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| | issue date = 02/06/1992 | | | issue date = 02/06/1992 |
| | title = LER 92-001-00:on 920107 & 28,SG Blowdown Outlet Isolation Valve Failed to Close.Caused by Dried & Torn Section of Valve Actuator Rubber Diaphragm.Subj Diaphragms Were Replaced.Valves Stroked successfully.W/920206 Ltr | | | title = LER 92-001-00:on 920107 & 28,SG Blowdown Outlet Isolation Valve Failed to Close.Caused by Dried & Torn Section of Valve Actuator Rubber Diaphragm.Subj Diaphragms Were Replaced.Valves Stroked successfully.W/920206 Ltr |
| | author name = POLLACK M J, VONDRA C A | | | author name = Pollack M, Vondra 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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| {{#Wiki_filter:( ., j \ PSECJ9 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:( ., j \ |
| | PSECJ9 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 6, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-001-00 February 6, 1992 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a} (2) (iv}. This report is required to be issued within thirty (30) days of event discovery.
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| MJP:pc Distribution 920206 S ADOCK 05000272 PDR The Energy People ,-. 0-l r. 8 J_ u ... _, Sincerely yours, C. A Vondra General Manager -Salem Operations 95-2189 (10M) 12-89 NRC FORM 366 16-89) e U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104
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| * EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LERI IMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH CP-5301, U.S. NUCLEAR REGULATORY COMMISSION.
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| WASHINGTON.
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| DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME Ill I DOCKET NUMBER 12) I PAGE 13) Salem Generating Station -Unit 1 0 I 5 I 0 I 0 I 0 I 2 I 7 12 1 I OF 0 I 4 \ TITLE 141 I ESF Component Actuation:
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| 12GB4 (Cont. Isol. Valve) Failed Closed Twice Due To Equip.
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| EVENT DATE 15) LER NUMBER 16) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR ;}}::SEQUENTIAL!::;:;:;:;
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| REVISION MONTH <*:*:*:*:*
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| NUMBER f:'.:'.:'.:'.:
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| NUMBER DAY YEAR FACILITY NAMES DOCKET NUMBERIS) o 11 ol 7 9 2 912 -o lo I 1 -o Io ol 2 o I 6 9 I 2 OPERATING MODE (9) 1 THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR §: (Ch*ck one or more of the following)
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| (11) 20.402(b) 20.406(c) x 50.73(1)(2l(iv) 73.7llb) -,_ ,__ 20.406(*111
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| )(I) 50.311(cl(1) 50.73(11(2)(¥)
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| 73.71(c) -....._ ,__ 20.406(*)(111111 50.38(cl(2) 50.73(*H2Hviil OTHER (Spocify in Abstract -....._ ,__ below and in TBxt, NRC Form POWER I LEVEL ,__ 1101 l JO I 0 20.406(*)(1
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| )(iii) 60.73(1)(211il 50.73(*)(2)(viiil(A) 366A) -.__ 20.406(*)(1 llM 60.73(*)(2)(ii) 60.73(*)(2)(viii)(B)
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| -.__ 20.408(*)(1 IM 60.73(*l!211iiil 50.73(*1(2l!xl LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 6 I o 19 3 I 3 19 I I 2 lo l 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED JN THIS REPORT (131 CAUSE SYSTEM COMPONENT MANUFAC* TUR ER MANUFAC* TUR ER B JIM r1s1v1 M 11 I 210 y I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR n YES (If comp/et* EXPECTED SUBMISSION DA TE) EXPECTED SUBMISSION DATE 1151 I I I ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen singltJ*SJ111Ce typewritten lines) (18) On 1/7/92, the No. 12 Steam Generator (S/G) Blowdown Outlet Isolation Valve (12GB4) (a Containment Isolation Valve) failed closed. Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure. Inspection of the 1/7/92 failed diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated S/G Blowdown pipe. On 1/8/92, the valve was returned to service. On 1/28/92, the 12GB4 again failed closed. Investigation revealed that the valve actuator's diaphragm again had failed. Inspection revealed that it tore at the same approximate section .as the diaphragm which failed on 1/7/92; however, the diaphragm had not dried. The cause of the 12GB4 valve closure events is equipment failure. A contributing factor to the cause of the 1/7/92 diaphragm failure was premature aging of the diaphragm caused by the prior removal of piping insulation adjacent to the valve actuator.
