B16376, Monthly Operating Rept for Mar 1997 for Mnps,Unit 2

Monthly Operating Rept for Mar 1997 for Mnps,Unit 2

ML20140D760
Person / Time
Site:	Millstone
Issue date:	03/31/1997
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16376, NUDOCS 9704240104
Download: ML20140D760 (7)

Text

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, ' 8l Northeast Hogw Ferry Rd. (Houte 156), Waterford, Cr 06385

'/jf NuclearEnergy suismne soacar Po.er smuon Northeet Nudear Energy Company P.O. Box 128 5

Waterford, Ur 06335-0128 (860) 447.!?91 l Fax (860) 444-4277 1 The Northeast Utilities Systern Mit i 4 ger l

Docket No. 50-336 B16376 1

Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk  !

Washington, DC 20555 I 1

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

. Monthly Operatina Report ,

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E in accordance with the reporting requirements of Technical Specification Section 4

6.9.1.7 for Millstone Unit No. 2, en~J osed, in Attachment 1, is the monthly

operating report for the month of March 1997.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY u

J. A./frice Director, Millstone Unit No. 2 cc: H. J. Miller, Region i Administratot D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 Dr. W. D. Travers, Director, Special Projects Office 240005 ~

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Docket No. 50-336

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i Attachment 1 Millstone Nuclear Power Station, Unit No. 2

Facility Operating License No. DPR45 I

Monthly Operating Report I

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l April 1997

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o. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone Unit 2 DATE 4/1/97 COMPLETED BY S. Stark TELEPHONE (860) 447-1791 EXT 4419 1 1

' MONTH: MARCH .1997 )

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net) (MWe-Net) I 1.. 0 17 0  !

2 0 18 0 3 0 19 0 4 0 20 0 ,

1 5 0 21 0 l 6 0 22 0  !

7 0 23 0 8 _0 24 0 9' O 25 0

-10 0 28 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 l day in the reporting month.- Compute to the nearest whole megawatt.

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, OPERATING DATA REPORT UNIT NAME Millstone Unit 2 l DATE 04/01/97 COMPLETED BY S. Stark TELEPHONE (860)447 1791 EXT 4419 OPERATING STATUS l

1. Docket Number 50-336 l

2. Reporting Period , Mar-97 Notes: Items 22 and 23

~ 3. Utility Contact ji. Stark culmulative are weighted j

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

5. Nameplate Rating (Gross MWe): 909 2560 MWTH prior to its 1

6. Design Electrical Rating (Net MWe): 870 uprating to its current c 1

7. Maximum Dependable Capacity (Gross MWe): 901.63 2700 MWTH power level.  !

8. Maximum Dependable Capacity (Net MWe):' 870.63 ,

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9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report,

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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(f). -

I This Month Yr.-To-Date Cumulative ,

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12. Hours in Reporting Period 744.0 2160.0 186408.0

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13. Number Of Hours Reactor Was Critical 0.0 0.0 121911.7  ;

14. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5 l

15. Hours Generator On-Line 0.0 0.0 116611.9 l

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 l 119, Net Electrical Energy Generated.(MWH) -2316.0 -6510.0 94634673.4  ;

20. Unit Service Factor - 0.0 - 0.0 62.6 1 21, Unit Availability Factor 0.0 0.0 62.8 'I

22. Unit Capacity Factor (Using MDC Net) - 0.0 0.0 59.3 23.' Unit Capacity Factor (Using DER Net) 0.0 0.0 58.5

24. Unit Forced Outage Rate 100.0 100.0 20.5 ]

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 Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY .

N/A N/A i INITIAL ELECTRICITY ~ N/A N/A COMMERCIAL OPERATION N/A N/A l I

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I UNIT SHUTDOWNS AND POWER REDUCTIONS '

DOCKET NO'. 50-336 -

UNIT NAME Millstone Unit 2 -

DATE 04/01/97 -

i COMPLETED BY S. Stark TELEPHONE - (860) 447-1791  !

