ML20064H584

Monthly Operating Rept for Feb 1994 for Millstone 2

ML20064H584
Person / Time
Site:	Millstone
Issue date:	02/28/1994
From:	Doboe S, Miller D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-94-164, NUDOCS 9403180073
Download: ML20064H584 (5)

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NORTHEAST UTILITIES cenerei Omc . . seicen sireei. Bernn. Conn ci,cui l .N[=.

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w **r. c'"* P.O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 k E J $r) ([,3)$ $C7d (203) 665-5000 DONALD B. MILLER, Jr.

SENIOR VICEPRESIDENT- MILLSTONE NGECh IN* 109N MP-94-164 Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336

Dear Sir:

This letter is. forwarded.to provide the report of operating and shutdown experience relating to Millstone Unit 2 for the month of February 1994, in accordance with

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Appendix- A Technical Specifications, Section 6.9.1.6. One additional copy'.of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENER Y COMPANY

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D.' B. Miller, -Jr'.

Senior Vice President - Millstone Station 1

DBM/std cc: ' T, T. Marti_n, Region I Administrator G. S. Vissing, NRC Projec't Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.'1, 2 &'3 L IL 9403180073.940228

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osaw sty ice . PDR ADOCK 05000336 'V R PDR 'L

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' AVERAGE DAILY UNIT POWER LEVEL  ;

DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 3/03/94 COMPLETED BY S. Doboe TELEPHONE (2031 447-1791 EXT 4678 MONTH: FEBRUARY 1994 DAY AVG, DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 875 17 877

, 2 876 18 808 3 875 19 864 4 875 20 875 5 876 21 876 6 876 22 876 7 _

875 23 874 8 874 24 875 9 874 25 875 '

10 874 26 874 11 875 27 874 12 876 28 875 13 876 29 --

14 876 30 ---

15 876 31 ---

16 877 INSTRUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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• e OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE 3/03/94 COMPLETED BY S.Doboe TELEPHONE (203)447 1791 EXT 4678 OPERATING STATUS

1. Docket Number 50 336

2. Reporting Period February 1994 Notes: Items 22 and 23

3. Utility Contact S.Doboe cumulative are weighted

4. Licensed Thermal Power (MWt): 2700 averages. Unit operated

5. Nameplate Rating (Gross MWe): 909 at 2560 MWTH prior to its

6. Design Electrical Rating (Net MWe): 870 uprating to the current

7. Maximum Dependable Capacity (Gross MWe): 903.10 2700 MWTH power level.

8. Maximum Dependable Capacity (Net MWe): 873.10

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): N/A

11. Reasons For Restrictions, if Any: N/A This Month Yr. To-Date Cumulative

12. Hours in Reporting Period 672.0 1416.0 159360.0_

13 Number Of Hours Reactor Was Critical 672.0 1416.0 114363.0

14. Reactor Reserve Shutdown Hours 0.0 - 0.0 2205.5

15. Hours Generator On Line 672.0 -1416.0 109230.7

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2-

17. Gross Thermal Energy Generated (MWH) 1808654.0 3795698.0 281395851.4

18. Gross Electrical Energy Generated (MWH) 607249.5 12737261 92225715.5

19. Net Electrical Energy Generated (MWH) 586254.5 1229688.5 88476476.3-

20. Unit Service Factor 100.0 100.0 68.5

21. Unit Availability Factor 100.0 100.0 68.8

22. Unit Capacity Factor (Using MDC Net) 99.9 99.5 65.0

- 23. Unit Capacity Factor (Using DER Net) 100.3 99.8 64.0-24 Unit Forced Outage Rate 0.0 0.0 15.0

25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None

26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup: N/A

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 l

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. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336  !

UNIT NAME Millstone Unit DATE 3/03/94 COMPLETED BY S. Doboe TELEPHONE (203)-447-1791  !

EXT 4678 '

REPORT MONTH: February 1994 No. Date Type' Duration Reason 2 Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code' Action to Down Reactor' Report # Prevent Recurrence 94-01 940218 F 0 A 4 N/A N/A N/A On 2/18/94 at 1406 a reactor downpower commenced due to degraded synchronizing circuits on two inverters.

During the downpower the  ;

affected circuits were repaired and the power reduction was stopped at approximately 66% power.

Power ascension was started and the unit reached 100% power at 0425 on 2/19/94 1

d 2

' 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 Reduction (Duration = 0) 5 F - Administrative 6 - Other (Explair) 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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l REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 2

2. Scheduled date for next refueling outage: July 1994 ~ j

3. Scheduled date for restart following refueling: October 1994

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? l Yes. License amendment changes are beina souaht for Enainneeed Safety i Actuation System chanaes. to take advantaae of Batterv Charaer flexabilitv. I Boron Dilution Accident Analvsis assumotion changes. and Generic Letter 90-06.

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

Aoril 1994.

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:

Same fuel sucolier, imoroved new fuel assembiv desian oursuant to 10CFR50.59.

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

In Core: (a) 212 In Spent Fuel Pool: (b) 2fL4 NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storage Boxes (3 total containing 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 planned, in number of fuel assemblies:

A license ammendment has been recentiv aooroved bv the NRC to increase the scent fuel cool storaae cana_ city to 1306 storaae locations.

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

1994. Soent Fuel Pool Full. Core offload caoacity is reached.

1998. Core Full Soent Fuel Pool Full.

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