ML20129G016
| ML20129G016 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/31/1985 |
| From: | Gibson J, Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| MP-6811, NUDOCS 8506070104 | |
| Download: ML20129G016 (7) | |
Text
.
OPERATING DATA REPORT DOCKET N0.
50 336 DATE 4/12/85 COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS 1.
Unit Name:
Hi11 stone Unit 2 Notes: Items 21 and 22 2.
Reporting Period:
March 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 Rcport, 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 2160 81216 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)
(-3156) 906540 43730063 19.
Unit Service Factor 0
51.4 68.3 20.
Unit Availability Factor 0
51.4 68.9 21.
Unit Capacity Factor (Using MDC Net) 0 50.4 64.0 22.
Unit Capacity Factor (Using DER Net) 0 48.2 63.1 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 B506070104 850331 PDR ADOCK 05000336 R
PDR k
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-336-UNIT Millstone 2 DATE 4/12/85 COMPLETED BY J. Gibson TELEPHONE'(203) 447-1791 Ext. 4431 MONTH March 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
l 10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
l 15 0
31 0
l 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.
i
DOCKET NO.
50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 4/12/85 COMPLETED BY J. Gibson REPORT MONTH March TELEPHONE (203) 447-1791 Ext. 4431 l
2 No.
Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours)
Shutting Event Code Code Action to Down Reactor Report #
Prevent Recurrence 1
850216 S
744 C
1 N/A N/A N/A Continuation of refuel maintenance outage from the
}
previous month, s
l 1
2 3
4 F: - Forced Reason:
Method:
Exhibit G - Instructions 5: 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 l
G-Operational Error (Explain)
(Duration = 0)
Exihibit 1 - Same Source H-Other (Explain) 9-Other (Explain) l i
i
e-Docket No.
50-336 Date:
ar p/gs Completed By: J. G ib~ son Telephone: (203) 447-1791 Ext. 4431 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 1995 4.
Will refueling or resumption of operation thireafter require a technical specification change or other license snendment?
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 May 15, 1985.
5.
Scheduled date(s) for submitting licensing action and supporting information:
a.
A techr.ical specification change request has been submitted for the outage equipment hatch and was approved February 12, 1985.
b.
A technical specification change request for the total planar peaking factor was submitted on February 4,1985, along with a preliminary reload analysis.
~
c.
Technical support information for reracking the spent fuel pool will be submitted second quarter 1985 to support a June 1985 proposed license ammendment.
d.
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.
e.
The NRC was advised of plans to inspect the core barrel.
Results from the core barrel inspection will be submitted prior to re-start.
f.
A Technical Specification Change Request was submitted on April 2, 1985 concerning Control Room Habitability Modifications, g.
The NRC received 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 Devision 1", on March 14, 1985.
4 f
m 7
Docket No.
50-336 Date:
4/12/85 Completed By:
J. Gibson Telephone: (203) 447-1791 Ext. 4431 REFUELING INFORMATION REQUEST (Cont'd) 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: 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 beginning in July 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.
I i
I I
l l
r
i Dock;t No.
50-336-Date 4/12/85 Unit Name Millstone 2 Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 l
CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT REPORT MONTH March 1985 DATE SYSTEM COMPONENT MAINTENANCE ACTION l
3/8/85 Spent Fuel Pool 2-RW-280 Repair valve.
Cooling Fuel Transfer Isolation l
Valve 3/10/85 Reactor Protection Channel 'D' Removed detector signal System pre-amplifier - send to vendor for modification.
3/16/85 Diesel Generator 2-DG-92A Replace valves.
2-DG-96A Air Solenoid Valves 3/20/85 Reactor Protection Safety Related Penetration Environmentally seal - terminations System Termination Blocks on containment interior penetrations.
3/21/85 Reactor Coolant and 2-RC-422 Install new stainless steel cover Vessel 2-RC-424 and adjust open & close reed Pressurizer Vent Solenoid switches.
Operator Valve Assembly 3/28/85 ESAS Actuation Cabinet #6 Relays Replace all actuation relays.
3/30/85 CVCS Loops - Pressurizer Level Converted entire loop to Spec 200.
and Pressure
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April 15, 1985 MP-6811 f
Director Office of Management Infccmation and Program Control U. S. Nuclear Regulatory Commissic, 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 85-03 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 C0MPANY g
N' E. J. Mroczka Station Superintendent Millstone Nuclear Power Station EJM/JG: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 hi i