ML20247P267

Monthly Operating Rept for Aug 1989 for Seabrook Unit 1

ML20247P267
Person / Time
Site:	Seabrook
Issue date:	08/31/1989
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89113, NUDOCS 8909270083
Download: ML20247P267 (7)

Text

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gNew Hampshire- 1 Yankee  !

j NYN- 89113 September. 15,'1989 United' States Nuclear Regulatory Commission

-Washington, DC 20555 Attention: Document Control Desk

References:

Facility Operating License NPF-67, Docket No. 50-443

Subject:

- Monthly Operating Report Gentlemen:

.In accordance with Technical Specification Sect!.on 6.8.1.5, enclosed please find Monthly Operating Report 89-08 covering the operation and shutdown experience relating to Seabrook Station Unit 1.

Very truly yours, fxs/6 Ted C. Feigenbaum Senior Vice President end Chief Operating Officer Enclosure cc: 'Mr. William T. Ruscell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Antone C. Cerne NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 8909270083 890831 PDR ADOCK 05000443 R PDC g ii New Hampshire Yonkee Division of Public Service Company of New Hampshee /

P.O. Box 300 = Seabrook, NH 03874

• Telephone (603) 474-9521

L DOCKET NO. 50-443 UNIT Seabrook 1 )

DATE 09/05/89 I CCMPLETED BY P. Nardone TELE 210NE (603) 474-9521 (Ext. 4074)

OPEATING STATUS

1. Unit Name: Seabrook Station thit 1

2. Reporting Period: AUGUST 1989

3. ' Licensed haal Power (MRt): 3411

4. Nameplate Rating (Gross MWe): .

1197

5. Eesign Electrical Rating (Net MWe): 1148

6. Max 12ran D pendable Capacity (Gross MWe): 1197 (Initial design value)

7. Maxinom Dependable Capacity (N3t MWe): 1118 (Initial design value)

8. If Changas Occur in Capacity Ratings (Items Number 3 9hrough 7)

Since Iast Report, Give Reasons: 'Not 7Dolicable

9. Power level To Which Restricted, If Any: _170 MWt

10. Reasons For Restrictions, If Ar.y: Licente issued on 05/26/89 in a low power license authorizing operation at reactor core power levels not in excess of 170 meaawatts thermal.

'311s Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744.0 58.31.0 25200'0 .

12. Number Of Houra Reactor Was Critical 0.0 194.4 194.4

13. Reactor reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 0.0 0.0 0.0

15. Unit Reserve Shutdown Hoars 0.0 0.0 0.0 ~

16. Gross 'Ibernel Energy Generated (MWH) 0 1090 1090 _

17. Gross ele.c. Energy Generated (MWH) -0 0 0

18. Net Electrical. Energy Generated (MWH) 0 0 0

19. Unit Service Factor 0.0 0.0 0.0

20. Unit Availability Factor 0.0 0.0 0.0

21. Unit Capacity Factor (Using MOC Net) _

0.0 0.0 0.0

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 0.0

23. Unit Forced Outage lhte 0.0 0.0 0.0

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

_ Reactor shutdown as of 06/22/89 for indefinite duration.

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: Indefinite

26. Units In Test Status (Prior to Cummulal Operation): Forecast Achieved INITIAL CRITICALITY 1989 06/13/89 INITIAL ELEC'IRICITY 1989 Not Applicable OCMMERCIAL OPERATIO 1989 Not Applicable 1 of 6

.. : . ;y- '

l', , AVEIUGE DMLY UNIT POWER LEVE DOCKETT NO.- 50-443-UNIT Seabrook 1 DATE 09/05/89 CXMPIRfED BY P. Nardane TELEPH21E (603) 474-9521

(Ert. 4074)-

M0tml AIEIUST, 1989 DU ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PONER LEVEL (MWe-Net) (NWe-Net) 1 0 16 0' 2 0 17 0 3 0 18 0 4- 0 19 0 5 0 20 0 6' 0 21 0 7 0 22 0 8 0 23 0 9 0 24 0 10 0 25 0 11 0 26 0 12 0 27 0 13 0 28 0 14 0 29 0 15 0 30 0 31 0 l

1Nsmcrras On this format, list the average daily unit power level in NWe-Net for each day in the reporting Irnth. Ocznpute to the nearest whole megawatt.

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} DOCKET 10. 50-443

."- UNIT Seabrook 1 DATE 09/05/89 COFLLTED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

REFUELIfC IfMIRMATION REQUEST

1. !broe of facility: Seabrook Unit 1

2. Scheduled date for next refueling shutdown: Not Scheduled 1

3. Scheduled date for restart following refueling: Not Scheduled

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

Unknown at this time.

l 5. Scheduled date(s) for subnitting licensing action and supporting i infonnation: '

Not Applicable

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

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

Ibne l

l

7. %e number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) In Core: 193 (b) 0

8. W e present licensed spent fuel pool storage capacity and the size cf any increase in license:1 storage capacity that has been requested or is planned, in number of fuel asscanblies:

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

9. h e projected date 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 refuelings and full core offload capability.

We current licensed capacity is adcquate until at least the year 2007.

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