EXT 4419  :

REPORT MONTH: MARCH 1997 2

No. Date Type' Duration - Reason Method of License System Component Cause & Corrective l (Hours) Shutting Event Code' Code' Action to  ;

Down Reactor Report # Prevent Recurrence i

97-01 03/07/96 S/F 744 B/D 4 N/A N/A N/A Scheduled: Continued mid  ;

cycle surveillance testing from previous year. l t

Forced: Continued from ,

previous year. NRC [

Category lli facility; NRC +

Confirmatory Order requiring independent corrective  ;

action verification; NRC ,

order requiring third party l review of Millstone Station j employee concerns program; design basis verification for response to NRC pursuant to 10CRF50.54(f).

'F: Forced Reason Method 'IEEE 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" j E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)  :

F - Administrative 6 - Other (Explain) "lEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in i Power Plants and Related i Facilities - Component Function Identifiers .

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= , 1 REFUELING INFORMATION REQUEST l

1. Name of the facility: Millstone Unit 2

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

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

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 specification change or other license amendment?

_Yes. There are 17 Technical Soecification Chance Reauests which will be submitted to the NRC orior to startuo. These include the followina: 1)

Modify aoolicability and actions associated with Steam Generator blowdown monitor and modifv aoolicability for Condensate Polishina Facility Waste Neutralization Sumo. 2) Modifv the minimum instrument accuracv for Meteoroloaical Tower instrumentation. 3) Make channes to oraanizational structure and titles in Section 6 of tile Technical Soecifications. 4) Eliminate the reference to the measurement location for the ultimate heat sink. 5)

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 inocerable (unable to create a vacuum within soecified time oeriod). 6)

Redefine containment intearity to oermit ooerator action durina oeriods when p_ontainment isolation valves may be onened under administrative controls.

Also relocates the list of containment isolation valves from Technical Soecifications to Technical Reauirements Manual. 7) Modifv the bases for soecification to resolve the emeraencv diesel aenerator fuel oil storaae caoacity issues. 8) Add 2 second time delav to ESFAS Table 3.3-4 8a to be consistent with 8b. 9) Delete Technical Soecification 3/4.9.14 and Table 3.9-1. Modifv LCO 3.9.15 to reauire two EBFS trains to be ooerable and add the reauirement to have at least one train in ooeration whenever fuel movement or crane coeration is in oroaress. Add a reauirement reaardina scent fuel o001 ventilation intearitv. chanae the associated action reauirements, chanae the surveillance reauirements, and the bases. This channe removes the reauirement for AEAS to be operatina orior to fuel movement. 10) Modifv action statement of LCO 3.4.1.3 for no shutdown 3 coolina loons ooerable. 11) Revise several surveillance reauirements j reaardina Control Room Ventilation Svstem. 12) Modifv oressurizer oower operated relief valve Technical Soecifications to sav that LCO 3.0.4 is not anolicable. Previousiv. Amendment 151 removed this wordina. 13) Chanae LCO 3.2.6 to add a note from the Core Operatina Limits Report and the Recarture from Nucleate Boilina carameters to the Technical Snecification.

14) Correct RCS Pressure /Temoerature curves due to errors.15) RPS and ESAS trio action statements allow indefinite b am31.gf an inocerable channel l

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This will be chanced to allow oniv 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before olacina the channel in the L trinoed condition. - 16) Modifv Table 3.7-1 to correct errors. Reactor trio

setooints for steam aenerator safetv valves in Table 3.7-1are incorrectiv I

based on 107% oower instead of 106.6 %. 17) Need to add a new RPS trio

. for MSIV closure.

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

Aoril 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 chanaes. Larae Break LOCA analysis chanaes, and Uncontrolled Rod Withdrawal analvsis chanaes.

-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 Fue! Storace 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 storaae capacitv: 1306 storaae 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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