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{{#Wiki_filter:NRC FOJIM 3&&
{{#Wiki_filter:NRC FOJIM 3&&                                           U.S. NUCLEAR REGULATORY COMMISSION                               APPROVED BY OllB 110. 3150.0104
* 14-951 FACILITY IAllE 111 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LEH) (See reverse for required numbar of digit1/char11:t11rs for 111ch block) SALEM GENERATING STATION, UNIT 1 TITU 141 APPROVED BY OllB 110. 3150.0104 EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT:
* 14-951                                                                                                                              EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT: 51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY. FOllWAID COllllEllT1 IEllAllDlllll LICENSEE EVENT REPORT (LEH)                                            IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT.. F33I.
51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY.
U.S. 1UCW1 llEGULA11HIY CllMMISSIOI. WAIHllGTlll. DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141. OFFICE OF llAIAllEllEIT AID IUDGET, (See reverse for required numbar of                                WlllllllllOI. DC 21513.
FOllWAID COllllEllT1 IEllAllDlllll IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT .. F33I. U.S. 1UCW1 llEGULA11HIY CllMMISSIOI.
digit1/char11:t11rs for 111ch block)
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FACILITY IAllE 111                                                                                  DOCIET IUlllEI 121                                                 PAGE !JI SALEM GENERATING STATION, UNIT 1                                                                    05000272                                                        1 of 4 TITU 141 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151                     LER NUMBER 161                       REPORT DATE 171                           OTHER FACILITIES INVOLVED 181 llOITH       DAY     YEAI     YEAI   I     IEQUEITW.
DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141.
IUlllEI I IEYlllOI lllWEI llOITH     DAY   YEAI FAcanYIWE SALEM UNIT 2 DOCIET IUlllEI 05000311 FAcanYIAllE 08         22       96       96             023               00         09       20   96 OPERATING             N     THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1) (11)
OFFICE OF llAIAllEllEIT AID IUDGET, WlllllllllOI.
MODEl91                       20.22011111                           20.2203(1HZ11vl                 X 5D.73(1H2Jlil                                     50.7311H2HviiiJ POWER                         2D.2203(1K11                           2D.22D311K311il                       5D.73(1HZlliiJ                                 5D.7311H21W LEVEL 1101       000         20.220311HZllil                       20.2203(1K311iiJ                     50.73(1H2Jliii)                                 73.71 20.2203!1HZ11iil                       20.2203(11141                         5D.73(1HZJlivl 2D.22D311H211iiil                     5D.3&1cH11                           50.73(1H2Hvl 2D.2203(1H211ivl                       50.3&1cH21                           50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE                                                                                                       TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator                                                                         609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 11--~"-Ul-E~+-~n-ITE-ll~-+-~COllPO~-*-u~+--llA~IUF-A_CIU_U_*~+---*~_~_:_::_._E~~'>-~CA_*_E~+--n-ITE~ll~+--COllPG---*-u~-+--llA~*~_'_CTU~U-*---1~-*ri_a_:_=_~_E---11 SUPPLEMENTAL REPORT EXPECTED 1141                                                       EXPECTED                MONTH              DAY          YEAR YES                                                                                                             SUBMISSION Pf yes, complete EXPECTED SUBMISSION DATE).                                                                       DATE(151 ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161 On     August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval.                                                                                           This is a violation of Technical Specification 4.0.4.
DC 21513. DOCIET IUlllEI 121 05000272 PAGE !JI 1 of 4 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 llOITH DAY YEAI YEAI I IEQUEITW.
The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time.                                                                                       Corrective actions include submission of a License Change Request to revise the Technical Specifications.
I IEYlllOI IUlllEI lllWEI llOITH DAY DOCIET IUlllEI FAcanYIWE SALEM UNIT 2 YEAI 05000311 08 22 96 96 023 00 09 20 96 FAcanYIAllE OPERATING N THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1)
(11) MODEl91 20.22011111 20.2203(1HZ11vl X 5D.73(1H2Jlil 50.7311H2HviiiJ POWER 2D.2203(1K11 2D.22D311K311il 5D.73(1HZlliiJ 5D.7311H21W LEVEL 1101 000 20.220311HZllil 20.2203(1K311iiJ 50.73(1H2Jliii) 73.71 20.2203!1HZ11iil 20.2203(11141 5D.73(1HZJlivl 2D.22D311H211iiil 5D.3&1cH11 50.73(1H2Hvl 2D.2203(1H211ivl 50.3&1cH21 50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 SUPPLEMENTAL REPORT EXPECTED 1141 'YES Pf yes, complete EXPECTED SUBMISSION DATE). ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161 EXPECTED SUBMISSION DATE(151 MONTH DAY YEAR On August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval.
This is a violation of Technical Specification 4.0.4. The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time. Corrective actions include submission of a License Change Request to revise the Technical Specifications.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.
9609270155 960920 PDR ADOCK 05000272 S PDR IRC FORM 316 14*95)
9609270155 960920 PDR ADOCK 05000272 S                                 PDR IRC FORM 316 14*95)
* llRC FORM 3&&A 14-151 U.S. llUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1J DOCKET NUMBER 121 05000272 SALEM GENERATING STATION, UNIT 1 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse  
* llRC FORM 3&&A                                                                                                   U.S. llUCLEAR REGULATORY COMMISSION 14-151 LICENSEE EVENT REPORT (LER)
-Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}* LER NUMBER 161 YEAI I IEDUEITIAL I -* IU*EI 11111m11 2 96 -023 -00 *Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} CONDITIONS PRIOR TO OCCURRENCE PAGE 131 of At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
TEXT CONTINUATION FACILITY NAME (1J                                   DOCKET NUMBER 121       LER NUMBER 161              PAGE 131 05000272       YEAI I  IEDUEITIAL IU*EI      I -*
DESCRIPTION OF OCCURRENCE 4 On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs. Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function.
11111m11 2  of    4 SALEM GENERATING STATION, UNIT 1 96 -      023      -    00 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}*
However, some components cannot be adequately tested in a lower Mode or operating condition.
    *Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC}
Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications.
CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.
This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification.
DESCRIPTION OF OCCURRENCE On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs.
Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4. The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3. Therefore, entry into Mode 3 is necessary to test the valves. Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure.
Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function.                         However, some components cannot be adequately tested in a lower Mode or operating condition. Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications. This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification.
The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available.
Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4.         The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3.
Therefore, entry into Mode 3 is necessary to test the valves.                                                           Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure. The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available.
At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications.
At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications.
Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4. NRC FORM 366A (4-95) lllRC FORM 366A U.S. lllUCLEAR REGULATORY COMMISSIOlll FACILITY lllAME 111 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER 121 05000272 SALEM. GENERATING STATION, UNIT 1 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE LER IUMBER 161 PAGE 131 YEAI I 3 of 4 96 -023 00 The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5. PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements.
Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4.
The corrective actions were specific to the missed surveillance issues addressed in each LER. The identification of programmatic issues related to the Technical Specification requirement
*implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation.
SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4. In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began. During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained.
A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position.
Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2. Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected.
NRC FORM 366A (4-95)
NRC FORM 366A (4-95)
* llRC FORM 31i&A 14-151 -. . .. . FACILITY MAME 111 LICENSEE EVENT REPORT (LEH) TEXT CONTINUATION DOCKET llUMBER 121 05000272 SALEM GENERATING STATION, UNIT 1 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION U.S. llUCLEAR REGULATORY COMMISSIOll TEAi I LER llUMBER 161 IEQUEITIAl I IU*EI 96 .. 023 -* -00 PAGE 131 4 of 4 1. A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996. . *-_ . 2. Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP .. program was described previously in LER 311/96-008-00.
 
