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| | issue date = 05/28/1992 | | | issue date = 05/28/1992 |
| | title = LER 92-007-01:on 920306 & 0429,radiation Monitoring Sys Channel 1R11A Spiked High,Resulting in ESF Signal Actuations.Caused by Design,Const,Mfg & Installation Error. Channel Calibr & New Detector ordered.W/920528 Ltr | | | title = LER 92-007-01:on 920306 & 0429,radiation Monitoring Sys Channel 1R11A Spiked High,Resulting in ESF Signal Actuations.Caused by Design,Const,Mfg & Installation Error. Channel Calibr & New Detector ordered.W/920528 Ltr |
| | author name = POLLACK M J, VONDRA C A | | | author name = Pollack M, Vondra C |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:e | | {{#Wiki_filter:e 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 May 28, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear sir:== | | ==Dear sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 May 28, 1992 SUPPLEMENTAL LICENSEE EVENT REPORT 92-007-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73. It addresses a second event which has the same root cause as the first event. Both events are reportable per Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required to be issued within thirty (30) days of event discovery. | | |
| MJP:pc Distribution | | SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 SUPPLEMENTAL LICENSEE EVENT REPORT 92-007-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73. It addresses a second event which has the same root cause as the first event. Both events are reportable per Code of Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required to be issued within thirty (30) days of event discovery. |
| ... (\ .4 1*\ :. :. '': J * .) ...... \ .. I .::;, J : \. . ; '\... 9206050084 PDR ADOCK PDR s Sincerely yours, c. A Vondra General Manager -Salem Operations ftf1 1' .I (/ j 95-2189 (10M) 12-89 | | Sincerely yours, |
| *NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89) EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS *, AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). | | : c. A Vondra General Manager - |
| OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (1) I DOCKET NUMBER (2) I PAGE 131 Salem Generating Station -Ul:iit,l o 1 s I o Io I o 12 I 712 1 loF o 1s TITLE (4) 2 ESF Signal Actuations | | Salem Operations MJP:pc Distribution |
| -Rad Moniitor Channel Spikes EVENT DATE (5) LEA NUMBER 16) REPORT DATE 17) OTHER FACILITIES INVOLVED (B) MONTH DAY YEAR YEAR ttf SEQUENTIAL | | ... (\ .4 1*\ |
| [) REVlSION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) | | : . :. ' ' : J *. ) |
| NUMBER NUMBER 01s1010101 I I ol 016 I -ol o I 1 -o-11 ols 21 8 91 3 9 2 9 2 2 o I 5 Io Io I o I I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Ch*ck on* or mor* of th* following)(11)
| | ~, \ .. I .::;, |
| MODE (9) l 20.402(b) 20.4051c) x 50.73(1)(2J(iv) 73.71(b) I 1 I -,_ -POWER 20.4061*)(1
| | 9206050084 6~88~~72 J |
| )(i) 50.3B(c)(1) 50.73(1)(2)(v) 73.71(c) LEVEL 010 .....-----(10) 20.405(1)(1)(ii) 50,3B(c)(2) 50.73(1)(2)(vii) | | : \. . ; '\... ftf11 ' |
| OTHER (Specify in Abstroct ---below and in Text, NRC. Form llllfl111Wllilllll 20.406(1)(1
| | (/ j 95-2189 (10M) 12-89 |
| )(iii) 50.73(1)(2)(;) | | .I PDR ADOCK PDR s |
| 60.73(1)(2)(viiil(A) 366AI --20.406(1)(1
| | |
| )(Iv) 60.73(1)(2)(ii) 50,7311)(2J(viiil(B) | | *NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS |
| "----20.406(1)(1
| | *, AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE FACILITY NAME (1) |
| )(vi 50.73(1) (2) (iii) 50.73(1)(2)(*) | | Salem Generating Station - Ul:iit,l I |
| LICENSEE CONTACT FOR THIS LEA (12) NAME TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 61 O I 9 3 f 3 I .9 f -12 IO f 2 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) (\ .. -:-::-;. :_*:1:_,:::,.:'!!l,\i::!:i:!l\:i.l!l:\::i!:,::1::::,:
| | OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| MANUFAC-REPORTABLE , ... ,.,. < ::: MANUFAC* REPORTABLE CAUSE SYSTEM COMPONENT TUR ER TO NPRDS *.*.*.* *.-.. *:* *.*.*.*. CAUSE SYSTEM COMPONENT TUR ER TO NPRD.S ...... * , ....... ... , ...... , . .. .. ,,::,: ....... .... *.;.;.; . .. ...... :11,1:::1,.::::,,-:i!i'l\:*
| | DOCKET NUMBER (2) o 1s I o Io I o 12 I 712 I |
| ... /: ... 1 .. :::*:*.:::::::: | | 1 loF PAGE 131 o1s TITLE (4) 2 ESF Signal Actuations - Rad Moniitor Channel Spikes EVENT DATE (5) LEA NUMBER 16) REPORT DATE 17) OTHER FACILITIES INVOLVED (B) |
| >> ::::::'*::*
| | MONTH DAY YEAR YEAR ttf SEQUENTIAL NUMBER [) REVlSION NUMBER MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) 01s1010101 I I ol 3 016 9 2 9 I 2 - ol o I 1 - o-11 ols THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR 21 8 91 2 |
| *>::-;..;.
