B16519, Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station,Unit 2

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

ML20148N375
Person / Time
Site:	Millstone
Issue date:	05/31/1997
From:	Price J, Stark S NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16519, NUDOCS 9706270090
Download: ML20148N375 (7)

Text

Ndeast Rope Fctry Rd. (Route 156), Witedord, CT 06385

1. ///])I NuclearEnergy niiistone Nuci,ar power station Northeast Nuclear Energy Company P.O. Box 128

' Watedord. CT 06385-0128 l (203) 447 1791 Fax (203) 4444277 The Northeast Utilities System Docket No. 50-336 B16519 JUN i 31997 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 1

Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No. DPR-65 Monthiv Operatina Report in accordance with the reporting requirernents of Technical Specification Section 6.9.1.7 for Millstone Unit No. 2, enclosed in Attachment 1, is the monthly operation report for the month of May 1997. 3 i

NORTHEAST NUCLEAR ENERGY COMPANY A a J.A.P@ j Directobl Millstone Unit No. 2 l i

cc: H. J. Miller, Region I Administrator  !

D. G. Mcdonald, Jr., NRC Project Manager, Millstone Unit No. 2 j D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 i W. D. Travers, PhD, Director, Special Projects Office  !

9706270090 970531 PDR ADOCK 05000336i }

R PDR amm m. vu IIIh$$ $$$,I$$fllllll

1 Docket No. 50-336 B16519 4

?

4 1

T l

4 i

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

Facility Operating License No. DPR45 Monthly Operating Report ,

1 1

1 i

l June 1997 e

AVERAGE DAILY UNIT POWER LEVEL l

• l

]

l l

DOCKET NO. 50-336 UNIT Millstone Unit 2  !

DATE 6/6/97 ' -]

COMPLETED BY S. Stark l TELEPHONE (860) 447-1791 EXT 4419 1

l l MONTH: MAY 1997 l

DAY AVG. DAILY POWER LEVEL DAY AVG DAILY POWER LEVEL (MWo-Net) (MWe-Net)

! \

l 1 0 17 0 'l

. i

! 2 _

0 18 0  !

3 0 19 0 4 0 20 0

! 5 0 21 0 6 __ _

0 __

22 _.

O _

7 __

O 23 _ _ ,_

0 8 0 24 0 9 0_ 25 0 10 _

0 26 _

0 11 0 -

27 0 -.

12 _

O 28 0 ,

13 0 29 0 . . - . - - -

14 0 30 0 16 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 l

OPERATING DATA REPORT UNIT NAME Millstone Unit 2 DATE OW65T97 COMPLETED BY S. Stark TELEPHONE (

