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| {{#Wiki_filter:NRC Form 318 (9.a31 U.I. NUCLEAR REGULATOllY COMMISllOfil APl'ROVEO OM! NO. Jl!I0-0104 LICENSEE EVENT REPORT (LER) EXPIRES: Sf.111815 FACILITY NAME (11 I OOCKET NUM*ER l2l I p,.. .. ., I'll Salem Generating Station -Unit 2 o I 5 Io Io I o 13 11 I l 1 loF 014 TITLE (41 ESF Actuation | | {{#Wiki_filter:NRC Form 318 U.I. NUCLEAR REGULATOllY COMMISllOfil (9.a31 APl'ROVEO OM! NO. Jl!I0-0104 EXPIRES: Sf.111815 LICENSEE EVENT REPORT (LER) |
| -Containment Vent. Isolation Due To System Design/Equip. | | I I |
| Concerns EVENT DATE (Ill LER NUMBllR (Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH CAY YEAR YEAR rt tt MONTH DAY YEAR FACIL.!iV NAMES DOCKET NUMBERISI ol 3 o 14 a 9 a I 9 -o I o 14 -o I o q 3 2 I 9 a I 9 OPERATING MOOE (II l THll REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock an* or m<HY of th* fallowing) | | FACILITY NAME (11 OOCKET NUM*ER l2l p,.. .. ., I'll Salem Generating Station - Unit 2 o I 5 Io Io I o 13 11 I l 1 loF 014 TITLE (41 ESF Actuation - Containment Vent. Isolation Due To System Design/Equip. Concerns EVENT DATE (Ill LER NUMBllR (Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH CAY YEAR YEAR rt ~E~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACIL.!iV NAMES DOCKET NUMBERISI ol 3 o14 a 9 a I 9 - o I o14 - oI o q 3 2 I9 a I 9 THll REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock an* or m<HY of th* fallowing) (111 OPERATING MOOE (II POWER I l 20.402(bl 20.40l5t*lt1lUI - |
| (111 20.402(bl 20.-(al x ll0.73(*11Zlllwl 73.71(bl --.._ 20.40l5t*lt1lUI ll0.3e(cl(11 ll0.73(81(Zltvl 73.71(*1 ,___ ,___ ....__ 20.-t*lt11(HI ll0.311taltZI ll0.73(*1tZ)(wHI OTHER (S,_,lfy in Ab-,___ -...._ IH/aw *nd In T*xt. NRC Fg,,,, POWER I LEVEL -1101 1 I 0 I 0 20.408(1111111111 ll0.73(*1(21(11 ll0.73(811ZltwillltAI 366A) .._ ,___ 20.40l(11(1 ltlvl ll0.73(11(Zl(lll ll0.73(1)(Zl(wlllltll | | ,___ |
| -...._ 20.40llt*lt1 IM ll0.73toltZltllll eo.73t*ltZHxl LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA COOE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRlllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC. TUR ER B IIL DIEITI v111 01 N I I I I I I I SUPl'LEMENTAL REPORT EXPECTED (141 n YES (If yn, oampl*tt EXPECTED DATE/ NO I I I I I I I I I I I I I I EXPECTED SUBMISSION DATE (151 MONTH DAY I I I AllSTRACT (Limit ID 14CO IP"C ... I.* ** *PPf'OKim*ttly flftHn 1/ngl**IPOCO typoWl'lttfn lintni 11111 On March 4, 1989, the Containment Purge/Pressure-Vacuum Relief System {CP/P-VRS}
| | 20.-(al ll0.3e(cl(11 - |
| valves isolated as a result of the failure of the Radiation Monitoring System (RMS) Containment Particl1late Radiation Monitor, 2R11A. With the failure of the 2RllA channel, Technical Specification 3.4.7.1 Action Statement was entered. The root cause of this event has been attributed to inadequate system design. The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer | | ,___ |
| {SPT). The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2R11A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value. Since the 2Rl1A RMS. monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail". Conservatively, failure of the channel causes CP/P-VRS isolation. | | x ll0.73(*11Zlllwl ll0.73(81(Zltvl |
| As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has initiated an investigation of RMS system concerns. | | .._ |
| This investigation includes *a review of power supply concerns. | | ....__ |
| The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989 at which time,* the channel was declared operable and the Specification 3.4.7.1 Action Statement was exited. NRC Form 3118 (9-831 4 -/.:. ( 1 C'*-* *-*90'=1" 7''7' :=: 9 o (_) -.. ) -**=-* (;5000311 ADOCK PDC s ._ .... , W' r f .. _..-* ; l '. ... | | 73.71(bl 73.71(*1 LEVEL 1101 1 I 0I0 |
| *.
