ML19259C096

Monthly Operating Rept for May 1979

ML19259C096
Person / Time
Site:	Millstone
Issue date:	06/07/1979
From:	Sudigala S NORTHEAST UTILITIES
To:
Shared Package
ML19259C094	List: ML19259C093 ML19259C096
References
NUDOCS 7906120347
Download: ML19259C096 (5)

Text

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OPERATING DATA REPORT DOCKET NO. 50-336 DATE 6/7/79 '

COMPLETED BY S 9"dicala TELEPHONE 201/447- 791 x366 OPERATING STATUS

1. Unit Name: Millstone 2 N' . 2

2. Reporting Period: May 1979

3. Licensed Thermal Power (MWt): 2560

4. Nameplate Rating (Gross MWe): 909

5. Design Electrical Rating (Net MWe): 830

6. Maximum Dependable Capacity (Gross MWe): 842

7. Maximum Dependable Capacity (Net MWe): 810

8. If Changes Occur in Capacity Ratings (Items Number 3 nrough 7) Since Last Report. Give Reasons:

None

9. Power Level To Which Restricted,If Any (Net MWe): None

10. Reasons For Restrictions. If Any: None

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This Month Yr.-to-Date Cumulative 30,071 '

11. Hours In Reporting Period 744 3623

12. Number Of Hours Reactor Was Critical 321.3 1893 21,420.7

13. Reactor Reserve Shutdown Hours 6.8 71.7 2,072.4

14. Hours Generator On.Line 220.7 1776.7 20,208.4

15. Unit Reserve Shutdown Hours 109.4 109.4 335.4

16. Gross nermal Energy Generated (MWH) al7 E7R 4 112 1 Fin 49.194.593 -

17. Gross Electrical Energy Generated (MWH) 117 110 _.1.418.560 15.447.361

18. Net Electrical Energy Generated (MWH) 125.089 1.350.764 14.767.455 '

19. Unit Service Factor 24.7 49.0 67.2

20. Unit Availability Factor 44.3 52.1 68.3

21. Unit Capacity Factor (Using MDC Net) - 20.8 46.0 60.6

22. Unit Capacity Factor (Using DER Net) 70 1 44 9 59.2

23. Unit Forced Outage Rate 0 0 22.7-

24. Shutdowns Scheduled Ovei Next 6 Months (Type. Date.and Duration of Each t: .

None 25 If Shut Down At End Of Report Period. Estimated Date of Startup: NA

20. Units In Tes Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 79061203M '*"

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AVERAGE D ALLY UNIT POhER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 6/7/79 CONIPLETED BY S. Sudigala TELEPHONE - 203/447-1791 x366 ,

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310NT11 May 1979 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (stWe-Net) (stwe Net) 0 (-4) 17 0 (-25)'

2 0 (-4) is 0 (-26) 0 (-4) 3 19 0 (-26) 4 0 (-2) 20 0 (-26) 5 0 (-4) 21 0 (-27) 6 0 (-4) 22 0 (-13) 7 0 (-4) 23 204 g 0 (-5) ,4 415 9 0 (-5) 25 417 10 0 (-5) 26 444

0 (-5) 27 732 12 0 (-5) ,g 797 13 0 (-6) 29 795 14 0 (-5) 30 796 15 0 (-5) 33 813 16 0 (-19)

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INSTRUCTIONS On this forrnat. fist the aserage daily unit power lesel in slWe-Net for each day in the reperting month. Compute to the nearest whole mepwatt.

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e DOCKET NO. 'iG 116 UNIT SillITDOWNS AND POWER REtJUCTIONS UNIT NAME Milletnnn ?

DATE 6/7/79 COMPLETED BY S. Sudicala REPORT MONTil May 1979 TELEPl!ONE 701/aa7.1701 x366 c es 3 c

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-., .E E g g Y =4 Licensee ,v, 2*L Cause & Corrective No. D.ite g gg  ; .3 g 5 Event u7 E" Action to

• g3 5 5 j;5g Report # NC Prevent Recurrence c5 3 790310 S 521.3 C 1/2 NA NA NA Refueling Outage Continuing 4 790522 S 2 B 3 NA NA NA Turbine Overspeed Trip Test I

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• Summarf: The unit returned to power operation following the cycle 3 refue' ling outage.

3 At the conclusion of the reporting period, the unit was at licensed thermal .

N' Power conducting power ascension testing. ,

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(9/77)

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Docket No. 50-336

, Page1 of Date '

6/7/79 -

l Unit Name Millstone 2

' Completed By S. Sudigala Telephone 203/447-1791 X366 i

N CORRECTIVE MAINTENANCE SUPEARY FOR SAFETY RELATED EQUIPMENT Report Month May 1979 DATE SYSTEM COMPONENT ' MAINTENANCE ACTION 3/3/79 Nuclear Instrumentation Uncompensated ion chamber - Replaced Detector Channel A 4/6/79 Reactor Protection Channel C Hot Leg RTD TE-ll2 HC Replaced RTD 4/16/79 Reactor Protection Channel A RCS Flow Instruments Repaired Signal Characterizer PDY-121A-1 4/18/79 Reactor Protection Channel D RCS Flow Transmitter Replaced Amplifier Circuit Board PDT-121D l 4/19/79 Incore Nuclear Incore Instrumentation Replace 32 Detedtor Strings

Monitoring 4/20/79 Reactor Protection Channel B RPS Flow Bistable Replaced Bistable Trip Unit 4/21/79 Reactor coolant and Pressure Instrument PI-103-1 Replaced PI-103-1 GE/MAC 180 Indicator vessel 4/30/79 Reactor Protection Channel A Module H4 in + 10V Replaced Module H4, In + 10 volt Reference Reference Power Supply CPC-1 6

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Docket No. 50-336

- - Date: g/o/7a Completed By: s snainala Telephone: 203/447-1791 x366 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown: June 1, 1980.

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

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

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

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5. Scheduled date(s)' for subn$itting proposed licensing action and supporting information:

The schedule for submitting proposed license action is as follows:

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

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 porcedures:

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:

(a) In Core: 217 (b) 144

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has bcen 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 capaci.ty; .

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

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

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