ML18096B196
| ML18096B196 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/31/1992 |
| From: | Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9301220167 | |
| Download: ML18096B196 (10) | |
Text
PS~G*
'Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station January 14, 1993 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 December 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
?tk 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 9301220167 921231 PDR ADOCK 05000311 R
PDR r 11~ cn~r yy rt:uJ.m:~
8-1-7.R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-311 Unit Name:
Salem #2 Date:
1/11/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month DECEMBER 1992 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 1116 17 1125 2
1108 18 1123 3
1124 19 1119 4
1102 20 1130 5
1130 21 1106 6
1124 22 1007 7
1138 23 1056 8
1129 24 1068 9
1114 25 1068 10 1118 26 1015 11 1129 27 1097 12 1110 28 1095 13 1124 29 1116 14 1124 30 1127 15 1122 31 1127 16 1122 P. 8.1-7 Rl
P.. 8.1-7 Rl OPERATING DATA REPORT Docket No:
50-311 Date:
1/11/93 Completed by:
Mark Shedlock Telephone:
339-2122 Operating Status
- 1.
Unit Name Salem No. 2 Notes
- 2.
Reporting Period December 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.~~~N~A=-~~~~~~~~~~~~~~~~~~~~~~~
- 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)
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 744 744 0
744 0
2506929.6 856180 823502 100 100 100.1 99.3 0
Year to Date Cumulative 8784 98353 5149.5 63765.6 0
0 4659.7 61558.5 0
0 14983968.0 145095689.8 4980440 64707488 4717691 61585976 53.0 62.6 53.0 62.6 48.6 56.1 48.2 56.2 16.8
- 24. Shutdowns scheduled over next 6. months (type, date and duration of each)
Refueling outage scheduled to start 3-27-93 and last 55 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA
NO.
DATE 1
2 F:
Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH DECEMBER 1992 DURATION TYPE1 (HOURS)
REASON2 Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing 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 REPORT #
Method:
1-Manual 2-Manual Scram SYSTEM CODE4 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
DOCKET NO.: _,5""'0..,_-=31"""1'"'=" __
UNIT NAME:
Salem #2 DATE:
01/11/93 COMPLETED BY:
Mark Shedlock TELEPHONE:
339-2122 COMPONENT CAUSE AND CORRECTIVE ACTION CODE5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161)
TO PREVENT RECURRENCE 5
Exhibit 1 - Same Source
SAFETY RELATED MAINTEN,CE MONTH: -
DECEMBER 1992 DOCKE~O:
UNIT NAME:
50-311
~ SALEM 2 WO NO UNIT DATE:
COMPLETED BY:
TELEPHONE:
JANUARY 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION 910405080 2
920811102 2
RADIATION MONITOR 2R41A FAILURE DESCRIPTION:
REPLACE FLOW ALARM BISTABLE VALVE 22SW25 FAILURE DESCRIPTION:
VALVE 26SW25 NOT FULLY CLOSING -
REPAIR
10CFR50.59 EVALUATIONS~
MONTH: -
DECEMBER 1992 DOCKE~O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 JANUARY 10, 1993 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 A.
Design Change Packages 2EC-3131 Pkg. 1 2EC-3130 Pkg. 1
SUMMARY
"No. 22 Component Cooling Heat Exchanger Pipe" -
This design change involves the replacement of 20 11 Pipe with 6% Moly austenitic stainless steel 20 11 pipe from the Inlet valve 22SW21 up to the existing 6% moly boundary at inlet spool 2-SW-P-146, and replacement of flow element F3890.
Electrical/I&C modifications associated with this package consist of disconnection, reconnection, and testing of the following equipment and instrumentation required to facilitate the piping replacement:
This DCP also includes rotation of the flow measurement taps for flow element F3890 up to a 45 degree angle to help mitigate the affect of silt blockage on these instrument lines.
A 2 11 drain valve is being added to the return side piping to complete the drainage segregation capability of the 22 CCHX area.
The modifications do not affect the ability of the Service Water System to perform its intended safety function.
There is no reduction in the margin of safety as defined in the basis of the Technical Specifications.
(SORC 92-121)
"Replacement of Various Steel in SW Piping in Salem Unit #2 SW Intake Bay #4" -
The purpose of this design change is to replace various sections of existing carbon steel, stainless steel and aluminum-bronze Service Water (SW) piping in the Salem Unit #2 SW Intake Bay #4.
The replacement pipe material is a 6% Molybdenum Austenitic Stainless Steel.
The temporary conditions associated with the installation of this modification do not impact the ability of the Service Water System to perform its intended safety function.
