ML20214B195
| ML20214B195 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1986 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8611200374 | |
| Download: ML20214B195 (16) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-272 Unit Name Salem # 1 Date November 10,1986 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month October 1986 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 898 17 1128 2
963 18 1126 3
1080 19 969 4
1062 20 1118 5
1088 21 1131 6
1096 22 1115 7
1102 23 1125 8
1089 24 1135 9
1107 25 1144 10 1113 26 1144 11 1093 27 1144 12 1110 28 1127 13 1136 29 1125 14 1102 30 1129 15 1126 31 1128 t
16 1109 P.
8.1-7 R1
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8611200374 861031 f
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PDR ADOCK 05000272 R
OPERATING DATA REPORT Docket No.50-272 Date November-10,1986 l
Telephone 935-6000 l
Completed by Pell White Extension 4451 Operating Status 1.
Unit Name Salem No. 1 Notes 2.
Reporting Period October 1986 3.
Licensed Thermal Power (MWt) 3411 4.
Nameplate Rating (Gross MWe) 1170 5.
Design Electrical Rating (Net MWe)
IIT5 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)
N/A
- 10. Reasons for Restrictions, if any This Month Year to Date Cumulative
- 11. Hours in Reporting Period 745 7296 81865 i
- 12. No. of Hrs. Reactor was Critical 745 5633.2 49818.6
- 13. Reactor Reserve Shutdown Hrs.
0 0
0 j
- 14. Hours Generator On-Line 745 5459.8 47964.6 2
- 15. Unit Reserve Shutdown Hours 0
0 0
i
- 16. Gross Thermal Energy Generated l
(MWH) 2512805 17226363 147710392
- 17. Gross Elec. Energy Generated (MWH) 848450 5714860 49010870
- 18. Net Elec. Energy Generated (MWH) 817373 5450206 46555698
- 19. Unit Service Factor 100 74.8 58.6 l
- 20. Unit Availability Factor 100 74.8 58.6
- 21. Unit Capacity Factor j
(using MDC Net) 99.2 67.5 51.4 i
- 22. Unit Capacity Factor (using DER Net) 98.4 67.0 51.0
- 23. Unit Forced Outage Rate 0
11.7 27.1 i
j
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A
- 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 OCTOBER 1986 Unit Name salem No.1 Date November 10,1986-
-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 702 0929 F
53.1 B
5 EG TRANSF power auxiliary Station Service Transformer station 704 10-01 F
17.4 B
5 EG TRANSF power auxiliary Other Feedwater 722 10-19 F
4.7 B
5 CH PUMPXX Problems Other Feedwater 724 10-19 F
2.9 B
5 CH PUMPXX Problems 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-Maintenance or Test 2-Manual Scram.
for Prepara-Source C-Refueling 3-Automatic 9 ran. 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 G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)
MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH OCTOBER 1986 UNIT NAME:
Salem 1 DATE:
November 10, 1986 COMPLETED BY:
L.
Miller TELEPHONE:
609/339-4497
- DCR NO.
PRINCIPAL SYSTEM SUBJECT 1EC-1531 Waste Disposal Gas Install redundant waste gas oxygen analysis capability.
1EC-1819 RMS Relocate sample line connections for main steam line RMS from the MS131 VAS.
to the MS130 VAS.
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- DCR - Design Change Request
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MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH OCTOBER 1986 UNIT NAME:
Salem 1 DATE:
November 10, 1986 COMPLETED BY:
L. Miller TELEPHONE:
609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1EC-1531 This design change does not affect the function of any system or component required to safely shutdown the Unit nor does it affect the ability to maintain the Unit in a shutdown condition.
This design change enhances the oxygen analysis capability of the Waste Gas System.
This modification does not alter any plant process or discharge.
No unreviewed safety or environmental questions are involved.
1EC-1819 The relocation of the Main Steam Line Radiation Monitoring System sample line from the MS131 Valves to the MS130 Valves will not affect any safety analysis previously done for either the Main Steam or the Main Steam Line Radiation Monitoring System.
This modification does not alter any plant process or discharge.
