Difference between revisions of "ML20023C247"
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PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
|Download: ML20023C247 (15)|
AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date May 10, 1983 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month April 1983 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 16 0 2 0 17 0 3 0 18 0 4 0 19 0 5 0 20 0 6 0 21 0 7 0 22 0 8 0 23 0 _
OPERATING DATA REPORT Docket No. 50-272 Date May 10, 1983 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status
- 1. Unit Name Salem No. 1 Notes
- 2. Reporting Period April 1983
- 3. Licensed Thermal Power (MWt) 3338
- 4. Nameplate Rating (Gross MWe) 1135
- 5. Design Electrical Rating (Net MWe) 1090
- 6. Maximum Dependable Capacity (Gross MWe)ll24
- 7. Maximum Dependable Capacity (Net MWe) 1079
- 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A
- 9. Power Level to Which Restricted, if any (Net MWe) 0
- 10. Reasons for Restrictions, if any REACTOR TRIP BREAKER PROBLEMS This Month Year to Date Cumulative
- 11. Hours in Reporting Period 719 2879 51888
- 12. No. of Hrs. Reactor was Critical 0 224.8 27950
- 13. Reactor Reserve Shutdown Hrs. 719 1558.6 2531.7
- 14. Hours Generator On-Line 0 15.8 26663.5
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 0 557.9 79170749
- 17. Gross Elec. Energy Generated (MWH) 0 2760 25967610
- 18. Net Elec. Energy Generated (MWH) (6694) (32355) 24562498
- 19. Unit Service Factor 0 .5 51.4
- 20. Unit Availability Factor 0 .5 51.4
- 21. Unit Capacity Factor (using MDC Net) 0 0 43.9
- 22. Unit Capacity Factor (using DER Net) 0 0 43.4
- 23. Unit Forced Outage Rate 100 99.2 31.5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page 3 of 16
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-272 -
REPORT MONTH APRIL 1983 Unit Name Salem No.1 Date May 10, 1983 Completed by L.K. Miller Telephone 609-935-6000 Extension 4455 ,
)' Method of Cause and Corrective Duration Shutting License No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Nuclear. Control Rod 83-030 2/25 F 1558.6 A 1 ---
IA CKTBRK Scram Mechanisms k
1 2 Reason 3 Method 4 Exhibit G S Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram, for Prepara- Source C-Refueling 3-Automatic Scram. tion lof Data
- D-Regulatory Restriction 4-Continuation of Entry Sheets
! E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report i G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)
! Page 4 of 16
MAJOR PLANT MODIFICATIONS DOCKET NO: 50-272 REPORT MONTH UNIT NAME: Salem 1 .
. APRIL 1983 .
DATE: May 10, 1983 ,
COMPLETED BY: L. K. Miller TELEPHONE: 609/935-6000 X4455
- DCR NO. PRINCIPLE SYSTEM SUBJECT LED-0014 Radiation Monitoring Add a new plant vent sampling system.
lEC-0777 Turbine Drains High pressure turbine interstage drain replacement using type ASTM-A-335 (P22) material.
lET-ll65 Fan Coil Unit #14 Add temperature connections to #14 FCU motor housing.
lEC-1351 Turbine Drains Revise pneumatic control for non-return valves of the extraction system.
lEC-1420 Radiation Monitoring Install a heating and AC system in the housing for the high range plant vent monitoring system.
lEC-1608 Reactor Coolant System Install in-line orifice on Barksdale pressure switch in #12 Reactor Coolant Pump Lift. Oil System. The orifice is to be .008" in diameter.
- DESIGN CHANGE REQUEST 8-1-7.R1 I
Page 5 of 16 b
MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH APRIL UNIT NAME: Salem 1 DATE: May 10, 1983 COMPLETED BY: L.K. Miller TELEPHONE: 609/935-6000 X4455_
- DCR NO. 10CFR50.59 SAFETY EVALUATION LED-0014 This change is an improvement and does not alter the production or quantity of radioactive materials. No unreviewed safety or environmental questions are involved.
lEC-0777 The material change does not alter the original design concept of the high pressure turbine. No unreviewed safety or environmental questions are involved.
lET-1165 The equipment installed by this DCR does not perform any control function nor will it affect any installed equipment. No unreviewed safety or environmental questions are involved, lEC-1351 Reduction of the closing time of these valves does not affect or change any existing safety analysis or the Technical Specifications. No unreviewed safety or environmental questions are involved, lEC-1362 Providing the cross connection will enhance system flexibility such that each motor driven feedwater pump can feed to all four or any of the steam generators if required. No unreviewed safety or environmental questions are involved.
lEC-1420 Implementation of this DCR insures ambient temperature remains within the correct operating temperature of the monitoring equipment. This ensures correct calibration of l the monitors and optimum performance. No unreviewed safety or environmental questions are involved.
