|
|
| (4 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 12/21/1992 | | | issue date = 12/21/1992 |
| | title = LER 92-024-00:on 921123,SI Pump Declared Inoperable When Room Cooler Condensate Leakage Observed Leaking Onto Pump Motor.Caused by Design,Mfg,Const/Installation.Drip Bag Installed on Room Cooler drain.W/921221 Ltr | | | title = LER 92-024-00:on 921123,SI Pump Declared Inoperable When Room Cooler Condensate Leakage Observed Leaking Onto Pump Motor.Caused by Design,Mfg,Const/Installation.Drip Bag Installed on Room Cooler drain.W/921221 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 = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:-e Public Service Electr_ic and Gas Company. P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:-e OPS~G Public Service Electr_ic and Gas Company. P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 21 , 1-9 9 2 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
|
| |
|
| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-024-00 December 21 , 1-9 9 2 .This Licensee Event Report is being sµbmitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). This report required to be issued within thirty (30) days of event discovery.
| |
| MJP:pc Distribution The Enerav F'eopie 9212230248 921221 PDR ADOCK -05000272 5 PDR Sincerely yours, c. AVondra General Manager -Salem Operations
| |
| -;;;::----
| |
| NRC FOJcM 366 16-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 LICENSEE EVENT REPORT (LER) . FACILITY NAME (1) Salem Generating Station -Unit 1 TITLE 141 TS 3.0.3 Entry; Both SI Pumps :Inoperable EVENT DATE (5) LER NUMBER (6) REPORT DATE 17) MONTH DAY YEAR YEAR .it tt MONTH DAY YEAR 1 11 2 I 3 .9 2 9 I 2 -ol 214 o lo l I 2 2 I 1 9 12 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE' PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT A.ND BUDGET, WASHINGTON, DC 20503 . I DOCKET NUMBER (2) I PAGE 131 o 15 I o Io I o 12 I 71 2 1 loF o 15 OTHER FACILITIES INVOLVED (Bl FACILITY NAMES DOCKET NUMBERISl OPERATING MODE IBl THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Ch*ck one or mor* of th* following/
| |
| 111) 20.4051cl 60.73l*ll2)(ivl 73.71lbl -i---1 20.402lbl
| |
| .........
| |
| --1----l 60.38lcll1l 60.73l*ll2lM 73.71lcl ---POWER I 20.4061*111)(1)
| |
| LEVEL l Q(Q -1101 1 20.4051011111111 50.381cll2l 60.73(e)(2)(vii)
| |
| OTHER (Spacify in Abstr*ct ---b*low *nd in Text, NRC Form x NAME 20.4051*111
| |
| )(iii) 20.406l*ll1lllvl 20.405l*ll1lM M. J. Pollack -LER Coordinator 50.731*ll2llil
| |
| --G0.731ell2lliil
| |
| --50.73l*ll2lliiil LICENSEE CONTACT FOR THIS LER 112) 60.73lell2llviiil1Al 60.731ell2llviiillBI 60.73lell2llxl AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) CAUSE SYSTEM COMPONENT I I I I I I I I MANUFAC* TUR ER I I I I I I 111::1:!1j,i*j,:.j,.*:*1.:::.::.::,*1*::1!:!:J*::.:**
| |
| CAUSE SYSTEM I I COMPONENT MANUFAC* TUR ER I I I I I I I I I I I I 366A/ TELEPHONE NUMBER SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 n YES (If yes, comp/st* EXPECTED SUBMiSSION DATE} b:l NO I I ABSTRACT (Limit to 1400 spaces, i.e., approximately fifterm singfs.sjJsce typewritten lint1s} (16) On 11/23/92, the 11 Safety-Injection
| |
| {SI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water {SW) header had been removed from service making the 12 SI Pump inoperable due to inoperability of the lube oil cooler. Technical Specification 3.5.2 Actions do not apply with both SI Pumps declared inoperable; therefore, Tech. Spec. 3.0.3 was entered. A Unit shutdown commenced.
| |
| The cause of this event is "Design, Manufacturing, Construction/Installation".
| |
| The room cooler design includes a drip pan which collects condensate.
