ML20108A774
| ML20108A774 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1984 |
| From: | Mroczka E, Neron G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-6380, NUDOCS 8411150189 | |
| Download: ML20108A774 (6) | |
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~ AVERAGE DhlLY UNIT:. POWER LEVEL:
. DOCKET:NO.:50-336i
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- UNIT MILLSTONE 2 J
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~DATE 10-10-84 s
_ COMPLETED BY G.NERON TELEPHONE (203) 447-1791 EXT. 4417-MONTH SEPTEMBER 1984 DAY-
' AVERAGE DAILY POWER LEVEL DAY AVERAGE. DAILY POWER LEVEL'
- (MWe-Net)
(MWe-Net).
1' 815' 17 776 2
818 18 817-
- 3
'818 19
'827 4'
- 820~
20 826 5
' 733-21 825 6
- 785 22 827
-7 727 23 824 8
819 24 823 9
823 25 823 10 819 26 824 11 818 27 827 12 819 28 826 13 820 29 711 14 819 30 800 15-825 31
'16 827 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.
h;' 7 k.
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9-OPERATING DATA REPORT-DOCKET NO. 50-336 DATE 10-10-84 COMPLETED BY G. NERON TELEPHONE (203) 447-1791
. EXT. 4417 OPERATING STATUS
~
1.
Unit Name: ' Millstone Unit 2 Notes:
Items 21 & 22 2.
Reporting Period:
September 1984 cumulative are weighted ave.
3.
Licensed Thermal Power (MWt):
2700 unit operated at 2560.MW' 4.
- Nameplate Rating (Gross MWe):
909 thermal prior to its uprating 5.
Design Electrical Rating (Net MWe):
870 to the current 2700 MW 6.
Maximum Dependable Capacity (Gross MWe):
895 thermal power level.
7.
Maximum Dependable Capacity (Net MWe): 864
' 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 6575 76847
- 12. Number Of Hours Reactor Was Critical 720 6451.9 54817.2 13.
Reactor Reserve Shutdown Hours 0
0 2205.5
- 14. Hours Generator On-Line 720 6149.1 52331.3
- 15. Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 1910948 15911059 132222728 17.
Gross Elec. Energy Generated (M4H) 604400 5109401
-42915779 18.
Net Electrical Energy Generated (MWH) 582128 4909139 41124840
- 19. Unit Service Factor 100 93.5 68.1 20.
Unit Availability Factor 100 93.5 68.7 21.
Unit Capacity Factor (Using MDC Net) 93.6 86.4 63.6 22.
Unit Capacity Factor (Using DER Net) 92.9 85.8 62.8 23.
Unit Forced Outage Rate 0
2.7 17.5 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 Feriod, Estimated Date of Startup: N/A
- 26. Units In Test Status (Prior to Commercial Operation):
FoFecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
3, DOCKET NO. 50-336
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UNIT SHUTDOWNS AND POWER REDUCTIONS-UNIT NAME. MILLSTONE-2 DATE 10-10-84 COMPLETED BY U NERUR.
REPORT MONTH SEPTEMBER'1984 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 9
840905 F
0 A
5 N/A SG C0' D Reduced power from 100%
N to 80% power to perform-leak check tests onl condenser'"D". water box.
Leak checks performed' and water box closed.
10 840907 F
0 A
5 N/A AA R00 While at 100% power CEA'
- 26 dropped into core due to power supply:
failure.1 Power was 4
reduced to < 70% power and CEA~was recovered.
4 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 i
D-Regulatory Restriction 4-Continued from
-(NUREG-0161)
E-Operator Training & License Examination
' previous month l
F-Administrative 5-Power Reduction 5-l G-Operational Error (Explain)
(Duration = 0)
Exihibit 1 -'Same Source H-0ther (Explain) 9-Other (Explain)
T i
y Docket No.'50-33'6l Date 10-10-84 Unit Name MRTSTDNE 2 Completed By G. NERON Telephone (203) 447-1791
. EXT. 4417 CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY-RELATED EQUIPMENT REPORT MONTH SEPTEMBER 1984 DATE SYSTEM COMPONENT MAINTENANCE ACTION 9/11/84 Diesel Generator 2-DG-9/A Supply Solenoid.
Replace broken copper line with Operated Valve stainless steel.
9/12/84 Main. Steam Drain Valve / Steam Supply Furmanite valve stuffing box.
from S/G #1 to Terry Turbine Header 9/14/84 Containment Post Hydrogen Recombiner Heater Replace filter board, one (1) SCR Incident Hydrogen Power H298 CE C 50 M in "C" phase, installed Control fuse in "B" and "C" phases.
9/11/84 Main Steam S/G #2 Header Drain Control Replaced operator shaft "0" ring Valve Air Operator seal.
9/12/84 Containment Structure Personnel Airlock _ Exterior Replaced one (1) bolt and tightened Hand Wheel Gasket packing around shaft.
9/13/84 Service Water Lube Water, Cross Tie Line Emergency Patch Install'ed.
9/12/84 Reactor Coolant &
Reactor Coolant Loop 1A to Replaced TY-112CA-1 and TY-122HA Vessel Channel "A" RPS Temp Transmitter (Dual V/I UNITS), and recalibrated.
9/12/84 Reactor Coolant &
Reactor Coolant Loop 1 Hot Leg Replace N-2AI-P2V card and calibrated.
Vessel Temp Transmitter 3
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Docket No. 50-336 Date: 10-10-84 Completed By: G. NERON Telephone: (203) 447-1791-EXT. 4417 REFUELING INFORMATION REQUEST
-1.
Name of fac.ility:
Millstone 2 2.
Scheduled date for next refueling shutdown:
Next refueling is in February 1985.
3.
Schedule date for restart following re/ueling:-June 1985 4.
.Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Currently under evaluatio'n 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 pre;ent 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:
1985, Spent Fuel Pool, Full core off load capacity is reached.
1987, Core Full, Spent Fuel Pool contains 648 bundles.
'O General Offices
- Selden Street, Berlin, Connecticut 1
7 O rts$sm*w ='
P.O. BOX 270
- eir ato rin,o.c.co HARTFORD, CONNECTICUT 06141-o270 g
omwast wsnes se cc.c.,
(203) 666-6911 feOfif>E AST *asCt& AR DeEnGV CoedPffrF October 12, 1984 MP-6380 Director Office of Management Information and Program Control 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 84-9 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 M
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l E. J. Mroczka Station Superintendent l
Millstone Nuclear Power Station EJM/GN: ck l
cc:
Director, Office of Inspection and Enforcement, Region I l
l _
Director, Office of Inspection and Enforcement, Washington, D. C. (10) l U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D.C. 20555 i
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