ML18093A528
| ML18093A528 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1987 |
| From: | Miller L, White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8712170049 | |
| Download: ML18093A528 (11) | |
Text
- .
e e
AVERAGE DAILY UNIT POWER LEVEL Completed by Pell White Docket No.
Unit Name Date Telephone Extension Month November Day Average Daily (MW'e-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
,---*ra7i2i :70049-* 071130 YDR ADOCK 05000272
.R
.. DCD*
.;.11.;
1987 Power Level Day Average Daily (MW'e-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
50-272 Salem ~#~l~~~~
December 10, 1987 609-935-6000 4451 Power Level
e OPERATING DATA REPORT Completed by Pell White Operating Status
- 1.
Unit Name Salem No. 1 Docket No.50-272
-~~~~~-=-=,---,'"'="'=""
Date: December 10,1987 Telephone: 935-6000 Extension: ~4~4~5~1~~~~~~~
Notes
- 2.
Reporting Period November 1987
- 3.
Licensed Thermal Power (l\\11Wt) 3411
- 4.
Nameplate Rating (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe) 1115
- 6.
Maximum Dependable Capacity(Gross M.we)1149
- 7.
Maximum Dependable Capacity (Net MWe) 1106
- 8.
If Changes Occur in Capacity Ratings (i terns 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
~-..:..~~~~~~~~~~~~~~~~~~~
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 8016 91345
- 12. No. of Hrs. Reactor was Critical 0
6412.5 57695.1
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 0
6363.2 55791.8
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (M.WH) 0 19612962.8 172269008.8
- 17. Gross Elec. Energy Generated (MWH) 0 6496490 57194490
- 18. Net Elec. Energy Generated (MWH)
-2077 6214534 54399302
- 19. Unit Service Factor 0
79.4 61.1
- 20. Unit Availability Factor 0
79.4 61.1
- 21. Unit Capacity Factor (using MDC Net) 0 70.1 53.8
- 22. Unit Capacity Factor (using DER Net) 0 69.5 53.4
- 23. Unit Forced Outage Rate 0
0.60 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:
1~-13-87 8-l-7.R2
Completed by No.
Date 0 280 10-02-87 1
F: Forced S: Scheduled GNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH NOVEMBER 1987 Docket No. 50--27 2 Unit Name
=s-a~l-e-m--=~~~o--.1,,..-----
Pell White Method of Duration Shutting License Type Hours Reason Down Event 1
2 Reactor Report s
1419 c
1 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
!:I-Other-explain Date December 10~ 198"7",.
Telephone 609-935-6000 Extension 44 51 System Component Code 4 Code 5 zz zzzzzz 3 Method 1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther
~--~--------~
Cause and Corrective Action to Prevent Recurrence REFUELING OUTAGE 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
I 5 Exhibit 1 Salem as Source
WO NO 870211007 870330019 870611052 870708040 870916172 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
1ASIS212 FAILURE DESCRIPTION:
HANGER HAS MOVED OFF ITS SUPPORT, MOVE HANGER BACK ONTO ITS SUPPORT.
1 SV-690 FAILURE DESCRIPTION:
SOLENOID VALVE SV-690 IS LEAKING AIR AND MUST BE REPLACED.
1 1CH63 FAILURE DESCRIPTION:
A128 PACKING LEAK.
REPACK VALVE.
1 11SW127 FAILURE DESCRIPTION:
11SW127 DOES NOT CONTROL IN AUTO TO CORRECT SETPOINT.
1 lB 125VDC BATTERY FAILURE DESCRIPTION:
lB 125VDC BATTERY HAS VOLTAGE PROBLEM.
INVESTIGATE
WO NO 87101150 871011051 871020162 871028155 871029078 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
lSW-710 PIPE SPOOL 1
FAILURE DESCRIPTION:
X-RAY SHOWED WELD lSW-710 HAS PITTING THAT VIOLATES MIN.
1SW-747B PIPE SPOOL FAILURE DESCRIPTION:
X-RAY.SHOWED WELD 1SW-747B 136 HAS LACK OF PENETRATION.
1 1VC6 VALVE ACTUATOR TUBING FAILURE DESCRIPTION:
1VC6 VALVE ACTUATOR TUBING IS BENT AND DAMAGED.
1 RVLIS/RX VESSEL LEVEL TRAIN A FAILURE DESCRIPTION:
RVLIS/REACTOR VESSEL LEVEL TRAIN A REMOTE DISPLAY IS VERY DIM.
1 1CV296 FA41 FAILURE DESCRIPTION:
1CV296 FA41 OPEN AND INSPECT VALVE INTERNALS.