| |
| However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach was taken to declare the pump inoperable until it could be tested. A contributing factor to this event was that the room thermostat was found set at 60°F instead of ss°F. This thermostat is *interlocked with the room cooler (i.e., fan and SW valve position control).
| |
| Consequently, the room cooler was on constant run resulting in excessive condensate The thermostat was reset. The other Room Cooler thermostat controls were verified to be appropriately set. Testing of 11 SI Pump motor was successful.
| |
| The pump was declared operable and Tech. Spec. 3.0.3 was exited. Power had been reduced to 92%. Drain line installation, on those room coolers without condensate drip pan drain lines, is being assessed.
| |
| NRC Form 366 16*89) I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
| |
| Westinghouse
| |
| -Pressurized Water Reactor LER NUMBER 92-024-00 PAGE 2 of 5 Energy Industry Identification system (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
| |
| Technical Specification
| |
|
| |
|
| ====3.0.3 entry====
| | SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-024-00 |
| both Safety Injection Pumps inoperable Event Date: 11/23/92 Report Date: 12/21/92 This report was initiated by Incident Report N6. 92-780. | | .This Licensee Event Report is being sµbmitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B). This report i~ required to be issued within thirty (30) days of event discovery. |
| | Sincerely yours, |
| | : c. AVondra General Manager - |
| | Salem Operations MJP:pc Distribution The Enerav F'eopie 9212230248 921221 PDR ADOCK -05000272 5 PDR |
| | |
| | NRC FOJcM 366 U.S. NUCLEAR REGULATORY COMMISSION 16-89) 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 (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE' PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT A.ND BUDGET, WASHINGTON, DC 20503 . |
| | . FACILITY NAME (1) DOCKET NUMBER (2) I PAGE 131 Salem Generating Station - Unit 1 TITLE 141 Io 15 I o Io I o 12 I 71 2 1 loF o 15 TS 3.0.3 Entry; Both SI Pumps :Inoperable EVENT DATE (5) LER NUMBER (6) REPORT DATE 17) OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR .it SE~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISl 1 11 2 3I .9 2 9 I 2 - ol 214 olo l I2 2 I 1 9 12 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Ch*ck one or mor* of th* following/ 111) |
| | MODE IBl 1 |
| | I 20.402lbl 20.4051cl 60.73l*ll2)(ivl 73.71lbl 1-~~--..~~ .........--1----l i-- |
| | POWER 20.4061*111)(1) 60.38lcll1l 60.73l*ll2lM 73.71lcl LEVEL 1101 l 1 Q(Q - 20.4051011111111 |
| | - 50.381cll2l 60.73(e)(2)(vii) |
| | - OTHER (Spacify in Abstr*ct |
| | -x - |
| | b*low *nd in Text, NRC Form 20.4051*111 )(iii) 50.731*ll2llil 60.73lell2llviiil1Al 366A/ |
| | 20.406l*ll1lllvl |
| | - G0.731ell2lliil 60.731ell2llviiillBI 20.405l*ll1lM |
| | - 50.73l*ll2lliiil 60.73lell2llxl LICENSEE CONTACT FOR THIS LER 112) |
| | NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) |
| | CAUSE SYSTEM COMPONENT MANUFAC* |
| | TUR ER R~60~~~~~E 111::1:!1j,i*j,:.j,.*:*1.:::.::.::,*1*::1!:!:J*::.:** CAUSE SYSTEM COMPONENT MANUFAC* |
| | TUR ER I I I I I I I 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 YEAR EXPECTED n YES (If yes, comp/st* EXPECTED SUBMiSSION DATE} b:l ABSTRACT (Limit to 1400 spaces, i.e., approximately fifterm singfs.sjJsce typewritten lint1s} (16) |
| | NO SUBMISSION DATE 1151 I I I On 11/23/92, the 11 Safety-Injection {SI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water {SW) header had been removed from service making the 12 SI Pump inoperable due to inoperability of the lube oil cooler. Technical Specification 3.5.2 Actions do not apply with both SI Pumps declared inoperable; therefore, Tech. Spec. 3.0.3 was entered. A Unit shutdown commenced. The cause of this event is "Design, Manufacturing, Construction/Installation". The room cooler design includes a drip pan which collects condensate. |