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| The 1/28/92 valve actuator diaphragm failure was not caused by premature aging. Testing of this failed diaphragm has been initiated to determine why it failed. Assessment of the contributing factors to the 12GB4 valve actuator diaphragm failures is continuing.
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| A review of the maintenance history of the 11-14GB4 valves has been initiated.
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| A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique.
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| NRC Farm 366 (6-89)
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| *
| | SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-001-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a} (2) (iv}. This report is required to be issued within thirty (30) days of event discovery. |
| -------------------- | | Sincerely yours, C. A Vondra General Manager - |
| -------*--- | | Salem Operations MJP:pc Distribution |
| ----------- | | ~gR02ll0267 920206 S ADOCK 05000272 PDR The Energy People |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER LER NUMBER PAGE | | ~ |
| __________ | | J_ u,-. 0- l...r._, 8 95-2189 (10M) 12-89 |
| _____ | | |
| | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 16-89) e LICENSEE EVENT REPORT (LERI APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 IMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH CP-5301, U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| | FACILITY NAME Ill DOCKET NUMBER 12) I PAGE 13) |
| | Salem Generating Station - Unit 1 TITLE 141 I0 I 5 I 0 I 0 I 0 I 2 I 7 12 I 1 OF 0 I 4 \ |
| | I ESF Component Actuation: 12GB4 (Cont. Isol. Valve) Failed Closed Twice Due To Equip. Failu~' |
| | EVENT DATE 15) LER NUMBER 16) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| | MONTH DAY YEAR YEAR ;}}::SEQUENTIAL!::;:;:;:; REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERIS) |
| | <*:*:*:*:* NUMBER f:'.:'.:'.:'.: NUMBER o11 ol 7 9 2 912 - olo I1 - oIo ol 2 o I 6 9 I2 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR §: (Ch*ck one or more of the following) (11) |
| | MODE (9) |
| | POWER I 1 20.402(b) 20.406(*111 )(I) -- 20.406(c) 50.311(cl(1) |
| | ,_x 50.73(1)(2l(iv) 50.73(11(2)(¥) |
| | 73.7llb) 73.71(c) |
| | LEVEL 1101 l JO I 0 20.406(*)(111111 |
| | -- 50.38(cl(2) |
| | ....._ 50.73(*H2Hviil ,__ OTHER (Spocify in Abstract below and in TBxt, NRC Form 11111mr~11m1111~ |
| | 20.406(*)(1 )(iii) 60.73(1)(211il 50.73(*)(2)(viiil(A) 366A) 20.406(*)(1 llM 20.408(*)(1 IM - 60.73(*)(2)(ii) 60.73(*l!211iiil LICENSEE CONTACT FOR THIS LER (12) 60.73(*)(2)(viii)(B) 50.73(*1(2l!xl NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 I o 19 3 I 3 19 I ~ I 2 lo l 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED JN THIS REPORT (131 CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC* |
| | TUR ER TUR ER B JIM r1s1v1 M 11 I 210 y I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED n ~NO SUBMISSION DATE 1151 YES (If y~s, comp/et* EXPECTED SUBMISSION DA TE) I I I ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen singltJ*SJ111Ce typewritten lines) (18) |
| | On 1/7/92, the No. 12 Steam Generator (S/G) Blowdown Outlet Isolation Valve (12GB4) (a Containment Isolation Valve) failed closed. |
| | Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure. |
| | Inspection of the 1/7/92 failed diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated S/G Blowdown pipe. On 1/8/92, the valve was returned to service. On 1/28/92, the 12GB4 again failed closed. |
| | Investigation revealed that the valve actuator's diaphragm again had failed. Inspection revealed that it tore at the same approximate section .as the diaphragm which failed on 1/7/92; however, the diaphragm had not dried. The cause of the 12GB4 valve closure events is equipment failure. A contributing factor to the cause of the 1/7/92 diaphragm failure was premature aging of the diaphragm caused by the prior removal of piping insulation adjacent to the valve actuator. The 1/28/92 valve actuator diaphragm failure was not caused by premature aging. Testing of this failed diaphragm has been initiated to determine why it failed. Assessment of the contributing factors to the 12GB4 valve actuator diaphragm failures is continuing. A review of the maintenance history of the 11-14GB4 valves has been initiated. A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique. |
