ML20154D765
| ML20154D765 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/30/1988 |
| From: | Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| MP-11803, NUDOCS 8805190333 | |
| Download: ML20154D765 (5) | |
Text
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o AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-336 UNIT Millstone 2 DATE 05-06-88 COMPl.ETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 MONTH April 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 863 17 858 2
864 18 861 3
864 19 863 4
864 20 862 5
864 21 864 6
864 22 861 7
863 23 864 8
851 24 866 9
7 25 865 l
10 0
26 865 11 0
27 863 12 0
28 864 13 0
29 866 14 0
30 866 15 197 31
---~-
16 636 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 l
8805190333 880430 PDR ADOCK 05000336 R
s OPERATING DATA REPORT 00CKET NO. 50-336 DATE b5-06-88 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 OPERATING STATUS 1.
Unit Name: Millstone Unit 2 l Notes:
Items 21 and 22 cumulativel 2.
Reporting Period: April 1938 l
are weighted averages.
l 3.
Licensed Thermal Power (MWt): 2700 l
Unit operated at 2560 MW l 4.
Nameplate Rating (Gross MWe): 909 l
thermal prior to its l
S.
Design Electrical Rating (Net MWe): 870 l
uprating to the current l
6.
Maximum Dependable Capacity (Gross MWe):888.75l 2700 MWTH power level.
l 7.
Maximum Dependable Capacity (Net MWe): 857.25 l l
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, It 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 2,903 108,239 12.
Number Of Hours Reactor Was Critical 597.2 1,633.7 79,014.0 13.
Reactor Reserve Shutdown Hours 0
0 2,205.5 14.
Hours Generator On-Line 580.2 1,539.0 74,792.0 15.
Unit Reserve Shutdown Hours 0
0 468.2 16.
Gross Thermal Energy Generated (MWH) 1,494,18'/
3,940,635 208,502,897 17.
Gross Elec. Energy Generated (MWH) 493,198.5 __ 1,297,998.5 62,169,577.5, 18.
Net Electrical Energy Generated (MWH) 473,448.5 1,240,329.5 59,616,867.5 19.
Unit Service Factor 80.7 53.0 69.1 20.
Unit Availability Factor 80.7 51.0 69.5 21.
Unit Capacity Factor (Using MDC Net) 76.8 49.8 65.0 22.
Unit Capacity Factor (Using DER Net) 75.7 49.1 64.0 23.
Unit Forced Outage Rate 19.3
- 8. 3 15.0 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:
N/A 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 l
l l
o
.~.
i DOCKET NO. 50-336 UNIT SHUlDOWNS AND POWER REDUCTIONS UNIT HAME Millstone 2 DATE 05-06-88 i
COMPLETED BY G. Neron REPORT MONTH APRIL 1988 TELEPHONE (203) 447-1791 Extension 4417 l
No.
Date Type Duration Reason 2 Method of Licensee System Component Cause & Corrective (Hours)
Shutting Event Codei Code 5 Action to Down Reactor 3 Report #
Prevent Recurrence 88-01 040888 5
141.9 8
3 88-08 AA,CD CL,CCL Initiated reactor 3
power reduction i
from 100% power for planned maintenance outage; l
CEA #22 dropped and l
power was reduced to ~70%; Continued reactor shutdown
- unable to recover the dropped CEA; CEA #4 also dropped before reactor j
was sub-critical; Ihe dropping of CEA's #4 and #22 was determined to have been caused by major loss of upper gripper coil resistance due to overheating; In addition, a high resistance of the CEA #5 upper gripper coil was found, and was determined to have been caused by a loose coil stack connection; Overheating was caused by the I
reduction of the CEDM Cooler efficiency due to boron clogging of the fan intakes; New CEDM Coil Stacks were installed for CEA's #4, #5, and #22; The CEDM Cooler intakes were cleaned; Determination of the boron source is 3
still under investigation.
See LER.
I 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 tntry Sheets for Licensee C-Refue~iing 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161) i E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction 5
G-Operational Error (Explain)
(Jaration = 0)
Exhibit 1 - Same Source H-Other (Explain) 6-Other (Explain) i
REFUELING INFORMATION REQUEST 1.
Name of facility:
Millstone 2 2.
Scheduled date for next refueling shutdown:
February, 1989 3.
Schedule date fo restart following refueling: N/A 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Technical Specification changes will be necessary resulting from the change in f uel and safety analysis supplier for cycle 10 operation.
5.
Scheduled date(s) for submitting licensing action and supporting information:
The projected date is November, 1988 6.
Important licensing consideratiens associated with refueling, e.g., new or dif'erent fuel design or supplier, unreviewed design or performance analys s methods, significant changes in fuel design, new operating procedures:
Cycle 10 will be unique in that it will be the first cycle where the fuel and safety analysis will be supplied by Advanced Nuclear Fuels for Mills, tone Unit 2 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core: (a) 217 (b) 580 8.
The present licensed spent fuel pool storage capaciti and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Currently 1277 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1998, Core Full, Spent Fuel Pool Full 2009, Spent Fuel Pool, Full core off load capacity is reached - On March 31, 1988, License Amendment #128 was issued to Millstone Unit 2 which allows the full scale storage of consolidated fuel in the Spent Fuel Dool.
GeneralOffices e Seiden Street Berkn Connecticut
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HARTFORD, CONNECTICUT 06141-o270 L
L J !".'Z ClME'.g; (203) 665-5000 May 10, 1988 MP-11803 Re:
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 88-04 in accordance with Appendix A Technical Specifications, Section 6.9.1.6.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY ifbit ACG Step' hen I. Scace Station Superintendent Millstone Nuclear Power Station SES/GN:faj cc:
W.T. Russell, Region I Administrator D.H. Jaffe, NRC Project Manager, Millstone Unit No. 2 W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3
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