| | However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach was taken to declare the pump inoperable until it could be tested. A contributing factor to this event was that the room thermostat was found set at 60°F instead of ss°F. This thermostat is *interlocked with the room cooler (i.e., fan and SW valve position control). Consequently, the room cooler was on constant run resulting in excessive condensate buildup~ The thermostat was reset. The other Room Cooler thermostat controls were verified to be appropriately set. Testing of 11 SI Pump motor was successful. The pump was declared operable and Tech. Spec. 3.0.3 was exited. Power had been reduced to 92%. Drain line installation, on those room coolers without condensate drip pan drain lines, is being assessed. |
| | NRC Form 366 16*89) |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION: |
| | Westinghouse - Pressurized Water Reactor Energy Industry Identification system (EIIS) codes are identified in the text as {xx} |
| | IDENTIFICATION OF OCCURRENCE: |
| | Technical Specification 3.0.3 entry: both Safety Injection Pumps inoperable Event Date: 11/23/92 Report Date: 12/21/92 This report was initiated by Incident Report N6. 92-780. |
| * CONDITIONS PRIOR TO OCCURRENCE: | | * CONDITIONS PRIOR TO OCCURRENCE: |
| Mode 1 Reactor Power 100% -Unit Load 1160 MWe . DESCRIPTION OF OCCURRENCE: | | Mode 1 Reactor Power 100% - Unit Load 1160 MWe |
| on November 23, 1992, at 0900 hours, the 11 Safety Injection | | . DESCRIPTION OF OCCURRENCE: |
| *csI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water (SW) {BI} header had been removed from service to support Chiller SW piping repairs. Consequently, 12 SI Pump. lube oil cooler was inoperable due to lack of SW coolant flow. This made 12 SI Pump inoperable. | | on November 23, 1992, at 0900 hours, the 11 Safety Injection *csI) |
| Technical Specification 3.5.2 Actions do not apply with both.SI Pumps declared inoperable; therefore, Technical Specification 3.0.3 was entered upon declaring 11 SI Pump inoperable. | | Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water (SW) {BI} header had been removed from service to support Chiller SW piping repairs. Consequently, 12 SI Pump. lube oil cooler was inoperable due to lack of SW coolant flow. This made 12 SI Pump inoperable. |
| The Nuclear Regulatory Commission was notified of the initiation of a controlled shutdown (per Technical Specification 3.0.3) on November 23, 1992, at 1011 hours, in accordance with Code of Federal Regulations lOCFR 50. 72 (b) (l)_(i) (A). Technical Specification | | Technical Specification 3.5.2 Actions do not apply with both.SI Pumps declared inoperable; therefore, Technical Specification 3.0.3 was entered upon declaring 11 SI Pump inoperable. The Nuclear Regulatory Commission was notified of the initiation of a controlled shutdown (per Technical Specification 3.0.3) on November 23, 1992, at 1011 hours, in accordance with Code of Federal Regulations 10CFR |
| | : 50. 72 (b) (l)_(i) (A). |
| | Technical Specification 3.5.2 states: |
| | Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following. injection systell\s: ... |
| | : a. One.OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; |
| | : 1. Discharging into each Reactor Coolant System |
|
| |
|
| ====3.5.2 states====
| | LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) |
| Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following.
