ML18094A341
| ML18094A341 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1989 |
| From: | Miller L, Orticelle A Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8904190227 | |
| Download: ML18094A341 (10) | |
Text
.,
OPS~G 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.
1 DOCKET NO. 50-272 April 13, 1989 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports for the month of March 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 Sincerely yours,
~~~
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 The Energy People 95-2189 (SM) 12-88'-
l~VFRAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name
-;::;S:-a'l_e_m-e#~l:------
Dat e 4-06-89 Completed by Art Orticelle
-;:-;::-:::--~>;=-"~,...,,,.-;..---~
Telephone 609-935-6000 Month MARCH 1989 Day Average Daily Power 011;ve-NET) 1 1068 2
1081 3
1104 4
1084 5
1093 6
1100 7
1084 8
1093 9
1085 10 1101 11 1098 12 1106 13 1080 14 1108 15 1084 16 1096 P. 8.1-7 Rl
~331 r-- 89041902?! ~0%800272 PDR ADOC~
~
PDC R
Extension 4451
~----------~
Level Day Average Daily Power Level (MWe-NET) 17 1106 18' 1082 19 1114 20 1090 21 968 22 968 23 96 8 24 0
25 0
26 0
27 0
28 0
29 0
30 0
31 0
Of'"f.RAT-NG DATA REPORT
.. e Docket No.50-272 Date: 4-o6=-89
- -:;-;:--;:~;-:::--~~~-
Telephone: 935-6000 Completed by Pell White Extension: 4451*~~-----
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period March 1989
- 3.
Licensed Thermal Power (MWt) 3411
- 4.
Nameplate Ra.ting (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe) 1115
- 6.
Maximum Dependable Capacity(Gross MWe)1149
- 7.
Maximum Dependable Capacity (Net MWe) 1106
- 8.
If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason_N/ ~---
- 9.
Power Level to Which Restricted, if any (Net MWe)
N/A *
- 10. R.easons for Restrictions, if any N/A
- ~~-~~--------~-~--~
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
1 8.
- 19.
2 0.
- 21.
- 22.
2 3.
Hours in Reporting Period No. of Hrs. Reactor was Critical Reactor Reserve Shutdown Hrs.
Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)
Gross Elec. Energy Generated (MWH)
Net Elec. Energy Generated (MWH)
Unit Service Factor Unit Availability Factor Unit Capacity Factor (using MDC Net)
Unit Capacity Factor (using DER Net)
Unit Forced Outage Rate This Month 744
---54 7. 75 0
547.44 0
1855636.8 618650 589690
--73:_6 __
73.6
- 71. 7 71.1 15.5 Year to Date 2160 1862. 33 0
1811.75 0
6106848 20 39200 1949124 83.9 83.9
- 81. 6 80.9 9.4 Cumulative 103033 66494.53 0
64447.65 0
201543640.4 66986380 63755239
- 62. 6 62.6 55.9
- 55. 5 22.0
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NONE LS. If shutdown at end ot Report Period, Estimated Date of Startup:
__ Refueling outage __ lasting approxima!:_~58 days ~tartup May 24, 1989.
8-1-7.R2
Completed by No.
Date 0068 3-22-89 0069 3-23-89 0071 3-28-89 0071 3-28-89 0071 3-28-89 1
F: Forced S: Scheduled UNTT SHUTDOWN AND POWER REDUCT TONS Docket No.50-272 REPORT MONTH MARCH 1989 Unit Name Salem No. 1 Art Orticelle Method of Duration Shutting Type Hours Reason Down 1
F F
s s
s 2
Reactor 5.58 F
5 100.58 F
2 95.98 c
4 95.98 c
4 95.98 c
4 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 License Event ReE ort Date 4-06-89 Telephone 609-935-6000 Extension 44 51 System Component Code 4 Code 5 HH HT EX CH EB TRAN SF CA VESSEL HA GENERA HA Tl1RB1N 3 Method I-Manual 2-Manual Scram.
3-Automatic Scram.
