ML20211E578
| ML20211E578 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1987 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8702240356 | |
| Download: ML20211E578 (14) | |
Text
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AVERAGE DAILY' UNIT POWER LEVEL Docket Fo.
50-272 Unit Name Salem # 1.
Date February 10,1987 Completed by.
Pell White Telephone 609-935-6000 Extension 4451 Month January 1987 Day Average Daily Power Level Day' Average Daily Power Level (MWe-NET)
(MWe-NET) 4 1
839 17 1023 i
2 903 18 977 3
912 19 1030 4-1022 20 1022 5
1005 21 1024 6
827 22 1026 7
615 23 1024 8
579 24 1019 9
950 25 1024 10 1015 26 1023 11 1014 27 1112 12 970 28 1111 13 961 29 1120 14 1017 30 1120 15 1006 31 1107 16 1028 P. 8.1-7 R1 8702240356 B70131 PDR ADOCK 05000272 R
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OPERATING DATA REPORT Docket No.50-272 Date February 10,1987 Telephone 935-6000 Completed by Pell White Extension.4451 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period January 1987 3.
Licensed Thermal Power (MWt) 3411 4.
Nameplate Rating (Gross MWe) 1170 5.
Design ~ Electrical Rating (Net MWe) 1115 6.
Maximum' Dependable Capacity (Gross MWe)1149 7.
. Maximum Dependable Capacity-(Net MWe) 1106-8.
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)
NA
- 10. Reasons for Restrictions, if any This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 744 84073 12.=No. of Hrs. Reactor was Critical 744 744 52026.6
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Horrs Generator On-Line 744 744 50172.6
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2257159 2257159 154913205
- 17. Gross Elec. Energy Generated (MWH) 759540 759540 51457540
- 18. Net Elec. Energy Generated (MWH) 729992 729992 48914760 1
- 19. Unit Service Factor 100 100 59.7
- 20. Unit Availability Factor-100-100 59.7
- 21. Unit Capacity Factor (using-MDC Net) 88.7 88.7 52.6
- 22. Unit capacity Factor (using DER Net) 88.0 88.0 52.2
- 23. Unit Forced Outage Rate 0
0 26.1
- 24. Shutdowns scheduled over next 6 months (type, date and duration of-each)
NA
- 25. If' shutdown at end of Report Period, Estimated Date of Startup:
N/A
- 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
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH JANUARY 1987 Unit Nane Swina No.1 Date February 10,1987 Completed by Pell White Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No.
Date Type Hours Reason Down Event System Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence Station Service Transformer Station 0002 12-31-86 F
25.17 B
5 EG TRANSF Power Auxiliary Feedwater Pump Local 0004 1-1-87 F
.42 B
5 HH PUMPXX Controls Station Service Transformer Station 0006 1-1-87 F
52.5 B
5 EG TRANSF Power Auxiliary Other Feedwater Pump 0012 1-6-87 F
38.10 B
5 HH PUMPXX Problems Other Feedwater Pump 0014 1-8-87 F
1.13 B
5 HH PUMPXX Problems Other Feedwater Pump 0016 1-8-87 F
.87 B
5 HH PUMPXX Problems Miscellaneous Drains and Vent Valves 0020 1-8-87 F
11.73 B
5 HH VALVEX Turbine Miscellaneous Drains and Vent Valves 0022 1-8-87 F
1.47 B
5 HH VALVEX Turbine Miscellaneous Drains and Vent Valves 0024 1-9-87 F
.83 B
5 HH VALVEX Turbine Miscellaneous Drains and Vent Valves 0026 1-9-87 F
1.33 B
5 HH VALVEX Turbine 1
2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Eaintenance or Test 2-Manual Scram.
for Prepara-Source C-Refueling 3-Automatic Scram, tion of 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 C-Operational Error-explain 9-Other (LER) File
'-Other-explain (NUREG 0161)
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH JANUARY 1987 UNIT NAME:
Salem 1 DATE:
February 10, 1987 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR NO.
