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)

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• f eab ook, NH 03874 r3gg Telephone (603)474 9521 m

fi[ath,5 l*O racsimiie <603) 474 2887 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

Reference:

Facilit jOperating License NPF-86, Docket No. 50 443

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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Very t our4/ -

th/td/,Yh 8 #,s Ted't Fei um/

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 -

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

R ADOCK 05000443 p pop I

a member of the Northeast Utilities system j p {

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• q North Atlantic a February 12,1993 4

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ENCLOSURE 1 TO NYN-93025 i

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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

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744.0 744.0 55177.0

12. Number Of Hours Reactor Was Critical. 590.7 590.7- 20094.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 , ~ 953.3

14. Hours Generator On-Line 571.6 571.6 18152.5-

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 _a 76.8- 78.0

• 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 ..

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2 U19 10 , , _ ,_ 9,, ,,, ,.

3 1 a 3 _ ,,

_, ,,,,,,, 19 , , , , , , , .

O j 4 , _ 148 20 57 '

5 882 2i ,,,,, 915 ,,,

6 ,,, 1040 22 1lJ,L _ _

7 . , , 1151 23 ,

1153

8. 1153 _,,, ,,,,- -24 1154 9 31.,L3 25 ),JJ $ -

10. Q$,J.,. 26 , , _ _ 1154 _

11 1153 _ 27 _,,_ 1155 12 ,,,, 1153 28 11 M 13 1153 29 1153 14 975- 30 .

1153 15 0 31~ 1153

.16 0 ,, .

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 Date Type3 ' Duration Reason 2 Method of Licensee Cause & Corrective

' No . -

(Bours) Shutting Event . Action to Down Reactor 3 Report i Prevent Recurrence Page 1 of 1 A, G- 2 '93-001 Manual reactor trip due to, loss-93-01~ F 30.9 of' bot ~n main feed water pumps on low section pressure. See LER 93-001 for infertiation and root cause and corrective action.

3 93-003' Automatic reactor trip caused by-93-02 F 141.5 A Turbine trip was turbine trip.

initi,a ted by the e g'nerator breaker opening o. a ground voltage relay. See LER 93-003 for infor: cation on root cause and .

. corrective action.

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Reason: Method Fr Forced 1-Manual 5: Scheduled A-Equipc:ent Failure (Explain)

B-Maintenance'or Test' 2-Manual Screm C-Eefueling 3-Automatic Scram.

D-Regulatory Eestriction 4'-Continued from

..E-Operator Training & License Examination . previous month F-Administrative ~5-Power Reduction 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 *

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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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