B17315, Monthly Operating Rept for May 1998 for Mnps,Unit 2

Monthly Operating Rept for May 1998 for Mnps,Unit 2

ML20249B251
Person / Time
Site:	Millstone
Issue date:	05/31/1998
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B17315, NUDOCS 9806220231
Download: ML20249B251 (7)

Text

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1 Northeas Rope Ferry Rd. (Route 156), W:terfi rd, CT 06385

'+ Nuclear Energy um. con, Noaear ro.cr station l

Northeast Nuclear Energy Comnany

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P.O. Box 128 j

Waterford, CT 06385-0128 (860) 447 1791 Fax (860) 444 4277 The Northeast Utilitica System JJ4 I 51998 Docket No. 50-336 B17315 Re: 10CFR50.71(a) l 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 Monthiv Operatino 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 May 1998.

There are no regulatory commitments contained within this letter.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY A

ga/M J. A. P(is:e Direct # Millstone Unit No. 2

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cc: H. J. Miller, Region i 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 P.esjects Office aper)M20231 990531 PDR ADOCK 05000336 R

PDR

Docket No. 50-336 B17315 i

Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 i

Monthly Operating Report i

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June 1998 i

U.S. Nuclear Regulatory Ccinmission B17315%ttachment 1\\Page 1

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l AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO:

50-336 UNIT:

Millstone Unit 2 DATE:

06/01/98 COMPLETED BY:

S. Stark TELEPHONE:

(860) 447-1791 EXT:

4419 MONTH: MAY.1998 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER 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

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

-12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

' INSTRUCTIONS 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

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U.S: Nuclear Regulatory Commission B17315%techment 1\\Page 2 OPERATING DATA REPORT UNIT NAME: Millstone Unit 2 DATE: 06/01/98 COMPLETED BY:

S. Stark TELEPHONE: (860)447-1791 EXT: 4419 OPERATING STATUS 1.

Docket Number 50-336

2. Reporting Period May 1998 Notes:ltems 22 and 23

3. Utility Contact S. Stark cumulative are weighted 4.

Licensed Thermal Puwer (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 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 Report, Give Reasons:

N/A

10. Power Level To Which Restricted, if any (Net MWe):

0

11. Reasons For Restrictions,if Any:

NRC Category lli 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 2; design basis verification response pursuant to 10CFR50.54(fl.

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744.0 3623.0 196631.0

13. Number Of H. e. Reactor Was Critical 0.0 0.0 121911.7

14. Reactor Reser... uutdown Hours 0.0 0.0 2205.5

15. Hours Generator ca Line 0.0 0.0 116611.9

16. Unit Reserve Shutdown Hours 0.0 0.0 468.2

17. Gross Thermal Energy Generated (MWH) 0.0 0.0 100862506.4

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

19. Net Electrical Energy Generated (MWH)

-1593.0

-8855.8 94610234.4

20. Unit Service Factor 0.0 0.0 59.3

21. Unit Availability Factor 0.0 0.0 59.5

22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 56.1

23. Unit Capacity Factor (Using DER Net) 0.0 0.0 55.4

24. Unit Forced Outage Rate 100.0 100.0 25.7

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

Shutdown at the time of this report

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

To be determined

27. Units in Test Statur (Prior to Commercial Operation):

i Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

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,7 U.S. Nudoar Re0ulatory Commission i

• B17315%ttachment 1Pa08 4 e

REFUELING INFORMATION' REQUEST g;

l.

1.

Name of the facility:

Millstone Unit 2 z2.

Scheduled date for next refueling outage: First Quarter of 2000

3. -. Scheduled date for restart following refueling: Fourth Quarter of 1998 (Note -

o The current shutdown is not a refuelina outaae. This date reoresents the exoected startuo date from the current shutdown.)-

4.

Will refueling or resumption. of - operation thereafter require a technical p

specification change or other license amendment?

q Yes.

There are 25 Technical Specification Chance Reauests or license amendments which are reaulred to be sooroved by the NRC orlor to startuo.

As of June 12.1998.15 reauests have been sent to the NRC. 8 have been aooroved, and 7 have been implemented. The 10 remainina chanaes to be submitted are: 1) Certain RPS and ESAS trios did not consider the uncertainty associated with a Harsh Environment. Some RPS and ESAS setooints were based on 24 months instead of 18 months 2)- Condensate Storaae Tank minimum level. 3) Service Water Coatina (USQ). 4) RCS head vent. 5) EDG

'LCO and GDC 17, 6)

Main Steam Line Ereak Analvsis USQ. 7) Boron

~ Precioltation Hot Leo inlection 8) Larae Break LOCA 9) Lona Term Coolina CST Makeun via Fire Wat.er. and 10) Post Accident Leakaae RWST.

. 5'.

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

' Auaust 31,1998 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 al1alvsis chanaes and Laroe Break LOCA analysis chances.

1 7.

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

In Core: (a)

_Q_

in Spent Fuel Pool: (b) 1085 NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storace Boxes (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) ltem Control Areas.

il, U.fl. Nuclear Regulatory Commission

~ * ' ' 817315%ttachment 1Page 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 j

number of fuel assemblies:

l Present storaae caoacity: 1306 storaae locations l

~ 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.

l 2005 Core Full. Soent Fuel Pool Full.

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