ML20011D750

Monthly Operating Rept for Nov 1989 for Seabrook Station Unit 1

ML20011D750
Person / Time
Site:	Seabrook
Issue date:	11/30/1989
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-89164, NUDOCS 8912280356
Download: ML20011D750 (7)

Text

..

e New Homoshire i

Yod C. F:.J.

r Senior Vice President and i

Chief Operating Ofheer i

i NYN-89164

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December 15, 1989 i

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Unite'.d fitates Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

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References:

Facility 01.erating 1,1 cense NPF-67. Docket No. 50-445 i

Subject:

Monthly Operating Report i

Gentlemen:

Enclosed please find Monthly Operating Report 89-11.

This report' addresses the operating and shutdown experience relating to Seabrook Station l

Unit i for the month of November 1989 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours, Ted C. Feigenbaum 1

Enclosure cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I l

475 Allendale Road King of Prussia, PA 19406 i

Mr. Antone C. Cerne NRC Senior Resident Inspector P.O. Box 1149 Seabrook. NH 05874

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8912200356 891130 PDR ADOCK 05000443 0

PNV I

New Hornpshire Yankee Division of Public Service Company of New Hampshire 1

P.O. Box 300

• Seabrook, NH 03874

• Llephone (603) 474 9521 g

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New Hampshire Yankee December 15, 1989 7

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ENCLOSURE 1 TO NYN-89164 l

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OPERATING DATA REPORT DOCKET NO.

50-443 UNIT _Seabrook 1 DATE 12/15/89 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

OPEEATING STATUS 1.

Unit Name:

Seabrook Station Unit 1 2.

Reporting Period:

NOVEMBER 1989 3.

Licensed Thermal Power (MWt):

3411 4.

Nameplate Rating (Gross MWe):

1197 7

Design Electrical Rating (Net MWe):

1148 6.

Maximum Dependable Capacity (Gross MWe):

1197 (Initial design value) 7.

Maximum Dependable capacity (Net MWe):

1148 (Initial design value) 8.

If Changee 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 Mhc

10. Reasons For Restrictions, If Any License issued on 05/26/89 is a low nower license authorizinn ooeration at reactor core never levels not in excess of 170 menawatts thermal.

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720.0 8016.0 27385.0 _

12. Number Of Hours Resctor Was Critical 0.0 194.4 194.4

13. Reactor P.eserve 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 Genera,ted (MWH) 0 1090 1090

17. Gross Elec. Energy Generated (MWH) 0 0

0

18. Net Electrical Energy Generated (HWH) 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 MDC Net) 0.0 0.0 0.0

22. Unit Capacity Factor (Using DER Het) 0. 0_,,

0.0 0.0

23. Unit Forced Outage Rate 0.0 0.0 0.0

84. Shutdowns Scheduled Over 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 Pate Of Startup Indefinite

26. Prior to Commercial Operation:

Forecast Achieved INITIAL CRITICALITY 1989 06/13/89 INITIAL ELECTRICITY 1989 Not Aeolicable COHHERCIAL OPERATION 1989 Not Aeolicable 1 of 5

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-443 UNIT Seabrook 1 DATE 12/15/89 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074) 1 MONTH NOVEMBER. 1989 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(HWe-Net)

(HWe-Net) 1 0

16 0

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0 17 0

3 0

18 0

4 0

19 0

t 5

0 20 0

I 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

INSTRUCTIONS on this format, list the average daily unit power level in Mile-Net for each day in the rcporting month.

Compute to the nearest whole megawatt.

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. UNIT SHUTD(TdNG ARD POWER REDUCTIONS DOCKET NO, 50-449 UNIT _SeatrooJt L.,

DATE _ 12/15'89 REPORT MONTH NOVEMBER. 1989 COMPLETED ST 1 Nardone TELEPHONK t6C~A 474-9521 (Ext. 4074) l No. Date Type Duratica Reason 2 Method of Licensee Cause & Corrective (Hours)

Shutting Event Action to Down Reactor 3 Report i Prevent Recurrence NO EFTRIES FOR THIS MONTH 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 fross E-Operator Training & License Kramination previous month F-Administrative 5-Power Reduction G-Operationaf. Ltrror (Explain)

(Duration = 0)

H Other (Explain) 9-Other (Explain) 3 of 5

DOCKET NO.

50-443 l

UNIT Seebrook 1 DATE 12/15/89 CORRECTIVE MAINTENANCE SUt98ARY FOR SAFETY RELATED EQUIPMENT COMPLETED BY P. Nardone REPORT MONTH N07 mBER. 1989 TELEPHONE (603) 474-9521 (Ext. 4074)

Page 1 of 1 DATE SYSTM COMPONENT MAINTENANCE ACTION 11/07/89 Feedwater 1-PW-FI-502 Loop power supply card failed. Replaced Steam Generator B card.

Wide Range Level PAM Indication 11/11/89 Radiation 1-RM-RM-6576B Power supply on log amplifier board failed.

Monitoring Train B Replaced board.

Post LOCA Monitor 11/15/89 Solid State Driver Board A516 Safeguard driver hoard A516 failed.

Re-Protection Train B placed board.

Phase B Isolation 11/18/89 Excore 1-NI-NM 6690 & 6691 Train A & B shutdown monitors failed to Nuclear Train A & B operate properly during low power physics Instrumentation PAM Nuclear testing. Iastalled nes pulse isolator Instrumentation at signal processors.

Channel 4 of 5 s

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• • 7 DOCKET NO.

50-443 UNIT Seabrook 1 DATE 12/15/89 I

COHPLETED BY P. Nardone i

TELEPHONE (603) 474-9521 i

(Ext. 4074)

REPVELING INFORMATI0h REQUEST

1. Name of facility:

Seabrook Unit 1 f

2. Scheduled date for next refueling shutdown:

Not Scheduled i

3. Scheduled date for restart following refueling: Not Scheduled

4. Will refueling or resumption of operation thereafter require a technical i

specification change or other license amendment?

Unknown at this time.

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

informations 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, new operating procedures:

None i

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:

Present licensed capacity:

1236 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 the spent fuel pool assuming the present licensed capacity:

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

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

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