B16464, Monthly Operating Rept for Apr 1997 for Millstone,Unit 2

Monthly Operating Rept for Apr 1997 for Millstone,Unit 2

ML20141D515
Person / Time
Site:	Millstone
Issue date:	04/30/1997
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16464, NUDOCS 9705200130
Download: ML20141D515 (7)

Text

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- \ Northeast ""pe Feny Rd. (Route IW, Watuford, CF 06385 T(g/f/jf NuclearEnergy stat,ione suaear ro.e, siation Northeast Nudear li.nergy Company P.O. Ikix 128 Waterford, UI 063850128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities Systern MAY l 21997 i

Docket No. 50-336  !

B16464 Re: 10CFR50.71(a)

I 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 Operatina 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 cf April 1997.

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i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY i

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9705200130 970430 PDR ADOCK 05000336 Director, Millstone Unit No. 2 i R PDR I 2ljUUUv

, 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 g 1 )

l Dr. W. D. Travers, Director, Special Projects Office l l

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. Docket No. 50-336  !

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Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 Monthly Operating Report May 1997

. AVERAGE DA!LY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 5/5/97 I

COMPLETED BY S. Stark TELEPHONE (860) 447-1791 EXT 4419 MONTH: APRIL 1997 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 O i

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' O 27 0 12 0 28 0 13 0 29 0 14 0 30 0  !

15 0 _

31 -

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.

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, OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE 05/05/97 COMPLETED BY S. Stark TELEPHONE (860)447 1791 EXT 4419 OPERATING STATUS

1. Docket Number 50-336

2. Reporting Period April 1997 Notes: Items 22 and 23

3. Utility Contact - S. Stark culmulative are weighted

4. Licensed Thermal Power (MWt): 2700 averages. Unit operated at

5. Namepl ate 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. ,1f 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 ill 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(f).

This Month Yr.-To-Date Cumulative

'i2. Hours in Reporting Period 719.0 2879.0 187127.0 ,

13. Number Of Hours Reactor Was Critical 0.0 0.0 121911.7

14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5 15.' Hours Generator On-Line 0.0 0.0 116611.9' i

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

19. Net Electrical Energy Generated (MWH) -2369.2 -8879.2 94632304.2

20. Unit Service Factor 0.0 0.0 62.3

21. Unit Availability Factor 0.0 0.0 62g

22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 59.0

23. Unit Capacity Factor (Using DER Net) 0.0 0.0 58.2

24. Unit Forced Outage Rate 100.0 100.0 20.9

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

Shutdown at the time of this report i

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

27. 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

UNIT SHUTDOWNS ANU POWER REDUCTIONS DOCKET NO. 50-336 UNIT NAME Millstone Unit 2 '.

DATE 05/05/97 COMPLETED BY S. Stark TELEPHONE (860) 447-1791 EXT 4419 REPORT MONTH: APRIL 1997 2

No. Date Type' Duration Reason Method of Licerise System Component Cause & Corrective (Hours) Shutting Evant Code' Code

• Action to Down Reactor Report # Prevent Recurrence 97-01 03/07/96 SiF 719 B/D 4 N/A N/A N/A Scheduled: Continued mid cycle surveillance testing from previous year.

Forced: Continued from previous year. NRC Category til facility; NRC Confirmatory Order requiring l independent corrective action verification: NRC order requiring third party review of Millstone Station employee concerns program; design basis verification for response to NRC pursuant to 10CRF50.54(f).

2 Reason Method 'lEEE Standard 805-1984,

'F: Forced S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices R - 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 & License Examination 5 - Power Reduction (Duration = 0)

S 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"

4 REFUELING INFORMATION REQUEST

1. Name of the facility: Millstone Unit 2

2. Scheduled date for next refueling outage: First Guarter of 1999

3. Scheduled date for restart following refueling: Last Quarter of 1997 (Note -

The current shutdown is net a reiuolina outaae. This date reoresents the exnected startuo date from the current shutdown.)

4. Wiii refueling or resumption of operation there* '+er require a technical specification change or other license amendment?

Yes. There are 15 Technical Soecification Chanae Recuests which will be submitted to the NRC orior to startuo. These include the followina: 1)

Modify anolicabi!itv and actions associated with Steam Generator blowdown monitor and modifv anolicability for Condensate Polishina Facility Waste Neutralization Sumo. 21 Modifv the minimum instrument accuracv for Meteoroloaical Tower instrumentation. 3) Eliminate the reference to the measurement location for the ultimate heat sink. 4) Eliminate the reauirement to enter LCO 3.0.3 when the enclosure buildina is breached, due to makina both trains of enclosure buildina ventilation system inonerable (unable to create a vacuum within specified time oeriod). 5) Redefine containment intearity to aprmit operator action durina ceriods wt - l containment isolation vyys may be ooened under administrative controls. ]

Also relocates the list of containment isolation valves from Technical Soecifications to Technical Rcuoirements Manual. 6) Modifv the bases for specification to resolve the emeraencv digesel aenerator fuel oil storane caoacity issues. 7) Add 2 second time delav to ESFAS Table 3.3-4 8a to be l p_onsistent with 8b. 8) Delete Technical Snecification 3/4.9.14 and Table )

3.9-1. Modifv LCO 3,9.15 to reauire two EBFS trains to be operable and add l 11)e reauirement EL' o at least one train in oneration whenever fuel movement or cran, operation is in oroaress. Add a reauirement reaardina seg.nt fuel o001 ventilation intearitv chance the associated action Ig_quirements, chance the surveillance reauirements, and the bases. This

( chance removes the reauirement for AEAS to be ooeratina orior to fuel j l movement. 9) Modify action statement of LCO 3.4.1.3 for no shutdown l coolina loons onerable. 10) Revise several surveillance requirements reoardina Control Room Ventilation Svstem. 11) Certain RPS and ESAS trio _g i did not consider the uncertaintv associated with a Harsh Environment. Some RP3 and ESAS setooints wgre based on 24 months instead of 18 months.

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12) Verbatim comoliance issues. ECCS throttle valves. AFW surv. 13)

Correct RCS Pressure /Temoerature curves due to errors

14) RPS and ESAS trio action statements allow indefinite bvoass of an inocerable channel. This will be chanced to allow only 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before olacino the channel in the tricoed condition. 15) Modify Table 3.7-1 to correct errors. Reactor trio setocints for steam aenerator safetv valves in Table 3.7-1 are incorrectiv based on 107% cower instead of 106.6%.

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

June 30,1997

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 chances, Larae Break LOCA analvsis channes, and Uncontrolled Rod Withdrawal analvsis channes.

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) 1065 NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storaae Boxes (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.

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 storace caoacity: 1306 storaae locations i

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

2001, Scent Fuel Pool Full, Core offload capacity is reached.  !

2005 Core Full, Sngnt Fuel Pool Full. I 4

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