| | (RCS) cold leg. |
| injection systell\s:
| | : b. One OPERABLE safety injection pump and associa~ed flow path capable of taking suction from the refueling water storage tank and transferring suction to the r~sidual heat removal pump discharge piping and; |
| ... a. One.OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1. Discharging into each Reactor Coolant System LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 92-024-00 PAGE 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) (RCS) cold leg. b. One OPERABLE safety injection pump and flow path capable of taking suction from the refueling water storage tank and transferring suction to the heat removal pump discharge piping and; 1. Discharging into each RCS cold leg, and; upon initiation, 2. Discharging into its two associated RCS hot legs. c. One OPERABLE residual heat removal heat pump and etc." Technical Specification
| | : 1. Discharging into each RCS cold leg, and; upon m~nual initiation, |
| | : 2. Discharging into its two associated RCS hot legs. |
| | : c. One OPERABLE residual heat removal heat pump and etc." |
| | Technical Specification 3.0.3 states: |
| | "When a Limiting Condition for Operation is not met except as provided in the a?sociated ACTION requirements, within one hour action*shall be initiated to place the unit in a MODE in which the specification does not apply by placing.it, as applicable, in: |
| | : 1. At least HOT STANDBY within the next 6 hours, |
| | : 2. At least HOT SHUTDOWN within the following 6 hours, and |
| | : 3. At least COLD SHUTDOWN within tbe subsequent 24 hours .. |
| | Where corrective measures are completed that permit operation under the ACTION 'requirements, the ACTION' may be*. taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation. |
| | Exceptions to these requirements are stated in the individual specifications." |
| | APPARENT CAUSE OF OCCURRENCE: |
| | The cause of this*event is "Design, Manufacturing, Construction/ |
| | Installation", per.NUREG.1022 {Licensee Event Report Program). The room cooler design includes a.drip pan which collects condensate. |
| | However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach_was taken to declare the pump inoperable until. *it could be tested .. |
| | A contributing factor to this event was that the room 'thermostat was found set at 60°F instead of ss°F. This thermostat is interlocked with the room cooler (i.e., fan and SW valve position control). |
| | Consequently, the room .cooler was on constant run resulting in excessive condensate buildup. The as found thermostat setting did not affect operability of equipment in the.SI Pump Room. Also, |
|
| |
|
| ====3.0.3 states====
| | . '"****--*-- -*~-~-* ~---** .. *------**-* |
| "When a Limiting Condition for Operation is not met except as provided in the a?sociated ACTION requirements, within one hour action*shall be initiated to place the unit in a MODE in which the specification does not apply by placing.it, as applicable, in: 1. At least HOT STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within tbe subsequent 24 hours .. Where corrective measures are completed that permit operation under the ACTION 'requirements, the ACTION' may be*. taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 *4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd) system Engineering_ determined that no ~etting would affect component operability since its maximum setting is 100 F. |
| Exceptions to these requirements are stated in the individual specifications." APPARENT CAUSE OF OCCURRENCE:
| | ANALYSIS OF OCCURRENCE: |
| The cause of this*event is "Design, Manufacturing, Construction/
| | The Emergency Core Cooling system incorporates high head safety injection pumps (centrifugal charging pumps), intermediate head safety injection pumps (SI Pumps) and low. head safety injection pumps (Residual Heat Removal Pumps).* There are two of each type of pump where either pump .provides 100% of the flow requirements during ECCS operation. In this event, 12 SI Pump was inoperable due to* 11 SW |
| Installation", per.NUREG.1022
| | * Header being out of service (as identified.in the Description of I Occurrence Section). 11 SI Pump was cleared and tagged to support I testing of its motor. |
| {Licensee Event Report Program).
| | * Per Technical Specification 3.0.3, a Unit shutdown was commenced.* On November 23, 1992, *.at 1120 hours, upon 11 SI Pump's return to service, the Specification was exited. Power hadbeen reduced to |
| The room cooler design includes a.drip pan which collects condensate.
| | -92%. |
| However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach_was taken to declare the pump inoperable until. *it could be tested .. A contributing factor to this event was that the room 'thermostat was found set at 60°F instead of ss°F. This thermostat is interlocked with the room cooler (i.e., fan and SW valve position control).
