ML20066E626

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Monthly Operating Rept for Dec 1990 for Millstone Unit 2
ML20066E626
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/31/1990
From: Gibson J, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-31, NUDOCS 9101220122
Download: ML20066E626 (5)


Text

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.6J ZZ".lOf07' igg (203) oosmo January 11, 1991 MP-91-31 Re: 10CFR50.71(a)

I U.S. Nuclear Ragulatory Commission -l Document Control Desk Washington, D. C. 2055$

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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 month of December, 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,.

NORTHEAST NUCLEAR ENERGY COMPANY j StephenE./cace S '

Station Director -l Millstone Nuclear Power Station SES/JC cc: T. T. Martin, Region I Administrator j C. S. Vissing, NRC Project Manager, Millstone Unit No. 2  ;

V. J. Raymond, Senior Resident Inspector, Millstone-Unit Nos. 1, 2 & 3 i

1 9101220122 901231 PDR T' 2h R ADOCK 05000336 '

PDR ,

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OPERATING DATA REPORT DOCKET NO. 50 336 DATE 01/07/91 COMPLETED BY J. Gibson TELEPHONE (203) 447 1791 EXT. _4,431 OPERATING STATUS Notes: Items 21 and 22

1. Unit Name: Millstone.pnit 2 cumulative are weighted
2. Reporting Period: December 1990 averages. Unit operated
3. Licensed Thermal Power (MWt): 2700 at 2560 MWTH prior to its
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,,53,
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 MWe): N/A
10. Reasons For Restrictions, If Any: N/A This Month Yr..To Date Cumulative
11. Hours In Reporting Period 744.0 8760.0 131640.0 12 Number Of Hours Reactor Was Critical 684 1 6551.5 96912.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
14. Hours Generator On Line 676.8 6392.4 92343.8
15. Unit Reserve Shutdown Hours 0.0 _ 0.0 468.2
16. Gross Thermal Energy Generated (MWH) 1822046.0 16920226.0 255056064.4 17 Gross Electrical Energy Generated (MWH) 610623.0 5520529.5 'r7439699.5
18. Not Electrical Energy Generated (HWH) 588794.0 5304415.5 74301049.1
19. Unit Service Factor 91.0 73.0 70.1 20, Unit Availability Factor 91.0 ,__ 73.0 70.5 i
21. Unit Capacity Factor (Using MDC Net) 91.7' 70 1_ 66.3 l 22. Unit Capacity Factor (Using DER Net) 91.0 69.6 65.0 l 23. Unit Forced Outage Rate 9.0 2.7 13.2 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25, If Unit Shutdown At End Of Report Period Estimated Date of Startup: January 7. 1991

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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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 336 UNIT: Millstone Unit 2  :

DATE: <01/07/91 COMPLETED BY J. Gibson TELEPHONE: (2031447 1791 EXTt _4431 MONT;1: DECEMBER 1990 DAY AVG. DAILY POWER LEVEL DAY AVO, DAILY POWER LEVEL (KWe Net) (MWe Net) 1 874 17 874 2 875 18 875 3 873 19 875 4 875 20 873 5 872 21 875 6 873 22 876 7 874 . 23 876 8 874 24 875 9 873 25 873 10 874 26 874 11 873 27 873 12 874 28 874 13 875 29 74 14 874 30 0 15 874 31 0 16 874 INSTRUCTIONS On this format, list the average daily unit power level in KWe Net for each day in the reporting month. Compute to the nearest whole megawatt,

- _ _ _ __ _ _ _ _ . _ _ _ _ . . . _ _ _ .___ _ _ _ _ _ _ , = _ _ _ _ . . _ _ . _ . _ _ _ _ .

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i UDCKET Wo. 50-336 ~

UNIT SHUTD(L35 AND PO*.iER REDUCTIONS l' NIT NAME Millstone 2 UATE 01/07/91 '

COMPLETED BY J. Gibsen TELEPHONE (203) 447-17?1  !

REFORT MONTH DECEMBER 1990 EXT. 4431 I i

i No. Date Type l Duration Reason2 Method of License Systgm Component Cause & Corrective  !

(Hours) Shutting Event Code Code > Action to i Down Reactor 3 Report

  • Prevent Recurrence i

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! 06 901229 F 67.2 A 1 N/A N/A N/A khile operating at 100% l power, unidentified RCS .

l 1eakage increased.  !

Identified 4 steam gener-ator primary manways '

leaking. Replaced gaskets i

' and diaphrams. Unit still {

l in cold shutdown at the  ;

end of report period.

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! I F: Forced 2Reason: 3 Method 0 Exhibit G - Instructions

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License f
. C-Refueling 3-Automatic Scram. Event Report (LER) File "

D-Regulatory Restriction 4-Continued from (NUREG-0161) ,

E-Operator Training & License Examination Previous month ,

F-Administrative 5-Power Reduction S Exhibit 1 -Same Source G-Operational Error (Explain) (Duration -0)

H- Other (Explain) 6-Other (Explain) i 1

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' p REFUELING INFORMATION REOUEST

1. Name of facility: Millstone 2
2. Scheduled date for next refueling shutdown: March 1992
3. Scheduled date for restart following refueling: N/A 1
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

None at this time-

, 5. Scheduled date(s)- for submitting licensing action and supporting information:

None

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 ,

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools In Cores (a) 212 In Spent Fuel Pools (b) _ lla
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:

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. Suent Pue: Pool Full, core off load caDacity is reached (with

-out consolidat:.on).

1998 -Core Full.-Soent Fuel Pool Full 2219_. SDent Fuel Pool Full, core off load caDacity is reached-contirig;3t uDon full scale storace of consolldated fuel in the Socnt Fuel Paol.

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