ML18094A577
| ML18094A577 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1989 |
| From: | Miller L, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8907200308 | |
| Download: ML18094A577 (10) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 July 12, 1989 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 1989 are being sent to you.
RH:sl Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Since~ely yours,
_;¢UJg<t, L. K. Miller General Manager -
Salem Operations cc:
Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures 8-l-7.R4 The Energy People 95-2189 (SM) 12-88
e e
AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name
~S-a~l-e_m_,,.#~1------~
Date 7-10-89 Completed by Art Orticelle Telephone 609-935-6000 Extension 4451 Month JUNE 1989 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 0
17 0
2 0
18 23 3
0 19 111 4
0 20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 181 13 0
29 466 14 0
30 777 15 0
16 0
P. 8.1-7 Rl
C1PERAT::";:NG DATA REPORT Completed by Pell White Operating Status Docket No.50-272 Date:
7~71~0~-~8~9,,.-~~~~
Telephone: 935-6000 Extension: 4451
~~~~~~~~~
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period June 1989
- 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.
It 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. Reactor 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 Generated (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 22 2. 9 0
88.01 0
146042.4 41090 18625 12.2 12.2 2.3 2.3 71.1 Year to Date 4343 20 85. 23 0
1899.76 0
6252890.4 2080290 1959998 43.7 43.7 40.8 40.5 19.8 Cumulative 105216 66717.43 0
64535. 66 0
201689682.8 67027470 63766113
- 61. 3
- 61. 3 54.8 54.4 22.3
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NONE
- 25. If shutdown at end of Report Period, Estimated Date or Startup:
N/A 8-l-7.R2
Completed by No.
Date 0072 6-01-89 0074 6-18-89 0075 6-18-89 0073 6-19-89 0076 6-19-89 0077 6-28-89 1
F: Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH JUNE 1989 Unit Name Salem No.1 Art Orticelle Method of Duration Shutting License Type Hours Reason Down Event 1
s s
F F
F s
2 Reactor 413.58 F
4
- 1. 97 B
4
- 15. 12 A
1 0
A 4
20 1. 33 A
2 0
B 9
2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction Report E-Operator Training & Licensing Exam F -Adm in i s t r a t iv e G-Operational Error-explain H-Other-explain Date 7-10-89 Telephone 609-935-6000 Extension 44 51 System Component Code 4 Code 5 zz zzzzzz HA TURBIN SH INSTRU SH INSTRU HE VAL VEX RB INSTRU 3 Method I-Manual 2-Manual Ser am.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther Cause and Corrective Action to Prevent Recurrence SCHEDULED OUTAGE EXTENSION TURBINE OVERS PEED TRIP TEST e
TSAS lA SEC INOPERABLE TSAS lA SEC INOPERABLE MS 167 VALVES REACTIVITY TESTING FLUX MAPPING 4 Exhibit G Instructions for Prepara-tion of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit 1 Salem as Source
WO NO 870601209 880517119 880830093 881011128 890520096 890606175 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
15 S.W.PUMP INSP.
FAILURE DESCRIPTION:
PULL 15 SERVICE WTR. PUMP AND INSTALL REBUILT PUMP lAW M6L-2.
1 lFITlll PRI WTR FLOW XMTR FAILURE DESCRIPTION:
lFITlll PRI WTR FLOW XMTR/MISMATCH W/P250/
TROUBLESHOOT.
1 100' AIRLOCK FAILURE DESCRIPTION:
100' AIRLOCK/HIGH LEAK RATE/REPACK DOOR SHAFTS.
1 1FA3407 FAILURE DESCRIPTION:
1FA3407 12 S/G STM FLOW IND/SPIKING DOWN/CORRECT.
1 RING DUCT FAILURE DESCRIPTION:
RING DUCT/ 3" RIP IN EXPANSION JOINT.
REPLACE IAW A.R.
1 1N32-SOURCE RANGE-CLIMBING.- REPAIR FAILURE DESCRIPTION:
1N32 -
WHILE PERFORMING ROD DROPS, 1N32 STARTED CLIMBING.
