ML20247C991
| ML20247C991 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/31/1989 |
| From: | Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-13485, NUDOCS 8909140158 | |
| Download: ML20247C991 (5) | |
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(203) 665-5000 September 8, 1989 MP-13485 Re:
10CFR50. 71 (a)
U.S. Nuclear Reguletory Commission Document' Control Desk Washington, D.C.
20555
Reference:
Facility Operating License DPR-21 Docket No. 50-245
Dear Sir:
In accordance with Millstone Unit 1 Technical Specification 6.9.1.6, the following monthly operatir.., data report for Millstone Unit 1 is enclosed.
One additional copy of the report is enclosed.
Very truly youts, NORTHEAST NUCLEAR ENERGY COMPANY fh7f041 vC4W Stepfen E. Scace Station Superintendent Millstone Nuclear Power Station SES/GSN:dlr
Enclosures:
(4) cc:
W. T. Russell, Regional Administrator Region I M. Boyle, NRC Project Manager, '4illstone Unit No.1 W. J. Raymond, Senior Resident inspector, Mi]lstone Unit Nos.1, 2 & 3 Y
8909140158 GcOS31 PDR ADOOK 05000245 R
FDC
., ;. :
- DOCKET NO, 50-245 6-UNIT' Millstone 1-
~
-7
.DATE.890901 COMPLETE BY G. Newburgh
. ).
TELEPHONE (203)' 447-1791-1 Extension 4400
) ';.
MONTH. August, 1989.
'~ DAY AVERAGE DAILY POWER LEVEL =
DAY AVERAGE DAILY POWER LEVEL c
(MWe-Net)'
(MWe-Net) 1 654 17 652' 2
654 18 652 647 19 653-3 4
653' 2 ',
~653 5-
'652 21 653
.6 651-22 653 7
652 23 652 8
314 24 646 9;
650 25 653 10; 651 26 653
'll 652 27 652 n
'12 652'
~28 643
-13 651 29 653 14 600 30 652 15-611 31 652 l-16 651 INSTRUCTIONS
'On this format, list the average daily unit power level in MWe-Net for tach
' day in the' reporting month.
Computer to the' nearest whole megawatt.
0 l
- , 2 -
a'
~
OPERATING DATA REPORT DOCKET NO.
50-245-EATE 890901 COMPLETED BY G. Newburgh TELEPHONE (203) 447-1791 Extension 4400
' OPERATING STATUS l.
Unit Name: Millstone 1 Notes':
2,
. Reporting Period: August, 1989 3.
Licensed Thermal Power 04Wt): 2011 4.
Nameplate Rating (Gross MWe):
662 5.
Design Electrical Rating (Net MWe): 660 6.
Maximum DependabJe Capacity (Gross MWe): 684 7.
Maximum Dependable Capacity (Net MWe): 654 8.
If Changes Occur in Capacity Ratangs (Items Number 3 Tb ough 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 i
. Hours In Reporting Period 744 5831 164,423 11.
12.
Number Of Hours Reactor Was Critical 744 4,529.8 129,517.4 13.
Reactor Reserve Shutdown Hours 0
0 3,283.3 14.
Hours General On-Line 744 4,466.5 126,263.6 15.
Unit Reserve Shutdown..vurs 0
0 93.7 16.
Gross Thermal Energy Generated (MWH) 1,464,018 S,689,663_
235.874,324 17-Gross Elec. Energy Generated 04WH) 495,900 2,969,8L9 79,533,396 10.
Net Electrical Energy Generated 04WH) 474,351 2,835,102 75,885,542 19.
Unit Service Factor 100
~~
76.6 76.8
- 20. Unit Availability Factor 100 76.6 76.8
~
- 21. Unit Capacity Factor (Using HDC Net) 97.5 74.3 70.6
- 22. - Unit Capacity Factor (Using DER Net) 96.6 73.6 69.9
- 23. Unit Forced Outage Rate 0
2.2 10.4
{
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, r.nd Duration of Each):
N/A 25.
If Shutdown at End of Report Period, Estimated rate of Startup:
N/A 12 6.
Units in Teat Status (Prior to Commercial Oper'4 tion):
Forcast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A
' COMMERCIAL OPERATION
_ N/A N/A
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. REFUELING INFORMATION REQUEST 1.
Name of facility: Millstone 1 l-2.
Scheduled date for next refueling shutdown: March 1991 3.
Schedule date for restart following refueling:
April 1991
.4.
'a
' refueling or resumption of operation thereafter require a y
niical specification change or other license amendment?
Yes, Technicial Specification Chances Recardinc:
(1)- Maximum Averace Planar Linear Heat Generatino Rate (2) Max 2. mum Critical Power Ratio 5.
Scheduled date(s) for submitting licensing action and supporting information:
Winter 1990-91
)
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:
196 GFBB Fuel Assemblies 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
In Core:
(a) 580 (b) 1928 8.
The present licensed spent fuel pool storage capacity and the size of ar? increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present capacity, 3229 assemblies 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
1997, Spent Fuel Pool, Full Cere Off Lead Capability is Reached
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