- Design Change Request Page 6 of 16 i
PSE&G SALEM GENERATIWG STATION '
SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 .
WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 901008 M 1 RCS LOOL DELTA T FAILURE DESCRIPTION: GREATER THAN 4 F DIFFERENCE BETWEEN THE FOUR LOOP DELTA T's. 820801 CORRECTIVE ACTION: REPLACED LOW LEVEL AMP ITM-441B. REPLACED RTD ITE-441B.
901608 M 1 UNWRAPPED CABLE TRAYS FAILURE DESCRIPTION: INSPECT ALL WRAPPED CABLE TRAYS AFTER EACH REFUELING OUTAGE PRIOR TO GOING TO MODE 3. 830113 COr%"c.TIVE ACTION: COMPLETED CABLE TRAY INSPECTION IAW M4H. WO# MD 927328 ISSUED TO BRING TRAYS 1A229 AND 1A033 INTO COMPLIANCE.
902293 M 1 12 iTr:A,' GENERATOR ThiLLah JASCRIPTION: CONDUCT SECONDARY SIDE INSPECTICN OF S/G INTERNALS. 821105 UT OF J NOZZELS FOUND ALL TO BE 200/1000 WITHIN 5 MILLS.
902311 M 1 VALVE, 14AF11 FAILURE DESCRIPTION: OPEN/ INSPECT / REWORK OR REPLACE AS NECESSARY. 821020 CORRECTIVE ACTION: REPLACED PLUG AND REPACKED. 821123 903042 M 1 VALVE, ISJ78 BIT RECIRC FAILURE DESCRIPTION: VALVE LEAKS THRU. 820414 CORRECTIVE ACTION: REPLACED STEM ASSEMBLY. 821127 Page 7 of 16
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 903393 M 1 RMS, R-45 SAMPLE PUMP FAILURE DESCRIPTION: SAMPLE PUMP WILL NOT RUN IN AUTO OR MANUAL. 830304 CORRECTIVE ACTION: REPLACED DUNCO RELAY AND FUSE. REWIRED CIRCUIT PROPERLY.
830307 904875 M 1 VALVE, 11MS15 FAILURE DESCRIPTION: SAFETY VALVE LEAKS THROUGH SEAT. 820803 CORRECTIVE ACTION: REPAIRED VALVE WITH CROSBY SERVICE REP USING CROSBY MACHINE. 821120 904876 M 1 SAFETY VALVE 12MS15 FAILURE DESCRIPTION: VALVE LEAKING THROUGH SEAT. 820803 CORRECTIVE ACTION: COMPLETED REPAIR WITH CROSBY SERVICE REP LAPPED SEAT.
821120 908979 M 1 VALVE, 1PR1 FAILURE DESCRIPTION: VALVE LEAKS THROUGH. 821102 CORRECTIVE ACTION: REMOVED BURRS FROM CAGE SEAT. REPLACED PLUG AND STEM ASSEMBLY. 821104 909804 M 1 4KV 200 AMP SPARE BREAKER FAILURE DESCRIPTION: PERFORM TESTS ON BREAKER FOR POSSIBLE USE IN VITAL BUS INFEED BREAKER POSITION. 821117 CORRECTIVE ACTION: PERFORMED INSPECTION AND TIMING AS PER M3D and M3J AND INSTALLED IN 12BSD POSITION. 821119 Page 8 of 16
I SALEM UNIT 1 ,
830211 CORRECTIVE ACTION: MAGNET ASSEMBLY WAS STUCK. CHECKED CAL. 830211 919731 P 1 11 S/G STEAM DUMP TO ATMOS FAILURE DESCRIPTION: VERIFY OPERABILITY OF LOOP. 830214 CORRECTIVE ACTION: REPLACED HAGAN CONTROLLER FROM PC-516E WITH ONE TAKEN FROM 2PC-516E. PERFORMED CHANNEL CAL SAT.
