ML20080T111

Monthly Operating Rept for Sept 1983

ML20080T111
Person / Time
Site:	Millstone
Issue date:	10/13/1983
From:	Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
MP-5443, NUDOCS 8310200167
Download: ML20080T111 (7)

Text

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OPERATING DATA REPORT .

I DOCKET NO. 50-336 DATE 10/13/83 COMPLETED BY J. Gibson TELEPHONE T203) 447-1791 Ext. 4433 OPERATING STATUS

1. Unit Name: Millstone 2 Notes Items 21 and 22

2. Reporting Period: September 1983 cumulative are weighted

3. Licensed Thermal Power (MWt): 2700 ave. unit operated at 2560 4 Nameplate Rating (Gross MWe): 909 MW thermal prior to its

5. Design Electrical Rating (Net MWe): 870 uprating to the current

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

7. Maximum Dependable Capacity (Net MWe): 864 level.

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

Since Last Report, Give Reasons:

N/A

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

10. Reasons For Restrictions, If Any:

N/A This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720 6551 68063 0 3130.5 48365.3

12. Number Of Hours Reactor Was Critical ---

0 0 2205.5

13. Reactor Reserve Shutdown Hours 0 2994.9 46182.2

14. Hours Generator On-Line 468.2 Unit Reserve Shutdown Hours 0 0 15.

Gross Thermal Energy Generated (MWH) 0 7877464 13171669 16.

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

(-3035) 2462401.4 36224214

18. Net Electrical Energy Generated (MWh) 67.9

19. Unit Service Factor 0 45.7 0 45.7 68.5

20. Unit Availability Factor 63.5

21. Unit Capacity Factor (Using MDC Net) 0 43.5 Unit Capacity Factor (Using DER Net) 0 43.2 62.6

22. 19.1

23. Unit Forced Outage Rate 0 13.7 ,

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

Continuation of Refuel / Maintenance Outaae

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved N/A N/A i INITIAL CRITICALITY N/A INITIAL ELECTRICITY N/A N/A N/A C0MMERCIAL OPERATION 8310200167 831013 PDR ADOCK 05000336 R PDR

D AVERAGE DAILY UNIT POWER. LEVEL ,

Y DOCKET NO. 50-336 UNIT Millstone 2 DATE 10/13/83 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 MONTH September 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (ifde-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 C 26 0 11 0 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 tc the nearest whole megawatt.

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DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 10/13/a3 COMPLETED BY J. Gibson REPORT MONTH September 1983 TELEPHONE (203) 44/-1791 Ext. 4431 l 2 No. Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours) Shutting ven Code Code Action to 3

Down Reactor Report # Prevent Recurrence 5 830528 S 720 C 1 N/A N/A P!/A Continuation of Refuel  :

and Maintenance Outage from previous month.

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

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

Docket No. 50-336 Date 10/13/83 Unit Name Millstone 2 1

Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH September 1983 DATE SYSTEM COMPONENT MAINTENANCE ACTION 9/1/83 Service Water "C" Service Water Pump Removed "C" Service Water Pump and Motor

) 9/10/83 RBCCW "B" RBCCW Heat Exchanger Plugged tubes and re-installed manway covers on "B" RBCCW Heat Exchanger 9/10/83 AEAS Actuation Module 613 Replaced Actuation Module 613

> 9/17/83 Main Steam Steam Dryers, SG #1 Removed and reinstalled steam dryers 9/17/83 Main S*.eam Deflector plate, SG #1 Installed new bolts and locking devices on deflector plate

9/17/83 Main Steam Steam Dryers, SG #2 Removed and reinstalled steam dryers 9/17/83 Main Steam Deflector plate, SG #2 Install deflector plate 9/26/83 LPSI "A" LPSI pump Replaced casing gasket on "A" LPSI pump 9/28/83 RPS Low Flow Bistable Replaced Channel D Low Flow Bistable I

Docket No. 50-336 .

Y Date: 10/13/83 Completed By: J. Gibson Telephone: (203) 447-1791 Ext. 4431 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown:

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

3. Schedule date for restart following refueling:

Estimated date for restart is unavailable. NNECo is currently developing a schedule consistent with the repair of the reactor vessel thermal shield. (See LER 83-24)

4. Will refueling or 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.

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

A schedule has not been determined for further submittals.

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significa'nt changes in fuel design, new operating procedures:

Additional plugged S.G. tubes will result in reactor coolant flow reduction. Currently planning to install sleeves in S.G. tubes.

Reactor Vessel thermal shield removal will be necessary prior to

! startup. As previously identified to the NRC, NNECo has identified failed fuel at Millstone Unit 2. The need to replace defective fuel assemblies will impact the core loading pattern and core physics l

l parameters used as input to the safety analyses. The effect of a

! new loading pattern on the ongoing review of docketed material is l not fully apparent at this time; however additional transient analysis may be required if significant loading pattern changes are needed.

(See LER 83-19/3L-1). In addition, recent problems identified with the top nozzles of a number of fuel assemblies (See LERS 83-25 & 83-26) have left uncertainty as to the core loading plan. These problems are currently under review.

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

4 (a) In Core: 0 (b) 535

8. Ti.e present licensed spent fuel pool storage capacity and the size of any increase in licensea 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 .

the spent fuel pool assuming the present licensed capacity:

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

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

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General Offices

• Selcen Street. Berlin. Connecticut g g P mc'eme ac w= cc=-- P.O box 270 l =i '* *$ 5 N W HARTFORD. CONNECTICUT 06141-0270 1',['[1",,7,'*,'[~ ,,,, " (203) 666-6911 e acrea5* Mana teemov:X>em October 14, 1983 MP-5443 Director Office of Management Information and Program Control U. S. Nuclear Pegulatory Commission Washington, D. C. 20555

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336

Dear Sir:

This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 Monthly Operating Report 83-9 in accordance with Appendix A Technical Specifications, L ction 6.9.1.3. One additional ccpy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 7

l E. J. Mroczka l Station Superintendent j

Millstone Nuclear Power Station EJM/JG:jlc cc: Director, Office of Inspection and Enforcement, Region I l

Director, Office of Inspection and Enforcement, Washington, D. C. (10)

U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D.C. 20555 i i4 7

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