ML18094B396
| ML18094B396 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1990 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004170009 | |
| Download: ML18094B396 (9) | |
Text
e OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SJl.LEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of March 1990 are being sent to you.
RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Sincerely yours, L. K. Miller General Manager -
Salem Operations cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People
~~
9004170009 900331 PDR ADOCk 05000272 R
PDC 95-2189 (11 M) 12-84
AVERAGE DAILY UNIT POWER LEVEL Docket No.
~5~0_-=2~7=2~~~~~-
Unit Name Salem # 1 Date 04-09-90
~~~~~~~~-
Completed by Art Orticelle Telephone 609-339-2122 Month MARCH[ 1990 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 1116 17 1015 2
1098 18 1005 3
559 19 999 4
780 20 995 5
1116 21 973 6
1115 22 1009 7
1114 23 1012 8
1112 24 1007 9
1119 25 992 10 1113 26 1029 11 1068 27 541 12 1016 28 0
13 1008 29 0
14 1006 30 0
15 1008 31 0
16 1004 P. 8.1-7 Rl
OPERATING DATA REPORT Docket No:
50-272 Date:
04-09-90 Completed by:
Art Orticelle Telephone:
609-339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period March 1990
- 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)
N/A
~~~~~~~~~~~
- 10. Reasons for Restrictions, if any N/A
~~~~~~~~~~~~~~~~~~~~-
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 2160 111793
- 12. No. of Hrs. Reactor was Critical 638 2054 72962.6
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 637.9 2053.9 70749.7
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2015980.8 6758474.4 221859400.4
- 17. Gross Elec. Energy Generated (MWH) 668040 2249320 73710680
- 18. Net Elec. Energy Generated (MWH) 643623 2176905 70188615
- 19. Unit Service Factor 85.7 95.1 63.3
- 20. Unit Availability Factor 85.7 95.1 63.3
- 21. Unit Capacity Factor (using MDC Net) 78.2 91.1 56.8
- 22. Unit Capacity Factor (using DER Net) 77.6 90.4 56.3
- 23. Unit Forced Outage Rate 14.3 4.9 21.1
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling Outage scheduled to start 10-6-90 and last 45 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
4-5-90 8-1-7.R2
DURATION NO.
'IYPE 1 (HOORS}
REl\\SOO' z 0025 3-03-90 F
34.6 B
0033 3-27-90 F
106.1 A
UNIT SlillTOOWN AND POWER REDUCTIONS REroRI' IDNTH MAA==CH"-=19;...:;.9-=-0 ___ _
MEI'HOD OF SHUTI'ING lJCENSE OOWN EVENT SYSTEM CX>>1roNENI' RFACIDR REroRI' It CODE 4 CODE 5 5
HJ PUMPXX 1
IB INSTRU OOCKEI' l\\TQ. : 50-272 UNIT NAME: Salem #1.
DA'IE: 04-09-90
<mPLEI'ED BY: Art Orticelle TELEPHONE: 339-2122 CAUSE AND CORRECTIVE ACTION
'IO PREVENT RIDJRRENCE
- 13 H.D. TANK PUMP 1A S.E.C.