| | - |
| __ _.:_ _ _..e. ____
| | 20.-t*lt11(HI 20.408(1111111111 |
| II LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station t 2 DOCKET NUMBER 5000311 ------*---
| | ,___ |
| ---PLA]'.JT AND SYSTEM IDENTIFICATION: | | .._ |
| Westinghouse | | ll0.311taltZI ll0.73(*1(21(11 -...._ |
| -Pressurized Water Reactor LER NUMBER PAGE | | ,___ |
| __
| | ll0.73(*1tZ)(wHI ll0.73(811ZltwillltAI |
| ___ Q__f_4_ __ Energy Industry Idez1tification System (EIIS) codes identified in the text as {xx! IDENTIFICATION OF OCCURRENCE:
| | ...._ OTHER (S,_,lfy in A b - |
| --------------- | | IH/aw *nd In T*xt. NRC Fg,,,, |
| Engineered Safety Feature Actuation | | 366A) 20.40l(11(1 ltlvl 20.40llt*lt1 IM - ll0.73(11(Zl(lll ll0.73toltZltllll LICENSEE CONTACT FOR THIS LER (121 ll0.73(1)(Zl(wlllltll eo.73t*ltZHxl NAME TELEPHONE NUMBER AREA COOE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRlllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC. |
| -Containment Ventilation Isolation Due To System Design/Equipment Concerns Event Date: 3/04/89 Report Date: 3/29/89 This report was initiated by Incident Report No. 89-122. CONDITIONS PRIOR TO Mode 1 Reactor Power 100% -Unit Load 1150 MWe DESCRIPTION OF OCCURRENCE: | | TUR ER B IIL DIEITI v111 01 N I I I I I I I I I I I I I I I I I I I I I SUPl'LEMENTAL REPORT EXPECTED (141 MONTH DAY Y~AR EXPECTED n ~ |
| On March 4, 1989 at 1620 hours, the Containment Purge/Pressure-Vacuum Relief System lCP/P-VRS} | | SUBMISSION YES (If yn, oampl*tt EXPECTED SUBMISSI~ DATE/ NO DATE (151 I I I AllSTRACT (Limit ID 14CO IP"C... I.*** *PPf'OKim*ttly flftHn 1/ngl**IPOCO typoWl'lttfn lintni 11111 On March 4, 1989, the Containment Purge/Pressure-Vacuum Relief System |
| valves isolated as a result of the failure of the Radiation Monitoring System (RMS) {ILi Containment Particulate Radiation Monitor, 2R11A. With the failure of the 2R11A channel, Technical Specification 3.4.7.1 Action Statement was entered. Technical Specification 3.4.7.1 states: "The following Reactor Coolant System leakage detection systems shall be OPERABLE: | | {CP/P-VRS} valves isolated as a result of the failure of the Radiation Monitoring System (RMS) Containment Particl1late Radiation Monitor, 2R11A. With the failure of the 2RllA channel, Technical Specification 3.4.7.1 Action Statement was entered. The root cause of this event has been attributed to inadequate system design. The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer {SPT). The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2R11A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value. Since the 2Rl1A RMS. |
| : a. The containment atmosphere particulate radioactivity monitoring system, b. The containment pocket sump level monitoring system, and c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system." Technical Specification 3.4.7.1 Action Statement states: "With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours when the required gaseous and/or particulate radioactivity monitoring system is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours." The CP/P-VRS is an Engineered Safety System (ESF). | | monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail". Conservatively, failure of the channel causes CP/P-VRS isolation. As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has initiated an investigation of RMS system concerns. This investigation includes *a review of power supply concerns. The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989 at which time,* the channel was declared operable and the Technic~l Specification 3.4.7.1 Action Statement was exited. |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE of 4 The root cause of this event has been attributed to inadequate system design. The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer (SPT) {EAi. The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2Rl1A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value. Since the 2R11A RMS monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail''. Conservatively, failure of the channel causes CP/P-VRS isolation. | | 7 |
| The No. 21 SPT had been returned to service after completion of a 13 KV leads compartment gasket cover oil leak repair. ANALYSIS OF OCCURRENCE:
| | :=: 9 o 4 (_)- /.:.-..( )1 C'*-* |
| -------The 2Rl1A Containment Particulate Monitor monitor's the air particulate gamma radioactivity in the Containment atmosphere.