REPAIR OR REPLACE.
WO NO 871101123 871106037 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
1SW21 PIPE SPOOL FAILURE DESCRIPTION:
DURING THE 10 YEAR ISI HYDRO, A LEAK WAS FOUND IN SPOOL.
1 lB DIESEL GEN FAILURE DESCRIPTION:
lB DIESEL GENERATOR TRIPPED AFTER 14 SECONDS OF START.
MAJOR PLANT MODIFICATIONS REPORT MONTH NOVEMBER 1987
- DCR NO.
lEC-1186 lEC-1966 lED-0221 lSC-1546 PRINCIPAL SYSTEM Rad Monitoring System RVLIS Service Water Full Length Con tro 1 Rods
- DCR -
Design Change Request DOCKET NO.:
50-272 UNIT NAME:
Sal_e_m___,1=---------
DATE:
December 10,1987 COMPLETED BY:L. Miller TELEPHONE:
_6_0_9_/_3_3_9 ___ 4_4_9_7 ______ _
SUBJECT Circuit design change on battery back-up and charging circuit for monitor 1-R40.
Modify the RVLIS system using Westinghouse procedure NSID-EIS-84-15, to upgrade the system to the current requirements.
Modification of service water system for control valves, controls and addition of pump recirculation system.
Delete the overhead annunciator (D-32) for bank D rod withdrawal at 228 steps.
MAJOR PLANT MODIFICATIONS REPORT MONTH NOVEMBER 1987 DOCKET NO.
UNIT NAME:
50-272 Salem 1
- DCR lEC-1186 lEC-1966 lED-0221 lSC-15 46 system DATE:
December 10,1987 COMPLETED BY:
J. Ronafalvy TELEPHONE:
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This design change modified the charging circuit of Radiation Monitor l-R40 to correct a deficiency.
The function of the monitor is not changed.
The monitor is not involved in any accident analysis or safety evaluation for the plant.
This modification does not alter any plant process or discharge or affect the impact of the plant.
No unreviewed safety or environmental questions are involved.
All potential electrical failure modes have been considered but do not present a problem.
This modification upgraded the RVLIS to meet the requirements of NUREG 0737, including the seismic requirements.
There has been no change to any plant process or discharge or the existing impact of the plant.
No unreviewed safety or environmental questions are involved.
This modification involved cabling to provide for limit switches on valves in the Service Water System.
No changes were made in any safety function, safety margin, or analysis.
There has been no change to any plant process or discharge or the existing impact of the plant.
No unreviewed safety or environmental questions are involved.
This is a change to the overhead annunciator which is not safety related.
The design change does not involve any safety related system, structure, or component nor does it affect any existing safety evaluation.
There has been no change to any plant process or discharge or the existing impact of the plant.
No unreviewed safety or environmental questions are involved.
DCR - Design Change Request
(
SALPM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 NOVEMBER 1987 The Unit began the period with the refueling outage in progress.
The core reload was stopped on November 24, 1987, because of fuel assembly interference problems with the new inserts recently installed in the lower core plate guide tubes to preclude flux thimble wear.
With the fuel removed, the inserts will either be machined in place or removed to eliminate the interference problem with the fuel assemblies.
Steam Generator "J" tube modifications have been completed and the SGs are in final inspection for closure.
Problems were identified in the SG feed ring area.
Apparently, the worn "J" tubes diverted the feedwater flow which caused impingment and erosion of the adjacent riser areas.
Several plugs in the SG feed ring have also been identified to be eroded.
The reactor vessel head thermocouple columns have been removed and caps have been welded in place.
The HP Turbine has been reassembled following replacement of the seal strip, inner gland weld repair, and repairs of the blade ring.
All turbine valve work has been returned from the Central Maintenance Facility.
Regrouting of the Main Generator has been completed following removal of the old grout, machining of the bent seating plates, and regrouting with flowable epoxy grout.
Inspection of the LP Turbine blades resulted in replacement of five L-0 blades between Nos. 11 & 12 LP Turbines, and 13 L-1 governor end blades being replaced on No. 12 LP Turbine.
I
.J REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
J. Ronafalvy UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
December 10,1987 609/935-6000 4497 Month NOVEMBER 1987
- 1.
Refueling information has changed from last month:
YES X
NO -----
- 2.
Scheduled date for next refueling:
Mar ch 4, 19 8 9
- 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 Committee?
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 0
657 1170 1170 September 2001
e 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. 1 DOCKET NO. 50-272 December 10, 1987 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 November 1987 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_w~:L~~r.
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