PRINCIPAL SYSTEM SUBJLCT lEC-0410 Fuel Handling Install cable support system to supplement existing stop log removal cable system.
1EC-1734 Emergency Diesel Generator Reroute and brace tubing similar to Unit 2 emergency diesels on the jacket water cooling system pressure instrument tubing connected to valves IDA43A,B & C, IDA44A,B,
& C, IDA45A,B, & C and IDA46A,B & C.
lEC-1770 Fire Protection Wrap "B" diesel control System cable tray 2A217 between tray 2A258 and 2A218 Fire Barrier material.
1EC-2154 Flux Mapping Provide clip anchors on System trolley frame and rail beams to restrain the flux mapping trolley from jumping off of the rails and impacting the seal table.
- DCR - Design Change Request i
i
MAJOR PLANT MODIFICATIONS DCCKET NO.:
50-272 REPORT MONTH JANUARY 1987 UNIT FAME:
Salem 1 DATE:
February 10, 1987 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59
-1EC-0410 This DCR provides additional supports to the monorail syrtem on Elevation 130' in the Fuel Handling Building.
The additional supports increase the margin of safety by increasing the capacity of the monorail-to withstand.
impact loads associated with the safety cable support system should a hoist failure occur.
The modification is on non-safety related equipment located in a Q Area, i
The seismic installation of the monorail is not affected as the supports meet the same seismic design criteria.
The seismic mounting design precludes the possibility of physical damage to any safety related equipment in the area.
No new failure modes were introduced by this modification.
This design change upgraded the capability of existing equipment.
There is no impact on any analysis in the UFSAR or the Technical Specifications.
This modification does not alter any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
i 1EC-1734 This design change made the Unit 1 diesel engine's water jacket pressure switch tubing run similar to Unit 2, and thereby reduced the susceptibility of the pipe i
nipple connections to vibration induced cracking.
l Neither the rerouting of the tubing nor the smaller I.D. of the fittings affects the ability of the i
Emergency Diesel Generators to function as required.
Functionally, there is no change to the system.
The change did not introduce any potential new failure modes of malfunctions.
The modification does not reduce the margin of safety as defined in the basis of any Technical Specification or impact the UFSAR.
The 4
modification did not alter any plant process or i
discharge or the existing environmental impact of the plant.
Therefore, no unreviwed safety or environmental questions are involved.
T 5
i
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH JANUARY 1987 UNIT NAME:
Salem 1 DATE:
February 10, 1987 COMPLETED BY:
L.
Miller TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1770 The installation of the wrapping provides a one hour fire barrier for the cable tray and results in increased fire protection for the diesel generators.
This modification did not alter any plant process or discharge nor did it affect the environmental impact of the plant.
Therefore, no unreviewed safety or environmental questions are involved.
1EC-2154 This design change provided anchorage for the flux mapping trolley and stabilizing for the trapezed flux map tube support frame over the seal table in the Seal Table Room.
The supports were designed and installed in accordance with established Seismic I criteria.
The addition of these supports does not impact any existing safety analysis or the Technical Specificaton basis of the UFEAR.
This design change did not alter any plant process or discharge or affect the existing environmental impact of the plant.
Therefore, no unreviewed safety or environmental questions are involved.
- Design Change Request
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8608270480 1
1& 2 R45/SA-16 ASSEMBLY FAILURE DESCRIPTION:
SA-16 SPARE DETECTOR SN 139 FOR R45D FAILED.
CORRECTIVE ACTION:
REPLACED DETECTOR FOR SA-16 SN 139.
PERFORMED CAL CHECK SAT UNDER IO 406364 WORK ORDER 86-10-10-070-7.
i s
]
8612081297 i
1 HAGAN DUAL COMP FAILURE DESCRIPTION:
OUTPUT TRIPS ERRATICALLY AND CHANGES BY TOUCHING POT.
