ML20070J413

Monthly Operating Rept for Feb 1991 for Millstone Unit 2.W/

ML20070J413
Person / Time
Site:	Millstone
Issue date:	02/28/1991
From:	Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-220, NUDOCS 9103150391
Download: ML20070J413 (5)

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(203) 665 5000 k

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March 11, 1991 MP-91-220 Re:

10CFR50.71(a)

U.S. Nuclear Fcoulatory Commission Document Contro[ Desk Washington, D. C. 20555 Re fe rence :

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 February, 1991, in accordance with Appendix A Technical Specifications, Section 6.9.1.6.

One additional copy of the report ta enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY ML S tephe/n E. Scace Station Director Millstone Nuclear Power Station SES/JG cc: T. T. Martin, Region I Administrator G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 W. J. Rayet,nd, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 9103150391,7.h,$hhh36 PDR ADOCh -

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OPERATING DATA REPORT DOCKET NO.

50 336 3 ATE 03/06/91 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 i

EXT.

4431

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OPERATING STATUS Notes: Items 21 and 22 1.

Unit Name:

Milistone Unit 2 cumulative are weighted j

2.

Reporting Period:

February 1991 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):

862.83 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-Pe*iod 672.0 1416.0_

133056.0

12. Number Of Hours Reactor Was Critical 656.8 1209.8 98122.4

13. Reactor Reserve Shutdown Hours 0.Q 0.0 2205.5

14. Hours Generator On Line 645.3

.1156.4 93500.2

15. Unit Reserve Shutdown Hours 0.0 0.0 468.2

16. Gross Thermal Energy Generated (HWH) 1687650.0 3011334.0 258067398.4

17. Gross Electrical Energy Generated (MWH) 561376.5 1000317.0 78440016.5

18. Not Electrical Energy Generated (MWH) 540549.5 960695.0 75261744.5

19. Unit Service Factor 96.0 81.7 70.3

20. Unit Availability Factor 96.0 81.7 70.6

21. Unit Capacity Factor (Using MDC Net) 93.2 78.6 66.4 22, Unit Capacity Factor (Using DER Net) 92.5 78.0 65.2

23. Unit Forced Outage Rate 4.0 18.3 13.2

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

N/A

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 l

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AVERACE DAILY UNIT POWER LEVEL DOCKET NO, 50-336 UNIT:

Millstone Unit 2 DATE:

03/06/91 COMPLETED BY:

J. Gibson TELEPHONE:

(2031447 1791 EXT:

4431 MONTH: FEBRUARY 1991 DAY AVC. DAILY POWER LEVEL DAY AVO. DAILY POWER LEVEL (MVe-Net)

(MVe Net) 1 869 17 0

2 872 18 445 3

874 19 573 4

874 20 868 5

875 21 868 6

875 22 870 7

874 23 869 8

873 24 868 9

872 25 869 10 869 26 868 11 869 27 867 12 866 28 869 13 869 29 14 872 30 15 872 31 16 630 INSTRUCTIONS On this format, list the average daily unit power level in HWe Net for each day in the reporting month.

Compute to the nearest whole megawatt.

DOCKET NO.

50-3' UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 03/06/91 COMPLETED BY J. Gibson

~

TELEPHONE (203) 447-1791 REPORT MONTH FEBRUARY 1991 EXT.

4431 l

2 Cause & Corrective No.

Date Type Duration Reason Method of License Systgm Compgnent (Hours)

Shutting Event Code Code Action to 3

Down Reactor Report n Prevent Recurrence I

02 910216 F

26.7 A

2 91-004 SG P

On February 16, 1991, while operating at 100%

power, the

'B' Steam Generator Feed Pump (SCFP) tripped. During recovery of the

'B' SGFP, several addditional SGFP trips were experienced. The reactor was manually tripped due to decreasing steam generator levels. The cause of the initial

'B' SGFP trip is unknown. See LER 91-004.

On February 17, 1991, the Unit was restarted.

The Unit reached 100% power on February 19, 1991.

1: Forced Reason:

Method

' Exhibit G - Instructions 2

3 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)

_.__---a~

REFUELING INFORMATION REOUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutoown:

March 1992 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?

None at this time S.

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:

Mil:. stone 2 will be reolacina the Steam Generator sub-assenblies dur:.no the uncomina End of Cycle 11 refuelina outaae.

It

.s antacinated this will be accomDlished under 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 Fuel Pool:

(b) lla NOTE:

These numbern represent the total fuel assemblies and E20solidated fuel storace boxes in these two (2) Item Control Areas 8.

The present licensed spent fuel pool storage captcity 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. Soent Fue:

Pool Full, core off load capacity is reached (with

-out consolidat:.on).

1998. Core Full. Scent Fuel Pool Full 2009. Spent Fuel Pool Full, core off load capacity is reached-continaent upon full scale storace of consolidated fuel in the Spent Fuel Pool.

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