| | -**=-* *-*90'=1" |
| It is used as an aid in the identification of Reactor Coolant System fABl leakage in conjunction with the containment sump level monitoring system and either the containment fan cooler condensate flow rate or the containment atmosphere gaseous (2R12A) radioactivity monitoring system. An alarm signal will cause the automatic isolation of the CP/P-VRS.
| | (;5000311 ''7' ...., |
| Air samples are pulled directly from the Containment atmosphere through a filter paper which continuously moves past the 2Rl1A scintillation detector.
| | ~bR ADOCK s |
| After the air sample passes through the filter paper, it passes through a charcoal cartridge (monitored by tl:e 2R12B monitor) and is then mixed into a fixed shielded volume where it is viewed by the 2R12A noble gas monitor. The air sample is then returned to the Containment.
| | PDC W' r |
| Several area radiation monitors, in addition to the 2R12A monitor, are used to corroborate the 2Rl1A channel's indications.
| | _..- *; |
| The corroborating area radiation monitors do not have isolation capabilities.
| | ._ |
| They only have alarm capability.
| | -.r~< f..~c ~:. ~ |
| The 1R41A Plant Vent Particulate monitor also corroborates the 2R11A channel indications.
| | '. |
| This monitor also has the capability of automatic isolation of the CP/P-VRS.
| | ~ l NRC Form 3118 (9-831 |
| It remained operable during the course of this event. During this event, RCS leakage within Containment did not increase.
| | |
| Additionally, a Containment purge or pressure-vacuum relief was not performed.
| | II LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE TJ~i t 2 5000311 |
| Therefore, this event did not affect the health or safety of the public. However, due to the automatic operation of an ESF system, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv). CORRECTIVE ACTION: As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 CORRECTIVE DOCKET NUMBER LER NUMBER 5000311 89-004-00
| | ------*--- - - - ~-~-=-Q_Q_1_=-_Q_O_ _ **----~ ___ Q__f_4_ __ |
| -----------------*--**------*-------
| | PLA]'.JT AND SYSTEM IDENTIFICATION: |
| ---initiated an investigation of RMS system concerns.
| | Westinghouse - Pressurized Water Reactor Energy Industry Idez1tification System (EIIS) codes ~re identified in the text as {xx! |
| This investigation includes a review of power supply concerns.
| | IDENTIFICATION OF OCCURRENCE: |
| PAGE 4 o!_ __
| | --------------- |
| The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989. At 0436 hours on March 5, the channel was declared operable and Technical Specification 3.4.7.1 Action Statement was exited.
