B17576, Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 2.With

Monthly Operating Rept for Nov 1998 for Millstone Nuclear Power Station,Unit 2.With

ML20197K211
Person / Time
Site:	Millstone
Issue date:	11/30/1998
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17576, NUDOCS 9812160120
Download: ML20197K211 (6)

Text

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Nodead R pe Ferry Rd. (Route 156), Waterford, Cr 06385 Nuclear En:rgy matoo. Noacar Po.e, station i

Northeast Nuclear Energy Company

! P.O. Box 128

• Waterford, CT 06385-0128 (860) 447-1791 l

Fax (860) 444-4277 The Northeast Utihties System DEC 91998 Docket No. 50-336 ,

B17576 Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 l

Millstone Nuclear Power Station, Unit No. 2 i Facility Operating License No DPR-65 Monthlv Operatina Report in accordance with the reporting requirements of Technical Specification Section 6.91.7 for Millstone Unit No. 2, enclosed, in Attachment 1, is the monthly operating j' repur t for the month of November 1998.

There are no regulatory commitments contained within this letter, j 1

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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J.A.Vrice kf 1

Dirytor, Millstone Unit No. 2 h ok* [

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cc: H. J. Miller, Region i Administrator /

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D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 I E.V. Imbro, Director, Millstone ICAVP inspections S. Dembek, NRC Project Manager, Millstone Unit No. 2 083422.$ REY.12-95

Docket No. 50-336 B17576 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 Monthly Operating Report l'

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December 1998

. U.S. Nuclear Regulakwy Commission l .* B17576%ttachment 1Page 1 AVERAGE DAILY UNIT POWER LEVEL i DOCKET NO: 50-336 UNIT: Millstone Unit 2 DATE: 12/01/98 l COMPLETED BY: S. Stark l TELEPHONE: (860) 447-1791 l i

EXT: 4419 MONTil: Novemtw 1998 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0- 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 -

16 0 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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. U.S. Nuclear Regulatory Commission

.'~ B17576%Itachment 1Page 2 I

OPERATING DATA REPORT UNIT NAME: Millstone Unit 2 e

! DATE: 12/01/98 \

l COMPLETED BY: S. Stark '

TELEPHONE: (880)447 1791 EXT: 4419 OPERATING STATUS

1. Docket Number 50-336 l 2. Reporting Period November 1998 Notes: Items 22 and 23 I 3. Udlity Contact S. Stark cumulative are weighted l 4. Licensed Thermal Power (MWt): 2700 averagas. Unit operated at l 5. Nameplate Rating (Gross MWe): 909 2560 MWTH prior to its

6. Design Electrica! Rating INet MWe): 870 uprating to its current

7. Maximum Depondable Capacity (Gross MWe): 901.63 2700 MWTH power level.

! 8. Maximum Dependable Capacity (Net MWe): 870.63

9. If Changes Occur in Capacity Ratings (items Number 4 Through 8) Since Last Report,

! Give Reasons:

N/A

10. Power Level To Which Restricted, if any (Net MWe): 0

11. Reasons For Restrictions,if Any: NRC Category lli Facility; NRC Confirmatory Order requiring implementation of an independent corrective action verification program; NRC order requiring a third-party review j of the employee concerns program at Millstone 2; design basis verification response pursuant to 10CFR50.54(fl.

l This Month Yr.-To-Date Cumulative l' 12. Hours in Reporting Period 720.0 8016.0 201024.0

13. Number Of Hours Reactor Was Critical 0.0 0.0 121911.7

14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 0.0 0.0 116611.9

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 300862506.4 i 18. Gross Electrical Energy Generated (MWH) 0.0 0.0 98709460.0 l I

19. Net Electrical Energy Generated (MWH) -1665.7 19348.6 94599741.6

20. Unit Service Factor 0.0 0.0 58.0

21. Unit Availability Factor 0.0 0.0 58.2

22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 54.9

23. Unit Capacity Factor (Using DER Net) 0.0 0.0 54.2

24. Unit Forced Outage Rate 100.0 100.0 27.7 l . 25. St.utdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Shutdown at the time of this report

26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup

To be determined

27. Units in Test Status (Prior to Commercial Operation):

l Forecast Achieved i INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l'

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U.S. Metaar Regulatory Commason B17576%ttachment 1Page 3- ,

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-336 -

UNIT NAME: Mdistone Unit 2.

DATE: 12/01/98 COMPLETED BY: S. Stark .

TELEPHONE: (8601447-1791 EXT: 4419.

REPORT MONTH: November 1998 No. Date Type' Duration Reason Method of License System Component Cause & Correctwe (Hours) Shuttmg Event Code' Code' Action to Down Reactor' Report # Prevent Recummce 98-01 03/07/96 S/F 720 B/D 4 N/A N/A N/A Scheduled: Contmuod mid cycle .

survedlance testeg from previous month.

Forced: Contmuod from previous month. NRC Category lit facility NRC Confirmatory Order requmns independent

) corrective action verification:

NRC order requmng third party review of Millstone Station employee concems program; design basis verification for response to NRC pursuant to 10CFR50.54(f).

'F: Forced ' Reason ' Method 'IEEE Standard 805-1984 S: Scheduled A - Equipment Failure (Explain) 1 - Manual

• Recommended Practices

. B - Maintenance or Test 2 - Manual Scram for System identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities

• E - Operator Training & License Examination 5 - Power Peduction (Duration = 01 F - Administrative 6 - Other (Explain) 'IEEE Standard 803A-1983,

[ G - Operational Bror (Explain)

• Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function identifiers

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+ . U.S. Nudear Regulatory Commission

.' B17576%Itachment 1Pa0e 4 REFUELING INFORMATION REQUEST

{

1. Name of the facility: Millstone Unit 2 l 2. Scheduled date for next refueling outage: Second Quarter of 2000 l 3. Scheduled date for restart following refue!;ng: First Quarter of 1999 (Note -

The current shutdown is not a refuelina outaae. This date reoresents the (

exnected startuo date from the current shutdown.)

)

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

Yes. There are 29 Technical Snacification Chanae Reauests or license amendments which are reouired to be nooroved by the NRC orior to startuo. As of November 30. 1998, 23 reauests have been sent to the NRC.12 have been anoroved, and 12 have been imolemented. The 6 remainina chanoes to be submitted are: 1) Boron Precinitation Hot Lea Iniection USQ 2) Cable Trav Seoaration - USQ 3) l Loss of Normal Feed - USQ and SG Water level Reactor Trio T.S. 4) Hydroaen Purae '

- USQ 5) ECCS Pumo IST - Flow T.S.. and 6) EBFS Bvoass Leakaae T.S..

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

January 25,1999 l 1

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: Small Break LOCA analysis chanaes and Laroe Break LOCA analvsis chanaes.

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

In Core: (a) Q. In Spent Fuel Pool: (b) 1085 NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storaas Boxes (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.

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 nlanned, in number of fuel assemblies:

Present storaae canacity

1306 storaae locations

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

2002. Soont Fuel Pool Full Core offload caoacity is reached.

i _2QQS Core Full. Soent Fuel Pool Full.

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