No unreviewed safety or environmental questions are involved.
- Design Change Request i
1 I
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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8610141268 1
STEAM GEN FLOWS FAILURE DESCRIPTION:
STEAM FLOW BISTABLES CONSTANTLY ALARMING DUE TO NOISY STEAM FLOW SIGNALS.
PLEASE PERFORM TEMP. TEST PROCEDURE TTP-001.
CORRECTIVE ACTION:
COMPLETED DATA FOR TTP-001 WITH LEAD LAG UNIT INSTALLED AND A LAG SETTING OF 1 SEC. PROCESSED NOISE WAS REDUCED TO APPROXIMATELY 0.
8610110176 1
12WG10 FAILURE DESCRIPTION:
PLEASE REPLACE VALVE DIAPHRAGM WHICH HAS PARTED FROM VALVE STEM.
DISCHARGE PRESSURE INTERLOCK LOCKS OUT COMPRESSOR, ALL OTHER VALVES VERIFIED IN CORRECT POSITION.
CORRECTIVE ACTION:
REMOVED AND REPLACED DIAPHRAGM IN 12WG10.
8610090825 1
1R-18 RAD MON STPT FAILURE DESCRIPTION:
REVISE THE RAD MON SETPOINT (lR18) FROM 800,00 CPM TO 400,000 CPM AND THE WARNING ALARM FROM-400,000 CPM;TO 300,000 CPM.
CORRECTIVE ACTION:
CHANGES 1R18 SETPOINTS WARNING 300K CPM ALARM 400K CPM.
_ - _. _. ~ _. _ _ _ _ _ _
_. _. ~.
d SALEM UFIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8610090868 1
LEVEL CHANNEL i
FAILURE DESCRIPTION:
RWST LEVEL CHANNEL D IS READING JUST ABOVE TECH SPEC MINIMUM AND LEVEL CHANNEL B IS READING JUST BELOW TECH SPEC MAXIMUM.
ONE OF THESE CHANNELS IS OFF.
I PLEASE INVESTIGATE AND REPAIR.
i CORRECTIVE ACTION:
RECALIBRATED ILT-920 PROCEDURE lIC-2.9.173 ZERO LOW RAIN ZERO WITHIN 1/2 FT OF OTHER CHANNEL.
RECALIBRATED INDICATION CHANNEL D WAS LOW ADJUSTED l
TO SPEC.
4 DIFF BETWEEN CH.
i
]
8610070018 1
i FAILURE DESCRIPTION:
THE CC HX DOES NOT OPERATE PROPERLY.
WHEN ATTEMPTING
)
TO DECREASE FLOW, THE PLOW WOULD TRANSFER TO THE i
OTHER HALF (FROM A TO B).
PLEASE REPAIR. ALSO FLOW IS NOT EVENLY DISTRIBUTED BETWEEN A AND B.
l CORRECTIVE ACTION:
REALIGNED POSITIONER CAM AND CAM WHEEL ON VALVE l
12SW379.
i l
8610070051 1
RWST LEVEL CHANNEL B l
l FAILURE DESCRIPTION:
CHANNEL B IS READING LOWER THAN ACTUAL LEVEL.
PLEASE INVESTIGATE AND REPAIR.
j CORRECTIVE ACTION:
CHECKED CAL OF LT-921 CHANNEL B AND FOUND READING LOW AT TOP END.
RECALIBRATED AND RETURNED TO SERVICE.
INSERVICE READING READ CLOSER TO CHANNEL D.
CHECKED
]
CAL OF LT-920 CHANNEL D AND FOUND READING HIGH.
l RECALIBRATED AND RETURNED TO SERVICE.
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SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8610030750 1
SILT REMOVAL FAILURE DESCRIPTION:
PER DISPOSITION OF DR MT86-ll4 PLEASE REMOVE SILT FROM 16 SW BAY.
NOTIFY ISI WHEN COMPLETE SO THEY CAN SCHEDULE A RETEST ON 16 SW PUMP WHICH HAS BEEN DECLARED INOPERABLE.
