ML20045H004
| ML20045H004 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 06/30/1993 |
| From: | Doboe L, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-93-548, NUDOCS 9307160234 | |
| Download: ML20045H004 (5) | |
Text
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9 E NORTHEAST UTILITIES o.nemi omc... seio n s1,.1. a,iin. Connecticut
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ormi..ss.ews ne v.e w.,o r2 O BOX 270 asUb.Iu5bb n HARTFORD, CONNECTICUT 06141-0270 k
J (203) 665-5000 vm ;ca.uyou July 9,.1993 MP-93-548 Re: 10CFR50.71(a)
L U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 f
I.
Reference:
Facility Operating License No. NPF-49 Docket No. 50-423 L
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 93-07 covering-operation for the month ofJune is hereby forwarded.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY e
W Stephen E.
cace Vice President, Millstone Station - NNECO 1
l 1
Attachment cc: T.T. Martin, Region I Administrator P. Swetland, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 L
9307160234'930630 y
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OS3W REV. H8 PDR-ADOCK 05000423 ry R
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- NRC OPERATING STATUS REPORT COMPLETED BY REACTOR ENGINEERING *******
l 1.
DOCKET.... 50 423 OPERATING STATUS 2.
REPORTING PERIOD... JUNE 1993 OUTAGE + ONLINE HOURS...
0.0
+ 720.0
= 720.0 I
3.
UT I L I T Y CONTACT................. L. C. D oboe 203-447-1791 x 6076 4.
LICENSED THERMAL P0WER.........................................
3411
- MILLSTONE
- 5.
NAMEPLAT E RAT I NG ( CROSS MWE )................................... 1,253 MW
- UNIT 3 6.
DESIGN ELECTRICAL RATING (NET MWE).............................
1,153.6 7.
MAXIMUM DEPENDABLE CAPACI TY (GROSS MWE )........................ 1,184.2 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWE ).......................... 1,137.0 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, REASONS ARE...........
N/A
- 10. POWER LEVEL TO WHICH RESTRICTED, I F ANY (WET MWE)...............W/A
- 11. REASON FOR RESTRICTION, IF ANY....N/A MONTH YEAR TO DATE CUMULATIVE TO DATE
=
==
======
- 12. HOURS IN REPORTING PERIOD 720.0 4,343.0 63,023.0
- 13. NUMBER OF HOURS THE REACTOR WAS CRITICAL 720.0 4,165.6 47,203.7
- 14. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 6,466.5
- 15. HOURS GENERATOR ONLINE 720.0 4,104.5 46,235.5
- 16. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 17. GROSS THERMAL ENERGY GENERATED (MWH) 2,449,102.0 13,678,605.0 150,868,903.6
- 18. CROSS ELECTRICAL ENERGY GENERATED (MWH) 829,473.0 4,663,530.0 51,981,768.6
- 19. NET ELECTRICAL ENERGY GENERATED (MWH) 789,007.1 4,426,407.0 49,413,674.3
- 20. UNIT SERVICE FACTOR 100.0 94.5 73.4
- 21. UNIT AVAILABILITY FACTOR 100.0 94.5 73.4
- 22. UNIT CAPACITY FACTOR (USING MDC NET) 96.4 89.6 68.8
- 23. UNIT CAPACITY FACTOR (USING DER NET) 95.0 88.3 68.0
- 24. UNIT FORCED OUTAGE RATE 0.0 5.5 17.7
- 25. UNIT FORCED OUTAGE HOURS 0.0 238.5 9,970.9 SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE, DATE, AND DURATION Oi EACH)..............
Refuel Outage - July 30,1993 - 59 Days, 5 Hours IF CURRENTLY SHU1DOWN, ESilMATED STARTUP DATE......N/A
r s
AVER AGE D AILY UNIT POWER LEVEL DOCKET NO: 50-423 UNIT:
MILLSTONE UNII 3 DATE:
July 6.1993 COMPLETED BY:LC. Doboe 203-447-1791 x 6076 MONTIl June 1993 DAY AVERAGE DA!LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 1104 16
- 1097 2
1104 17 1097 3
1104 18 1094 4
1105 19 1097 5
1101 20 1008 6
1104 21 1096 7
1102 22 1084 8
1102 23 1102 9
1102 24 1093
~
10 1104 25 1101 1I 1102 26 1098 12 1098 27 1097 13 1096 28 1095 14 1100 29 1097 15 1097 30 1096
^
U N IT S II U T D O W N S A N D POWER REDUCTIONS DOCKET NO:
50-423 UNIT:
MILLSTONE UNIT 3 DATE:
July 6.1993 COMPLETED BY: L. C. Doboe TELEPHONE:
203-447-1791 x 6076 T pc Duration Acason Method of Licensce System Component Cause and Corrective Action to Prevent Number Date 3
(1)
(Hours)
(2)
Shutting Event Report Code Code Recurrence Down the Number (4)
(5)
Reactor (3)
None I
_1_;
Type:
2; Reasons:
3; 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 Presious I,fonth E Operator Training & License 5 Power Reduction Exam (Duration = 0)
F Administrative 9 Other (Explain)
G. Operational Error (Explain)
H Other
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,'.'o R E F U E LING IN FO R M A TIO N R EO U EST
]
June 1993
- 1. Name of facility: hfillstone 3.
~ i
- 2. Scheduled date for next refueling shutdown: July 30.1993
- 3. Scheduled date for restart following refueling: September 27.1993
- 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.
j Submitted March 15.1993
- 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 incorporates a stainless steel skeleton and zircaloy fpel claddine design. Cycle 5 feed assemblies will utilize zirlo fuel rod cladding:
glected assemblies will incorocrate a zirlo skeleton. -A Technical Specification change was submitted as per question 5 above
- 7. The number of fuel assemblies (a) in the core and (b)in the spent fuel storage pool:
(a): 193 (b): 248
- 3. The present licarsad <pam fuel poci :tomge c?pacity W. the Ei.- of any !a-av-6 licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present size - 756.
No increase riquested.
- 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.
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