ML18094B133
| ML18094B133 | |
| 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 8910270141 | |
| Download: ML18094B133 (9) | |
Text
e 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. 2 DOCKET NO. 50-311 October 11, 19 89 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specification, 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, x~
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 8-1-7.R4 95-2189 (SM) 12-88
(_
Completed by Art Month SEPTEMBER Day Average Daily (MWe-NET) 1 1086 2
1072 3
1078 4
1089 5
1070 6
1075 7
1075 8
1069 9
99 6 10 1031 11 1069 12 1082 13 1065 14 1069 15 1066 16 1056 Pg. 8.1-7 Rl Jl_VFRAGE DA-LY UNIT POWER LEVEL Orticelle 1989 Power Level Day Docket No.
Pnit Name Date Telephone Extension Average Daily (MWe-NET) 17 10 62 18 1098 19 1070 20 1045 21 1087 22 1082 23 1061 24 1076 25 1086 26 1096 27 1068 28 1078.
29 10 62 30 935 31 50-311 Salem # 2 10-11-89 609-935-6000 4722 Power Level
e OPERATING DATA REPORT Completed by Art Orticelle Operating Status
- 1.
Unit Name Salem No. 2
- 2.
Reporting Period SeEtember 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)1149
- 7.
Maximum Dependable Capacity (Net MWe) 1106
- 8.
If Changes Occur in Capacity Ratings (items Report, Give Reason N/A Docket No.
Date Telephone Extension Notes 3 through 50* *311 t0-11-89 935-6000 4722
- 7) since Last
- 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 720 720 0
720 0
2429035.2 806186 773470 100 100 97.1 Year to Date 6551*
5930 0
5753.3 0
18881006.4 62 86920 6033197 87.8 87.8 83.3 Cumulative 69840 44285.8 0
42875.9 0
83546103.4 44171220 42008502
- 61. 4 61.4 54.4 96.3 82.6 53.9 0
12.2 26.7
- 24. Shutdowns 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 8-1-7.R2
Completed by No.
Date 0202 09-29-89 1
F: Forced S:
S~heduled I.
llNTT SHUTf,OWN AND.ER REDUCTIONS REPORT MONTH SEPTEMBER 1989 Docket No. 50-311.
Unit Name Date Telephone Extension Salem No.2 Art Orticelle Type 1
F Duration Hours
- 11. 1 7 Reason 2
A Method of Shutting Down Reactor 5
... \\*
~** '. ~
License Event Report
. ~--.
-~**.. *.
- '"'i.
2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensin~
F-Administrative G-Operational Error-explain H-Other-explain Exam 10-11-89 609-935-6000 4722 System Code 4 Component Code 5 Cause and Corrective Action to Prevent Recurrence EB TRAN SF 460 VOLT TRANSFORMER 3 Method 4 Exhibit G 1-Manual Instructions 2-Manual Scram.
for Prepara~
3-Automatic Scram. tion of Data 4-Continuation of Entry Sheets Pr~vious Outage for Licensee 5-Lpad Reduction Event Report 9-cither (LER) File (NUREG 0161) 5 Exhib:91 Salem as Source I
__ _J
WO NO 870717053 880915029 890224102 890906116 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 2.
UNIT EQUIPMENT IDENTIFICATION 2
23 AUX FEED PUMP FAILURE DESCRIPTION:
23 AUX FEED PUMP/INSTALL TRIP TEST DEVICE ON 23 AUX FEED.
2 21 WEST M.S.R.
FAILURE DESCRIPTION:
OPEN 21 WEST M.S.R./INSPECT INTERNALS AND
- HYDROSTATIC TEST.
2 2CV57 FAILURE DESCRIPTION:. 2CV57 BUSHING STRIPPED/REPLACE BONNET. M-66 2
22 EHC PUMP FAILURE DESCRIPTION:
22 EHC PUMP START INDICATION/GOES.
OUT/TROUBLESHOOT.
MAJOR PLANT MODIFicttIONS REPORT MONTH SEPTEMBER 1989
- DCR NO.
PRINCIPAL SYSTEM 2SM-OO 178 S/G Blowdown 2SM-00348 4160 Switchgear 2SM-00426 Turbine Bypass 2SM-00638 Feedwater Control Design Change Request DOCKET NA UNIT NA.MP:'
DATE:
COMPLETED BY:
TELEPHONE:
DESCRIPTION 50-311 Salem 2 October 10, 1989 P. White 60 9/ 339-44 55 This design change added isolation valves (21, 22, 23, 24 GB189) upstream of the GBlO Valves.
This design change added dampening material to the 4160 Vital Switchgear doors.
This design change resequenced the turbine bypass valves such that the valves to open first are those on No. 23 Condenser versus No. 21 Condenser.
This design change modified the SGFP speed control program and the feedwater regulating valve delta "P" program.
e
!1AL70R P:!".. ANT MODIFICATIONS REPOR~ MONTH SEPTEMBER 1989 DOCKET NO'.
UNIT NAME:
50--272 Salem 2 DATE:
COMPLETED BY:
TELEPHONE:
October 10, 1989 P. White (609)339-4455
- DCR SAFETY EVALUATION 10 CFR 50.59 2SM-00178 2SM-00348 2SM-00426 2SM-00638 This design change added isolation valves upstream of the GBlO Valves to provide more complete isolation capability of the S/G blowdown tank.
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 and frames to prevent nuisance PVD relay operation due to 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 resequenced the turbine bypass valves such that the valves to open first are those on No. 23 Condenser versus No. 21 Condenser.
This modification more equally shares the heat load between the condensers, enhancing the ability to maintain condenser vacuum.
There was no change to any plant process or discharge or to the environmental impact of plant.
No unreviewed safety or environmental questions are involved.
This design change modified the SGFP speed control program and the feedwater regulating valve delta "P" program.
The modicication allows for enhanced S/G water level control by maintaining the feedwater regulating valves approximately 85% open at 100%
power.
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 STATroN MONTHLY OPERATING
SUMMARY
UNIT NO. 2 SEPTEMBER 1989 The Unit began the period operating at 100% power and with the exception of minor load reductions for maintenance, continued to operate at essentially full power until September 29, 1989.
During that period, combustible gas concentrations were noted to increase in the Phase "B" Main Power Transformer.
Frequent samples were taken and analyzed in conjunction with an engineering evaluation.
On September 29, 1989, power was reduced to 80% to assess the impact of reducing Phase "B" Transformer loading, and the combustible gas concentrations stabilized.
Power was gradually increased to 90% on September 30, 1989, and the unit continued to operate at that power for the remainder of the period.
REFUELING INFORMATION DOCKET NO.:
50-311 UNIT NAME:
Salem 2 COMPLETED BY:
P. White DATE:
October 10, 19 89 TELEPHONE:
609/935-6000 EXTENSION 4455 Month SEPTEMBER 1989
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
March 31, 1990
- 3.
Scheduled date for restart following refueling:
May 14, 1990
- 4.
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.
- 8.
- 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:
193 224 1170 1170 March 2003