4 PLEASE REWORK AND BENCH CALIBRATE AS REQUIRED.
REFERENCE EDL #704.
CORRECTIVE ACTION:
FOUND ST POT POTS BAD, REPLACED POTS FOUND OP AMP A, BAD CHANGED OP-AMP.
0099185857 1
SI FLOW METER FAILURE DESCRIPTION:
THERE IS A FLANGE LEAK ON FE 0922 BETWEEN 11SJ37 AND 12SJ28.
PLEASE REPAIR AND INVESTIGATE.
)
CORRECTIVE ACTION:
REPLACED GASKETS AND TORQUED FLANGES.
1
SALEM UNIT 1 WO NO UNIT EOUIPMENT IDENTIFICATION 8604141260 1
LEVEL CONTROL FAILURE DESCRIPTION:
PLEASE CHECK CAL ON LT-1003.
THE DEAD WEIGHT TESTER SA I&C 592 WAS "INOP".
PLEASE SEND "AS FOUND" DATA TO J.KOVAR.
CORRECTIVE ACTION:
REPLACED TEST AIR REGULATOR IN PANEL 231.
FOUND OUTPUT WOULD ONLY GO TO 18.99 MO.
POWER SUPPLY NOT ABLE TO HANDLE THE EXTRA LOAD RESISTANCE DUE TO THE ADDITION OF SPDS IN THE LOOP.
INSTALLED NEW POWER SUPPLY IAW FQ 38628.
8607230085 1
FLEX COUPLING FAILURE DESCRIPTION:
- 11 CONTROL ROOM AIR CONDITION SUPPLY FAN DISCHARGE FLEXIBLE EXPANSION COUPLING IS TORN.
THE TEAR IS ON THE IB SIDE.
PLEASE REPAIR AS NECESSARY.
CORRECTIVE ACTION:
REPLACED EXPANSION JOINT.
8608130319 1
REACTOR VESSEL LEVEL FAILURE DESCRIPTION:
REMOTE DISPLAY ON CONT ROOM BEZEL IS IN MALFUNCTION WITH SELF TEST FAILURE. REWORK AS NECESSARY.
CORRECTIVE ACTION:
REPLACED Ull PRONG ON CHIP 5000H WITH TEST CHIP A2 i
BOARD.
REMOVED TEST CHIP AND REINSTALLED ORIGINAL CHIP.
VERIFIED PROPER OPERATION.
4 i
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8611220021 1
VALVE 11SW53 RADIOGRAPH FAILURE DESCRIPTION:
RADIOGRAPHY REVEALED VALVE 11SW53 IS HALF OPEN.
REMOVE VALVE FROM SYSTEM AND INSPECT FOR ANY ABNORMAL CONDITIONS.
NOTIFY ISI OF RESULTS.
CORRECTIVE ACTION:
REMOVED VALVE, FOUND BELZONA TO BE CAUGHT INSIDE.
REDID ENTIRE VALVE WITH NEW BELZONA, INSTALLED VALVE.
8611240545 1
REACTOR TRIP BREAKER A P4 FUNCTION FAILURE DESCRIPTION:
UNIT #1, EQUIPMENT / TASK SSPS-TRAIN A.
PERFORM FUNCTIONAL TEST ON REACTOR TRIP BREAKER A AND P-4 PERMISSIVE.
CORRECTIVE ACTION:
COMPLETED IIC-18.1.004, SAT.
8612010594 1
SSPS TRAIN B BUS 3 FAILURE DESCRIPTION:
THERE IS A BLO'WN FUSE ON BUS 3 OF SSPS TRAIN B.
PLEASE REPAIR.
CORRECTIVE ACTION:
REPLACED FUSE INPUT BOY III VERIFY VOLTAGE OF 115.38V AND INTERMITTENT CORD ON RP4 PANEL.
8612020280 1
12 BAT PUMP FAILURE DESCRIPTION:
OPEN AND INSPECT 12 BORIC ACID TRANSFER PUMP.