| | NRC Farm 366 (6-89) |
| | |
| | --1~. ~------------- |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5_Q_Q_Q_~7-~__________ 9_~_-:-_Q_Q_!_-:-_Q_Q _____ ------~-_(?~--~-- |
| PLANT AND SYSTEM IDENTIFICATION: | | PLANT AND SYSTEM IDENTIFICATION: |
| Westinghouse | | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS} codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE: |
| -Pressurized Water Reactor Energy Industry Identification System (EIIS} codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE: | | Engineered Safety Feature equipment operation; Containment Isolation Valve 12GB4 failed closed twice Event Dates: 1/7/92 and 1/28/92 Report Date: 2/6/92 This report was initiated by Incident Report No(s). 92-015 and 92-064. |
| Engineered Safety Feature equipment operation; Containment Isolation Valve 12GB4 failed closed twice Event Dates: 1/7/92 and 1/28/92 Report Date: 2/6/92 This report was initiated by Incident Report No(s). 92-015 and 92-064. CONDITIONS PRIOR TO OCCURRENCE: | | CONDITIONS PRIOR TO OCCURRENCE: |
| January 7, 1992 January 28, 1992 Mode 1 Mode 1 DESCRIPTION OF Reactor Power 100% -Unit Load 1160 MWe Reactor Power 90% -Unit Load 1000 MWe On January 7, 1992, at 0935 hours, the No. 12 Steam Generator Blowdown Outlet Isolation Valve (12GB4) {WI} failed closed. The 12GB4 valve is a Masoneillan International air operated globe valve (model number 38-20761). | | January 7, 1992 Mode 1 Reactor Power 100% - Unit Load 1160 MWe January 28, 1992 Mode 1 Reactor Power 90% - Unit Load 1000 MWe DESCRIPTION OF OCCURRENC~: |
| It takes air to open and is spring loaded to fail close. Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure. Inspection of the diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated Steam Generator Blowdown pipe. On January 8, 1992, the valve was returned to service after actuator diaphragm replacement and successful functional testing. On January 28, 1992 at 0910 hours, the 12GB4 again failed closed. Investigation revealed that the valve actuator's diaphragm had failed, resulting in closure of the valve. Inspection revealed that it tore at the same approximate section as the diaphragm which failed on January 7, 1992; however, the diaphragm had not dried. It appeared to retain its resiliency. | | On January 7, 1992, at 0935 hours, the No. 12 Steam Generator Blowdown Outlet Isolation Valve (12GB4) {WI} failed closed. The 12GB4 valve is a Masoneillan International air operated globe valve (model number 38-20761). It takes air to open and is spring loaded to fail close. |
| The 12GB4 valve is a Containment Isolation Valve {JM}. Containment isolation is an Engineered Safety Feature (ESF}. Therefore, on January 7, 1992 at 1140 hours and on January 28, 1992 at 1051 hours, respectively, the Nuclear Regulatory Commission (NRC) was notified of the 12GB4 valve closures, in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii). APPARENT CAUSE OF OCCURRENCE: | | Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure. |
| The cause of the 12GB4 valve closure events is equipment failure. In LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE 92-0_01-QQ__ | | Inspection of the diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated Steam Generator Blowdown pipe. |
| __ 3 APPARENT CAUSE OF OCCURRENCE: (cont'd) both cases, the valve actuator diaphragm had failed resulting in air leakage and eventual valve closure. A contributing factor to the cause of the January 7, 1992 diaphragm failure was premature aging of the diaphragm caused by the prior removal of insulation on Steam Generator Blowdown piping adjacent to the valve actuator (located a few inches from the valve). The valve actuator diaphragm had dried and failed on the part of the diaphragm closest to the uninsulated pipe. The valve is located in a cramped area approximately 8' off the floor in the Mechanical Penetration Area. The actuator is behind the valve, away from the open work area. The January 28, 1992 valve actuator diaphragm failure was not caused by premature aging, as was the January 7th event. The diaphragm, although found torn in the same location as the January 7th diaphragm failure, was not dry (its resiliency was still intact). Testing of this failed diaphragm has been initiated to determine why it failed. System Engineering has initiated a review of the failure history of the GB4 valves. The 12GB4 valve actuator diaphragm had failed previously on August 23, 1991 (reference LER 272/91-028-00).