| | Engineered Safety Feature Actuation - Containment Ventilation Isolation Due To System Design/Equipment Concerns Event Date: 3/04/89 Report Date: 3/29/89 This report was initiated by Incident Report No. 89-122. |
| -Salem Operations MJP:pc SORC Mtg. 89-026 Public Ser-vice Electric and Gas Company P 0. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | CONDITIONS PRIOR TO OCCVRR~~CE: |
| | Mode 1 Reactor Power 100% - Unit Load 1150 MWe DESCRIPTION OF OCCURRENCE: |
| | On March 4, 1989 at 1620 hours, the Containment Purge/Pressure-Vacuum Relief System lCP/P-VRS} valves isolated as a result of the failure of the Radiation Monitoring System (RMS) {ILi Containment Particulate Radiation Monitor, 2R11A. With the failure of the 2R11A channel, Technical Specification 3.4.7.1 Action Statement was entered. |
| | Technical Specification 3.4.7.1 states: |
| | "The following Reactor Coolant System leakage detection systems shall be OPERABLE: |
| | : a. The containment atmosphere particulate radioactivity monitoring system, |
| | : b. The containment pocket sump level monitoring system, and |
| | : c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system." |
| | Technical Specification 3.4.7.1 Action Statement states: |
| | "With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours when the required gaseous and/or particulate radioactivity monitoring system is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours." |
| | The CP/P-VRS is an Engineered Safety System (ESF). |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION |
| | ~---------------------------------------~--~-- |
| | Salem Generating Station DOCKET NUMBER LER NUMBER PAGE |
| | ~-n~i_t~2~~~~~~~~~~~~~~~~~03i_1~~~~~8_9-004-00~~~~3 of 4 The root cause of this event has been attributed to inadequate system design. |
| | The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer (SPT) {EAi. The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2Rl1A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value. |
| | Since the 2R11A RMS monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail''. |
| | Conservatively, failure of the channel causes CP/P-VRS isolation. |
| | The No. 21 SPT had been returned to service after completion of a 13 KV leads compartment gasket cover oil leak repair. |
| | ANALYSIS OF OCCURRENCE: |
| | ------- |
| | The 2Rl1A Containment Particulate Monitor monitor's the air particulate gamma radioactivity in the Containment atmosphere. It is used as an aid in the identification of Reactor Coolant System fABl leakage in conjunction with the containment sump level monitoring system and either the containment fan cooler condensate flow rate or the containment atmosphere gaseous (2R12A) radioactivity monitoring system. An alarm signal will cause the automatic isolation of the CP/P-VRS. |
| | Air samples are pulled directly from the Containment atmosphere through a filter paper which continuously moves past the 2Rl1A scintillation detector. After the air sample passes through the filter paper, it passes through a charcoal cartridge (monitored by tl:e 2R12B monitor) and is then mixed into a fixed shielded volume where it is viewed by the 2R12A noble gas monitor. The air sample is then returned to the Containment. |
| | Several area radiation monitors, in addition to the 2R12A monitor, are used to corroborate the 2Rl1A channel's indications. The corroborating area radiation monitors do not have isolation capabilities. They only have alarm capability. The 1R41A Plant Vent Particulate monitor also corroborates the 2R11A channel indications. |
| | This monitor also has the capability of automatic isolation of the CP/P-VRS. It remained operable during the course of this event. |
| | During this event, RCS leakage within Containment did not increase. |
| | Additionally, a Containment purge or pressure-vacuum relief was not performed. Therefore, this event did not affect the health or safety of the public. However, due to the automatic operation of an ESF system, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv). |
| | CORRECTIVE ACTION: |
| | As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 ---5000311 89-004-00 |
| | --------------*--**------*------- - - - 4 o!___~----*-- |
| | CORRECTIVE ACTION~=-~(~c~o,~n~t-=--'~d~) |
| | initiated an investigation of RMS system concerns. This investigation includes a review of power supply concerns. |
| | The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989. At 0436 hours on March 5, the channel was declared operable and Technical Specification 3.4.7.1 Action Statement was exited. |
