. 1                                                       05000272                             1 OF 4 TITLE (4)
This weakness was previously identified in LER 311/95-008.
Containment Isolation Valve Missed Technical Specification Surveillance EVENT DATE (5)                 LER NUMBER (6)               REPORT DATE (7)                     OTHER FACILITIES INVOLVED (8)
Corrective actions as stated in this previous LER are still in progress, and will include verification of the adequacy of all Technical Specification surveillance procedures, with 1-imi ted exceptions, and verification that controls are in place to maint3in the adequacy of the procedures.
MONTH       DAY     YEAR   YEAR  I  SEQUENTIAL NUMBER
This event is reportable in accordance with 10 CFR 73(a) (2) (i) (B) I any condition prohibited by the plant's Technical Specifications.
                                                            'REVISION NUMBER MONTH   DAY     YEAR FACILITY NAME SALEM - UNIT 2 DOCKET NUMBER 05000311 FACILITY NAME                            DOCKET NUMBER 03 .. 07           96     96 -      004       -    00       04     08     96 OPERATING                 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
NRC FORM 366 (4-95)
MODE (9)       N/A         20.2201(b)                     20.2203(a)(2)(v)             x 50. 73(a)(2)(i)                         50. 73(a)(2)(viii)
\ *' I NRC FORM 366A (495) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) Salem Generating Station -Unit 1 DOCKET NUMBER (2) 05000 05000272 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION Westinghouse
POWER                       20.2203(a)(1)                   20.2203(a)(3)(i)                 50. 73(a)(2)(ii)                     50. 73(a)(2)(x)
-Pressurized Water Reactor Waste Disposal Liquid System (WL) IDENTIFICATION OF OCCURRENCE Discovery Date: March 7, 1996 LER NUMBER (6) YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 9 6 00 PAGE (3) 2 OF 4 Event Dates: The failure to perform adequate, documented verification of the referenced containment isolation valves occurred during each required surveillance interval, possibly since initial licer.sing, with the plants in Modes 1 through 4. CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Uni ts 1 and 2 were shutdown and defueled.
LEVEL (10)         0         20.2203(a)(2)(i)               20.2203(a)(3)(ii)                 50. 73(a)(2)(iii)                     73.71
The Technical Specification surveillance Mode applicability is 1 through 4. DESCRIPTION OF OCCURRENCE Technical Specification 4.6.1.1 states, "Primary CONTAINMENT INTEGRITY shall be demonstrated at least once per 31 days by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided ip Table 3.6-1 of Specification 3.6.3.1, and all equipment hatches are closed and sealed." In response to questions raised during the NRC Restart Team Inspection at Hope Creek, Salem Station initiated a review of its procedure for containment isolation valve position verification.
      -
The review identified four valves (1WL190, 1WL191, 2WL190, ana 2WL191) that were not included in the monthly (31 day) Containment Isolation Valves surveillance procedure.
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)                 Spec~in Abstract below or in     C Form 366A 20.2203(a)(2)(iv)               50.36(c)(2)                       50. 73(a)(2)(vii)
A random sampling of historical records showed that the valves had been missing from the surveillance tests at both units since at least 1986. The valves have been listed in Table 3.6-1 of the Unit 1 and 2 Technical Specifications since the licenses were issued. NRC FORM 366A (4-95)
LICENSEE CONTACT FOR THIS LER (12)
. ,* ' I NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) Salem Generating Station -Unit 1 DOCKET NUMBER (2) 05000 05000272 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) APPARENT CAUSE OF OCCURRENCE LER NUMBER (6) YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 9 6 --04 00 PAGE (3) 3 OF 4 The apparent cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures.
NAME                                                                                         TELEPHONE NUMBER (Include Area Code)
This weakness was previously identified in LER 311/95-008.
Dave Dodson, Station Licensing Engineer                                                                           609-339-1282 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 SUPPLEMENTAL REPORT EXPECTED (14)                                             EXPECTED             MONTH         DAY         YEAR SUBMISSION
          'YES (If yes, complete EXPECTED SUBMISSION DATE).                         X 'NO                        DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On March 7, 1996, it was identified that the requirements of Technical Specification 4.6.1.1 were not fully implemented at Units 1 and 2 .
Specifically, the monthly surveillance procedure that has been used to implement               Technical             Specification                 4.6.1.1           did         not       direct             position verification of                     the     Refueling             Canal Supply and Discharge Containment Isolation Valves.' This condition has existed since at least 1986.
The apparent 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.               Corrective actions as stated in this previous LER are still in progress, and will include verification of the adequacy of all Technical Specification                   surveillance                 procedures,             with         1-imi ted         exceptions,                   and verification that controls are in place to maint3in the adequacy of the procedures.
This event is reportable in accordance with 10 CFR 73(a) (2) (i)                                                                         (B)   I   any condition prohibited by the plant's Technical Specifications.
NRC FORM 366 (4-95)
 
