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| | issue date = 11/19/1992 | | | issue date = 11/19/1992 |
| | title = LER 92-022-00:on 921027,controlled Shutdown from Mode 2 Commenced in Anticipation of Inability to Meet 72 H TS Time Requirement.Caused by Emergent Work Preventing Return of 12 Svc Water Header to Svc.Pipe Section replaced.W/921119 Ltr | | | title = LER 92-022-00:on 921027,controlled Shutdown from Mode 2 Commenced in Anticipation of Inability to Meet 72 H TS Time Requirement.Caused by Emergent Work Preventing Return of 12 Svc Water Header to Svc.Pipe Section replaced.W/921119 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:.. e Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:e |
| | .. PS~G Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038 |
| | . i Salem Generating Station November 19, 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-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 November 19, 1992 This Licensee Event requirements of the 50. 73 (a) (2) (i) (A). thirty (30) days of Report is being submitted pursuant to the Code of Federal Regulations lOCFR MJP:pc Distribution | | |
| ;9211300223 921130 S PDR ADOCK 05000272 PnP* This report is required to be issued within event discovery.
| | SALEM GENERATING STATION LICENSE NO. DPR-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR |
| Sincerely | | : 50. 73 (a) (2) (i) (A). This report is required to be issued within thirty (30) days of event discovery. |
| : yours, l{ttKJ-c. A Vondra *. General Manager -Salem Operations . i i2-ss NRC FORM 366 *U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 . ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD . COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). 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 (11 I DOCKET NUMBER 121 I PAGE 131 Salem Generating Station -Unit 1 o 1s1010101217 .I 2 J 1 OF 0 13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement
| | Sincerely yours, |
| : 3. 7 .* 4 .1. EVENT DATE (5) LER NUMBER (6) REPORT DATE 171 OTHER FACILITIES INVOLVED (81 MONTH DAV VEAR VEAR :::::::::::
| | *~.* |
| SEQUENTIAL
| | l{ttKJ- |
| ){ REVlSION MONTH DAV VEAR FAc;I LITY NAMES DOCKET NUMBERISI NUMBER NUMBER OJ5JOJOJOI I I 1 lo 217 9! 2 -I 2 l2 -ol 111 11 9 91 9 2 0 0 2 0 I 5 I 0 I 0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE OF 10 CFR §: (Chock on* or moro of th* following} | | : c. A Vondra General Manager - |
| (11) MODE 18) 2 20.402(bl 20.405(cl 50.73(1)(2)(ivl 73.71lbl I ---POWER 20.40611111 | | Salem Operations MJP:pc Distribution |
| )(i) 50.38(c)(1) 50.73(1l121M . 73.71(cl LEVEL ----1101 I I 20.405111(1 lliil 50.38lcll2l 50.7311112) (viii OTHER (Spocify in Abstroct --btJ(ow and in Text, NRC Form 20.406(1)(1 llilil x 60.73(1ll211il 60.7311112llviiillAI 366AI ,____ --20.40611111 | | ;9211300223 921130 es-2~asi rsr.~1 i2-ss PDR ADOCK 05000272 S PnP* |
| )(Iv) 50.731*ll2lliil 50.7l(1)(2llvliillBl --20.4061*111 llvl 50.7311112lliiil 50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M.. ,J. Pollack -LER Coordinator 610 19 313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 .*.;.*.*. | | |
| ...... * . ... , ..... ,.* ... , -:*:*:*:*
| | NRC FORM 366 *U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89) |
| MANUFAC-REPORTABLE | | ~ |
| ;.;.; *:*;.*;* *:*::*;-MANUFAC* REPORTABLE | | EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS |
| <:> ...... ,. . .... ,. *.*:* ... . ... *.;. CAUSE SYSTEM
| | . LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, .AND TO THE. PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE FACILITY NAME (11 Salem Generating Station - Unit 1 I |
| * COMPONENT TUR ER TO*NPRDS . ;.*.*.;. ;.; . CAUSE SYSTEM COMPONENT TUR ER TO NPRDS .;.*.;.* .. ,, ,',",', ;.: *:*. .*:* *.*.*.* . . * .. :*.* ;-;* .... ,',' ;:;: *.*: *.;. *:*; *.* .. *:* .... :.* . .... *.*. ;.;. *:*: . ;.; I I I I I I I ;.; :*:* .*.* :*.* *.*. I . I I I I . I I .... .::; :*:*=*=* *.*. *.;. ,:.; *.*. .;.* ;.;. ..... ;.;., ..... *.* . ., .. ,.; ...... *. *.*.:::-;.; | | OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| .... ; :-:*::*:*
| | DOCKET NUMBER 121 o 1s1010101217 .I 2 J 1 I PAGE 131 OF 0 13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement 3. 7.* 4 .1. |
| .;.;:.*. ,',' .; .. ;.; I . *.* .*.* ;*.**:.:.;.;*.* . f;.; .. *.* *.*. ;.;. *.* ..