| | During the period of 11 SI Pump inoperability, safety injection was not required. Also, the constraints of Technical Specif~cation 3.0.3 were met; therefore, .this event did not affect the health or safety of the public. |
| Consequently, the room .cooler was on constant run resulting in excessive condensate buildup. The as found thermostat setting did not affect operability of equipment in the.SI Pump Room. Also,
| | * Technical Specification 3.0.3 was required to be entered with both SI Pumps inoperable. Therefore, this event is reportable to the Nuclear Regulatory Commission in accordance with the Code of Federal . |
| * ---. '"****--*-- | | Regulations 10CFR s9.73(a) (2) (i) (B). |
| .. *------**-* | | CORRECTIVE ACTION: |
| --LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 APPARENT CAUSE OF OCCURRENCE: (cont'd) LER NUMBER 92-024-00 PAGE *4 of 5 system Engineering_
| | Upon identification of the condensate overflow, the 11 SI Pump motor was wiped down. A drip bag was installed on the room cooler drain to collect condensate overflow. Testing of 11 SI Pump motor to check |
| determined that no would affect component operability since its maximum setting is 100 F. ANALYSIS OF OCCURRENCE: | | ** resistance (i.e. , 1 minute "megger" test) , was successful. The motor was then started and acceptable current measurements were observed. |
| The Emergency Core Cooling system incorporates high head safety injection pumps (centrifugal charging pumps), intermediate head safety injection pumps (SI Pumps) and low. head safety injection pumps (Residual Heat Removal Pumps).* There are two of each type of pump where either pump .provides 100% of the flow requirements during ECCS operation. | | The pump was declared operable, at 1120 hours, on November 23, 1992 and Technical Specification 3. o.. 3 was exited and the Unit returned to full power operation. |
| In this event, 12 SI Pump was inoperable due to* 11 SW | | The other.room coolers (e.g., Auxiliary Feedwater Pump area, *.. |
| * Header being out of service (as identified.in the Description of Occurrence Section). | | etc. ) were inspected.* |
| 11 SI Pump was cleared and tagged to support testing of its motor. | | System Engineering is assessing whether drain line installation is needed on room coolers without condensa~e drip pan drain lines. |
| * Per Technical Specification 3.0.3, a Unit shutdown was commenced.* | | The incorrect as f ourtd setting of the SI Pump Room Cooler thermostat was corrected. The other Salem Units 1 and 2 Room Cooler thermostat controls were verified to be appropriately set. |
| On November 23, 1992, *.at 1120 hours, upon 11 SI Pump's return to service, the Specification was exited. Power hadbeen reduced to -92%. During the period of 11 SI Pump inoperability, safety injection was not required. | | |
| Also, the constraints of Technical 3.0.3 were met; therefore, .this event did not affect the health or safety of the public. | | .. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 5 of 5 CORRECTIVE ACTION: (cont'd) |
| * Technical Specification 3.0.3 was required to be entered with both SI Pumps inoperable. | | Room Cooler thermostats will be posted to indicate their intended function. |
| Therefore, this event is reportable to the Nuclear Regulatory Commission in accordance with the Code of Federal . Regulations lOCFR s9.73(a) (2) (i) (B). CORRECTIVE ACTION: Upon identification of the condensate overflow, the 11 SI Pump motor was wiped down. A drip bag was installed on the room cooler drain to collect condensate overflow. | | eneral Manager - |
| Testing of 11 SI Pump motor to check * | | Salem Operations MJP:pc SORC Mtg. 92-125 I}} |
| * resistance (i.e. , 1 minute "megger" test) , was successful. | |
| The motor was then started and acceptable current measurements were observed. | |
| The pump was declared operable, at 1120 hours, on November 23, 1992 and Technical Specification | |
| : 3. o .. 3 was exited and the Unit returned to full power operation.
| |
| The other.room coolers (e.g., Auxiliary Feedwater Pump area, *.. etc. ) were inspected.* | |
| System Engineering is assessing whether drain line installation is needed on room coolers without drip pan drain lines. The incorrect as f ourtd setting of the SI Pump Room Cooler thermostat was corrected. | |
| The other Salem Units 1 and 2 Room Cooler thermostat controls were verified to be appropriately set. I I ! | |
| .. * | |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: (cont'd) DOCKET NUMBER 5000272 LER NUMBER 92-024-00 PAGE 5 of 5 Room Cooler thermostats will be posted to indicate their intended function.
| |
| MJP:pc SORC Mtg. 92-125 eneral Manager -Salem Operations I}} | |
Similar Documents at Salem |
|---|
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
[Table view] |
Text
-e OPS~G Public Service Electr_ic and Gas Company. P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 21 , 1-9 9 2 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 92-024-00
.This Licensee Event Report is being sµbmitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B). This report i~ required to be issued within thirty (30) days of event discovery.
Sincerely yours,
- c. AVondra General Manager -
Salem Operations MJP:pc Distribution The Enerav F'eopie 9212230248 921221 PDR ADOCK -05000272 5 PDR
NRC FOJcM 366 U.S. NUCLEAR REGULATORY COMMISSION 16-89) 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 (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE' PAPERWORK REDUCTION PROJECT 13150-0104), OFFICE OF MANAGEMENT A.ND BUDGET, WASHINGTON, DC 20503 .
