ML18094A335
| ML18094A335 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1989 |
| From: | Orticelle A, White P Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18094A331 | List: |
| References | |
| NUDOCS 8904180338 | |
| Download: ML18094A335 (11) | |
Text
AVERAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Month FEBRUARY 1989 Day Average Daily Power Level (MWe-NET) 1 1085 2
1085 3
1085 4
868 5
102 6
0 7
0 8
0 9
23 6 10 737 11 49 9 12 480 13 496 14 933 15 975 16 1034 Pg. 8.1-7 Rl
~~~~~~~~--=~~:--~~\\
r 8904180338 89041L F*r1F)
A~OCK 05000311
/..:
PDC R
Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 97 4 18 867 19 866 20 956 21 979 22 1036 23 1042 24 1101 25 1095 26 1101 27 1109 28 1110 29 30 31 50*-311 Salem # 2 3-10-89 609-935-6000 4451 Power Level
OPERATING DATA REPORT Completed by Pell White Operating Status Docket No.
Date Telephone Extension CORRECTED COPY 50-311 3-10-89 935-6000
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
Unit Name Salem Noa 2 Notes Reporting Period February 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 672 59 0. 5 0
568.3 0
1708567.2 558165 532113 84.6 84.6 71.6 Year to Date 1416 1129.9 0
10 23. 7 0
32 212 44 1051345 1011469 72.3 72.3 64.6 Cumulative 65449 39485. 7 0
38146.3 0
67886341 38935645 36986774 57.6 57.6 51.1 71.0 64.0 50.7 15.4 27.7 28.8
- 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:
N/A 8-l-7.R2
Completed by No~
Date 0043 02-01-89 Art Orticelle Type 1
F Duration Hours
- 2. 18 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1989 Reason 2
B Method of Shutting Down Reactor 5
License Event Report System Code 4 HG Docket No. 50-311 U"nit Name Date Telephone Extension Salem No.2 3-10-89 609-935-6000 4451 Component Code 5 HTEXCH Cause and Corrective Action to Prevent Recurrence WATER BOX CLEANING FEED PUMP TRIP 0052 02-05-89 F
103.73 A
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~T~H"-=E~R~M-A~L---D~I~S~C~H-A_R_G~E----t 0058 02-10-89 F
0059 02-10-89 F
0053 02-10-89 F
0054 02-10-89 F
0060 02-11-89 F
0061 02-13-89 F
0055 02-13-89 F
0062 02-13-89 F
1 F: Forced S: Scheduled
- Corrected Copy 8.65 A
5 24.00 A
5
- 1. 5 B
5 12.00 B
5 52.22 A
5
- 1. 9 2 A
5
- 1. 92 A
5
- 1. 9 2 A
5 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing F-Administrative G-Operational Error-explain H-Other-explain Exam IB INSTRU IB INSTRU HF PUMPXX HF PUMPXX IB INSTRU IB INSTRU HF PUMPXX HF PUMPXX 3 Method I-Manual 2-Manu'al Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load*Reduction 9-0ther LIMITS THERMAL DISCHARGE LIMITS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS THERMAL DISCHARGE LIMITS THERMAL DISCHARGE LIMITS CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS 4 Exhibit G Instructions for Pre para-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit.
Salem as Source
1 UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH FEBRUARY 1989 Unit Name Salem No.2 Date 3-10-1989 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Method of Duration Shutting License Cause and Corrective No.
Date Type Hours Reason Down Event System Component Action to 1
2 Reactor Report Code 4 Code 5 Prevent Recurrence CIRCULATING WATER 0056 02-13-89 F
- 1. 83 A
5 HF PUMPXX PUMPS CIRCULATING WATER 0063 02-13-89 F
- 1. 83 A
5 HF PUMPXX PUMPS THERMAL DISCHARGE
- 0064 02-13-89 F
2.78 A
5 IB INSTRU LIMITS THERMAL DISCHARGE 0065 02.,..14-89 F
.83 A
5 IB INSTRU LIMITS THERMAL DISCHARGE 0066 02-14-89 F
.83 A
5 IB INSTRU LIMITS THERMAL DISCHARGE 0067 02-14-89 F
8.17 A
5 IB INSTRU LIMITS THERMAL DISCHARGE 0068 02-14-89 F
7.75 A
5 IB INSTRU LIMITS CONDENSER TUBE 0070 02-14-89 F
7.65 A
5 HC HT EX CH LEAK INSPECTION CONDENSER TUBE 0075 02-16-89 F
8.73 A
5 HC HT EX CH LEAK INSPECTION CONDENSER TUBE 0082 02-22-89 F
2.52 A
5 HC HT EX CH LEAK INSPECTION CONDENSER TUBE
- 0085 02-23-89 F
- 88 A
5 HC HTEXCH LEAK INSPECTION
SALEM UNIT 2 W_O_N_O ________
U_N_I_T EQ1JIPME~..!_.IDENTIFICATION 890112105 2
23 AFP FAILURE DESCRIPTION:
ERRATIC OPERATION/TROUBLESHOOT.