\ I *' NRC FORM 366A                                                                       U.S. NUCLEAR REGULATORY COMMISSION (495)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)                           DOCKET NUMBER (2)     LER NUMBER (6)            PAGE (3) 05000      YEAR I SEQUENTIAL NUMBER IREVISION NUMBER  2  OF    4 Salem Generating Station - Unit 1                                      05000272      96 -      04    -    00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Waste Disposal Liquid System (WL)
IDENTIFICATION OF OCCURRENCE Discovery Date:                      March 7, 1996 Event Dates: The failure to perform adequate, documented                                             verification of the referenced containment isolation valves occurred during each required surveillance interval, possibly since initial licer.sing, with the plants in Modes 1 through 4.
CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Uni ts 1 and 2 were shutdown and defueled.           The Technical Specification surveillance Mode applicability is 1 through 4.
DESCRIPTION OF OCCURRENCE Technical Specification 4.6.1.1 states, "Primary CONTAINMENT INTEGRITY shall be demonstrated at least once per 31 days by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided ip Table 3.6-1 of Specification 3.6.3.1, and all equipment hatches are closed and sealed."
In response to questions raised during the NRC Restart Asse~sment Team Inspection at Hope Creek, Salem Station initiated a review of its procedure for containment isolation valve position verification.                                         The review identified four valves (1WL190, 1WL191, 2WL190, ana 2WL191) that were not included in the monthly (31 day) Containment Isolation Valves surveillance procedure. A random sampling of historical records showed that the valves had been missing from the surveillance tests at both units since at least 1986. The valves have been listed in Table 3.6-1 of the Unit 1 and 2 Technical Specifications since the licenses were issued.
NRC FORM 366A (4-95)
 