| | §: (Ch*ck on* or mor* of th* following)(11) o I 5 Io Io I o I I I OPERATING MODE (9) l 20.402(b) 20.4051c) |
| B IIL DfE IT I LI 118 (5 y .;.;.;.:-:-:*
| | ,_ x 50.73(1)(2J(iv) 73.71(b) |
| *.* .. *.-I I I I I I I ':*:':*: , ... .,., :: .... :-:-:-:-:
| | POWER LEVEL (10) I 1 I 010 20.4061*)(1 )(i) 20.405(1)(1)(ii) 50.3B(c)(1) 50,3B(c)(2) -- 50.73(1)(2)(v) 50.73(1)(2)(vii) 73.71(c) |
| ';:: .... 1*11':._::
| | OTHER (Specify in Abstroct below and in Text, NRC. Form 20.406(1)(1 )(iii) 50.73(1)(2)(;) 60.73(1)(2)(viiil(A) 366AI |
| ... *1;.!.!:i_l::.**:**:.,-_*:.-:1
| | ~ - |
| .;.* :-:*:::*:*:*: | | llllfl111Wllilllll 20.406(1)(1 )(Iv) 60.73(1)(2)(ii) 50,7311)(2J(viiil(B) 20.406(1)(1 )(vi |
| I I I I I I I *:*:-:*: ........ :::-:-:*:*:*
| | - 50.73(1) (2) (iii) 50.73(1)(2)(*) |
| I I I I I I I .... SUPPLEMENTAL REPORT 'EXPECTED 114) MONTH DAY YEAR bi EXPECTED SUBMISSION I YES (If v*s. compl*t* EXPECTED SUBMISSION DATE! DATE (151 I I I NO ABSTRACT (Limit ro 1400 spaces. i.e., approxima.tefy fifteen lines) (161 This LER addresses 2 Engineered Safety Feature {ESF) signals initiated by the 1R11A Containment Particulate Radiation Monitoring system (RMS) Monitor channel. The signals were for Containment Purge/Pressure-Vaouum Relief (CP/P-VR)
| | LICENSEE CONTACT FOR THIS LEA (12) |
| System isolation.
| | NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 61 O I 9 3 f 3 I .9 f - 12 IO f 2 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) |
| On 3/6/92, the 1R11A RMS channel momentarily spiked high_resulting in a CP/P-VR System isolation signal. Channel indication returned to normal after the spike. The 1Rl1A RMS channel was declared inoperable and an investigation into the cause of the event was initiated.
| | (\ .. ,...,.,. -:-::-;. ::: |
| Investigation included checking the detector cable for insulation resistance and for continuity.
| | MANUFAC- REPORTABLE MANUFAC* REPORTABLE CAUSE SYSTEM COMPONENT *.*.*.* *.- ..*:* ...,*.*.*.*. CAUSE SYSTEM COMPONENT TUR ER TO NPRDS |
| Results were satisfactory.
