ML20057B248: Difference between revisions

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| number = ML20057B248
| number = ML20057B248
| issue date = 08/31/1993
| issue date = 08/31/1993
| title = Monthly Operating Rept for Aug 1993 for Seabrook Station, Unit 1.W/930913 Ltr
| title = Monthly Operating Rept for Aug 1993 for Seabrook Station, Unit 1
| author name = Feigenbaum T, Nardone P
| author name = Feigenbaum T, Nardone P
| author affiliation = NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
| author affiliation = NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)

Latest revision as of 21:15, 12 November 2023

Monthly Operating Rept for Aug 1993 for Seabrook Station, Unit 1
ML20057B248
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 08/31/1993
From: Feigenbaum T, Nardone P
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9309200216
Download: ML20057B248 (5)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. Seab k 4H 03874

= Telephone (603)474-9521 y

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jh Facsimile (603)474-2987 Energy Service Corporation Ted C. Feigenbaum Senior Vice President and Chief Nuclear Officer NYN-September 13,1993 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk.

Reference:

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

Subject:

Monthly Operating Report Gentlemen: l Enclosed please find Monthly Operating Report 93-08. This report addresses the operating and shutdown experience relating to Seabrook Station Unit I for the month of August,1993 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours,

, /M Ted C. FeigenbIm Enclosure  ;

TCF:ALUact l cc: Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission ' ,

Region I 1 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NII 03874

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9309500516 930831 PDR ADOCK 05000443 4 d'**'-

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, OPERATING DATA REPORT DOCKET i40. 50 443 UNIT Seabrook 1 DATE 09/13/93 COMPLETED BY P. E. Nardone TELEPHONE (603) 474-9521 Ext. 4074 OPERATING STATUS

1. Unit Name: Seabrook Station Unit 1
2. Reporting Period: AUGUST 1993 ,
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Gross MWe): 1197
5. Design Electrical Rating (Net MWe): 1148
6. Maximum Dependable Capacity (Gross MWe): 1200
7. Maximum Dependable Capacity (Net MWe): 1150
8. If Changes Occur in Capacity Ratings (1tems Number 3 Through 7)

Since Last Report. Give Reasons: Not Apolicable 1

9. Power Level To Which Restricted. If Any: None
10. Reasons for Restrictions. If Any: Not Apolicable This Month Yr.-to-Date Cumulative .
11. Hours in Reporting Period 744.0 5831.0 60264.0  !
12. Number Of Hours Reactor Was Critical 744.0 5583.3 25086.7 ,
13. Reactor Reserve Shutdown Hours 0.0 0.0 953.3  ;
14. Hours Generator On-Line 744.0 5527.5 23108.4
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2537509 18677278 75200835  ;
17. Gross Elec. Energy Generated (MWH) 889305 6550153 26111791 4
18. Net Electrical Energy Generated (MWH) 855929 6300355 25077168-
  • 19. Unit Service Factor 100.0 94.8 81-.7
  • 20. Unit Availability Factor 100.0 94.8 81.7
  • 21. Unit Capacity Factor (Using MDC Net) 100.0- 94.0 78.6
  • 22. Unit Capacity Factor (Using DER Net) 100.2 94.1 78.7
  • 23, Unit Forced Outage Rate. 0.0 5.2 5.5 ,
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

None Scheduled

25. If Shut Down At End Of Report Period. Estimated Date Of Startup: Not Apolicable 'f
  • NOTE: " Cumulative' values based on total hours starting 08/19/90. date Regular full Power Operation began.  !

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-443 UNIT Seabrook 1 i DATE 09/13/93 COMPLETED BY P. E. Nardone TELEPHONE (603) 474-9521 Ext. 4074 i MONTH AUGUST. 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(MWe-Net) (MWe-Net) i 1 1150 17 1152 i

2 1151 18 1151 3 1151 19 1150 4

1151 20 1149 5 1152 21 1150 6 1152 22 1147 7 1151 _ 23 1146 8 1151 24 1147 9 1151 25 1150 10 1151 26 1150  !

11 1152 27 1151 i

, 12 1152 28 1150-13 1152 29 1151 1 14 1151 30 1150 l 15 1151 31 1151 1

16 1150 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. j 2 of 4 - ,

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. _ . _ _ _ . . . _ _ _ _ _ _ _ _ _ . . . _ _ = . _ _ _ . _ - ---_ .- . . _ _ _ . _ . _ _ _ . _ _ _ _ _ _ , _ -..._.. _ __ ~._._ . _ _ _ . . .

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-443 UNIT Seabrook 1 DATE 09/13/93' REPORT MONTH AUGUST. 1993 COMPLETED BY P. E. Nardone TELEPHONE (603) 474-9521

. Ext. 4074 l No. Date Type l Duration Reason? Method of Licensee Cause & Corrective (Hours) Shutting Event Action to Down Reactor 3 Report # Prevent Recurrence Page 1 of I NO ENTRIES FOR THIS MONTH

!' 1 2- 3 i F: Forced Reason: Method.

j. S: Schedulert ' A-Equipment Failure (Explain) 1-Manual  !

r B-Maintenance or Test 2-Manual Scram I C-Refueling 3-Automatic Scram

! .. D-Regulatory Restriction 4-Continued from l E-Operator Training & License Examination previous month

-F-Administrative 5-Power Reduction j G-Operational Error (Explain) .

(Duration - 0)

! H-Other (Explain)~ U 9-Other (Explain) f f

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DOCKET NO. 50-443 UNIT Seabrook 1

-DATE 09/13/93 J COMPLETED BY P. E. Nardone ]

TELEPHONE (603) 474-9521 Ext. 4014 i REFUELING INFORMATION REQUEST

1. Name of facility: Seabrook Unit 1
2. Scheduled date for next refueling shutdown: '

Refueling Outage 3. 03/26/94

3. Scheduled date for restart following refueling:

i Refueling Outage 3. 05/20/94 i

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

No  ;

5. Scheduled date(s) for submitting licensing action and supporting information:

N/A j i

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

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

(a) In Core: 193 (b) 136 l

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 eighteena l month refuelings with full core offload capability.

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

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