The TSSIP review is expected to be completed by December 31, 1997. 3. This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications.
lllRC FORM 366A                                                                                                  U.S. lllUCLEAR REGULATORY COMMISSIOlll
~51 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY lllAME 111                                  DOCKET NUMBER 121       LER IUMBER 161              PAGE 131 05000272       YEAI I                          3    of    4 SALEM. GENERATING STATION, UNIT 1 96 -      023          00 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5.
PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements. The corrective actions were specific to the missed surveillance issues addressed in each LER.
The identification of programmatic issues related to the Technical Specification requirement *implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation.
SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4.                                                    In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began.
During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained. A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position.                                            Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2.
Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected.
NRC FORM 366A (4-95)
* llRC FORM 31i&A                                                                                                    U.S. llUCLEAR REGULATORY COMMISSIOll 14-151
              .                                                    LICENSEE EVENT REPORT (LEH)
TEXT CONTINUATION FACILITY MAME 111                                    DOCKET llUMBER 121        LER llUMBER 161             PAGE 131 05000272        TEAi I  IEQUEITIAl IU*EI I          4    of    4 SALEM GENERATING STATION, UNIT 1                                                                        96 ..     023           00 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION
: 1.         A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996.                                                                                                     . *- _ .
: 2.         Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP ..
program was described previously in LER 311/96-008-00. The TSSIP review is expected to be completed by December 31, 1997.
: 3.         This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications.
NRC FORM 366A (4-95)}}
NRC FORM 366A (4-95)}}