. ,*
NRC FORM 366A                                                                       U.S. NUCLEAR REGULATORY COMMISSION
  'I (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)                           DOCKET NUMBER (2)      LER NUMBER (6)            PAGE (3) 05000      YEAR I  SEQUENTIAL NUMBER IREVISION NUMBER  3  OF    4 Salem Generating Station - Unit 1                                     05000272       9 6 --    04          00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
APPARENT CAUSE OF OCCURRENCE The apparent 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.
PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 identified the following two LERs issued in the last two years relating to missed Technical Specification surveillances due to procedural deficiencies:
PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 identified the following two LERs issued in the last two years relating to missed Technical Specification surveillances due to procedural deficiencies:
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 Specifications
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.
: 4. 9. 9 Missed Isolation Testing" identified that the surveillance testing performed, prior to core alterations, for the Containment Purge and Pressure-Vacuum Relief isolation system did not confirm the manually initiated isolation function as required by Technical Specifications 4.9.9. SAFETY CONSEQUENCES AND IMPLICATIONS Administrative controls such as post outage valve lineup checks would likely have ensured that the valves were properly shut prior to power operations following an outage. Additionally, the monthly surveillance procedures did include position verification of the outside Containment Refueling Canal Supply and Discharge isolation valves (1SF22, 1SF36, 2SF22, and 2SF36). Thus there were no safety consequences associated with this condition since containment integrity would not have been affected in the unlikely event of an accident.
LER 311/95-008 "Technical Specifications 4. 9. 9 Missed Isolation Testing" identified that                   the       surveillance             testing performed,               prior     to   core alterations, for the Containment Purge and Pressure-Vacuum Relief isolation system did not confirm the manually initiated isolation function as required by Technical Specifications 4.9.9.
Based on the above, the heal th and safety of the public were not affected.
SAFETY CONSEQUENCES AND IMPLICATIONS Administrative controls such as post outage valve lineup checks would likely have ensured that the valves were properly shut prior to power operations following an outage.                                 Additionally, the monthly surveillance procedures did include position verification of the outside Containment Refueling Canal Supply and Discharge isolation valves (1SF22, 1SF36, 2SF22, and 2SF36).             Thus there were no safety consequences associated with this condition since containment integrity would not have been affected in the unlikely event of an accident.                               Based on the above, the heal th and safety of the public were not affected.
NRC FORM 366A (4-95)
NRC FORM 366A (4-95)
' ' . . . f><RC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 4 OF 4 Salem Generating Station Unit -1 05000 05000272 9 6 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) CORRECTIVE ACTIONS 1) A review is being valves are included, surveillance tests. affected units. performed to ensure that all containment isolation as required, in the periodic position verification This review will be complete prior to restart of the 2) 1WL190, 1WL191, 2WL190, and 2WL191 will be. added to the appropriate monthly surveillance procedures prior to the affected units' core reload. 3) 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 complete by December 31, 1997. NRC FORM 366A (4-95)}}
    ' .
                ..
' f><RC FORM 366A (4-95)
FACILITY NAME (1)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET NUMBER (2) 05000 U.S. NUCLEAR REGULATORY COMMISSION YEAR LER NUMBER (6)
I SEQUENTIAL NUMBER IREVISION NUMBER 4 PAGE (3)
OF     4 Salem Generating Station Unit - 1                                     05000272       96 -      04    -    00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
CORRECTIVE ACTIONS
: 1) A review is being performed to ensure that all containment isolation valves are included, as required, in the periodic position verification surveillance tests.                    This review will be complete prior to restart of the affected units.
: 2) 1WL190, 1WL191, 2WL190, and 2WL191 will be. added to the appropriate monthly surveillance procedures prior to the affected units' core reload.
: 3) 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 complete by December 31, 1997.
NRC FORM 366A (4-95)}}

Revision as of 10:02, 21 October 2019

LER 96-004-00:on 960307,identified That Ci Valve TS Surveillance Missed Due to Lack of Adequate Controls for Development & Maint of TS Sps.Util Verifying Adequacy of All TS SPs.W/960408 Ltr
ML18101B314
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/08/1996
From: Douglas Dodson, Warren C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-004-01, LER-96-4-1, LR-N96094, NUDOCS 9604120009
Download: ML18101B314 (5)
v • d • e


Text

e OPS~G 1...1 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 0 81996 LR-N96094 U. S. Nuclear Regulatory Commission Document Control Desk

Dear Sir:

    • *LER 272/96-004-00 SALEM GENERATING STATION - UNIT 1 LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Containment Isolation Valve Missed Technical Specification Surveillance" is being submitted pursuant to the requirements of the Code of Federal Regulations, 10CFR50.73 (a) (2) (i) (B).

s;nx~!Juu_

C~rren General Manager -

Salem Operations Attachment SORC Mtg.96-041 DWD/

C: Distribution LER File 3.7 12nn11-1 960412000~ 6~868~72 PDR ADOC~ PDR s

  • The power is in your hands.
  • 95-2168 REV. 6/94

\

'...

'

NRC FORM 366 U.S. NUCLEAR 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: 50.0 HRS.

REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS ANO FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH (T-e F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF digits/characters for each block) MANAGEMENT ANO BUDGET, WASHINGTON, DC 20503.

FACILITY NAllE (1) DOCKET NUllBER (2) PAGE (3)

Salem Generating Station - Unit No. 1 05000272 1 OF 4 TITLE (4)

Containment Isolation Valve Missed Technical Specification Surveillance 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 FACILITY NAME DOCKET NUMBER 03 .. 07 96 96 - 004 - 00 04 08 96 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

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

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

LEVEL (10) 0 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) Spec~in Abstract below or in C Form 366A 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)

Dave Dodson, Station Licensing Engineer 609-339-1282 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 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION

'YES (If yes, complete EXPECTED SUBMISSION DATE). X 'NO DATE (15)

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

On March 7, 1996, it was identified that the requirements of Technical Specification 4.6.1.1 were not fully implemented at Units 1 and 2 .

