ML20136H311

Monthly Operating Rept for Feb 1997 for Millstone Nuclear Power Station,Unit 2

ML20136H311
Person / Time
Site:	Millstone
Issue date:	02/28/1997
From:	Stark S NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20136H298	List: B16320, Revised Monthly Operating Rept for Jan 1997 for Millstone Nuclear Power Station,Unit 2 ML20136H294 ML20136H311
References
NUDOCS 9703190113
Download: ML20136H311 (6)

Text

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Docket No. 50-336

' B16320 3-i 1

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i Attachment 1 l i

Millstone Nuclear Power Station, Unit No. 2 l J

i Facility Operating License No. DPR i Monthly Operating Report c

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i March 1997 9703190113 970313 PDR ADOCK 05000336l R PDR %

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OPERATING DATA REPORT l

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• UNIT NAME Millstone Unit 2 l

DATE 03/05/97 COMPLETED BY S. Stark TELEPHONE (860)447-1791 EXT 4419 l

OPERATING STATUS l-

! 1. Docket Number 50-336

2. Reporting Period February _1997 Notes: Items 22 and 23 l 3. Utility Contact S. Stark culmulative are weighted

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

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 Thr'ough 8) Since Last Report, l

Give Reasons:

N/A __

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

0 I 11. Reasons For Restrictions, if Any: NRC Category _Ill Facility: NRC Confirmatory Order requiring j implementation of an indepe,ndent corrective action verifica_ tion program; NRC order requiring e third-party review

[ of the employee concerns progra_m,at Millstone 2; design basis verification response pursuant to 10CFR50.54(f).

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 672.0 _

1416.0 185664.0 l 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

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) 1911.0 4194.0 94636989.4

20. Unit Service Factor 0.0 ~

0.0 ^ ^ ~ ~ 62.8

21. Unit Availability Factor ~ U.~0 0.0 63.1

22. Unit Capacity Factor (Using MDC Net) 0.0 0.0 59.5

23. Unit Capacity Factor (Using DER Net) 0.0 0.0 58.7

24. Unit Forced Outage Rate . 100.0 100.0 20.1

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 j COMMERCIAL OPERATION N/A N/A d

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. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-336 4

UNIT Millstone Unit 2

DATE 3/5/97 COMPLETED BY S. Stark i

TELEPHONE' (860) 4471791

EXT 4419 i

MONTH: FEBRUARY 1997 4:

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL

{ (MWe-Net) (MWe-Net) 1 _

0 17- 0 2 0 18 0 1

3 0 19 0 4 0 __

20 0 5 0 21 0 6 0 22 0 L l

7 _

O 23 0 8 O_ 24 0 l 9 0 _

'25 __

0 10 __ , 0_ _ , _ ._ 26 ___

0 11 _ _

0, 27 _.

0 12 _.

O 28 _0 .___ _

13 0 29 _._.__- __

j 14 _ , . _

0,_ _ _ . _ _ _ _ _

30 _ _ _ _ _ . _ _ _

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.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-336 ~

UNIT NAME Millstone Unit 2 DATE 03/05/97 COMPLETED BY S. Stark TELEPHONE (8601 447-1791 EXT 4419 REPORT MONTH: February 1997 2

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 672 B/D 4 N/A N/A N/A Scheduled: Continued mid cycle surveillance testing from previous month.

Forced: Continued from previous month. NRC Category til facility: NRC Confirmatory Order requiring 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).

'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" 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"

REFUELING INFORMATION REQUESI

1. Name of the facility: Millstone Unit 2

2. Scheduled date for next refueling outage: First Quarter of 1999 4

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

The current shutdown is not a refueling outage. 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 16 Technical Soecification Change Reauests currently identified which will be submitted to the NRC orior to startuo. These include the following: 1) Modifv aoplicability and actions associated with Steam Generator blowdown monitor and modifv aoplicability for Cpdensate Polishing Facility Waste Neutralization Sumo. 2) Modifv the minimum  ;

instrument accuraev for Meteorological Tower instrumentation. 3) Make changes to organizational structure and titles in Section 6 of the Technical Specifications. 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 building is breached. due to making both trains of enclosure building ventilation svstem inocerable (unable to create a vacuum within soecified time ,

oeriod). 6) Redefine containment integritv to oermit operator action during penods when containment isolation valves mav be ooened 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 emergencv diesel generator fuel oil storage caoacity issues. 8) Add 2 second time delay 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 contable and add the I reauirement to have at least one train in ooeration whenever fuel movement or crane ooeration is in orogress. Add a reauirement regarding scent fuel cool I ventilation integritv. change the associated action reauirements. change the j surveillance reauirements. and the bases. This change removes the  ;

reauirement for AEAS to be coerating orior to fuel movement. 10) Modifv I action statement of LCO 3.4.1.3 for no shutdown cooling loons coerable. 11)

Revise several surveillance requirements regarding Control Room Ventilation System. 12) Modifv oressurizer oower coerated relief valve Technical Soecifications to sav that LCO 3.0.4 is not aoolicable. Previousiv. Amendment 151 removed this wording. 13) Change LCO 3.2.6 to add a note from the Core Ooerating Limits Reoort and the Deoarture from Nucleate Boiling parameters to the Technical Soecification. 14) Correct RCS Pressure /Temoerature curves due to errors. 15) RPS and ESAS trio action s.tatements allow indefinite bvoass of an inocerable channel. This will be

changed to allow oniv 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before olacing the channel in the trioned condition. 16) Modifv Table 3.7-1 to correct errors. Reactor trio setooints for steam generator safetv valves in Table 3.7-1are incorrectiv based on 107%

oower instead of 106.6%.

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 changes. Large Break LOCA analvsis changes.

and Uncontrolled Rod Withdrawal analvsis changes.

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

In Core: (a) _0_. 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.

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 caoacitv: 1306 storage locations i

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 capacitv_is reached.

2005. Core Full. Soent Fuel Pool Full.

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