ML18093B039
| ML18093B039 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1988 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8808250088 | |
| Download: ML18093B039 (12) | |
Text
AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month JULY 1988 Day Average Daily Power Level (MWe-NET) 1 635 2
1054 3
1091 4
1078
--*----~-----
5 1090 6
1091 7
10 65 8
1088 9
10 62 10 1070 11 1052 12 1114 13 1085 14 1033 15 1062 16 1050 Pg. 8.1-7 Rl Day Docket No.
Unit Name Date Telephone Extension 50-311 Salem # 2 8-4-88 609-935-6000 4451 Average Daily Power Level (MWe-NET) 17 1061 18 1052 19 1073 20 1051 21 1056 22 1057 23 1061 24 1047 25 1026 26 1016 27 1004 28 998 29 978 30 734 31 0
e OPERATING DATA REPORT 50-311 8-4-88 Docket No.
Date Telephone Extension 935-6000 Completed by Pell White Operating Status Unit Name Salem No. 2 Notes Reporting Period July 1988 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 4451 1
- 2.
3
- 4.
5.
6.
7.
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
~~~~~~~~~~~~~~~~~~~~~~
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 5111 59616
- 12. No. of Hrs. Reactor was Critical 718 4962.7 37325.6
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 714.2 4913.2 36195
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 2388288 16452295.2 62102816.2
- 17. Gross Elec. Energy Generated (MWH) 775310 5454620 37084090
- 18. Net Elec. Energy Generated (MWH) 741649 5229114 35248492
- 19. Unit Service Factor 96.0 96.1 60.7
- 20. Unit Availability Factor 96.0 96.1 60.7
- 21. Unit Capacity Factor (using MDC Net) 90.1 92.5 53.5
- 22. Unit Capacity Factor (using DER Net) 89.4 91.8 53.0
- 23. Unit Forced Outage Rate 4.0 3.9 28.3
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling Outage scheduled for 9-2-88 and lasting for approximately 52 da s.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Unit Returned back on line on August 1 at 0524 8-l-7.R2
Completed by No.
Date 0150 7-01-88 0174 7-30-88 1
F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JULY 1988 Docket No. 50-311 Unit Name Date Telephone Extension
~~~~~~~~
Salem No.2 Pell White Method of Duration Shutting License Type Hours Reason Down Event 1
2 Reactor Report F
10.50 A
5 F
29.85 A
3 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 Component Code 4 Code 5 xx FUEL XX EB TRAN SF 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
August 4, 1988" 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence Nuclear Fuel Limits Neutron Flux II c II Vital Instrument Bus Exhibit G 5
Exhibit Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Salem as A Source.,
J
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880622051 2
2R42A FAILURE DESCRIPTION:
MONITOR FAILED/INVESTIGATE AND REPAIR.
880623110 2
23AF 21 FAILURE DESCRIPTION:
23 S/G FD VLV/NOT CLOSING/TROUBLESHOOT.
880627072 2
23SW72 FAILURE DESCRIPTION:
VALVE BINDING/OPEN INSPECT/REPAIR.
880629103 2
F.H. CRANE FAILURE DESCRIPTION:
HOIST LIMITS INOPERABLE/RESET AND TEST.
880705160 2
2B4(NA5664)
FAILURE DESCRIPTION:
CONTROL ROD/IND HIGH/TROUBLESHOOT.
WO NO 871221176 880223113 880330089 8 803310.93 880517123 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2XA5132 FAILURE DESCRIPTION:
MAIN GEN. H2 PURITY/PEGGED HIGH 2
1SW137 FAILURE DESCRIPTION:
AFW PP RM CLR VLV/NO RESPONSE/TROUBLESHOOT.
2 24SW22 3 FAILURE DESCRIPTION:
24 CFCU VLV/IMPROPER IND/TROUBLESHCX>T.
2 23 CHG. PMP.
FAILURE DESCRIPTION:
COVER LEAKS/REWORK.
THE HORZINAL COVER ON NUMBER 2 CYLINDER ON 23 CHARGING PUMP.
2 2SW175 FAILURE DESCRIPTION:
VALVE WON'T CLOSE COMPLETELY/REPAIR.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880519080 2
SPDS FAILURE DESCRIPTION:
FAILED POINTS/REPAIR.
880531118 2
2RlA FAILURE DESCRIPTION:
MONITOR FAILED/REPAIR.
880608096 2
23 SI ACCUM LVL CONSOLE ALARM FAILURE DESCRIPTION:
NOT ALARMING/TROUBLESHOOT.
880610090 2
2HY93 FAILURE DESCRIPTION:
VALVE WILL NOT CLOSE/REPLACE SPINDLE PIN.
TROUBLESHOOT.
880620122 2
2CAA31 FAILURE DESCRIPTION:
BATT RM DAMPER LIMIT/NO OPEN IND/REWORK.