| | On January 8, 1992, the valve was returned to service after actuator diaphragm replacement and successful functional testing. |
| That failure was also attributed to equipment failure. Review of the 12GB4 Work Order history identified another failed valve actuator diaphragm (which was replaced} | | On January 28, 1992 at 0910 hours, the 12GB4 again failed closed. |
| in June 1990. ANALYSIS OF OCCURRENCE: | | Investigation revealed that the valve actuator's diaphragm had failed, resulting in closure of the valve. Inspection revealed that it tore at the same approximate section as the diaphragm which failed on January 7, 1992; however, the diaphragm had not dried. It appeared to retain its resiliency. |
| The ll-14GB4 valves isolate Steam Generator blowdown in support of normal operations. | | The 12GB4 valve is a Containment Isolation Valve {JM}. Containment isolation is an Engineered Safety Feature (ESF}. Therefore, on January 7, 1992 at 1140 hours and on January 28, 1992 at 1051 hours, respectively, the Nuclear Regulatory Commission (NRC) was notified of the 12GB4 valve closures, in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii). |
| They also function as containment isolation valves. The operability.of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. | | APPARENT CAUSE OF OCCURRENCE: |
| In these two (2) events, the 12GB4 valve failed to the safe configuration, as per design. Therefore, there was no affect on the health or safety of the public. However, since containment isolation is an ESF function, the two (2) 12GB4 valve inadvertent closures is reportable in accordance with Code of Federal Regulations lOCFR 50. 73(a) (2) (iv). CORRECTIVE ACTION: The 12GB4 valve actuator diaphragms were replaced and the valve stroked successfully on January 8, 1992 and January 29, 1992, respectively. | | The cause of the 12GB4 valve closure events is equipment failure. In |
| The valve was then returned to service after each repair. The uninsulated section of blowdown piping, adjacent to the valve actuator, has been reinsulated. | | |
| Investigation as to the removal of the adjacent pipe insulation is continuing. | | LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE |
| -LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE CORRECTIVE ACTION: (cont'd) A faiiure analysis of the January 28, 1992 failed valve actuator diaphragm has been initiated.
| | ~U=n=i~t~l"-~~~~~~~~~~~~~~5000272 92-0_01-QQ__ _ _ 3 o_L_~-- |
| | APPARENT CAUSE OF OCCURRENCE: (cont'd) both cases, the valve actuator diaphragm had failed resulting in air leakage and eventual valve closure. |
| | A contributing factor to the cause of the January 7, 1992 diaphragm failure was premature aging of the diaphragm caused by the prior removal of insulation on Steam Generator Blowdown piping adjacent to the valve actuator (located a few inches from the valve). The valve actuator diaphragm had dried and failed on the part of the diaphragm closest to the uninsulated pipe. The valve is located in a cramped area approximately 8' off the floor in the Mechanical Penetration Area. The actuator is behind the valve, away from the open work area. |
| | The January 28, 1992 valve actuator diaphragm failure was not caused by premature aging, as was the January 7th event. The diaphragm, although found torn in the same location as the January 7th diaphragm failure, was not dry (its resiliency was still intact). |
| | Testing of this failed diaphragm has been initiated to determine why it failed. |
| | System Engineering has initiated a review of the failure history of the GB4 valves. The 12GB4 valve actuator diaphragm had failed previously on August 23, 1991 (reference LER 272/91-028-00). That failure was also attributed to equipment failure. Review of the 12GB4 Work Order history identified another failed valve actuator diaphragm (which was replaced} in June 1990. |
