B16840, Monthly Operating Rept for Oct 1997 for Mnps,Unit 2

Monthly Operating Rept for Oct 1997 for Mnps,Unit 2

ML20199B098
Person / Time
Site:	Millstone
Issue date:	10/31/1997
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16840, NUDOCS 9711180209
Download: ML20199B098 (7)

Text

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ggg Itope l'erry lid. (Itouie 1T4), Wierferd, CT (%385 Nuclear Energy nai,u.o, Nmie., e., sinia, Northeast Nucleat 11cqry Congiaoy aicif r 0M85 0128 (860) 447 1791 fas (fW ) 444-4277

'n e Northret Utihtice Systein NOV 8 P97 Docket No. 50-336 B16SfD Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No DPR-65 Monthly Operating Report in accordance with the reporting requirements of Technical Specification Section 6.9.1.7 for Millstone Unit No. 2, enclosed, in Attachment 1, is the monthly operating report for the month of October,1997.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY T4 J. A. hice DirectBr, Millstone Unit No. 2 e

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cc: H. J. Miller, Region l Administrator D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, Ph.D, Director, Special Projects Office l~

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t Millstone Nuclear Power Station, Unit No. 2.

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- Facility Operating License No. DPR-65 Monthly Operating Report N

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f B16840\\ Attachment 1\\Page i i

AVERAGE DAILY UNIT POWER LEVEL -

DOCKET NO:.

50-336 UNIT:

Millstone Unit 2 DATE:

11/3/97 COMPLETED BY:-

S. Stark TELEPHONE:

(860) 447-1791 EXT:

4419' MONTH: OCTOBER 1997 DAY-AVG. DAILY POWER LEVEL DAY AVG. DAILY F'OWER LEVEL (MWe-Net) -

(MWe-Net)

~1 0

17 0

2-0 18 0

3 0

19 0

4 0

20 0

-5 0-21 0

6 0

22 0

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0-23 0

8 0-24 0

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~9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

11 4 0

30 0

15 0

31 0

-16 0

-. lNSTRUCTIONS -

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- 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.

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. B16840) Attachment 1\\Page 2.'-

-c OPERATING DATA REPORT.

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' UNIT NAME: Millstone Unit 2 DATE: 11/03/97 COMPLETED BY: - S. Stark i

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TELEPHONE: (860)447 1791 EXT: 4419.

l OPERATING STATUS :

1. ; Docket Number -

50-336..

2 : Reporting Period October 1997 Notes: Items 22 and 23 -

3.

Utility Contact' S. Stark -

cumulative are weighted

- 4.

Licensed Thermal Power (MWt):

2700 averages. Unit operated at

- 5, Nameplate Rating (Gross MWe):

909 2560 MWTH prior to its

6. -_ Design Electrical Rating (Net MWe):

870 uprating to its current L 7.

Maximum Dependable Capacity'(Gross MWe):

901.63 2700 MWTH power level, 8.'

Maximum Dependable Capacity (Net MWe):

870.63 9.~ 'If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Repou, Give Reasons:

N/A I'

' 10.= Power Level To Which %stricted, if any (Net MWe):

0

11. Reasons For Restrictions, if Any:

NRC Category 111 Facility; NRC Confirmatory Order requiring

. implementation of an independent corrective action verification program; NRC order requiring a third party review of the employee concerns program at Millstone 2i design basis verification response pursuant to 1vCFR50.54(fl.

Thia Month Yr. To-Date Cumulative 12; Hours in Reporting Period 745.0 7296.0 191544.0

13. Number Of Hours Reactor Was Critical 0,0 0.0 121911.7

10. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

15. Hours Generator On-Line 0.0 3.0 116611.9

'16. Unit Reserve Shutdown Hours 0.0 0.0 468.2

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 300862506.4

18. Gross Electrical Energy Generated (MWH) 0.0 0.0 98709460.0 19824.6 94623087.8

19. Net Electrical Energy Generated (MWH) 1704.4

30. Unit Service Factor 0.0 0.0 60.9

- 21. Unit Availability Factor 0.0 0.0

- 61.1

- 23. Unit Capacity Factor (Using MDC Net) -

0.0 0.0 57.6

83. Unit Capacity Factor (Using DER Net) 0.0 0.0 56.9 24.. Unit Forced Outage Rate 100.0 100.0 23.2 25.; Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Shutdown at the time of this report i

- 26f if Unit Shu'tdown At End Of Report Period, Estimated Date of Startup:

To be determir'ad

" 37. 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 g

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v-U.S. Nuclear Regulatory Commission B16840%ttachment 1\\Page 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-336 UNIT NAME:

Matistone Unit 2 DATE:

11/03/97-COMPLETED BY:

S. Stark TELEPHONE:

(860) 447-1791 EXT:

4419 REPORT MONTH: October 1997 No.

Date Type' Duration Reason' Method of License System Component Cause & Corrective (Hours)

Shutting Event Code' Code' Action to Down Reactor' Report #

Prevent Recurrence 97-01 03/07/96 S/F 745 B/D 4

N/A N/A N/A Scheduled: Continued cycle surveillance testing from previous month.

Forced: Continued from previous month. NRC Category lit facil;ty: NRC Confirmatory Order requiring independent corrective action verification; NRC order requiring third party review of Millstone Station employee concems program; design basis verification for response to NRC pursuant to10CFR50.54(f).

'F: Forced

• Reason

' Method

• lEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual

" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System Identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & Ucense Examination 5 - Power Reduction (Duration =- 0)

F - Administrative 6 - Other (Explain)

'IEEE Standard 803A-1983, G - Operational Error (Explain)

" Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers'

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U.S. Nuclear Regulatory Commssion -

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- B16840%t'achment 1Page 4 -

REFUELING INFORMATION REQUEST--

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1. - N'ame of the facility: _ Millstone Unit 2 -

-2..

Scheduled date for next rctueling outage: Second Quarter of 1999 3.

- Scheduled date for restart following refueling: First Quarter of 1998 (Note -

The current shutdown is not a refueling outage. This date reoresents the exoected startuo date from the current shutdown.)

4.

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

Yas.

There are 13 Technical Snecification Change Raouests or license amendments 'which are reouired to be nooroved bv the NRC orior to startun.

As of-November 8.- 1997. ~ 10 reouests have been sent to the NRC. 3 have been anoroved. and 2 have been imolemented. The 3 remaining changes to be submitted are: 1) Correct RCS Pressure /Temnerature curves due to errors. 21 Technical Snecification comoliance issues (e.g. mode soolicability for CEA droo -

time ~soecification).- and 3) Certain RPS' and ESAS trios did not' considei the uncertaintv associated with a Harsh EnvirQQment.

Some RPS 'and ESAS setooints were based on 24 months instead of 18 months.

5.

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

December 31.1997 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: Small Break LOCA analvsis changes and Large Break LOCA analvsis changes.

7.

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

pool: ~

In Core: (a)

,_Q In Spent Fuel Pool: (b).1085 NOTE: -These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storage Boxes (3 total containing the fuel rods from 6 fuel assemblies) in these two"(2) Item Control Areas.

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816840%ttachrnent 1\\Page 5 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:-

Present storage canacitv: 1306 storage locations 9.

.The projected date of the last ' refueling that can be discharged to the spent fuel pool assuming present license capacity:

2001. Soent Fuel Pool Full. Core offload caoacity is reached.

2005. Core Full. Soent Fuel Pool Full.

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