ML20133G458

Monthly Operating Rept for May 1985

ML20133G458
Person / Time
Site:	Millstone
Issue date:	05/31/1985
From:	Neron G, Romberg W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
MP-7002, NUDOCS 8508080691
Download: ML20133G458 (12)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 6/13/85 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Ext. 4417 MONTH May 1985 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.

8508080691 850531 1 PDR ADOCK 05000336 )

R. PDR

OPERATING DATA REPORT DOCKET N0. 50-336 DATE 6n3/av COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Ext. 4417 OPERATING STATUS

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

. 2. . Reporting Period: May 1985 cumulative are weighted

3. Licensed Thermal Power (MWt): 2700 averages. Unit operated

4. Nameplate Rating (Gross MWe): 909 at 2560 MW thermal prior

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

6. Maximum Dependable Capacity (Gross MWe): 866.25 2700 MW thermal power level.

7. Maximum Dependable Capacity (Net MWe): 833.25

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 744 3623 82679

12. Number Of Hours Reactor Was Critical 0 1112.1 58074.2

13. Reactor Reserve Shutdown Hours 0 0 2205.5

14. Hours Generator On-Line 0 1109.8 55502.8

15. Unit Reserve Shutdown Hours 0 0 468.2

16. Gross Thermal Energy Generated (MWH) 0 2895103 140579560

17. Gross Elec. Energy Generated (MWH) 0 945800 45627479

18. Net Electrical Energy Generated (MWH) (-2686) 900701 43724224

19. Unit Service Factor 0 30.6 67.1

20. Unit Availability Factor 0 30.6 67.9

21. Unit Capacity Factor (Using MDC Net) 0 29.8 63.2

22. Unit Capacity Factor (Using DER Net) 0 28.6 62.3

23. Unit Forced Outage Rate 0 0 16.8

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

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup: June 1985

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

H DOCKET NO. 50-336 UNIT SHUTDOWNS AN0' POWER REDUCTIONSL UNIT NAME Millstone 2 ,

DATE 6/13/85 COMPLETED BY G. Neron JREPORT-MONTH' May: TELEPHONE (203) 447-1791 Ext. 4417 ,

l Cause & Corrective No. Date Type iDuration Reason 2' . Method of Licensee Systeg Compogent (Hours) . Shutting Event Code Code Action-to 3

Down Reactor Report # Prevent Recurrence 1 850216 S 744 C 1 N/A N/A N/A. Continuation of Refuel Maintenance Outage 1from previous month.

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 Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training & License Examination previous' month ,

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

Docket No. 50-336 Date 6/13/85 .

Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791~

Ext. 4417 i CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 5/2/85 RBCCW RBCCW Shutdown Heat Exchanger Inlet Replaced nut and bolt Pipe Support 405043 Spring Can 5/3/85 RBCCW "A" Spent Fuel Pool Cooling Heat Overhaul valve and replaced liner Exchanger Outlet Stop Valve 5/3/85 RBCCW "B"~RBCCW Heat Exchanger Plugged 35 tubes (following hydrolazing and ECT) 5/5/85 Service Water RBCCW "A" to Chlorine System Replaced valve Discharge Valve 5/9/85 RWST RWST Outlet to S1 &- CTMT Spray Pump Torqued hanger nuts Pipe 5/10/85 120 Volt Vital Inverter #3 Replaced damaged transformer in Reg. Instrument AC Inverter #3 5/14/85 Feedwater #2 S/G Main Feed Supply Air-Assist Weld repaired to flange and ground Check Valve smooth 5/15/85 Boric Acid Boric Acid Heat Trace (Pri.) Temp Replaced thermocouple and thermister; Recorder mounted and filled with thermon cement

.1 Docket No. 50-336-Date 6/13/85' .