The permanent configuration does not affect the emergency operation of the
10CFR50.59 EVALUATIONS~
MONTH: -
DECEMBER 1992 (cont'd)
ITEM 2EC-3128 Pkg. 1 2EC-3177 Pkg. 1 2EA-1028 Pkg. 1 DOCKE~O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-311 SALEM 2 JANUARY 10, 1993 J. FEST (609)339-2904 Service Water System.
The system will function in the same manner as it did prior to this modification since this is a material change and the configuration changes are minor.
The proposed modifications do not reduce the margin of safety as defined in the bases of the Technical Specifications.
(SORC 92-122)
"Nuclear Header Crossover Unit 2 11 The purpose of this design change is to upgrade Service Water Piping, eliminate overpressurization line in the SW valve rooms (delete the SW49 and SW305 valves and ancillary devices), establish set points for 2SW308 and 2SW311 at 130 PSIG, provide a means to achieve a minimum 7500 GPM flow single SW pump operations by installing a pump bypass, and eliminate the SW79 check valve in the SW valve room.
Penetration seals are included in the design change.
The interim and test conditions will be in full compliance with the Technical Specifications.
Those portions required for operation by the Technical Specifications will have normal valve line up and configuration.
There are no safety limits
~
associated with this change.
This change does not reduce the margin of safety as defined in the bases of the Technical Specifications.
(SORC 92-122)
"RVLIS Refueling" -
The purpose of this design change is to rescale the RVLIS level transmitter and correct program valves for proper refueling mode RVLIS operation.
This change also modifies the head vent sensor isolation valve to drain the sensor for refueling mode.
The proposed change makes no alteration to the margin of safety as defined in the bases for the Technical Specifications.
(SORC 92-122)
"Counting and Calibration Room Floor Drains" -
The floor drains in the counting and calibration rooms on Elevation 100 1 of the No. 2 Unit Auxiliary Building are covered and sealed by an
e 10CFR50.59 EVALUATIONS MONTH: -
DECEMBER 1992 (cont'd)
DOCKE"O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-311 SALEM 2 JANUARY 10, 1993 J. FEST (609)339-2904 ITEM
SUMMARY
epoxy resin floor which has been installed in the lab.
The floor drain grates were taped over so that the self-leveling floor could be poured over the existing lab floor.
Thus, the floor drains have been permanently plugged.
The Counting and Calibration Room and floor drain system are not discussed in the Technical Specifications.
The proposed changes will not reduce the margin of safety as defined in the bases for the Technical Specifications.
{SORC 92-127)
B.
Procedures and Revisions S2.0P-SO.CVC-0006(Q)
"Boron Concentration Control" -
The purpose of this change is as follows: 1.)0perate the eves Makeup Control system in automatic, manual,
'dilute, borate and alternate dilute modes; 2.)
Use the eves Makeup Control System to makeup to the RWST or eves Holdup Tank; 3.) use the Demineralized Water System as a source of primary Grade water for RCS makeup when the Primary Water Storage Tank is not available.
Reg. Guide 1.33 requires there be procedures for operation of the Chemical and Volume Control System.
Therefore, this is a procedure described in the SAR.
The changes in this revision were made in accordance with NC.NA-AP.ZZ-0032{Q) and include the following:
1.) Reduction of minimum required RHR flow to 1000 gpm in accordance with Tech Spec 3.9.8.1; 2.) Deletion of instructions for filling the RWST of CVCS Holdup Tanks from the Deroin Water System; 3.) Addition of instruction which alters the alternate dilution method for more rapid dilution.
Operability of the systems/components as defined in the Technical Specifications is not affected.
Therefore, the margin of safety as defined in the bases of the Technical Specifications is not reduced.
{SORC 92-121)
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 2 DECEMBER 1992 SALEM UNIT NO. 2 The Unit began the period operating at full power.
On December 13, 1992, operators discovered that the overhead annunciation system was locked up.
The operators took the appropriate action and reset the system within three minutes of discovery.
On December 14, 1992, and NRC Augmented Inspection Team arrived to investigate the event.
A SERT was also established to independently assess the event.
On December 21, 1992, a power reduction to 80% commenced in order-to repair the bellmouth of 23 circulating pump.
22B circulator was also taken out of service to clean the waterbox.
The Unit was returned to 100% power on December 24, 1992.
Power was reduced to 82% on December 26, 1992, due to debris problems at the circulating pump screens.
The Unit returned to 100% power on December 26, 1992, and continued to operate at full power throughout the remainder of the period.
- EF~E~ING INFORMATION ~
MONTH: -
DECEMBER 1992 MONTH DECEMBER 1992 DOCKE~O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES X
NO
- 2.
Scheduled date for next refueling:
MARCH 27, 1993 50-311 SALEM 2 JANUARY 10, 1993 J. FEST (609)339-2904
- 3.
Scheduled date for restart following refueling:
JUNE 3, 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