ML18094A632
| ML18094A632 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1989 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8908230291 | |
| Download: ML18094A632 (9) | |
Text
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. 2 DOCKET NO. 50-311 August 11, 1989 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, the original copy of the monthly operating reports for the month of July 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 8-1-7.R4
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PDR ADOCK 05000311 R
AVERAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Docket No.
Unit Name Date Telephone Extension Month JULY 1989 Day Average Daily Power Level Day Average Daily (MWe-NET)
(MWe-NET) 1 1085 17 78 7 2
1107 18 922 3
10 40 19 1045 4
1072 20 951 5
1083 21 1068 6
1053 22 1039 7
1058 23 1075 8
1063 24 1058 9
1066 25 1055 10 1070 26 1089 11 1067 27 1089 12 1086 28 1016 13 10 56 29 10 66 14 1078 30 1091 15 945 31 1068 16 695 Pg. 8.1-7 Rl 50-311 Salem # 2 8-10-89 609-935-6000 4722 Power Level
r _________ - ---- ---------
e OPERATING DATA REPORT Completed by Art Orticelle Operating Status Docket No.
Date Telephone Extension 50-311 8-10-89 935-6000 4722
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit Name Salem No. 2 Notes Reporting Period July 1989 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) 1170 Design Electrical Rating (Net MWe) 1115 Maximum Dependable Capacity(Gross MWe)1149 Maximum Dependable Capacity (Net MWe) 1106 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 744 744 0
744 0
2475830 836079 789000 100 100 95.9 Year to Date 5087 44 66 0
42 89. 3 0
14 067 854 4691864 4504565 84.3 84.3 80.0 Cumulative 68376 42 821. 8 0
41411. 9 0
78732951 42576164 40479870 62.6 62.6 53.5 95.1 79.4 53.1 0
15.7 27.4
- 24. Shutdowns scheduled over
-..,...,..--.,.,~-
next 6 months (type, date and duration of each)
NONE
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A 8-l-7.R2
Completed by No.
Date 0165 07-15-89 0166 07-17-89 0167 07-17-89 0169 07-19-89 1
F: Forced S: Scheduled PNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1989 Docket No. 50-311 Unit Name Date Telephone Extension
~~~~~~~~-
Salem No.2 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1
2 Reactor Report F
0 A
5 F
0 A
5 F
0 A
5 F
0 A
5 2 Reason A-Equipment Failure-explain B-Maintenance or Test C - Ref ue 1 in g D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain System Component Code 4 Code 5 EG GENERA EG GENERA EG GENERA HF xx xx xx 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 8-10-89 609-935-6000 4722 Cause and Corrective Action to Prevent Recurrence MAIN BUS COOLING PROBLEM MAIN BUS COOLING PROBLEM MAIN BUS COOLING e PROBLEM 22A CIRCULATOR 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit-Salem as Source I
I I
WO NO 8 90609120 890626092 890630102 890630103 890706112 PSR&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2R42A FAILURE DESCRIPTION:
21 GAS DECAY TANK AREA RAD MON/FAILED/REPAIR.
2 2FT523 FAILURE DESCRIPTION:
2FT523 22 SG STM FLW/LOW IND/TROUBLESHOOT.
2 2LI935B FAILURE DESCRIPTION:
22 ACCUM LVL/IND INCORRECT/TROUBLESHOOT.
2 2LI934B FAILURE DESCRIPTION:
22 ACCUM LVL/IND INCORRECT/TROUBLESHOOT.
2*
2R1B FAILURE DESCRIPTION:
CONTROL RM.. DUCT RAD. MON. /NO COMMUMICATION TO CPU/REPAIR.
\\l I
I
- MAJOR PLANT MODIFictt.IONS RRPORT MONTH JULY 1989
- DCR NO.
2EC-01381A 2EC-02245 2SM-00637 PRINCIPAL SYSTEM Condensate Reactor Protection Safety Injection Design Change Request DOCKET.
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
DESCRIPTION 50-311 Salem 2 August 10, 1989 P. White 609/339-4455 This design change replaced the existing condensate pumps with higher capacity pumps and motors.
This design change deleted the 1/4 Reactor Coolant Pump Breaker Open Anticipatory Trip Signal.
This design change drilled weep holes in the disks of the 21 and 22 SJ40 valves on the upstream side of the valve disks.
F e
MA:'JOR PLANT MODIFICATIONS REPORT MONTH JULY 1989 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- DCR SAFETY EVALUATION 10 CFR 50.59 50-272 Salem 2 August 10, 1989 P. White (609)339-4455 2EC-01381A This design change replaced the existing condensate pumps with higher capacity pumps.
Installation of the new pumps and motors provides higher net positive suction head to the Steam Generator Feed Pumps (SGFP) and reduces the likelihood of a reactor trip as a result of low suction pressure to the SGFPs.
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.
2EC-02245 This design change deleted the 1/4 reactor Coolant Pump Breaker Open Anticpatory Trip Signal.
This modification was made in accordance with the recommendations of the Westinghouse Owner's Group Trip Reduction Program to enhance the reliability of Unit operation.
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.
2SM-00637 This design change drilled weep holes in the disks of the 21 and 22 SJ40 valves on the upstream side of the valve disks.
Drilling of the weep holes provides a thermal expansion path for fluid trapped between the two disks and helps to prevent valve binding.
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. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
-- UNIT NO. 2 JULY 1989 The Unit began the period operating at 100% power and continued.to operate at essentially full power until July 15, 1989.
During the period between July 15 and July 20, 1989, several load reductions were performed to accomplish necessary maintenance activities.
On July 20, 1989, the Unit was restored to 100% power and continued to operate at essentially full power for the remainder of the period.
f L
REFUELING INFORMATION DOCKET NO.:
50-311 UNIT NAME:
Salem 2 COMPLETED BY:
P. White DATE:
August 10, 1989 TELEPHONE:
609/935-6000 EXTENSION 4455 Month JULY 1989
- 1.
Refueling information has changed from last month:
- 2.
- 3.
- 4.
YES NO X
Scheduled date for next refueling:
March 30, 19 90 Scheduled date for restart following refueling:
May 15, 1990 A)
B)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMIN_E_D_T_O-DATE X
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
February 1990
- 5.
Scheduled date(s) for submitting proposed licensing action:
January 1990
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
- 8.
- 9.
8-l-7.R4 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:
193 224 11 70 1170 March 2003