ML18093B222
| ML18093B222 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/30/1988 |
| From: | Miller L, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8810190152 | |
| Download: ML18093B222 (10) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date 10-5-88 Completed by Pell White Telephone 609-935-6000 Extension 4451 Month SEPTEMBER 1988 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 10 89 2
0 18 1096 3
0 19 1093 4
0 20 1086 5
0 21 1082 6
0 22 1087 7
119.7 23 1097 8
1048 24 109 8 9
1082 25 1097 10 1114 26 1079 11 1085 27 1107 12 1100 28 1092 13 1100 29 1107 14 1110 30 1094 15 1078 31 16 1107 P. 8.1-7 Rl
,~
e OPERATING DATA REPORT Docket No.50-272 Date:
~l~0--~5~-~8~8,,.-.~~--~
Completed by Pell White Telephone: 935-6000 Extension: ~4~4~5~1--~--~~---
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period September 1988
- 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)ll49
- 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
---'-----~------------~--------------~
- 11. Hours in Reporting Period
- 12. No. of Hrs. Reactor was Critical
- 13. Reactor Reserve Shutdown Hrs.
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net) 2 3. Unit Forced Outage Rate This Month 720 57 0. 6 0
560.7 0
1892143~2 632660 603144 77.9 77.9
- 75. 7
- 75. 1 22 Year to Date 6575 47 28. 1 0
46 35. 1
- o.
15638450.8 5214160 4972885 70.5 70.5 68.4 67.8 4.5 Cumulative 98664 62423.2 0
60426.9 0
187907459.6 62408650 59369094
- 61. 2
- 61. 2 54.4 53.9 23.0
- 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 8-l-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH SEPTEMBER 1988 Docket No.50-272 Unit Name Date Telephone Extension
~~~~~~~~-
Salem No.1 Completed by Pell White No.
0164 Date Type 1
9-01-88 F
Duration Hours 159.27 Reason 2
A Method of Shutting Down Reactor 3
License Event Report 1
2 Reason F: Forced S: Scheduled A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Code 4 HA 3 Method 1-Manual Component Code 5 TURBIN 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 10-5-88 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence Turbine Trip Inst. and Controls 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source
WO NO 880506098 880815176 880825113 880831092 880903044 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
14-CFCU FAILURE DESCRIPTION:
LOW FLOW IN HIGH AND LOW SPEEDS/REPAIR.
1 lC DIESEL PRELUBE PUMP FAILURE DESCRIPTION:
THE PRELUBE PUMP ON lC DIESEL APPEARS TO BE SEIZED REWORK.
1 1N36 INTER MED RNG FAILURE DESCRIPTION:
1N36 INTER MED RNG/SWITCH DEFECTIVE/REPLACE.
1 1CV27 8 FAILURE DESCRIPTION:
1CV278 BODY TO BONNET LEAK/REPLACE GASKET AND AND CLEAN*OFF 1
lPR-1 FAILURE DESCRIPTION:
lPR-1 REPLACE ACTUATOR DIAPHRAM.
WO NO 880905103 880920148 900918002 900919004 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
WELD JOINT FAILURE DESCRIPTION:
THE WELD JOINT DOWN STREAM OF llSW 222 IS LEAKING/REWORK.
1 14AF23 FAILURE DESCRIPTION:
14AF23 BODY TO BONNET LEAK-MAKE TEM. REPAIR.
1 11CV14 8 FAILURE DESCRIPTION:
REPLACE DIAPHRAGM/0-RINGS 1
12CV148 FAILURE DESCRIPTION:
REPLACE DIAPHRAGM/0-RINGS
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- ITAJOR PLANT MODIFICATIONS REPGRT MONTH SEPTEMBER 1988
- DCR NO.
lSM-0124 lSM-0201 lSM-0310 lSM-0391 lSM-0537/A lSM-0556 PRINCIPAL SYSTEM Radiation Monitoring SGFP Recirc Piping Safety Injection Relief Valves Reactor Head Insul.
