ML18096B339
| ML18096B339 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/28/1993 |
| From: | Fest J, Polizzi V, Shedlock M Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9303170219 | |
| Download: ML18096B339 (9) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station March 12, 1993 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 February 1993 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 Sincerely yours,
~Wo-&o~
~eneral Manager -
0 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 Pe.ople
-9303i70219 930220-- ----- -~8000
- 1)
PDR ADOCK 05000272
~
R PDR
{Wf ',
95-2189 (10M) 12-89
8-1-7*~ R2 AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-272 Unit Name:
Salem #1 Date:
3/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month February 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 1078 17 0
2 1121 18 0
3 1071 19 0
4 1113 20 0
5 1107 21 0
6 1101 22 0
7 1110 23 283 8
1109 24 854 9
1114 25 972 10 1121 26 981 11 1119 27 1003 12 1105 28 1089 13 1102 29 14 1120 30 15 1121 31 16 757
OPERATING DATA REPORT Docket No:
Date:
Completed by:
Mark Shedlock Telephone:
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period February 1993 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)
Report, Give Reason NA 2
- 9.
Power Level to Which Restricted, if any (Net MWe)
- 10. Reasons for Restrictions, if any
- 12. 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 NA This Month Year to Date 672 1416 555.79 1159.91 0
0 514.25 1074.35 0
0 1684833.6 3456124.8 564680 1162710 536143 1103276 76.5 75.9 76.5 75.9 72.1 70.4
- 71. 6 69.9 23.4 24.1 50-272 03/10/93 339-2122 since Last N/A Cumulative 137353 90341.89 0
87214.76 0
275654733.2 91535700 87174935 63.5 63.5 50.4 56.9
- 21. 5
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NA
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA
NO.
DATE 0014 02/03/93 0015 02/16/93 0017 02/24/93 0018 02/24/93 0020 02/25/93 0019 02/25/93 0021 02/26/93 2
F:
Forced S:
Scheduled DURATION TYPE' (HOURS)
REASON2 F
2.68 B
F 157.75 H
F 3.42 B
F 16.00 B
F
- 17. 72 B
F 7.38 A
F 34.62 A
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH FEBRUARY 1993 METHOD OF SHUTTING DOWN REACTOR 5
3 5
5 5
5 5
3 LICENSE EVENT REPORT #
Method:
1-Manual 2-Manual Scram SYSTEM CODE 4
cc IA HA HB HF HF HF 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 GENERA INSTRU VAL VEX zzzzzz PUMP XX PUMP XX PUMPXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-311 Salem #1' 03/10/93 Mark *Shedlock 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE NUCLEAR STM GEN. CONTROLS NUCLEAR AFD SPIKES INTERCEPT VALVES TURBINE MAIN STM ISOLATION TEST STM UNITS THERMAL DISCHARGE LIMITS ENVIRONM.
CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161)
Exhibit 1 - Same Source
e SAFETY RELATED MAINTENANCE DOCKE,NO:
50-272 SALEM 1 MONTH: -
FEBRUARY 1993 UNIT NAME:
WO NO UNIT 920707099 1
930219067 1
930225180 1
930314022 1
DATE:
COMPLETED BY:
TELEPHONE:
MARCH 10, 1993 J. FEST (609)339-2904 EQUIPMENT IDENTIFICATION lC D/G CHART RECORDER FAILURE DESCRIPTION:
RECORDER DOES NOT AGREE WITH SPDS TROUBLESHOOT AFD MONITOR FAILURE DESCRIPTION:
MONITOR RECORDER SPIKING -
INVESTIGATE RADIATION MONITOR 1R44A FAILURE DESCRIPTION:
HIGH RANGE MONITOR FAILED -
INVESTIGATE HYDROGEN ANALYZER FAILURE DESCRIPTION:
12 CAN HYDROGEN ANALYZER LEAK -
CHECK KIP SOLENOID
10CFR50. 59 EVALUATION' MONTH: -
FEBRUARY 1993
~
DOCK.NO:
UNIT NAME:
DATE:
COMPLETED BY:
T:ELEPHONE:
50-272 SALEM 1 MARCH 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
SUMMARY
A.
