B17441, Monthly Operating Rept for Aug 1998 for Millstone Nuclear Power Station,Unit 1.With

Monthly Operating Rept for Aug 1998 for Millstone Nuclear Power Station,Unit 1.With

ML20151V621
Person / Time
Site:	Millstone
Issue date:	08/31/1998
From:	Harkness E, Newburgh G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17441, NUDOCS 9809150035
Download: ML20151V621 (6)

Text

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l Rope Ferry Rd. (Route 156), Waterford, CT 06385

.N h t Nuclear Energy Malstone Nuclear Power Station Northeast Nuclear Energy Company )

P.O. Box 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277

%e Northeast Utilitics System

!> 8 1998

'l Docket No. 50-245 l B17441 l I

U.S. Nuclear Regulatory Commission i Attention: Document Control Desk I Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1  !

Facility Operating License No. DPR-21 l Monthly Operatina Report in accordance with the report requirements of Technical Specification  !

Section 6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report i for the month of August 1998.

Should you have any questions regarding this submittal, please contact Mr. P. J.

Miner at (860) 440-2085.

Very truly yours,  ;

(

NORTHEAST NUCLEAR ENERGY COMPANY

. /f -

E. Harkdeks, Director - Unit Operations ,

Attachments (1) cc: H. J. Miller, Region i Administrator I

S. Dembek, NRC Project Manager, Millstone -Unit No.1 T. A. Eastick, Senior Resident inspector, Millstone Unit No.1 L. L. Wheeler, Senior Project Manager iip ' /

9909150035 990931 E , a,r PDR ADOCK 05000245 R PDRn 0834224 REY,12-95

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, , Docket No. 50-245  !

B17441  :,

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Attachment 1 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report - August 1998 t

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September 1998 i

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.. U.S. Nuclear Regulatory Commission B17441%ttachment 1\Prge 1 REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 1

2. Scheduled date for next refueling outage: Permanentiv ceased oneration and certifications submitted to the NRC in accordance with 10CFR50.82.G

- 3. Scheduled date for restart following refueling: N/A

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

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

N/A

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: N/A

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) 3068 Unconsolidated

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 Caoacity: Maximum 3229 fuel assembiv locations

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

'h B. D. Kenyon letter to U.S. Nuclear Regulatory Commission, " Millstone Nuclear Power Station, Unit No.1, Certification of Permanent Cessation of Power Operations and that Fuel has been Permanently Removed from the Reactor," dated July 21,1998.

U.S. Nuclear R:gul:t:ry C:mmission B17441%ttachment 1\Pzge 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-245  !

UNIT: Millstene Unit 1 DATE: 9/03/98 '

COMPLETED BY: G. Newburah TELEPHONE: (860)444-5730 l MONTH: Auaust 1998 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWa-Net) (MWe-Net) I 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 l 11 0 27 0 0

12 28 0 13 0 29 0 ,

14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS i On this format, list the average daily unit power levelin MWe-Net for each day in the l reporting month. Compute to the nearest whole megawatt.

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- U.S. NucleCr Regulatory Commission  ;

B17441%ttachment 1\Page 3 DOCKET NO.: 50-245  !

UNIT NAME: Millstone Unit 1 DATE: 9/3/98 COMPLETED BY: G. Newburgh TELEPHONE: (860)444-5730 OPERATING STATUS

1. Docket Number 50-245

2. Reporting Period August 1998 Notes: ,

3. Utility Contact G. Newburgh

4. Licensed Thermal Power (MWt): 2011

5. Nameplate Rating (Gross MWe): 662 i

6. Design Electrical Rating (Net MWe): 660

7. Maximum Dependable Capacity (Gross MWe): 670 {

8. Maximum Dependable Capacity (Net MWe): 641 l

9. If Changes Occur in Capacity Ratings (ltems Number 4 Through 8) Since Last Report, Give Reasons:

l N/A

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

11. Reasons For Restrictions, if Any: Permanently ceased operations and certifications submitted to the NRC in accordance with 10CFR50.82 I

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, T.'t: ."Aonth Yr.-To-Date Cumulative l

12. Hours in Reporting Period 744.") 5831.0 242591.0

13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9

14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3

- 15. Hours Generator On-Line 0.0 0.0 166560.7 l

16. Unit Reserve Shutdown Hours 0.0 0.0 93.7 i

17. Gross Thermal Energy Generated (MWF., 0.0 0.0 314372827.0

18. Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0

19. Net Electrical Energy Generated (MWH) -2029.0 -16097.0 101001629.0

20. Unit Service Factor 0.0 0.0 68.7

21. Unit Availability Factor 0.0 0.0 68.7

22. Unit Capacity Factor (Using MDC Net) -0.4 -0.4 63.7

23. . Unit Capacity Factor (Using DER Net) -0.4 -0.4 63.1

24. Unit Forced Outage Rate - 100.0 100.0 21.5

25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Shutdown at time of this report

26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup: Unit has permanently ceased operations

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

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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U.S. Nuclear Regulatory Commission '- .* ,

B17441%ttachment 1\Page 4  ;

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.: 50-245-UNIT NAME: Millstone Unit 1 COMPLETED BY: G. Newburah TELEPHONE. (8601444-5730 REPORT MONTH: August 1998 No. Date Type' Duration Reason *. Met %d of License System Component Cause & Corrective (Hours) . Shutting Event Code' Code' Action to 8

Down Reactor P.eport # Prevent Recurrence i

1 95-10FF 951213 S 744 F 4 N/A 10CFR50.82(a)(1)(il 10CFR50.82(a)(1)(ii)

' 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

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E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - Administrative 6 - Other (Explain) ' IEEE Standard 803A-1983, G - Operational Error (Explain)

• Recommended Practices  !

H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function identifiers * +

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