ML20207Q226
| ML20207Q226 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1986 |
| From: | Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| MP-9923, NUDOCS 8701270038 | |
| Download: ML20207Q226 (10) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 1/13/87 J
COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Ext. 4417 MONTH DECEMBER 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 161 4
0 20 192 5
0 21 210 6
0 22 381 7
0 23 129 1
8 0
24 231 9
0 25 394 10 0
26 417 11 0
27 732 12 0
28 830 13 0
29 831 14 0
30 831 15 0
31 831 r
16 0
i INSTRUCTIONS On thfa format, list the ave
- age daily unit power level in HWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt, i
OPERATING DATA REPORT
-DOCKET NO. 50-336 DATE 1/13/87 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Ext. 4417 OPERATING STATUS 1.
Unit Name: Millstone Unit 2 Notes Items 21 and 22 cumulative, 2.
Reporting Period:
December, 1986 are weighted averages.
3.
Licensed Thermal Power (MWt):
2700 Unit operated at 2560 MW 4.
' 5..
Nameplate Rating (Gross MWe):
909 thermal prior to its Design Electrical Rating (Net MWe):
870 uprating to the current 6.
Maximum Dependable Capacity (Gross MWe):
888.75 2700 MW thermal power 7.
Maximum Dependable Capacity (Net MWe): 857.25 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 744 8760 96576 12.
Number Of Hours Reactor Was Critical 407.7 6600.6 69138.3 13.
Reactor Reserve Shutdown Hours 0
0 2205.5 14.
Hours Generator On-Line 296.5 6355.2 65072.9 15.
Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 496285 16644084 164747886
- 17. Gross Elec. Energy Generated (MWH) 157000 5376000 53717479 18.
Net Electrical Energy Generated (MWH) 142486 5162788 51484007 19.
Unit Service Factor 39.9 72.5 67.4 20.
Unit Availability Factor 39.9 72.5 67.9 21.
Unit Capacity Factor (Using MDC Net) 22.3 68.7 62.9 22.
Unit Capacity Factor (Using DER Net) 22.0 67.7 62.0 23.
Unit Forced Outage Rate 6.2 2.6 16.1 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A 25.
If Shut Doven At End Of Repert Period, Estimated Date of Startup: N/A 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved i
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l-l c
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DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 1/13/87 COMPLETED BY G. Neron REPORT MONTH DECEMBER, 1986 TELEPHONE (203) 447-1791 Ext. 4417 l
2 No.
Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours)
Shutting Event Code Code Action to 3
Down Reactor Report #
Prevent Recurrence 5
09-20-86 S 400.7 C
4 N/A N/A N/A Completion of Refuel and Maintenance Outage.
6 12-23-86 F 19.6 A
3 86-22 EB XPT While operating at 50% power, the reactor tripped following the loss of Bus 24C and 24A.
The loss of Bus 24C and 24A was due to an undervoltage sensed on 24C Vital 4160 Volt Bus. See LER.
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)
Exhibit 1 - Same Source H-Other (Explain) 9-Other (Explain)
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Dock:t No. 50-336 Date 1/13/87 Unit Name Millstone 2 Completed By G._ Neron Telephone (203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH DECEMBER, 1986 l
l l
DATE SYSTEM COMPONENT MAINTENANCE ACTION 10-15-86 Chemical Volume and 2-CH-006 - Letdown Header In Replaced Body-to-Bonnet Flexitallic Control System Containment Isolation Valve Gasket.
10-27-86 High Pressure Safety 2-SI-616M "B" HPSI Header Replaced 2 Rotary Type Limit Injection To Loop 1A Injection Valve Motor Switches with new switches, adjusted switches and replaced gasket.
11-13-86 Containment Spray 2-CS-4.1BM "B" Containment Repaired Loose Wire Spray Header Isolation Valve Motor.
12-30-86 Vital Switchgear X183-6.9 and 4.16 KV Switchgear Manufactured and Installed new Emergency Cooling Room Cooling Coil.
Cooler Heads.
1 11-30-86 Feedwater 2-FW-5BV-#2 S/G Main Feed Supply Repacked Valve, Installed new Air - Assist Check Valve stuffing box gasket and torqued bonnet nuts.
10-25-86 Service Water PSA "A" Service Water Pump Vendor performed weld repairs on l
Assembly inside of the column welds.
l 9-27-86 Service Water 2.5-HUD-112 - Vital AC switchgear Welded pre-fabricated piping in room cooling coil X182 place to effect repair of Service Water Return pipe.
leaking pipe.
L______
Docket No. 50-336 Date 1/13/87 Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH DECEMBER, 1986 DATE SYSTEM COMPONENT MAINTENANCE ACTION-9-27-86 Service Water 2.5-HUD-114 - Vital AC switchgear Welded pre-fabricated piping in room cooling coil X183 Service place to effect repair of ' leaking Water Return pipe, pipe.
11-10-86 Service Water 24-JGD Service Water Pumps Pre-fabricated piping installed (above ground) discharge pipe.
to effect repair of leaking pipe.
11-14-86 Service Water 8-JGD Diesel Engine Performed clad weld on pipe.
Coolers Service Water Supply Header Pipe.
10-20-86 Reactor Building 2-RB-37.2AM "A" RBCCW Header Replaced 2 rotary. type limit Closed Cooling Water Containment Return Valve Moter switches, set up switches and replaced limitorque cover gasket.