SALEM UNIT 2 WO NO UNIT EQUIPMENT IDENTIFICATION 880712126 2
25SW248 FAILURE DESCRIPTION:
PIPING LEAK IN HEADER/REPAIR.
880715106 2
21 CHG PUMP FAILURE DESCRIPTION:
HIGH VIBRATION/INSPECT OTBD BEARING.
880727106 2
2WL 16 FAILURE DESCRIPTION:
VALVE FAILED STROKE TIME/INVESTIGATE.
MA,JOR PLANT MODIFAtTIONS REPORT MONTH JULY 1988
- OCR NO.
PRINCIPAL SYSTEM 2EC-2168 Solid State 2SM-0117/a Service Water 2SM-0129 Service Water 2SM-0132/a Service Water 2SM-0152 Reactor Coolant 2SM-0186/a Service Water 2SM-0618 S/G Blowdown Design Change Request DOCKET -
50-311 UNIT NAME:
Salem 2 DATE:
August 10,1988 COMPLETED BY:
J. Ronafalvy TELEPHONE: 609/339-4455 DESCRIPTION This design change installed a modified undervoltage driver card in the Solid State Protection system.
The fusible link driver card will prevent maintenance errors from going undetected.
This modification removed Valve 22SW262 from the system as it is no longer required for draining the header.
This modification replaced Valve 21SW8 with a valve of a similar design.
The original valve was corroded beyond repair and was obsolete, therefore it was replaced with a valve of a newer design.
This modification replaced the corroded piping downstream of Valve 21SW122.
The inside of the new pipe was coated with Belzona to create an erosion/corrosion barrier.
This modification replaced the pressure transmitter on the RCDT with a newer design.
The original transmitter was broken and no spare parts were available.
This modification replaced the carbon steel pipe spool on the Service Water return from No.
21 CFCU with a spool made of stainless steel.
This modification installed a pressure gauge between the high pressure and low pressure regulators on the S/G Blowdown sample line to allow calibration of the high pressure regulator.
e MAJOR PLANT MODIFICATIONS REPORT MONTH -
JULY 1988
- DCR SAFETY EVALUATION 10 CFR 50.59 e
DOCKET NO: 50-272
~~---~___,___,___, ___ _
UNIT NAME: Salem 2
.;;;;...;;;.;;.;;;;..;;'-"----.--~--.----
DATE:
August 10,1988 COMPLETED BY:J.Ronafalvy TELEPHONE:
(609)339-4455 2EC-2168 This modified card has a fusible link and will prevent maintenance errors from going undetected.
This modification did not affect any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0117/a The valve removed by this design change is no longer necessary.
This modification did not affect any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0129 This design change did not affect the function or operation of the system.
This modification did not affect any plant process or discharge or affect the envioronmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0132/a The new pipe spool has been coated with Belzona for enhanced erosion/corrosion resistance.
This modification did not affect any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0152 The replacement transmitter installed by this design change is fully qualified for this application.
This modification did not affect any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0186/a The new spoolpiece has greater resistance to erosion and corrosion.
This modification did not affect any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SM-0618 This modification allows for calibration of the high pressure transmitter.
This modification did not affect any plant process or discharge or affect 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 1988 The Unit began the period in a power escalation and achieved full power on July 1, 1988.
The Unit continued to operate at essentially full power until July 24, 1988, when it entered an end-of cycle coastdown.
On July 30, 1988, the Unit experienced a reactor trip due to problems experienced with 2C Vital instrument Bus Inverter.
The Reactor remained shutdown throughout the remainder of the period.
The primary to secondary leak rate calculations for Nos. 22 and 24 Steam Generators continue to indicate less than five gallons per day per Steam Generator.
r REFUELING INFORMATION DOCKET NO.: 50-311 UN IT NAME: _S_a_l,....e-m--2------
COMPLETED BY:
J. Ronafalvy DATE: August 10, 1988 TELEPHONE: 609/935-6000 EXTENSION 4455 Month JULY 1988
- 1.
Refueling information has changed from last month:
- 2.
3 *
- 4.
YES NO X
Scheduled date for next refueling:
September 3, 1988 Scheduled date for restart following refueling: November 2,1988 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 NO X
If no, when is it scheduled?
August, 1988
- 5.
Scheduled date(s) for submitting proposed licensing action:
August 1988 if required
- 6.
Important licensing considerations associated with refueling:
NONE 7
- 8.
- 9.
8-1-7.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:
19 3 224 117 0 1170 March 2003
PS~G Public Service Electric and Gas Company P.O. Box E 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 10, 1988 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 1988 are being 'sent to you.
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, J.~tt!:P-General Manager -
Salem Operations RH:sl cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-1-7.R4 The Energy People 95-2189 () 1M)12-84