| | ......* ,....... . . ,,::,: TUR ER TO NPRD.S :_*:1:_,:::,.:'!!l,\i::!:i:!l\:i.l!l:\::i!:,::1::::,: |
| The event could not be reproduced.
| | y >> ::::::'*::* *>::-;..;. |
| The channel was returned to service on 3/7/92. On 4/29/92, the 1R11A RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress.
| | .;.;.;.:-:-:* *.*.. *.- :11,1:::1,.::::,,-:i!i'l\:*.../:...1.. :::*:*.:::::::: |
| Upon initiation of the isolation signal the containment Purge valves closed per design. The root cause of both lRllA RMS channel ESF signal actuations is "Design, Construction, Manufacturing/Installation" error. The detector can exhibit ground loop conditions.
| | B IIL DfE IT I LI 118 (5 ':*:':*: ,... .,., I I I I I I I |
| A successful 1R11A RMS channel calibration was completed after the second 1R11A channel spike. On May 26, *1992' the channel was returned to service. A new detector has been ordered from the manufacturer.
| | *:*:-:*: ........ :::-:-:*:*:* I I I ';::....1*11':._::...*1;.!.!:i_l::.**:**:.,-_*:.-:1 I I I I I I I .... I I I I SUPPLEMENTAL REPORT 'EXPECTED 114) MONTH DAY YEAR EXPECTED bi SUBMISSION I YES (If v*s. compl*t* EXPECTED SUBMISSION DATE! NO DATE (151 I I I ABSTRACT (Limit ro 1400 spaces. i.e., approxima.tefy fifteen single-spsce*type~ritten lines) (161 This LER addresses 2 Engineered Safety Feature {ESF) signals initiated by the 1R11A Containment Particulate Radiation Monitoring system (RMS) |
| Upon receipt, it will be installed.
| | Monitor channel. The signals were for Containment Purge/Pressure-Vaouum Relief (CP/P-VR) System isolation. On 3/6/92, the 1R11A RMS channel momentarily spiked high_resulting in a CP/P-VR System isolation signal. |
| A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern. NRC Form 366 (6-89)
| | Channel indication returned to normal after the spike. The 1Rl1A RMS channel was declared inoperable and an investigation into the cause of the event was initiated. Investigation included checking the detector cable for insulation resistance and for continuity. Results were satisfactory. The event could not be reproduced. The channel was returned to service on 3/7/92. On 4/29/92, the 1R11A RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress. Upon initiation of the isolation signal the containment Purge valves closed per design. The root cause of both lRllA RMS channel ESF signal actuations is "Design, Construction, Manufacturing/Installation" error. The detector can exhibit ground loop conditions. A successful 1R11A RMS channel calibration was completed after the second 1R11A channel spike. On May 26, *1992' the channel was returned to service. A new detector has been ordered from the manufacturer. Upon receipt, it will be installed. A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern. |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
| | NRC Form 366 (6-89) |
| Westinghouse
| | |
| -Pressurized Water Reactor LER NUMBER 92-007-01
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 2 of 5 PLANT AND SYSTEM IDENTIFICATION: |
| * PAGE 2 of 5 Energy Industry Identification System (EIIS) codes are ideptif ied in the text as {xx} IDENTIFICATION OF OCCURRENCE:
| | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are ideptif ied in the text as {xx} |
| Two Engineered Safety Feature signal actuations; Radiation Monitoring System channel spikes Event Dates: 3/06/92 and 4/29/92 Report Date: 5/28/92 This report was initiated by Incident Report Nos. 92-167 and 92-280. CONDITIONS PRIOR TO OCCURRENCE:
| | IDENTIFICATION OF OCCURRENCE: |
| 3/6/92: Mode 1 Reactor Powet 100% -Unit Load 1160 MWe 4/29/92: Reactor defueled -10 h Refueling outage in progress DESCRIPTION OF OCCURRENCE:
| | Two Engineered Safety Feature signal actuations; Radiation Monitoring System channel spikes Event Dates: 3/06/92 and 4/29/92 Report Date: 5/28/92 This report was initiated by Incident Report Nos. 92-167 and 92-280. |
| This LER addresses two (2) Engineered Safety Feature (ESF) signals initiated by the lRllA Containment Particulate Radiation Monitoring System (RMS) {IL} Monitor* channel. The signals were for Containment Purge/Pressure-Vacuum Relief (CP/P-VR)
| | CONDITIONS PRIOR TO OCCURRENCE: |
| System {BF} isolation. | | 3/6/92: Mode 1 Reactor Powet 100% - Unit Load 1160 MWe 4/29/92: Reactor defueled - 10 h Refueling outage in progress DESCRIPTION OF OCCURRENCE: |
| On March 6, 1992, at 1926 hours, the lRllA RMS channel momentarily spiked high resulting in a CP/P-VR system isolation signal. Channel indication returned to normal after the spike. The lRllA RMS channel was declared inoperable and an investigation into the cause of the event was initiated.