| | EVENT DATE (5) LER NUMBER (6) REPORT DATE 171 OTHER FACILITIES INVOLVED (81 SEQUENTIAL MONTH DAV VEAR VEAR ::::::::::: NUMBER ){ REVlSION NUMBER MONTH DAV VEAR FAc;I LITY NAMES DOCKET NUMBERISI OJ5JOJOJOI I I 1 lo 217 9 2 9! 2 |
| * I I I 1-I I ........ ... **:*:::*:****
| | - 0 I 2 l2 - ol 0 111 11 9 91 2 0 I 5I0 I 0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Chock on* or moro of th* following} (11) |
| I I I I I I I :::: :::::::: :::::::: ?\ SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY* YEAR bi NO EXPECTED SUBMISSION n YES (If yos, EXPECTED SUBMISSION DATE} DATE (151 I I I ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space lines} (16) | | MODE 18) 2 20.402(bl 20.405(cl 50.73(1)(2)(ivl 73.71lbl I - |
| * On October 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination. | | POWER 20.40611111 )(i) 50.38(c)(1) 50.73(1l121M . 73.71(cl LEVEL - - - |
| The Unit was placed in Mode 2 on October. 24, 1992 for repair of a packing leak on the 12BF19 f eedwater valve. Although a Safety -Evaluation had documented the abs.ence | | 1101 I I 20.405111(1 lliil |
| | ~ |
| | 50.38lcll2l |
| | - 50.7311112) (viii OTHER (Spocify in Abstroct btJ(ow and in Text, NRC Form l l~l1l l l l l l lil l l l l 20.406(1)(1 llilil x 60.73(1ll211il 60.7311112llviiillAI 366AI 20.40611111 )(Iv) |
| | - 50.731*ll2lliil |
| | - 50.7l(1)(2llvliillBl |
| | ~ |
| | 20.4061*111 llvl |
| | - 50.7311112lliiil |
| | - 50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M.. ,J. Pollack - LER Coordinator 610 19 313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC- REPORTABLE ;.;.; *:*;.*;* *:*::*;- MANUFAC* REPORTABLE CAUSE SYSTEM |
| | * COMPONENT .;.*.*.;. . CAUSE SYSTEM COMPONENT ,',",', |
| | TUR ER TO*NPRDS TUR ER TO NPRDS *.*.*.*. .*.. :*.* ;-;* .... |
| | .*.* *.*. .... .::; :*:*=*=* |
| | I I I I I I I ;.; :*.* |
| | *.*. I .I I I I .I I *.;. ,:.; *.*. .;.* |
| | f;.; .. *.* |
| | I I I I 1- I I I I I I I I I :::: :::::::: :::::::: ?\ |
| | SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY* YEAR EXPECTED n YES (If yos, co~plot* EXPECTED SUBMISSION DATE} bi ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space typ~writttJn lines} (16) |
| | * NO SUBMISSION DATE (151 I I I On October 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet th~ 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination. The Unit was placed in Mode 2 on October. |
| | 24, 1992 for repair of a packing leak on the 12BF19 f eedwater regulati~g valve. Although a Safety -Evaluation had documented the abs.ence |
| * of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition. | | * of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition. |
| Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown. | | ~ |
| Repairs to the 12 Service Water header were completed at 0215 hours on October 29. Cooldown was secured prior . to entry into Mode 4 (Hot Shutdown). | | Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown. Repairs to the 12 Service Water header were completed at 0215 hours on October 29. Cooldown was secured prior .to entry into Mode 4 (Hot Shutdown). The root cause of this occurrence is "Other". |
| The root cause of this occurrence is "Other". As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint. | | As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint. |
| NRC Form 366 (6-J91 | | NRC Form 366 (6-J91 |
| -.e -' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION: | | |
| Westinghouse | | -.e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 2 of 3 PLANT AND SYSTEM IDENTIFICATION: |
| -Pressurized Water Reactor LER NUMBER 92-022-00 PAGE 2 of 3 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE: | | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx} |
| Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1. Event Date: 10/27/92 Report Date: 11/19/92 This report was initiated by Incident Report No *. 92-695. CONDITIONS PRIOR TO OCCURRENCE:- | | IDENTIFICATION OF OCCURRENCE: |
| | Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1. |
| | Event Date: 10/27/92 Report Date: 11/19/92 This report was initiated by Incident Report No *. 92-695. |
| | CONDITIONS PRIOR TO OCCURRENCE:- |
| Mode 2 {Startup) | | Mode 2 {Startup) |
| DESCRIPTION OF OCCURRENCE: | | DESCRIPTION OF OCCURRENCE: |
| On 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion. | | On Octob~r 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion. |
