ML20100L536

Monthly Operating Rept for Oct 1984

ML20100L536
Person / Time
Site:	Millstone
Issue date:	10/31/1984
From:	Kelley J, Neron G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
References
MP-6436, NUDOCS 8412110584
Download: ML20100L536 (6)

Text

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' AVERAGE DAILY UNIT P0WER LEVEL

' DOCKET NO. 50-336 UNIT Millstone'2 l.

L~ DATE 11-9-84 COMPLETED BY G. Neron-TELEPHONE 203/447-1791 Eit. 4417 MONTH October 1984 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ~

(MWe-Net) (MWe-Net) 1 831 17 831 2 832 18 704 3 832 19 830 4 831 20 830 5 832 21 832 6 832 22 830 7 833 23 832 8 832 24 832 9 831 25 832 10 831 26 832 11 831 27 832 12 831 28 831 13 831 29 831 14 832 30 832 15 832 31 834 16 833

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.

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_ OPERATING DATA REPORT

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-DOCKET NO. 50-336-

, DATE 11-9 -  : COMPLETED BY G. Neron TELEPHONE 203/447-1791-OPERATING STATUS

1. -Unit Name: Millsto Unit 2 -Notes Items'21'and 22 cum-

2. Reporting Period: October 1984 ulative are weighted ave.

3. Licensed Thermal Power (MWt): 2700 Unit operated at 2560 MW :

4. - , Nameplate Rating (Gross MWe)

909 . thermal prio'r to its up-

'5. - Design Electrical Rating (Net MWe): 870 rating to the: current

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

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

-8. .If Changes-Occur in Capacity. Ratings (Items Number 3 Through37)

(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 .

-745' '7320 77592

12. Number Of Hours Reactor Was Critical 745- 7196.9 55562.2-

13. Reactor Reserve Shutdown Hours 0 0 2205.5

.14. Hours Generator On-Line 745 6894.1- =53076.3-

15. Unit Reserve Shutdown Hours 0 0 468.2

16. Gross Thermal. Energy Generated (MWH) ,_ -2001607 17912666 - 134224335

17. Gross Elec. Energy Generated (MWH) 639300 5748701- 43555079_

18. Net Electrical Energy Generated (MWH) 616372 5525511- 41741212 Unit Service Factor 94.2 68.4-

19. 100

20. Unit Availability Factor . 100 -94.2 69.0

21. Unit Capacity Factor (Using MDC Net) _ 95.8 87.4 63.9-l 22. Unit' Capacity Factor (Using DER _ Net) 95.1 86.8 63.1

'~ 23. Unit Forced Outage Rate 0 2.5 17.3-

24. . Shutdowns Scheduled Over Next_6' Months-(Type, Date, and Duration of Each):

Millstone Unit 2 is scheduled to shutdown in February 1985 for a 16-week Refueling

!, and Maintenance Outage

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A 26.~ Units In Test Status (Prior to Commercial-Operation): Forecast Achieved-l

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMERCIAL OPERATION N/A ,N/A l

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DOCKET NO. 50-336

UNIT SHUTDOWNS AND POWER REDUCTIONS' UNIT NAME Millstone 2 DATE 11-9-84 COMPLETED BY G. Neron REPORT MONTH October 1984 TELEPHONE 203/447-1791 Ext. 4417 Typel Duration 2 No. Date Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours) Shutting 3 Event Code Code Action to Down Reactor Report # Prevent Recurrence 11 841018 F 0 A 5 N/A AA ROD' While at 100%

power-CEA #48 I dropped into core

] due to power supply failure.

. Power was reduced' to < 70% power-l! and CEA was recovered N

1 2 3 4 i F: Forced Reason: Method: Exhibit G - Instructions l S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File i D-Regulatory Restriction 4-Continued from (NUREG-0161) i E-Operator Training & License Examination previous month

! F-Administrative 5-Power Reduction 5 j G-Operational Error (Explain) (Duration = 0) . Exihibit 1 - Same Source H-Other.(Explain) 9-Other (Explain)

-c Docket No. 50-336 .,

Date 11-9-84 'I Unit Name Millstone 2 Completed By G. Neron Telephone 203/447-1791 Ext. 4417 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT-MONTH October 1984 DATE SYSTEM COMPONENT MAINTENANCE ACTION ,

10/11/84 Clean Liquid Radwaste "A" Coolant Waste Monitor Adjusted packing to stop packing Tank Mixer Shaft leak 10/12/84 Main Steam #1 S/G Blowdown to Quench Welded and machined to effect Tank Control Valve repair on bonnet steam cut leak' 10/17/84 CVCS "C" Charging Pump Replace baffle' stuffing box plunger packing to stop oil' leak 10/22/84 Service Water FE-6923 Isolation Valve Threaded 90* elbow installed to and Nipple relieve plugging 10/16/84 Reactor Protection Wide Range Drawer RPS-D Replaced bad relay on A8 card and resoldered point 19-21 10/17/84 Process and Area Spent Fuel Pool Radiation Replaced photomJ1tiplier tube Radiation Monitoring Detector (West) and recalibrated 10/23/84 Process and Area Spent Fuel Pool Radiation Replaced photomultiplier tube Radiation Monitoring Detector and recalibrated 10/24/84 Process and Area Spent Fuel Pool Radiation Replaced photomultiplier tube Radiation Monitoring Detector (South) and recalibrated 10/30/84 Reactor Coolant and Pressurizer Pressure E to Replaced PY-1028-2 and Vessel I Converter PY-8114-2, indicator; calibrated and replaced PS 1028

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-Docket No. 50-336 Date: 11-9-84 i Completed By: G. Neron Telephone: 203/447-1791-Ext. 4417 REFUELING INFORMATION REQUEST l

1. Name of facility: Millstone 2  ;

2. Scheduled date for next refueling shutdown: Next refueling is in February 1985.

3. Schedule date for restart following refueling: June 1985

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

Currently under evaluation due to the impact of failed fuel.

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

4th quarter of 1984.

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:

Discharge of failed fuel will impact reload analysis.

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

(a) In Core: 217 (b) 376

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:

Currently 667 Plans are being formulated to rerack the spent fuel pool.

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

Ic?,5, Spent Fuel Pool, Full core off load capacity is reached.

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

O gg General Offices

• Selden Street. Serlin, Connecticut

,",,71%*g* [*,' "," P.O. BOX 270

.aos .uin w co,. HARTFORD CONNECTICUT 06141-0270 g g g as e cow- (203)666-6911 November 9, 1984 MP-6436 Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

Facility Operating License No. OPR-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 84-10 in accordance with Appendix A Technical Specifications, Section 6.9.1.3. One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: E. J. Mroczka Station Superintendent Millstone Nuclear Power Station A

BY: J. J. Kelley l Unit 2 Superintendent Millstone Nuclear Power Station i

! EJM/GN:jic 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 8

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