CORRECTIVE ACTION:
REMOVED SILT FROM 16 BAY.
8610010015 1
11 SW223 VALVE FAILURE DESCRIPTION:
WHEN PLACED IN LOW SPEED, HIGH FLOW, 11 CFCU DID NOT ACHIEVE 2500 GPM.
SHIFT TECH HAS DETERMINED THAT 11SW223 IS THE PROBLEM.
PLEASE CONTINUE INVESTIGATION AND REPAIR. THIS IS A 72 HOUR ACTION STATEMENT.
CORRECTIVE ACTION:
FOUND POSITIONER AND STROKE OF VALVE SAT.
FOUND SUPPLY REGULATOR TO SV-1468 READING 30 PSI, WHEN IT SHOULD BE 15 PSI.
ADJUSTED ACCORDINGLY, THEN SET HIGH LOW SETPOINT REGULATORS VERIFIED WITH CONTROL ROOM FOR PROPER INDICATION.
8610020045 1
11 CC HX TEMP CONT VALVE FAILURE DESCRIPTION:
VALVES DOES NOT CONTROL IN AUTO AT ALL.
VALVE APPEARS TO REMAIN IN WHATEVER POSITION LAST ESTABLISHED BY MANUAL CONTROL.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
REPLACED LOWER SEAL BENCHING.
REPLACED LANGE SPRING.
ADJUSTED CONTROLLERS, CALIBRATED POSITIONER, STROKED VALVE.
i SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8609270025 1
CHANNEL B ALARM I
FAILURE DESCRIPTION:
THE HI/LO LEVEL ALARM ON CHANNEL B FOR #11 ACCUMULATOR IS IN.
THE ACTUAL LEVEL IS ONLY 70% AND THE ALARM SETPOINT IS 75%.
l CORRECTIVE ACTION:
COMPARATOR ILC-935A/B OUTPUT WOULD NOT RESET.
j REPLACED CAPS C2, C3, S/N GO 200 IT WOULD NOT FUNCTION PROPERLY OR RESET ERRATIC.
REPLACED BY
}
S/N GO 110 INSERVICE.
PAGE 6 OF PROCEDURE 1
lIC-2.10.186.
I 1
8609260267 1
SSPS TRAIN A SAFETY RELATED FAILURE DESCRIPTION:
SSPS TRAIN A.
PERFORM PERIODIC TEST FOR TRAIN A.
)
CORRECTIVE ACTION:
PERFORMED PERIODIC TEST FOR TRAIN A LOGIC SWITCH B23 TESTED BAD FOUND PUSHBUTTON ON CONTROL BOARD FOR CONTAINMENT VENTILATION ISOLATION REST FOR TRAIN A.
8609230465 1
13 SW PUMP STRAINER BREAKER FAILURE DESCRIPTION:
BREAKER KEEPS TRIPPING.
PLEASE REPAIR.
CORRECTIVE ACTION:
FOUND STRAINER SEIZED NEEDS MECH REPAIR, STRAINER NEEDS NEW SHOES, NONE ON FOLIO, REPLACED DISTRIBUTION BARRELS, UPPER THRUST BEARING REPACKED.
i
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8609120759 1
13 CHARGING PUMP FAILURE DESCRIPTION:
INVESTIGATE AND REPAIR CAUSE OF PACKING FAILURES IN 13 CHARGING PUMP.
CORRECTIVE ACTION:
REPACKED PUMP AND INSTALLED NEW STUFFING BOX.
8609110559 1
11MS46 FAILURE DESCRIPTION:
PLEASE DISASSEMBLE AND INSPECT SHAFT FOR SCORING OR CORROSION.
VALVE IS BINDING.
ALSO REPACK VALVE.
CORRECTIVE ACTION:
REBUILT AND REPACKED VALVE.
8608290642 1
13MS46 CHECK VALVE FAILURE DESCRIPTION:
13MS46 HAS A BODY TO BONNET LEAK.
PLEASE REPAIR.
CORRECTIVE ACTION:
REBUILT AND REPACKED VALVE.
