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| | issue date = 05/12/1999 | | | issue date = 05/12/1999 |
| | title = 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 | | | title = 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 |
| | author name = GARCHOW D F, NAGLE J C | | | author name = Garchow D, Nagle J |
| | 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:Prjbfic Ser.vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen: | | {{#Wiki_filter:OPS~G Prjbfic Ser.vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit IAY 181999 LR-N990221 Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen: |
| IAY 181999 LR-N990221 LICENSEE EVENT REPORT 272199-002-00 SALEM GENERA TING STATION -UNIT 1 FACILITY OPERA TING LICENSE NO DPR 70 DOCKET NO. 50-272 This Licensee Event Report entitled "Auxiliary Building Ventilation Found Outside of Design" is being submitted in accordance with the requirements of 10CFR50.73 (a)(2)(ii)(B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;.
| | LICENSEE EVENT REPORT 272199-002-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO DPR 70 DOCKET NO. 50-272 This Licensee Event Report entitled "Auxiliary Building Ventilation Found Outside of Design" is being submitted in accordance with the requirements of 10CFR50.73 (a)(2)(ii)(B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;. or that resulted in the nuclear power plant being in a condition that was outsidethe design basis of the plant". |
| or that resulted in the nuclear power plant being in a condition that was outsidethe design basis of the plant". Attachment David F. Garcho General Manag -Salem Operations C U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 /JCN Distribution: | | David F. Garcho General Manag - |
| LER File 3.7 9905210035 990512 PDR ADOCK 05000272 S PDR The pu\rer is in your hands. 95*2168 REV. 6194 | | Salem Operations Attachment C U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
| --1 NRC F.ORM 366 U.S. NUCLEAR REGULATORY COMMISSION | | /JCN Distribution: |
| * (6-1998) LICENSEE EVENT REPORT (LER) (See reverse for required number of digits/characters for each block) APPROVED BY 011118 NO. 3150-0104 EXPIRES 06/30/2001 Estimated burden per response to comply with this mandatOI}'
| | LER File 3.7 9905210035 990512 PDR ADOCK 05000272 S PDR The pu\rer is in your hands. |
| information collection request 50 hm. Reported lessons learned are incorporated into the licensing process and fed back to industry. | | 95*2168 REV. 6194 |
| Forward comments regarding burden estimate to the t'tacords Management Branch (T-S F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-000.1, and to the Paperwork Reduction Project (3150-0104), Office of Management and Budget. Washington, DC 20503. 11' an infonnation collection does not display a currentty valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. . FACILITY NAME 111 DOCKET NUMBER (21 PAGE!31 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Auxiliary Ventilation Found Outsid.e of Desian EVENT DATE (S) MONTH DAY YEAR 04 13 OPERATING MODE(9) POWER LEVEL 101 NAME 99 100 LER NUMBER 161 | | |
| * REPORT DATE 171 OTHER FACILITIES INVOLVED 181 I SEQUENTIAL I REVISION YEAR NUMBER NUMBER MONTH DAY YEAR FACILITY NAME DQCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER 99 2 00 05 12 99 05000 TL-''" --"'"' ---n. *-* *---* --1111 20.2201 (bl 20.22031a)l2llvl | | --1 NRC F.ORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 011118 NO. 3150-0104 EXPIRES 06/30/2001 |
| : 50. 731all211il