Specifically, the monthly surveillance procedure that has been used to implement Technical Specification 4.6.1.1 did not direct position verification of the Refueling Canal Supply and Discharge Containment Isolation Valves.' This condition has existed since at least 1986.

The apparent 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. Corrective actions as stated in this previous LER are still in progress, and will include verification of the adequacy of all Technical Specification surveillance procedures, with 1-imi ted exceptions, and verification that controls are in place to maint3in the adequacy of the procedures.

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

NRC FORM 366 (4-95)

\ I *' NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (495)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 4 Salem Generating Station - Unit 1 05000272 96 - 04 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Waste Disposal Liquid System (WL)

IDENTIFICATION OF OCCURRENCE Discovery Date: March 7, 1996 Event Dates: The failure to perform adequate, documented verification of the referenced containment isolation valves occurred during each required surveillance interval, possibly since initial licer.sing, with the plants in Modes 1 through 4.

CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Uni ts 1 and 2 were shutdown and defueled. The Technical Specification surveillance Mode applicability is 1 through 4.

DESCRIPTION OF OCCURRENCE Technical Specification 4.6.1.1 states, "Primary CONTAINMENT INTEGRITY shall be demonstrated at least once per 31 days by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided ip Table 3.6-1 of Specification 3.6.3.1, and all equipment hatches are closed and sealed."

In response to questions raised during the NRC Restart Asse~sment Team Inspection at Hope Creek, Salem Station initiated a review of its procedure for containment isolation valve position verification. The review identified four valves (1WL190, 1WL191, 2WL190, ana 2WL191) that were not included in the monthly (31 day) Containment Isolation Valves surveillance procedure. A random sampling of historical records showed that the valves had been missing from the surveillance tests at both units since at least 1986. The valves have been listed in Table 3.6-1 of the Unit 1 and 2 Technical Specifications since the licenses were issued.

NRC FORM 366A (4-95)

. ,*

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION

'I (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 4 Salem Generating Station - Unit 1 05000272 9 6 -- 04 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

APPARENT CAUSE OF OCCURRENCE The apparent 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.

PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 identified the following two LERs issued in the last two years relating to missed Technical Specification surveillances due to procedural deficiencies:

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 Specifications 4. 9. 9 Missed Isolation Testing" identified that the surveillance testing performed, prior to core alterations, for the Containment Purge and Pressure-Vacuum Relief isolation system did not confirm the manually initiated isolation function as required by Technical Specifications 4.9.9.

SAFETY CONSEQUENCES AND IMPLICATIONS Administrative controls such as post outage valve lineup checks would likely have ensured that the valves were properly shut prior to power operations following an outage. Additionally, the monthly surveillance procedures did include position verification of the outside Containment Refueling Canal Supply and Discharge isolation valves (1SF22, 1SF36, 2SF22, and 2SF36). Thus there were no safety consequences associated with this condition since containment integrity would not have been affected in the unlikely event of an accident. Based on the above, the heal th and safety of the public were not affected.

NRC FORM 366A (4-95)

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' f><RC FORM 366A (4-95)

FACILITY NAME (1)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION DOCKET NUMBER (2) 05000 U.S. NUCLEAR REGULATORY COMMISSION YEAR LER NUMBER (6)

I SEQUENTIAL NUMBER IREVISION NUMBER 4 PAGE (3)

OF 4 Salem Generating Station Unit - 1 05000272 96 - 04 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

CORRECTIVE ACTIONS

1) A review is being performed to ensure that all containment isolation valves are included, as required, in the periodic position verification surveillance tests. This review will be complete prior to restart of the affected units.
2) 1WL190, 1WL191, 2WL190, and 2WL191 will be. added to the appropriate monthly surveillance procedures prior to the affected units' core reload.
3) 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 complete by December 31, 1997.

NRC FORM 366A (4-95)

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