| | ANALYSIS OF OCCURRENCE: |
| | The ll-14GB4 valves isolate Steam Generator blowdown in support of normal operations. They also function as containment isolation valves. The operability.of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. |
| | In these two (2) events, the 12GB4 valve failed to the safe configuration, as per design. Therefore, there was no affect on the health or safety of the public. However, since containment isolation is an ESF function, the two (2) 12GB4 valve inadvertent closures is reportable in accordance with Code of Federal Regulations 10CFR |
| | : 50. 73(a) (2) (iv). |
| | CORRECTIVE ACTION: |
| | The 12GB4 valve actuator diaphragms were replaced and the valve stroked successfully on January 8, 1992 and January 29, 1992, respectively. The valve was then returned to service after each repair. |
| | The uninsulated section of blowdown piping, adjacent to the valve actuator, has been reinsulated. Investigation as to the removal of the adjacent pipe insulation is continuing. |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE U-"-=n=i~t-=1~~~~~~~~~~~~~~~5~0~0~0=2=7-=--=2~~~~~~9.2-001-0_0~~~-4_o~f~4-CORRECTIVE ACTION: (cont'd) |
| | A faiiure analysis of the January 28, 1992 failed valve actuator diaphragm has been initiated. |
| System Engineering is continuing its assessment as to the contributing factors to the 12GB4 valve actuator diaphragm failures. | | System Engineering is continuing its assessment as to the contributing factors to the 12GB4 valve actuator diaphragm failures. |
| Upon completion, additional corrective action will be taken as appropriate. | | Upon completion, additional corrective action will be taken as appropriate. |
| As stated previously, a review of the maintenance history {1987 to present) of the 11-14GB4 valves has been initiated. | | As stated previously, a review of the maintenance history {1987 to present) of the 11-14GB4 valves has been initiated. The 12GB4 valve actuator diaphragm had been replaced in August 1991 {reference LER 272/91-028-00) and June 1990 in addition to the two (2) recent events. The 13GB4 valve actuator diaphragm was replaced on January 8, 1991 and again on February 6, 1991. The 11GB4 and 14GB4 valve diaphragms have not been replaced beyond preventive maintenance requirements which include valve actuator maintenance every four (4) years. |
| The 12GB4 valve actuator diaphragm had been replaced in August 1991 {reference LER 272/91-028-00) and June 1990 in addition to the two (2) recent events. The 13GB4 valve actuator diaphragm was replaced on January 8, 1991 and again on February 6, 1991. The 11GB4 and 14GB4 valve diaphragms have not been replaced beyond preventive maintenance requirements which include valve actuator maintenance every four (4) years. A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique and administrative controls. | | A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique and administrative controls. |
| MJP:pc SORC Mtg. 92-014}} | | MJP:pc SORC Mtg. 92-014}} |
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Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:RO)
MONTHYEARML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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PSECJ9 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 6, 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-001-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a} (2) (iv}. This report is required to be issued within thirty (30) days of event discovery.
