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| | issue date = 01/17/1990 | | | issue date = 01/17/1990 |
| | title = LER 89-036-00:on 891220,steam Generator 13 Blowdown Radiation Monitoring Sys Channel 1R19C Failed High,Resulting in Isolation of Steam Generator Blowdown.Caused by Equipment Failure.Detector Replaced & Channel calibr.W/900117 Ltr | | | title = LER 89-036-00:on 891220,steam Generator 13 Blowdown Radiation Monitoring Sys Channel 1R19C Failed High,Resulting in Isolation of Steam Generator Blowdown.Caused by Equipment Failure.Detector Replaced & Channel calibr.W/900117 Ltr |
| | author name = MILLER L K, POLLACK M J | | | author name = Miller L, Pollack M |
| | 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:* | | {{#Wiki_filter:PS~G * |
| * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | * Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 17, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 January 17, 1990 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery. | | |
| MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC Sincerely yours, L. K. Miller General Manager -Salem Operations 0 . ts-2189 (SM) 12-88 NRC F0<m :Jee 19-831 U.S. NUCLE"R REOULATOAY
| | SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery. |
| ""'ROVED OMll NO. 3150....0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31 II& F"CILITY NAME 111 Salem Generating Station -Unit 1 'DOCKET NUMIER 12) I 1;,i o 1s101010121112 1loF 013 TITLE 141 No. 13 Blowdown Automatic Isolation Due To Failure of The 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/ | | Sincerely yours, L. K. Miller General Manager - |
| {) | | Salem Operations MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC |
| MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 -316 -ol o ol 1 111 91 _o. OPERATING THll REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFA §: (Choclt OM or morw of th* fol/owing} | | .££~;< |
| (111 t---MOO-E-.(_11 | | 0 . |
| _ ___,i..;;l;;;.+--
| | ts-2189 (SM) 12-88 |
| 20.402(bl POWER I 20.40ll(ol(11(11 20.40ll(cl | | |
| -x -ll0.73(11ll2lllwl ll0.731oll2lM ll0.73(oll2ll*Hl ll0.73(oll2llw11111Al ll0.731*l(2ll*tllllll ll0.731*ll2ll*l 73.711bl 73.71Ccl ll0.311(c)(1 l LEVEL . ---,__ too..-....-0..,01_........,...,1_10,,..1\,o,;o.,..._ | | NRC F0<m :Jee U.S. NUCLE"R REOULATOAY C~lalON 19-831 |
| 20.40ll1.11111111 l:ltfJl= | | ""'ROVED OMll NO. 3150....0104 EXPIRES: 8/31 II& |
| -ll0.311fcl 12l -OTHER 15/>>clfy In Ab1r-:t />>low ond In To*t, NRC Fo"" 366AI !!0.73(e)(2l(ll
| | LICENSEE EVENT REPORT (LER) |
| -.__ ll0.73(*11211111
| | F"CILITY NAME 111 DOCKET NUMIER 12) I ~-u~ 1;,i Salem Generating Station - Unit 1 o 1s101010121112 1loF 013 TITLE 141 No. 13 ~/G Blowdown Automatic Isolation Due To Failure of The ' 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/ SE~~~~~~AL { ) ~~~~?.: MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 - ~ 316 - ol o ol 1 111 91 _o. |
| --ll0.73(11ll21Ulll LICENSEE CONTACT FOR THIS LEA (12) NAME TELEPHONE Nl/MBER AREA CODE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC* TUR ER MANUFAC TUA ER B I IL DIE fT I y I I I I I I I I I I I I I . I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YJ"R j YES (If yn, comp/or. EXPECTED SUBMISSION DATE} NO EXPECTED SUBMl$SION DATE 1151 I I I Aal'TRACT (Limit to 1400 1pocn, i.* .. opproximor.ly fifteon 1ingl1*1,,.c1 ry,,.wrlmn | | OPERATING THll REPORT II SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFA §: (Choclt OM or morw of th* fol/owing} (111 t---MOO-E-.(_11_ |
| /inn} (1111 On December 20, 1989 at 0345 hours, the No. 13 Steam Generator (S/G) blowdown Radiation Monitoring System (RMS) channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown. | | POWER I ___,i..;;l;;;.+-- 20.402(bl 20.40ll(ol(11(11 -- 20.40ll(cl ll0.311(c)(1 l --x ll0.73(11ll2lllwl ll0.731oll2lM ,__ |
| Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint. | | 73.711bl 73.71Ccl LEVEL . - |