. FACILITY NAME (1) DOCKET NUMBER (2) I PAGE 131 Salem Generating Station - Unit 1 TITLE 141 Io 15 I o Io I o 12 I 71 2 1 loF o 15 TS 3.0.3 Entry; Both SI Pumps :Inoperable EVENT DATE (5) LER NUMBER (6) REPORT DATE 17) OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR .it SE~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISl 1 11 2 3I .9 2 9 I 2 - ol 214 olo l I2 2 I 1 9 12 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Ch*ck one or mor* of th* following/ 111)
MODE IBl 1
I 20.402lbl 20.4051cl 60.73l*ll2)(ivl 73.71lbl 1-~~--..~~ .........--1----l i--
POWER 20.4061*111)(1) 60.38lcll1l 60.73l*ll2lM 73.71lcl LEVEL 1101 l 1 Q(Q - 20.4051011111111
- 50.381cll2l 60.73(e)(2)(vii)
- OTHER (Spacify in Abstr*ct
-x -
b*low *nd in Text, NRC Form 20.4051*111 )(iii) 50.731*ll2llil 60.73lell2llviiil1Al 366A/
20.406l*ll1lllvl
- G0.731ell2lliil 60.731ell2llviiillBI 20.405l*ll1lM
- 50.73l*ll2lliiil 60.73lell2llxl LICENSEE CONTACT FOR THIS LER 112)
NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)
CAUSE SYSTEM COMPONENT MANUFAC*
TUR ER R~60~~~~~E 111::1:!1j,i*j,:.j,.*:*1.:::.::.::,*1*::1!:!:J*::.:** CAUSE SYSTEM COMPONENT MANUFAC*
TUR ER I I I I I I I 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 YEAR EXPECTED n YES (If yes, comp/st* EXPECTED SUBMiSSION DATE} b:l ABSTRACT (Limit to 1400 spaces, i.e., approximately fifterm singfs.sjJsce typewritten lint1s} (16)
NO SUBMISSION DATE 1151 I I I On 11/23/92, the 11 Safety-Injection {SI) Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water {SW) header had been removed from service making the 12 SI Pump inoperable due to inoperability of the lube oil cooler. Technical Specification 3.5.2 Actions do not apply with both SI Pumps declared inoperable; therefore, Tech. Spec. 3.0.3 was entered. A Unit shutdown commenced. The cause of this event is "Design, Manufacturing, Construction/Installation". The room cooler design includes a drip pan which collects condensate.
However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach was taken to declare the pump inoperable until it could be tested. A contributing factor to this event was that the room thermostat was found set at 60°F instead of ss°F. This thermostat is *interlocked with the room cooler (i.e., fan and SW valve position control). Consequently, the room cooler was on constant run resulting in excessive condensate buildup~ The thermostat was reset. The other Room Cooler thermostat controls were verified to be appropriately set. Testing of 11 SI Pump motor was successful. The pump was declared operable and Tech. Spec. 3.0.3 was exited. Power had been reduced to 92%. Drain line installation, on those room coolers without condensate drip pan drain lines, is being assessed.
NRC Form 366 16*89)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification system (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Technical Specification 3.0.3 entry: both Safety Injection Pumps inoperable Event Date: 11/23/92 Report Date: 12/21/92 This report was initiated by Incident Report N6.92-780.
- CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 Reactor Power 100% - Unit Load 1160 MWe
. DESCRIPTION OF OCCURRENCE:
on November 23, 1992, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the 11 Safety Injection *csI)
Pump was declared inoperable when room cooler condensate leakage was observed leaking onto the pump's motor. Prior to this event, the 11 Service Water (SW) {BI} header had been removed from service to support Chiller SW piping repairs. Consequently, 12 SI Pump. lube oil cooler was inoperable due to lack of SW coolant flow. This made 12 SI Pump inoperable.
Technical Specification 3.5.2 Actions do not apply with both.SI Pumps declared inoperable; therefore, Technical Specification 3.0.3 was entered upon declaring 11 SI Pump inoperable. The Nuclear Regulatory Commission was notified of the initiation of a controlled shutdown (per Technical Specification 3.0.3) on November 23, 1992, at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br />, in accordance with Code of Federal Regulations 10CFR
- 50. 72 (b) (l)_(i) (A).
