ML20056H087

Monthly Operating Rept for Aug 1993 for Millstone Unit 2

ML20056H087
Person / Time
Site:	Millstone
Issue date:	08/31/1993
From:	Doboe S, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-703, NUDOCS 9309080210
Download: ML20056H087 (5)

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l September 2, 1993 MP-93-703 i 1

Re: 10CFR50.71(a) J U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Reference:

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

Dear Sir:

i This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 for the month of August 1993, in accordance with Appendix A Technical Specifications, Section 6.9.1.6. One I additional copy of the report is enclosed.  ;

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY -

/ aw A tephe E. Scace Vice President - Millstone Station 1

SES/sid cc: T. T. Martin, Region I Administrator G. S. Vissing, h7C Project Manager, Millstone Unit No. 2 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1,2&3 j l l i

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93090B0210 930831 P I PDR ADOCK 05000336 h.. V i R PDR Q l os34u nrv 4-BS I

l AVERAGE DAILY UNIT POWER LEVEL r

i DOCKET NO. 50-336  !

UNIT Millstone Unit 2  !

DATE 9/02/93 l l COMPLETED BY S. Doboe  !

! TELEPHONE __ (203) 447-1791 l l

EXT 4678 l t

i MONTH: AUGUST 1993 l i

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 870 17 865 2 869 18 866  ;

3 869 19 806 [

4 865 20 866  !

5 549 21 866 6 0 22 867 i 7 0 23 865 8 0 24 865 9 0 25 865 i 10 0 26 864 [

11 0 27 860 l 12 0 28 865 i 13 0 29 866' l

l 14 0 30 865 l l

15 34 31 861 16 785 l

I INSTRUCTIONS l 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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- l OPERATING DATA REPORT 7

t UNIT NAME Millstone Unit 2 r DATE 9/02/93  !

COMPLETED BY S. Doboe [

TELEPHONE (203) 447-1791 {

EXT 4678  !

I OPERATING STATUS '

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1. Docket Number 50-336 i

2. Reporting Period August 1993 Notes: ltems 22 and 23 i

3. Utility Contad S.Doboe cumulative are weighted j

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

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

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: l N/A i l

10. Power t.evel To Which Restricted, if any (Net MWe): N/A f

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

12. Hours in Reporting Period 744.0 5831 155015.0 i 13 Number Of Hours Reactor Was Critical 570.6 5349.9 110607.5  :

l 14. Reactor Reserv6 Shutdown Hours 0.0 0.0 2205.5 ,

15. Hours Generator On-Line 503.0 5157.2 105514.6

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2. j

17. Gross Thermal Erlergy Generated (MWH) 1347720.0 13520068.0 271501772.4 *

18. Gross Electrical Energy Generated (MWH) 444198.0 4509896.0 88914203.5

19. Net Electrical Energy Generated (MWH) 424810.0 4339848.0 85290724.3  !

20. Unit Service Factor 67.6 88.4 68.1  ;

21. Unit Availability Factor 67.6 -

88.4 68.4 ,

22. Unit Capacity Factor (Using MDC Net) 65.4 85.2 64.5

33. Unit Capacity Factor (Using DER Net) 65.6 85.5 63.4 l

24. Unit Forced Outage Rate . 32.4 6.6 15.0- ,

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

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

27. Units in Test Status (Prior to Commercial Operation): I Forecast ' Acheived  !

l INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A 1

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336 UNIT NAME Millstone Unit 2_ .

DATE 9/02/93 COMPLETED BY _SmDoboe TELEPHONE _(203) 447-1Z.9,1 REPORT MONTH _A_UGUST 1923 EXT 4678 No. Date Type' Duration Reason 2 Method of License System Component Cause & Corrective (Hours) Shutting Event Coded Code 5 Action to Down Reactor a Report # Prevent Recurrence 7 930805 F 241 A 1 93-018 CB ISV On 8/5/93 at 1554 the main generator was taken out of service and the reactor was shutdown due to a Reactor Coolant System leakrate of greater than 1 gpm. The leak was due to a failure of a letdown isolation valve. The valve was replaced. The reactor was restarted on 8/12/93 at 1247.

The reactor automatically tripped on 8/12/93 at 1344 due to low steam generator level (See LER 93-019). The main generator was retumed to service 8/15/93 at 1652. The unit retumed to 100% power on 8/16/93.

1 F: Forced 2 Reason 3 Method 4 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 Related Facilities" E -Operator Training & License Examination Previous Month F -Administrative 5 -Power Reduction 5 IEEE Standard 803A-1983, G -Operational Error (Explain) (Duration - 0) " Recommended Practices H -Other (Explain) 6 -Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

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- REFUELING INFORMATION REOUEST l I

1. Name of facility: Millstone 2 l, l

2. Scheduled date for next refueling shutdown: June 1994 l

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

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

None at this time

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

l None at this time ,

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:

l None l

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

In Core: (a) 217 In Spent Fuel Pool: (b) 784 f NOTE: The;.e numbers represent the total Fuel Assemblies and Consol-idated Fuel S*orace 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 planned, in number of fuel assemblies:

Currently 1237. A license amendment has been submitted to the NRC to increase the spent fuel pool storace capacity to 1306 storace locations.

9. The projected date of the last refueling that can be discharged to

the spent fuel pool assuming the present licensed capacity.

l 1994. Soent Fuel Pool Full. Core Off Load capacity is reached.

1998. Core Full. Spent Fuel Pool Full.

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