ML20058N308
| ML20058N308 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 07/31/1990 |
| From: | Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-90-787, NUDOCS 9008140042 | |
| Download: ML20058N308 (5) | |
Text
-
g y
7 -.
a.$,
.L. >'W c
g.-
mesmemastummes LM-t
.+
aann, m n.
180R1'E481 Utt>IES N#MA Canarm
~
{
g o-Tri j
i
! (p't i
. August 9,1990 glP MP-90-787-i Re:
10CFR50.71(a) t U.S.- Nuclear Regulatory Commission Document Control Desk-(
i.
Washington, D. C. 20555
'l 1
Reference:
Facility Operating License No, DPR 65 Docket No. 50 336
Dear. Sir:
.i
'This letter ~is forwarded to provide the report of operating and' shutdown
(
. experience relating to Millstone Unit 2 for the month of. July,1990, in I
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' i
3 r
4-S
- anE, ca
-Station Director' Millstone Nuclear Power Station L
.SES/GN cc: T.'-T.' Martin, Region I Administrator
- G. S. Vissing, NRC Project Manager, M111 scone Unit No. 2 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3-
.4,
nr 9008140042 900731 PDR ADOCK 05000336
- R -
PDC oS70 REY 745 ~
. BP9,1
/
1 G
4 8 OPERATING DATA REPORT DOCKET NO.
50 336-DATE 08/09/90 COMPLETED BY G. Neron TELEPHONE (203) 447-1791 EXT.
4417 OPERATING STATUS Notes: Items 21 and 22 1.
Unit Name:
Millstone Unit 2 cumulative are weighted 2.
Reporting Period:
July 1990 averages. Unit operated-3.
Licensed Thermal Power (MWt):
2700 at 2560 MWTH prior to its
~ 4.
Nameplate Rating (Gross MWe):
909 uprating to the current 5.
Design Electrical Rating (Net MWe):
870 2700 MWTH power level.
6.
Maximum Dependable Capacity (Gross MWe):
893.88 7.
Maximum Dependable Capacity (Net MWe):
862.88 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, 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 744.0 5087.0 127967.0
- 12. Number Of Hours Reactor Was Critical 744.0 4195.9 94557.0
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5
- 14. Hours Generator On-Line 744.0 4158.4 90109.8
- 15. Unit Reserve Shutdown Hours 0.0 0.0 468.2
- 16. Gross Thermal Energy Generated (MWH) 2008021.0-11110870.0 249246708.4
- 17. Gross Electrical Energy Generated (MWH) 657496.5 3613471.5 75532641.5 j
- 18. Net' Electrical Energy Generated (MWH) 634705.5 3477468.5 72474102.5
- 19. Unit Service Factor 100.0 81.7 70.4-
- 20. Unit Availability Factor 100.0 81.7 70.8
- 21. Unit Capacity Factor (Using MDC Net) 98.9 79.2 66.6
- 22. Unit Capacity Factor (Using DER Net) 98.1 78.6 65.3
- 23. Unit Forced Outage Rate 0.0 1.8 13.4' i
- 24. Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
l End of Ovele 10 Refuel Outare. Seotember 15. 1990. 40 days.
25, If Unit Shutdown At End Of Report Period, Estimated Date of Startup:
N/A
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY N/A N/A l
INITIAL ELECTRICITY N/A N/A l
COMMERCIAL OPERATION N/A N/A l
l l'
i i
i
T j
H 1
u
-,,t,
,9 l
4 AVERAGE DAILY UNIT POWER LEVEL'-
DOCKET NO.
50 336
. UNIT:
Millstone Unit 2.
DATE:
08/09/90 COMPLETED:BY:
G. Neron
-TELEPHONE:
(203)447-1791-EXT:
4417 NONTH:
' JULY 1990 DAY AVG. DAILY POWER ~ LEVEL DAY AVG. DAILY POWER LEVEL i
(MWe-Net)
(NWe-Net)-
'l-854 17 856 o 1 2
853 18 855 3
854 19 855 4
856 20 854 5
856 21 853 6-856 22 852 7
856 23 851
'8 856 24 851 9'
856 25 850 10 856 26' 849 i
i 11 857 27 849
.12 857 28 849 f
13 857 29 847 14 856 30 845 15 856 31 841 16-855 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.
f
73 l~-
~
?;
(; ?
~
! ~
=._
m x.
DOCKET NO.'
"50-336'
~
' UNIT SHUTDOWNS AND POWER REDUCTIONS aUNIT NAME Millstone'2 1_
DATE.
08/09/90
-COMPLETED BY G.-Neron
~
^
TELEPHONE
'(203) 447-1791
~
. REPORT MONTH.-
JULY 1990 EXT.
4417~~
l 2-
.:.Method of
-License.
Systgm.
Compgnent.
Cause &. Corrective.:=
No.
Date Type Duration Reason (Hours)
Shutting Event' Code Code
- Action toi' 3
Down Reactor Report #
- Prevent: Recurrence' N/A N/A N/A N/A N/A N/A N/A N/A N/A--
N/A 1: Forced Reason:
Method
' Exhibit G - Instructions 2
3 F
S: Scheduled A-Equipment Failure-(Explain) 1-Manual
'for Preparation'of' Data B-Maintenance'or Test 2-Manual Scram Entry. Sheets for License C-Refueling 4-Continued from' (NUREG-0161)
D-Regulatory Restriction.
3-Automatic Scram-Event Report (LER) File E-Operator Training & License Examination Previous month 3
F-Administrative ~
5-Power Reduction-Exhibit 1 -Same Source C-Operational-Error (Explain)
(Duration -0) l H-Other.(Explain).
. 6-Other (Explain).:-
l p+-
- vr.*
).
p.tm"g, w'
-~
-w-'
g-i MMN.*-
. e 'y
- yrein, en-
-s
-I
>},'--'--
m
.rmee.
-+i.,(
anWgn.
6-m
-wg-M,
.*y-w-
e--
g-7-w.Am_
.,m%$.6.,w.4._.,m-
,_._L_ _ _ _ - -_,
__y g,u-
,q____q__
3
-_i_prqM
,.'[ ' f '
1 1
REFUELING INFORMATION REOUEST
- 1. ; Name.of_ facility:- Millstone 2 2.
Scheduled date'for next refueling-shutdown:
SeDtember 15. 1990 H3.
Scheduled date for restart following' refueling:
N/A 4.
Will refueling or resumption of operation thereafter require a
' technical specification change or other license amendment?-
YES 5.-
Scheduled date(s) for submitting licensing action and supporting information:
ProDosed Technical Specification submittal for the CORE OPERATING LIMITS REPORT was submitted on 6/26/90; ADoroval is anticioated Drior to restart.
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:
=
None
'7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core:
(a) 212 In Spent Fuel Pool:
(b) 512
-8.
The present licensed spent fuel pool storage capacity andlthe 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 L
the spent fuel pool assuming the present licensed capacity:
{
-1994. Soent Fue:
Pool Full, core off load caDacity is reached (with L
-out consolidat:.on).
1998. Core Full.-SDent Fuel Pool Full 2009'. SDent Fuel Pool Full, core off load caDacity is reached-continaent uDon full scale storace of consolldated fuel in the Eggnt Fuel Pool.
l l
o i