| | This LER addresses two (2) Engineered Safety Feature (ESF) signals initiated by the lRllA Containment Particulate Radiation Monitoring System (RMS) {IL} Monitor* channel. The signals were for Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System {BF} isolation. |
| The isolation valves were closed at the time and did not change position as a result of the isolation signal. Technical Specification 3.3.2.1, 3.3.3.1, and 3.4.6.l Action Statements were entered. At about the time of this event, a Chemistry technician was obtain_ing a Containment grab sample using the lRllA sample piping. The Chemistry technician was interviewed and his work procedure reviewed; however, it could not be shown that his activities contributed to the cause of the channel spike. Investigation of the March 6, 1992 event included checking the detector cable for insulation resistance (i.e., meggered the cable) and for continuity.
| | On March 6, 1992, at 1926 hours, the lRllA RMS channel momentarily spiked high resulting in a CP/P-VR system isolation signal. Channel indication returned to normal after the spike. The lRllA RMS channel was declared inoperable and an investigation into the cause of the event was initiated. The isolation valves were closed at the time and did not change position as a result of the isolation signal. |
| Results were satisfactory.
| | Technical Specification 3.3.2.1, 3.3.3.1, 3.3.3~9 and 3.4.6.l Action Statements were entered. |
| Also, the cable was manipulated, at the detector and the ratemeter drawer, in an attempt to reproduce the channel spiking; however, it could not be reproduced.
| | At about the time of this event, a Chemistry technician was obtain_ing a Containment grab sample using the lRllA sample piping. The Chemistry technician was interviewed and his work procedure reviewed; however, it could not be shown that his activities contributed to the cause of the channel spike. |
| The channel was returned to service and the Technical Specification Action Statements exited on March 7, 1992, at 0103 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 DESCRIPTION OF OCCURRENCE: | | Investigation of the March 6, 1992 event included checking the detector cable for insulation resistance (i.e., meggered the cable) and for continuity. Results were satisfactory. Also, the cable was manipulated, at the detector and the ratemeter drawer, in an attempt to reproduce the channel spiking; however, it could not be reproduced. The channel was returned to service and the Technical Specification Action Statements exited on March 7, 1992, at 0103 |
| {cont'd) LER NUMBER 92-007-01 PAGE 3 of 5 hours. Based on an engineering assessinent of investigation results, the lRllA detector was to be replaced.
| | |
| On April 29, 1992, at 0736 hours, the lRllA RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress.
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 3 of 5 DESCRIPTION OF OCCURRENCE: {cont'd) hours. Based on an engineering assessinent of investigation results, the lRllA detector was to be replaced. |
| Upon initiation of the isolation signal the Containment Purge valves closed per design. The CP/P-VR System isolation signal is an Engineered Safety Feature (ESF). Therefore, the Nuclear Regulatory Commission was notified in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii) on March 6, 1992, at 1944 hours and April 29, 1992, at 1034 hours, upon each ESF signal. Technical Specification Table 3.3-6 Action 20 states: "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1 11* Technical Specification 3.4.6.1 states: "The following Reactor Coolant Sys,tem leakage detection systems shall be OPERABLE:
| | On April 29, 1992, at 0736 hours, the lRllA RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress. Upon initiation of the isolation signal the Containment Purge valves closed per design. |
| * a. The containment atmosphere particulate radioactivity monitoring system, b. The containment sump level monitoring system, and c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system." Technical Specification 3.4.6.1 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." APPARENT CAUSE OF OCCURRENCE:
| | The CP/P-VR System isolation signal is an Engineered Safety Feature (ESF). Therefore, the Nuclear Regulatory Commission was notified in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii) on March 6, 1992, at 1944 hours and April 29, 1992, at 1034 hours, upon each ESF signal. |
| The root cause of both lRllA channel ESF signal actuations is attributed to "Design, Construction, Manufacturing/
| | Technical Specification Table 3.3-6 Action 20 states: |
| Installation" error, as per NUREG 1022, "Licensee Event Report System".