WO NO 890610083 890617053 890617063 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
"B" RX TRIP BKR SHUNT COIL FAILURE DESCRIPTION:
"B" RX TRIP BKR SHUNT COIL/DID NOT REGISTER ON P250 COMPUTER.
1 12BF4 0 FAILURE DESCRIPTION:
SEEMS TO BE LEAKING BY.
PLEASE TROUBLE SHOOT AND REPAIR.
1 1-A S.E.C FAILURE DESCRIPTION:
1-A S.E.C FALIED TEST/TROUBLESHOOT & REPAIR.
FAILED WHILE DOING THE M3T PROCEDURE.
e
. MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1989
- DCR NO.
PRINCIPAL SYSTEM lEC-02163 Caustic Control lSM-00231 Waste Collection
- DCR - Design Change Request e
DOCKET NO.:
50-272 UNIT NAME:
Salem 1 DATE:
July 10, 1989 COMPLETED BY:
P. White TELEPHONE:
609/339-4455 DESCRIPTION This design change added secondary containment facilities at the caustic loading area as required by NJAC 7:1E-4.7.
This design change installed a new waste line connecting the Waste Collector Tank and the High Conductivity Pit.
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. MAJOR PLANT MODIFICATIONS REPORT MONTH JUNE 1989 DOCKET NO.:
UNIT NAME:
50- 27 2 Salem 1
- DCR lEC-02163 lSM-00231 DATE:
July 10, 19 89 COMPLETED BY:
P. White TELEPHONE:
609/339-4455 SAFETY EVALUATION 10 CFR 50.59 This design change installed secondary containment facilities at the NRLWDS caustic loading area to prevent spilled hazardous substances from reaching the waters of the State.
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 a new, properly sized waste line connecting the Waste Collector Tank and
.the High Conductivity Pit.
This improves the operation of the system and reduces the possibility of spilling waste material.
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
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 JUNE 1989 The Unit began the period shutdown for a refueling outage.
Major work accomplished during the period included the following:
- 1.
Steam Generator and Feed Pump turbine overspeea tests;
- 2.
RTD cross calibrations;
- 3.
Establishing condenser vacuum,
- 4.
Individual Rod Position Indication (IRPI) calibrations
- 5.
Testing of all safety valves
- 6.
Main Turbine Overspeed Test On June 9, 1989, an automatic safety injection occurred as a result of the premature opening of a main steam safety valve.
A startup was commenced on June 14, 1989, and the Unit was synchronized on June 18, 1989, following completion of repairs to a main steam isolation valve and feedwater regulating valves.
Subsequently, the Unit was shutdown due to problems encountered with lA SEC.
The Unit was resynchronized on June 19, 1989, and a power escalation commenced.
The Unit tripped later, the same day, while Operators were performing a surveillance test on the main steam isolation valves.
The test circuitry was subsequently modified to prevent possible trips during future surveillance testing.
A Safety Injection check valve bonnet leak was identified in the Containment and a cooldown and depressurization was performed to effect repairs.
Following repairs to the check valve, technicians discovered the presence of sodium in the Reactor Coolant System during routine chemistry sampling.
Investigations revealed that improper boric acid had been inadvertently used in the batching process and subsequently injected into the system.
A thorough analysis of the event demonstrated that there were no adverse affects to the primary system.
The sodium was subsequently removed from the system by use of demineralizers.
The Unit was returned to service on June 28, 1989, and a power ascension was performed throughout the remainder of the period.
REFUELING INFORMATION DOCKET NO.~
50-272 COMPLETED BY:
P. White UNIT NAME:
Salem 1 DATE:
July 10, 1989 TELEPHONE:
609/935-6000 EXTENSION:
44 97 Month JUNE 1989
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
March 28, 1989
- 3.
Scheduled date for restart following refueling: May 24, 1989
- 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 X
NO 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.
- 8.
- 9.
NONE Number ot Fuel Assemblies:
A)
Inc ore B)
In Spent Fuel Storage Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
8-1-7.R4 193 540 1170 1170 September 2001