ML20247D143

Monthly Operating Rept for Apr 1989 for Millstone Nuclear Power Station Unit 2

ML20247D143
Person / Time
Site:	Millstone
Issue date:	04/30/1989
From:	Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-13066, NUDOCS 8905250180
Download: ML20247D143 (5)

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

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336 Daar Sir:  !

This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 Monthly Operating Report 89-04 in accordance with Appendix A Technical Specifications, Section 6.9.1.6 One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY l

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Station Superintendent 1 Millstone Nuclear Power Station l

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} cc: W. T. Russell, Region I Administrator l G. S. Vising, URO Froject Manager, F4'le*+ne Unit NO. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2 & 3 8905250180 890430 "~

PDR ADOCK 05000336U R Pi4U g hhk e, i

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' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 5-10 COMPLETED BY J. Gibson TELEPHONE (203)447-1791 Extension 4431 MONTH April 1989 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 -

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i INSTRUCTIONS ,

i' On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Computer to the nearest whole megawatt.

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OPERATING DATA REPORT

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DOCKET NO. 50-336-DATE 5-10-89 COMPLETED BY J. Gibson TELEPHONE (203) 447 1791 Extension 4431

' OPERATING STATUS l

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

2. Reporting Period: April 1989 cumulative are weighted

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

4. Nameplate Rating (Gross MWe): 909 at 2560 MW' Thermal prior

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

6. Maximum Dependable Capacity (Gross MWe) : 893.88 current 2700 MWTH power

7. Maximum Dependable Capacity (Net MWe): 862.88 level.

8. If Changes Occur in Capacity Ratings (Items Number 3 Tnrough 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 Year to Date Cumulative

11. Hours In Reporting Period 719 2,879 116,999

12. Number Of Hours Reactor Was Critical 96.3 922.4 85255.8

13. Reactor Reserve Shutdown Hours 0 0 2205.5

14. Hours General On-Line 0 0 80885.7

15. Unit Reserve Shutdown Hours 0 0 468.2

16. Gross Thermal Energy Generated (MWH) 2469.0 2212703.0 224863983.0

17. Gross Elec. Energy Generated (MWH) 0.0 721026.0 67551546.0 ,

18. Net Electrical Energy Generated (MWH) -9620.0 680589.0 64789735.5

19. Unit Service Factor 0.0 28.5 69.1

20. Unit Availability Factor 0.0 28.5 69.5

21. Unit Capacity Factor (Using MDC Net) 0.0 27.4 65.2-

22. Unit Capacity Factor (Using DER Net) 0.0 27.2 64.3

23. Unit Forced Outage Rate 0.0 0.0 14.6

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

N/A

25. If Shutdown at End of Report Period, Estimated Date of Startup: Startup commenced April 23, 1989

26. Units in Test Status (Prior to Commercial Operation): Forcast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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. REFUELING INFORMATION REQUEST

1. Name of. facility: Fullstone 2

2. Scheduled date for next refueling shutdown: Currently in cycle 10 startuo

3. Schedule date for restart following refueling: April 23, 1989

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

Technical Specification changes for Cycle 10 Operation were approved by the NRC on March 20, 1989.

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

None

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:

Cycle 10 will be unique in that it will be the first cycle where the fuel and safety analysis will be supplied by Advanced Nuclear Fuels for Millstone Unit 2.

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

(a) In Core: (a) 217 (b) 640

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 Currently 1277 i 9. The projected date of the last refueling that can be discharged to the l spent-fuel pool assuming the present licensed capacity:

1994, Spent Fuel Pool Full, core off load capacity is reached (without consolidation).

1998, Core Full, Spent Fuel Pool Full  ;

2009, Spent Fuel Pool Full, core off load capacity is reached -

contingent upon full scale storage of consolidated fuel in the Spent Fuel Pool.

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