ML19207A323

Monthly Operating Rept for Jul 1979

ML19207A323
Person / Time
Site:	Millstone
Issue date:	08/02/1979
From:	Howlett G NORTHEAST UTILITIES
To:
Shared Package
ML19207A321	List: ML19207A320 ML19207A323
References
NUDOCS 7908160444
Download: ML19207A323 (4)

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OPERATLNG DATA REPORT DOCKET NO. 50-336 DATE 8/2/79 COMPLETED BY G.H. Howlett TELEPHONE 203/447-1791 X364 OPERATING STATUS Notes *l Items 21 and 22

1. Unit Name: l'i.llstone 2 Yr-To-Date and cumulative

2. Reporting Period: Juiv 1979 re computed by using a

3. Licensed Thermal Power (MWtp: 2700 weighted average.

4. Nameplate Rating (Gross MWe): 909 S. Design Electrical Rating (Net MWe): 870

6. Maximum Dependable Capacity (Gross MWe): 896

7. Masimum Dependable Capacity (Net MWe): 864

8. !f Changes Occur in Capacity Rt.:ngs (Items Number 3 Through 7) Since Lrst Report. Give Reascns:

Items 5, 6 & 7 reflect increase in L~, ?nsed Thermal Power from 2560 to 2700 Mwth.

9. Power Lesel To Which Restricted.lf Any (Net MWe): None

10. Reasons For Restrictions. If Any: None This Month Yr -to-Dat e Cumulative il. Hours in Reporting Period 744 5,087 31.535

12. Number Of Hours Reactor Was Critical 744 3,135.7 22.663.4

13. Reactor Reserve Shutdown Hours 0 71- 2.072.4

14. Hours Generator On-Line 744 3.005.6 21.437.3

15. Unit Reserve Shutdown Hours 0 109.4 335.4

16. Gross Thermal Energy Generated (MWH) 1.989.041 7.531.524 51.413,757 .

17. Gross Electrical Energy Generated (MWH) 656J60 2,485,850 16,514,651

18. Net Electrical Energy Generated (MWH) 633,743 2,376,218 15,792,909

19. Unit Sersice Factor 100 59.1 68.0

20. Unit Asailability Factor 100 61.2 69..

21. Unit Capacity Factor (Using MDC Net) 98.6 67.4 *l 61.8 *l

22. Unit Capacity Factor (Using DER Net) 97.9 56.1 *1 60.3 *1

23. Unit Forced Outage Rate 0 7.3 22'.3

24. Shutdowns Scheduled Oser Next 6 Months (T)pe. Date, and Duration of Eacht-Steam Generator Feedwater Nozzle Inspection, Sept.mber 1, 1979, 3 Weeks.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A 26 Units In Test Status (Prior to Commercia! Operation): Forecast Achiesed INITIA' CRITICALITY N/A N/A '

INITIAL ELECTRICITY N/A N/A COMMERCIAL OPER ATION N/A N/A 798, 347 (9/77 )

7908160

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O f f' U.E D ALLY UNil POhf R LE\ EL DOCKE F NO. 50-336 UNir Mil.lstone_2_.

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DOCKET NO.60-116 UNIT SilUTDOWN5 AND POWER REDUCTIONS Mill onno 2 UNIT NAME DATE R/7/79 COMPLETED BY G.H. Howlett REPORT MONT11 July 19 3 TELEPl10NE '701/447-1741 X364'

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m ~2 -C 4 C, et g -s Licensee Cause & Corrective m No. Date E. '5 5 !2 3 .g j Event 5 *.

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1. 33 oO e 5 3 cc Renort # mL gu Prevent Recurrence g di { CC C 7

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N 6 790727 F 0 A 4 ti/A HJ PIPE XX Power was manually reduced to 68% to allow the isolation of a Heater Drains -

line leak. Weld repairs were completec and normal power operations resumed.

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Sun:r,a ry : The ur.it operated at or near full pawer tiiroughout the reporting period except for the power reduction 27th.

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Docket No. 50-336 Page 1 of 1 Date 8/7/79

. Unit Name Millstone 2 Completed By G.H. Howlett

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Telephone 203/447-1791 X364 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month June 1979 DATE SYSTEM COMPONENT MAINTENANCE ACTION 6/13/79 Reactor Coolant  ?-RC-252 Loop 1A Spray Header Replaced leaking seal ring. c3 Molation Valve. tr3 m

6/13/79 Reactor Coolant 2-RC-253 l oop 1B Spray Header Replaced leaking seal ring.

Isolation Valve.

cc Replaced leaking seal ring. C7' 6/14/79 Reactor Coolant 2-RC-405 Pressurizer power I'

aperated relief isolation valve. I

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6/19/79 Auxiliary Feedwater Aux Feed Pump P-93 Replaced failed bearing and rebuilt pump. ,

6/19/79 Reactor Protection RPS Ch. 'D' Bistable power supply Replaced _+ 15 VDC power supply.

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6/29/79 Non-Radwaste ' A' DC Switchgear Room supply fan Replaced failed bearings Ventilation F-54A

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Docket No. 50-336 Date: 8/2/79 Completed By: G.H. Howlett III Telephone: 203/447-1971 X364 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown June 28, 1980

3. Schedule date for restart following refueling: August 1, 1980

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

Technical Specification changes will be necessary as a result of the change in fuel and safety analysis supplier.

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

The schedule for submitting proposed license action is as follows:

Basic Safety Report 2-1-80 ECCS Results 4 ' 80 Reload Safety Evaluation 5-1-80

6. Important licens;,a 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 4 will be unique in that it will be the first where the fuel and safety analysis will be supplied by Westinghouse.

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

In Core: 217 (b) 144 (a) _ _

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed stcrage capacity that has been requested or is planned, in number of fuel assemblies:

667

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

1983, Spent Fuel Pool, full core off load capability is reached.

1986, Ne Full, Spent Fuel Pool contains 648 bundles.

798. 351