| The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from . recent ultrasonic examinations. | | The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from . |
| Although a Safety Evaluation had documented the absence of an immediate operability concern, management | | recent ultrasonic examinations. Although a Safety Evaluation had documented the absence of an immediate operability concern, management |
| *decided to replace the pipe section in the current plant condition. | | *decided to replace the pipe section in the current plant condition. |
| The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown. | | The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown. |
| . . LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 DESCRIPTION OF OCCURRENCE: (cont'd) LER NUMBER 92-022-00 PAGE 3 of 3 Repairs to the 12 Service Water header were completed at 0215 hours on | | |
| * October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown). | | . . LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 3 of 3 DESCRIPTION OF OCCURRENCE: (cont'd) |
| Plant heatup commenced at 0330 on October 29 and the Unit .was synchronized to the grid at 2316 on November 1, 1992. Technical Specification 3.7.4.1 states: "At least two independent service water loops shall be OPERABLE." Technical Specification 3.7.4.1 Action states: "With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours." APPARENT CAUSE OF OCCURRENCE: | | Repairs to the 12 Service Water header were completed at 0215 hours on |
| The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint. | | * October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown). Plant heatup commenced at 0330 on October 29 and the Unit |
| Consequently, the Unit entered Mode 3. ANALYSIS OF OCCURRENCE: | | .was synchronized to the grid at 2316 on November 1, 1992. |
| The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions. | | Technical Specification 3.7.4.1 states: |
| The redundant cooling capacity of this system, assuming a single failure, is . *consistent with the assumptions used in the accident analyses. | | "At least two independent service water loops shall be OPERABLE." |
| In this event,.the other SW loop remained available. | | Technical Specification 3.7.4.1 Action states: |
| The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th lOCFR 50. 73 (a) (2) (i) (A). CORRECTIVE ACTION: The Service Water pipe section was replaced and the system returned to service. MJP:pc SORC Mtg. 92-116 General Manager Salem Operations}} | | "With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours." |
| | APPARENT CAUSE OF OCCURRENCE: |
| | The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint. Consequently, the Unit entered Mode 3. |
| | ANALYSIS OF OCCURRENCE: |
| | The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is . |
| | *consistent with the assumptions used in the accident analyses. |
| | In this event,.the other SW loop remained available. The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th 10CFR |
| | : 50. 73 (a) (2) (i) (A). |
| | CORRECTIVE ACTION: |
| | The Service Water pipe section was replaced and the system returned to service. |
| | p{L;#~L General Manager ~ |
| | Salem Operations MJP:pc SORC Mtg. 92-116}} |
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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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e
.. PS~G Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038
. i Salem Generating Station November 19, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR
- 50. 73 (a) (2) (i) (A). This report is required to be issued within thirty (30) days of event discovery.
Sincerely yours,
l{ttKJ-
- c. A Vondra General Manager -
Salem Operations MJP:pc Distribution
- 9211300223 921130 es-2~asi rsr.~1 i2-ss PDR ADOCK 05000272 S PnP*
NRC FORM 366 *U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89)
~
EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS
. LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, .AND TO THE. PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE FACILITY NAME (11 Salem Generating Station - Unit 1 I
OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
DOCKET NUMBER 121 o 1s1010101217 .I 2 J 1 I PAGE 131 OF 0 13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement 3. 7.* 4 .1.