| | * (6-1998) |
| : 50. 731all2llviii) 20.22031all1 l 20.22031a)l311il X 50. 73(a)(2l(ii)
| | Estimated burden per response to comply with this mandatOI}' information collection request 50 hm. Reported lessons learned are incorporated into the LICENSEE EVENT REPORT (LER) licensing process and fed back to industry. Forward comments regarding burden estimate to the t'tacords Management Branch (T-S F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-000.1, and to the Paperwork (See reverse for required number of Reduction Project (3150-0104), Office of Management and Budget. |
| : 50. 73(a)l21(x) 20.22031all2llil 20.22031all311iil
| | Washington, DC 20503. 11' an infonnation collection does not display a currentty digits/characters for each block) valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. . |
| : 50. 731all2lliiil
| | FACILITY NAME 111 DOCKET NUMBER (21 PAGE!31 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Auxiliary Buildin~ Ventilation Found Outsid.e of Desian EVENT DATE (S) LER NUMBER 161 |
| : 73. 71
| | * REPORT DATE 171 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME DQCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER 04 13 99 99 2 00 05 12 99 05000 TL-''" -- "'"' --- n. *-* *---* -- 1111 OPERATING MODE(9) 20.2201 (bl 20.22031a)l2llvl 50. 731all211il 50. 731all2llviii) |
| ____ -+-_.0THER 20.2203(all2lliiil 50.361cll1 I 50. 731al(2)1vl Specify in Abstract below 20.22031al(211ivl 50.361cll21
| | POWER 20.22031all1 l 20.22031a)l311il X 50. 73(a)(2l(ii) 50. 73(a)l21(x) |
| : 50. 731all2llviil or in NRC Form 366A LICENSEE CONTACT FOR THIS LER 1121 TELEPHONE NUMBER (Include Area Codel John C. NaQle Senior Licensina Enaineer 609-339-3171 rnMDI i:Ti: nu., 1 ,.,., p--p _,, REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX C:l IDlll -----*-A I 11A\ 'YES (If ves comolete EXPECTED SUBMISSION DATE). ....... ., CAUSE oo.o *LI*" DCDnDT l 1 '2\ REPORTABLE SYSTEM COMPONENT MANUFACTURER TO EPIX EXPECTED SUBMISSION DATE 1151 Mnl\lTM nAV ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 1161 On 04/13/99 at 2135, the Unit 1 auxiliary building was identified by the operators as being at a pressure of+0.03 inches of water with respect to the outdoors.
| | LEVEL 101 100 20.22031all2llil 20.22031all311iil 50. 731all2lliiil 73. 71 |
| The Updated Final Safety Report (UFSAR) Section 9.4.2.2.1 states that the auxiliary building is designed to be at a slight negative pressure continuously, with respect to the outdoors, to satisfy the criterion for preventing the uncontrolled release of radioactivity, therefore the plant was being operated outside of the design basis. Subsequent investigation determined that the #12 auxiliary building exhaust fan was rotating backwards.
| | -+"2~0=.2=2~0=3=(a~)(=2l~li=il-----i~+-20_.~2=20_3~11~all.*4~1-----+--+-5~0~.-73~1~al~l2~)~1iv~1>_ _ _ _-+-_.0THER 20.2203(all2lliiil 50.361cll1 I 50. 731al(2)1vl |
| Corrective maintenance activities had been performed on the prior day that required the motor leads to be disconnected.
| | -+""""";;..;;;.;;'-"-"='"'""'"'---+--+.;;..:.=='-'"'"'------+--+-=..:..:;"""""='"'-"'-----~ Specify in Abstract below 20.22031al(211ivl 50.361cll21 50. 731all2llviil or in NRC Form 366A LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER (Include Area Codel John C. NaQle Senior Licensina Enaineer 609-339-3171 rnMDI i:Ti: nu., 1 ,.,., p-- p_,, ........, oo.o *LI*" DCDnDT l 1 '2\ |
| The apparent cause is mis-wiring of the motor due to human error by the maintenance technician.
| | REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX C:l IDlll -----*-A I 11A\ Mnl\lTM nAV EXPECTED YES SUBMISSION (If ves comolete EXPECTED SUBMISSION DATE). DATE 1151 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 1161 On ' 04/13/99 at 2135, the Unit 1 auxiliary building was identified by the operators as being at a pressure of+0.03 inches of water with respect to the outdoors. The Updated Final Safety An~lysis Report (UFSAR) Section 9.4.2.2.1 states that the auxiliary building is designed to be at a slight negative pressure continuously, with respect to the outdoors, to satisfy the criterion for preventing the uncontrolled release of radioactivity, therefore the plant was being operated outside of the design basis. Subsequent investigation determined that the #12 auxiliary building exhaust fan was rotating backwards. Corrective maintenance activities had been performed on the prior day that required the motor leads to be disconnected. The apparent cause is mis-wiring of the motor due to human error by the maintenance technician. The mis-wired fan had been returned to service at 1337 on 04/13/99. The mis-wiring was corrected and the fan was returned to service at 1110 on 04/14/99 .. Tech Spec 3.7.7.1, which provides a seven day action statement, was in effect for the duration of the event. A 4-hour report was made to the NRC as requi*red by the plant's Emergency Classification Guide and 10CFR50. 72 (b) ( 1) (ii) . |
| The mis-wired fan had been returned to service at 1337 on 04/13/99.
| | This report is being made pursuant to 10CFR50. 73 (a) (2) (ii) (B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;. or that resulted in the nuclear power plant being in a condition that was outsiae the design basis of the plant;" |
| The mis-wiring was corrected and the fan was returned to service at 1110 on 04/14/99 .. Tech Spec 3.7.7.1, which provides a seven day action statement, was in effect for the duration of the event. A 4-hour report was made to the NRC as requi*red by the plant's Emergency Classification Guide and 10CFR50. 72 (b) ( 1) (ii) . This report is being made pursuant to 10CFR50. 73 (a) (2) (ii) (B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;.
| | NRC FORM 366 (6-1998) |
| or that resulted in the nuclear power plant being in a condition that was outsiae the design basis of the plant;" NRC FORM 366 (6-1998)
| | |
| NRC FORM 366A (6-19981 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 Salem Generating Station Unit 1 DOCKE:T 121 NUMBER 121 05000272 TEXT (If more space is required, use additional copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse | | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-19981 LICENSEE EVENT REPORT (LER) |
| -Pressurized Water *Reactor LER NUMBER 161 I SEQUENTIAL I REVISION YEAR NUMBER NUMBER 99 02 00 Auxiliary Building Environmental Control System/Fan
| | TEXT CONTINUATION DOCKE:T 121 FACILITY NAME 111 NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Generating Station Unit 1 05000272 99 02 00 2 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water *Reactor Auxiliary Building Environmental Control System/Fan {VF /FAN}** |
| {VF /FAN}** PAGE 131 2 OF 3
| | * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text. |
| * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text. CONDITIONS PRIOR TO OCCURRENCE The unit was operating at 100% power at the time of the event. DESCRIPTION OF OCCURRENCE Operations noted, on 4713/99 at approximately 2135 hours, that the Unit*l auxiliary building pressure was indicating
| | CONDITIONS PRIOR TO OCCURRENCE The unit was operating at 100% power at the time of the event. |
| +0.03 inches of water with respect to the outdoors.