| | "With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1 11 |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SaJ_em Generating Station Unit 1 DOCKET NUMBER 5000272 APPARENT CAUSE OF OCCURRENCE: (cont'd) LER NUMBER 92-007-01 PAGE 4 of 5 Subsequent discussion with the vendor (Nuclear Research corporation) identified "older series of MD-3, 4, 5 detectors, can exhibit ground loop conditions which contributes to spurious count rates (spiking, transients).
| | * Technical Specification 3.4.6.1 states: |
| This is caused by connections between chassis ground and signal ground at* the detector and rate meter.11 Troubleshooting after the second channel spike did not identify any failed components.
| | "The following Reactor Coolant Sys,tem leakage detection systems shall be OPERABLE: * |
| A lRllA channel calibratio.n was successfully completed.
| | : a. The containment atmosphere particulate radioactivity monitoring system, |
| lRllA RMS channel spiking has occurred periodically in the past in which a specific cause could not be identified (e.g., reference LER 272/91-001-00).
| | : b. The containment sump level monitoring system, and |
| It is believed that those events were also caused by the ground loop condition discussed above. ANALYSIS OF OCCURRENCE:
| | : c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system." |
| | Technical Specification 3.4.6.1 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." |
| | APPARENT CAUSE OF OCCURRENCE: |
| | The root cause of both lRllA channel ESF signal actuations is attributed to "Design, Construction, Manufacturing/ Installation" error, as per NUREG 1022, "Licensee Event Report System". |
| | * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SaJ_em Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd) |
| | Subsequent discussion with the vendor (Nuclear Research corporation) identified that~ "older series of MD-3, 4, 5 detectors, can exhibit ground loop conditions which contributes to spurious count rates (spiking, transients). This is caused by connections between chassis ground and signal ground at* the detector and rate meter. 11 Troubleshooting after the second channel spike did not identify any failed components. A lRllA channel calibratio.n was successfully completed. |
| | lRllA RMS channel spiking has occurred periodically in the past in which a specific cause could not be identified (e.g., reference LER 272/91-001-00). It is believed that those events were also caused by the ground loop condition discussed above. |
| | ANALYSIS OF OCCURRENCE: |
| Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident. | | Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident. |
| * Air samples are pulled from the Containment through filter pap1ar which continuously moves past the. lRllA (Containment Particulate Radiation Monitor) detector. | | * Air samples are pulled from the Containment through filter pap1ar which continuously moves past the. lRllA (Containment Particulate Radiation Monitor) detector. The air sample then passes through a charcoal cartridge (monitored by the 1R12B detector) and is mixed into a fixed shielded volume where i t is viewed by the 1R12A (Containment Noble Gas Radiation Monitor) detector. The air sample is then returned to the Containment. |
| The air sample then passes through a charcoal cartridge (monitored by the 1R12B detector) and is mixed into a fixed shielded volume where it is viewed by the 1R12A (Containment Noble Gas Radiation Monitor) detector. | | The lRllA Containment Particulate Monitor, (a Na! scintillation type detector, model LFE MD5B) monitors air particulate gamma radio- |
| The air sample is then returned to the Containment. | | * activity in the Containment atmosphere. It is used to identify Reactor Coolant System (RCS) {AB} leakage in conjunction with the containment sump level monitoring system, and either the containment fan.cooler condensate flow rate or the containment atmosphere gaseous (1R12A) radioactivity monitoring system. |
| The lRllA Containment Particulate Monitor, (a Na! scintillation type detector, model LFE MD5B) monitors air particulate gamma radio-* activity in the Containment atmosphere. | | * Both the lRllA and 1R12A RMS channels provide an alarm signal which will cause the automatic isolation of the CP/P-VR System. |
