ML18095A199
| ML18095A199 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/30/1990 |
| From: | Miller L, Orticelle A Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005180057 | |
| Download: ML18095A199 (10) | |
Text
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 11, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 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 April 1990 are being sent to you.
RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modifications Operating Summary Refueling Information Safety Valve Actuations 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 19046 Enclosures 8-1-7.R4 The Energy People 95-21 89 (11 M) 1 2-84
I AVERAGE DAILY UNIT POWER LEVEL Month APRIL, 1990 Day Average Daily Power Level (MWe-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 Docket No.
Unit Name Date Completed by Telephone 50-272 Salem # 2 05-10-90 Art Orticelle 609-339-2122 Day Average Daily Power Level (MWe-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
31
OPERATING DATA REPORT Docket No:
50-311 Date:
05-10-90 Completed by:
Art Orticelle Telephone:
609-339-2122 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period APRILt 1990
- 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 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 Year to Date Cumulative
- 11. Hours in Reporting Period 719 2879 74928
- 12. No. of Hrs. Reactor was Critical 0
1993.8 47999.7
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 0
1974.1 46519.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy.Generated (MWH) 0 6555801.6 95607541.0
- 17. Gross Elec. Energy Generated (MWH)
-2923 2237880 48284932
- 18. Net Elec. Energy Generated (MWH) 0 2142906 45942812
- 19. Unit Service Factor 0
68.6 62.1
- 20. Unit Availability Factor 0
68.6 62.1
- 21. Unit Capacity Factor (using MDC Net) 0 67.3 55.4
- 22. Unit Capacity Factor (using DER Net) 0 66.8 55.0
- 23. Unit Forced Outage Rate 0
7.6 25.4
- 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:
Estimated date for Unit 2 start-up is May 24, 1990.
8-1-7.R2
NO.
DATE 0050 04/01/90 1
F: Forced S: Scheduled I
I DURATION TYPE 1 (HOURS)
RE.l\\SON 2 s
719 c
UNIT SHUTOOWN AND POWER REDUCTIONS REPORT MONTH APRIL, 1990 METHOD OF I
SHUTITNG LICENSE DOWN EVENT SYS'ID:!
REACIDR REPORT #
CODE 4 4
RC I
ffi'1PONENT CODE 5 FUEI1Q{
OOCKEI' NO. : -'5'--"-0-'-3=11"'-----
UNIT NAME:
Salem #2 DATE:
05-10-90 CDt'1PlEI'ED BY: Art Orticelle TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION
'ID PREVENT RECURRENCE REFUELING 2
3 4
5 Reason:
A-Equipment Failure (&'})lain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E--Operator Training & License Examination F-Administrative G--Operational Error (Ex"})lain)
H--Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous outage 5-1.Dad Reduction 9--0ther Exhibit G - Instrnctions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report (LER} File (NUREG--0161}
I I
MAJOR PLANT MODIFICATIONS MONTH: -
~PRIL 1990 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 MAY 10, 1990 M. MORRONI (609) 339-2068
7------
Design Change Request DESCRIPTION This design change provided motor operators for the Component Cooling Water Pumps suction header valves 2CC17 and 2CC18.
MAJOR PLANT MODIFICATIONS MONTH: -
APRIL 1990 DOCKET NO:
50-311 UNIT NAME:
SALEM 2 DATE:
MAY 10, 1990 COMPLETED BY:
M. MORRONI TELEPHONE:
(609) 339-2068
- DCR 2EC-01015 SAFETY EVALUATION 10 CFR 50.59 This design change provided motor operators for the Component Cooling Water Pumps suction header valves 2CC17 and 2CC18.
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
SAFETY R&LATED MAINTENANCE MONTH: -
APRIL 1990 DOCKET NO:
50-311 UNIT NAME:
SALEM 2 WO NO UNIT 880403036 2
880403037 2
881214127 2
891201123 2
900410187 2
DATE:
MAY 10, 1990 COMPLETED BY:
M. MORRONI TELEPHONE:
(609) 339-2068 EQUIPMENT IDENTIFICATION VALVE 22CS2 FAILURE DESCRIPTION:
REPLACE TORQUE SWICH, PERFORM WIRING CHANGE AND MOVATS TESTING VALVE 21CS2 FAILURE DESCRIPTION:
REPLACE TORQUE SWITCH, PERFORM WIRING CHANGE AND MOVATS TESTING VALVE 22CC293 PIPING FAILURE DESCRIPTION:
PIPE UPSTREAM OF VALVE 22CC293 HAS A HOLE -
WELD/REPAIR 25 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
REMOVE AND DISPOSE OF EXISTING SERVICE WATER PIPING 2C DIESEL GENERATOR FAILURE DESCRIPTION:
6R & 9R HEAD REPLACEMENT
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 APRIL 1990 The Unit remained shutdown throughout the period for a refueling outag*e.
REFUELIN~ ~NFORMATION MONTH: -
APRIL 1990 MONTH APRIL 1990 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 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:
so-3i1 SALEM 2 MAY 10, 1990 M. MORRONI (609) 339-2068 May 24, 1990
- 4.
a)
Will Technical Specification changes or other license amendments be required?:
YES NO NOT DETERMINED TO DATE ~-x~-
b)
Has the reload fuel design been reviewed by the Station Operating Review Committee?:
YES x
NO If no, when is it scheduled?:
- 5.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 6.
Important licensing considerations associated with refueling:
- 7.
Number of Fuel Assemblies:
- a.
Incore 0
- b.
In Spent Fuel Storage 509
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170
- 9.
Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
March 2003 8-1-7.R4
CHALLENGES TO PORVs OR SAFETY VALVES Salem Unit 2 In accordance with the requirements of Salem Generating Station Unit 2 Technical Specifications Section 6.9.1.6, the following recent challenges to PORVs or Safety Valves are being reported:
04/03/90 -
On April 3, 1990, Salem Unit 2 POPS valve 2PR1 actuated after removing No. 23 Reactor Coolant Pump (RCP) from service and placing No. 21 RCP in service.
The RCPs were swapped in support of "crud burst" operations.
Reactor Coolant System (RCS) indicated pressure was 320 psig at the time of swapping the RCPs.
The indicated RCS pressure during the POPS actuation was 360 psig.
After the first POPS actuation, three additional actuations occurred until pressure control was regained by removing No. 21 RCP from service and placing No. 23 RCP back in service.
The maximum RCS pressure observed during any of these actuations was 365 psig.
RCS pressure was reduced to approximately 310 psig upon regaining pressure control.