ML20070K655
| ML20070K655 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/28/1991 |
| From: | Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-91043, NUDOCS 9103190069 | |
| Download: ML20070K655 (7) | |
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New Hampshire Yh Ted C. Folgenbaum President and -
Chief Executive Offker NYN 91043 March 14,1991 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk l
Reference:
Facility Operating License NPF 86, Docket No. 50 443
Subject:
Monthly Operating Report Gentlemen:
Enclosed please find Monthly Operating Report 9102. This report addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of February,1991 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
Very truly yours, Q WM b--
- Ted C. Feigenbaum Enclosure (s)
TCP:WJT/ tad cc: Mr. Thomas T. Martin Regional Administrator i
United States Nuclear Regulatory Commission I Region I l
475 Allendale Road l King of Prussia, PA 19406 A
Qg Mr. Gordon E. Edison, Sr Project Manager coeca Project Directorate 13 NP Division of Reactor Projects 08 U.S. Nuclear Regulatory Commission 40 Washington, DC 20555 02
$ Mr. Noel Dudley
$q NRC Senior Resident inspector P.O. Box 1149 4 3e 190016 brook, Nii .03874 E$ct New Hampshire Yonkee Division of Public Service Company of New Hompshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521.
76M g// N
New flampshire Yankee March 14,1991 ENCLOSURE 1 TO NYN 91043 4
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OPERAT8NG DATA REPORT DOCKET NO. 50-443
- UNIT Seabrook 1 DATE 03/14/91 COMPLETED BY P. Nardone TELEP110NE (603) 474-9571 (Ext. 4074) ,
OPERATING STAT 21
- 1. Unit Name Seabrook Station Unit 1
- 2. Reporting Period FEBRUARY 1991
- 3. Licensed Thermal Power (MWt): 3411
- 4. Nameplate Rating (Gross MWe): 1197
- 5. Design Electrical Rating (Net MWe): 1148
- 6. Maximum Dependable Capacity (Gross MWe): 1200
- 7. Maximum Dependable Capacity (Net MWe): 1150
- 8. If Changes occur in Capacity Ratings (Items Number 3 Througb 7)
Since Last Report, Give Reasons: Not Aeolicable .
- 9. Power Level To Which Restricted, If Any: None
- 10. Reasons For Restrictions, If Any: Not Applicable i
This Month Yr..to-Date Cumulative ,
- 11. Hours In Reporting Period 672.0 1416.0 3830$.0
- 12. Number of Hours Reactor Vas Critical 648.0 1392.0 7111.3
- 13. Reactor Reserve Shutdown Hours ,,
0.0 0.0 953.3
- 14. Hours Generator On Line 636.3., 1380.3 5507.7 1
- 15. Unit Reserve Shutdown !!ours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1669920 4205396 16805722
- 17. Gross Elec. Energy Generated (MWH) 570762 1459892 5731Eq9
- 18. Net Electrical Energy Generated (MVH) 542275 1397048 5491046 i *19. Unit Service Factor 94.7 97.5 89.2
- 20. Unit Availability Factor 94.7 97.5 89.2 l *21. Unit Capacity Factor (Using MDC Net) 70.2 __ 85.8 83.4
- *22. Unit Capacity Factor (Using DER Net) 70.3 85.9 _ 83.6 4
+23. Unit Forced Outage Rate 5.3 2.5 10.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each)
REFUELING. 07/27/91. 67 DAYS
~2'$. If Shut Down At End Of Repore Period, Estimated Date Of Startup: Not Aeolicable
- NOTE: Values based on accumulated hours starting 08/19/90, date Regular Full Power Operation began.
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AVERAGE DATLY UNIT POWER LEVEL i
DOCKET NO. 50-443 3
UNIT Seabrook 1 ,
4 DATE 03/14/91 COMPLETED BY P. Nordone TELEPHONE (603) 474-9521 (Ext. 4074)
MONTH FEBRUARY. 1991 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe. Net) (MWe-Net) 1 1140 16 519 2 1149 17 $28 3 1151 18 530 4 1151 19 529 5 1151 20 $27 6 1150 21 529 7 1151 22 531 8 1151 23 528 9 1151 24 645 10 1151 25 1143
- 11 1151 26 1150 12 398 27 1154 13 _.
28 28 497 14 345 15 . 360 INSTRUCTIONS i
On this format list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nes. rest whole megawatt.
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UNIT SEUTDO~JNS AND FO"4ER REDUCTIONS DOCEET NO. 50-403 .
UNIT Seabrock 1 .
DATE 03/14/91 REPORT MONTH FEBRUARY. 1991 COMPLETED BY P. Nardone -
TELEPHONE (603) 474-9521 (Ext. 4074)
No. Date Type i Duration Reason' Method of Licensee Cause & Corrective (Hours) Shutting Event Action to Down Reactor 3 Report i Prevent Recurrence y Page 1 of 1 91-01 02/12/91 F 35.7 B 3 91-001 Loss of turbine EEC system pressure caused an automatic turbine / reactor trip. See LER 91-001 for information on root cause and corrective action.
Conmenced normal restart on 02/13/91.
Problems with steam generator chemistry and main feed pump A vibration pre-vented a return to full power operation until 02/25/91.
91-02 02/28/91 F 0.0 F 5 N/A Steam generator chemistry out of specification (Action Level II) required PWR reduction to 30I RTP.
Power being maintained at 27I RTP.
1 2 3 F: Forced Reason: Method:
S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued from E-Operator Training & License Examination previous month F-Administrative- 5-Power R 'setion -
G-Operational Error (Explain) '
(Durata m = 0)
H-Other (Explain) 9-Other (Explain) 3 of 5
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DOCKET NO. 50-443 .
UNIT Seabrook 1 ,
DATE 03/14/91 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT COMPLETED BY P. Nardone REPORT MONTH FEBRUARY. 1991 TELEPHONE (603) 474-9521 (Ext. 4074)
Page 1 of 1 DATE SYSTEM COMPONENT MAINTENANCE ACTION 02/11/91 Reactor 1-RC-PCV-456A Intrusion of hydrogen into magnet capsule Coolant Train A caused failure of limit switch. Replaced Pressurizer magnetic rod and reed switch in limit Power Operated switch assembly. Train B PORV limit switch Relief Valve assembly was also reworked as a preventative measure.
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DOCKET NO.- 50-443 UNIT Seabrook 1 DATE 03/14/91 COMPLETED BY P. Hardone ,_
- TELEPHONE (603) 474-9521 (Ext. 4074) 4 REFUELING INFORMATION REQUEST
- 1. Name of facility: Seabrook Unit 1
- 2. Scheduled date for next refueling shutdown: 07/27/91
- 3. Scheduled date for restart following refueling: 10/02/91 3
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, the removal of the Residual Heat Removal System Autoclosure interlock j 5. Scheduled date(s) for submitting licensing action and supporting
- informations New Hampshire Yankee Letter NYN-91011, submitted on January 24, 1991 4 6. Important licensing considerations associated with refueling, e.g..
j new or offferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design.
new operating procedures:
i None j 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool
- (s) In Cores 193 __ (b) 0
- 8. The present licensed spent fuel pool storage capacity and t'..s slae of 1 any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present licensed capacity: 1236 l No increase in storage capacity requested or planned.
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- 9. The projected date of the-last refueling that can be discharged to j the spent fuel pool assuming the present licensed capacity
- Licensed capacity of 1236 fuel assemblies based on sixteen refuelings and full core offload capability.
i The current licensed capacity is adequate until at least the year 2014.
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