ML20024F009

Monthly Operating Rept for Jul 1983

ML20024F009
Person / Time
Site:	Millstone
Issue date:	08/15/1983
From:	Gibson J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20024F006	List: ML20024F005 ML20024F009 ML20024F010 ML20024F012
References
NUDOCS 8309080110
Download: ML20024F009 (6)

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OPERATING DATA REPORT DOCKET NO. 50-336 DATE 8/15/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS

1. Unit Name: Millstone 2 Notes: Items 21 and 22 cumulative

2. Reporting Period: July 1983 are weighted ave. unit

3. Licensed Thermal Power (MWt): 2700 operated at 2560 MW

4. Nameplate Rating (Gross MWe): 909 thermal prior to its

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

6. Maximum Dependable Capacity (Gross MWe): 895 2700 MW thermal power

7. Maximum Dependable Capacity (Net MWe): 864 level.

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

Since Last Report, Give Reasons:

N/A

9. Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 5087 66599

12. Number Of Hours Reactor Was Critical 0 3130.5 48365.3

13. Reactor Reserve Shutdown Hours 0 0 2205.5

14. Hours Generator On-Line 0 2994.9 46182.2

15. Unit Reserve Shutdown Hours 0 0 468.2

16. Gross Thermal Energy Generated (MWH) 0 7877464 13171669

17. Gross Elec. Energy Generated (MWH) 0 2575530 37806378

18. Net Electrical Energy Generated (MWH) (-2914.9) 2468443.4 36230256

19. Unit Service Factor 0 58.9 69.3

20. Unit Availability Factor 0 58.9 70.0

21. Unit Capacity Factor (Using MDC Net) 0 56.2 65.0

22. Unit Capacity Factor (Using DER Net) 0 55.8 64.2

23. Unit Forced Outage Rate 0 13.7 19.1

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

Continuation of Refuel / Maintenance Outage

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. -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 8309000110 830815 PDR ADOCK 05000336 R PDR

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 8/15/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH July 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE 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 0 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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DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 8/15/83 COMPLETED BY J. Gibson i REPORT MONTH JULY TELEPHONE (203) 447-1791 Ext. 4431 t

1 2 No. Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective  ;

(Hours) Shutting Event Code Code Action to 3

Down Reactor Report # Prevent Recurrence

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5 830528 S 744 C 1 N/A N/A N/A Continuation of j refuel and maintenance 4 outage from previous month, i

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Docket No. 50-336 Date 8/15/83 Unit Name Millstone 2 Completed By J. Gibson

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Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH July DATE SYSTEM COMPONENT MAINTENANCE ACTION 7/4/83 Reactor Building Closed 'B' Heat Exchanger Installed 62 plugs Cooling Water 7/7/83 Reactor Building Closed 'C' RBCCW Pump Replace seal Cooling Water 7/6/83 Control Element Drive CEDM Ball Seats Replaced all ball seats 7/6/83 CVCS 2-CH-207 Replace bonnet gasket 7/12/83 Main Steam 'A' Aux Feed Pump Replaced bearings, installed new couplings 7/22/83 Reactor Coolant 'B','C,' RCP Pump Install new seal 7/22/83 Safety Injection 2-51-726 Replaced valve ,

l 7/26/83 Safety Injection 2-SI-453 Replaced valve 7/5/83 Nuclear Instrumenation Fission Chambers Excore detectors changeout to install new fission chambers

. 7/11/83 Reactor Protection RCS Loop RTD Install and calibrate new RTD 7/7/83 - Ree:ter Coel =+ cys t-- Press- 9:;; P4223 & P4224 Replace with new kg//5/f/kcV.$

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Docket No. 50-336 Date: 8/15/83 Completed By: J. Gibson Telephone: 1203) 447-1791 Ext. 4431 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown:

Currently in Refuel / Maintenance Outage which commenced May 28, 1983.

3. Schedule date for restart following refueling:

Estimated date for restart is unavailable. NNECo is currently develcping a schedule consistent with the repair of the reactor vessel thermal shield. (See LER 83-24)

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

It is anticipated that Cycle 6 operations will require Technical Specification changes or other License amendments.

Supporting information has already been submitted.

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

A schedule has not been determined for further submittals.

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:

Additional plugged S.G. tubes will result in reactor coolant flow reduction. Currently planning to install sleeves in S.G. tubes.

Reactor Vessel thermal shield removal will be necessary prior to startup. As previously identified to the NRC, NNECo has identified failed fuel at Millstone Unit 2. The need to replace defective fuel assemblies will impact the core loading pattern and core physics parameters used as input to the safety analyses. The effect of a new loading pattern on the ongoing review of docketed material is not fully apparent at this time; however additional transient analysis may be required if significant loading pattern changes are needed.

(See LER 83-19/3L-1)

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

(a) In Core: 0 (b) 505

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:

.l 667

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

1985, Spent Fuel Pool, full core off load capability is reached.

1987, Core Full, Spent Fuel Pool contains 648 bundles.

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