Sincerely yours, C. A Vondra General Manager -
Salem Operations MJP:pc Distribution
~gR02ll0267 920206 S ADOCK 05000272 PDR The Energy People
~
J_ u,-. 0- l...r._, 8 95-2189 (10M) 12-89
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 16-89) e LICENSEE EVENT REPORT (LERI APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 IMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH CP-5301, U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME Ill DOCKET NUMBER 12) I PAGE 13)
Salem Generating Station - Unit 1 TITLE 141 I0 I 5 I 0 I 0 I 0 I 2 I 7 12 I 1 OF 0 I 4 \
I ESF Component Actuation: 12GB4 (Cont. Isol. Valve) Failed Closed Twice Due To Equip. Failu~'
EVENT DATE 15) LER NUMBER 16) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR ;::SEQUENTIAL!::;:;:;:; REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERIS)
<*:*:*:*:* NUMBER f:'.:'.:'.:'.: NUMBER o11 ol 7 9 2 912 - olo I1 - oIo ol 2 o I 6 9 I2 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rl:QUIREMENTS OF 10 CFR §: (Ch*ck one or more of the following) (11)
MODE (9)
POWER I 1 20.402(b) 20.406(*111 )(I) -- 20.406(c) 50.311(cl(1)
,_x 50.73(1)(2l(iv) 50.73(11(2)(¥)
73.7llb) 73.71(c)
LEVEL 1101 l JO I 0 20.406(*)(111111
-- 50.38(cl(2)
....._ 50.73(*H2Hviil ,__ OTHER (Spocify in Abstract below and in TBxt, NRC Form 11111mr~11m1111~
20.406(*)(1 )(iii) 60.73(1)(211il 50.73(*)(2)(viiil(A) 366A) 20.406(*)(1 llM 20.408(*)(1 IM - 60.73(*)(2)(ii) 60.73(*l!211iiil LICENSEE CONTACT FOR THIS LER (12) 60.73(*)(2)(viii)(B) 50.73(*1(2l!xl NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 I o 19 3 I 3 19 I ~ I 2 lo l 2 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED JN THIS REPORT (131 CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC*
TUR ER TUR ER B JIM r1s1v1 M 11 I 210 y I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED n ~NO SUBMISSION DATE 1151 YES (If y~s, comp/et* EXPECTED SUBMISSION DA TE) I I I ABSTRACT (Limit to 1400 spacss, i.e., approximately fifteen singltJ*SJ111Ce typewritten lines) (18)
On 1/7/92, the No. 12 Steam Generator (S/G) Blowdown Outlet Isolation Valve (12GB4) (a Containment Isolation Valve) failed closed.
Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure.
Inspection of the 1/7/92 failed diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated S/G Blowdown pipe. On 1/8/92, the valve was returned to service. On 1/28/92, the 12GB4 again failed closed.
Investigation revealed that the valve actuator's diaphragm again had failed. Inspection revealed that it tore at the same approximate section .as the diaphragm which failed on 1/7/92; however, the diaphragm had not dried. The cause of the 12GB4 valve closure events is equipment failure. A contributing factor to the cause of the 1/7/92 diaphragm failure was premature aging of the diaphragm caused by the prior removal of piping insulation adjacent to the valve actuator. The 1/28/92 valve actuator diaphragm failure was not caused by premature aging. Testing of this failed diaphragm has been initiated to determine why it failed. Assessment of the contributing factors to the 12GB4 valve actuator diaphragm failures is continuing. A review of the maintenance history of the 11-14GB4 valves has been initiated. A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique.
NRC Farm 366 (6-89)
--1~. ~-------------
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5_Q_Q_Q_~7-~__________ 9_~_-:-_Q_Q_!_-:-_Q_Q _____ ------~-_(?~--~--
PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS} codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE:
Engineered Safety Feature equipment operation; Containment Isolation Valve 12GB4 failed closed twice Event Dates: 1/7/92 and 1/28/92 Report Date: 2/6/92 This report was initiated by Incident Report No(s). 92-015 and 92-064.
CONDITIONS PRIOR TO OCCURRENCE:
January 7, 1992 Mode 1 Reactor Power 100% - Unit Load 1160 MWe January 28, 1992 Mode 1 Reactor Power 90% - Unit Load 1000 MWe DESCRIPTION OF OCCURRENC~:
On January 7, 1992, at 0935 hours, the No. 12 Steam Generator Blowdown Outlet Isolation Valve (12GB4) {WI} failed closed. The 12GB4 valve is a Masoneillan International air operated globe valve (model number 38-20761). It takes air to open and is spring loaded to fail close.
Investigation showed that the valve actuator's rubber diaphragm had failed, resulting in air leakage and subsequent valve closure.
Inspection of the diaphragm revealed that a section of the diaphragm had dried and tore. The section that dried is located nearest to an uninsulated Steam Generator Blowdown pipe.
On January 8, 1992, the valve was returned to service after actuator diaphragm replacement and successful functional testing.
On January 28, 1992 at 0910 hours, the 12GB4 again failed closed.
