ML20077Q259

Monthly Operating Rept for Jul 1991 for Seabrook Station Unit 1

ML20077Q259
Person / Time
Site:	Seabrook
Issue date:	07/31/1991
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-91124, NUDOCS 9108210146
Download: ML20077Q259 (7)

Text

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I New Hampshire Y e' #

Ted C. Feigenbovm President and Chief Executive Of ficer NYN- 91124 August 14, 1991 United States Nuclear Regulatory Commis.sion Washington, DC 20555 Attention: Document Control r)esk

Reference:

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

Subject:

Monthly Operating Report Gentlemen:

Enclosed please find Monthly Operating Report 91-07. This report addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of J uly, 1991 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours, f f # J' Ted C. Fei, nbaum Enclosure (s)

TCF:WJT/ tad cc: Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commissioe Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senio Resident Inspector P.O. Box 1149 Seabrook, NH 03874 9108210146 >10731 PDR ADOCK O'3000441 R PDR

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,. Q New Hampshire Yankee Division of Public Service Company of New Hampshire

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J- ;1g P.O. Box 300 = Seabrook, NH 03874 = Telephone (603) 474-9521 iI

• • New llampshire Yankee

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OPERATING DATA REPORT

'. DOCKET NO. 50-443 UNIT Seabrook 1 DATE 08/34/91 COMPLETED BY P. Hy done TELEPHONE (603) 474 9521 (Ext. 4074)

OPERATING STATUS

1. Unit Name: Seabrook Station Unit 1

2. keporting Period: JULY 1991

3. Licensed Thermal Power (MWt): 3411

4. Nameplate Rating (Gross HWe): 1197

5. Design Electrical Rating (Net MWe): 1148

6. Maximum Dependable Capacity-(Cross MWe): 1200

7. Maximum Dependable Capscity (Net MWe) . . 1150

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons: Not Applicable .

9. Power Level To Which Restricted, If Anys: None .

10. Reasons For Restrictions. If Any: Not Ano11 cable This Month Yr. to-Date Cumulative

11. Hours In Reporting Period 744,0 5087.0__ 41976t0

12. Number Of !!ours Reactor Was Critical 530.1 4650.1 10369.4

13.-Reactor Reserve Shutdown !!ours o q__ 0.0 953.3

14. Hours Generator On-Line 513.9 4575.6 _ _ _ 8703.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HWH) 1642082 14687730 _27288055

17. Gross Elec. Energy Generated (MWH) 56974P 5107161 9379078 18 Het Electrical Energy Generated (HWH) 548318 4904131 8998129

• 19. Unit Service Factor _ 69.1 89.9 88.2 L *20.' Unit AvaA1 ability Factor 69.1 89.9' 88.2-

• 21. Unit Capacity Factor (Using MDC Net) 64.1 83.8 83.3

• 22. Unit Capacity Factor (Using DER Net). 64.2 84.0 83.4 L *23. Unit Forced Outage Rate 17.6 7.9 10.5 24; Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

REFUELING. 07/27/91. 67 DAYS _

- 25. If Shut Down At End Of Report Period. Eitimated Date of Startup: 09/30/91

• NOTE' ' Values based on accumulated hours starting 08/19/90, date Regular Full Power Operation began.

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AVERAGE DAILY UNIT POWER LEVEL i .

DOCKET NO. 50-441 UNIT Seabreok 1 DATE 08/14/01 COMPLETED BY P. Nnrdone TELEPHONE (603) 474-9521 (Ext. 4074)

MONTH ,_ JULY. 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (1Ne - Ne t )

1 _

9M 16 1145 2 1145 17 1144 3 1145 18 1146 4 401 19 1149 5 0 20 1150 6 0 21 1150 7 89 _

22 1150 8 282 23 1149 9 915 24 1149 10 1149 25 662 11 1150 26 0 12 1150 27 0 13 1149 28 0 14 1149 29 0 13 1348 30 0 31 0 INSTRUCTIONS On this f ormat, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whcle negawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-443 UNIT Seabrock I i DATE OS/14/91'

REPORT MONTH ' JULY. 1991 COMPLETED BY P. Nardone

TELEPHONE 1603) 474-9521 (Ext. 4074)

No. Date Type i Duration . Reason' Method of Licensee Cause & Corrective

. (Hours) Shutting Event Action to i Down Reactor 3 Report f Prevent Recurrence Page 1 of 2 l 91-06 07/04/91 F 77.7 A. 3 91-009 Low flow in reactor coolant system loop 3 caused an auto-matic reactor / turbine trip. See LER 91-009 for information on

! root cause and corrective action.

l 91-07 07/25/91 F 32.4 A 91-010 Reactor coolant system unidenti-

j. fled leakage exceeded 1.0 g;m

l. which required a manual plant i shutdown. .iee LER 91-010 for

l. information on root cause and

corrective action.

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F: Forced Reason: Method:

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Scheduled A-Equipment Failure (Explain) 1-Manesi B-Maintenance or Test 2-Manual Scram l C-Refueling 3-Automatic Scram l D-Regulatory Restriction 4-Continued from j E-Operator Training & License Examination previous month l F-Administrative 5-Fower Reduction G-Operational Error (Explain) (Duration - O}

H-Other (Explain) 9-Other (Explain) l l' 3 of 5 i

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UNIT SHUTDOWNS AND POWER EEDUCTIONS DOCKET NO. 50-403 '

UNIT Seabrock 1 l DATE 08/14/91' .

REFCRT MONTH JULY. 1991 COMPLETED BY F. Nardene TELEPHONE (603) 474-9521 (Ext. 4074) 4 No. Date Type! Duration Reason.2 Method of Licensee. Cause & Corrective

, (Hours) Shutting Event Action to l Down Reactor 3 Report i . Prevent Recurrence Page 2 of 2 i

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! 91-08 07/27/91- S' 120 C. 9 N/A Start of scheduled refueling j outage following manual shut-down on 07/25/91.

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DOCKET NO.- 50-443 i UNIT Seabrook 3 1

.. DATE ,_ 08/14/91 t

• - COMPLETED BY P. Hardone

. TELEPHONE (603) 474-9521  :

(Ext. 4074) l REFUELING _INFORMATION REQUEST l

1. Name of facility: Seabrook Unit 1 ,

2. Scheduled date for next refueling shutdown: 07/27/91 actual 07/25/91

3. Scheduled date for restart following refueling: 09/30/91

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

I Hone 5

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

1 None +

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

new or different fuel design ur supplier, unreviewed design or .

performance analysis methods, significant changes in fuel design,  ;

new operating procedures t None  ;

-7. The number of fuel assemblies-(a) in the core and (b) in the spent ,

fuel storage pools (a) 'In Core: 193 (b) 60 (new) l

8. The present licensed spent fuel pool storage capacity and the size of I 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, i.

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

L Licensed capacity of 1236 fuel assemblies based on sixteen l

annual refuell.1gs and full core offload capability.

1 The current licensed capacity is adequate until ct least the

[ year 2007.

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