ML20057E851
| ML20057E851 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 09/30/1993 |
| From: | Doboe L, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-93-796, NUDOCS 9310130242 | |
| Download: ML20057E851 (5) | |
Text
.
NORTHEAST UTILITIES cene,ei omee.. seiaen sireet. serun. Connecticut w c m ec.n(m.a ee m aa -.
I wsna e.ces rucw c ***
P O. BOX 270 n et..n. em a coww HARTFORD. CONNECTICUT 06141-0270 k
k J U $ ($$Yaov I.
(203) 665-5000 l
Re: 10CFR50.71(a)
October 7,1993 MP-93-796 U.S. Nuclear Regulatory Commission j
Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating License No. NPF-49 Docket No. 50-423 I
Dear Sir:
In accordance with reporting requirements of Technical Specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 93-10 covering operation for the month of Septmeber is hereby forwarded.
Very tmly yours, NORTHEAST NUCLEAR ENERGY COMPANY Stephen E. cac N Vice President, Millstone Station - NNECO Attachment cc: T. T. Martin, Region 1 Administrator P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 j
l i
1 l
9310130242 930930 M
PDR ADDCK 05000423 N
')
l R
pon y'
0 S342/ REV. 4-BB 1 g g) v v L j
l i
I I
i 1
l
- NRC DPERATING STATUS REPORT COMPLETED BY REACTOR ENGINEERING **8 ****
4 1
1.
DOCKET.... 50-423 DPERATING STATUS 2.
REPORTING PER100... SEPTEMBER 1993 OUTAGE
- ONLINE HOURS.. 720.0
+
0.0
= 720.0 3.
UT I L I TT CONT ACT.................L. C. Doboe 203-447-1791 x 6076 -
4.
LICENSED THERMAL P0WER.........................................
3411
- MILLSTONE
- l 5.
N AMEPLAT E R AT I NG ( CROSS MWE ).................................... 1,253 MW
- UNIT 3 l
6.
DESI GN ELE CTR I CAL RAT I NG ( NE T MWE )............................. 1,153.6 7.
MAX I MUM DEPENDABLE CAPACI T Y ( GROSS MWE )........................ 1,184.2 8.
MAX I MUM DEPEND ABLE CAP AC I TY ( NET MWE ).......................... 1,137.0 i
9.
IF CHANGES DCCUR ABOVE $1NCE LAST REPORT, REASONS ARE...........
N/A
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (WET MWE)...............N/A
- 11. REASON FOR RESTRICTIDW, IF AUT....%/A l
MONTH YEAR TO DATE COMULAT!VE TO DATE
=
============.
======
i
- 12. HOURS IN REPORTING PERIDO 720.0 6,551.0 65,231.0 i
- 13. WUMBER OF HOURS THE REACTOR WAS CRITICAL 0.0 4,891.8 47,929.9 i
- 14. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 6,466.5 i
i
- 15. HOURS GENERATOR ONLINE 0.0 4,B25.5' 46,956.5 t
- 16. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 l
- 17. CROSS THERMAL ENERGY GENERATED (MWH) 0.0 16,060,834.0 153,251,102.6 l
18.' GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.0 5,464,147.5 52,782,386.1
)
l
- 19. NET ELECTRICAL ENERGY GENERATED (MVH)
-5,247.6 5,174,743.5 50,162,010.8 l
l l
- 20. UNIT SERVICE FACTOR 0.0 73.7 72.0 l
- 21. UNIT AVAILABILITY FACTOR 0.0 73.7 72.0
- 22. UNIT CAPACITY FACTOR (USING MOC NET) 0.0 69.5 67.5
- 23. UNIT CAPACITY FACTOR (USING DER NET) 0.0 68.5 66.7
- 24. UNIT FORCED OUTACE RATE 0.0 4.7 17.5 i
- 25. UNIT FORCED QUTAGE HOURS 0.0 238.5 9,970.9 SHUTDOWNS SCHEDULED DVFR NEXT SIX MONTHS (TfPE, DATE, AND DURATION OF EACH)..............
N/A l
l l
IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE..... 0ctober 20 1993 l
l l
l~
i l
A VERAGE D AILY UNIT POWER LEVEL DOCKET NO: 50-423 UNIT:
MILLSTONE UNIT 3 DATE:
October 2.1993 COMPLETED BY: L. C. Doboe 203-447-1791 x 6076 l
MONTH September 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) i 1
0 16 0
l 2
o 17 0
3 o
18 0
4 0
19 0
5 0
20 0
6 0
21 0
7 0
22 0
8 0
23 0
9 0
24 0
10 0
25 o
11 0
26 0
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
U N I T S II U T D O W N S A N D POWER REDUCTIONS DOCKET NO:
50-423 UNIT:
MILLSTONE UNIT 3 '
DATE:
October 2.1993 COMPLETED BY: L. C. Doboe TELEPHONE:
203-447-1791 x 6076 Number Date Type Duration Reason Method of Licenscc System Component Cause and Correctisc Action to Prevent (1)
(flours)
(2)
Shutting Event Report Code Code Recurrence Down the Number (4)
(5)
Reactor (3) 93-04 930731 S
720 C
4 N/A N/A N/A Refuel Outage 4 continued from previous month.
t Tvoc:
1 Reasons:
1 Method 4: IEEE Standard 805-1984 F: Forced A Equipment Failure (Explain) 1 Manual S: Scheduled B Maintenance or Test 2 Manual Scram 5:
IEEE Standard 803A-1983 C Refueling 3 Automatic Scram D Regulatory Restriction 4 Continued from Previous Month E Operator Training & License 5 Power Reduction Exam (Duration = 0)
F Administrative 9 Other (Explain)
G Operational Error (Explain)
II Other i
m
1 R EFU ELING INFO R M ATION R EO UEST September 1993
- 1. Name offacility: Millstone 3.
- 2. Scheduled date for next refueling shutdown: July 30.1993 Currently in Refuel Outage
- 3. Scheduled date for restart following refueling: October 20.1993 l
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendments?
Yes
- 5. Scheduled date for submitting licensing action and supporting information.
Submitted March 15.1993 & Julv 30.1993
- 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design of performance analysis methods, significant changes in fuel design, new operating procedures:
Millstone Unit 3 current fuel design incoroorates a stainless steel skeleton and zircalov fuel cladding design. Cycle 5 feed assemblies will utilize zirlo fuel rod cladding:
selected assemblies willincorporate a zirlo skeleton. A Technical Soecification change was submitted as per cuestion 5 above. In addition. a Technical Specification change to increase the required boric acid volume in the Boric Acid Storage Tank was submicted on July 30.1993.
- 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a): 19] (b): 332
- 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 l
i assemblies:
Present size - 756.
No increase reauested.
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
End of cycle 5.