Design Change Packages (DCPs) lEC-3216 Pkg. 1 lEA-1033 Pkg. 1 "Replacement of Boric Acid Instrumentation" -
The following changes apply to both units unless otherwise stated: a.) Install new pressure indication filled system at the BAT pumps discharge and BA filter inlet to replace existing installation; also at the Unit 2 BA filter discharge; b.) Install new assemblies as above at the BAT pumps suction.
The addition and rework of the instrumentation does not affect the ability of the Bo~on Injection system to perform its intended function since they are being used for indication only.
Therefore, the margin of safety is not compromised.
(SORC 93-012)
"Unit #1 RCP Motor Bearing Temperature Alarm Setpoint Changes" -
Supplement No. 3 to the Safety Evaluation Report, NUREG-0517, approved lowering the RCP bearing temperature alarm to 175 F on Salem Unit #2 (also applicable to Unit #1).
In the presence of a loss of component cooling water flow alarm, the RCP motor bearing temperature alarm will signal the operator to immediately execute the pump trip procedure.
While reviewing station documents against NUREG-0517, System Engineering discovered drawings that were not in agreement with the NUREG; the drawings showed the RCP motor bearing temperature alarms as being 185 F instead of 175 F.
This change proposal will update drawings to agree with as-built conditions that are consistent with NUREG-0517.
This change will not reduce the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-015)
10CFR50.59 EVALUATION' MONTH: -
FEBRUARY 1993 (cont'd)
ITEM DOCKE,NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 MARCH 10, 1993 J. FEST (609)339-2904 B.
Temporary Modification Requests T-Mod #
93-018
- c.
SAR Change Notice SAR CN # 91-26 1111 & 12 BASTs Cross Connect" - This T-Mod will cross connect 11 BAST and 22 BAST allowing the transfer of borated water from 22 BAST to 11 BAST, utilizing 22 BAT pump.
This will support the additional BAST volume needed.
The cross connect, located at the discharge of 22 BAT pump and.the inlet to 11 BAST, will use a 3/4 11 stainless steel flexible hose and pipe as a tie-in at valves 11 &
22CV158.
The T-Mod will be isolated when both sample valves are closed.
The temporary pipe will be heat traced and insulated to prevent boron from crystallizing.
At all times for both Units the limiting condition for operation will be satisfied per Technical Specification Requirements.
The Technical Specification design basis assumption will not be altered, therefore there is no reduction in the margin of safety.
(SORC 93-012)
"Diesel Start Motor Air System" -
The purpose of this change is to simply change UFSAR Section 9.5.6 to reflect as-built configuration of the diesel generator start motor air system.
Open Item 8 (DES-90-01378) of the Salem Emergency Diesel-Generator System CBD (Ref. 1) states that the required piping and valves to connect the four starting air motors to a common header are not available.
The purpose of this Engineering Evaluation is to evaluate the installed configuration of the starting air piping between the four starting air motors and the air receiver tanks.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-012)
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 FEBRUARY 1993 The Unit began the period operating at full power and continued to operate at essentially full power until February 16, 1993, when the Reactor tripped during calibration of an OT Delta T channel.
On February 21, 1993, during the trip recovery, following completion of repairs, a condenser tube leak developed.
Also on February 21, 1993, a partial loss of offsite power occurred during a test of the Unit 3 gas turbine.
On February 23, 1993, the Unit was synchronized and a power escalation commenced.
Power was briefly held at 65% to repair a turbine intercept valve.
Power was then raised to 85% where it was held for axial flux difference control and to allow stabilization of containment airborne.
The Unit achieved full power on February 27, 1993, and continued to operate at full power throughout the remainder of the period.
e
- 'REFUELING INFORMATION DOCKE,NO:
~ONTH: -
FEBRUARY 1993 UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
MONTH FEBRUARY 1993
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
OCTOBER 2. 1993 50-272 SALEM 1 MARCH 10, 1993 J. FEST (609)339-2904
- 3.
Scheduled date for restart following refueling:
DECEMBER 13, 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?:
- 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 656
- 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 8-1-7.R4