ML20132E151
| ML20132E151 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/30/1985 |
| From: | Neron G, Romberg W NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-6912, NUDOCS 8507170636 | |
| Download: ML20132E151 (9) | |
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 i
UNIT Millstone 2 0
i DATE 5/10/85 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 MONTH April 1985
.,.g 9#
DAY 4-AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)
A 0
17 0
1 v
2 0
18 0
4 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
'.'i 16 '
0
>[s INSTRUCTIONS Okthis format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
8507170636 850430 PDR ADOCK 05000336 R
PDR-f b
9
OPERATING DATA REPORT DOCKET'NO. 50-336 DATE 5/10/85 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 OPERATING STATUS a
1.
Unit Name: Millstone Unit 2 Notes Items 21 and 22 2.
Reporting Period:
April 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 to its uprating to the 6.
Maximum Dependable Capacity (Gross MWe): 866.25 current 2700 MW thermal 7.
Maximum Dependable Capacity (Net MWe):
833.25 power 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 719 2879 81935
- 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)
(-3153) 903387 43726910
' 19. Unit Service Factor 0
38.5 67.7
-20.
Unit Availability Factor 0
38.5 68.3
- 21. Unit Capacity Factor (Using MDC Net) 0 37.7 64.1
- 22. Unit Capacity Factor (Using DER Net) 0 36.1 63.2
- 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
,i.
'. DOCKET NO. 50-336-UNIT SHUTDOWNS AND POWER REDUCTIONS
-UNIT NAME Millstone 2 DATE 5/10/85 COMPLETED BY G. Neron REPORT MONTH April TELEPHONE (203) 447-1791'
~
Extension 4417 l
2 l
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 l
L 1
850216-. S 719 C
1 N/A N/A N/A Continuation of l
-refuel maintenance L
outage from the L
previous month.
t l
l l
l L
l l
I 1
2-3 4
l F:
Forced.
Reason:
Method:
Exhibit G - Instructions 1
S: ~ Scheduled ~ A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Lic9nsee 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 l
G-Operational Error (Explain)
(Duration = 0)
Exihibit 1 - Same Source H-Other (Explain) 9-OtheC (Explain) l l
I
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Docket No. 50-336'.,
Date 5/10/85 Unit Name Millstone 2 Completed By G. Neron Telephone (203) 447-1791 Extension 4417 CORRECTIVE MAINTENANCE SumARY FOR SAFETY RELATED EQUIPMENT REPORT MONTH April 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION 3/15/85 Containment Structure Containment Airlock Locktight Interior Door Pin 3/16/85 Containment Structure Containment Airlock Tackweld Interior Door Pin 3/23/85 Service Water 24-JGD-1 Installed new piping between 2-SW-97B Service Water Pump Discharge and 2-SW-3B-Piping (above ground) l 4/2/85 120 Volt Vital Regulated Inverter #5 Replaced KAA-300 Fuse Instrument AC' 4/2/85 125 Volt DC 125 VDC Bus 2010 to Repaired Bent Arm (Racking Device) l Inverter INV6 4/9/85 125 Volt DC 00204 (DC Breaker)
Removed Overcurrent Trip Devices adjusted and Installed EC-1 4/13/85 Service Water 24-JGD-6 Install New Flange and Elbow RBCCW Heat Exchanger Service Water Outlet Pipe 4/17/85 Service Water 24-JGD-1 Installed New Elbow Service Water Pumps Discharge Piping (Above Ground) l j
f
N Dock 2t No. 50-336 Date 5[10/85 Unit Name Millstone 2 Completed By G. Neron.
Telephone (203) 447-1791 Extension 4417
^
CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH April 1985 DATE SYSTEM-COMPONENT
. MAINTENANCE ACTION 4/17/85
-Service Water P5B Performed U.T., Ground out pits in "B" Service Water Pump intermediate column lower flange inner weld, built up ground area with weld, performed L.P.
4/1/85 Containment Post Incident Containment Pressure Replaced 0-Rings and retorqued covers.
Hydrogen Control Transmitter-Wide Range 4/6/85 Reactor Coolant and Vessel Reactor Coolant 2A Cold Swapped resistance tolerances (+)R7 to r
Leg Temp Signal Selector
(-)R8 and R8(-) to R7(+)
4/8/85 Reactor Coolant and Vessel' Reactor Coolant 2A Cold Repaired Card S/N 71066 and Leg Temp Signal Selector recalibrated (Returned to Warehouse) 4/9/85 Reactor Protection RPS Channel "C" Burnished / Cleaned K1 Relay Contacts 4/9/85 Reactor Protection RPS Channels A, B and D Cleaned K1 Relay Contacts 4/23/85 ESAS ESAS Actuation Cabinet New sequencer could not pass functional "6"
(RCO2C) test in test bin - waiting for spare 4/24/85 Main Steam Steam Generator #1 Replaced 0-ring / grease and retorqued Dump to atmosphere cover pressure transmitter e
9
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Docket No. 50-336 L
Date 5/10/85 Unit Name Millstone 2.
Completed By G. Neron Telephone (203) 447-1791 Extension 4417 l
. CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT-MONTH April 1985 t
.DATE SYSTEM COMPONENT-MAINTENANCE ACTION 4/12/85
. Reactor' Coolant and Pressurizer System Installed two (2) 0-rings and Vessel torqued covers on PT-103-1, LT-110X and LT-110Y l
4/17/85.
Reactor Protection Core Protection Replaced CPC-C-1 1 18 VDC power Calculator 1, RPS-C supply PS-2 4/17/85 Reactor Protection Core Protection Replaced CPC-C-1 1 18 VDC power
'~
Calculator 1, RPS-C supply PS-1 I
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Docket No. 50-336 Date: 5/10/85 Completed By: G. Neron Telephone: (203) 447-1791 Extension 4417 REFUELING INFORMATION REQUEST 1.
Name of facility:
Millstcne 2 2.
Scheduled date for next refueling shutdown:
Currently in refuel / maintenance outag; which commenced February 16, 1985 3.
Schedule date for restart following refueling: June 23, 1985 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
The discharge of failed fuel may require additional technical specification changes and a new reload safety evaluation for the revised core loading pattern and is expected by June 1, 1985.
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.
B.
Technical support information for reracking the spent fuel pool will be submitted approximately May 27, 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 will be submitted prior to re-start.
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.
=
Docket No. 50-336 i :
Date: 5/10/85 Completed By: G. Neron Telephone: (203) 447-1791 Extension 4417 REFUELING INFORMATION REQUEST (Cont'd) 4-6.
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 may require additional technical specification changes and will impact the reload safety evaluation.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core: 0 (b) 593 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 July 1985, to increase the : storage' capacity to 1106 fuel assemblies.
9.
The projected aate 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, r
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m y 13, 1985 MP-6912 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 85-04 in accordance with Appendix A Technical Specifications, Section 6.9.1.3.
One additional copy of the report is enclosed, i
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY h) / -
W. D. Rombe Station Superintendent Millstone Nuclear Power Station WDR/GN:ck 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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