| | DESCRIPTION OF OCCURRENCE Operations noted, on 4713/99 at approximately 2135 hours, that the Unit*l auxiliary building pressure was indicating +0.03 inches of water with respect to the outdoors. The design of the auxiliary building is for a continuous slight negative pressure with respect to the outdoors (UFSAR 9.4.). This design assures that there is no unfiltered unmonitored release of radioactivity to the environs. Upon investigation, it was determined that the |
| The design of the auxiliary building is for a continuous slight negative pressure with respect to the outdoors (UFSAR 9.4.). This design assures that there is no unfiltered unmonitored release of radioactivity to the environs. | | #12 auxiliary building exhaust fan was rotating backwards. A review.of work relative to this fan revealed that the fan was removed from service at 2216 hours on 4/12/99 for corrective maintenance activities on a the junction box. |
| Upon investigation, it was determined that the #12 auxiliary building exhaust fan was rotating backwards. | | The fan had been returned to service at 1337 hours on 04/13/99. A reverse rotating centrifugal fan is able to move air but at a reduced capacity thus the total capability of the two exhaust fans was less than that of the supply fan, resulting in a slight pressurization of the building, a condition outside of the design bases. |
| A review.of work relative to this fan revealed that the fan was removed from service at 2216 hours on 4/12/99 for corrective maintenance activities on a the junction box. The fan had been returned to service at 1337 hours on 04/13/99. | | The auxiliary building is equipped with a low differential pressure (DP) alarm which did not function during this event. Investigation determined that the associated actuating device was not providing consistent actuation prior to the event and has been removed from service for repairs. |
| A reverse rotating centrifugal fan is able to move air but at a reduced capacity thus the total capability of the two exhaust fans was less than that of the supply fan, resulting in a slight pressurization of the building, a condition outside of the design bases. The auxiliary building is equipped with a low differential pressure (DP) alarm which did not function during this event. Investigation determined that the associated actuating device was not providing consistent actuation prior to the event and has been removed from service for repairs. During an after-the-fact review of corrective action requests by licensing, the fact that this event had been mis-classified was noted and the shift was notified to make a report to the NRC as required by the plant's Emergency Classification Guide and 10CFR50.72(b) | | During an after-the-fact review of corrective action requests by licensing, the fact that this event had been mis-classified was noted and the shift was notified to make a 4~hour report to the NRC as required by the plant's Emergency Classification Guide and 10CFR50.72(b) (1) (ii) (B), which requires reporting when the plant is found, during operation, to be in a condition that is outside of the design basis. |
| (1) (ii) (B), which requires reporting when the plant is found, during operation, to be in a condition that is outside of the design basis. CAUSE OF OCCURRENCE The fan had been rewired incorrectly due to human error .during restoration from corrective maintenance activities. | | CAUSE OF OCCURRENCE The fan had been rewired incorrectly due to human error .during restoration from corrective maintenance activities. The independent verification associated with the activity also failed to identify the incorrect re-termination. |
| The independent verification associated with the activity also failed to identify the incorrect termination. | | NRC FORM 366A (6-19981 |
| NRC FORM 366A (6-19981 | | |
| . [NHC FORM 366A (6-1998) U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET (2) NUMBER 121 SALEM GENERATING STATION UNIT 1 05000272 TEXT (If more space is required, use additional copies of NRC Form 366AJ ( 17) PRIOR SIMILAR OCCURRENCES YEAR 99 LER NUMBER (6) PAGE (3) I I REVISION NUMBER NUMBER 02 00 3 OF 3 Over the past two years several examples of improper equipment restoration have been cited in both Licensee Event Reports and Inspection Reports for Salem Units 1 and 2. (Inspection Report 98-09 and LERs 272/98-005 Inoperability Of The 12 Fuel Oil Transfer Pump Due To Installation Of Incorrect Control Switch, 311/98-002 23 Over temperature Delta Temperature Channel Found Inoperable, 311/98-004 Failure to Comply With Technical Specification Surveillance Requirement 4.1.3.1.1, and 311/98-012 22 Auxiliary Feedwater. | | . [NHC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998) |
| Pump Inoperabili ty Caused By The Failure To Restore The Pump Runout Protection Pressure Transmitter To Service Following Calibration). | | LICENSEE EVENT REPORT (LER) |
| SAFETY CONSEQUENCES AND IMPLICATIONS The auxiliary building ventilation system consists of two 100% supply fans and three 50% capacity exhaust fans. During normal operation one supply and two exhaust fans are in operation with exhaust flow exceeding supply flow. The exhaust fan was able to provide a significant percentage of the design flow while rotating backward, as *is typical of centrifugal fans. However, due to the reduced exhaust capacity the auxiliary building was at a slight positive pressure relative to outdoors such that there was a potential for an unmonitored leakage pathway. During the short period that the fan was operating incorrectly the radiological conditions within the auxiliary building were acceptable (no airborne contamination) thus the likelihood of an unmonitored release was very low. In addition, continuous monitoring equipment was reviewed after the event and no increase in activity was noted for the time that the building was potentially pressurized.
