ML20055F188

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Monthly Operating Rept for June 1990 for Millstone Unit 2.W/
ML20055F188
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/30/1990
From: Neron G, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-672, NUDOCS 9007160053
Download: ML20055F188 (5)


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July 6, 1990 MP-90-672 Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Reference:

Facility Operating License No. DPR 65 l

Docket No. 50 336

Dear Sir:

1-

~This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 for the month of June,1990, in accordance with Appendix A. Technical Specifications, Section 6.9.1.6.

One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY t'

W Steph n

. Scace Station Director i

Millstone Nuclear Power Station SES/CN 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

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9007160053 900630

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gg PDR ADOCK 05000336 i

R PDC f

oS70 REY.7-85 eP91

l OPERATING DATA REPORT I

DOCKET NO.

50-336 DATE 07/06/90 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 EXT.

4417 OPERATING STATUS Notes: Items 21 and 22 t

1.

Unit Name:

Millstone Unit 2 cumulative are weighted 2.

Reporting Period:

June 1990 averages. Unit operated 3.

Licensed Thermal Power (MWt):

2700 at 2560 MWTH prior to its i

4.

Nameplate Rating (Gross MWe):

909 uprating to the current 5.

Design Electrical Rating (Net MWe):

870 2700 MWTH power level.

6.

Maximum Dependable Capacity (Gross MWe):

893.88 7~

Maximum Dependable Capacity (Net MWe):

862.88 8.

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

N/A 9.

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

N/A

10. Reasons For Restrictions, If Any:

N/A i

This Month Yr. To Date Cumulative

11. Hours In Reporting Period 722 Q 4543.0 127223.0'
12. Number Of Hours Reactor Was Critical 404.1 3451.9 93813.0
13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
14. Hours Generator On Line 380.3 3414.4_

89365.8

15. Unit _ Reserve Shutdown Hours 0.0 0.Q_

468.2

16. Cross Thermal Energy Generated (MVH) 945947.0 9102849.0 247238687.4
17. Cross Electrical Energy. Generated (MWH) 309013.5

.1955975.0.,

74875145.0

18. Net Electrical Energy Generated (MVH) 293833.5 2842763.0 71839397.0
19. Unit Service Factor 52.8 78.6 70.2
20. Unit Availability Factor 52.8 78.6 70 h
21. Unit capacity Factor (Using MDC Net) 47.3 75.9 66.4

.22. Unit Capacity Factor (Using DER Net) 46 2 75.2 65.1

23. Unit Forced Outage Rate 0.0 2.1 13.5
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

End of Cycle 10 Refuel Outage. Sentember 15. 1990. 40 days.

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

N/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

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I AVERACE DAILY UNIT POVF.R LEVEL DOCKET NO.

_50 336 3;

UNIT:

Millstone Unit 2 DATE:

07/06/90 COMPLETED BY:

G. Neron TELEPHONE:

(203)447-1791 EXT:

4417 MONTH:

JUNE 1990 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (NWe-Net)

(NWe-Net) 1 0

17 744 2

0 18 816 3

0 19 859 4

0 20 860 l

5 0

21 859 6

0~

22 858 7

0 23 857 8

0 24 857 9-0 25 858

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10 0

26 858 t

11 0

27 858 12 0

28 857 l

13 0

29 855 14 0

30 854

.15 149 31 16 390 INSTRUCTIONS E

i 1,

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

I

. =

V

.. [.l-DOCKET NO.

50-336' t

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME.

Millstone 2-DATE 07/06/90 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 REPORT MONTH June 1990 EXT..

4417 l

2 No.

Date Type Duration Reason Method of License Systga C qdenent Cause & Corrective (Hours)

Shutting Event Code Co Action to 3

Down Reactor Report #

Prevent Recurrence 03 900510 S

339.7 H

4 N/A N/A N/A Continuation of previous month's S/G inspection and repair outage; The main generator was-placed "on-line" on 6/15/90 and the Unit reached 100% power on 6/18/90.

1:

Forced Reason:

Method Exhibit G - Instructions 2

3 0

F 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 from-(NUREG-0161)

E-Operator Training & License Examination Previous month 5

F-Administrative 5-Power Reduction Exhibit 1 -Same Source G-Operational Error (Explain)

(Duration -0)

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

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REFUELING INFORMATION REOUEST

\\

1.

me of facility:

Millstone 2 l

2.

Scheduled date for next refueling shutdown:

SeDtember 15. 1990

+

3.

Scheduled date for restart following refueling:

N/A 4.

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

YES l

5.

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

ProDosed Technical SDecification submittal for the CORE OPERATIEJ LIMITS REPORT was submitted on 6/26/90f ADDroval is anticiDated prior to restart.

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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, new operating procedures None l

l 7.

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

In Core:

(a) 112 In Spent Fuel Pools (b) gap I

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:

Currentiv 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. SDent Fuel Pool Full 2009. SDent Fuel Pool Full, core off load caDacity is reached-

'ggntinuent uDon full scale storace of consolldated fuel in the i

SDent Fuel Pool.

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