J Unit Name Millstone 2 Completed By G. Neron Telephone-(203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 l

DATE SYSTEM COMPONENT MAINTENANCE ACTION 4

5/15/85 Boric Acid Boric Acid Heat Trace (Sec.) Temp Replaced thermocouple and thermister; i Recorder mounted and filled with thermon cement i

5/16/85 Shutdown Cooling Shutdown Cooling Heat Exchanger Flow Installed new flange gaskets Control Valve Assembly 5/16/85 Shutdown Cooling Shutdown Cooling Heat Exchanger Flow Repacked valve and stroked Control Valve 4

5/17/85 480 Volt Load C33B Hydrogen Recombiner Power Overcurrent devices replaced and set Centers Panel - 480V Breaker by Satin, tested breaker and found satisfactory j 5/17/85 Diesel Generators "A" Diesel Generator Standby Lube Replaced pump and motor; reversed i

Oil Pump Assembly two leads for proper operation

, 5/18/85 480 Volt Load C33A Hydrogen Recombiner Power -Sent three EC-1 devices.to Satin-AM.  !

j Centers Panel - 480V Breaker For conversion to 1C-2A from 1C-2C. l

Installed new EC-1 devices; PM'd i breaker and cleaned; cleaned and a lubricated cubicle; installed

breaker s

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D:ckst No. 50-336' Date 6/13/85 ,

Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 5/21/85 Station Elec. 4.16 KV Breaker - Bus 24G to Tightened bus connections Service 4.16 KV 24D Feeder Breaker 22S3-240-2 5/22/85 Reactor Coolant & Thermo Well for TE-111X Removed old nipple and cleaned Vessel threads; chased threads w/ tap 5/22/85 Containment Containment Personnel Airlock Installed modifications to transfer Structure box; checked doors for plumbness; inspected by Factory Reps 5/22/85 Containment Containment Personnel Airlock Removed old gaskets and replaced Structure with new gaskets (inner door) 5/22/85 Station Elec. 4.16 KV Breaker - PSA Service Water Changed out bushings; cleaned fire Service 4.16 KV Pump 24C-IT-2 foam off of breaker, spring charging motor and switches.

5/24/85 Shutdown Cooling Shutdown Cooling Flow Control Valve Install new air line Air-0perator .

-D:cket N). 50-336-Date 6/13/85 .

Unit Name Millstone 2 Completed-By G. Neron-Telephone (203) 447-1791-Ext. 4417 CORRECTIVE MAINTENANCE StM4ARY FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION.

5/25/85 120V. Vital Inverter #1- Replaced one 40' micro farad capacitor.

Regulated (C2) and all twelve DC capacitors Instrument AC 5/30/85 Station Elec. 4.16 KV. Breaker 24C to 24E 24C-2T Disassabled ML-13 mechanism and found Service 4.16 KV cracked pin. Ordered, received and installed pin. Cleaned mechanism-and tested both mechanically and-electrically 5/30/85 Station Elec. P11A RBCCW Pump 24C7-2 . Disassembled ML-13 mechanism and Service 4.16 KV found missing roller in latch bearing. . Ordered and received part.-

Cleaned, lubricated and reassembled; tested 5/1/85 Reactor Coolant & PressurizerLLevel Auto / Manual Found blown. mini fuse.on card, but-Vessel :Bumpless Transfer Control Card could not balance zero; returned card to Foxboro 5/2/85 Reactor Coolant & Pressurizer System Removed all controllers, modified ~the repaired the pins on

~

Vessel s'eismic braces several of the controllers

Dockst No. 50-336 Date 6/13/85 ,

Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Ext. 4417

. CORRECTIVE MAINTENANCE

SUMMARY

.FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 5/10/85 Process & Area CTMT Hi Range Radiation Monitor Loop Found intermittent connection in Radiation readout module meter; tightened Monitoring connection in meter; replaced detector and verified proper operation of RM 8241; replaced Raychem Envir.

5/10/85 Reactor Reactor Coolant ~ Loop 1A Cold Leg Replaced zero span potentiometers Regulating Temp XMTR on TT-111Y/ performed recal of TT-111Y and. loop after 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, burn test 5/20/85 Reactor Protection Amplifier Assembly-Includes (2) Removed existing preamp unit and-Preamps and Amplifier installed unit drawn from warehouse, found pot for HV adjust broken.