| It is used to identify Reactor Coolant System (RCS) {AB} leakage in conjunction with the containment sump level monitoring system, and either the containment fan.cooler condensate flow rate or the containment atmosphere gaseous (1R12A) radioactivity monitoring system. | | During these events, airborne activity within Containment did not increase. Also, the CP/P-VR System isolation valves functioned per design. Therefore, this event did not affect the health or safety of the public. However, due to the automatic actuation signal of an ESF system, they are reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (iv). |
| * Both the lRllA and 1R12A RMS channels provide an alarm signal which will cause the automatic isolation of the CP/P-VR System. During these events, airborne activity within Containment did not increase. | | CORRECTIVE ACTION: |
| Also, the CP/P-VR System isolation valves functioned per design. Therefore, this event did not affect the health or safety of the public. However, due to the automatic actuation signal of an ESF system, they are reportable in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv). CORRECTIVE ACTION: A successful lRllA RMS channel calibration was completed after. the r LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: DOCKET NUMBER 5000272 LER NUMBER 92-007-01 PAGE 5 of 5 second lRllA channel spike. On May 26, 1992, at 0306 hours, the channel was returned to service. A new detector has been ordered from the manufacturer.which does not have the ground loop problem (see Apparent Cause of Occurrence section). | | A successful lRllA RMS channel calibration was completed after. the r |
| Upon receipt, it will be installed. | | |
| A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern. The circumstances surrounding the first lRllA ESF signal actuation event has been reviewed with applicable Chemistry Department personnel. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 5 of 5 CORRECTIVE ACTION: |
| MJP:pc SORC Mtg. 92-063 General Manager Salem Operations}} | | second lRllA channel spike. On May 26, 1992, at 0306 hours, the channel was returned to service. |
| | A new detector has been ordered from the manufacturer.which does not have the ground loop problem (see Apparent Cause of Occurrence section). Upon receipt, it will be installed. |
| | A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern. |
| | The circumstances surrounding the first lRllA ESF signal actuation event has been reviewed with applicable Chemistry Department personnel. |
| | General Manager ~ |
| | Salem Operations MJP:pc SORC Mtg. 92-063}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
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:RO)
MONTHYEARML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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Text
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- Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 28, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 SUPPLEMENTAL LICENSEE EVENT REPORT 92-007-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73. It addresses a second event which has the same root cause as the first event. Both events are reportable per Code of Federal Regulations 10CFR 50.73(a) (2) (iv). This report is required to be issued within thirty (30) days of event discovery.
Sincerely yours,
- c. A Vondra General Manager -
Salem Operations MJP:pc Distribution
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- NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS
- , AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE FACILITY NAME (1)
Salem Generating Station - Ul:iit,l I
OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
DOCKET NUMBER (2) o 1s I o Io I o 12 I 712 I
1 loF PAGE 131 o1s TITLE (4) 2 ESF Signal Actuations - Rad Moniitor Channel Spikes EVENT DATE (5) LEA NUMBER 16) REPORT DATE 17) OTHER FACILITIES INVOLVED (B)
MONTH DAY YEAR YEAR ttf SEQUENTIAL NUMBER [) REVlSION NUMBER MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) 01s1010101 I I ol 3 016 9 2 9 I 2 - ol o I 1 - o-11 ols THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR 21 8 91 2