9-7-86 Gaseous Radwaste F1AC "A" Waste Gas Compressor Rebuilt Suction Discharge Check, Tested and set oil relief and changed process filter.
11-15-86 120 Volt Vital INV4 - Inverter #4 Replaced capacitors.
Regulated Instrument AC.
9-25-86 125 Volt DC DC2 "B" Battery Charger to Replaced 4 Capacitors and cleaned Battery Bus bus bars.
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~ Docket No.'50-336' Date 1/13/87 Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791-Ext. 4417-CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH DECEMBER, 1986' DATE SYSTEM
. COMPONENT MAINTENANCE ACTION 12-9-86 Safety Injection Tanks LT-311 - SIT Level T39A Installed spare transmitter and new amplifier, changed span input jumpers.-
to high and sealed transmitter (EEQ).
12-2-86 Control Room AC AE-9792 - Control Room HVAC Replaced detector.and matching f
Chlorine Detector amplifier card.
12-2-86 Control Room AC AE-9793 - Control Room Replaced Detector and matching HVAC Chlorine Detector amplifier card.
12-22-86 Control Room AC RIT-9799B - Control
-Removed old pin connector and Room Ventilation Radiation Monitor installed.new pin connector.
12-26-86 Main Steam RIT-42998 - Main Steam Line Replaced RIT-4299B with' Rad Monitor Loop spare module.
12-29-86 Main Steam
'RIT-42998 - Main Steam Line Replaced H.V. and NIM BIN-Rad Monitor Loop Connector.
12-31-80 Main Steam RM-4299 - Main Steam Line.
Installed Raychem Sleeving ove'r Rad Monitor Loop Main Steam High Voltage and Signal Cable BNC~ connectors.
9 0
Docket No. 50-336 Date 1/13/87.
Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Ext. 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH DECEMBER, 1986-DATE SYSTEM COMPONENT MAINTENANCE ACTION 10-13-86 Process and Area RM-8262A - CTMT Air Particulate Replace HVS-72 Card and detector Radiation Monitoring Radiation Monitor L,oop probe.
12-6-86 ESAS ESA - Engineered Safeguards Replaced relays K535A and K621A.
Actuation System 12-4-86 Reactor Protection CPC-C Core Protection Replaced Zero Pot on K1-5.
Calculator 2, RPS-C 12-3-86 Reactor Protection RPS-D - RPS-D Panel D Loop Repaired TU-1 Pin FF and TU-4 (RC050) pin F in the NIM (Females),
replaced aux. logic drawer 24VDC Power Supply.
12-4-86 Reactor Protection TU-C Channel-C Trip Bistable:
Repaired pin BB in trip High Power Unit 1 NIM BIN (Female) and replaced trip unit 1 (High Power) with new unit.
O
i Docket No. 50-336 i
Date 1/13/87 Unit Name Millstone 2 i
Completed By G. Neron Telephone (203) 447-1791 Ext. 4417 i
CORRECTIVE MAINT5'!AECE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH DECEMBER, 1986 DATE SYSTEM COMPONENT MAINTENANCE ACTION 12-11-86 Reactor Protection WR-LOG-A - Wide Range Drawer Replaced Audio count rate' card.
RPS-A.
10-29-86 Reactor Protection WR-LOG-B - Wide range drawer Repaired amplifier assembly RPS-B and reinstalled.
12-8-86 Reactor Protection WR-LOG-B - Wide range drawer Replaced H.V. Power Supply RPS-B pot wiring.
12-8-86 Reactor Protection WR-LOG-C - Wide range drawer Replaced H.V. Adjust pot RPS-C wiring.
12-1-86 CEA Position Reed-SW Reed Switch Replaced Reed switch SN38 Indication Assembly (Reg. Group 3) with SN6.
12-1-86 CEA Position Reed-SW Reed Switch Replaced Reed switch SN92 Indication Assembly (Reg. Group 3) with SN80.
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Docket No. 50-336 Date: 1/13/87 Completed By: G. Neron Telephone: (203)447-1791 Ext. 4471 REFUELING INFORMATION REQUEST 1.
Name of facility: Millstone 2 2.
Scheduled date for next refueling shutdown:
January 23, 1988 3.
Schedule date for restart following refueling: April 1988.
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Ng 5.
Scheduled date(s) for submitting licensing action and supporting information:
None at this time.
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:
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
217 (b) 512 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 1112 The 1112 available locations reflects the re-racked Spent Fuel Pool.
The re-racking of the Unit 2 Spent Fuel Pool has been completed.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1994, Spent Fuel Pool, Full Core off load capacity is reached.
1998, Core Full, Spent Fuel Pool.
These numbers are based on the recently re-racked Spent Fuel Pool.
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(203) 665-5000 January lti, 1987 MP-9923 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Commission Document Control Desk 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 86-12 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:
Stephen E. Scace Station Superintendent Millstone Nuclear Power Station
^ ~ - -
BY:
James J. Kelley Station Services Superintendent Millstone Nuclear Power Station SES/GN:ck cc:
Regional Administrator, Office of Inspection and Enforcement, Region I Director, Office of Inspection and Enforcement, Washington, D. C. (10)
Director, Office of Resource Management T. Rebelowski, Res. Insp.
g8Y f
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