ML20006F084

Monthly Operating Rept for Jan 1990 for Seabrook Station Unit 1

ML20006F084
Person / Time
Site:	Seabrook
Issue date:	01/31/1990
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90039, NUDOCS 9002270151
Download: ML20006F084 (7)

Text

rwn f$ Mw Hampshire Tod C. F '.

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Senior Vice Presi Chief Operating Oflicer

.p lin NYN-90039 February 15, 1990 i

i United States Nuclear Regulatory Comission Washington, DC 20555

' Attention:

Document Control Desk

References:

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

Subject:

Monthly Operating Report Gentlemen:

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Enclosed please find Monthly Operating Report 90-01. 'This report

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addresses the operating.and shutdown experience relating to Seabrook Station-

. Unit 1 for the month of January 1990 and is-submitted in.accordance with the-roquirements of Seabrook. Station Technical Specification 6.8~.1.5.

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=Very truly yours, l

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Ted C. Fe genbaum-Enclosure.

ces-Mr. William T. Russell-Regional' Administrator United States Nuclear Regulatory Comission Region I 475 Allendale Road

-King of Prussia, PA 19406 1

~Mr.' Noel Dudley-1 NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874

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h2270151900131

'R ADoCK 0500o443:

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

• Seabrook, NH 03874

• Telephone (603) 474 9521

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OPERATING DATA REPORT

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DOCKET NO.

50-443 UNIT Seabrook 1 DATE '02/15/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)-

OPERATING STATUS 1.-

Unit Name ~

Seabrook Station Unit 1 2.

Reporting Period:

JANUARY 1990 3.

Licensed Thermal Power'(ISit):

3411 4.

Nameplate Rating (Gross-MWe):

1197

5.. 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. Changes Occur in Capacity Ratings (Items Number 3 Through 7)

-Since Last Report, Give Reasons:

Not Applicable

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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 power license authorizinn operation at reactor core power levels not in excess of 170 megawatts thernel.

This Month Yr.-to-Date Cumulative 11.-Hours In Reporting Period' 744.0 744.0 28873.0-j

12. Number Of Hours Reactor Was Critical 0.0 0.0 194.4 i

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 L

14. Hours Generator.On-Line 0.0 0.0 0.0

15. Unit Re' serve. Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0 0

1090

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

0 L

18. Net Electrical Energy Generated (MWH) 0 0

0 l-

19. Unit Service Factor 0.0 0.0 0.0 i

'20. Unit Availability Factor 0.0 0.0 0.0 l

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 0.0 22.JUnit Capacity Factor (Using DER Net) 0.0 0.0 0.0

23. Unit Forced Outage Rate 0.0 0.0

-0.0 i.

J24. 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 Date Of Startup:

Indefinite

26. Prior to Commercial Operation:

Forecast Achieved

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INITIAL CRITICALITY 1989 06/13/89 L

INITIAL ELECTRICITY 1990 Not Applicable COMMERCIAL OPERATION 1990 Not Applicable l

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AVERAGE DAILY UNIT POWER LEVEL

DOCKET NO. -

50-443 UNIT Seabrook 1 DATE 02/15/90 COMPLETED BY-P. Nardone TELEPHONE (603) 474-9521:

(Ext. 4074) l l.

'HONTH JANUARY. 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

,1 -

0 16

'O g

21 0

17 0

j

!3-0 18 0

4 0

19 0

.5 0

20 0

,e:

'6~

21-

'O 0-

' 7.

0 22 0

i 8

-0 23 0

9 0

24 0

1 4

i 10 0

25 0

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'11 0

26 0'

.j 12 0

.27 0

13

-0 28 0

l 1

14 0

29 0

.j 15 0

30 0

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31 0

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INSTRUCTIONS-

-On this format, list the average daily unit power level in MWe-Net for each day in the raporting month.- Compute to the nearest whole megawatt.

2 of 6 c

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-,- : w UNIT SHUTDOWNS AND POWER REDUCTIONS

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.. DOCKET NO6 7 50-443 J-i UNIT Seabrook'l~

DATE 02/15/90 REPORT MONTH JANUARY.'1990 ~

-COMPLETED BY P. Nardone TELEPHONE'(603) 474-9521~-

(Ext.-4074)

No. Date Type Duration ' Reason 2-

Method of-Licensee Cause & Corrective-l (Hours)

Shutting Event Action to 3

Down Reactor Report i Prevent' Recurrence i

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NO ENTRIES FOR THIS 210 NTH 1

2 3-F: Forced Reason:-

Method:-

S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 4-Continued from 3-Automatic Scram D-Regulatory Restriction E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction G-Operational Error (Explain).

(Duration = 0)

H-Other (Explain)-

9-Other~(Explain) l l

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DOCKET NO.

50-443

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UNIT Seabrook 1 DATE 02115/90 COMPLETED BY P. Nardone CORRECTIVE MAINTENANCE SUt99LRY FOR SAFETY RELATED EQUIPMENT TELEPHONE (603) 474-9521 REPORT MONTH JANUARY. 1990 (Ext. 4074)

Page 1 of 2 MAINTENANCE ACTION DATE SYSTDi COMPONENT 01/06/90 Primary 1-CC-V-121 Air operated valve failed to apen.

Component Train A Repaired broken wire at solenoid coil Cooling Water Inside Containment termination.

Isolation Valve Both reactor trip breakers failed to 01/06/90 Rod Control 1-CP-CP-111 Train A and B close during surveillance testing.

Reactor Trip Cleaned dirty contacts on charging Switchgear motor cutoff limit switches. Replaced faulty spring release coil on Breaker B.

01/06/90 Reactor 1-RC-LCV-459 Air operated valve failed to close during Coolant Train A letdown isolation test. Replaced defective Letdown Isolation solenoid valve.

Valve 4 of 6

. w-DOCKET NO.

Sti-443 UNIT Seabrook 1 DATE 02115190 CORRECTIVE MAINTENANCE SUt9%RY FOR SAFETY REIATED EQUIPMENT COMPLETED BT P. Nardone REPORT MONTH JANUARY. 1990 TELEPHONE (603) 474-9521 (Ext. 4074)

Page 2 of 2 DATE SYSTEM COMPONENT MAINTENANCE ACTION 01/08/90 Residual Heat 1-RB-P-9B Installed redesigned impellar to reduce Removal Train B thrust loads during operation.

RER Pump 01/17/90 Primary 1-CC-E-17B Heat exchanger leaking. Plugged tubes Component Train B identified during eddy current testing.

Cooling Water Primary Component Resleeved all remaining tubes.

Cooling Water Heat Exchanger 01/22/90 Reactor Coolant 1-RC-TB-412D/G Bistable failed to operate during Protection Set 1 surveillance test. Replaced fuse.

LO TAVG, LO-LO TAVG Temperature Bistable 5 of 6 m

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o D00KET NO.

50-443 UNIT Seabrook 1

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DATE 02/15/90 COMPLETED BY P. Hardone TELEPHONE (603) 474-9521 (Ext. 4074)

REFUELING INFORMATION REOUEST

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. Vill refueling or resumption of operation thereafter require a technical specification change or other license amendmentt Unknown at this time.

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

Not Applicable 1

6. Important licensing considerations associated with refueling, e.Bae new or different fuel design or supplier, unreviewed design or parformance 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 opert 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 requestod 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 l

refuelings and full core offload capability.

The current licensed capacity is adequate until at least the l

year 2010.

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