919734 P 1 14 S/G LEVEL SETPOINT DEVIATION FAILURE DESCRIPTION: ALARM DOES NOT COME UP AT 5% FROM LEVEL SETPOINT. HIGH AC NOISE ON INPUT OF COMPARATOR. LLC-500 H/M CORRECTIVE ACTION: REPLACED CAPACITORS C2, 3, 4, 6 AND 7 IN ISOLATOR 1LM-505D. 830220 919736 P 1 14 RCP SEAL FLOW
FAILURE DESCRIPTION: RECORDER SHOWS STRAIGHT LINE INDICATION OF FLOW. 830301 CORRECTIVE ACTION: FREED STUCK HIGH RANGE TRANSMITTER. VERIFIED PROPER LOW RANGE INDICATION. 830301 922924 P 1 RMS, 1R21 FAILURE DESCRIPTION: CHANNEL FAILED. 830316 CORRECTIVE ACTION: REPLACED DETECTOR. 830316 Page 9 of 16
SALEM UNIT 1 .
WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 925367 P 1 RMS, 1R41A FAILURE DESCRIPTION: CHANNEL READING HIGH IN CONTROL ROOM. 830214 CORRECTIVE ACTION: FOUND CONTROLLER MODULE IMPROPERLY SEATED. RESEATED CONTROLLER. CHANNEL SAT.
925441 P 1 RMS, 1R5 9
FAILURE DESCRIPTION: CHANNEL FAILED LOW. 830207 CORRECTIVE ACTION: REPLACED DETECTOR AND PERFORMED DETECTOR CALIBRATION.
927565 P 1 SPARE SOURCE RANGE PRE AMP FAILURE DESCRIPTION: CORRECT AMPHENOL PLUG ON CABLES INIS7H-C0 AND INIS7G-CG TO CONFORM TO DCR ISC-0152 ODCN-C1. 830208 CORRECTIVE ACTION: FOUND WHITE WIRE PAIR #2 CABLE 7G ROLLED IN WITH WHITE PAIR #1 CABLE 7G. CORRECTED AND RANGE OUT CABLE.
Page 10 of 16 l
SALEM UNIT 1 .
WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 916973 M 1 12BSD INFEED BREAKER FAILURE DESCRIPTION: SPRING CHARGING FAILURE LIGHT REMAINS ON AFTER BREAKER IS MADE READY. HOWEVER, SPRING APPEARS TO BE CHARGED. 821120 CORRECTIVE ACTION: REPLACED AND CALIBRATED TIME RELAY AD-MO38. REWIRED CHARGING SPRING MOTOR LIMIT SWITCHES. 821120 923071 M 1 100 EL CONTAINMENT AIR LOCK FAILURE DESCRIPTION: INNER AND OUTER DOOR AIR FLOWS GREATER THAN 100%. REPLACE SEALS. 830301 CORRECTIVE ACTION: ADJUSTED DOORS.
923127 M 1 130 EL CONTAINMENT AIR LOCK FAILURE DESCRIPTION: AIR LOCK FAILED SP (0) 126.96.36.199A. HIGH AIR FLOW BOTH INNER AND OUTER DOORS. 830302 CORRECTIVE ACTION: DOOR GASKET ON INNER DOOR WAS OUT OF GROOVE. RESET GASKET 907248 P 1 VALVE, ICV 79 FAILURE DESCRIPTION: VALVE CAN NOT BE CLOSED FROM CONTROL CONSOLE. 821003 CORRECTIVE ACTION: CHECKED SV-488 OPERATING PROPERLY. REPLACED RUPTURED DIAPHRAM IN VALVE OPERATOR. 821129 917455 P 1 14 ACCUMULATOR LEVEL CHANNEL C FAILURE DESCRIPTION: CHANNEL FAILED HIGH. 821015 CORRECTIVE ACTION: NEW TRANSMITTER INSTALLED UNDER DCR lEC-1423. 821016 Page 11 of 16
SALEM UNIT 1 9 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 923133 P 1 RMS APD CHANNEL Rll & R12 FAILURE DESCRIPTION: BREAKER KEEPS TRIPPING. PUMP WILL NOT STAY ON. 830228' CORRECTIVE ACTION: INSTALLED NEW CONDE APD PUMP.
923167 M 1 12 CC PUMP ROOM COOLER FAILURE DESCRIPTION: COOLER HAS 5 GAL / MIN LEAK ON OUTLET SIDE. 830224 CORRECTIVE ACTION: REPAIRED LEAK AS PER MllE 923217 M 1 13 AUX FEEDWATER PUMP FAILURE DESCRIPTION: BEARING OIL RESERVOIR SIGHT GLASS LEAKING. 830222 CORRECTIVE ACTION: REMOVED EXCESS OIL FROM INBOARD AND OUTBOARD SIGHT GLASSES AND WIPED CLEAN.
