ML18093B338
| ML18093B338 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1988 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8812190256 | |
| Download: ML18093B338 (12) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Docket No.
Unit Name Date Telephone Extension Month NOVEMBER 1988 Day Average Daily Power Level Day Average Daily (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
16 0
Pg. 8.1-7 Rl 50-311 Salem # 2 12-2-88 609-935-6000 4451 Power Level
e OPERATING DATA REPORT Completed by Pell White Operating Status
- 1.
Unit Name Salem No. 2 2.
Reporting Period November 1988 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)1149 7.
Maximum Dependable Capacity (Net MWe) 110 6
- 8.
If Changes Occur in Capacity Ratings (items Report, Give Reason Docket No.
Date Telephone Extension Notes 3 through 50-311 12-2-88 935-6000 4451
- 7) since Last 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 Serv~ce Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns scheduled over next 6 N/A This Month 720
- 90. 97 0
0 0
10756.8 0
0 0
0 0
0 0
months (type, Year to Date Cumulative 8040 69865 5779.6 38142.5 0
0 5633.7 36915.5 0
0 18475493" 64126014 6085020 37714490 5800419 35819797 7 0. 1 52.8 7 0. 1 52.8 65.2 46.4 64.7 46.0 4.6 2 7. 9 date and duration of each)
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Unit returned to Service December 1, 1988 at 0122 8-1-7.R2
Completed by No.
Date 0 223 11-01-88 0 223 11-01-88 0 223 11-01-88 0 223 11-01-88 0 223 11-01-88 1
F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH.
NOVEMBER 1988 Unit Name Salem No.2 Date 12-2-88 Art Orticelle Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective Type Hours Reason Down Event System Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence Normal.Nuclear s
720 c
4 RC VESSEL Refueling Nuclear Reactor s
720 c
4 RC VESSEL Overhaul Genera tor s
720 c
4 HA GENERA Major Overhaul e
Maj or Turbine s
7 20 c
4 HA TURBIN Overhaul Misc. Major s
720 c
4 RC HTEXCH Condenser Overhaul 2 Reason 3 Method 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 A-Equipment Failure-explain B-Maintenance or Test C - R e f ue 1 in g D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther
WO NO 861001016 871026146 871026149 880301220 880510199 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2SV759-PZR FAILURE DESCRIPTION:
2SV759-PZR VENT LINE 2PR1/PM/REPLACE AIR REG.
2 22GB923 FAILURE DESCRIPTION:
IS RUSTED IN THE OPEN POSITION REWORK THE BONNET.
2 24GB923 FAILURE DESCRIPTION:
RUSTED IN THE OPEN POSITION REWORK D-8 BONNET.
2 21SW77 FAILURE DESCRIPTION:
VALVE FAILS TO CLOSE/REPAIR/A-114.
2 ELIMINATE RTD BYPASS PIPING PER 2EC-2230 PKG #2 FAILURE DESCRIPTION:
INSTALLATION OF NEW THERMOWELLS/RTDS ON HOT AND COLD LEG.
WO NO 880518010 880518011 880518012 880518013 880608116 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
11 A 11 REACTOR TRIP BYPASS BREAKER FAILURE DESCRIPTION:
REPLACE UV TRIP DEVICE.
2 11 B 11 REACTOR TRIP BREAKER FAILURE DESCRIPTION:
REPLACE UV TRIP DEVICE.
2 II B II REACTOR TRIP BREAKER FAILURE DESCRIPTION:
REPLACE UV TRIP DEVICE.
2 II A II REACTOR TRIP BREAKER FAILURE DESCRIPTION:
REPLACE UV TRIP DEVICE.
2 REACTOR HEAD THERMOCOUPLE COLUMN DEMOLITION.
FAILURE DESCRIPTION:
CUT AND WELD CAPS ON FIVE (5) CONOSEALS ON THE REACTOR HEAD.
SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 880620115 2
21 STM. GEN. "J" NOZZLE FAILURE DESCRIPTION:
REPLACEMENT DCR. 2-SM-0567.
880620128 2
22 STM. GEN. "J" NOZZLE FAILURE DESCRIPTION:
REPLACEMENT/DCR 2-SM-0567.
880621083 2
23 STM. GEN. "J" NOZZLE FAILURE DESCRIPTION:
REPLACEMENT/DCR 2-SM-0567.
880621085 2
24 STM. GEN. "J" NOZZLE FAILURE DESCRIPTION:
REPLACEMENT/2-SM-0567.
880906130 2
2C DIESEL GEN SUMP PUMP FAILURE DESCRIPTION:
DOES NOT RUN/TROUBLESHOOT.
