ML19225A143

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Monthly Operating Rept for June 1979
ML19225A143
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/09/1979
From: Howlett G
NORTHEAST UTILITIES
To:
Shared Package
ML19225A140 List:
References
MOR-790630, NUDOCS 7907180470
Download: ML19225A143 (7)


Text

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OPERATLNG DATA REPORT DOCKET NO. 50-336 DATE 7 /0 /70 C051FLETED BY G.W . Wodett TELEPHONE 2n3/447_1791 X364 OPERATING STATUS

1. Unit Name: Millstone 2 Notes
  • Unit received amended
2. Reporting Period: June 1979 license allowing operation at 2700 2700 MWth. Iterr.s 5, 6 & 7
3. Licensed Thermal Power (SIWI): , ,

reflect unit operation at ggg

4. Nameplate Rating (Gross MWe): 2560 MWth and will be updated o
5. Design Electrical Rating (Net MWe): >>30*

in the July 1979 Operating

6. Staximum DepenAble Capacity (Gross MWe): 842* Data Report.
7. Maximum Dependable Capacity (Net MWe): 810*
8. If Changes Occur in Capscity Ratings (Items Number 3 Dirough 7) S.' ace Last Report. Give Reasons:
9. Power Level To Which Restricted,If Any (Net MWe): WA
10. Reasons For Restrictions,If Any: Nov This Month Yr.-to Date Cumulative
11. Hours In Reporting Period 7?n 4,343 30291
12. Number Of Hours Reactor Was Critical 409 7 2.301 .7 21,919.4
13. Reactor Reserve Shutdown Hours 0 71 7  ?.072.a
14. Hours Generator On.Line del o cor;1 A 90_ cog 1
15. Unit Reserve Shutdown Hours 0 1no a 335.4
16. Gross Thermal Energy Gcnerated (MWH) 1.230.123 5.542.483 a9.424.716 .

17 Gross Electrical Energy Generated (MWH) 410.53.D_ ,_. 1.829.090 15,857,891

18. Net Electrical Energy Genersted (MWH) 391,711 1,742,475 15,159,166
19. Unit Sersice Factor 67.3 52.1 67.2
20. Unit Asailability Factor 57.3 54.6 68.3
21. Unit Capacity Factor (Using MDC Net) 67.2 49.5 60.8
22. Unit Capacity Factor (Using DER Net) 65.5 48.3 59.3
23. Unit Forced Outage P.aie  ?? 7 9.4 _

22.9

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each1:

Stean Genetator Feedwater Nozzle Insoection, Sectember 1,1979, Accrox. 5 Days

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/ A
26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICA LITY N/A N/A INITIAL ELECTRICITY N/A N/A COMM ERCI A L OPER A TION N/A N/A (4/77) ~

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O ER \GE D r.lLY l' NIT POh ER LL\ EL D0l'NE T NO. 50-336 L' NIT __Idi.l.11tQli; 1 DATE 7/9/79 CO\1PLE TED BY G.H. Howlett TELEPHONE 203/447-1791 X364 stoN r4 .. Ju i l9/9 DAY O ER \GE D AILY P0hER LEVEL DAY \VER AGE D \lLY POh f R l.EVEL t N.h c. Net i i siwe.Neo i 8d

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I DOCKET NO. 50-336 UNIT SilUTDOWNS AND POWF.R REDUCTIONS Millstone 2 UNIT NAME DATE //10//9 COMPLETED 11Y G.II. flowlof f REPORT MONT11 June i979 TELEPilONE 20Udd7_1701

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3 A 5 790610 F 235.1 A 1 LER 79-15 CB VALVEX Body to Boncet leak on 2-RC-405.

LER 79-17 Cil PUMPXX Pressurizer Power Operated Relief Isolation Valve, forced a manual reactor shutdown and subsequent system cooldown for ' pair of the valve.

During heatup tne 'A' Motor driven Aux. Feed Pump sha f t, broke extending the shutdown. Repairs were completed and the unit returned to normal power operations.

Suninary: The unit ~ operated at 94.8% (2560 MWth)'through the 26th except for the shutdown of the 10th through 19th.

The unit received a license amendment (Amendment #52 License #65) allowing unit operation at 2700 MWth.

Power was increased to 100~,(2700 MWth) on 27th with continued normal operations through the 30th.

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Docket No. 50-336 Date: 7/10/79 Completed By: G.H. Howlett III Telephone: 203/J47-1971 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 16, 1980
4. Will refueling or resumption of operation thereaf ter 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 proposea 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 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: 21 7 (b) 144

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:

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.

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