ML20072S572

Monthly Operating Rept for Mar 1991 for Seabrook Station Unit 1

ML20072S572
Person / Time
Site:	Seabrook
Issue date:	03/31/1991
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-91057, NUDOCS 9104160352
Download: ML20072S572 (6)

Text

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.* s New. Hampshire T Ted C. Feigenbovm hh- President and-Chief Esecutive Officer NYN. 91057.

April 12,' 1991 United States' Nuclear Regulatory Commission Washington, DC 20555 Attentior: 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-9103. This report addresses- the, J operating and ' shutdown experience relating to -Seabrook Station Unit -1' for . the month of .

March,1991 and is submitted in accordance with 'the -requirements of Seabrook -Station -  ;

Technical Specification 6.8.1.5.

Very truly. yours,

-T l

l Enclosure (s)

TCF:WJT/ tad cc: ~ Mr. Thomas T. Martin

Regional Administrator United States Nuclear Regulatory Commission .

Region 1 475 Allendale Road.

King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager

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t Project Directorate-l 3 Division of- Reactor-Projects U.St Nuclear Regulatory Commission -i Washington, DC , 20555 Mr. Noel Dudley-NRC Senior . Resident' Inspector P.O.~ Box 1149 Seabrook, NH 03874 9104160352 910331

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PDR ADOCK 05000443 -

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, New Hampshi_re Yankee Division of Public Service Company of New Hampshire  !

P.O. Box 300

• Seabrook,' NH 03874

• Telephone (603) 474 9521-

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New Hampshire Yankee April 12,1991 l

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KNCLOSURE 1 TO NYN-91057 t

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. 'l OPERATING DATA REPORT DOCKET NO. 50-443 UNIT Seabrook 1 DATE 04/12/91 ,

COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

OPERATING STATUS i

1. Unit Name. Seabrook Station Unit 1

2. Reporting Period: MARCH 1991

3. Licensed ' thermal Power (Wt): 3411

4. Nameplate Rating (Gross We): 1197

5. Design Electrical Rating (Net We): 1148

6. Maximum Dependable Capacity (Gross We): 1200

7. Maximum Dependable Capacity (Not MWe): 1150

8. If Changes Occur in Capacity Ratings (Items Number 3 Through-7)

Since Last Report, Give Reasons: Not Anolicable

9. Power Level To Which Restricted, If my: None

10. Reasons For Restrictions, If Any: Not Anolicable v

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744.0 2160.0 39049.0

' 12. Number Of Hours Reactor Was Critical 707.8 2099.8 7819.1

13. Reactor Reserve Shutdown Hours OA_ 0.0 953.3

14. Hours Generator On-Line 707.8 2088.1 6215,5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 2355827 6561223 19161549

17. Gross Elec. En'rgy e Generated (MWH) 824741- 2284633 6556550

18. Net Electrical Energy Generated (MWH) 792397 2189445 6283443

• 19. Unit Service Factor 95.1 96,7 90.0

, *20. Unit Availability Factor 95.1 9 6 . 7___ 90.0

• 21. Unit Capacity Factor (Using MDC Net) 92.6 88.1 84.7

• 22. Unit Capacity Factor (Using DER Net) 92.8 88.3 84,9

• 23. Unit Forced Outage Rate 4.9 3.3 _

10.0 h

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

REFUELING. 07/27/91. 67 DAYS

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: 04/06/01 a

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• NOTE: Values based on accumulated hours starting 08/19/90, date Regular Full P)wer Operation began.

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s AVERAGE DAILY UNIT POWER LEVEL DOCl"ET NO. 50-443 UNIT Seabrook 1-DATE 04/12/91 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

MONTH MARCH. 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)- ,

f 1 344 16 1150 2 1085 17 1150 3 1152 18 1151 ,,,,,

4 _ 1151 19 1150 5 1151 20 1150 i 6 1151 21 1149 7 1151 ;22 1148 8 1150 23 1148' 4-1150 9 , 24 1148-

! 10 1150 25 1148 4

11 1147 26 1147 12 1147 17' 1148 7

I 13 1146 28 1148 14 1147 29 1148 15 1147 -

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, 31 0 INSTRUCTION.9 On this format, list the average daily unit power level in MWe-Net for each day. in the -

reporting month. Computa to the nearest whole megawatt.

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A UNIT SHUTDOWNS AND POWER REDUCTIONS DOCEET NO.30-443 UNIT Seabrook 1 DATE 04112191 REPORT MONTH MARCH. 1991 COMPLETED BT P. Nardone TELEPHONE (603) 474-9521

( Es t. 4074)

No. Date Type l Duration Reason2 Method of Licensee Cause & Corrective (Hours) Shutting Event Action to Down Reactor 3 Report i Prevent Recurrence Page 1 of 1 91-02 03/01/91 F 0 F 4 N/A Steam generator chemistry out of specification (Action Level II) required power reduction to 302 RTP.

Retczned to full power operation on 03/02/91.

91-63 03/30/91 F 36.2 A 2 91-002 Manual trip fue to turbine runback and failure of condenser steam dumps eo open.

See LER 91-002 for information on root cause and corrective action.

1 2 3 F: Forced Reason: Method:

S: Scheduled A-Equipment Failure (Explain) 'l-Manual B-Maintenance or Test 2-Manual Scrum C-Refueling' - tomatic Scram D-Regulatory Restriction 4-Contir.aed from E-Operator Training & License hamination previous month F-Administrative 5-Power Reduction G-Operational Error (Explain) (hre tion - 0)

H-Other (Explain) 9-Other (Explain) (

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l c.... J DOCKET NO. 50-443 UNIT Seabrook 1

. DATE 04/12/91 COMPLETED BY _P. Hardone TELEPHONE (603) 474-9521 (Ext. 4074)

REFUELING INFORMATION REQUEST

1. Name of facility: Seabrook Unit 1

2. Scheduled date ! r . ext refueling chutdown: 07/27/91

3. Scheduled date for restart following refueling: 10/02/91 '

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Ye*,, the removal of the Residual Heat Removal System Autoclosure Interlock

5. Scheduled date(s) for submitting licensing action and supporting information:

New Hampshire Yankee Letter NYN-91011, submitted on January 24, 1991

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None

7. The number of fuel assemblies (a) in the core and (b) in the spent N fuel storage pools (a) In Core 193 (b) 0 ,

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or '

is planned, in number of fuel assemblies:

Present licensed capac'ty: 1236 No increase in storage capacity requested or planned.

9. The projected dste of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Licensed capacity of 1236 fuel assemblies based on sixteen i refuelings and full core offload capability.

The current licensed capacity is adequate until at least the.

year 2014.

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