§: (Ch*ck on* or mor* of th* following)(11) o I 5 Io Io I o I I I OPERATING MODE (9) l 20.402(b) 20.4051c)
,_ x 50.73(1)(2J(iv) 73.71(b)
POWER LEVEL (10) I 1 I 010 20.4061*)(1 )(i) 20.405(1)(1)(ii) 50.3B(c)(1) 50,3B(c)(2) -- 50.73(1)(2)(v) 50.73(1)(2)(vii) 73.71(c)
OTHER (Specify in Abstroct below and in Text, NRC. Form 20.406(1)(1 )(iii) 50.73(1)(2)(;) 60.73(1)(2)(viiil(A) 366AI
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- 50.73(1) (2) (iii) 50.73(1)(2)(*)
LICENSEE CONTACT FOR THIS LEA (12)
NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 61 O I 9 3 f 3 I .9 f - 12 IO f 2 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)
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MANUFAC- REPORTABLE MANUFAC* REPORTABLE CAUSE SYSTEM COMPONENT *.*.*.* *.- ..*:* ...,*.*.*.*. CAUSE SYSTEM COMPONENT TUR ER TO NPRDS
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- -:*: ........ :::-:-:*:*:* I I I ';::....1*11':._::...*1;.!.!:i_l::.**:**:.,-_*:.-:1 I I I I I I I .... I I I I SUPPLEMENTAL REPORT 'EXPECTED 114) MONTH DAY YEAR EXPECTED bi SUBMISSION I YES (If v*s. compl*t* EXPECTED SUBMISSION DATE! NO DATE (151 I I I ABSTRACT (Limit ro 1400 spaces. i.e., approxima.tefy fifteen single-spsce*type~ritten lines) (161 This LER addresses 2 Engineered Safety Feature {ESF) signals initiated by the 1R11A Containment Particulate Radiation Monitoring system (RMS)
Monitor channel. The signals were for Containment Purge/Pressure-Vaouum Relief (CP/P-VR) System isolation. On 3/6/92, the 1R11A RMS channel momentarily spiked high_resulting in a CP/P-VR System isolation signal.
Channel indication returned to normal after the spike. The 1Rl1A RMS channel was declared inoperable and an investigation into the cause of the event was initiated. Investigation included checking the detector cable for insulation resistance and for continuity. Results were satisfactory. The event could not be reproduced. The channel was returned to service on 3/7/92. On 4/29/92, the 1R11A RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress. Upon initiation of the isolation signal the containment Purge valves closed per design. The root cause of both lRllA RMS channel ESF signal actuations is "Design, Construction, Manufacturing/Installation" error. The detector can exhibit ground loop conditions. A successful 1R11A RMS channel calibration was completed after the second 1R11A channel spike. On May 26, *1992' the channel was returned to service. A new detector has been ordered from the manufacturer. Upon receipt, it will be installed. A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern.
NRC Form 366 (6-89)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are ideptif ied in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Two Engineered Safety Feature signal actuations; Radiation Monitoring System channel spikes Event Dates: 3/06/92 and 4/29/92 Report Date: 5/28/92 This report was initiated by Incident Report Nos.92-167 and 92-280.
CONDITIONS PRIOR TO OCCURRENCE:
3/6/92: Mode 1 Reactor Powet 100% - Unit Load 1160 MWe 4/29/92: Reactor defueled - 10 h Refueling outage in progress DESCRIPTION OF OCCURRENCE:
This LER addresses two (2) Engineered Safety Feature (ESF) signals initiated by the lRllA Containment Particulate Radiation Monitoring System (RMS) {IL} Monitor* channel. The signals were for Containment Purge/Pressure-Vacuum Relief (CP/P-VR) System {BF} isolation.
On March 6, 1992, at 1926 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.32843e-4 months <br />, the lRllA RMS channel momentarily spiked high resulting in a CP/P-VR system isolation signal. Channel indication returned to normal after the spike. The lRllA RMS channel was declared inoperable and an investigation into the cause of the event was initiated. The isolation valves were closed at the time and did not change position as a result of the isolation signal.
Technical Specification 3.3.2.1, 3.3.3.1, 3.3.3~9 and 3.4.6.l Action Statements were entered.
At about the time of this event, a Chemistry technician was obtain_ing a Containment grab sample using the lRllA sample piping. The Chemistry technician was interviewed and his work procedure reviewed; however, it could not be shown that his activities contributed to the cause of the channel spike.
