ML20128J927

Monthly Operating Rept for Jan 1993 for Seabrook Station Unit 1

ML20128J927
Person / Time
Site:	Seabrook
Issue date:	01/31/1993
From:	Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-93025, NUDOCS 9302180005
Download: ML20128J927 (6)

Text

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eab ook, NH 03874 Telephone (603)474 9521 fi[ath,5 *O r3gg l

racsimiie <603) 474 2887 m

Energy Service Corporation Tod C. Feigenbaum Senior Vice President and Chief Nuclear Officer NYN-93025.

February 12, 1993 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk Facilit Operating License NPF-86, Docket No. 50 443

Reference:

j

Subject:

hionthly Operating Report Gentlemen:

Enclosed please find hionthly Operating Report 93 01. This report addresses the operating and shutdown experieuce relating to Seabrook Station Unit I for the month of January,1993 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

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Enclosure (s)

TCF:ALL/ tad cc:

hir. Thomas T. hiartin Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 hf r. Albert W. De Agazio, Sr. Project hianager Project Directorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Wachington, DC 20555 hir. Noel Dudley NRC Senior Resident Inspec o

1. I 7 P.O. Box 1149 Scabrook, NH 03874 9302180005 930131

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February 12,1993 a

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OPERATING DATA REPORT.

-DOCKET'NO. _50-443 UNIT Seabrook 1 DATE 02/12!23_

= COMPLETED BY.P. E. Nardone TELEPHONE (603) 474-9521 Ext. 4074 OPERATING' STATUS 1.

Unit Names Seabrook Station Unit 1 2.

Reporting Period:

JANUARY 1993-s 3.

Licensed Thermal Power (}04t):

3411 4.. Nameplate Rating (Gross MWe):

1197 5.

Design Electrical Rating (Net MWe):

1148 6.

Maximum Dependable Capacity (Gross Mde):

1200' 7.

Maximum Dependable Capacity (Net MWe):

1150-8.

If Changes Occur in Capacity Ratinga-(Items. Number 3.Through 7)

Since Last P.eport,- Give Reacons:

Not Applicable 9.

Power Level To Which Restricted. If Any:

None 10.

Reasons For Restrictions. If Any:

_,Not Apulicable-This Month Yr.-to-Late Cumulative

11. Hours In Reporting Period 744.0 744.0 55177.0

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12. Number Of Hours Reactor Was Critical.

590.7 590.7-20094.1

13. Reactor Reserve Shutdown Hours 0.0 0.0, ~

18152.5-953.3

14. Hours Generator On-Line 571.6 571.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWE);

1870107 1870107..

5839?664

17. Gross Elec. Energy Generated (MWH}-

652723--

__652723-20214361

18. Net Electrical Energy Generated (MWH) 626614 626614

_1_9403426

• 19. Unit Service Factor 76.8 76.8-78.0

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• 20. Unit Availability Factor 76.8 76.8 78.0

• 21. Unit Capacity Factor (Using MDC Net) 7 3. 2__,

73.2 74.2

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

73,4 73.4 74.4

• 23. Unit Forced 04tageLRate 23.2 23.2

6.3-

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

None Scheduled

25. If Shut-Down At End Of Report Period,-Estimated Date-Of Startup: Not-Applicable

• NOTE:

' Cumulative" values based on total hours. starting 08/19/90, date Regular Full _ Power Operation began.

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MARAGE DAILY UllIT POWER LEVEL DCCKET No. 50-443 UNIT Egf.),Lqp,k 1 DATE,9],LUj93-ColtPLETED BY fdwNardone TELEP110NE (M1) 674 91id, Ext. 4074 HONTil J Al{UARY. 199 3,,,

DAY IVER.10E DAILY POWER LEVP't DAY AVERAGE DA.UY POWER-LEVEL i

(HWe-Net)

(hWe-Net) 1 1154

'17 O.

2 U19 10

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3 1 a 3 _,,

19 O

4 148 20 57 j

5 882 2i 915 6

1040 22 1lJ,L _ _

7 1151 23 1153 8.

1153

-24 1154 9

31.,L3 25

),JJ $ -

10.

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26 1154 11 1153 27 1155 12 1153 28 11 M 13 1153 29 1153 14 975-30 1153 15 0

31~

1153

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INSTRUCTIONS On this format. -list the average daily unit power level in HWe-Net for each day in the -

reporting month. Compute to the nearest whole megawatt.

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UNIT SHUTDOL*NS AND POWER REDUCTIONS DMT ttO. 50 A43 UNIT Seabrook 1 DATE 02/12/93

.I REPORT HONTH JANUARY. 1993 COMPLETED BY P. E. Nardone TELEPHONE (623) a74-9521 Ext. !076 3

2 Method of Licensee Cause & Corrective

' No. -

Date Type '

Duration Reason (Bours)

Shutting Event

. Action to Down Reactor Report i Prevent Recurrence 3

Page 1 of 1 93-01~

F 30.9 A, G-2

'93-001 Manual reactor trip due to, loss-of' bot ~n main feed water pumps on low section pressure.

See LER 93-001 for infertiation and root cause and corrective action.

93-02 F

141.5 A

3 93-003' Automatic reactor trip caused by-turbine trip.

Turbine trip was initi,a ted by the g'nerator e

breaker opening o.

a ground voltage relay.

See LER 93-003 for infor: cation on root cause and.

. corrective action.

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2 Method Fr Forced Reason:

1-Manual 5: Scheduled A-Equipc:ent Failure (Explain) 2-Manual Screm B-Maintenance'or Test' 3-Automatic Scram.

C-Eefueling 4'-Continued from D-Regulatory Eestriction

..E-Operator Training & License Examination

. previous month

~5-Power Reduction F-Administrative G-Operational 1 Error (Erplain)

(Duration = 0)

H-Other (Explain)-

9-Other (Explain)

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DOCKET NO. 50 443 4

UNIT Seabroph I 3

DATE 02/12L9}

COMPLETED BY P. E, Nardone TELEPHONE (603) 474-9571 Ext. 4074 BEFUELING INFORMATION RE00EST f

1. Name of facilitys Seabrook Unit 1

2. Scheduled date for next refueling shutdown Refueling Outage 3, 0$/26/94

3. Scheduled date for restart following refueling:

Refuel.ing Outage 3. 05/20/94 i

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

No

5. Scheduled date(s) for uubm).tting licensing action and supporting informations N/A

6. Important licensing considerations.aosociated v ch refueling, e.g.,

new or different fuel design or supplier, unrevj <ed design or-perfornance analysin methods, significant changer in fuel design, new operating procedures i

None

7. The number of fuel assemblies (a) in the core aind (b).in the spent fuel storage pool (a) In Coro

_,,J,9 3 (b) _,,136

8. The present licensed spent fuel pool storage = capacity-and the sine of any increase in licensed storage capacity that has been requested or-l 1s planned, in number of fusi assembifesa l

Present licensed capacity:

1236 No increase in storage capscity requented or planned.

9. The' projected dutc of the last refueling that can be discharged'to the spent fuel pool ausuning the present licensed capacity:

Licensed - capacity -of ' 1236 fuel assemblies based on two annual and twelve eighteen-month refuelings with full core offload' capability.

The -current licensed capacAty is adequate until1at least-the year _ 2010.

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