Cause and Corrective Action to Prevent Recurrence CONDENSER TUBE WATF.R BOX CLEAN PHASE A AND c MAIN POWER TRANSFORMERS NUC:l.F.AR REACTOR OVERHAUL GENERATOR MAJOR OVERHAUL MAJ 0 R TURBINE OVERHAUL 5 Exhibit 1 Salem as Source 1 4-Continuation of 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exam Previous Outage 5-Load Reduction 9-0ther
WO NO 870815152 871028116 880801162 880824076 881129125 890131111 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
11DA14C(SV-891)
FAILURE DESCRIPTION:
lCDG START AIR MOTOR SV/REPLACE.
1 12CS48 FAILURE DESCRIPTION:
AA45 FAILED.LEAK RATE TEST/OPEN AND INSPECT VALVE INTERNALS.
1 lC DIESEL 1
1 1
FAILURE DESCRIPTION:
SR CYL. JACKET WATER INLET IS LEAKING AT THE TRIANGLE FITTING.
- 12 AUX EXH FAN FAILURE DESCRIPTION:
SHEAVE WORN OUT/REPLACE WITH NEW ONE.
13 CHG. PUMP FAILURE DESCRIPTION:
SUCTION STABILIZER/BLADDER LEAK/REWORK.
14MS10 FAILURE DESCRIPTION:
MN STM VLV/NOT CLOSING/TROUBLESHOOT.
WO NO 890301222 890306149 890315129 890317118 890821005 SALEM UNIT 1
- UNIT EQUIPMENT IDENTIFICATION 1
1WR81 FAILURE DESCRIPTION:
FAILED THE 4.0.5-V-MISC-l/REWORK AA-42.
1 FA5753 FAILURE DESCRIPTION:
13 AFP IND/ERRONEOUS IND/INVESTIGATE.
1 1WG38 WST GAS VALVE FAILURE DESCRIPTION:
NO BACKPRESS CONTROL/REWORK.
1 13 AUX FEED PUMP FAILURE DESCRIPTION:
AUX FEED WATER PUMP START INDICATION/DOES NOT LIGHT/TROUBLESHOOT.
1 llESD FAILURE DESCRIPTION:
BKR FAIL 24 MO PM/RELAY DEPT TO DO 2 YR PM ON 11 llESD BKR FAIL RELAYS.
MAJOR PLANT MODIFICATIONS REPORT MONTH MARCH 1989
- DCR NO.
PRINCIPAL SYSTEM lSC-1189 Various
- DCR -
Design Change Request e
DOCKET NO.:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 Salem 1 April 10, 1989 P. White 609/339-4455 DESCRIPTION This design change replaced various obsolete ASCO solenoid va*lves with new HC coil type valves.
The new valves are identified on the solenoid valve equipment list as acceptable replacements to be used.
e e
MA*JOR PLANT MODIFICATIONS REPORT MONTH MARCH 1989 DOCKET NO.:
UNIT NAME:
50-272 Salem 1
- DCR lSC-1189 DATE:
April 10, 1989 COMPLETED BY:
P. White TELEPHONE:
60 9 /3 39-44 55 SAFETY EVALUATION 10 CFR 50.59 This design change replaced obsolete solenoid valves with similar valves of an upgraded type.
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. 1 SA.LEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 MARCH 1989 The Unit began the month operating at full power and continued to operate at essentially full power until March 22, 1989, when the power was reduced to 60%, as a precautionary measure, while technicians cleared a steam generator feed pump vacuum sensing line.
On March 23, 1989, the Unit was briefly restored to full power, however, it was removed from service later the same day due to the discovery of an accumulation of combustible gases in phase "A 11 of the main power transformer.
An internal inspection of the transformer revealed that the long series connector on the low voltage side was partially burned.
Because of the time requirea to repair or replace the transformer, the start of the refueling outage was moved from April 15, 1989 to March 28, 1_989.
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
P. White UNIT NAME:
Salem 1 DATE:
April 10, 1989 TELEPHONE:
609/935-6000 EXTENSION:
4497 Month MARCH 1989
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
March 28, 1989
- 3.
Scheduled date for restart following refueling: May 24, 1989
- 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO
'-4 NOT DETERMINED TO DATE X
B)
Ras the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no,- when is it scheduled?
April 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
April 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 193 518 1170 1170 September 2001