e 1
2 3
4 5
F: Forced Reason:
S: Scheduled A-FquiIXOOilt Failure (Explain}
B-Maintenance or Test C-Refueling D--Regulatory Restriction E-Qperator Training & License Examination F-Administrative G--Operational Error (Explain}
H-other (Explain}
Method:
1-Manual 2-Manual Scram 3-Autanatic Scram 4-COntinuation of Previous outage 5-1.Dad Reduction 9-other Exhibit G - Instructions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report {LER) File (NUREG-0161)
SAFETY RELATED MAINTENANCE MONTH: -
MARCH 1990 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 890822124 1
890926098 1
891116142 1
900207045 1
900302166 1
900315082 1
DATE:
COMPLETED BY:
TELEPHONE:
APRIL 10, 1990 P. WHITE (609} 339-4455 EQUIPMENT IDENTIFICATION 13 CFCU FLOW DEVIATION ALARM FAILURE DESCRIPTION:
FLOW DEVIATION ALARM FAULTY -
TROUBLESHOOT AND REPAIR 13 CFCU BACKPRESSURE TRANSMITTER FAILURE DESCRIPTION:
BACKPRESSURE TRANSMITTER DEFECTIVE -
REPLACE 12SW49 FAILURE DESCRIPTION:
VALVE DOES NOT RESPOND TO SETPOINT -
TROUBLESHOOT 11 S/G WIDE RANGE TRANSMITTER FAILURE DESCRIPTION:
11 S/G WIDE RANGE TRANSMITTER SPIKING -
REPLACE CIRCUIT CARDS FIRE DAMPER 1CAF204 FAILURE DESCRIPTION:
FIRE DAMPER FAILED TO OPERATE DURING INSPECTION -
TROUBLESHOOT lA SEC FAILURE DESCRIPTION:
CHANGE OUT SEC CHASSIS WITH SPARE
MAJOR PLANT MODIFICATIONS MONTH: -
MARCH 1990
- DCR PRINCIPAL SYSTEM lEC-02192 Rx Protection lSC-02008 Non-Radwaste
- Design Change Request DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 APRIL 10, 1990 P. WHITE (609) 339-4455 DESCRIPTION This design change replaced the P-7 interlock which provided a direct Rx trip following a turbine trip with a setpoint of 11% power with interlock P-9.
This design change installed electric actuators on NRW valves 1LW283, 1LW284, 1LW285, and 1LW286 with logic inputs from operating Circulating Water System Pumps.
MAJOR PLANT MODIFICATIONS MONTH: -
MARCH 1990 DOCKET NO:
UNIT NAME:
50-272 SALEM 1
- DCR lEC-02192 lSC-02008 DATE:
COMPLETED BY:
TELEPHONE:
SAFETY EVALUATION 10 CFR 50.59 APRIL 10, 1990 P. WHITE (609) 339-4455 This design change replaced the P-7 interlock which provided a direct Rx trip following a turbine trip with a setpoint of 11% power with interlock P-9.
This design change reduces the potential for inadvertent Rx trips and challenges to the Reactor Protection System.
There was no change to any plant process or discharge or to the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
This design change installed electric actuators on Non-Radwaste Valves 1LW283, 1LW284, 1LW285, and 1LW286 with logic inputs from operating Circulating Water System (CWS)
Pumps.
The logic is set to close the valves if there is no flow in the CWS loops.
The valves have a manual/auto feature to discharge into a non-operating CWS loop if the system pH is between 6.0 and 9.0.
There was no adverse change to any plant process or discharge or to the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 MARCH 1990 The Unit entered the period operating at 100% power and continued to operate at that level until March 3, 1990, when power was reduced for repair to No. 11 Steam Generator Feedwater Pump.
The repairs were completed and the Unit was restored to full power on March 4, 1990.
The Unit continued to operate at full power until March 11, 1990, when power was reduced to 92% to remove No. 11 Heater Drain Pump from service for repairs.
With the exception of two minor load reductions, due to solar magnetic disturbance alerts, the Unit continued to operate at 92% power until March 26, 1990.
The Unit was restored to full power on March 26, 1990, and continued to operate at that level until March 27, 1990, when it was shutdown in compliance with a Technical Specification Action Statement.
The Action Statement had been entered due to 1A Safeguards Equipment Cabinet being declared inoperable.
The Unit remained shutdown for the rest of the period.
REFUELING INFORMATION MONTH: -
MARCH 1990 MONTH DECEMBER 1989 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO x
- 2.
Scheduled date for next refueling:
October 6, 1990 50-272 SALEM 1 APRIL 10, 1990 P. WHITE (609) 339-4455
- 3.
Scheduled date for restart following refueling:
November 19, 1990
- 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?:
September 1990
- 5.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 6.
Important licensing considerations associated with refueling:
- 7.
Number of Fuel Assemblies:
- a.
Incore 193
- b.
In Spent Fuel Storage 540
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170
- 9.
Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4
,