Latest revision as of 05:27, 3 February 2020

LER 96-023-00:on 960822,review Identified Units Transitioned from Mode 4 to Mode 3 W/Msiv Surveillance Requirement 4.7.1.5 Not Met within Stated Surveillance Interval.Caused by Inadequate Review.Ts Surveillance Improvement Initiated
ML18102A420
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/20/1996
From: Hassler D
Public Service Enterprise Group
To:
Shared Package
ML18102A419 List:
References
LER-96-023-01, LER-96-23-1, NUDOCS 9609270155
Download: ML18102A420 (4)
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Text

NRC FOJIM 3&& U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OllB 110. 3150.0104

  • 14-951 EXPIRES D4/3D/H ESTlllATED 1U11DE1 PBI llDPlllSE 10 CIM'l.Y Wll1I lllS IUIDllOllY llFlllllUTIOI COwmDI llEllUEIT: 51.11 1111. llEPOllTBI LIJSOD WlllEI llE lllCOllPOlllTED m1D m LICBllllll P110CE1S Am FID IACI 10 llllUSTIIY. FOllWAID COllllEllT1 IEllAllDlllll LICENSEE EVENT REPORT (LEH) IUllDO ESTlllATE 10 THE lllFOllllllATIOI AID llECOllllS lllllGEMEIT lllAICH IT.. F33I.

U.S. 1UCW1 llEGULA11HIY CllMMISSIOI. WAIHllGTlll. DC 21555-llDDI, AID 10 THE Pll'lllWlllll llEDUCTIOI PllOJECT (315'"'1141. OFFICE OF llAIAllEllEIT AID IUDGET, (See reverse for required numbar of WlllllllllOI. DC 21513.

digit1/char11:t11rs for 111ch block)

FACILITY IAllE 111 DOCIET IUlllEI 121 PAGE !JI SALEM GENERATING STATION, UNIT 1 05000272 1 of 4 TITU 141 Surveillance For Main Steam Isolation Valves Not Performed Prior To Entry Into Mode 3 As Required By Technical Specifications EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 llOITH DAY YEAI YEAI I IEQUEITW.