8608270439 1
CHANNEL A LEVEL ALARM FAILURE DESCRIPTION:
12 ACCUMULATOR CHANNEL A LEVEL ALARM BLIPS INTERMITTENTLY.
PLEASE INVESTIGATE AND REPAIR.
CORRECTIVE ACTION:
VERIFIED SETPOINT OF ILC-935B/F HI-LO ALARM ALSO OUTPUT VOLTAGE SAT.
MAINT ELECTRICIAN REPLACED ALARM AND VERIFIED BOTH OUTPUT ALARM AND CLEAR SAT.
l i
j SALEM UNIT 1 j
WO NO UNIT EQUIPMENT IDENTIFICATION
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8509251231 1
REACTOR COOLANT SYSTEM PRESSURE l
FAILURE DESCRIPTION:
PERFORM A THREE POINT CALIBRATION CHECK ON THE j
REACTOR COOLANT SYSTEM PRESSURE (PA-8088 & PA-0039)
IAW THE TEST PACKAGE FOR lEC-1365. REFER TO PROCEDURES i
l lIC-2.2.070 AND IIC-2.2.071.
i CORRECTIVE ACTION:
PERFORMED THREE POINT CHECK ON LOOP 403.
AFTER t
TERMINATING WIRING ON SPDS lEC-1365.
PERFORMED l
THREE POINT CHECK ON LOOP 405 AFTER TERMINATING j
l E
8509251266 1
1 CONTAINMENT PRESSURE i
FAILURE DESCRIPTION:
PERFORM THREE POINT CALIBRATION CHECK ON CONTAIMENT I
PRESSURE (PA-2386,PA-2405,PA-2344,PA-2345,PA-2346 i
AND PA-2568) IN ACCORDANCE WITH THE TEST PACKAGE FROM lEC-1365. REFER TO PROCEDURES lIC-2.2.066 THROUGH IIC-2,2.069 AND lIC-1.4.003.
i 1
l CORRECTIVE ACTION:
TERMINATED WIRING FOR PA-2405 SEE ATTACHED SHEET FOR INFORMATION. TERMINATED WIRING FOR PA-2386 SEE i
i ATTACHED SHEET FOR INFORMATION. PERFORMED THREE i
i POINT CHECK ON LOOP 1PT-948C AFTER LANDING WIRING t
j ON SPOS lIC-2.2.069 SAT. PERFORMED CHECK ON i
IPT-948A.
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SALEM UNIT 1 1
WO NO UNIT EQUIPMENT IDENTIFICATION 8509260176 1
BORIC ACID CHARGE FLOW l
FAILURE DESCRIPTION:
PERFORM A THREE POINT CALIBRATION CHECK ON THE BORIC ACID CHARGING FLOW (FA-135 & FA-2174) IAW THE 4
l TEST PACKAGE FOR 1EC-1365. REFER TO PROCEDURE IIC-2.1.007 AND lIC-2.1.017.
CORRECTIVE ACTION:
PERFORMED THREE POINT CHECK ON LOOP FT-113 AFTER TERMINATING WIRING ON 1EC-1365 SPDS.
WORK ORDER 4
86-05-22-106-2.
PERFORMED THREE POINT CHECK ON LOOP FT-128 AFTER TERMINATING WIRING ON SPDS.
MEASURED POWER SUPPLY = 44.23 VDC.
i I
8509260273 1
PRESSURIZER LEVEL 4
FAILURE DESCRIPTION:
PERFORM A THREE POINT CALIBRATION CHECK ON THE l
PRESSURIZER LEVEL (LA-0086 THROUGH LA-0089) IAW THE i
TEST PACKAGE FOR 1EC-1365. REFER TO PROCEDURES j
IIC-2.2.020,1IC-2.2.021,1IC-2.2.022 AND lIC-2.9.092.
CORRECTIVE ACTION:
PERFORMED THREE POINT CHECK ON LT-459'CH I AFTER TERMINATING WIRING ON SPDS lEC-1365 WO#
1 86-05-22-106-2.
PERFORMED THREE POINT CHECK ON i
1LT-460 CHANNEL II.