| | TEXT CONTINUATION DOCKET (2) |
| If there had been an accident during the period of time that the fan was rotating backwards the safety significance would have been minimal because there was an additional exhaust fan available which would have started automatically, thus ensuring negative pressurization. | | FACILITY NAME (1) NUMBER 121 LER NUMBER (6) PAGE (3) |
| | YEAR ISEO~I_NTI I NUMBER REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 99 02 00 3 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366AJ ( 17) |
| | PRIOR SIMILAR OCCURRENCES Over the past two years several examples of improper equipment restoration have been cited in both Licensee Event Reports and Inspection Reports for Salem Units 1 and 2. (Inspection Report 98-09 and LERs 272/98-005 Inoperability Of The 12 Fuel Oil Transfer Pump Due To Installation Of Incorrect Control Switch, 311/98-002 23 Over temperature Delta Temperature Channel Found Inoperable, 311/98-004 Failure to Comply With Technical Specification Surveillance Requirement 4.1.3.1.1, and 311/98-012 22 Auxiliary Feedwater. Pump Inoperabili ty Caused By The Failure To Restore The Pump Runout Protection Pressure Transmitter To Service Following Calibration). |
| | SAFETY CONSEQUENCES AND IMPLICATIONS The auxiliary building ventilation system consists of two 100% supply fans and three 50% capacity exhaust fans. During normal operation one supply and two exhaust fans are in operation with exhaust flow exceeding supply flow. |
| | The exhaust fan was able to provide a significant percentage of the design flow while rotating backward, as *is typical of centrifugal fans. However, due to the reduced exhaust capacity the auxiliary building was at a slight positive pressure relative to outdoors such that there was a potential for an unmonitored leakage pathway. During the short period that the fan was operating incorrectly the radiological conditions within the auxiliary building were acceptable (no airborne contamination) thus the likelihood of an unmonitored release was very low. In addition, continuous monitoring equipment was reviewed after the event and no increase in activity was noted for the time that the building was potentially pressurized. If there had been an accident during the period of time that the fan was rotating backwards the safety significance would have been minimal because there was an additional exhaust fan available which would have started automatically, thus ensuring negative pressurization. |
| CORRECTIVE ACTIONS Personnel involved with the event have been held accountable consistent with Corporate Policies. | | CORRECTIVE ACTIONS Personnel involved with the event have been held accountable consistent with Corporate Policies. |
| Procedures are being modified to require the use of a phase rotation meter whenever equipment is electrically terminated. | | Procedures are being modified to require the use of a phase rotation meter whenever equipment is electrically terminated. These revisions will be completed by 06/30/99. |
| These revisions will be completed by 06/30/99. | | Although not a causal factor, the auxiliary building Low DP alarm is being repaired. The work is currently scheduled mid July. |
| Although not a causal factor, the auxiliary building Low DP alarm is being repaired. | | NRC FORM 366A (6-1998)}} |
| The work is currently scheduled mid July. NRC FORM 366A (6-1998)}} | |
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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
[Table view] |
Text
OPS~G Prjbfic Ser.vice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit IAY 181999 LR-N990221 Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Gentlemen:
LICENSEE EVENT REPORT 272199-002-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO DPR 70 DOCKET NO. 50-272 This Licensee Event Report entitled "Auxiliary Building Ventilation Found Outside of Design" is being submitted in accordance with the requirements of 10CFR50.73 (a)(2)(ii)(B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;. or that resulted in the nuclear power plant being in a condition that was outsidethe design basis of the plant".
David F. Garcho General Manag -
Salem Operations Attachment C U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
/JCN Distribution:
LER File 3.7 9905210035 990512 PDR ADOCK 05000272 S PDR The pu\rer is in your hands.
95*2168 REV. 6194
--1 NRC F.ORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 011118 NO. 3150-0104 EXPIRES 06/30/2001
Estimated burden per response to comply with this mandatOI}' information collection request 50 hm. Reported lessons learned are incorporated into the LICENSEE EVENT REPORT (LER) licensing process and fed back to industry. Forward comments regarding burden estimate to the t'tacords Management Branch (T-S F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-000.1, and to the Paperwork (See reverse for required number of Reduction Project (3150-0104), Office of Management and Budget.