890119095 2
2B D/G FAILURE DESCRIPTION:
GEAR DRIVEN L.O. PMP NOISY/REPLACE PUMP.
890123100 2
2FI53 2 FAILURE DESCRIPTION:
23 S/G STM FLW/IND LOW/TROUBLESHOOT.
890123105 2
2FI510 FAILURE DESCRIPTION:
21 S/G FD FLW/IND LOW//TROUBLESHOOT.
890125116 2
25SW58 FAILURE DESCRIPTION:
25 CFCU SW VLV/STROKE PROBLEM/TROUBLESHOOT.
890202054 2
2FT531 FAILURE DESCRIPTION:
23 S/G FD FLOW/HIGH READING/TROUBLESHOOT.
WO NO 890202062 8902 030 82 890209141 890216102 890223129 930216001 SALEM UNIT 2 2
2DR432 FAILURE DESCRIPTION:
ROD LIMIT REC/SETPT PEN ERRATIC/TROUBLESHOOT.
2 2PI474A FAILURE DESCRIPTION:
PZR PRESS IND/METER FAILED/TROUBLESHOOT.
2 24MS10-AO FAILURE DESCRIPTION:
MAIN STEAM RELIEF/NO AUTO CONTROL/REPAIR AS REQ.
2 2C DG TURBO CHARGER FAILURE DESCRIPTION:
SUPPORT BOLT BROKEN/REPLACE.
2 2PI 47 4A FAILURE DESCRIPTION:
PZR PRESS IND/METER FAILED/TROUBLESHOOT.
2 21 S.W. PUMP INSP.
FAILURE DESCRIPTION:
PULL 21 SERVICE WTR. PUMP AND INSTALL REBUILT PUMP IAW M6L-2.
WO NO 871201416 880916081 881028117 881121178 890109081 890110185
.FSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2 UNIT EQUIPMENT IDENTIFICATION 2
22MS19 7 FAILURE DESCRIPTION:
HAS A PACKING LEAK, REPLACE THIS D-3 WITH A F-81 VALVE.
2 2C DG/EXHAUST PIPE FAILURE DESCRIPTION:
LEAK/REPLACE GASKETS.
2 2SWE55-FAILURE DESCRIPTION:
REPLACE EXPANSION JOINT.
2 22SW42 FAILURE DESCRIPTION:
FLANGE LEAK/REPLACE GASKETS/MARK NO. BA-100.
2 21 WASTE GAS COMPRESSOR FAILURE DESCRIPTION:
INOPERABLE/REPLACE.
2 2B D/G JACKET WTR HTR FAILURE DESCRIPTION:
LEAKING/REWORK.
~
MALl"OR PLANT MODIFI.IONS "REPORT MONTH FEBRUARY 1989
- OCR NO.
PRINCIPAL SYSTEM None reported for this period.
Design Change Request DOCKET
- UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311
-Salem 2 March 10, 1989
-~hite 6 o 9 I 3 3 9 __...,..4-4=5=5---
DESCRIPTION
MAJOR PLANT MODIFICATIONS REPORT MONTH FEBRUARY 1989 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- DCR SAFETY EVALUATION 10 CFR 50.59 None reported for this period DCR -
Design Change Request 50-272 Salem 2 March 10, 19 89 P. White (609)339-4455
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 FEBRUARY 1989 The Unit began the period operating at full power.
On February l, 1989, a load reduction* was performed for condenser water box cleaning.
On February 2, 1989, the Unit was restored to full power, and, with the exception of some minor load reductions for circulator maintenance, continued to operate at full power until February 5, 1989.
On February 5, 1989, following a power reduction from 90% to 60%, the Unit experienced a Reactor Trip on No. 23 Steam Generator (S/G) Low Level concurrent with a Steam Flow/Feed Flow mismatch.
At the time of the event, Nos. 23A and 238 Circulating Water Pumps and No. 23 Heater Drain Pump were out of service. Four minutes prior to the unit trip, No. 22 S/G Feed Pump (SGFP) had tripped due to low ~
suction pressure.
It was found that the low suction trip setpointlfor No.. 22 SGFP responded high due to failure of the low suction press4re switch.
The Unit was returned to service on February 9, 1989, and power was held at 60% to maintain condenser delta T's due to several circulators being out of service for repairs.
On February 14, 1989, the Unit was restored to full power following the return of a circulator to service.
From February 14, 1989 to February 25, 1989, several load reductions were perf orrned to address condenser tube leak problems, maintain thermal discharge limits, and perform circ pump maintenance.
On February 25, 1989, the Unit was restored to full power and continued to operate at that level throughout the remainder of the period.
REF'UE!,JNG INFORMATION DOCKET NO.:
UNIT NAME:
50-311
-salem---=2-------
COMPLETED BY:
P. White DATE:
March 10, 1989 TELEPHONE:
609/935-6000 EXTENSION 4455 Month February 1989
- 1.
Refueling information has changed from last month:
- 2.
- 3.
- 4.
YES X
NO Scheduled date for next refueling:
March 31, *1990 Scheduled date for restart following refueling:
May 14,1990 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.
B.
- 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:
19 3 224 1170 1170 March 2003
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