ML18093A646
| ML18093A646 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1988 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8802230091 | |
| Download: ML18093A646 (12) | |
Text
e e
AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Month January 1988 Day Average Daily Power Level (MWe-NET) 1 0
2 0
3 0
4 0
5 0
6 0
7 0
8 0
9 0
10 0
11 0 ---
12 0
13 0
14 0
15 0
16 0
P. 8.1-7 Rl Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 50-272 Salem # 1 February 10, 1988 609-935-6000 4451 Power Level
e OPERATING DATA REPORT Completed by Pell White Operating Status Docket No.50-272
-...-~~--=-=-~-=-=-
Date: February 10,1988 Telephone: 935-6000 Extension: ~4~4~5~1~~~~~~-
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period January 1988
- 3.
Licensed Thermal Power (MWt) 3411
- 4.
Nameplate Rating (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe) 1115
- 6.
Maximum Depen~able 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)
NA
~~~-~~~~~~~~~
- 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 0
0 0
0 0
0
-8658 0
0 0
0 0
Year to Date 744 0
0 0
0 0
0
-8658 0
0 0
0 0
Cumulative 92833 57695.1 0
55791.8 0
172269008.8 57194490 54387551 60.1 60.1 53.0 52.5 24.2
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
N/A
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
2-22-88 8-l-7.R2
Completed by No.
Date 0 356 12-24-87 0001 1-8-88 1
F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1988 Docket No.50-272 Unit Name Date Telephone Extension Salem No.1 Pell White Method of Duration Shutting License Type Hours Reason Down Event 1
2 Reactor Report s
364.5 B
9 s
571. 5 B
9 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 WA zzzzzz CA CRDRVE 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther February 10,1988 609-935-6000 4451 Cause and Corrective Action to Prevent Recurrence SERVICE WATER REPAIR CONTROL ROD DRIVE MECHANISM LEAKS -
4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source
WO NO 870225094 870507053 870615045 870805089 870908147 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
lRCEOO 1 1
1 1
1 REACTOR VESSEL STUDS FAILURE DESCRIPTION:
MODIFY REACTOR VESSEL STUDS TO RECEIVE BIACH QUICK DISCONNECT.
lRCEI FAILURE DESCRIPTION:
PLEASE DISASSEMBLE UNIT 1 REACTOR FOR REFUELING.
13 REACTOR COOLANT PUMP FAILURE DESCRIPTION:
INSPECT AND REPLACE 13 REACTOR COOLANT PUMP SEAL.
14SW10 FAILURE DESCRIPTION:
PIPING DOWNSTREAM OF 14SW10 HAS A HOLE IN IT.
REPAIR.
1CC16 0 FAILURE DESCRIPTION:
1CC160 LEAKING PAST ITS SEATS, DISASSEMBLE VALVE.
WO NO 871010046 871012125 871015131 871016079 871028128 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
1RA3908 FAILURE DESCRIPTION:
lRA.3908 HAS A THRU THE WALL LEAK.
REPAIR.
1 13RC13 FAILURE DESCRIPTION:
13RC13 HAS DAMAGED THREADS ON THE STEM AND ON HANDWHEEL.
REWORK.
1 llCFCU FAILURE DESCRIPTION:
llCFCU DISCHARGE FLEX JOINT RIPPED AT STAIRWAY LANDING.
1 11 BAT PUMP FAILURE DESCRIPTION:
11 BORIC ACID TRANSFER PUMP HAS A MECHANICAL SEAL LEAK.
REPLACE SEAL.
1
- 1CC368 FAILURE DESCRIPTION:
1CC368 HAS FAILED THE LEAK RATE TEST.
WO NO 871120047 871121018 871203177 871205033 871220050 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
lHllX 460V #1 DEAR.VAC. PUMP BREAKER 1
FAILURE DESCRIPTION:
lHllX 460 VOLT BREAKER FOR
~:l DEAERATOR VACUUM PUMP DOES NOT CLOSE.
15SW12 FAILURE DESCRIPTION:
15SW12, REPAIR PIPING LEAK AT ELBOW UPSTREAM OF VALVE (SS).
1 HANGER MSG-168 FAILURE DESCRIPTION:
HANGER MSG-168, WELD REPAIR AND REINFORCE HANGER SUPPORT.
1 eves LINE HANGER FAILURE DESCRIPTION:
HANGER HAS BENT RODS ON eves LINE HANGER LOCATED AT #12 RCP.
REPAIR.
1 1VC6 FAILURE DESCRIPTION:
1VC6 IS LEAKING.
REWORK.
WO NO 871221188 871223128 871226037 871230153 871230174 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
11SW21 FAILURE DESCRIPTION:
11SW21, WELD LEAK DOWNSTREAM OF 11SW21, REPAIR.