| | G:~J~ager - |
| | Salem Operations MJP:pc SORC Mtg. 89-026 |
| | |
| | Public Ser-vice Electric and Gas Company P 0. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 29, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
|
| |
|
| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 89-004-00 March 29, 1989 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73 (a) (2) (iv}. | | |
| report is being submitted within thirty (30) days of discovery. | | SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 89-004-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73 (a) (2) (iv}. ~his report is being submitted within thirty (30) days of discovery. |
| MJP:pc Distribution The Energy People Sincerely
| | Sincerely yours, |
| : yours, General Manager -Salem Operations}} | | :~!~(~er General Manager - |
| | Salem Operations MJP:pc Distribution The Energy People}} |
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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
NRC Form 318 U.I. NUCLEAR REGULATOllY COMMISllOfil (9.a31 APl'ROVEO OM! NO. Jl!I0-0104 EXPIRES: Sf.111815 LICENSEE EVENT REPORT (LER)
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FACILITY NAME (11 OOCKET NUM*ER l2l p,.. .. ., I'll Salem Generating Station - Unit 2 o I 5 Io Io I o 13 11 I l 1 loF 014 TITLE (41 ESF Actuation - Containment Vent. Isolation Due To System Design/Equip. Concerns EVENT DATE (Ill LER NUMBllR (Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH CAY YEAR YEAR rt ~E~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACIL.!iV NAMES DOCKET NUMBERISI ol 3 o14 a 9 a I 9 - o I o14 - oI o q 3 2 I9 a I 9 THll REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock an* or m<HY of th* fallowing) (111 OPERATING MOOE (II POWER I l 20.402(bl 20.40l5t*lt1lUI -
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366A) 20.40l(11(1 ltlvl 20.40llt*lt1 IM - ll0.73(11(Zl(lll ll0.73toltZltllll LICENSEE CONTACT FOR THIS LER (121 ll0.73(1)(Zl(wlllltll eo.73t*ltZHxl NAME TELEPHONE NUMBER AREA COOE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRlllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC.
TUR ER B IIL DIEITI v111 01 N I I I I I I I I I I I I I I I I I I I I I SUPl'LEMENTAL REPORT EXPECTED (141 MONTH DAY Y~AR EXPECTED n ~
SUBMISSION YES (If yn, oampl*tt EXPECTED SUBMISSI~ DATE/ NO DATE (151 I I I AllSTRACT (Limit ID 14CO IP"C... I.*** *PPf'OKim*ttly flftHn 1/ngl**IPOCO typoWl'lttfn lintni 11111 On March 4, 1989, the Containment Purge/Pressure-Vacuum Relief System
{CP/P-VRS} valves isolated as a result of the failure of the Radiation Monitoring System (RMS) Containment Particl1late Radiation Monitor, 2R11A. With the failure of the 2RllA channel, Technical Specification 3.4.7.1 Action Statement was entered. The root cause of this event has been attributed to inadequate system design. The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer {SPT). The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2R11A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value. Since the 2Rl1A RMS.
monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail". Conservatively, failure of the channel causes CP/P-VRS isolation. As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has initiated an investigation of RMS system concerns. This investigation includes *a review of power supply concerns. The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989 at which time,* the channel was declared operable and the Technic~l Specification 3.4.7.1 Action Statement was exited.
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II LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE TJ~i t 2 5000311
*--- - - - ~-~-=-Q_Q_1_=-_Q_O_ _ **----~ ___ Q__f_4_ __
PLA]'.JT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Idez1tification System (EIIS) codes ~re identified in the text as {xx!
IDENTIFICATION OF OCCURRENCE:
Engineered Safety Feature Actuation - Containment Ventilation Isolation Due To System Design/Equipment Concerns Event Date: 3/04/89 Report Date: 3/29/89 This report was initiated by Incident Report No.89-122.
CONDITIONS PRIOR TO OCCVRR~~CE:
Mode 1 Reactor Power 100% - Unit Load 1150 MWe DESCRIPTION OF OCCURRENCE:
On March 4, 1989 at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, the Containment Purge/Pressure-Vacuum Relief System lCP/P-VRS} valves isolated as a result of the failure of the Radiation Monitoring System (RMS) {ILi Containment Particulate Radiation Monitor, 2R11A. With the failure of the 2R11A channel, Technical Specification 3.4.7.1 Action Statement was entered.
