ML20094L138

Monthly Operating Rept for Oct 1995 for Seabrook Station Unit 1

ML20094L138
Person / Time
Site:	Seabrook
Issue date:	10/31/1995
From:	Feigenbaum T, Nardone P NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-95093, NUDOCS 9511200067
Download: ML20094L138 (5)

Text

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Nortli.

North Atlantic Energy Service Corporation i

y.o.

,x 300 f(jan(ic Seabrook, NH 03874 I

(603)474-9521, Fax (603)474-2987 4

NYN 95093 The Northeast Utilities System s

November 10,1995 Ted C. Feigenbaum Semor Vice President &

Chief Nuclear Officer

[

United States Nuclear Regulatory Commission Washington, DC 20555-I Attention:

Document Control Desk

References:

Facility Operating License NPF-86, Docket No. 50-443

Subject:

Monthly Operating Report i

Gentlemen:

4 Enclosed please find Monthly Operating Report 95-10. This report addresses the operating and i

shutdown experience relating to Seabrook Station Unit 1 for the month of October,1995 and is i

submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very trul

urs, j

4 07

[A'GP Ted C. Feigenba Enclosure cc:

Mr. Thomas T. Martin i

Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager

[

Project Directorate 1-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 J

Mr. John B. Macdonald NRC Senior Resident Inspector 4

PO Box 1149 Seabrook, NH 03874 l

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'gr 9511200067 951031 PDR ADOCK 05000443 1

R-PDR i

OPERATING DATA REPORT i

DOCKET NO.

50-443 UNIT Seabrooki DATE 11/10/95 COMPLETED BY P.E. Nardone TELEPliONE 603/474-9521 Ext. 4074 QPERATING STA'IUS 1.

Unit Name:

Seabrook Station Unit 1 I

2.

Reporting Period:

OCTOBER 1995 i

3.

Licensed Thermal Power (MW ):

3411 1

4.

Nameplate Rating (Gross MWe):

1197 l

5.

Design Electrical Rating (Net MWe):

1148 I

6.

Maximum Dependable Capacity (Gross MWe):

1200 7.

Maximum Dependable Capacity (Net MWe):

1150 8.

If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Not Applicable l

Report, Give Reasons:

l l

9.

Power Level To Which Restricted, if Any (Net MWe):

Il10MWe 10.

Reasons For Restrictions,if Any:

Final Stage FW lleating capability lost for remainder of Cycle. Throtding Reheat Steam to MSR's to improve Unit Efficiency.

This Month Yr-to-Date Cumulative 11.

Ilours in Reporting Period 745.0 72 %.0 79249.0 12.

Number of flours Reactor Was Critical 745.0 7045.6 40312.6 13.

Reactor Reserve Shutdown llours 0.0 0.0 953.3 14.

Ilours Generator On-Line 745.0 6902.9 38047.1 15.

Unit Reserve Shutdown liours 0.0 0.0 0.0 16.

Gross Thermal Energy Generated (MWH) 2540835 23564545 125401354 17.

Gross Elec. Energy Generated (MWII) 862894 8133318 43557652 18.

Net Electrical Energy Generated (MWII) 828611 7818253 41845369

• 19.

Unit Service Factor 100.0 94.6 80.5

• 20.

Unit Availability Factor 100.0 94.6 80.5

• 21.

Unit Capacity Factor (Using MDC Neo 96 7 93.2 77.8

• 22.

Unit Capacity Factor (Using DER Nc0 96 9 93.3 78.0

• 23.

Unit Forced Outage Rate 0.0 5.4 6.5 24.

Shutdowns Scheduled Over Next 6 Months (Typ3 Date.

Refueling, 11/04/95,36 Days and Duration of Each):

25.

If Shut Down At End Of Report Period. Estimated Date of Not Applicable Startup:

• NOTE: " Cumulative" values based on total hours starting 8/19/90. date Regular Full Power Operation began.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-443 UNIT Seabrook 1 DATE 11/10/95 COMPLETED BY P.E. Nardone TELEPiiONE 603/474-9521 Ext. 4074 MONTil: OCTOBER 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1111 17 1113 2

1111 18 1113 3

1111 19 1113 4

till 20 1113 5

1110 21 1!!3 6

1110 22 1113 7

1111 23 1!!4 8

1110 24 1114 9

till 25 1114 10 1111 26 1114 11 1112 27 1113 12 1112 28 1114 13 IIll 29 1114 14 1112 30 1114 15 1112 31 1114 16 1112 l

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50443 UNIT Seabrook i DATE 11/10/95 COMPLETED BY P.E. Nardone TELEPIIONE 603/474-9521 Ext. 4074 REPORT MONT11 OCTORFR 1995 NO.

DATE TYPE' DURATION REASON:

METIIOD OF SIIUITING LICENSEE EVENT CAUSE & CORRECTIVE ACTION TO PREVENT (IIOURS)

DOWN REACTOR' REPORT #

RECURRENCE PageI ofI No enries for stus mondL l

a 3

F: Forced Reason.

Methmi:

S: Scheduled A - Equipment Failure (Explain) 1 - Mamal B

u=i=*=~a or Test 2 - Mumal Scram C - Refuelmg 3 - Automatic Scram D - Regulatory Restriction 4 - Contmued from previous month E - Operator Trainmg & License F==ia*=

5 - Power Reduction (Duration = 0)

F-Admuustrauve 9 - Odwr (Explam)

G - Operanonal Error (Explain)

H - Other (Explain) e 3of4 9

REFUELING INFORMATION REQUEST DOCKET NO.

50-443 UNIT Seabrook 1 DATE lt/10/95 COMPLETED BY P.E. Nardone TELEPIIONE 603/474-9521 Ext. 4074 1.

Name of Facility:

Seabrook Unit 1 2.

Scheduled date for next refueling shutdown:

Refueling Outage 4,11/04/95 3.

Scheduled date for restart following refueling: Refueling Outage 4,12/09/95 l

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes, revisions to Technical Specifications for Main Steam Safety Valve setpoints, Pressure Isolation Valves, Feedwater Isolation and RCS Temperature for oxygen control will be required.

5.

Schedule date(s) for submitting licensing action and supporting information:

License Amendment 43 for Main Steam Safety Valves setpoints has been issued. Other Technical Specification changes are in NRC review.

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:

Implementation of Amendment #33 to Facility Operating License Wide Band Operation.

7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

(a)In Core:

193 (b) 265*

• Fuel receipt in progress, i

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.

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 two annual and twelve eighteen-month refuelings with full core offload capability.

The current licensed capacity is adequate until at least the year 2010.

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