Washington, DC 20503. 11' an infonnation collection does not display a currentty digits/characters for each block) valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. .
FACILITY NAME 111 DOCKET NUMBER (21 PAGE!31 SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE 141 Auxiliary Buildin~ Ventilation Found Outsid.e of Desian EVENT DATE (S) LER NUMBER 161
- REPORT DATE 171 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME DQCKET NUMBER 05000 FACILITY NAME DOCKET NUMBER 04 13 99 99 2 00 05 12 99 05000 TL-" -- "'"' --- n. *-* *---* -- 1111 OPERATING MODE(9) 20.2201 (bl 20.22031a)l2llvl 50. 731all211il 50. 731all2llviii)
POWER 20.22031all1 l 20.22031a)l311il X 50. 73(a)(2l(ii) 50. 73(a)l21(x)
LEVEL 101 100 20.22031all2llil 20.22031all311iil 50. 731all2lliiil 73. 71
-+"2~0=.2=2~0=3=(a~)(=2l~li=il-----i~+-20_.~2=20_3~11~all.*4~1-----+--+-5~0~.-73~1~al~l2~)~1iv~1>_ _ _ _-+-_.0THER 20.2203(all2lliiil 50.361cll1 I 50. 731al(2)1vl
-+""""";;..;;;.;;'-"-"='"'""'"'---+--+.;;..:.=='-'"'"'------+--+-=..:..:;"""""='"'-"'-----~ Specify in Abstract below 20.22031al(211ivl 50.361cll21 50. 731all2llviil or in NRC Form 366A LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER (Include Area Codel John C. NaQle Senior Licensina Enaineer 609-339-3171 rnMDI i:Ti: nu., 1 ,.,., p-- p_,, ........, oo.o *LI*" DCDnDT l 1 '2\
REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER TO EPIX C:l IDlll -----*-A I 11A\ Mnl\lTM nAV EXPECTED YES SUBMISSION (If ves comolete EXPECTED SUBMISSION DATE). DATE 1151 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 1161 On ' 04/13/99 at 2135, the Unit 1 auxiliary building was identified by the operators as being at a pressure of+0.03 inches of water with respect to the outdoors. The Updated Final Safety An~lysis Report (UFSAR) Section 9.4.2.2.1 states that the auxiliary building is designed to be at a slight negative pressure continuously, with respect to the outdoors, to satisfy the criterion for preventing the uncontrolled release of radioactivity, therefore the plant was being operated outside of the design basis. Subsequent investigation determined that the #12 auxiliary building exhaust fan was rotating backwards. Corrective maintenance activities had been performed on the prior day that required the motor leads to be disconnected. The apparent cause is mis-wiring of the motor due to human error by the maintenance technician. The mis-wired fan had been returned to service at 1337 on 04/13/99. The mis-wiring was corrected and the fan was returned to service at 1110 on 04/14/99 .. Tech Spec 3.7.7.1, which provides a seven day action statement, was in effect for the duration of the event. A 4-hour report was made to the NRC as requi*red by the plant's Emergency Classification Guide and 10CFR50. 72 (b) ( 1) (ii) .
This report is being made pursuant to 10CFR50. 73 (a) (2) (ii) (B) "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded;. or that resulted in the nuclear power plant being in a condition that was outsiae the design basis of the plant;"
NRC FORM 366 (6-1998)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-19981 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKE:T 121 FACILITY NAME 111 NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER Salem Generating Station Unit 1 05000272 99 02 00 2 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366AJ 1171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water *Reactor Auxiliary Building Environmental Control System/Fan {VF /FAN}**
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text.
CONDITIONS PRIOR TO OCCURRENCE The unit was operating at 100% power at the time of the event.
