ML20067B122

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Monthly Operating Rept for Jan 1994 for Seabrook Station Unit 2
ML20067B122
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 01/31/1994
From: Feigenbaum T, Nardone P
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-94014, NUDOCS 9402230245
Download: ML20067B122 (5)


Text

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f P.O. Box 300 Odi =

seabroox. "" 03874 Telephone (603)474-9521 j

Jh Energy Service Corporation

( Facsimile (603)474 2987 Ted C. Feigenbaum Senior Vice President and Chief Nuclear Officer NYN- 94014 February 15,1994 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

References:

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

Subject:

Monthly Operating Report Gentlemen:

Enclosed please find Monthly Operating Report 94-01. This report addresses the operating and shutdown experience relating to Seabrook Station Unit I for the month of January,1994 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

i Very tr j yours,

\ W/ pg &V i

Ted C. Fe . aum l 1

TCF:ALL/sm Enclosure cc: Mr. Thomas T. Martin Regional Administrator .

United States Nuclear Regulatory Commission  !

Region 1 475 Allendale Road )

King of Prussia, PA 19406 I l

Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate 1-4 Division of Reactor Projects l U.S. Nuclear Regulatory Commission Washington, DC 20555 l l

Mr. Antone C. Cerne NRC Senior Resident inspector P.O. Box 1149 Seabrook, Nil 03874 l

i y 'tember of the Northeast Utilities system 9402230245 940131 PDR ADOCK 05000443 3

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o OPERATING DATA REPORT l l

l DOCKET NO. 50-443 UNIT Seabrook 1 l DATE 02/15/94 COMPLETED BY P. F. Nardone i TELEPHONE (603) 474-9521 Ext. 40/4 l i

OPERATING STATUS

1. Unit Name: Seabrook Station Unit 1
2. Reporting Period: JANUARY 1994
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Gross MWe): 1197
5. Design Electrical Rating (Net MWe): 1148 l
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) l i

Since Last Report. Give Reasons: Not Acolicable '

9. Power Level Tu Which Restricted, If Any: None
10. Reasons For Restrictions. If Any: Not Acolicable i This Month Yr.-to-Date Cumulative ,
11. Hours In Reporting Period 744,0 744.0 63937.0 -
12. Number Of Hours Reactor Was Critical 585 6 585.6 28292.7
13. Reactor Reserve Shutdown Hours 0.0 0.0 953 T
14. Hours Generator On-Line 585.6 585.6 26262.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1997765 1997765 85430211
17. Gross Elec. Energy Generated (MWH) 69/064 697064 29670807'
18. Net Electrical Energy Generated (MWH) 670087 670087 28493705 '
  • 19. Unit Service Factor 78.7 78.7 82.2
  • 20. Unit Availability Factor 78.7 78./ 82 2
  • 21. Unit Capacity Factor (Using MDC Net) 78.3 78.3 78 9
  • 22. Unit Capacity Factor (Using DER Net) 78.5 78.5 79.0
  • 23. Unit Forced Outage Rate 21.3 21.3 6.7
24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):

REFUELING. 03/26/94. 57 DAYS

25. If Shut Down At End Of Report Period. Estimated Date Of Startup: Feb. 12. 1994
  • NOTE: " Cumulative" values based on total hours starting 08/19/90. date Regular 4 Full Power Operation began. i i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-443 UNIT Seabrook 1 DATE 02/15/94

. COMPLETED BY P. F. Nardone TELEPHONE (603) 474-9521 r Ext. 40/4 MONTH . 1ANUARY. 1994  ;

i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)-

1 1131 17 1145 2 1144 18 1145 3 1145 19 1144 4 1146 20 1145 5 1146 21 1145 l

6 1145 22 1144 7 1145 23 1144

]

8 1143 24 1145- ,

l 9 1145 25 456 l l

10 1145 26 0 l

11 1145 27 0 12 1146 28 0 13 1146 29 0 14 1146 30 0 15 1145 31 0 16 1144 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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I I UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-443 ".

UNIT Seabrook 1 DATE 02/15/94 - '

i REPORT MONTH JANUARY. 1994 COMPLETED BY P.E. Nardone TELEPHONE (603) 474-9521 ,

. Ext. 40/4 i No. Date Type' Duration Reason' Method of Licensee Cause & Corrective (Hours) Shutting 3

Event Action to '

Down Reactor Report-# Prevent Recurrence Page 1 of 1 i

94-01 01/25/94 F 158.4 B/A 3 94-001 Automatic trip as a result of decreasing level in SG A This was caused by the slow full closure of MSIV A during the performance of the quarterly 10% partial stroke test.

See LER 94-001 for information on root cause and corrective action.

$ 1 2 3 i' F: Forced Reason: Method:

3 S: Scheduled A-Equipment Failure (Explain) 1-Manual ,

B-Maintenance or Test 2-Manual Scram
C-Refueling 3-Automatic Scram i D-Regulatory Restriction 4-Continued from .

[ E-Operator Training & License Examination previous month '

F-Administrative .

5-Power Reduction l G-Operational Error (Explain) (Duration - 0) .

1 H-Other (Explain) 9-Other-(Explain)  !

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j DOCKET NO. 50 d43 i'

UNIT Seabrook i DATE 02/15/94 l COMPLETED BY P. -t. Nardone

! TELEPHONE (603) 4/4-95?1

Ext 4074 l REFUELING INFORMATION RE0 VEST l

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

Refueling Outage 3. 03/26/94 l

} 3. Scheduled date for restart following refueling:

Refueling Outage 3. 05/21/94 I
4. Will refueling or resumption of operation thereafter require a technical spec 1fication change or other license amendment'?

No a

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

information

)

4 N/A

6. Important licensing considerations associated with refueling, e.g.,

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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 assemb'ies (a) in the core and (b) in the spent fuel storage pool:

(a) In Core
193 (b) 136

) 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:

i i Present licensed capacity: 1236 No increase in storage capacity requested or planned.

9. The projected date of the last refueling that can be discharged tu 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 of fload capability. '

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

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