ML18096A831
| ML18096A831 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1992 |
| From: | Fest J, Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9207200215 | |
| Download: ML18096A831 (10) | |
Text
PSIOCie Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 14, 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 June 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 cc:
Mr. Thomas T. Martin Regional Adminis,trator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 The Energy People 92-072002 920630 PDR ADOCK 05000311 R
~ERAGE DAILY UNIT POWER L~
Completed by:
Mark Shedlock Month June 1992 Day Average Daily Power Level (MWe-NET) 1 435 2
507 3
940 4
774 5
1078 6
1106 7
1110 8
1064 9
1059 10 863 11 1103 12 1095 13 1007 14 1003 15 1113 16 1086 P. 8.1-7 R1 Day Docket No.:
50-311 Unit Name:
Salem #2 Date:
07/10/92 Telephone:
339-2122 Average Daily Power Level (MWe-NET) 17 1095 18 813 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 e Docket No:
50-311 Date:
07/10/92 Completed by:
Mark Shedlock Telephone:
339-2122 Operating status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period June 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 720 429.8 0
429.7 0
1306413.6 433460 409726 59.7 59.7 51.5
- 51. 0 40.3 Year to Date 4367 1161.8 0
822.0 0
2276719.2 709490 631411 18.8 18.8 13.1 13.0 30.6 Cumulative 93936 59777.9 0
57720.7 0
132388441. 0 60436538 57499696.
61.4 61.4 55.3 54.9 23.4
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
We are presently in a forced maintenance outage.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
July 21. 1992 8-l-7.R2
NO.
DATE 0006 05/30/92 0007 06/02/92 0009 06/03/92 0010 06/04/92 0011 06/09/92 0013 06/13/92 0014 06/18/92 1
2 F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON 2 F
70.9 F
6.9 F
12.9 F
17.7 F
15.0 F
5.0 F
290.3 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction A
B B
A B
B B
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JUNE 1992 METHOD OF SHUTTING DOWN REACTOR 5
5 5
5 5
5 1
3 LICENSE EVENT REPORT #
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 HH HH HH HH HH HF CH E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE5 INSTRU PUMPXX PUMPXX INSTRU PUMPXX HTEXCH PIPEXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #2 07/10/92 Mark*Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE
- 21 & #22 S.G. FEED PUMP OIL PROBLEMS
- 21 CONDENSATE PUMP SEAL REPAIR
- 22 CONDENSATE PUMP SEAL REPAIR
- 21 S.G.FEED PUMP OIL LEAK
- 21 CONDENSATE PUMP MAINTENANCE
- 23A & #23B WATERBOX CLEANING STEAM GEN. PIPING REPAIRS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)
Exhibit 1 - Same Source I
el
S~F~Ti RELATED MAINTENANCE DOCKET NO:
50-311 SALEM 2 MONTH: -
JUNE 1992 WO NO UNIT UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1992 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION 920303074 2
920527073 2
920607079 2
920607080 2
920609142 2
2B VITAL INSTRUMENT BUS FAILURE DESCRIPTION:
2B VITAL INSTRUMENT BUS LOW FLOW ALARM -
INVESTIGATE.
FT113 HEAT TRACE FAILURE DESCRIPTION:
2B RMS UPS INVERTER FT113 HEAT TRACE NOT MAINTAINING TEMPERATURE >1450F -
INVESTIGATE FAILURE DESCRIPTION:
INVESTIGATE NON-LATCH TRANSFER OF 2B RMS UPS INVERTER VALVE 22GB4 FAILURE DESCRIPTION:
BLOWDOWN ISOLATION WILL NOT FULLY OPEN -
INVESTIGATE 21 LOOP Tavg CHANNEL FAILURE DESCRIPTION:
21 LOOP Tavg CHANNEL FAILURE -
TROUBLESHOOT 920612140 2
920625194 2
21 EMERGENCY LIGHTING INVERTER FAILURE DESCRIPTION:
THE BREAKER FOR 21 EMERGENCY LIGHTING INVERTER BACKUP FEED TRIPPED -
INVESTIGATE VALVE 2SS33 FAILURE DESCRIPTION:
VALVE 2SS33 SHOWS OPEN & CLOSED INDICATION -
INVESTIGATE
10CFR5'0. 59 EVALUATIONS
- MONTH: -
JUNE 1992 DOCKET':
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 JULY 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
A.
Design Change Packages {DCP)
DCP# 2EC-3142 Pkg. 1 DCP# 2EC-3105 Pkg. 1 "Upgrading Power Supply to 230V Generator Control Center" - This change will upgrade Salem Generating station, Unit 2, Generator Control Center's regular and emergency power supply breakers and associated cables so that it can supply its connected loads without interruption.
This modification does not affect any system design philosophy or criteria for the plant auxiliary AC power* distribution system.