880915099 2
M.T.L.O. LEVEL ALARM FAILURE DESCRIPTION:
CAN NOT BE ACKNOWLEDGED/REWORK.
WO NO 881021093 881029051 881029060 881031132 881101223 881101242 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
22 AUX FEED PUMP FAILURE DESCRIPTION:
HAS EXCESSIVE PACKING LEAKAGE
- 2 21 CFCU FAILURE DESCRIPTION:
LEAK ON MOTOR COOLER/REPLACE.*
2 2A DIESEL FAILURE DESCRIPTION:
WAS SYNCHRONIZED OUT OF PHASE PLEASE INSPECT FOR DAMAGE.
2 2A DIESEL GENERATOR FAILURE DESCRIPTION:
REMOVE 2A 4KV GENERATOR/SHIP TO CMS FOR REPAIR/
REINSTALL.
2 2EP PZR HTR BUS FAILURE DESCRIPTION:
WIRING DEGRADED/REWORK.
2 2C 125 VDC BTRY RM EXH FAN MTR FAILURE DESCRIPTION:
INOPERABLE/REWORK.
WO NO 881111047 881112046 881114078 881114082 881116089 920301006 SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
2LT461 PZR LVL FAILURE DESCRIPTION:
TRACKING 5% LOW/TROUBLESHOOT.
- 2.
2LT93 5B-2 2 2
2 2
FAILURE DESCRIPTION:
2LT935B-22 ACCUM LVL CHAN "A"-NO ALARM WITH UNSAT LEVEL.
2PT403-POPS CHANNEL FAILURE DESCRIPTION:
NO ALARM WITH HI PRESS-INVESTIGATE & FIX.
2PT-405-POPS CHANNEL FAILURE DESCRIPTION:
NO ALARM WITH HI PRESS-INVESTIGATE & FIX.
22 RCP FAILURE DESCRIPTION:
ADD BALANCE WEIGHTS AS DIRECTED BY MAPLEWOOD LAB.
2 23 REACTOR COOLANT PUMP SEALS FAILURE DESCRIPTION:
INSPECT AND OR REPLACE 23 REACTOR COOLANT PUMP SEAL PACKAGE.
I
MA~OR PLANT MODIFICA~NS REPORT. MONTH NOVEMBER 1988
- OCR NO.
PRINCIPAL SYSTEM 2EC-1808/A Circulating Water 2EC-2085 Fire Protection 2SC-0382 Circulating Water Design Change Request DOCKET NO: e UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
DESCRIPTION 50-311 Salem 2 December 10, 1988 P. White 609/339-4455 This design change upgraded the materials of construction of the strainer shells.
The backwash was also revised to be continuous at a reduced flow.
This design change installed five 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire dampers in the Auxiliary Building stairwells to prevent the spread of fire between floor elevations via the stairwells.
This design change upgraded the circulating water travelling screen contactor panels and bearing lubrication strainer timing panels from carbon steel to fiberglass NEMA 4 enclosures.
The internal components were also upgraded.
e MAJOR PLANT MODIFICATIONS REPORT MONTH -
NOVEMBER 1988 e
DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- DCR SAFETY EVALUATION 10 CFR 50.59 50-272 Salem 2 December 10, 1988 P. White (609)339-4455 2EC-1808/A This design change upgraded the materials of construction as the previous materials were not suitable for the service water environment and experienced excessive corrosion.
The modification to the backwash operation was to reduce strainer clogging and the frequency of manual cleaning.
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-2085 The installation of the fire dampers in the Auxiliary Building stairwells will prevent fire spread between floors via the stairwells.
This modification did not alter any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
2SC-0382 This design change will eliminate the severe corrosion problems experienced with the control panel enclosures and associated electrical components.
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 NOVEMBER 1988 The Unit began the period shutdown for a refueling/maintenance outage.
On November 28, 1988, following completion of the outage activities, a unit startup was performed and a power escalation commenced.
- Later, the same day, the Unit tripped on a lo-lo level condition in No. 22 Steam Generator.
The trip was caused by problems with No. 23 feedwater regulating valve.
The feedwater regulating valves were adjusted and the process loop tuned and a startup was again commenced.
The Unit completed the period operating at reduced power to heat soak the turbine prior to performance of the overspeed trip test.
REFUELING INFORMATION DOCKET NO.: 50-311 UNIT NAME: Salem 2 COMPLETED BY:
P. White DATE: December 10, 1988 609/935-6000 TELEPHONE:
EXTENSION 4455 Month November 1988
- 1.
Refueling information has changed from last month:
- 2.
- 3.
- 4.
YES NO X
Scheduled date for next refueling:
January 6, 1990 Scheduled date for restart following refueling:
February 20,1990 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?
November 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
8 0
- 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:
193 308 1170 1170 March 2003