| The root cause of the 1Rl9C channel failure has been attributed to an equipment The channel's detector and connector had failed. The 1Rl9C detector is a NaI Gamma Scintillator model LFE MD5C. The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. | | too..-....-0..,01_........,...,1_10,,..1\,o,;o.,..._ 20.40ll1.11111111 ll0.311fcl 12l ll0.73(oll2ll*Hl OTHER 15/>>clfy In Ab1r-:t |
| The channel was declared operable on December 21, 1989 at 2235 hours and Technical Specification Table 3.3-12 Action 27 was subsequently exited. NAC FDl'm :Jee (9-831 I *----*---* LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station Unit 1 ----------- | | />>low ond In To*t, NRC Fo"" |
| DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
| | l:ltfJl= :::::::~: |
| Westinghouse
| | !!0.73(e)(2l(ll .__ ll0.73(oll2llw11111Al 366AI |
| -Pressurized Water Reactor LER NUMBER 89-036-00 PAGE 2 of 3 ----==--*
| | - ll0.73(*11211111 ll0.73(11ll21Ulll LICENSEE CONTACT FOR THIS LEA (12) |
| Energy Industry Identification System {EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE: | | - ll0.731*l(2ll*tllllll ll0.731*ll2ll*l NAME TELEPHONE Nl/MBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC TUR ER TUA ER B I IL DIE fT I y I I I I I I I I I I I I I .I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YJ"R EXPECTED |
| No. 13 Stearn Generator Blowdown automatic isolation due to failure of the 1R19C Radiation Monitoring System channel Event Date: 12/20/89 Report Date: 1/17/90 This report was initiated by Incident Report Nos. 89-783 and 89-784. CONDITIONS PRIOR TO OCCURRENCE: | | ~ |
| Mode 1 Reactor Power 100% -Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE: | | SUBMl$SION j YES (If yn, comp/or. EXPECTED SUBMISSION DATE} NO DATE 1151 I I I Aal'TRACT (Limit to 1400 1pocn, i.*.. opproximor.ly fifteon 1ingl1*1,,.c1 ry,,.wrlmn /inn} (1111 On December 20, 1989 at 0345 hours, the No. 13 Steam Generator (S/G) blowdown Radiation Monitoring System (RMS) channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown. |
| On December 20, 1989 at 0345 hours, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown. | | Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint. The root cause of the 1Rl9C channel failure has been attributed to an equipment failure~ The channel's detector and connector had failed. The 1Rl9C detector is a NaI Gamma Scintillator model LFE MD5C. The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. The channel was declared operable on December 21, 1989 at 2235 hours and Technical Specification Table 3.3-12 Action 27 was subsequently exited. |
| Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint. | | NAC FDl'm :Jee (9-831 |
| On December 19, 1989 at 1150 hours Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states: "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/gram: | | |
| : a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131. B. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131." S/G Blowdown Isolation is considered an Engineered Safety Feature. Subsequently, on December 20, 1989 at 0435 hours, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii). | | I LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit - - - - - - - - - 5000272 89-036-00 ----==--* |
| -----------------
| | 2 of 3 PLANT AND SYSTEM IDENTIFICATION: |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET-NUMBER 5000272 LER NUMBER 89-036-00
| | Westinghouse - Pressurized Water Reactor Energy Industry Identification System {EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE: |
| *-------------
| | No. 13 Stearn Generator Blowdown automatic isolation due to failure of the 1R19C Radiation Monitoring System channel Event Date: 12/20/89 Report Date: 1/17/90 This report was initiated by Incident Report Nos. 89-783 and 89-784. |
| *----PAGE 3 of 3 The root cause of the 1R19C channel failure has been attributed to an equipment failure. The channel's detector and connector had failed. The 1R19C detector is a NaI Gamma Scintillator model LFE MDSC. Initial investigation of this event identified a bad high voltage cable connector.
