ML19208A993

Monthly Operating Rept for Aug 1979

ML19208A993
Person / Time
Site:	Millstone
Issue date:	09/04/1979
From:	Howlett G NORTHEAST UTILITIES
To:
Shared Package
ML19208A989	List: ML19208A988 ML19208A993
References
NUDOCS 7909180395
Download: ML19208A993 (4)

Text

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OPERATING DATA REPORT DOCKET NO. 50-336 DATE Seot. 4, 1979 COMPLETED BY G. 4. Howlett TELEPHONE 201/447-1791 X364 OPERATING STATUS Millstone 2 Notes

1. Unit Name:

2. Reporting Period: August 1979 *1 Items 21 and 22, Yr.-to-2700

3. Licmed Thermal Power (MWt): date and Cumulative are com-

4. Nameplate Rating (Gross MWe): Ano puted using a weighted av-

5. Design Electrical Rating (Net MWe): 870 erage.

6. Maximum Dependable Capacity (Gross MWe): 896

7. Maximum Dependable Capacity (Net MWe): 864

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

None

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

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

11. Hours in Reporting Period 744  :; . All 17 270

12. Number Of Hours Reactor Was Critical 300 3.435.7 22.963.4

13. Reactor Reserve Shutdown Hours 0 71.7 2,072.4

14. Hours Generator On-Line 283.1 3.288.7 91.72n 4

15. Unit Reserve Shutdown Hours 0 109.4 335.4

16. Gross Thermal Energy Generated (MWH) 745,654 8,277,178 52,159,411 -

17. Gross Electrical Energy Generated (MWH) 244,660 , _ . 2.730.510 16.759.311

18. Net Electrical Energy Generated (MWH) 232.580 2,608,798 16.025,489

19. Unit Service Factor 38.1 56.4 67.3

20. Unit Availability Factor 38.1 58.3 68.3

21. Unit Capacity Factor (Using MDC Net) 36.2

• 54.3 61.1

22. Unit Capacity Factor (Using DER Net) 35.9

• 53.3 59.7

23. Unit Forced Outage Rate 61.9 17.5 23.4

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

Reinsoection of S/G Feedwater No7'19s. October 6. 1470 3 weeks

25. If Shut Down At End Of Report Period. Estimated Date of Startup: 4/A

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 Ob.})'Nb 7909180 3 [

\VER \GE D tiLY UNIT POh ER LEVEL DOCKET NO. 50-236 cs:T Millstone 2 DATE Sept. 4, 1979 CON!PLETED BY G. H. Howlett TELEPHONE 203/447-1791 X364 s10 NTH AuCust 1979 DAY AVERAGE DAILY P0hER LEVEL DAY AVERAGE D ALLY POhER LEVEL Othe-Net) t MWe-Net )

1 857 17 0 (-6) 2 856 18 0 (-5) 856 3 19 0 (-5) 4 856 20 o ( -M S 855 21 0 (-51 6 855 22 0 (-51 7 854 23 0 (O g 350 24 0 (-5) 9 n (-6) 25 0 (-5) 10 0 (-5) 26 0 (-19) 11 0 (-5) 3, 71 12 n (-5) 3 g43 13 0 (-5) 29 848 i4 0 (-6) 30 R49 15 0 (-6) 3: 852 16 0 (-6)

INSTRUCTIONS On :his format. rs :he se a .:Ze dail) unit power fese! :n MWe Net for each Liy in :Le rg..rt:nc

.. nth. C onraie to the nearest whole mega.satt.

qq,-*)

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• s UNITSilUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-336 UNIT NAM E Millstone 2 DATE Sept. 4. 1979 COMPLETED BY G. H. llowlett REPORT MONTil August 1979 TELEPilONE ?Ol/447-1791 Y164 m

c

-, .! g } j .E ~ Licensee E r, $n, Cause & Corrective No. Date Q ~g  ;:; j s5 Event g 'g gO 3 Action to H y= $ e

~gc Report # mV u

o Prevent Recurrence 6

7 790808 F 460.9 A 1 llB PIPEXX Un-isolable Main steam line leak, forced a manual shutdown of the unit with a subsequent plant cool-down for repairs. ' Concurrently, the Steam Generator feedwater nozzles were inspected per N.R.C. Directive.

I Suumary: The unit operated at or near 100% rated thermal throughout the report period

,, except for the outage of the 8th through 27th.

W w

U 4

~J (9/77)

Docket No. 50-336 Date: 9/11/79 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 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.

5. Scheduled date(s) for submitting proposed licens.ing 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 supiier, 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:

(a) In Core: 217 (b) 144

8. The present licensed spent fuel pool s'orage capacity and the size of any increase in licensed storage capacity tnat 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, Core Full, Spent Fuel Pool contains 648 bundles.

3612518