REPAIR AS REQUIRED.
CORRECTIVE ACTION:
INSTALLED NEW SPARE PUMP.
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8612090059 1
14 HOT LEG TEMPERATURE FAILURE DESCRIPTION:
- 14 RCS HOT LEG TEMP READING APPROXIMATELY 23 DEGREES HIGH.
READS 623 DEGREES FARENHEIT.
PLEASE REPAIR.
CORRECTIVE ACTION:
RECALIBRATED ITE-443A AND RECORDER ITR-443A FOUND IN SPEC.
ADJUSTED LOW LEVEL AMP TO BRING CLOSER TO REQUIRED OUTPUT.
READJUSTED RECORDER TO SPEC.
8612160049 1
11 BAT PUMP FAILURE DESCRIPTION:
11 BAT PUMP WILL NOT START FROM THE CONTROL ROOM.
NO PROBLEMS EVIDENT WITH THE BREAKER OR THE PUMP.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
FOUND BREAKERS TRIPPING, MEGGERED MOTOR, FOUND SAT, UNCOUPLED MOTOR, FOUND PUMP SEIZED.
8612170664 1
1A CVCVE-438A SUPPORT FAILURE DESCRIPTION:
PLEASE REWORK THE #13 CHARGING PUMP SUCTION LINE VIBRATION ELIMINATOR, SUPPORT #1A-CVCVE-438A.
THE SUPPORT HAS TWO CRACKED WELDS, WELDS WHICH ATTACHES ANGLE IRONG TO U-BOLT SUPPORT.
PLEASE REWORK THE 1/ 4 WELDS.
CORRECTIVE ACTION:
LIFTED LINE, REMOVED SUPPORT, REWELDED, PUT BACK INTO SERVICE.
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SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 JANUARY 1987 The Unit began the period operating at eighty one percent (81%) power.
Power was increased to ninety two percent (92%) on January 3,
- 1987, and continued at that level until January 6, 1987, when No. 11 Steam Generator Feed Pump tripped, forcing a load reduction to fifty seven percent (57%).
The feed pump trip was caused by a malfunction in the speed control circuitry.
Repairs were completed and power restored to ninety two percent (92%) on January 8, 1987.
Power was reduced later the same day due to a leak on No. 13 Moisture Separator Reheater - (MSR),
Since the leak could not be repaired during power operation, the decision was made to run with the MSR main steam coil isolated (with concurrence from Westinghouse).
Power was increased to ninety one percent (91%) on January 9, 1987 where it remained fairly constant until a minor load reduction was performed on Janaury 12, 1987, to repack No. 12 Heater Drain Pump.
Another minor load reduction was performed on January 15, 1987, at the request of the load dispatcher.
Later the same day, power was increased, but remained limited to ninety two percent (92%) due to transformer power limitations and work on No. 11 Condensate Pump.
On January 26, 1987, No. 11 Condensate Pump was returned to service and power was increased to one hundred percent (100%). The unit continued to operate at one hundred percent (100%) for the remainder of the period.
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 1 DATE:
February 10, 1987 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month January 1987 1.
Refueling information~has changed from last month:
YES NO X
2.
Scheduled date for next refueling:
September 12, 1987 3.
Scheduled date for restart following refueling: November 26, 1987 4.
A)
Will Technical Specification changes or other license amendments be required?-
YES NO NOT DETERMINED TO DATE X
B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
August 1987 5.
Scheduled date (s) for submitting proposed licensing action:
August 1987 if required 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fue] Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 380 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 2001 8-1-7.R4
O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 i
Salem Generati ig Station February 17, 1987 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 I
Dear Sir:
(
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of January 1987 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, m
e7
/DC J.
M.
Zupko, Jr.
General Manager - Salem Operations JR:sl cc:
Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk.
Washington, DC 20555 Enclosures 8-1-7.R4
)
4,7
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The Energy People
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