B16952, Monthly Operating Rept for Dec 1997 for Mnps,Unit 1
| ML20198Q024 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1997 |
| From: | Hinnenkamp P, Newburgh G NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B16952, NUDOCS 9801220318 | |
| Download: ML20198Q024 (6) | |
Text
_.. _ _. ~ _
g Ege Terry Rd. (mmte 156), Eberford. CT 06385 o
h Fanergy wiii s.a a, r., si.t.n
, cast Nwhr D,rrFy Cungany Waterfurd, Cr 06385-0128 (860) 447 1791 Fas (860) 444 4277 lie Nortlmt ti ibties Systein t
JAN I 51998 Docket No. 50-245 B16952 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 Monthly 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 December 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 P. D. Hinnenkamp V
Director - Unit Operations 7
Attachments (1) e
/ y 'g) h g
cc:
H. J. Miller, Region l Administrator i)
W. D. Travers, PhD., Director, Special Projects Office S. Dembek, NRC Project Manager, Millstone Unit No.1
~
T. A. Easlick, Senior Resident inspector, Millstone Unit No.1
@2M E 5
git!ty.w...it.
fue4304 MV.13 M '
' L i
i o
i e
Docket NgJQ:2si I
B16952 1
i I
i i
Millstone Nuclesr Power Station, Unit No.1 i
Facility. Operating License No. DPR 21 Monthly Operating Report - Dowmber 1997 h
I i
e i
i i
6
=
January 1998
?
b t
t
,e w
y-4...e---,--~ra_.-r,-,-+me-.y-,a.-r-,-,r-y--,.
--m-.,-,
r---
v y
,vw<,
s, w
--,r%,e y
i
'U.S. Nuclear Regulatory Commission B16952%ttachment 1\\Page 1 REFUELING INFORMATION REQtjiSI i
- 1. Name of the facility:
Millstone Unit i 2.
Scheduled date for next refueling outage: Current refuelina outaae started l
November 1995. Next refuelina outaae date to be determined.
3.
Scheduled date for restart following refueling: To be determinea 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.
3cheduled 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 fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
184 GE 11 fpel 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 Canacity: Maximum 3229 fuel assembly leaatinnt
- 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
2QQQl2001, soent fuel cool full, core offload capacity is reached
+
~
,ya g
es
,e
=-_.
U.S. Nuclear Regulatory Commission B16952%ttachment 1\\Page 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50 245 UNIT:
Millstone Unit 1 DATE:
1/6/98 COMPLETED BY:
G.Newburah TELEPHONE:
(8601444 5730 MONTH: December,1997 DAY AVG. DAILY POWER LEVEL DAY AVG. 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
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 O
S1 O
16 O
INSTRUCTIONS On this format, list the average daily unit power lovs!in MWe-Net for each day in the reporting month Compute to the nearest whole megawatt-
U h, huClear Regulatory Commission B16952%ttachment 1\\Page 3 DOCKET NO.: 50 245 UNIT NAME: Millstone Hti j
i DATE: 1/6/98 i
COMPLETED sY:
G. New',.;,
TELEPHONE: (86014aev/30 i
OPERATING STATUS 1.
Docket Number 50 246
- 2. Reporting Period December 1997 Notes:
- 3. Utility Contact G. Newburgh i
4.
Licensed Tiermal Powv,/ (MWt):
2011 4
- 6. Nameplate Rating (Gross MWe):
662 l
- 6. Design Electrical Rating (Net MWe):
060
- 7. Maximum Dependable Capacity (Gross MWe):
670 t
- 8. Maximum Dependable Capacity (Net MWe):
641
- 9. If Changes Occur in Capacity Ratings (items Number 4 Through 8) Since Last Repcrt, Give Reasons:
N/A
- 10. Power Level To Which Restricted, if any (Net MWe):
0
- 11. Reasons For Restrictions,if Any:
NRC Category 111 Facility This Month Yr. To Date Cumulative
- 12. Hours in Reporting Period 744.0 8760.0 236760.0
- 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 OrrLine 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 i
- 16. Net Electrical Energy Generated (MWH) 2221.0 26821.0 101017726.0
- 20. Unit Service Factor 0.0 0.0 70.4 21, Unit Availability Factor 0.0 0.0 70.4
- 22. Unit Capacity Factor (Using MDC Net)
-0.5
-0.5 65.3
- 23. Unit Capacity Factor (Using DER Net)
-0.5
-0.5 64.7
- 24. Unit Forced Outage Mate 100.0 100.0 19.3
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
St";tdown 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 r
U.S. Nuclear Regulatory Commission B16952Wtachment 1\\Page 4 UMT SHUTDOWNS AND POWER REDUCDONS DOCKET NO.:
50-245 UNIT NAME:
Millstone Urwt 1 COMPLETED BY:
G. Newburah TELEPHONE:
(8601444-5730 REPORT MONTH: December,1997 No.
Date Type' Duration Reason
- Method of bcense System Component rame & Corrective (Hours)
Shuttmg Event Code
- Code
- Action to Down Reactor
- Report #
Prevent Recurrence 95-10X 951213 F
744 D
4 N/A 10CFR50.54(f) e i
' F: Forced a g,,,,,
Method
S: ScMw A - Equipment Failure IExplain) 1 - Manual
- Recommended Practaces 8 - Maintenance or Test 2 - Manual Scram for System identif~ cation in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restnction 4 - Continued from Previous Month Related Facalities*
E - Operator Traerung & bcense Examination 5 - Power Reduction (Duration = 01 F - Admsrmstratrwe 6 - Other (Explain)
- IEEE Standard 803A-1983, G - Operational Error (Explain)
" Recommended Practces H - Other (Explain) for Uneque identification in Power P. ants and Related Facahties - Component Functm klentifiers" OO
-]