ML18093B461
| ML18093B461 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1989 |
| From: | Orticelle A, White P Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8902270223 | |
| Download: ML18093B461 (10) | |
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AVERAGE DAILY UNIT POWER LEVEL Completed by Art Orticelle Month January 1989 Day Average Daily Power Level (MWe-NET) 1 1111 2
1117 3
1119 4
1059 5
1132 6
1131 7
1123 8
1051 9
1074 10 1135 11 1135 12 10 27 13 1097 14 1097 15 1101 16 1101 P. 8.1-7 Rl Day Docket No.
Unit Name Date Telephone Extension Average Daily (MWe-NET) 17 1093 18 1097 19 1104 20 936 21 1071 22 1095 23 1100 24 1098 25 1099 26 1059 27 1039 28 1044 29 1030 30 1064 31 1110 50* 272 Salem~T#-:-1~~~~
2 89 609-935-6000 4451 Power Level
e OPERATING DATA REPORT Docket No.50-272 Date:
2-10~-~8~9--~~~--
Completed by Pell White Telephone: 935-6000 Extension: ~4~4~5~1~~~~~~-
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period January 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)ll49
- 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
'-~----~~~--~--~~~~~------~-
This Month
- 11. Hours in Reporting Period 744
- 12. No. of Hrs. Reactor was Critical 744
- 13. Reactor Reserve Shutdown Hrs.
O
- 14. Hours Generator On-Line
--=7~4~4--~
- 15. Unit Reserve Shutdown Hours O
- 16. Gross Thermal Energy Generated -------
(MWH) 2503238
- 17. Gross Elec. Energy Generated (MWH) 840630
- 18. Net Elec. Energy Generated (MWH) 807583
- 19. Unit Service Factor 10 0 2 0. Unit Availability Factor 100
- 21. Unit Capacity Factor (using MDC Net) 98.1
- 22. Unit Capacity F~ctor (using DER Net)
- 97. 4 2 3. Unit Forced Outage Rate 0
Year to Date 744 74 4 0
744 0
2503238 840630 807583 100 100 98.1 97.4 0
Cumulative 101617 65376.2 0
63379.9 0
197940030 65787810 62613698 62.4 62.4 55.7 55.3 22.2
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling outage scheduled for April 9, 1989 and lasting approximately 55 da s.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A 8-l-7.R2
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY I989 Docket No.50-272
"'.::'"""""-:-~-=-----..,,------~
Unit Name Salem No.I Date 2-I0-89 Completed by Art Orticelle
~-=--=-::-=--,,.---~~
Telephone 609-935-6000 No.
Date 0003 I-04-89 0024 I-20-89 0052 I-2I-89 0039 I-26-89 004 I I-27-89 0044 I-28-89 0045 I-28-89 0048 I-29-89 0049 I-29-89 0050 I-30-89 I
F: Forced S: Scheduled Type I
F F
F F
F F
F F
F F
Duration Hours 4.0 3.3 2.0
.82 6.33
.98
.58
.67
- 1. 97 3.45 Reason 2
A B
B B
B B
B B
B B
Method of Shutting Down Reactor 5
5 5
5 5
5 5
5 5
5 License Event Report 89-00I-OO 2 Reason A-Equipment Failure-explain B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & Licensing Exam F-Administrative G-Operational Error-explain H-Other-explain Extension 445I System Code 4 SB IA IA HF HF HF HF HF HF HF 3 Method Component Code 5 HT EX CH CKTBRK CKTBRK FILTER zzzzzz zzzzzz zzzzzz FILTER FILTER FILTER
~~~~~~~~
Cause and Corrective Action to Prevent Returrence NUCLEAR CONTAINMENT SYSTEM PROBLEMS RX TRIP SYSTEM INCLUDING LOGIC RX TRIP SYSTEM INCLUDING LOGIC CIRCULATING WATER PUMPS CONDENSER INSPECTION LOSS OF VACUUM/
HIGH BACK PRESSURE LOSS OF VUCUUM/
HIGH BACK PRESSURE CIRCULATING WATER PUMPS CIRCULATING WATER PUMPS TRAVELING SCREENS/
HIGH BACK PRESSURE~
4 Exhibit G I-Manual Instructions 5 Exhibit I
.Salem as Source 2-Manual Scram.
for Prepara-3-Au.tomatic Scram. tion of Data 4-Continuation of Previous Outage 5-Load Reduction 9-0ther Entry Sheets for Licensee Event Report (LER) File (NUREG OI6I)
WO NO 871025086 880315082 881011147 881102121 890103085 890105084 PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
llCS 2 FAILURE DESCRIPTION:
RUST AND CORROSION FROM SW LEAK/REPAIR.
