ML18094B134
| ML18094B134 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/30/1989 |
| From: | Miller L, Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8910270153 | |
| Download: ML18094B134 (9) | |
Text
- c pstocf 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 October 11, 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 September 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 95-2189 (SM) 12-88
Completed by Art Month SEPTEMBER Day Average Daily (MWe-NET) 1 1039 2
500 3
556 4
531 5
53 9 6
540 7
549 8
534 9
545 10 886 11 1065 12 1075 13 1070 14 1062 15 1075 16 1078 P. 8.1-7 Rl 1-VFRAGE DAJT,Y UNIT POWER LEVEL Orticelle 1989 Power Level Day Docket No.
enit Name Dclte Telephone Extension 50-272 Salem # 1 10-11-89 609-935-6000
. 4722 Average Daily Power Level (MWe-NET) 17 1080 18 993 19 534 20 540 21 530 22 535 23 550 24 549 25 88 9 26 1118 27 1094 28 1116 29 1086 30 1105 31
'/
\\.PFRATING DATA REPORT Docket No 50* 272
-=-~c--'.=-=-~~-~
Date: 10-11-89 Telephone: 935-6000
-..-::=-:::--~~~---
Art Orticelle Ex t~nsion: 4722 Completed by
-~~--~---
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period September 1989
- 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)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)
N/A
~~~~---~~~--
- 10. Reasons for Restrictions, if any N/A
~--~-----~----~~----~-
This Month
- 11. Hours in Reporting Period 720
- 12. No. of Hrs. Reactor was Critical 720
- 13. Reactor Reserve Shutdown Hrs.
0
- 14. Hours Generator On-Line 720
- 15. Unit Reserve Shutdown Hours 0
- 16. Gross Thermal Energy Generated (MWH).
1905448. 8
- 17. Gross Elec. Energy Generated (MWH) 615700
- 18. Net Elec. Energy Generated (MWH) 584693
- 19. Unit Service Factor 100 2 0. Unit Availability Factor 100
- 21. Unit Capacity Factor (using MDC Net) 73.4
- 22. Unit Capacity Factor (using DER Net) 72.8 2 3. Unit Forced Outage Rate 0
Year to Date 6551 42 93. 2 0
4107.8 0
13126840.8 4329890
--:rr11761 6 2. 7 62.7 5 6. 7 56.3 10.2 Cumulative 107424 68925.4 0
66743. 7 0
208563633.2 69277070 65917876 62.1 62.1 55.5 55
- 21. 7
- 24. Shutdown*s scheduled over next 6 months (type, date and duration of each)
NONE*
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A 8-l-7.R2
/j
Completed by No.
Date 0114 9-02-89 0113 9-02-89 0115 Q-04-89 0121 9-18-89 0123 9-19-89 0125 9-20-89 1
F: Forced S: Scheduled PNT.T SnUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH SEPTEMBER* 1989 Unit Name Salem No.1 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Even.t 1
F F
F F
F F
2 Reactor
- 31. 5 A
5 40.75 A
5 148. 8*3 A
5 14.5 A
5
- 16. 1 7 A
5 13 2 A
5 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Ref ue ling D-Regulatory Restriction Report E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain Tl
"'.._ t...,... -
,...,..,.,.... 1...,, ~ -
Date 10-11-89 Telephone 609-935-6000 Extension 47 22 System Component Code 4 Code 5 cc VALVEX CH PUMP XX CH VALVEX CH PUMP XX CH PUMP XX CH PUMP XX 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 EHC LEAK fl 12 SGFP CONTROLS FEEDWATER CHECK e
VALVE fl 12 SGFP fl 12 SGFP fll 2 SGFP 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 890511092 890806066 890831150 890922039 890925090 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
lA PRE LUBE PUMP FAILURE DESCRIPTION:
THE PRE LUBE PUMP ON lA DIESEL IS LEAKING.
1 llSW FAILURE DESCRIPTION:
llSW STR PACKING LEAK/REPACK.
1 12SW91 FAILURE DESCRIPTION:
12SW91/TEE LEAKING/REWORK.
1 4KV FAILURE DESCRIPTION:
4KV VITAL & GROUP BUSES/PERFORM M3T/PER FEG LIST.
1 16SW2 4 FAILURE DESCRIPTION:
16SW24: 16 SERVICE WATER PUMP STRAINER BACKWASH VALVE DOESN'T OPEN.
Ml\\.JOR PLANT MODIFICATIONS REPORT MONTH SEPTEMBER 1989
- OCR NO.
PRINCIPAL SYSTEM lEC-02186 Boron Injection 1SC-00821A Turbine Sump lSM-00348 4160 Switchgear lSM-00351 Rx Cavity
- DCR -
Design Change Request
- e.
DOCKET NO.:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50- 27 2 Salem 1 October 10, 1989 P. White 609/339-4455 DESCRIPTION This design change reduced the boron concentration in the Boron Injection Tank (BIT) from 21,000 ppm to less than 7,000 ppm.
Additionally, the recirculation line between the BIT and Boron Addition Tank (BAT) was cut and capped and the heat tracing disconnected.
This design change replaced the turbine area sump pump with a vertical cantilever pump.
This design change added dampening material to the 4160 Vital Swit~hgear doors.
This design change provided for the installation of new quick locking sandbox & NI covers in the Reactor Cavity during refueling operations.
MAJOR PLANT MODIFICATIONS REPORT MONTH SEPTEMBER 1989 DOCKET NO.:
UNIT NAME:
50-27 2 Salem 1
- DCR lEC-02186 1SC-00821A lSM-00348 lSM-00351 DATE:
COMPLETED BY:
TELEPHONE:
SAFETY EVALUATION 10 CFR 50.59 October 10, 1989-P. White 609/339-4455 This design change reduced the Boron concentration in the Bornon Injection Tank (BIT) from 21,000 ppm to less than 7,000 ppm.
Additionally, the recirculation line between the BIT and Boron Addition Tank (BAT) was cut and capped and the heat tracing disconnected.
It was determined that sufficient boration capability exists with the inventory of borated water maintained in the RWST.
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.
This design change replaced the turbine area sump pump with a vertical cantilever pump.
The new pump is of improved design and should serve better in the intended application.
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.
This design change added dampening material to the 4160 Vital Switchgear doors to prevent nuisance PVD relay operation due to inadvertent door closure.
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.
This design change provided for the installation of new quick locking sandbox & NI covers in the Reactor Cavity during refueling operations.
Use of the new covers reduces installation time and personnel exposure.
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 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 SEPTEMBER 19 8 9 The Unit began the period in a power escalation and achieved full power on September 1, 1989.
On September 2, 1989, power was reduced to approximately 35% and then raised to 54% to facilitate repair of identified EHC system leaks.
During the power reduction, a failure of No. 12 Steam Generator Feedpump (SGFP) discharge check valve was identified.
While repairs were in progress the Unit continued to operate at approximately 54% power.
The repairs were completed and the Unit was restored to full power on September 10, 1989.
The Unit continued to operate at essentially full power until September 18, 1989, when power was reduced to approximately 54% to allow inspection of No. 12 SGFP coupling and alignment.
On September 25, 1989, the Unit was restored to full power and continued to operate at essentially full power for the remainder of the period.
PEFUELING INFORMATION DOCKET NO.~
50-27 2 COMPLETED BY:
P. White UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
October 10, 1989 609/935-6000 4497 Month SEPTEMBER 1989
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
October 6, 1990
- 3.
Scheduled date for restart following refueling: November 19, 1990
- 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?
September 1990
- 5.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 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:
8-1-7.R4 193 540 1170 1170 September 2001