- DCR - Design Change Request e
DOCKET NO.:
50-272 UNIT NAME:
Salem 1 DATE:
October 10, 1988 COMPLETED BY: J. Jackson TELEPHONE:
~6~0~9~/~3~3~9--~4~4-5-5~~~
DESCRIPTION This design change revised the lR-18 Radiation Monitor alarm setpoint from 800,000 cpm to 400,000 cpm, and the warning alarm from 400,000 cpm to 300,000 cpm to allow the liquid radioactive release rate to be increased while keeping in compliance with regulatory requirements.
This design change replaced the carbon steel recirc piping on Nos.
11 & 12 SGFP recirc lines with ASTM A-335 P22 Cr-Mb piping due to erosion problems.
This design change removed the clutch trip mechanism from Valves Nos. 11 & 12 SJ44 to avoid potential failure of the gear assemblies.
This design change replaced Valves Nos. 1SJ133, 1AF99, and 1WR123 to provide proper overpressure protection for their associated heat exchangers.
The valves which were replaced had been set above the allowable equipment pressure ratings.
This design change replaced the worn reactor head insulation.
The new insulation has been fabricated in accordance with original vendor specifications and drawings.
This design change replaced Valve 13SW20 which had been leaking past its seat.
The existing valve operator from 13SW20 was used on the new valve.
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- MAJOR PLANT MODIFICATIONS REPORT MONTH SEMPTEMBER 1988 DOCKET NO. ~
50--27 2 UNIT NAME:
Salem 1
- DCR lSM-0124 lSM-0201 lSM-0310 lSM-0391 lSM-0537/A lSM-0556 DATE:
October 10, 1988 COMPLETED BY: J. Jackson TELEPHONE:
--;:6=0~9~/~3~3~9--~4~4~5~5-------
SAFETY EVALUATION 10 CFR 50.59 The previous setpoint imposed an unnecessary delay in discharging radwaste liquids.
By lowering the setpoint to 400,000 cpm, the liquid release flow rate was optimized, while still ensuring that all required documents pertinent to the discharge of liquid radioactive waste are being complied with.
No unreviewed safety,or environmental questions are involved.
This design change upgraded the material of the recirc piping to material with greater erosion resistance.
The system configuration remained unchanged.
There was no change to any plant process or discharge or the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
The removal of the clutch trippers did not alter the safety function of the SJ44 valves.
There was no change to any plant process or discharge or to the environmental impact of the plant.
No unreviewed safety or invironmental questions are involved.
The installation of the new relief valves with lower set pressures increased the safety and reliability of the affected systems by guarding against accidental overpressurization.
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.
The replacement insulation was fabricated in accordance with the original vendor specifications and drawings.
There was no change to any plant process or discharge or the the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
The additional weight of the new valve has been stress analyzed to ensure the seismic integrity of the system was maintained.
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.
DCR -
Design Change Request
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 SEPTEMBER 1988 The Unit began the period shutdown for investigation of the circumstances which resulted in a turbine/reactor trip on August 31, 1988, and for repairs to a leak in the pressurizer spray line.
The investigation and repairs were completed and a startup commenced *. The Unit was restored to full power on September 7, 1988, and continued to operate at essentially full power for the remainder of the period.
i--
1 F.EFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
J. Jackson UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
October 10, 1988 609/935-6000 4497 Month SEPTEMBER 1988
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
April 15, 1989
- 3.
Scheduled date for restart following refueling: May 30, 1989
- 4.
A)
B)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO _D_A_T=E-X Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
February 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
February if required
- 6.
Important licensing considerations associated with refueling:
- 7.
- 8.
- 9.
NONE Number of Fuel Assemblies:
A)
Inc ore B)
In Spent Fuel Storage Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-l-7.R4 193 464 1170 1170 September 2001
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PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 October 11, 1988 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 September 1988 are being sent to you.
RH:sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, fl~
L. K. Miller General Manager -
Salem Operations cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 The Energy People 95-2168 (1 DOM) 12-84