Technical Specification 3.4.7.1 states:
"The following Reactor Coolant System leakage detection systems shall be OPERABLE:
- a. The containment atmosphere particulate radioactivity monitoring system,
- b. The containment pocket sump level monitoring system, and
- c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system."
Technical Specification 3.4.7.1 Action Statement states:
"With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring system is inoperable; otherwise, 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 />."
The CP/P-VRS is an Engineered Safety System (ESF).
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
~---------------------------------------~--~--
Salem Generating Station DOCKET NUMBER LER NUMBER PAGE
~-n~i_t~2~~~~~~~~~~~~~~~~~03i_1~~~~~8_9-004-00~~~~3 of 4 The root cause of this event has been attributed to inadequate system design.
The CP/P-VRS isolation was preceded by the transfer of 2A Vital Bus to the No. 21 Station Power Transformer (SPT) {EAi. The No. 21 SPT is the normal power supply for the 2A Vital Bus which powers the 2Rl1A RMS monitor. The transfer to the No. 21 SPT utilizes a "slow" transfer scheme which will drop line voltage to 35% of nominal value.
Since the 2R11A RMS monitor is directly powered from the 2A Vital Bus it will see the voltage drop too causing the channel to "fail.
Conservatively, failure of the channel causes CP/P-VRS isolation.
The No. 21 SPT had been returned to service after completion of a 13 KV leads compartment gasket cover oil leak repair.
ANALYSIS OF OCCURRENCE:
The 2Rl1A Containment Particulate Monitor monitor's the air particulate gamma radioactivity in the Containment atmosphere. It is used as an aid in the identification of Reactor Coolant System fABl leakage in conjunction with the containment sump level monitoring system and either the containment fan cooler condensate flow rate or the containment atmosphere gaseous (2R12A) radioactivity monitoring system. An alarm signal will cause the automatic isolation of the CP/P-VRS.
Air samples are pulled directly from the Containment atmosphere through a filter paper which continuously moves past the 2Rl1A scintillation detector. After the air sample passes through the filter paper, it passes through a charcoal cartridge (monitored by tl:e 2R12B monitor) and is then mixed into a fixed shielded volume where it is viewed by the 2R12A noble gas monitor. The air sample is then returned to the Containment.
Several area radiation monitors, in addition to the 2R12A monitor, are used to corroborate the 2Rl1A channel's indications. The corroborating area radiation monitors do not have isolation capabilities. They only have alarm capability. The 1R41A Plant Vent Particulate monitor also corroborates the 2R11A channel indications.
This monitor also has the capability of automatic isolation of the CP/P-VRS. It remained operable during the course of this event.
During this event, RCS leakage within Containment did not increase.
Additionally, a Containment purge or pressure-vacuum relief was not performed. Therefore, this event did not affect the health or safety of the public. However, due to the automatic operation of an ESF system, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv).
CORRECTIVE ACTION:
As identified in Unit 2 LER 89-002-00, PSE&G System Engineering has
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 ---5000311 89-004-00
*--**------*------- - - - 4 o!___~----*--
CORRECTIVE ACTION~=-~(~c~o,~n~t-=--'~d~)
initiated an investigation of RMS system concerns. This investigation includes a review of power supply concerns.
The 2R11A channel was reset, the setpoints were verified and a channel check was successfully completed on March 5, 1989. At 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br /> on March 5, the channel was declared operable and Technical Specification 3.4.7.1 Action Statement was exited.
G:~J~ager -
Salem Operations MJP:pc SORC Mtg.89-026
Public Ser-vice Electric and Gas Company P 0. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station March 29, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 89-004-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73 (a) (2) (iv}. ~his report is being submitted within thirty (30) days of discovery.
Sincerely yours,
- ~!~(~er General Manager -
Salem Operations MJP:pc Distribution The Energy People