Investigation of the March 6, 1992 event included checking the detector cable for insulation resistance (i.e., meggered the cable) and for continuity. Results were satisfactory. Also, the cable was manipulated, at the detector and the ratemeter drawer, in an attempt to reproduce the channel spiking; however, it could not be reproduced. The channel was returned to service and the Technical Specification Action Statements exited on March 7, 1992, at 0103
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 3 of 5 DESCRIPTION OF OCCURRENCE: {cont'd) hours. Based on an engineering assessinent of investigation results, the lRllA detector was to be replaced.
On April 29, 1992, at 0736 hours0.00852 days <br />0.204 hours <br />0.00122 weeks <br />2.80048e-4 months <br />, the lRllA RMS channel spiked, again resulting in a CP/P-VR System isolation signal. During this event, Containment Purge was in progress. Upon initiation of the isolation signal the Containment Purge valves closed per design.
The CP/P-VR System isolation signal is an Engineered Safety Feature (ESF). Therefore, the Nuclear Regulatory Commission was notified in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii) on March 6, 1992, at 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br /> and April 29, 1992, at 1034 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.93437e-4 months <br />, upon each ESF signal.
Technical Specification Table 3.3-6 Action 20 states:
"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1 11
"The following Reactor Coolant Sys,tem leakage detection systems shall be OPERABLE: *
- a. The containment atmosphere particulate radioactivity monitoring system,
- b. The containment sump level monitoring system, and
- c. Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system."
Technical Specification 3.4.6.1 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 />."
APPARENT CAUSE OF OCCURRENCE:
The root cause of both lRllA channel ESF signal actuations is attributed to "Design, Construction, Manufacturing/ Installation" error, as per NUREG 1022, "Licensee Event Report System".
- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SaJ_em Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd)
Subsequent discussion with the vendor (Nuclear Research corporation) identified that~ "older series of MD-3, 4, 5 detectors, can exhibit ground loop conditions which contributes to spurious count rates (spiking, transients). This is caused by connections between chassis ground and signal ground at* the detector and rate meter. 11 Troubleshooting after the second channel spike did not identify any failed components. A lRllA channel calibratio.n was successfully completed.
lRllA RMS channel spiking has occurred periodically in the past in which a specific cause could not be identified (e.g., reference LER 272/91-001-00). It is believed that those events were also caused by the ground loop condition discussed above.
ANALYSIS OF OCCURRENCE:
Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident.
- Air samples are pulled from the Containment through filter pap1ar which continuously moves past the. lRllA (Containment Particulate Radiation Monitor) detector. The air sample then passes through a charcoal cartridge (monitored by the 1R12B detector) and is mixed into a fixed shielded volume where i t is viewed by the 1R12A (Containment Noble Gas Radiation Monitor) detector. The air sample is then returned to the Containment.
The lRllA Containment Particulate Monitor, (a Na! scintillation type detector, model LFE MD5B) monitors air particulate gamma radio-
- activity in the Containment atmosphere. It is used to identify Reactor Coolant System (RCS) {AB} leakage in conjunction with the containment sump level monitoring system, and either the containment fan.cooler condensate flow rate or the containment atmosphere gaseous (1R12A) radioactivity monitoring system.
- Both the lRllA and 1R12A RMS channels provide an alarm signal which will cause the automatic isolation of the CP/P-VR System.
During these events, airborne activity within Containment did not increase. Also, the CP/P-VR System isolation valves functioned per design. Therefore, this event did not affect the health or safety of the public. However, due to the automatic actuation signal of an ESF system, they are reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (iv).
CORRECTIVE ACTION:
A successful lRllA RMS channel calibration was completed after. the r
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-007-01 5 of 5 CORRECTIVE ACTION:
second lRllA channel spike. On May 26, 1992, at 0306 hours0.00354 days <br />0.085 hours <br />5.059524e-4 weeks <br />1.16433e-4 months <br />, the channel was returned to service.
A new detector has been ordered from the manufacturer.which does not have the ground loop problem (see Apparent Cause of Occurrence section). Upon receipt, it will be installed.
A review will be conducted of other RMS channel detectors to determine if they too have a ground loop concern.
The circumstances surrounding the first lRllA ESF signal actuation event has been reviewed with applicable Chemistry Department personnel.
General Manager ~
Salem Operations MJP:pc SORC Mtg.92-063