ML20059J748

Monthly Operating Rept for Aug 1990 for Millstone Unit 2.W/

ML20059J748
Person / Time
Site:	Millstone
Issue date:	08/31/1990
From:	Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-997, NUDOCS 9009200150
Download: ML20059J748 (5)

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i September 11, 1990-MP-90-997 Re: 10CFR50.71(a)' H I

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'U.S. Nuclear' Regulatory Commisston- l Document Control Desk a Washington, D. : C. 20555 l

Reference:

Facility. Operating-License'No.'DPR-05= 1 Docket No. 50 336 l

Dear Sir:

This letter is forwarded to provide:the report of operating and shutdown experience relating to Millstone Unit 2 for the month of August, 1990, in. .!

accordance-with Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of-the report is-enclosed. -;

I Very truly yours, j a

NORTHEAST NUCLEAR ENERGY COMPANY. .l

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.Stepnen E.;Scace  !

Director, Millstone Station -

SES/JG cc: T. T. Martin, 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 t

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1. ' ' OPERATING' DATA REPORT DOCKET NO. 50-336 DATE 09/06/90 COMPLETED'BY J. Gibson >

. TELEPHONE (203) 447-1791 (

. EXT. 4431 OPERATING STATUS-Notes: Items 21 and '

1. Unit Name:- Millstone Unit 2 cumulative'are weighted

=2. Reporting Period:- August 1990 -averages. Unit operated;

3. Licensed Thermal Power _(MWt): -2700: Lat 2560 MWTH prior.to its

'4.. Nameplate Rating- (Gross JGJe): 909 .

uprating'to the current-  !

. 5 .- ~ Design Electrical Rating (Net MWe): 870 2700 MWTH power level. i

~6. Maximum Dependable Capacity -(Gross MWe):: 893.88-

7. Maximum Dependable Capacity (Net MWe): _ 862.88 .

8. If Changes Occur in Capacity R3 tings (Items Number 3.Through 7) Since Last Report,.

Give Reasons:

N/&

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

'N/A .,

10. Reasons For Restrictions, If Any: N/A'

=This Month Yr.-Tb-Date Cumulative .!

11. Hours In Reporting Period .

'744.0- '5831.0 '128711.0

12. Number Of. Hours Reactor Was Critical . 714.7 4910.6- 95271.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

14. Hours Generator On-Line '707.3- 4865.7- 90817.1 l J15. Unit Reserve Shutdown Hours .

0.0 ,,

0.0- 468.2

16. Gross Thermal Energy Generated (MWH) ,1869028.0' 12979898.0- 251115736.4

, 17. Gross Electrical Energy Generated (MWH) 602835.0 4216306.5 76135476.-5

18. Net Electrical Energy Generated (MWH) 580198.0 4057666.5 73054300.5

19. Unit Service Factor '

95.1- 83.4 70.6 '

20. Unit Availability Factor 95.1 83'.4 70.9

21. Unit Capacity Factor (Using MDC Net)- 90.4 80.6 66.7

22. Unit Capacity Factor (Using DER Net) 89'.9 80.0 65.4

23. Unit Forced Outage Rate 4.9' 2.2 13.3

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

End of Cycle 10 Refuel Outare. Seotember 15'. 1990; 40 days.

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

26. Units In Test StatusE(Prior to Commercial Operation): .

Forecast ~ Achieved  !

INITIAL CRITICALITY N/A ~N/A >

INITIAL ELECTRICITY N/A N/A ,

COMMERCIAL OPERATION N/A N/A  !

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' AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO. 50-336 UNIT: Millstone Unit 2-DATE: 09/06/90 COMPLETED BY: . J. Gibson TELEPHONE: (203)447 1791

? x. :EET:l 4431 ,_

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-MONTH: AUGUST 1990~  !

DAY' AVO.' DAILY POWER LEVEL DAY ' AVG. DAILY POWER LEVEL'

.(MWe-Nat) (MWe-Net) i 1 -842 17- '840 2 -- 843 18. 840 1

3. 844 L19 842~

4 _ 844 20 '842 1

5 844 21 843 6 843 22 ~843 7 844 -23. 842  !

8 843- 24 842 9 844 25 840 l

10 844- 26- 839  ;

i

-11 844 27 8- '

12 844 28 _ 60-13 842 29 530

'14 842 30 835 15 841 31 839

.16 841 INSTRUCTIONS On this format, list the aserage daily unit power-level in MWe-Net for each day f.e the reporting month, compute to=the nearest whole megawatt.

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. s DOCKET NO. 50-336~

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 .

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DATE. 09/06/90- .-

COMPLETED BY 'J. Gibson TELEPHONE (203) 447-1791 REPORT MONTH AUGUST 1990 EXT. 4431 No. Date Type l Duration Reason2 Method of License Systgm Compgnent Cause & Corrective (Hours) Shutting Event Code Code Action to Down Reactor 3 Report # Prevent Recurrence-04 900827 F 36.7 G 3 90-012 JC N/A While at 100% power and with a trip signal pre-sent on RPS channel A, the operator:inadvert.

ently inserted a 2nd-trip on. channel:B prior

-to bypassing channel B.

Procedural changes will be implemented to-

. ensure proper use of bypass keys. See LER.

4 Exhibit G - Instruetions 1:F Forced 2 Reason: 3 Method S: Scheduled 'A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License C-Refueling .

3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued fror: (NUREG-0161)

E-Operator Training & License Examination Previous month S

F-Administrative 5-Power Reduction Exhibit 1 -Same Source C-Operational Error (Explain). (Duration -0)'

H- Other (Explain) 6-Other (Explain)

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REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2 1 1

2. Scheduled date for next refueling. shutdown: SeDtember 15, 1990 1

3. Scheduled date for restart.following refueling: N/A ,

? .

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

YES S. Scheduled date(s) for submitting licensing action and supporting  ;

information:- i ProDosed Technical SDecification submittal-for the CORE OPERATING i LIMITS REPORT was submitted on 6/26/90; ADoroval is anticiDated Drior to restart. l

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,. .i new operating procedures:

None

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

In Core: (a) 212 In Spent Fuel Pool: (b) 5AA

8. The present licensed spent fuel pool storage capacity 1and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Currently 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 caDacity is reached (with

-out consolidat:.on).

1998. Core Full. Soent Fuel Pool Full 2009. SDent Fuel Pool Full, core off load caDacity is reached-continaent uoon full scale storace of consolidated fuel in the Soent Fuel Pool. .

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