Technical Specification 3.5.2 states:
Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following. injection systell\s: ...
- a. One.OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and;
- 1. Discharging into each Reactor Coolant System
LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd)
(RCS) cold leg.
- b. One OPERABLE safety injection pump and associa~ed flow path capable of taking suction from the refueling water storage tank and transferring suction to the r~sidual heat removal pump discharge piping and;
- 1. Discharging into each RCS cold leg, and; upon m~nual initiation,
- 2. Discharging into its two associated RCS hot legs.
- c. One OPERABLE residual heat removal heat pump and etc."
Technical Specification 3.0.3 states:
"When a Limiting Condition for Operation is not met except as provided in the a?sociated ACTION requirements, within one hour action*shall be initiated to place the unit in a MODE in which the specification does not apply by placing.it, as applicable, in:
- 1. 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 />,
- 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- 3. At least COLD SHUTDOWN within tbe subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ..
Where corrective measures are completed that permit operation under the ACTION 'requirements, the ACTION' may be*. taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation.
Exceptions to these requirements are stated in the individual specifications."
APPARENT CAUSE OF OCCURRENCE:
The cause of this*event is "Design, Manufacturing, Construction/
Installation", per.NUREG.1022 {Licensee Event Report Program). The room cooler design includes a.drip pan which collects condensate.
However, there is no drainage when the drip pan is full. The pan filled resulting in spillage onto the 11 SI Pump motor. Although the SI Pump motor is a "drip proof motor", the conservative approach_was taken to declare the pump inoperable until. *it could be tested ..
A contributing factor to this event was that the room 'thermostat was found set at 60°F instead of ss°F. This thermostat is interlocked with the room cooler (i.e., fan and SW valve position control).
Consequently, the room .cooler was on constant run resulting in excessive condensate buildup. The as found thermostat setting did not affect operability of equipment in the.SI Pump Room. Also,
. '"****--*-- -*~-~-* ~---** .. *------**-*
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 *4 of 5 APPARENT CAUSE OF OCCURRENCE: (cont'd) system Engineering_ determined that no ~etting would affect component operability since its maximum setting is 100 F.
ANALYSIS OF OCCURRENCE:
The Emergency Core Cooling system incorporates high head safety injection pumps (centrifugal charging pumps), intermediate head safety injection pumps (SI Pumps) and low. head safety injection pumps (Residual Heat Removal Pumps).* There are two of each type of pump where either pump .provides 100% of the flow requirements during ECCS operation. In this event, 12 SI Pump was inoperable due to* 11 SW
- Header being out of service (as identified.in the Description of I Occurrence Section). 11 SI Pump was cleared and tagged to support I testing of its motor.
- Per Technical Specification 3.0.3, a Unit shutdown was commenced.* On November 23, 1992, *.at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, upon 11 SI Pump's return to service, the Specification was exited. Power hadbeen reduced to
-92%.
During the period of 11 SI Pump inoperability, safety injection was not required. Also, the constraints of Technical Specif~cation 3.0.3 were met; therefore, .this event did not affect the health or safety of the public.
Regulations 10CFR s9.73(a) (2) (i) (B).
CORRECTIVE ACTION:
Upon identification of the condensate overflow, the 11 SI Pump motor was wiped down. A drip bag was installed on the room cooler drain to collect condensate overflow. Testing of 11 SI Pump motor to check
- resistance (i.e. , 1 minute "megger" test) , was successful. The motor was then started and acceptable current measurements were observed.
The pump was declared operable, at 1120 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.2616e-4 months <br />, on November 23, 1992 and Technical Specification 3. o.. 3 was exited and the Unit returned to full power operation.
The other.room coolers (e.g., Auxiliary Feedwater Pump area, *..
etc. ) were inspected.*
System Engineering is assessing whether drain line installation is needed on room coolers without condensa~e drip pan drain lines.
The incorrect as f ourtd setting of the SI Pump Room Cooler thermostat was corrected. The other Salem Units 1 and 2 Room Cooler thermostat controls were verified to be appropriately set.
.. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-024-00 5 of 5 CORRECTIVE ACTION: (cont'd)
Room Cooler thermostats will be posted to indicate their intended function.
eneral Manager -
Salem Operations MJP:pc SORC Mtg.92-125 I
