ML18094A578
| ML18094A578 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1989 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8907200313 | |
| Download: ML18094A578 (10) | |
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 July 12, 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 June 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 Safety Valve Challenges Sincerely yours,
$/uJJL 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
- 9o726c:>::.;r:3' ::::96~.::::6 - ---
PDR ADOCK 05000311 R
PDC The Energy People 95-2189 (5M) 12-88
Completed by Art Month JUNE 1989 Day Aver age Daily (MWe-NET) 1 536 2
921 3
1020 4
1079 5
1114 6
1034 7
1081 8
1082 9
1064 10 1030 11 0
12 0
13 0
14 0
15 897 16 1063 Pg. 8.1-7 Rl AVERAGE DAILY UNIT POWER LEVEL Orticelle Power Level Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 1063 18 1119 19 1066 20 1065 21 1066 22 1112 23 1053 24 1097 25 1071 26 1077 27 1046 28 1096 29 1102 30 1036 50-311 Salem # 2 7-10-89 609-935-6000 4451 Power Level
OPERATING DATA REPORT Completed by Pell White Operating Status Docket No.
Date Telephone Extension 50-311 7-10-89 935-6000 4451
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit Name Salem No. 2 Notes Reporting Period June 1989 Licensed Thermal Power (MWt) 3411 Nameplate Rating (Gross MWe) 1170 Design Electrical Rating (Net MWe) 1115 Maximum Dependable Capacity(Gross MWe)ll49 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 720 64 4. 40 0
623.25 0
2070988.8 676600 666837 86.6 86.6 83.7 Year to Date 4343 3722.0 0
35 45. 3 0
11592024.0 37 93 655 3715565
- 81. 6
- 81. 6 77.4 Cumulative 67632 42077.8 0
40667.87 0
76257121.0 41677955 39690870 60.1 60.1 53.1 83.1 76.7 52.6 13.4 18.4 I
27.8
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NONE 2~. If shutdown at end of Report Period, Estimated Date of Startup:
N/A 8-l-7.R2
Completed by No.
Date 0147 06-01-89 0148 06-01-89 0149 06-01-89 0155 06-10-89 1
F: Forced S: Scheduled l
UNIT SHU TD OWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH JUNE 1989 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1
2 Rea eta r Re12ort F
3.68 A
1 F
0 A
4 F
0 A
4 F
93.07 A
2 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 Unit Name Salem No.2 Date 7-10-89 Telephone 609-935-6000 '
Extension 4451 System Component Code 4 Code 5 CH VAL VEX HE VAL VEX HE VAL VEX HF PUMP XX 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther Cause and Corrective Action to Prevent Recurrence BF19 PROBLEM MODIFICATION MAIN STEAM SAFETY RELIEF VALVES II MAIN STEAM SAFETY RELIEF VALVES LOSS OF CIRCULATING WATER PUMPS 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Sou re e
WO NO 880418321 881103101 890508101 890612028 890629152 I_
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2SV1042(2CAA8)
FAILURE DESCRIPTION:
23 CONTROL ROOM SUPPLY FAN DAMPER-REPLACE SOLENOID VALVE.
2 100' AIRLOCK FAILURE DESCRIPTION:
TROUBLESHOOT CLOSING MECHANISM.
2 21BF19 FAILURE DESCRIPTION:
BODY TO BONNET LEAK, MAKE TEMPORARY REPAIR.
2 INSP: #2SJ12 AND 2SJ13 FAILURE DESCRIPTION:
LEAKAGE/PERFORM PI/S-SJ-3.
2 2R46B FAILURE DESCRIPTION:
COOLING FLOW MONITOR FAILING LOW.
INVESTIGATE.
I I l
-~JOR PLANT MOD~ATIONS REPORT MONTH JUNE 1989
- OCR NO.
PRINCIPAL SYSTEM 2SM-00185 Spent Fuel 2SM-00231 Waste Collection 2SM-00612 Station Batteries 2SM-00781 Main Turbine Design Change Request DOCKE-0:
50-311 UNIT NAME:
Salem 2 DATE:
July 10, 19 89 COMPLETED BY:
P. White TELEPHONE:
609/339-4455 DESCRIPTION This design change installed a check valve on the inlet to the Spent Fuel Pit Demineralizer to prevent backf low through the demineralizer.
This design change installed a new waste line connecting the Waste Collector Tank and the High Conductivity Pit.
This design change replaced the existing C&D LCU -17 cells with C&D XTL-27 cells.
This design change installed the Main Turbine Blade and Torsional Vibration Monitoring System in order to detect and measure the vibration of the rotating turbine blades.
e e
MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1989 DOCKET NO~
UNIT NAME:
50--272 Salem 2 DATE:
July 10, 1989 COMPLETED BY:
P. White TELEPHONE:
(609)339-4455
- DCR SAFETY EVALUATION 10 CFR 50.59 2SM-00185 This design change installed a check valve in the inlet to the Spent Fuel Pit Demineralizer to minimize the possibility of backflow through the demineralizer which could result in a potential chemical/radiation problem.
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-00231 2SM-00612 2SM-00781 This design change installed a new, properly sized waste line connecting the Waste Collector Tank and the High Conductivity Pit.
This improves the operation of the system and reduces the possibility of spilling waste material.
There was no change to any plant process or discharge or to the environmental impact of the plant.
No unreviewed safety o~ environmental questions are involved.
This design change replaced the existing C&D LCU-17 cells with higher capacity XTL-27 cells.
This new battery has the necessary increased capacity to meet the system needs.
The new battery performs the same function as the one replaced and does not introduce any new failure modes which could degrade any surrounding safety related equipment.
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 a system to measure and detect the vibration of rotating main Turbine blades.
This system will help detect and prevent possible fatigue, stress corrosion failure of the blades at the blade root.
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 JUNE 1989 The Unit began the period in a power ascension.
The power ascension was temporarily halted at 70% due to problems identified with Valve 23MS15.
The valve was restored to operable status on June 2, 1989 and power was increased to 100%.
The Unit continued to operate at essentially full power until June 10, 1989, when Operators manually tripped the Reactor when five Circulating Water Pumps tripped due to heavy grass conditions.
A startup was commenced on June 14, 1989, and the Unit achieved full power on June 15, 1989.
The Unit continued to operate at essentially full power throughout the remainder of the period.
hEFUELING INFORMATION DOCKET NO.:
50-311 UNIT NAME:
Salem 2 COMPLETED BY:
P. White DATE:
July 10, 1989 TELEPHONE:
609/935-6000 EXTENSION 4455 Month JUNE 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)
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 1170 1170 March 2003
. CEJ\\J.,~ENGES TO PORVs or SAFETY VALVES Salem Unit 2 In accordance with the requirements of Salem Generating Station Unit 2 Technical Spec~fications Section 6.9.1.6, the following recent challenges to PORVs or Safety Valves are being reported:
04-11 On June 10, 1989, Salem Unit 2 was manually tripped when five Circulating Water Pumps tripped as a result of heavy grass conditions.
During this occurrence, several Main Steam Safety Valves lifted as a result of the loss of the Main Condenser as a heat sink.