ML20096C836

Monthly Operating Rept for April 1992 for Millstone Unit 2

ML20096C836
Person / Time
Site:	Millstone
Issue date:	04/30/1992
From:	Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-92-477, NUDOCS 9205150009
Download: ML20096C836 (5)

Text

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(203) 60$-5000 May ll, 1992 MP-92-477 Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Controi Desk Washington, D. C.

20555

Reference:

Facility Operating License No. DPR.65 Docket No. 50 336

Dear Sir:

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

One additional copy of the report is enclosed.

y Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

-83 Stephen E. Scace Station Director Millstone Nuclear Power Station SES/JG cc: T. T. Mart'.n, Region I Administrator G.

S, Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1,2&3 9.. n 3

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[ j, 9205150009 920430 PDR ADOCK 05000336

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OPERATING DA1A RF. PORT DOCKET NO.

50-336 DATE 05/06/92 COMPLETED BY J. Gibson TEL1. PHONE (203) 447 1791

EXT,

_4431 OPERAIING STATUS Notes: Items 21 and 22 1.

Unit Name:

Millstone Unit 2 cumulative are weighted 2.. Reporting Period:

April 1992 averages. Unit operated 3.

Licensed Thermal Power (MWt):

270Q at 2560 MVTH prior to its 4

Nameplate Rating (Gross MWe):

9Q2 uprating to the current 5.

Design Electrical Rating (Net MWe):

_.870 2700 MWTH power icvel.

6.- Maximum Dependable Capacity-(Cross MWe):-

903.10 7.

Maximum Dependabis Capacity (Not MWe):

873.10 B.

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

The increast_in Maximum Denendable Capacity is the result of Moisture Senarator /

Reheater mod [fications_rerformed durinr_ the end of_Cvele 10 refueling outano.

l 9.

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

N/A

10. hassons.For Rectrictions, If Any:

N/A l

i This Month Yr..To Date Cumulative.

11. Hours In Reporting Period 719.0 2903.0 143303.0

-12. Number Of Hours Reactor Was Critical

/19.0-2506,2 104560.5 i

13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

14. Hours Generator On Line 719.0 2493.8 99662.6 15; Unit Reserve Shutdown Hours 0.0 0.Q 468.2

16. Gross-Thermal Energy Cencrated (MWH) 1940643.2 6633812.0 274156276.4

-17.- Gross Electrical-Energy-Cenerated (MWH) 644250.0 2209083.0 83785754.0 18.1 Net Electrical Energy Generated (MWH) 622028.0 2128171.0 80373949.0 100.0 85.9 69.5-

19. Unit' Service Factor 110. Unit Availability Factor.

100.0 8 5. ')

69.2

'21. Unit Capacity Factor (Using MDC Net) 99.1-84.0 65.8 i

22. Unit Capacity Factor (Using DER Net) 99.4 84.3 64.6

23. Unit Forced Outage Rate 0.0 14.1 15.5

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

EOC 11 Refuel and' Steam Ofnerator Replacement Outage. May 30. 1992. 160 days.

25. If Unit Shutdown At_ End Of Report Period Estimated Date of Startup:

N/A 1

.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 i

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-336 UNIT:

M111 stone Unit 2 DATE:

_05/06/92 COMPLETED BY:

J. Gibson

?ELEPHONE:

_J2031447-1791 EXT:

4431 MONTil: AFRIL 1992 DAY AVO. DAILY POVER LEVEL DAY AVG. DAILY POWER LEVEL (MVe-Net)

(MVe-Net) 1 866 17 867 2

866 18 866 3

867 19 865 4

867 20 864 5

831 21 865 6

867 22 864-7 868 23 864 8

868 24 863 9

866 25 863 10 865 26 863 11 865 27 862 12 866 28 861 13 866 29 860 14 866 30 863 15

-865-31 16 868-INSTRUCTIONS On this format, list the average daily unit power level in MVe Net for each day in the reporting month.

Compute to the nearest whole me;awatt.

.i BDCKET NO.

50-336

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UNIT SHUTD0'.'NS AND PO'.'ER REDUCTIONS UNIT WAME Millstone 7 DATE 05/06r32 i

COMPLETED BY J. Gibson J

TELEPHONE (203) 447-1771

' REPORT MONTH APRIL 1992 EXT.

4431 l

2 No.

Date Type

' Duration

.. Reason Method of

. License Systgm Comppent Cause 6 Corrective (Hours)-

Shutting Event Code Code Action to I

3 Down Reactor Report #

Prevent Recurrence N/A N/A N/A N/A N/A-N/A N/A N/A N/A D

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1: Forced 2

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Reason:

Method

' Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

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B-Maintenance or Test 2-Manual Scram Entry Sheets for License

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C-Refueling 3-Automatic Scram Event Report (LER) File i

D-Regulatory Restriction 4-Continued from (NUREC-0161) l E-Operator Training & License Examination Previous month j

5 F-Administrative 5-Power Reduction Exhibit 1 - Same Source f

G-Operational Error (Explain)

(Duration -0) f H-Other (Explain).

6-Other (Explain)

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REFUELING INFORMA1' ION REQUEST 6

1.. Name of facility:

Millstone 2

-2.

Scheduled date for next refueling shutdowns

__Bry_lQ. 1992 3.

Scheduled date for restart following refuelings Scotember 1992 4.

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

YES 5.-

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

Soont Fuel Pool license ammendment was subnitted to thg_UEC on April 16. 1992.

The NRC technical review

<.s exnected by May 31.

1992.

6.

Important licensing considerations associated wi'.h refueling, e.g.,

new or different fuel design or supplier, unrcviewod design or performance analysis methods,-significant changes in fuel design, new operating procedures Mil stone 2 will' be renlacina the Stpam Generator suh-Appemblies ijur:.nc the uos_omina End of Cycle 11 refqcljnq_ouhace.

It is ant:.cinated this will be accomplished under 10CFR 50.59.

7.

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

In Core:

(a) 111 In Spent Fuel Pools (b) 212 UOTE:

These numbers reorespnt the tctal fuel assemblies ar,d EQngplidated fuel storace boxes in these tEo (2) Item CQatrol Areas lB.

The present licensed spent fuel pool storage capacity and the site of any increase in licensed storage capacity that has been i

requested or is planned, in number of fuel assemblies:

. cgrnqntly 1277 9.

- The projected date of the last refueling that can be discharged to

-the spent fuel pool assuming the present licensed capacity:

1994. Soent Fue:

Pool Full, core off load caEacity is reaghed (with

-out qpnsolidat:.on).

1998. Core full._Soent Fuel Pool Full 2009. Soent Fuel Pool Full. core off load capacity is reached-contincent_unon full scale storace of c_quS.qlldated fuel in the Snent Fuel Pool.

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