EVENT DATE (5) LER NUMBER (6) REPORT DATE 171 OTHER FACILITIES INVOLVED (81 SEQUENTIAL MONTH DAV VEAR VEAR ::::::::::: NUMBER ){ REVlSION NUMBER MONTH DAV VEAR FAc;I LITY NAMES DOCKET NUMBERISI OJ5JOJOJOI I I 1 lo 217 9 2 9! 2
- 0 I 2 l2 - ol 0 111 11 9 91 2 0 I 5I0 I 0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Chock on* or moro of th* following} (11)
MODE 18) 2 20.402(bl 20.405(cl 50.73(1)(2)(ivl 73.71lbl I -
POWER 20.40611111 )(i) 50.38(c)(1) 50.73(1l121M . 73.71(cl LEVEL - - -
1101 I I 20.405111(1 lliil
~
50.38lcll2l
- 50.7311112) (viii OTHER (Spocify in Abstroct btJ(ow and in Text, NRC Form l l~l1l l l l l l lil l l l l 20.406(1)(1 llilil x 60.73(1ll211il 60.7311112llviiillAI 366AI 20.40611111 )(Iv)
- 50.731*ll2lliil
- 50.7l(1)(2llvliillBl
~
20.4061*111 llvl
- 50.7311112lliiil
- 50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M.. ,J. Pollack - LER Coordinator 610 19 313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC- REPORTABLE ;.;.; *:*;.*;* *:*::*;- MANUFAC* REPORTABLE CAUSE SYSTEM
- COMPONENT .;.*.*.;. . CAUSE SYSTEM COMPONENT ,',",',
TUR ER TO*NPRDS TUR ER TO NPRDS *.*.*.*. .*.. :*.* ;-;* ....
.*.* *.*. .... .::; :*:*=*=*
I I I I I I I ;.; :*.*
- .*. I .I I I I .I I *.;. ,:.; *.*. .;.*
f;.; .. *.*
I I I I 1- I I I I I I I I I :::: :::::::: :::::::: ?\
SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY* YEAR EXPECTED n YES (If yos, co~plot* EXPECTED SUBMISSION DATE} bi ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space typ~writttJn lines} (16)
- NO SUBMISSION DATE (151 I I I On October 27, 1992 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet th~ 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination. The Unit was placed in Mode 2 on October.
24, 1992 for repair of a packing leak on the 12BF19 f eedwater regulati~g valve. Although a Safety -Evaluation had documented the abs.ence
- of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition.
~
Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours0.004 days <br />0.0961 hours <br />5.720899e-4 weeks <br />1.31653e-4 months <br /> on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown. Repairs to the 12 Service Water header were completed at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on October 29. Cooldown was secured prior .to entry into Mode 4 (Hot Shutdown). The root cause of this occurrence is "Other".
As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint.
NRC Form 366 (6-J91
-.e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 2 of 3 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1.
Event Date: 10/27/92 Report Date: 11/19/92 This report was initiated by Incident Report No *.92-695.
CONDITIONS PRIOR TO OCCURRENCE:-
Mode 2 {Startup)
DESCRIPTION OF OCCURRENCE:
On Octob~r 27, 1992 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion.
The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from .
recent ultrasonic examinations. Although a Safety Evaluation had documented the absence of an immediate operability concern, management
- decided to replace the pipe section in the current plant condition.
The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours0.004 days <br />0.0961 hours <br />5.720899e-4 weeks <br />1.31653e-4 months <br /> on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown.
. . LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 3 of 3 DESCRIPTION OF OCCURRENCE: (cont'd)
Repairs to the 12 Service Water header were completed at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on
- October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown). Plant heatup commenced at 0330 on October 29 and the Unit
.was synchronized to the grid at 2316 on November 1, 1992.
Technical Specification 3.7.4.1 states:
"At least two independent service water loops shall be OPERABLE."
Technical Specification 3.7.4.1 Action states:
"With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."
APPARENT CAUSE OF OCCURRENCE:
The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint. Consequently, the Unit entered Mode 3.
ANALYSIS OF OCCURRENCE:
The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is .
- consistent with the assumptions used in the accident analyses.
In this event,.the other SW loop remained available. The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th 10CFR
- 50. 73 (a) (2) (i) (A).
CORRECTIVE ACTION:
The Service Water pipe section was replaced and the system returned to service.
p{L;#~L General Manager ~
Salem Operations MJP:pc SORC Mtg.92-116