B16747, Monthly Operating Rept for Aug 1997 for Millstone,Unit 1
| ML20217A912 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/31/1997 |
| From: | Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B16747, NUDOCS 9709230091 | |
| Download: ML20217A912 (6) | |
Text
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Northeast Ry Fem Rct Nte W hh4 W W Nuclear Fnergy wai.ione Noacar Pow siaeon Nurecast Nuclear f.nergy Company P.O. Ilos 128 Wateriord, Cr 06385-0128 (203) 447 1791 l'as (203) 444-4277
'Ihe Northeast Utihues System SEP I 21997 Docket No. 50-245 B16747 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No.1 Facility Operating License No. DPR-21 Monthlv Operatina Report in accordance with the report requirements of Technical Specification Section 6.9.1.6 for Millstone Unit No.1, enclosed is the monthly operating report for the month of August 1997.
Should you have any questions regarding this submittal, please contact Mr. P. J.
Miner at (860) 440-2085.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 3
P. D. Hinnen'ksmp U Director - Unit Operations Millstone Unit No.1 Attachments (1)
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cc:
H. J. Miller, Region I Administrator W. D. Travers, PhD., Director, Special Projects Office l
S. Dembek, NRC Projec' Manager, Millstone Unit No.1 l
T. A. Easlick, Senior Resident inspector, Millstone Unit No.1
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e Docket No. 50-245 B16747 Millstone Unit No.1 Facility Operating License No. DPR-21 Monthly Operating Report - August Y
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September 1997
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- U.3. Nuclear Regulatory Commission B16747%ttachment 1Page 1 1
4 REFUELING INFORMATION REQUEST 1.
Name of the facility:
Millstone Unit 1 2.
ScheduleJ date for next refueling outage: Current refuelina outaae started November 1995. Next refuelina outaae date to be determined.
3.
Scheduled date for restart following refueling: To be determined 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, however the entire scone is to be determined.
5.
Scheduled date(s) for submitting licensing action and supporting information:
None at this time 6.
Important licensing considerations associated with refueling, e.g., new or different j
fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
184 GE-11 fuel assemblies 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core: (a)
Q In Spent Fuel Pool: (b) 3068 Unconsolidated 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:
Present Caoacity: Maximum 3229 fuel assembly locations _
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
1998/1999, soent fuel cool full. core offload caoacity is reached 4
J
U.S Nuclear Regulatory Con. mission 816747%ttachment 1Page 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50 245-i-
Ul41T:
Millstone Unit 1 DATE:
9/5/97 COMPLETED BY:
G. Newburah 1
TELEPHONE: (8601444-5730 J
4 l
MONTH: Auoust.1997 i
j DAY AVG DAILY POWER LEVEL DAY AVG, DAILY POWER LEVEL j
(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
i 7
0 23 0
8 0
24 0
l 9
0 25 0
1 10 0
26 0
l 11 0
27 0
?
12 0
28 0
i 13 0
29 0
j 14 0
30 0
1'
-15 0
31 0
16 0
i.
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in i
the reporting month Compute to the nearest whole megawatt.
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- Y
.S. Nuclear Reguistory Commission U
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+ 8167*47%ttachmerd 1Page 3
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UNIT MAME: Millstone Unit 1 DATE: 9/5/97 j
COMPLETED IN:
G, Newburgh TELEPHONE: (860)444-5730
)
OPERATING STATUS 1.
Docl6et Number 50-245 l
- 2. Reporting Period August 1997 Notes:
- 3. Utility Contact G. Newburgh 1
4 Licensed Thermal Power (MWt):
2011 5.
Nameplate Rating (Gross MWe):
662 l
- 6. Design Electrical Rating (Net MWe): _
660 7, Maximum Dependable Capacity (Gross MWe):
670
- 8. Maximum Dependable Capacity (Net MWe):
641 9,
if Changes Occur in Capacity Ratings (items Number 4 Throegh 8) Since Last Report, Give Reasons:
N/A
- 10. Power Level To Which Restricted, if any (Net Mwe):
0
- 11. Reasons For Restrictions, l' Any:
Regulatory Restriction (10CFR50.54f)
This Month Yr. To-Date Cumulative
- 12. Hours in Reporting Period 744.0 5831.0 233831.0
- 13. Number Of Hours Reactor Was Critical 0.0 0.0 170529.9
- 14. Reactor Reserve Shutdown Hours 0.0 0.0 3283.3
- 15. Hours Generator On-Line 0.0 0.0 166560.7
- 16. Unit Reserve Shutdown Hours 0.0 0.0 93.7
- 17. Gross Thermal Energy Generated (MWH) 0.0 0.0 314372827.0 18, Gross Electrical Energy Generated (MWH) 0.0 0.0 105938737.0
- 19. Net Electrical Energy Generated (MWH) 2335.0 17367.0 101026182.0
- 20. Unit Service Factor 0.0 0.0 71.2
- 21. Unit Availability Factor 0.0 0.0 71.3
- 22. Unit Capacity Factor (Usity MDC Net)
-0.5
-0.5 66.1
- 23. Unit Capacity Factor (Using DER Net)
-0.5
-0.5 65.5
- 24. Unit Forced Outage Rate 100.0 100.0 18.2
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- Shutdown at time of this report
- 26. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:
To be determined
- 27. 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
?.
a U.S. Nuclear Regulatory Commissson B16747%ttachment 1Page 4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-245 UNIT NAME: Mestone Unst 1 COMPLETED BY:
G. Newburah TELEPHONE : 18601-444-5730 REPORT MONTH: August,1997 No.
Date Type' Duration Reason:
Method of License System Component Cause & Conectrve (Hours)
Shutting Event Code' Code
- Acten to Down Reactor
- Report # '
Prevent Recunence 95-10T 951213 F
744 D
4 N/A 10CFR50.54f
' F: Forced
- Reason Method
S: Scheduled A - Equipment Failuro (Explain) 1 - Manuel
" Recommended Practces B - Maintenea ce or Test 2 - Manual Scram for System Iderefesten in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction.
4 - Continued from Previous Month Related Facilities
- E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)
F - Administrative 6 - Other (Explain)
- IEEE Standard 803A-1983, G - Operational Error (Explain)
" Recommended Practces H - Other (Explain) for Urwoue adentifcanon in Power Plants and Related FacArties - Component Function identifiers *
,