ML18095A200
| ML18095A200 | |
| 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 9005180058 | |
| Download: ML18095A200 (9) | |
Text
e 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. 1 DOCKET NO. 50-272 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 Sincerely yours,
- le~
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 95-2189 (11M)12-84
Month APRIL, 1990 Day Average Daily Power (MWe-NET) 1 0
2 0
3 0
4 0
5 0
6 0
7 122 8
890 9
587 10 0
11 0
12 0
13 0
14 0
15
- 0.
16 0
P. 8.1-7 Rl AVERAGE DAILY UNIT POWER LEVEL Level Docket No.
Unit Name Date Completed by Telephone 50-272 Salem # 1 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:
50-272 Date:
05-10-90 Completed by:
Art Orticelle Telephone:
609-339-2122 Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period April 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 112512
- 12. No. of Hrs. Reactor was Critical 108.68 2162.68 73071.23
- 13. Reactor Reserve Shutdown Hrs.
0 0
0
- 14. Hours Generator On-Line 48.87 2102.79 70798.55
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 134088.0 6892562.4 221993488.4
- 17. Gross Elec. Energy Generated (MWH) 41440 2290760 73752120
- 18. Net Elec. Energy Generated (MWH) 26313 2203218 70214928
- 19. Unit Service Factor 6.8 73.0 62.9
- 20. Unit Availability Factor 6.8 73.0 62.9
- 21. Unit Capacity Factor (using MDC Net) 3.3 69.2 56.4
- 22. Unit Capacity Factor (using DER Net) 3.3 68.6 56.0
- 23. Unit Forced Outage Rate 93.2 27.0 21.6
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Unit #1 Eighth Refueling scheduled on October 6, 1990 and lasting 45 da s.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
Estimated start-up date of May 11, 1990.
8-1-7.R2
NO.
DATE 0033 4-01-90 0035 4-09-90 I
I I
1 F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REFDRI' MONTH APRIL 1990 OOCKEI' NO.:
--'5'--"0--'-2"'--'7~2 ___ _
UNIT NAME:
Salem #1 DURATION TYPE 1 (HOURS}
REASON 2 F
262.8 A
F 513.5 A
I 2
Reason:
A-Equillll8nt Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction MEI'HOD OF SHUITING OOWN REACIDR 4
3 E--Operator Training & Lic-ense Examination F-Admi.llistrati ve G--Operational Error (&'Plain)
H-Other (Ex-plain)
LICENSE EVENT SY STEN REFDRI' #
CODE 4 IB CH 3
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous outage 5-1.oad Reduction 9-0ther CD.'1PONENT CODE 5 INSTRU INSTRU DATE:
05-10-90 COMPLEI'ED BY: Art Orticelle TELEPHONE:
339-2122 CAUSE AND CORRECTIVE ACTION
'ID PREVENT RECURRENCE 1A S.E.C.
- 12 S.G. FEED PUMP 4
5 Exhibit G - Instrnctions Exhibit 1 - Same for Preparation of Data Source Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)
I I
MAJOR ~LANT MODIFICATIONS MdNTH: -
APRIL 1990
- DCR lEC-02245 1EC-02251A lSC-2092 PRINCIPAL SYSTEM Reactor Coolant Smoke Detection Residual Heat Removal
- Design Change Request DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 MAY 10, 1990 M. MORRONI (609) 339-2068 DESCRIPTION This design change replaced the 1/4 Reactor Coolant Pump (RCP} Breaker Open Anticipatory Trip signal above P-8 with a 2/4 RCP Breaker Open Anticipatory trip signal above P-7.
This design change installed additional smoke detection equipment to various zones of the Auxiliary Building.
This design change modified the control circuits for Valves RHl and RH2 to delete the auto closure interlock feature.
MiJ6R PLANT MODIFICATIONS MONTH: -
APRIL 1990 DOCKET NO:
UNIT NAME:
50-272 SALEM 1
- DCR lEC-02245 1EC-02251A lSC-2092 DATE:
COMPLETED BY:
TELEPHONE:
SAFETY EVALUATION 10 CFR 50.59 MAY 10, 1990 M. MORRONI (609) 339-2068 This design change replaced the 1/4 Reactor Coolant Pump (RCP) Breaker Open Anticipatory Trip signal above P-8 with a 2/4 RCP Breaker Open Anticipatory trip signal above P-7.
This design change reduces the potential for inadvertent Rx trips and challenges to the Reactor Protection System.
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 installed additional smoke detection equipment to various zones of the Auxiliary Building.
This provides additional coverage of equipment areas by the automatic detection system.
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 modified the control circuits for Valves RHl and RH2 to delete the auto closure interlock feature.
Elimination of this feature reduced the potential for inadvertant actuation of these valves and brought the system design in conformance with current requirements.
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
________ _J
S~F~TY RELATED MAINTENANCE MONTH: -
APRIL 1990 DOCKET NO:
UNIT NAME:
50-272 SALEM 1 WO NO 890804101 900104080 900309121 900321100 900402122 900419103 UNIT 1
1 1
1 1
DATE:
COMPLETED BY:
TELEPHONE:
MAY 10, 1990 M. MORRON!
(609) 339-2068 EQUIPMENT IDENTIFICATION 13 SERVICE WATER PUMP FAILURE DESCRIPTION:
REMOVE AND REPLACE WITH SPARE PUMP 12 SAFETY INJECTION PUMP FLOW ORIFICE FAILURE DESCRIPTION:
ORIFICE FLANGE LEAKING -
REPLACE GASKET 11SW127 FAILURE DESCRIPTION:
NO AUTO CONTROL -
TROUBLESHOOT 14 SWITCHGEAR FAILURE DESCRIPTION:
EXHAUST FAN STOP INDICATION DOES NOT LIGHT -
TROUBLESHOOT 15 CONTAINMENT FAN COIL UNIT FAILURE DESCRIPTION:
INDICATION PEGS AT LOW SPEED -
TROUBLESHOOT 1
- 1 MAIN TRANSFORMER FAILURE DESCRIPTION:
TROUBLESHOOT GEOMAGNETIC INDUCTION COUNTERS
I I
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 APRIL 1990 The Unit entered the period shutdown for repairs to lA Safeguards Equipment Cabinet (SEC).
Following repairs to the SEC, delays were encountered during heatup due to leakage from an Emergency Core Cooling System (ECCS) check valve.
The valve was reseated and the Unit was restored to approximately 91% power on April 7, 1990.
The Unit continued to operate at that level until April 9, 1990, when the reactor tripped following separation of the linkage on 12 Steam Generator Feed Pump which resulted in a low water level in 12 Steam Generator.
The Unit remained shutdown through the rest of the period for ECCS full flow testing and correction of identified concerns.
R~FUELING INFORMATION MONTH: -
APRIL 1990 MONTH APRIL 1990 DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO x
- 2.
Scheduled date for next refueling:
October 6, 1990 50-272 SALEM 1 MAY 10, 1990 M. MORRON!
(609) 339-2068
- 3.
Scheduled date for restart following refueling:
November 19, 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 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.
Number of Fuel Assemblies:
- a.
Incore 193
- b.
In Spent Fuel Storage 540
- 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:
September 2001 8-l-7.R4