ML18094A709
| ML18094A709 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1989 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909270007 | |
| Download: ML18094A709 (9) | |
Text
e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO.
1 DOCKET NO. 50-272 September 11, 1989 In compliance with Section 6.9.1.6, Reporting Requirements for the Sale~ Technical Specifications, the original copy of the monthly operating reports for the month of August 1989 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,
- /!
- ~
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
---::::9l)*:.;:;~7l)(>Ci7-
- 1 (>
- ::::~~:-r ----~
PDR ADOCK 05000272 R
PDC The Energy People 95-2189 (SM) 12-88
Completed by Month AUGUST AVERAGE DAILY UNIT POWER LEVEL Art Orticelle 1989 Docket No.
Unit Name Date Telephone Extension Day Average Daily Power Level Day Average Daily (MWe-NET)
(MWe-NET) 1 1076 17 10 69 2
1086 18 1077 3
1102 19 1128 4
1106 20 1080 5
1091 21 112 2 6
10 92 22 1122 7
1059 23 1028 8
10 86 24 1107 9
1102 25 1081 10 1085 26 1089 11 1062 27 1093 12 990 28 1086 13 1115 29 1080 14 1115 30 887 15 1057 31 539 16 1112 P. 8.1-7 Rl 50-*272 Salem # 1 9-11-89 609-935-6000 4722 Power Level
0PERATING DATA REPORT Docket No.50-272 Date:
9-1 71--~8~9,...--~~~~
Completed by Art Orticelle Telephone: 935-6000
-:-=;~,--~~~~~-
Extension: 4722
~~~~~~~~-
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period August 1989
- 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)
- 23. Unit Forced Outage Rate
~~~~~~~~~~~~~~~~~~~~-
This Month 744 74 4 0
744 0
2486186.4 823920 790182 100 100 96 95.3 0
Year to Date 5831 35 73. 2 0
33 87. 8 0
11221392 3714190 3527068 58.1 58.1 5 4. 7 54.2 12.2 Cumulative 106704 68205.4 0
66 023. 7 0
206658184.4 68 661370 65333183
- 61. 9
- 61. 9 55.4 54.9
- 21. 9
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NONE
- 25. If shutdown at end ot Report Period, Estimated Date of Startup:
N/A 8-1-7.R2
lT~!TT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH AUGUST 1989 Docket No.50-272 Unit Name
_S_a_l_e_m_N_o-.-1-.-~
Date 9-11-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4722 No.
Date 0107 8-11-89 0 llO 8-30-89 1
F: Forced S: Scheduled Type 1
F F
Duration Hours
- 11. 5 30.3 Reason 2
B A
Method of Shutting Down Reactor 5
5 License Event Report 2 Reason 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 RH HF 3 Method 1-Manual Component Code 5 FILTER MOTORX 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther Cause and Corrective Action to Prevent Recurrence CONDENSATE PUMP STRAINERS CIRC. WATER MOTORS TRIPPED 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (N:UREG 0161) 5 Exhib-1 Salem as Sou re e
WO NO 870501220 890120097 890622108 890821113 890825089 890829071 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
lSWVlO FAILURE DESCRIPTION:
lSWVlO 14 PUMP BAY OUTLET VENT DMPR/REBUILD DMPR.
1 1MSE23 FAILURE DESCRIPTION:
1MSE23/STEAM TRAP LEAKS THRU/REPAIR/M-91.
1 11-14MS167 FAILURE DESCRIPTION:
11-14MS167 WIRING MODIFICATION AS PER DCR lEC-3008.
1 12SW39 FAILURE DESCRIPTION:
12SW39/WELD LEAK ON UPPER FLANGE/REPAIR.
PINHOLE WELD LEAK ON DOWNSTREAM SIDE OF VALVE.
1 1WR81 FAILURE DESCRIPTION:
1WR81/FAILED THE 4.0.5-V-MISC-l/REWORK AA-42.
1 1SJ5 FAILURE DESCRIPTION:
1SJ5 WOULD NOT CLOSE WHEN DEMANDED.
~~-1
e MAJOR PLANT MODIFICATIONS REPORT MONTH AUGUST 1989
- OCR NO.
PRINCIPAL SYSTEM Diesel Generator Service Water lSC-02025 Feedwater Controls lSM-00643 Rod Control
- DCR -
Design Change Request e
DOCKET NO.. :
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50....,27 2 Salem 1 September 10, 1989 P. White 609/339....,4455 DESCRIPTION This design change installed (2) 70A and (4) 15A seismically qualified, 125VDC molded case circuit breakers into the diesel generator 125VDC control power and field flashing circuits.
This design change installed parallel conductors to existing feeders from the 230V vital busses to the service water motor control centers.
This design change replaced the existing feedwater flow transmitters with new Rosemount transmitters.
It also added new summator filter modules with associated I/V resistors in the steam flow loops.
This design added test switches in the rod control M-G set cabinets.
e MAJOR PLANT MODIFICATIONS REPORT MONTH AUGUST 1989
- DOCKET NO. :
UNIT NAME:
50-272 Salem 1
~
- DCR lEC-02263 lEC-02294 lSC-02 025 lSM-00643 DATE:
COMPLETED BY:
TELEPHONE:
SAFETY EVALUATION 10 CFR 50.59 September 10, 1989 P. White 609/339-4455 This design change added breakers to the D/G field flashing and control power circuits to provide an expeditious method of power transfer from the normal to the standby power supply.
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 paralled conductors to existing feeders from the 230V vital busses to the service water motor control centers to raise the voltage to an acceptable level of 90% of rated voltage and increase reliability.
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.
This design change replaced the existing feedwater flow transmitters with new Rosemount transmitters and added new summator filter modules with associated I/V resistors in the steam flow loops to enhance the reliability and operation of the 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 added test switches in the rod control M-G set cabinets to allow for troubleshooting of the bus overvoltage and overcurrent protection circuitry while the control rods are withdrawn from the reactor core.
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 AUGUST 1989 The Unit began the period operating at 100% power and continued to operate at essentially full power until August 11, 1989, when the power was briefly reduced to clean condensate pump suction strainers.
The Unit was restored to full power on August 12, 1989, and continued to operate at full power until August 30, 1989, when a load reduction occurred following a 13KV cable break.
The cable break had resulted in a loss of power to three Circulating Water pumps~
The Unit continued to operate at reduced power throughout the remainder of the period while repairs were affected.
~*
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
P. White UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
September 10, 1989 609/935-6000 44 97 Month AUGUST 1989
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
March 28, 19 89
- 3.
Scheduled date for restart following refueling: May 24, 1989
- 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 X
NO -.,---=-
If no, when is it scheduled?
- 5.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 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 storag~ capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-l-7.R4 193 540 11 70 1170 September 2001