ML20101P922

Monthly Operating Rept for June 1992 for Millstone Unit 2

ML20101P922
Person / Time
Site:	Millstone
Issue date:	06/30/1992
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-92-741, NUDOCS 9207140092
Download: ML20101P922 (5)

Text

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July 10, 1992 j

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10CFR$0.7 t(a) 1 3.

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U.S. Nuclear Regulatory Connuission Document Control Desk j

j Washington, D.C, 20555

Reference:

Facility Operating 1.icense No. DPit 65 4

Docket No. 50 336

]

j Dear Sir; a

1 j

This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 for the month of June,1992, in accordance with Appendix A Technical Specificationt,. Section 6.9.1.6.

One additional copy of the report is enclosed, f

Very truly yours, j

NORTilliAST NUClliAR liNiiROY COMPANY FOR: Stephen E. Scace Station Director, i

Millstone Nucl -

Power Station i

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!!Y; Fred R.

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Site Services. Director Millstone Nuclear Power Station SES:mo ec:

T. T. Martin, Region 1 Administrator.

G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident inspector. Millstone Unit Nos.1, 2 & 3

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s 9207140092 920630 PDR ADOCK 05000336

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i OPERATING DATA REPORT f

DOCKET NO.

50 336 i

DATE 07/08/92 i

COMPLETED BY G. Neron

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TELEPil0NE (203) 444 5517 i

EXT.

5517 l

't li OPEPATING STATUS l

l Notes: Items 21 and 22 j

1.

Unit Name:

Millstone Unit 2.

cumulative are weighted 2.

Reporting Period:

June 1992 averages. Unit operated 3.

Licensed Thermal Power (HWt):

2700 at 2560 MWTH prior to its i

4.

Nameplate Rating (Cross MWe):

.2,09 uprating-to the current'-

4 5.

Design Electrical Rating (Net HWe):

870 2700 MWTH power level.

6.

Maximum Dependable Capacity (Cross MWe):

903.10 4

1 7.

Maximum Dependable Capacity (Net MWe):

873.10 8.

If Changes Occur in Capacity Ratings (Items-Number 3 Through 7) Since-Last Report, i

Give Rena.ons:

}

N/A i

1 9.

Power Level To Which Restricted..If any (Net MWe):

N/A l

10. Reasons For Restrictions, If Any:

N/A i

1 i

l This Month Yr. To-Date Cumulative i

11. Hours In Reportin6 Period 720.0

'4367.0 144767.0 3

l

12. Number Of Hours Reactor Was Critical 0.0 3204.0 105257.6-1

13. Reactor Reserve Shutdown llours 0.0 O.0 2205.5

14. Hours Generator On Line 0.0 3188.6 100357.4

15. Unit Reserve Shutdown Hours 0.0 0.0 468.2 i

16. Cross Thermal Energy Generated (MWH) 0.0 8506218.0 276028682 4

17. Cross Electrical Energy Generated (MWH)'

(-3499.0)-

2721518.3 0.0-2827636.5 84404307.5 j

18. Net Electrical Energy Generated (MWil) 8096/296.3

19. Unit Service Factor 0.0 73.0 69.3 j

20. Unit Availability Factor.

0.0

-73.0 69.6 i-

21. Unit Capacity Factor (Using MDC Net)

-0.6 71.4 65.6 l

22. Unit Capacity Factor (Using DER Net)

- 0.,,b.

71.6-64.4

23. Unit Forced Outage Rate 0.0: _

11.4 15.4

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

The Unit is nresentiv shutdown for refteline. reulacement of the steam cererators and main-

~

tenance.

Duration - 141 days.

-25. If Unit Shutdown At End Of Report Period, Estimated Date.of' Startup:

October.-1992

- 26'. Units In Test Status'(Prior to Commercial Operation);

f

. Forecast Achieved INITIAL CRITICALITY N/A_,,,

N/A INITIAL ELECTRICITY N/A-N/A-COMMERCIAL OPERATION N/A-N/A e

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a

6 AVERACE DAILY UNIT POWEP. LE51EL -

DOCKET NO.

50-336 g;

UNIT: _Ei)1 stone Unit 2 di -

DATE:

07/08/92 COMPLETED BY:

G. Erron TELEPHONE:

(203) 444-5517 EXT:

5517 b

'E 1992 D A'.

rL7 PCWER LEVEL DAY AVG. DAILY POWER LEVEL

!Ne -Ne t)

(MVe-Net) 1 0

17 0

2 0

18 0

.2 3

m.

0 10 0

r, 0

20 0

^

5 0

21 0

6 0

22 0

7 0

23 0

8 9

24 0

9 0

25 q

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29

_ 0, 14 0

30 0

15 0

.11 4

16 0

INSTRUCTIONS On this format, list the overege daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole negawatt.

m.

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DOCKET NO.

50-336 UNIT SHUTDOWNS AND PO"wTR REDUCTIONS UNIT NAME Millstone 2-DATE 07/08/92 COMPLETED LY Gary Neron TELEPHONE (2031 444-5517 REPORT MONTH JUNE 1992 EXT.

5517 1

2 Cause & Corrective No.

.Date Type ~

' Duration Reason Method of License Systp Compgnent (Hours)

Shutting Event Code Code Action to 3

Down Reactor Report #

Prevent Recurrence I'

(i

.03 920529

.S 720 C'

1 N/A N/A N/A Continuation of the re-fueling, steam generator replacement and mainten-ance outage from the previous month.

l.

0 2

l3 Method Exhibit G'- Instructions-

'Fl: Forced' Reason:

1-Manual.

for Preparation of Data

-5:JScheduled' TA-Equipment. Failure ~(Explain)

B-Ma'

enance or Test '

'2-Manual Scram Entry Sheets for License C-Refuellt.,-.

3-Automatic-Scram Event Report (LER) File-

~D-Regulatory Restriction 4-Continued frca (NUR6G-0161)

E-Operator Training 6 Licenre Examination-

' Previous month h

5 F-Administrative 5-Power Reduction Exhibit 1 - Same Source G-Operationa? Error =(Explain)'

(Duration -0).

6-O the r.. (Explain)

H-Other--(Explain).

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1 BEFUELING INFORMATION REQUEST i

1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown:

Currently in tJhg EOC 11 Refuelina. Maintenance and Steam Gglerator Rep.lAggagnt Outace.

3.

Scheduled date for restart following refueling:

,_pctober. 1992 4.

Will refueling or resumption of oper7 tion thereafter require a technical specification change or otner license t-ndment?

YES i

5.

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

None at this lira.

~ ~.

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:

Millstone 2 will be roolacino the Steam Generator sub-assemblies 1;lurino the Socomina End of_ Cycle 11 refuelina o_Utagg.

It is anticipated this will be accomolished undgr 10CFR 50.59.

7.

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

In Core:

(a) 212 In Spent Puel Pool:-

(b) 212 NOTE: "hese numbers ret tesent the total Fuel Assemblies and Consol-

. dated _ FygLS;nnace Boxes (3 total - containina the fuel rods fron 6_ fuel assembliesL in these two (2) Iter. Control Areas.

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 _assamblies:

Currently 1237 I

9.

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

l 1994. Scent Fuel Pool Full, core off load capacity is reached (with l

-out consolidation).

l 1998. Core Full, Spent Fuel Pool Full-l 2.009. Spent Fuel' Pool Full, core off load capacity ig reached-continoent uoon full _ scale storace of ecnsolidated fuel-it}_the Scent Fuel Pool.

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