ML18094A710
| ML18094A710 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1989 |
| From: | Miller L, Orticelle A Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909270011 | |
| Download: ML18094A710 (10) | |
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. 2 DOCKET NO. 50-311 September 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 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 The Energy People 95-2189 (SM) 12-88
l\\.VYRAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Month AUGUST 1989 Day Average Daily Power Level (MWe-NET) 1 1063 2
1072 3
1089 4
1075 5
10 85 6
1102 7
1048 8
1069 9
1090 10 1077 11 1086 12 1072 13 1088 14 1089 15 10 8 6 16 1119 Pg. 8.1-7 Rl Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 1026 18 1066 19 1100 20 897 21 624 22 588 23 45 9 24 767 25 810 26 1024 27 1062 28 1057 29 1057 30 1071 31 10 91 50-311 Salem # 2 9-11-89 609-935-6000 4722 Power Level
--~--
OPERATING DATA REPORT Completed by Art Orticelle Operating Status Docket No.
Date Telephone Extension 50-311 9-11-8""'"9 ___ _
935-6000 4722
- 1.
Unit Name Salem No. 2 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 Availapility 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
2384116.8 78 887 0 755162 100 100
- 91. 8 Year to Date 5831 5210 0
5033.3 0
16 451971. 2 54 807 34 5259727 86.3 84.3
- 81. 6 Cumulative 69120 43565.8 0
42155.9 0
81117068.2 43365034 41235032 61 61 53.9 91 80.9 53.5 0
13.7 27.1
- 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 0181 08-20-89 0182 08-20-89 0183 08-21-89 0184 08-21-89 0185 08-22-89 0186 08-24-89 0187 08-25-89 0188 08-25-89 0189 08-25-89 1
F: Forced S: Scheduled T'NTT SHUTDOWN AND POWER REDUCTTONS Docket No. 50-311 REPORT MONTH AUGUST 1989 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1
2 Reactor Report F
14.3 A
5 F
5.0 A
5 F
13 A
5 F
96 A
5 F
49.3 B
5 F
2.4 A
5 F
2.2 A
5 F
. 2 A
5 F
- 32. 1 A
5 2 Reason A-Equipme~t 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.
Unit Name Salem No.2 Date 9-11-89 Telephone 609-935-6000 Extension 4722 Cause and Corrective System Component Action to Code 4 Code 5 Prevent Recurrence CH xxxxxx fl 24 S.G. LEVEL fl 2 1 SGFP COOLER LEAK WA HTEXCH (SERVICE WATER)
CH xx xx xx fl 21 SGFP CONTROLS II*
CH xxxxxx fl 21 SGFP CONTROLS BLOWDOWN fl21 and fl 22 CH FILTER SGFP STRAINERS CH CH CH CH 3 Method 1-Manual xx xx xx xx xx xx xx xx xx xxxxxx 1121 SGFP fl 21 SGFP fl 2 1 SGFP fl 21 SGFP 4 Exhibit G Instructions 2-Manual Scram.
for Prepara-3-Automatic Scram. tion of Data 4-Continuation of Entry Sheets Previous Outage for Licensee 5-Load Reduction Event Report 9-0ther (LER) File (NUREG 0161)
CONTROLS CONTROLS CONTROLS CONTROLS 5 Exhibit....l Salem as.
Source
WO NO 890721078 890811113 890821114 890822105 890823132 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
PA6951 FAILURE DESCRIPTION:
PA6951 AUX BLDG PRESS CTL/CONTROLLING LOW/TRBLST.
2 2NR41 FAILURE DESCRIPTION:
2NR41 LOWER FLUX -
GREEN -
READS 105% with 2N41 LOWER DETECTOR.
2 AXIAL FLUX FAILURE DESCRIPTION:
CHANGE TARGET AXIAL FLUX DIFFERENCE TO -
3. 0 FOR N 41-N 4 4
- 2 2R41B FAILURE DESCRIPTION:
FAILED SCALER DURING THE CHANNEL FUNCTIONAL TEST.
2 2R41A FAILURE DESCRIPTION:
2R41A/PLANT VENT PART RAD MON/FAILED/REWORK.
. l SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 890828103 2
2R45B FAILURE DESCRIPTION:
2R45B/DAM4 UNIT/LOCKED UP/REWORK.
890828106 2
2R45C FAILURE DESCRIPTION:
2R45C/DAM4 UNIT/LOCKED UP/REWORK.
MAJOR PLANT MODIFI~IONS REPORT MONTH AUGUST 1989
- DCR NO.
PRINCIPAL SYSTEM 2EC-02063 Charging 2SM-00158 Moisture Separator 2SM-00190 Feedwater 2SM-00731 Charging Design Change Request DOCKET..
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
DESCRIPTION 50-311 Salem 2 September 10, 1989 P. White 60 9/339-4455 This design change added a suction stabilizer upstream of No. 23 Charging Pump.
This design change resized the orifice from the feedwater heater and MSR drain tank.
-This design change replaced spools 2S-FWR-22 and 2S-FWR-25 in the feedpump recirculation lines with spools constructed of chrome moly.
This design change drilled 1/32" holes in the discharge valves for No. 23 Charging Pump.
e
.MAJOR PLANT MODIFICATIONS REPORT MONTH AUGUST 1989 DOCKET NO:
UNIT NAME:
50-272 Salem 2 DATE:
COMPLETED BY:
TELEPHONE:
- DCR SAFETY EVALUATION 10 CFR 50.59 September 10, 1989 P. White (609)339-4455 2EC-02063 This design change added a gas charged bladder suction stabilizer to the suction piping of No. 23 Charging Pump.
The unit selected is a gas charged bladder design that is currently used in the same application at several operating plants.
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-00158 This design change resized the orifice from the f eedwater heater and MSR drain tank to allow for proper operation of the 4th pass.
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-00190 This design change replaced carbon steel spools in the feedpump recirculation lines with spools made of chrome moly for better corrosion resistance.
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-00731 This design change drilled weep holes in the disks of No. 23 charging Pump discharge 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 AUGUST 1989 The Unit began the period operating at 100% power and continued to operate at essentially full power until August 201 1989.
During the period of August 20 and August 26, 1989, the Unit was operated at reduced power to address feedwater control problems and a leak on a feedpump lube oil cooler.
The Unit was restored to 100% power on August 26, 1989, and continued to operate at essentially full power for the remainder of the period.
REFUELING INFORMATION DOCKET NO.:
50-311 UNIT NAME:
Salem 2 COMPLETED BY:
P. White DATE:
September 10, 1989 609/935-6000 TELEPHONE:
EXTENSION 4455 Month AUGUST 1989
- 1.
Refueling information has changed from last month:
- 2.
- 3.
- 4.
YES NO X
Scheduled date for next refueling:
March 30, 1990 Scheduled date for restart following refueling:
May 15, 1990 A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMIN_E_D~T-0-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?
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 1170 1170 March 2003