ML20011D750

Monthly Operating Rept for Nov 1989 for Seabrook Station Unit 1.W/891215 Ltr

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 l New Homoshire

• Yod C. F:.J. r i

Senior Vice President and i Chief Operating Ofheer i

i NYN-89164 [

December 15, 1989 i

l I 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 New Hornpshire Yankee Division of Public Service Company of New Hampshire

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P.O. Box 300

• Seabrook, NH 03874

• Llephone (603) 474 9521 g

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New Hampshire Yankee  ;

December 15, 1989 7 i

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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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I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-443 l 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 {

l 2 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)

No. Date Type l 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 UNIT Seebrook 1 l 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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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  !

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