The new circuit breakers have similar characteristics compared to the original breakers and are of higher capacity.
As such, these components will perform their intended functions with improved reliability.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
{SORC 92-065)
"Radwaste Panel Upgrade" - This DCP will provide for revitalization upgrades to Rad Waste Panel 104 and related equipment on elevations 84 1 and 64 1 of the Auxiliary Building.
The upgrades will consist of the following: a) replacement of the obsolete instrumentation, b) physical repair of Panel 104, c) provision of new labels to enhance operator interface with this panel, d) removal of unused components, including associated components external to the panel, e) upgrade of panel wire, cable restraints and labels, and f) functional verification of all panel instruments and components.
Replacement of certain components used to monitor the administratively controlled transfer and release of radiological liquids and gasses will not affect the limiting conditions or safety margins as described in the Technical Specifications.
{SORC 92-065)
r---------------------------------~---o-c~=----~-----
l'OCF~5*o. 59 EVALUATIONS.
_MONTH: -
JUNE 1992 (cont'd)
DOCKET':
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 JULY 10, 1992 J. FEST (609)339-2904 ITEM
SUMMARY
B.
Procedures and Revisions S2.0P-PT.SW-0026(Q)
S2.0P-PT.SW-Ob27(Q)
- 21 Component Cooling Water Heat Exchanger Temperature Monitoring" - This procedure is written to obtain operating data (temperature, pressure and flow) for the #21 Component Cooling Water Heat Exchanger.
This data will be used to determine the thermal efficiency of #21 CCW Heat Exchange as required by NRC Generic Letter 89-13.
In order to evaluate the thermal efficiency of the heat exchanger, the flow rates, the inlet and outlet temperatures of the service water and the component cooling water will be measured.
Component cooling temperature will be measured by removing the existing temperature detectors at the inlet and outlet of
- 21 CCW Heat Exchanger and installing temporary more accurate instruments.
This will disable the high ccw inlet temperature alarm, ccw outlet temperature indication in the c0ntr0i room and the temperature control mode of operation for the ccw system.
Additional temporary instrumentation will be installed when the flow control mode is used.
All temporary instruments will be removed at the completion of this test and the permanent instruments that were removed will be reinstalled.
Format and Human Factors are IAW the Implementing Procedure Writer's Guide.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
"#22 Component Cooling Water Heat Exchanger Temperature Monitoring" - This is a new procedure produced by the Procedure Upgrade Project.
This procedure is written to obtain operating data (temperature, pressure and flow) for #22 Component Cooling Water Heat Exchanger.
This data will be used to determine the thermal efficiency of #22 ccw Heat Exchange as required by the NRC Generic Letter 89-13.
In order to evaluate the thermal efficiency of the heat exchanger, the flow rates, the inlet and outlet temperatures of the service water and the component cooling water will be measured.
b 1 C~R50.59 EVALUATIONS
,MONTH: -
JUNE 1992 (cont'd)
ITEM DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 JULY 10, 1992 J. FEST (609)339-2904
~-------------------
Component cooling temperature will be measured by removing the existing temperature detectors at the inlet and outlet of #22 ccw Heat Exchanger and installing temporary more accurate instruments.
This will disable the high CCW inlet temperature alarm of operation for the CCW system.
Additional temporary instrumentation will be installed to facilitate data gathering.
Data collection will be done during a normal plant cooldown when the flow control mode is used.
All temporary instruments will be removed at the completion of this test and the permanent instruments that were removed will be reinstalled.
Format and Human Factors are IAW the Implementing Procedure Writer's Guide.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 92-067)
SALEM UNIT NO. 2 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 JUNE 1992 The Unit began the period operating at 47% power. Power ascension was commenced on June 2, 1992, and the Unit achieved full power on June 3, 1992, following completion of repairs to #21 Condensate Pump seal.
Later, the same day, power was reduced for repairs to #22 Condensate Pump seal.
On June 4, 1992, following completion of the repairs, the Unit was restored to full power.
Later, the same day, power was reduced due to an oil leak on #21 steam Generator Feedwater Pump Governor.
The leak was repaired and the Unit was restored to full power on June 5, 1992.
On June 9, 1992, power was reduced to repair a motor cooler leak on #21 Condensate Pump Motor Cooler.
On June 10, 1992, following completion of repairs, the Unit was restored to full power.
With the exception of a minor load reduction on June 13, 1992, for condenser waterbox cleaning, the Unit continued to operate at full power until June 18, 1992.
On June 18, 1992, the Unit was taken off line to test feedwater piping wall thickness due to erosion/corrosion concerns identified on Unit 1.
The Unit remained shutdown throughout the rest of the period.
RBFUELING INFORMATION
.MONTH: -
JUNE 1992 MONTH JUNE 1992 DOCKET':
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 JULY 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