925369 M 1 11 SERVICE WATER PUMP FAILURE DESCRIPTION: PUMP EXPANSION JOINT ON DISCHARGE LINE IS CRACKED FROM -
OVERPRESSURIZATION. 830206 CORRECTIVE ACTION: REPLACED EXPANSION JOINT.
925371 M 1 VALVE, 16SW24 FAILURE DESCRIPTION: VALVE TELL TALE LEAKING. APPEARS TO BE A BLOWN DIAPHRAM.
CORRECTIVE ACTION: REPLACED DIAPHRAM.
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIF ICATION 923206 P 1 VALVE, 1CV35 FAILURE DESCRIPTION: VALVE CONTROLLER IS TRIPPED TO MANUAL AND WILL NOT GO INTO AUTO. 830221 CORRECTIVE ACTION: REPLACED CAPACITORS C21, C26 AND TRANSISTOR 0 19 IN POWER SUPPLY OF CONTROLLER LLC-134B 923219 P 1 VALVE, ICH74 FAILURE DESCRIPTION: VALVE WAS NOT CONTROLLING FLOW PROPERLY. HAD TO JACK VALVE OPEN TO GET CORRECT FLOW. 830220 CORRECTIVE ACTION: STROKED VALVE SAT. FOUND TEMP CONTROLLER FOR 1CH74 TO HAVE WRONG SETPOINTS. INSTALLED PROPER SETPOINTS.
925362 P 1 1A EMERGENCY DIESEL FAILURE DESCRIPTION: DURING SURVEILLANCE TEST, RECEIVED HIGH JACKET WATER TEMP ALARM. BELIEVE COOLING WATER CONTROL VALVE SETPOINT POSITION IS TOO CLOSE TO THE CLOSED POSITION. 830210 .
CORRECTIVE ACTION: FOUND HIGH SIDE SENSING LINE TO DELTA P CONTROLLER SECURED. OPENED VALVE AND TESTED SAT.
925363 P 1 RMS, 1R5 FAILURE DESCRIPTION: FAILURE LIGHT FLASHING. 830210 CORRECTIVE ACTION: REPLACED DETECTOR AND PERFORMED DETECTOR CALIBRATION.
925366 P 1 14 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION: SERVICE WATER FLOW INDICATION ERRATIC. 830210 CORRECTIVE ACTION: FOUND SETPOINT REGULATORS NOT SET PROPERLY FOR AUTO CONTROL. SET UP HIGH FLOW FOR 2500 GPM AND LOW' FLOW FOR 700 GPM.
Page 13 of 16
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 927743 P 1 . VALVE, 13MS10 ATMOS RELIEF FAILURE DESCRIPTION: VERIFY 13MS10 CONTROL AND VALVE OPERATION. 830215 CORRECTIVE ACTION: TIGHTENED ZERO LOCKING NUTS ON VALVE POSITIONER. REPLACED 1PC-536C WITH CONTROLLER FROM UNIT 2.
Page 14 of 16
SALEM UNIT 1 OPERATIONS
REPORT APRIL 1983 Unit I was placed in cold shutdown in February following two occurrences of failure of the Reactor Trip Breakers to operate upon receiving an automatic signal from the Solid State Protection System.
The unit has remained shutdown throughout the months of March and April while extensive investigations were conducted by PSE&G, the NRC, and Westinghouse. A number of short and long term corrective actions were identified by these investigations. On April 26, 1983, the NRC Commissioners voted 4 to 1 to authorize the NRC Staff to allow startup of Salem Unit 1. Startup of the Unit is expected shortly, following completion of a requirement for the Office of Nuclear Reactor Regulation.
Page 15 of 16
REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY: L.K. Miller UNIT NAME: Salem 1 DATE: May 10, 1983 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month May 1983
- 1. Refueling information has changed from last month:
YES NO X
- 2. Scheduled date for next refueling: December 31, 1983
- 3. Scheduled date for restart following refueling: March 11, 1984
- 4. A) Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE 5/1/83 B) Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X If no, when is it scheduled? December 1983
- 5. Scheduled date (s) for submitting proposed licensing action:
December 1983 (if required)
- 6. Important licensing considerations associated with refueling:
- 7. Number of Fuel Assemblies:
A) Incore 193 B) In Spent Fuel Storage 212
- 8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
- 9. Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity: September 1996 8-1-7.R4 Page 16 of 16
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