IUlllEI I IEYlllOI lllWEI llOITH DAY YEAI FAcanYIWE SALEM UNIT 2 DOCIET IUlllEI 05000311 FAcanYIAllE 08 22 96 96 023 00 09 20 96 OPERATING N THIS REPORT IS SUBMITTED PURSUANT TD THE REQUIREMENTS OF 10 CFR I: (Checllon1armor1) (11)

MODEl91 20.22011111 20.2203(1HZ11vl X 5D.73(1H2Jlil 50.7311H2HviiiJ POWER 2D.2203(1K11 2D.22D311K311il 5D.73(1HZlliiJ 5D.7311H21W LEVEL 1101 000 20.220311HZllil 20.2203(1K311iiJ 50.73(1H2Jliii) 73.71 20.2203!1HZ11iil 20.2203(11141 5D.73(1HZJlivl 2D.22D311H211iiil 5D.3&1cH11 50.73(1H2Hvl 2D.2203(1H211ivl 50.3&1cH21 50.7311HZHviiJ LICENSEE CONTACT FOR THIS LER 1121 UllE TELEPHOIE IUl8El llodd1 Ano CMll Dennis V. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 11--~"-Ul-E~+-~n-ITE-ll~-+-~COllPO~-*-u~+--llA~IUF-A_CIU_U_*~+---*~_~_:_::_._E~~'>-~CA_*_E~+--n-ITE~ll~+--COllPG---*-u~-+--llA~*~_'_CTU~U-*---1~-*ri_a_:_=_~_E---11 SUPPLEMENTAL REPORT EXPECTED 1141 EXPECTED MONTH DAY YEAR YES SUBMISSION Pf yes, complete EXPECTED SUBMISSION DATE). DATE(151 ABSTRACT !Limit to 1400 spaces, i.11., 11pproximat11ly 151ingla-spac11d typawritten lines) 1161 On August 22, 1996, a review identified that Salem Units 1 and 2 have transitioned from Mode 4 to Mode 3 with Main Steam Isolation Valve Surveillance Requirement 4.7.1.5 not met within the stated surveillance interval. This is a violation of Technical Specification 4.0.4.

The cause of this occurrence was determined to be inadequate review of the original Technical Specification 4.7.1.5 as compared to the Westinghouse Standard Technical Specification 4.7.1.5 in existence at the time. Corrective actions include submission of a License Change Request to revise the Technical Specifications.

This event is reportable in accordance with 10 CFR 50.73(a) (2) (i) (B), any condition prohibited by the plant's Technical Specifications.

9609270155 960920 PDR ADOCK 05000272 S PDR IRC FORM 316 14*95)

  • llRC FORM 3&&A U.S. llUCLEAR REGULATORY COMMISSION 14-151 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1J DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 05000272 YEAI I IEDUEITIAL IU*EI I -*

11111m11 2 of 4 SALEM GENERATING STATION, UNIT 1 96 - 023 - 00 TEXT Of mare sp1c1 is required, use 1ddition1I copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Main Stearn/Main Stearn Isolation Valve {SB/V}*

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

CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.

DESCRIPTION OF OCCURRENCE On August 22, 1996, a review determined that Technical Specification Surveillance Requirement 4.7.1.5, Main Steam Isolation Valve (MSIV) Full Closure Time Test, had been performed in Mode 2. The surveillance requirement is applicable in Modes 1, 2 and 3. Entry into Mode 3, without the required surveillance completed, constitutes a violation of Technical Specification 4.0.4. The Technical Specifications do not include an exception to the provisions of Technical Specification 4.0.4 to allow entry into Modes 3 and 2 from Mode 4 for the MSIVs.

Technical Specifications normally require completion of the specified surveillance test within the stated periodicity to prove operability of a safety system or component before entry into a Mode or operational condition that requires the system or component to be operable and capable of performing its required function. However, some components cannot be adequately tested in a lower Mode or operating condition. Because of this, special provisions that allow entry into the applicable Mode (provided surveillances are promptly performed to verify operability) are inciuded in Technical Specifications. This is accomplished by a specific exemption to Technical Specification 4.0.4 in the applicable Technical Specification.

Main Steam Isolation Valve operability testing at Salem is a specific example of the need for a provision to exempt compliance with Technical Specification 4.0.4. The steam pressure needed to properly test the valves is not available in* Mode 4, but the valves are required to be operable in Modes 1, 2 and 3.

