ML20070K655

Monthly Operating Rept for Feb 1991 for Seabrook Station Unit 1

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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