Investigation revealed that the valve actuator's diaphragm had failed, resulting in closure of the valve. Inspection revealed that it tore at the same approximate section as the diaphragm which failed on January 7, 1992; however, the diaphragm had not dried. It appeared to retain its resiliency.
The 12GB4 valve is a Containment Isolation Valve {JM}. Containment isolation is an Engineered Safety Feature (ESF}. Therefore, on January 7, 1992 at 1140 hours and on January 28, 1992 at 1051 hours, respectively, the Nuclear Regulatory Commission (NRC) was notified of the 12GB4 valve closures, in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii).
APPARENT CAUSE OF OCCURRENCE:
The cause of the 12GB4 valve closure events is equipment failure. In
LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE
~U=n=i~t~l"-~~~~~~~~~~~~~~5000272 92-0_01-QQ__ _ _ 3 o_L_~--
APPARENT CAUSE OF OCCURRENCE: (cont'd) both cases, the valve actuator diaphragm had failed resulting in air leakage and eventual valve closure.
A contributing factor to the cause of the January 7, 1992 diaphragm failure was premature aging of the diaphragm caused by the prior removal of insulation on Steam Generator Blowdown piping adjacent to the valve actuator (located a few inches from the valve). The valve actuator diaphragm had dried and failed on the part of the diaphragm closest to the uninsulated pipe. The valve is located in a cramped area approximately 8' off the floor in the Mechanical Penetration Area. The actuator is behind the valve, away from the open work area.
The January 28, 1992 valve actuator diaphragm failure was not caused by premature aging, as was the January 7th event. The diaphragm, although found torn in the same location as the January 7th diaphragm failure, was not dry (its resiliency was still intact).
Testing of this failed diaphragm has been initiated to determine why it failed.
System Engineering has initiated a review of the failure history of the GB4 valves. The 12GB4 valve actuator diaphragm had failed previously on August 23, 1991 (reference LER 272/91-028-00). That failure was also attributed to equipment failure. Review of the 12GB4 Work Order history identified another failed valve actuator diaphragm (which was replaced} in June 1990.
ANALYSIS OF OCCURRENCE:
The ll-14GB4 valves isolate Steam Generator blowdown in support of normal operations. They also function as containment isolation valves. The operability.of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
In these two (2) events, the 12GB4 valve failed to the safe configuration, as per design. Therefore, there was no affect on the health or safety of the public. However, since containment isolation is an ESF function, the two (2) 12GB4 valve inadvertent closures is reportable in accordance with Code of Federal Regulations 10CFR
- 50. 73(a) (2) (iv).
CORRECTIVE ACTION:
The 12GB4 valve actuator diaphragms were replaced and the valve stroked successfully on January 8, 1992 and January 29, 1992, respectively. The valve was then returned to service after each repair.
The uninsulated section of blowdown piping, adjacent to the valve actuator, has been reinsulated. Investigation as to the removal of the adjacent pipe insulation is continuing.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE U-"-=n=i~t-=1~~~~~~~~~~~~~~~5~0~0~0=2=7-=--=2~~~~~~9.2-001-0_0~~~-4_o~f~4-CORRECTIVE ACTION: (cont'd)
A faiiure analysis of the January 28, 1992 failed valve actuator diaphragm has been initiated.
System Engineering is continuing its assessment as to the contributing factors to the 12GB4 valve actuator diaphragm failures.
Upon completion, additional corrective action will be taken as appropriate.
As stated previously, a review of the maintenance history {1987 to present) of the 11-14GB4 valves has been initiated. The 12GB4 valve actuator diaphragm had been replaced in August 1991 {reference LER 272/91-028-00) and June 1990 in addition to the two (2) recent events. The 13GB4 valve actuator diaphragm was replaced on January 8, 1991 and again on February 6, 1991. The 11GB4 and 14GB4 valve diaphragms have not been replaced beyond preventive maintenance requirements which include valve actuator maintenance every four (4) years.
A review has been initiated to determine the adequacy of the valve actuator diaphragm installation technique and administrative controls.
MJP:pc SORC Mtg. 92-014}}