Therefore, entry into Mode 3 is necessary to test the valves. Section 10.3 of the UFSAR states that the surveillance test of the Main Stearn Isolation Valves is performed at or near 1000 psig steam pressure. The highest steam pressure available in Mode 4 is approximately 150 psig. Past practice at Salem has been to perform the test when in Mode 2 when adequate steam is available.

At present, Technical Specification 3/4.7.1.5 remains similar to its original wording which was based on Westinghouse Standard Technical Specifications.

Salem Specification 4.7.1.5, like the Standard Technical Specification, does not provide an exemption to Specification 4.0.4.

NRC FORM 366A (4-95)

lllRC FORM 366A U.S. lllUCLEAR REGULATORY COMMISSIOlll

~51 LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY lllAME 111 DOCKET NUMBER 121 LER IUMBER 161 PAGE 131 05000272 YEAI I 3 of 4 SALEM. GENERATING STATION, UNIT 1 96 - 023 00 TEXT Pf mor111p1ce is required, use 1ddition1I copi111 of NRC Form 3&&AJ 1171 CAUSE OF OCCURRENCE The cause of this occurrence was determined to be a less than adequate review of the original Technical Specification with regard to differences from the Westinghouse Standard Technical Specifications and subsequent inadequate interpretation of Technical Specification 4.7.1.5.

PRIOR' SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last .two years identified seven LERs (272/94-008, 272/95-004, 272/95-019, 272/95-028, 311/95-006, 311/95-008, .and 272/96-016) that were a result of missed surveillances due to inadequate implementation of Technical Specification requirements. The corrective actions were specific to the missed surveillance issues addressed in each LER.

The identification of programmatic issues related to the Technical Specification requirement *implementation resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER 311/95-008. The TSSIP should ensure that Technical Specification surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Conditions for Operation.

SAFETY CONSEQUENCES AND IMPLICATIONS Although entry into Modes 3 and 2 is prohibited when the MSIV testing required by Technical Specification 4.7.1.5 had not been performed, subsequent performance of MSIV testing in Mode 2 is within the currently analyzed plant operation as discussed in UFSAR Sections 10.3 and 15.4. In the occurrences described in which Specification 4.0.4 was not met, while the Unit was in Modes 2 or 3, all of the MSIVs remained closed until testing began.

During testing, only one valve is opened at any time, the other three valves remaining closed, already in the safe position, thus, had* a postulated steam line break or secondary system malfunction occurred that resulted in depressurization, isolation capability would have been maintained. A postulated failure of the tested valve in the open position would have resulted in the blowdown of only a single steam generator since the remaining three MSIVs would have been in the closed position. Failure of a single MSIV to close is consistent with the accident assumptions presented in UFSAR Section 15.4.2.

Therefore, there was no safety significance to the improper entry into Modes 3 and 2, and the health and safety of the public remained unaffected.

NRC FORM 366A (4-95)

  • llRC FORM 31i&A U.S. llUCLEAR REGULATORY COMMISSIOll 14-151

. LICENSEE EVENT REPORT (LEH)

TEXT CONTINUATION FACILITY MAME 111 DOCKET llUMBER 121 LER llUMBER 161 PAGE 131 05000272 TEAi I IEQUEITIAl IU*EI I 4 of 4 SALEM GENERATING STATION, UNIT 1 96 .. 023 00 TEXT Pf mar111p1c11 is required, use 1dditian1I copies of NRC Form 366AI 1171 CORRECTIVE ACTION

1. A License Change Request to include an exemption to the provisions of Specification 4.0.4 in Technical Specification 4.7.1.5 will be submitted to the NRC by October 4, 1996. . *- _ .
2. Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP ..

program was described previously in LER 311/96-008-00. The TSSIP review is expected to be completed by December 31, 1997.

3. This LER will be issued to the Operations Department as required reading by September 30, 1996, to further emphasize the conservative understanding and implementation of Technical Specifications.

NRC FORM 366A (4-95)

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