__860) 447-1791 EXT 4419 _

l OPERATING STATUS

1. Docket Number 50-336 E]l y]917 ]

~~~

2. Reporting Period liotes: Items 22 and 23 l l

3. Utility Contact culmulative are weighted S. Stark _

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):

7.

((_~))f0 ] ____ _

uprating to its current Maximum Dependable Capacity (Gross MWe):

8. Maximum Dependable Capacity (Net MWe):

_ 901.63 _ _

u _70_02 MWTH power level. ,

9.

._ 87_0.6'4 _ _

l If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, I Give Reasons:

N/A

10. Power Level To Which Restricted, 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 OI_the employee co9cerns_ program at Millstone _2; design bas _is_ve_rifica_ tion respons,e pursuant to 10CFR50.54(f).

This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 744.0 3623.0 187871.0

13. Number Of Hours Reactor Was Critical ~d3 --- 03 ~ EI5lTJ 1

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) 0.6 03 ~3UUii52ii66 4~~

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

19. Net Electrical Energy Generated (MWH) -2050.7 -10929.9 94630253.5

20. Unit Service Factor 0.0 0.0 62.1

21. Unit Availability Factor 0.0 0.0 62.3

22. Unit Capacity Factor (Using MDC Net) - ' ~ ~ ~00 0.0 58.8

23. Unit Capacity Factor (Using DER Net) 0.0 0.0 58.0

24. Unit Forced Outage Rate 100.0 100.0 21.3

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

Shutdown at the time of this report

~ ~ ~ ~ ~ ~ ~

267if linit 5fiutdiwi t EniO[ lip 5rTPeriod,is~tiria~ted Daieif 5 tar 5p:~ ~

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

To be deteimine(( _))[

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A ~-

N/A '-

COMMERCIAL OPERATION _ _ - - -

~R/4 _-__ _A TA '.-_ _

UNIT SHUTDOWNS AND POWER REDUCTIONS

• DOCKET NO. 50-336 -

j UNIT NAME Millstone Unit 2 '

i DATE 06/02/97 [

COMPLETED BY S.' Doboe l TELEPHONE (8601 447-1791 EXT 4419 REPORT MONTH: May 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 ,

i l

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. i i

Forced: Continued from f previous year. NRC l Category ill facility; - NRC [

Confirmatory Order requiring  !

independent corrective - [

action verification; NRC [

order requiring third party review of Millstone Station r employee concerns program; j design basis verification for }

response to NRC pursuant to l 10CRF50.54(f).

t

'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 Frevious Month Related Facilities" 3 E - Operator Training & License Examination 5 - Power Reduction (Duration = 0) 5 F - Administrative 6 - Other (Explain) 1EEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices 3 H - Other (Explain) for Unique identification in  !

Power Plants and Related j Facilities - Component  !

Function Identifiers" t

l. ,

- a

('

i REFUELING INFORMATION REQUEST I

r

1. Name of the facility: Millstone Unit 2

2. Scheduled date for next refueling outa9a: first Quarter of 1999

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 15 Technical Soecification Change Reauests which will be submitted to the NRC orior to startuo. These include the following: 1)

Modifv aoolicabilitv and actions associated with Steam Generator blowdown monitor and modifv anolicabilitv for Condensate Polishing Facility Waste

Neutralization Sumo. 2) Modifv the minimum instrument accuraev for Meteorological 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 building is breached. due to making both trains of enclosure building ventilation system inocerable (unable to create a vacuum within soecified time oeriod). 5) Redefine containment integrity to oermit ooerator action during oeriods when containment isolation valves may be ooened under administrative controls.

Also relocates the list of containment isolation valves from Technical Soecifications to Technical Reauirements Manual. 6) Modifv the bases for soecification to resolve the emergencv diesel generator fuel oil storage caoacitv issues. 7) Add 2 second time delav to ESFAS Table 3.3-4 8a to be consistent with 8b. 8) Delete Technical Soecification 3/4.9.14 and Table 3.91. Modifv LCO 3.9.15 to reauire two EBFS trains to be coerable and add the reauirement to have at least one train in ooeration whenever fuel movement or crane ooeration is in orogress. Add a reauirement regarding soent fuel cool ventilation integritv. change the associated action reauirements change the surveillance reauirements and the bases. This change removes the reauirement for AEAS to be coerating orior to fuel movement. 9) Modifv action statement of LCO 3.4.1.3 for no shutdown cooling loons coerable. 10) Revise several surveiljance reauirements agarding Control Room Ventilation Svstem. 11) Certain RPS and ESAS trios did not concider the uncertaintv associated with a Harsh Environment. Some RPS and ESAS setooints were based on 24 months instead of 18 months.

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

[

Correct RCS Pressure /Temoerature curves due to errors.

n . - , -. - - - , - , - , , , , ., ,

r~

~

1' '

i ,

14) RPS and ESAS trio action statements 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. 15) Modifv Table 3.7-1 to correct errors. Reactor trio setooints for steam generator safetv valves in Table 3.7-1 are incorrectiv based on 107% oower instead of 106.6%.

i

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

.c Julv 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 ,

l pool: '

In Core: (a) _Q. In Spent Fuel Pool: (b) 1085 i

[ NOTE: These numbers reoresent the total Fuel Assemblies and Consolidated Fuel Storace Boxes (3 total containino the fuel rods from 6 fuel i assemblies) in these two (2) Item Control Areas. I

1

?

8. The present licensed spent fuel pool storage capacity and the size of any 1

increase in licensed storage capacity that has been requested or is planned, in l number of fuel assemblies:

Present storage caoacitv: 1306 storage locations 4

4 d

9. The projected date of the last refueling that can be discharged to the spent

, fuel pool assuming present license capacity:

2001. Spent Fuel Pool Full. Core offload caoacitv is reached. _  ;

2005.~ Core Full. Soent Fuel Pool Full. j 4

a 1

l W

e w - , , -