ML18096B104
| ML18096B104 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1992 |
| From: | Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9211240047 | |
| Download: ML18096B104 (9) | |
Text
====---,,-,--===---------------------~
PS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 13, 1992 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 October 1992 are being sent to you.
RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information
?);;;i_
General Manager -
Salem Operations cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People 9211240047 921031 PDR ADOCK 05000311 R
PDR Ou*-*n2 iv_
95-2189 (10M) 12-89
.,ERAGE DAILY UNIT POWER L:i9r.
Completed by:
Mark Shedlock Month October 1992 Day Average Daily Power Level (MWe-NET) 1 1090 2
1090 3
1034 4
1084 5
1031 6
1107 7
1111 8
1122 9
1122 10 1116 11 1115 12 1115 13 1110 14 1117 15 1112 16 1120 P. 8.1-7 Rl Day Docket No.:
50-311 Unit Name:
Salem #2 Date:
11/10/92 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 1120 18 1112 19 1085 20 1110 21 1122 22 1120 23 1120 24 1116 25 1116 26 1116 27 1128 28 1093 29 1124 30 1118 31 1118
==---------
OPERATING DATA REPORT.
Docket No:
50-311 Date:
11/10/92 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period October 1992
- 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 NA
- 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. Rx. 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 Gen. (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 745 745 0
745 0
2522004.0 857540 824583 100 100 100.1 99.3 0
Year to Date Cumulative 7320 96889 3685.5 62301. 6 0
0 3256.8 60155.6 0
0 10311556.8 140423278.6 3393510 63120558 3194826 60063111 44.5 62.1 44.5 62.1 39.5 56.1 39.1 55.6 21.3 23.2
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling outage scheduled to start 03/29/93 and last 55 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA 8-1-7.R2
NO.
DATE 1
2 F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH OCTOBER 1992 DURATION TYPE 1 (HOURS)
REASON 2 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refueling D-Requlatory Restriction METHOD OF SHUTTING DOWN REACTOR E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain) 3 LICENSE EVENT SYSTEM REPORT #
CODE4 Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #2 11/10/92 Mark*shedlock 339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE6 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)
TO PREVENT RECURRENCE 5
Exhibit 1 - Same Source
- SAFETY* RELATED MAINTENANCE DOCKET'°:
MONTH: -
OCTOBER 1992 UNIT NAME:
50-311 SALEM 2 WO NO UNIT 881103132 2
921029089 2
DATE:
COMPLETED BY:
TELEPHONE:
NOVEMBER 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION RADIATION MONITORING FAILURE DESCRIPTION:
ENCLOSURE SUPPLY WILL NOT STAY OPEN -
INVESTIGATE.
21 SERVICE WATER ROOM COOLER FAILURE DESCRIPTION:
ROOM COOLER INLET VALVE PANEL VALVE AIR LEAK -
REPAIR
.10CFR50.59 EVALUATIONS.
DOCKET-0:
MQNTH: -
OCTOBER 1992 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 NOVEMBER 10, 1992 J. FEST (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed and concurs with these evaluations.
ITEM 2EC-3098 Pkg. 1 2SC-2267 Pkg. 3
SUMMARY
"Rosemount Transmitter Upgrade" -
The purpose of this change is to: 1) Replace 30 Rosemount electronic pressure and differential pressure transmitters with equivalent Series H transmitters.
- 2) Upgrade 16 Rosemount electronics transmitters to Type "R" output.
- 3)
Install new electrical quick-disconnects at the transmitters.
- 4) Modify tubing at the transmitters for proper arrangement of valving.
There is no change to instrument process variable spans.
The new or modified transmitters are equal to or better than the previous instruments under all conditions.
There is no impact on the margin of safety as defined in the basis for any Technical Specification.
{SORC 92-108)
"SEC Circuit - Service Water Pump Start Test switch Installation" -
The purpose of this change is to provide a Key Lock Test switch in service water pump breaker cubicle 2B8D for 24 primary service water pump, located in the 4KV Vital Bus Switchgear Room.
This switch will be placed in the test position during Full Flow Test Surveillance of the service water pumps in Bay 4, to ensure that two service water pumps aligned to the plant will start upon receipt of an SEC initiation signal during all SEC Mode Operation conditions, thus avoiding a situation in which only a single pump aligned to the plant is started.
The switch is not required when full flow testing is completed on the pumps located in Bay 2.
This proposal does not reduce the margin of safety as defined in the basis for any Technical SpeQif ication.
The only Technical Specification for the Service Water system states that "At least two independent service water loops shall be operable".
Since the installation of a key lock test switch to provide an added degree of personnel safety
---~-- -
. 1CiC~R50. 59 EVALUATIONS.
DOCKET,O:
MONTH: -
OCTOBER 1992 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 NOVEMBER 10, 1992 J. FEST (609)339-2904 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed and concurs with these evaluations.
ITEM
SUMMARY
during performance of existing test procedures does not affect the subject Technical Specification requirement, the margin of safety as defined in the basis for any Technical Specification is not reduced.
(SORC 92-110)
SALEM UNIT NO. 2 SALEM GENERATING STATION
- MONTHLY OPERATING
SUMMARY
UNIT 2 OCTOBER 1992 The Unit began the period operating at full power, and with the exception of a brief load reduction to support Hope Creek switching, continued to operate at full power throughout the remainder of the period.
REFUEL~NG INFORMATION MONTH: -
OCTOBER 1992 MONTH OCTOBER 1992 DOCKETttO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
MARCH 27, 1993 50-311 SALEM 2 NOVEMBER 10, 1992 J. FEST
{609)339-2904
- 3.
Scheduled date for restart following refueling:
MAY 21, 1993
- 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?: FEBRUARY 1993
- 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 408
- 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