ML19354D891

Monthly Operating Rept for Dec 1989 for Seabrook Station Unit 1.W/900112 Ltr

ML19354D891
Person / Time
Site:	Seabrook
Issue date:	12/31/1989
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90014, NUDOCS 9001230173
Download: ML19354D891 (7)

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, New Hampshire-- '

- :m Tod C. F?"e President and Senior Vic Chief Operating Officer NYN 90014 January 12, 1990 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:

Enclosed please find Monthly Operating Report 89-12. .This report.

addresses the operating and shutdown experience' relating to Seabrook Station ~

Unit'l for the month of December 1989 and is submitted in-accordance with the.

requirements of Seabrook Station' Technical Specification 6.8.1.5s.

--i Very truly yours,

/* __

Ted C. Fei enbaum Enclosure cc Mr. William T. Russell  !

Regional Administrator United States Nuclear Regulatory Commission Region I .;

475 Allendale Road 1 King of-Prussia,.PA 19406 i

Mr. Antone C. Cerne NRC Senior-Resident Inspector P.O.-Box 1149' Seabrook,-NH 03874

1 9001230173 891231 '

PDR ADOCK 05000443 R PDC

- l( ,

New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474 9521. .

New Hampshire Yankee January. 12, 1990 ENCLOSURE 1 TO NYN- 90014; l-I 1

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} OPERATING DATA REPORT DOCKET NO. 50-443-UNIT Seabrook 1 DATE 01/12/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9511 (Ext. 4074)

OPERATING STATUS

1. Unit Name: Seabrook Station Unit 1

2. . Reporting Period DECEMBER 1989

3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross MWe): 1197

5. Design Electrical Rating (Net HWe): 1148-6 '. Maximum Dependable Capacity (Gross MWe): 1197 (Initial design value)

7. Maximum Dependable Capacity (Net MWe): 1148 (Initial design value)

8. If Changes occur in capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons: Not Aeolicable-

9. Power Level To Which Restricted If Any 170 MWt

10. Reasons.For Restrictions, If Any: License issued on- 05/26/89 is a low oower license authoriaina operation at reactor core power levels not in excess of 170 menawatts thermal.

This Month Yr.-to-Date ' Cumulative l

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11. Hours In Reporting Period 744.0 8760.0 28129.0

12. Number Of Hours 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 Hours 0.0 0.0- 0.0

16. Gross Thermal Energy Generated (MWH) ,

-O' 1090 1090

17. Gross Elec. Energy Generated (MWH) 0 0 0- '!

18.- Net Electrical Energy Generated (FMH) 0 0 0

19. Unit Service Factor- 0.0 0.0 0.0

20. Unit Availability. Factor 0.0 0.0 0.0 j

21. Unit Capacity Factor (Using MDC. Net) 0.0 - 0. 0 0.0 {

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

23. Unit Forced Outage Rate .

0.0 -0.0 0.0

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

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. Prior to Commercial' Operation: Forecast Achieved- j i

j INITIAL CRITICALITY 1989 06/13/89 INITIAL ELECTRICITY 1990 Not-Aeolicable  ;

COMMERCIAL OPERATION 1990 Not Aeolicable i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-443 UNIT Seabrook 1-DATE- 01/12/90

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

MONTH DECEMBER. 1989 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER-LEVELI (MWe-Net) (MWe-Net) 1 0 '16 0 1 2 0 17 0 3 0 18. 0 4 0 19 0-5 0 20 0 '!

6 0 21 0 7 0 22 0 -l 8 0 23- 0 "

9 0 24 0 1 10 0 25 0 11 0 26 0-12 0 27- -0 13 0 28 0 l

.14 0 '29 _ O' 15 0 30 0  ;

1 31 0 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 nearest whole megawatt.

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UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-443 ,

UNIT Seabrook l' DATE 01/12/90 REPORT MONTH DECl!MB2R . 1989 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521-(Ext. 4074)

-No. Date - Type l Duration Reason 2 Method of' ' Licensee. Cause & Corrective (Hours) Shutting Event ' Action to Down Reactor 3' Report # Prevent Recurrence NO ENTRIES FOR THIS MONTH

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1 2. .3 F: Forced Reason: Method:

G: 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 Reduction G-Operational Error.(Explain) (Duration =.0)

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

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DOCKET NO. 50-443 .

UNIT Seabrook 1 DATE 01/12/90 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 REPORT MONTH DECEMBER. 1989 (Ext. 4074)

Page 1 of 1 DATE SYSTEM COMPONENT MAINTENANCE ACTION 12/05/89 Service 1-SW-P-110B Surveillance data showed high pump vibra-Water Train B tion. Replaced worn stuffing box bearing.

~ Cooling Tower Pump 12/27/89 ' Primary 1-CC-E-17A Heat exchanger leaking. Plugged tubes Component Train A identified during eddy current testing.

Cooling Water Primary Component 'Resleeved all remaining tubes.

Cooling Water Heat Exchanger 12/30/89 Containment 1-CAP-V-2 and 3 Valves would not open. Replaced defective Air Purge . Train B quick exhauster on valves.

Inside Containment Isolation Valves 1

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DOCKET NO. 50-443 UNIT _Seabrook 1 DATE 01/12/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

REFUELING INFORMATION REQUEST

1. Name of facility: Seabrook Unit 1

2. Scheduled date for next refueling shutdown: Not Scheduled

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 amendment?

Unknown at this time.

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

Not Applicable ^

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, 3 new operating procedures:

None I i

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7. The number of fuel assemblies (a) in the core and.(b) in the spent-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:

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

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

Licenced capacity of 1236 fuel assemblies based on sixteen  :

refuelings and full core offload capability.  !

The current licensed capacity is adequate until at least the j year 2007.

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