| | CONDITIONS PRIOR TO OCCURRENCE: |
| After replacing the cable connector, a channel caiibration was conducted. | | Mode 1 Reactor Power 100% - Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE: |
| The calibration identified the detector as not performing to its full capabilities. | | On December 20, 1989 at 0345 hours, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown. Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint. |
| Channel calibration of the 2R1A channel is performed quarterly in accordance with manufacturers recommendations. | | On December 19, 1989 at 1150 hours Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states: |
| The calibration was last prior to this event, on September 27, 1989. It was scheduled to be done January 3, 1990. ANALYSIS OF OCCURRENCE: | | "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10- 7 microcuries/gram: |
| The 1R19 RMS channels monitor S/G blowdown water from the individual S/Gs for radioactivity. | | : a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131. |
| An alarm of this channel may indicate a significant primary to secondary leak. The alarm setpoint is set at a release rate which is less than the limits set by the Technical Specifications and the Updated Final Safety Analysis Report. Upon receipt of a channel alarm indication, the SGBI valve (GB4), for the respective S/G, will automatically close, resulting in SGBI. During this event the No. 13 SGBI GB4 valve closed as designed. | | B. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131." |
| The Condenser Air Ejector radiation monitor is used as the corroborating channel for the 1R19 radiation monitors. | | S/G Blowdown Isolation is considered an Engineered Safety Feature. |
| However, an alarm from this channel would not identify the specific S/G where a primary to secondary leak has occurred. | | Subsequently, on December 20, 1989 at 0435 hours, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii). |
| A review of this event has shown that the 1R19C alarm was not actuated due to high radiation levels in the No. 13 S/G blowdown line. Therefore, the health and safety of the public was not affected by this event. However, since SGBI is considered an ESF system, this event is reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv}. CORRECTIVE ACTION: The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. | | |
| The channel was declared operable on December 21, 1989 at 2235 hours and Technical Specification Table 3.3-12 Action 27 was subsequently exited. k:tte...:i&v General Manager -Salem Operations MJP:pc SORC Mtg. 90-006}} | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET- NUMBER LER NUMBER PAGE Unit 1 *------------- 5000272 *---- |
| | 89-036-00 3 of 3 The root cause of the 1R19C channel failure has been attributed to an equipment failure. The channel's detector and connector had failed. |
| | The 1R19C detector is a NaI Gamma Scintillator model LFE MDSC. |
| | Initial investigation of this event identified a bad high voltage cable connector. After replacing the cable connector, a channel caiibration was conducted. The calibration identified the detector as not performing to its full capabilities. |
| | Channel calibration of the 2R1A channel is performed quarterly in accordance with manufacturers recommendations. The calibration was last performed~ prior to this event, on September 27, 1989. It was scheduled to be done January 3, 1990. |
| | ANALYSIS OF OCCURRENCE: |
| | The 1R19 RMS channels monitor S/G blowdown water from the individual S/Gs for radioactivity. An alarm of this channel may indicate a significant primary to secondary leak. The alarm setpoint is set at a release rate which is less than the limits set by the Technical Specifications and the Updated Final Safety Analysis Report. Upon receipt of a channel alarm indication, the SGBI valve (GB4), for the respective S/G, will automatically close, resulting in SGBI. During this event the No. 13 SGBI GB4 valve closed as designed. |
| | The lRl~ Condenser Air Ejector radiation monitor is used as the corroborating channel for the 1R19 radiation monitors. However, an alarm from this channel would not identify the specific S/G where a primary to secondary leak has occurred. |
| | A review of this event has shown that the 1R19C alarm was not actuated due to high radiation levels in the No. 13 S/G blowdown line. Therefore, the health and safety of the public was not affected by this event. However, since SGBI is considered an ESF system, this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (iv}. |
| | CORRECTIVE ACTION: |
| | The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. The channel was declared operable on December 21, 1989 at 2235 hours and Technical Specification Table 3.3-12 Action 27 was subsequently exited. |
| | k:tte...:i&v General Manager - |
| | Salem Operations MJP:pc SORC Mtg. 90-006}} |
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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
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- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 17, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 89-036-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required within thirty (30) days of discovery.
Sincerely yours, L. K. Miller General Manager -
Salem Operations MJP:pc Distribution 9001300330 900117 PDR ADOCK 05000272 S PDC
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LICENSEE EVENT REPORT (LER)
F"CILITY NAME 111 DOCKET NUMIER 12) I ~-u~ 1;,i Salem Generating Station - Unit 1 o 1s101010121112 1loF 013 TITLE 141 No. 13 ~/G Blowdown Automatic Isolation Due To Failure of The ' 1Rl9C RMS Channel EVENT DATE (151 LEA NUMBER Ill REPORT DATE 171 OTHER FACILITIES INVOLVED (II MONTH DAY YEAR YEAR k/ SE~~~~~~AL { ) ~~~~?.: MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 112 2 lo s 9 al 9 - ~ 316 - ol o ol 1 111 91 _o.