Installed new pot 5/21/85 Reactor Protection Linear Power Range Drawer RPS-C Replaced JS connector 5/22/85 Reactor Protection Wide Range Drawer RPS-C -Replaced A2 preamp discriminator card

~ 5/28/85 Reactor Protection Auxiliary Logic Drawer RPS-A Replaced RI with 150K 0HM resistor, jumpered Point C to Point B and Point D to Point A. Used QA bus wire and insulation.

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O Docket No. 50-336 '

Date 6/13/85 -

Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE St# MARY FOR SAFETY RELATED EQUIPMENT REPORT MONTH May 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 5/29/85 Reactor Protection RPS-A Power Supply Drawer DRA 15 .750/15 .750 power mate power i

supply was replaced and adjusted for 15V output.

l 5/31/85 Reactor Coolant & Reactor Coolant Loop.2A Cold Leg Cut off affected wire, relugged and Vessel Temp RTD landed the same. Cut back other two wires,'relugged and landed also.

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Docket No. 50-336 Date: 6/13/85 Completed By: G. Neron Telephone: (203) 447-1791 Ext. 4417 REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

2. Scheduled date for next refueling shutdown: Currently in refuel / maintenance outage which commenced February 16, 1985

3. Schedule date for restart following refueling: June 24, 1985

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

All Technical Specification changes have been forwarded to the NRC for the new core loading plan. The reload safety evaluation has also been sent to the NRC to support the startup of Cycle 7.

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

A. A technical specification change request for the total planar peaking factor was submitted on February 4, 1985, along with a preliminary reload analysis.

An update to this Technical Specification Change Request was sent June 11, 1985. The final reload analysis was sent on June 5, 1985.

B. Technical support information for reracking the spent fuel pool will be submitted approximately June 18, 1985 to support a proposed license ammendment.

C. A Technical Specification Change Request for excluding up to 10 steam generator tubes from~100% eddy current testing requirements (end of cycle 6) was submitted on February 8, 1985.

D. The NRC was advised of plans to inspect the core barrel.

Results from the core barrel inspection was submitted to the NRC on June 11, 1985.

E. A Technical Specification Change Request was submitted on April 2, 1985 concerning Control Room Habitability Modifications.

F. The NRC approved a request for authorization to use ASME Code Class N-416, " Alternative Rules for Hydrostatic Testing of Repair or Replacement for Class 2 Piping Section XI Division 1", on March 14, 1985.

G. Supply the NRC with results of sleeving and plugging of the steam generator tubes. Per Technical Specifications this will be '

i sent within 15 days of completion of S/G ISI.

Docket No. 50-336 Date: 6/13/85 Completed By: G. Neron Telephone: (203) 447-1791 Ext. 4417 REFUELING INFORMATION REQUEST (Cont'd)

H. A letter summarizing fuel and CEA inspection results during the recently completed outage was forwarded to the NRC on June 11, 1985.

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:

The discharge of failed fuel required a new fuel loading plan.

A final revised reload safety evaluation has been forwarded for review.

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

(a) In Core: 217 (b) 449

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 beginning in August 1985, to increase the storage capacity to 1106 fuel assemblies.

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 load capacity is reached.

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

0 ggg General Offices

• Selden Street. Berlin, Connecticut J P.O. BOX 270

.a m .ana m . m . HARTFORD. CONNECTICUT 06141-0270 L L J ['['j

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" (203) 666-69M June 13, 1985 MP-7002 Director, Office of Resource Management U. S. Nuclear Regulatory 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 85-05 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

&0l W. D. Romberg Station Superintendent Millstone Nuclear Power Station WDR/GN:jlc cc: Director, Office of Inspection and Enforcement, Region I Director, Office of Inspection and Enforcement, Washington, D. C. (10)

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

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