1 1CH272 FAILURE DESCRIPTION:
LEAK THRU/INSPECT.
1 12 SERVICE WATER PUMP 1
1 1
FAILURE DESCRIPTION:
TUBE TENSIONER LOOSE/PULL 12 SERVICE WATER PUMP AND REPAIR, REPLACE OR REWORK.
lSJll 4 FAILURE DESCRIPTION:
BODY TO BONNET LEAK-ENCRUSTED IN BORON.
15 CFCU/SW FAILURE DESCRIPTION:
FLOW HI SPD LOW/INVESTIGATE AND CORRECT.
12SW379 FAILURE DESCRIPTION:
12 CCHX VLV/NO AUTO OPERATION/INVESTIGATE AND CORRECT.
WO NO 890111086 890111150 901001006 SALEM UNIT 1 UNIT EQUIPMENT IDENTIFICATION 1
1LA3186Z FAILURE DESCRIPTION:
11 SG BLWDN TNK/FAILED IND/TROUBLESHOOT AND, CORRECT.
1 13 SER. WTR. PUMP FAILURE DESCRIPTION:
FAILED 4.0.SP/REPLACE/AND INSTALL SPARE PUMP.
1 14 S.W. PUMP FAILURE DESCRIPTION:
PULL 14 SERVICE WTR. PUMP AND INSTALL REBUILT PUMP IAW M6L-2.
e MA 0"JOR PLANT MODIFICATIONS REPORT MONTH JANUARY 1989
- DCR NO.
PRINCIPAL SYSTEM lEC-1496 Deroin. Water lSC-1249 Diesel Generators
- DCR -
Design Change Request e
DOCKET NO.:
50-272 UNIT NAME:
Salem 1 DATE:
February 10, 1989 COMPLETED BY: P. White
~~......_,...,.-....,.--__ ~~~~~
TELEPHONE:
609/339-4455 DESCRIPTION This design change provided two new chemical waste pumps for non-radioactive liquid waste transfer from No. 1 Chemical Waste Tank to the non-rad liquid waste basin.
This design change involved retubing the coolers with titanium tubes to better withstand service water erosion.
e e
MA00R PLANT MODIFICATIONS REPORT MONTH JANUARY 1989 DOCKET NO.:
50-272 UNIT NAME:
Salem 1
- DCR lEC-1496 lSC-12 49 DATE:
February 10, 1989 COMPLETED BY: P. White
~~--,.-=-=~~~--~~~-
TELEP H 0 NE:
60 9/ 339-4455 SAFETY EVALUATION 10 CFR 50.59 Installation of the new pumps was required to ensure continued DM water production.
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.
Retubing the coolers with the titanium material enhanced their resistance to service water erosion.
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
L SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT NO. 1 JANUARY 1989 The Unit began the month operating at full power and continued to operate at that level until January 4, 1989, power was briefly reduced due to a service water leak on No. 11 Containment fan Coil Unit (CFCU).
Another CFCU was placed in service and the Unit was restored to full power later the same day.
The Unit continued to operate at full power until January 20, 1989, when a shutdown was initiated because a test of the reactor coolant pump breaker trip circuitry to the Solid State Protection System could not be verified.
The shutdown was terminated at approximately 50% power when verification of the test was satisfactorily resolved.
The Unit was restored to full power later the same day, and with the exception of some minor load reductions for waterbox cleaning and a faulty SSPS test circuit, continued to operate at full power for the remainder of the period.
~-.
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
P. White UNIT NAME:
Salem 1 DATE:
TELEPHONE:
EXTENSION:
February 10, 1989 609/935-6000 4497 Month JANUARY 1989
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date for next refueling:
Apr i 1 15, 19 8 9
- 3.
Scheduled date for restart following refueling: May 30, 1989
- 4.
A)
Will Technical Specification changes or other license amendments be required?
YES NO NOT DET-ERMINED 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 1989
- 5.
Scheduled date(s) for submitting proposed licensing action:
February if required
- 6.
Important licensing considerations associated with refueling:
7 *
- 8.
- 9.
NONE Number of 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 193 464 1170 1170 September 2001
e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 February 11, 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 January 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 Sincerely yours, L:.~lti'er 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