PERFORMED THREE POINT CHECK ON ILT-461 CHANNEL III.
PERFORMED THREE POINT CHECK ON 1LT-462.
I l
I.
SALEM UNIT 1 WO NO UNIT EQUIPMENT IDENTIFICATION 8509260508 1
REACTOR COOLANT SYSTEM FAILURE DESCRIPTION:
PERFORM A THREE POINT CALIBRATION CHECK ON THE REACTOR COOLANT SYSTEM LOOP AVERAGE TEMPERATURE (TA-5360 THROUGH TA-5363) IAW THE TEST PACKAGE FOR lEC-1365.
REFER TO PROCEDURES IIC-2.2.001,1IC-2.2.005, lIC-2.2.009 AND IIC-2.2.013.
CORRECTIVE ACTION:
PERFORMED THREE POINT CHECK ON LOOP 1TM-412 AS PER ICD CARD AFTER TERMINATING WIRING ON SPDS lEC-1365. PERFORMED THREE POINT CHECK ON LOOP 1TM-422 AS PER ICD AFTER TERMINATING WIRING ON SPDS lEC-1365.
PERFORMED THREE POINT CHECK ON ITM-432, 8610272079 1
HAGAN LOOP POWER SUPPLY FAILURE DESCRIPTION:
REWORK MODULE SN# AO 829, MODEL 121, PER VENDOR'S MANUAL.
CORRECTIVE ACTION:
FOUND BAD CAP Cl WHICH CAUSED AC NOISE.
- REPLACED, INSTALLED D3 ZENER DIODE 47 VDC AS PER 1EC-365 AND 2EC-1366 OUTPUT CHECKED AT 46.18 VDC WITH MAX LOAD.
8609290107 1
GE 4KV MAGBLAST BREAKER CHECK FAILURE DESCRIPTION:
VISUALLY INSPECT AND TIME 4KV MAGNABLAST BREAKER 5 YEAR OVERHAUL BY GE P.O.
NO P1-123227, BREAKER SERIAL NO. 0224A6257-001.
CORRECTIVE ACTION:
PERFORMED M3J.
PUT IN 2BDD.
1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 OCTOBER 1986 The Unit began the period operating at eighty three percent (83%)
power, 930 MWe.
Power was increased to ninety percent (90%) on October 2, 1986, by swapping loads and maintaining the limitations of the station power transformers.
Power was further increased from ninety percent (90%) to one hundred percent (100%) on October 3,
- 1986, following removal of Unit 2 from service.
No. 12 Heater Drain Pump was returned to service on October 14, 1986, following installation of a temporary power feed fron Unit 2.
Gross electrical generation increased from 1,145 megawatts to 1,170 megawatts due to the increase in efficiency.
One circulator remains out of service at all times due to the transformer load limitations. The Unit continued to run at one hundred percent (100%) power until October 19, 1986, when a load reduction to fifty eight percent (58%) was taken to correct a vacuum indication problem on No. 12 Steam Generator Feed Pump.
No. 12 Heater Drain Pump was repacked during the power reduction.
The Unit returned to one hundred percent (100%) power at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> the same day and continued to operate at one hundred percent (100%) power for the remainder of the period.
l
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 1 DATE:
November 10, 1986 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month October 1986 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 Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 380 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170 l
9.
Date of last refueling that can be discharged to spent fuel pool assuming the present i
licensed capacity:
September 2001 I
8-1-7.R4 l
i I
O PSEG i
Public Service Electric and Gas Company P.O. Box E Hancocks Bndge, New Jersey 08038 Salem Generating Station November 10, 1986 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission
{
Washington, DC 20555
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 October 1986 are being sent to you.
Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions i
Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information f
Sincerely yours, j
hN J. M.
Zupko, Jr.
General Manager - Salem Operations i
JR:sl cc:
Dr. Thomas E. Murley j
l Regional Administrator USNRC Region I 631 Park Avenue i
King of Prussia, PA 19406 Director, Office of Management U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l
Enclosures i
8-1-7.R4 sh (f'ql' g\\
l The Energy People m,m.,,,,,
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