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- ll0.731*l(2ll*tllllll ll0.731*ll2ll*l NAME TELEPHONE Nl/MBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll REPORT 1131 CAUSE SYSTEM COMPONENT MANUFAC* MANUFAC TUR ER TUA ER B I IL DIE fT I y I I I I I I I I I I I I I .I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YJ"R EXPECTED
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SUBMl$SION j YES (If yn, comp/or. EXPECTED SUBMISSION DATE} NO DATE 1151 I I I Aal'TRACT (Limit to 1400 1pocn, i.*.. opproximor.ly fifteon 1ingl1*1,,.c1 ry,,.wrlmn /inn} (1111 On December 20, 1989 at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br />, the No. 13 Steam Generator (S/G) blowdown Radiation Monitoring System (RMS) channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown.
Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint. The root cause of the 1Rl9C channel failure has been attributed to an equipment failure~ The channel's detector and connector had failed. The 1Rl9C detector is a NaI Gamma Scintillator model LFE MD5C. The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. The channel was declared operable on December 21, 1989 at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> and Technical Specification Table 3.3-12 Action 27 was subsequently exited.
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I LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit - - - - - - - - - 5000272 89-036-00 ----==--*
2 of 3 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System {EIIS) codes are identified in the text as {xxl IDENTIFICATION OF OCCURRENCE:
No. 13 Stearn Generator Blowdown automatic isolation due to failure of the 1R19C Radiation Monitoring System channel Event Date: 12/20/89 Report Date: 1/17/90 This report was initiated by Incident Report Nos.89-783 and 89-784.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 Reactor Power 100% - Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE:
On December 20, 1989 at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br />, during normal plant operations, the No. 13 Steam Generator (S/G) blowdown {WI} Radiation Monitoring System (RMS) {ILl channel, 1R19C, failed high. The channel failure caused isolation of No. 13 S/G Blowdown. Previously, the 1R19C channel had been declared inoperable, on December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, due to alternating illumination/clearance of the Control Room 1R19C channel fail light and periodic spiking of the radiation indication above the warning setpoint.
On December 19, 1989 at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> Technical Specification 3.3.3.8 Table 3.3-12 Action 27 was entered. It states:
"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10- 7 microcuries/gram:
- a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131.
B. 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 specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT I-131."
S/G Blowdown Isolation is considered an Engineered Safety Feature.
Subsequently, on December 20, 1989 at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br />, the Nuclear Regulatory Commission was notified of the automatic actuation of SGBI in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii).
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET- NUMBER LER NUMBER PAGE Unit 1 *------------- 5000272 *----
89-036-00 3 of 3 The root cause of the 1R19C channel failure has been attributed to an equipment failure. The channel's detector and connector had failed.
The 1R19C detector is a NaI Gamma Scintillator model LFE MDSC.
Initial investigation of this event identified a bad high voltage cable connector. After replacing the cable connector, a channel caiibration was conducted. The calibration identified the detector as not performing to its full capabilities.
Channel calibration of the 2R1A channel is performed quarterly in accordance with manufacturers recommendations. The calibration was last performed~ prior to this event, on September 27, 1989. It was scheduled to be done January 3, 1990.
ANALYSIS OF OCCURRENCE:
The 1R19 RMS channels monitor S/G blowdown water from the individual S/Gs for radioactivity. An alarm of this channel may indicate a significant primary to secondary leak. The alarm setpoint is set at a release rate which is less than the limits set by the Technical Specifications and the Updated Final Safety Analysis Report. Upon receipt of a channel alarm indication, the SGBI valve (GB4), for the respective S/G, will automatically close, resulting in SGBI. During this event the No. 13 SGBI GB4 valve closed as designed.
The lRl~ Condenser Air Ejector radiation monitor is used as the corroborating channel for the 1R19 radiation monitors. However, an alarm from this channel would not identify the specific S/G where a primary to secondary leak has occurred.
A review of this event has shown that the 1R19C alarm was not actuated due to high radiation levels in the No. 13 S/G blowdown line. Therefore, the health and safety of the public was not affected by this event. However, since SGBI is considered an ESF system, this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (iv}.
CORRECTIVE ACTION:
The 1R19C detector and associated connector were replaced and a channel calibration successfully completed. The channel was declared operable on December 21, 1989 at 2235 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.504175e-4 months <br /> and Technical Specification Table 3.3-12 Action 27 was subsequently exited.
k:tte...:i&v General Manager -
Salem Operations MJP:pc SORC Mtg.90-006