DESCRIPTION OF OCCURRENCE Operations noted, on 4713/99 at approximately 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br />, that the Unit*l auxiliary building pressure was indicating +0.03 inches of water with respect to the outdoors. The design of the auxiliary building is for a continuous slight negative pressure with respect to the outdoors (UFSAR 9.4.). This design assures that there is no unfiltered unmonitored release of radioactivity to the environs. Upon investigation, it was determined that the
- 12 auxiliary building exhaust fan was rotating backwards. A review.of work relative to this fan revealed that the fan was removed from service at 2216 hours0.0256 days <br />0.616 hours <br />0.00366 weeks <br />8.43188e-4 months <br /> on 4/12/99 for corrective maintenance activities on a the junction box.
The fan had been returned to service at 1337 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.087285e-4 months <br /> on 04/13/99. A reverse rotating centrifugal fan is able to move air but at a reduced capacity thus the total capability of the two exhaust fans was less than that of the supply fan, resulting in a slight pressurization of the building, a condition outside of the design bases.
The auxiliary building is equipped with a low differential pressure (DP) alarm which did not function during this event. Investigation determined that the associated actuating device was not providing consistent actuation prior to the event and has been removed from service for repairs.
During an after-the-fact review of corrective action requests by licensing, the fact that this event had been mis-classified was noted and the shift was notified to make a 4~hour report to the NRC as required by the plant's Emergency Classification Guide and 10CFR50.72(b) (1) (ii) (B), which requires reporting when the plant is found, during operation, to be in a condition that is outside of the design basis.
CAUSE OF OCCURRENCE The fan had been rewired incorrectly due to human error .during restoration from corrective maintenance activities. The independent verification associated with the activity also failed to identify the incorrect re-termination.
NRC FORM 366A (6-19981
. [NHC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION DOCKET (2)
FACILITY NAME (1) NUMBER 121 LER NUMBER (6) PAGE (3)
YEAR ISEO~I_NTI I NUMBER REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 99 02 00 3 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366AJ ( 17)
PRIOR SIMILAR OCCURRENCES Over the past two years several examples of improper equipment restoration have been cited in both Licensee Event Reports and Inspection Reports for Salem Units 1 and 2. (Inspection Report 98-09 and LERs 272/98-005 Inoperability Of The 12 Fuel Oil Transfer Pump Due To Installation Of Incorrect Control Switch, 311/98-002 23 Over temperature Delta Temperature Channel Found Inoperable, 311/98-004 Failure to Comply With Technical Specification Surveillance Requirement 4.1.3.1.1, and 311/98-012 22 Auxiliary Feedwater. Pump Inoperabili ty Caused By The Failure To Restore The Pump Runout Protection Pressure Transmitter To Service Following Calibration).
SAFETY CONSEQUENCES AND IMPLICATIONS The auxiliary building ventilation system consists of two 100% supply fans and three 50% capacity exhaust fans. During normal operation one supply and two exhaust fans are in operation with exhaust flow exceeding supply flow.
The exhaust fan was able to provide a significant percentage of the design flow while rotating backward, as *is typical of centrifugal fans. However, due to the reduced exhaust capacity the auxiliary building was at a slight positive pressure relative to outdoors such that there was a potential for an unmonitored leakage pathway. During the short period that the fan was operating incorrectly the radiological conditions within the auxiliary building were acceptable (no airborne contamination) thus the likelihood of an unmonitored release was very low. In addition, continuous monitoring equipment was reviewed after the event and no increase in activity was noted for the time that the building was potentially pressurized. If there had been an accident during the period of time that the fan was rotating backwards the safety significance would have been minimal because there was an additional exhaust fan available which would have started automatically, thus ensuring negative pressurization.
CORRECTIVE ACTIONS Personnel involved with the event have been held accountable consistent with Corporate Policies.
Procedures are being modified to require the use of a phase rotation meter whenever equipment is electrically terminated. These revisions will be completed by 06/30/99.
Although not a causal factor, the auxiliary building Low DP alarm is being repaired. The work is currently scheduled mid July.
NRC FORM 366A (6-1998)