1 12 SW PUMP MOTOR FAILURE DESCRIPTION:
12 SW PUMP MOTOR SUBMERGED IN WATER DUE TO S.W. BAY FLOODING.
REMOVE FOR OVERHAUL.
1 13SW20 FAILURE DESCRIPTION:
13SW20 VALVE DAMAGED.
REPLACE VALVE.
1 1WR81 1
FAILURE DESCRIPTION:
1WR81 HAS FAILED THE LEAK. RATE TEST.
REWORK AA-42.
1SW26 FAILURE DESCRIPTION:
1SW26 LEAKS THROUGH.
OPEN, INSPECT AND REPAIR AS REQUIRED.
WO NO 880107089 880110098 UNIT EQUIPMENT IDENTIFICATION 1
1CV24 l AA27 RELIEF VALVE SALEM UNIT 1 FAILURE DESCRIPTION:
1CV241 AA27 RELIEF VALVE LEAKING THROUGH, INSPECT AND REPAIR.
1 lRCEl-REACTOR CAVITY FLOOR FAILURE DESCRIPTION:
PERFORM NECESSARY STEPS TO REPAIR THE DEFECT IN THE CAVITY.
MAJOR PLANT MODIFICATIONS REPORT MONTH JANAURY 1988 DOCKET NO.
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 Salem 1 February 10, 19 8 8 J. Ronafalvy 609/339-4455
- OCR SAFETY EVALUATION 10 CFR 50.59 This information was not available at the time of this report, however, it will be included in future reports.
DCR -
Design Change Request
Sl~LEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 JANAURY 1988 The Unit entered Mode 3 on January 6, 1988.
During the 102%
hydrostatic test of the Reactor Coolant System (RCS), leaks were discovered on three (3) spare control rod drive mechanism (CRDM) penetrations at their lower canopy seal welds.
The Unit was cooled down to Mode 5 on January 9, 1988, to facilitate repairs.
During a detailed inspection of all CRDM columns while in Mode 5, evidence of leakage was found on three additional columns at the same area.
Dye penetrant tests confirmed the existence of possible "pinhole" leaks on two (2) of the three (3} columns.
Since none of the leaking columns were removed, the actual cause of the leakage was undetermined.
However, inspection and analysis of the five (5) thermocouple columns yielded a possible cause.
The thermocouple columns, which are similar in design to the spare CRDM columns, were removed in conjunction with the installation of the Bottom Mounted Instrument System.
The canopy seal areas of all five thermocouple columns exhibited evidence of thermal crevices postulated to be from incomplete fusion of the consumable insert used during the welding process of the canopy seals during the original fabrication.
Our analysis, and that of our consultant, suspect some type of pitting originating in the crevice area might be the cause of the canopy seal leaks.
None of the five (5) thermocouple columns had any evidence of crevice propagation pitting or leakage.
Since there are a total of thirteen spare CRDM columns, it was decided to repair all of them to preclude further problems due to leakage.
A weld buildup technique was used on twelve (12) columns and a split canopy seal ring was used on the thirteenth.
The NRC, both at the Region I and NRR levels, was given a presentation and kept informed of our findings and repairs.
Other work performed during the period included:
detensioning, removal, and retensioning of nine (9) Reactor Vessel Head studs to remove any boric acid accumulation; cleaning of the vessel head; repairs to the Reactor Cavity seal area; replacement of 12MS14 Main Steam Safety Valve, and replacement of PR3 Pressurizer Safety Valve.
In addition, a leak detection system utilizing an air particulate monitor has been designed and is being installed to detect RCS leakage from penetrations in the Reactor Vessel Head.
The Service Water Bay 1 flood in December 1987, was caused by partial failure of the 13SW20 butterfly valve seat.
The valve has been replaced with a new type, hydrostatically tested, and returned to service.
All recovery activities associated with other equipment in the Bay have been completed.
REFUELING INFORMATION DOCKET NO.:
50-27 2 COMPLETED BY:
J. Ronafalvy UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
February 10, 19 88 609/935-6000 4497 Month JANUARY 1988
- 1.
Refueling information has changed from last month:
YES X
NO -----
- 2.
Scheduled date for next refueling:
March 4, 1989
- 3.
Scheduled date for restart following refueling: April 18, 1989
- 4.
A)
B)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO DATE X
Has the reload fuel design been reviewed by the Station Operating Review Conunittee?
YES NO X
If no, when is it scheduled?
January 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
January if required
- 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 storage capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-l-7.R4 19 3 464 11 70 1170 September 2001
e OPS~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. 1 DOCKET NO. 50-272 February 15, 1988 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the ori.ginal copy of the monthly operating reports for the month of January 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~~~L~~t~~
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-l-7.R4 The Energy People 95-2189 (11 M) 12-84