ML20082T193

Monthly Operating Rept for Oct 1983

ML20082T193
Person / Time
Site:	Millstone
Issue date:	11/14/1983
From:	Gibson J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20082T191	List: ML20082T188 ML20082T193 ML20082T308 ML20082T315 ML20082T321 ML20082T332 ML20082T336 ML20082T341
References
NUDOCS 8312150215
Download: ML20082T193 (5)

Text

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OPERATING DATA REPORT DOCKET NO. 50-336 __

DATE 11/14/83

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COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 i Ext. 4431 OPERATING STATUS i

1. Unit Name:~ .M111 stone-2~ Notes Items 21 and 22

2. Reporting Period: October 1983- cumulative are weighted

3. Licensed Thermal. Power (MWt)

2700 Ave. unit operated at 4.- Nameplate _ Rating (Gross MWe): 909 2560 MW thermal prior

5. Design Electrical Rating (Net MNe): 870 to its uprating to the

6. Maximum Dependable Capacity (Gross MWe): -895 current 2700 MW thermal

7. Maximum Dependable Capacity (Net MWe): 664 power level.

8._ .If Changes Occur in Capacity _ Ratings (Items Number 3 Through 7)

-Since Last. Report,;Give Reasons:

NA ,

l

9. Power Level To Which Restricted. If Any (Net MWe): N/A l

10. Reasons For Restrictions, If Any:

N/A 4

This Month Yr.-tc-Date Cumulative r

'11. Hours-In Reporting Period .

745 7296 68808

12. . Number;0f Hours Reactor Was Critical 0 3130.5 48365.3 E13. ' Reactor Reserve Shutdown Hours 0 0 2205.5

.14. Hours Generator On-Line 0 2994.9 46182.2 15.' Unit Reserve Shutdown Hours 0 0 468.2 16.. Gross Thermal Energy Generated (MWH) 0 7877464 116311669

~17. Gross ~Elec. Energy Generated (MWH) 0 2575530 37806378

! 18. Net Electrical Energy Generated (MWH) (-2692) 2459709.4 36221522

19. Unit Service Factor 0 41.0 67.1

20. Unit Availability Factor 0 41.0 67.8

21. Unit Capacity Factor (Using MOC Net) 0 39.0 62.7 i 22. Unit Capacity Factor (Using DER Net) 0 38.8 61.9

23. Uni't Forced. Outage Rate 0 13.7 19.1

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

. Continuation of Refuel / Maintenance Outage

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. : 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

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, 8312150215 831115

PDR ADOCK 05000336 R PDR

AVERAGE DAILY UNIT POWER LEVEL I

DOCKET NO. 50-336 UNIT Millstone 2 DATE 11/14/83 COMPLETED BY J. Gioson TELEPHONE (203) 447-1791 ,

EXT. 4431 MONTH October 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE 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.

DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 ,

-DATE 11/14/83 COMPLETED BY J. Gibson .

REPORT MONTH October 1983 TELEPHONE (203) 447-1791 Ext. 4431 1

No. Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours) Shutting 3

Event Code Code Action to Down Reactor Report # Prevent Recurrence 5 830528 S 745 C 1 N/A N/A N/A Continuation of Refuel and Maintenance Outage ,

from previous month i

1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data i B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exihibit 1 - Same Source H-Other (Explain)

Docket No. 50-336 Date 11/14/83 .

Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1791 EXT. 4431 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH October 1983 DATE SYSTEM COMPONENT MAINTENANCE ACTION 10/3/83 Safety Injection Safety Valve 2-51-466 Adjusted blowdown ring, overhauled and tested valve.

10/4/83 Diesel Generator "A" Lube Oil Cooler "A" Lube oil cooler vent line  !

installed l I i 10/4/83 Diesel Generator "A" Heat exchanger Thermometer well modification 10/6/83 Safety Injection Safety Injection Tank Installed "0" rings and torqued Level Transmitters covers to environmentally l qualify transmitters. )

10/21/83 RPS Trip unit power supplies Replaced Channel A, 8, and C Trip Unit power supplies.

10/27/83 Main Steam Safety Valve 2-MS-254 Installed 2-MS-254 10/28/83 Main Steam Safety Valve 2-MS-244 Installed 2-MS-244 10/31/83 ESAS Actuation Module S.N. 058 Replaced failed component in f i

actuatior,aodule.

10/31/83 RPS Potentiometer Channel "B" cold voltage adjustment potentiometer replaced i

c. -

- Docket No:'50-336-Date': -11/14/83 Completed By: J.- Gibson

-Telephone: (203) 447<1791 Ext. 4431 REFUELING INFORMATION REQUEST

. 1. fName of facility: Millstone 2 2f. Scheduled date for next re' fueling shutdown:

Currently;in Refuel /Mantenance Outage which commenced May 28, 1983.

'3. Schedule date for restart following refueling: Estimated date for

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restart. is reactor critical on Dec. 31, 1983; Turbine On-Line Jan. 5, 1984. NNECo is currently working to a schedule consistent with the removal of the reactor vessel thermal shield and examination of the Core Support Barrel.

4. Will refueling er resumption of operation.thereafter require a technical specification change or.other license amendment?

'It is anticipated'that Cycle 6 operations will require Technical Specification changes or other License amendments. Supporting information has already been submitted.

t

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

Reassessments of the small & large break LOCA analyses were submitted on Nov. 2, 1983. This reassessment of the LOCA analyses takes into

. account the thermal shield removal and Cycle 6 core redesign characteristics.

.A' supplement to the Reload Safety Evaluation (RSE) Report will be ser.t on about Nov. 7, 1983 to address the Cycle 6 core redesign. Further transmittals will be made on the effects of thermal shield removal.

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:

Steam Generator sleeves have been installed as well as some Steam Generator Tube plugging has been performed. The Thermal Shield has been removed from the Core Support Barrel. The Core Support Barrel

'is' currently being inspected.

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

(a). In Core: 0 (b) 505

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:

667

9. The projected date of the last refueling that can be discharged to othe spent fuel pool assuming the present licensed capacity:

1985, Spent Fuel Pool, Full core off load capacity is reached.

'1987, Core Full, Spent Fuel Pool contains 648 bundles.

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