ML20101Q955
| ML20101Q955 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1992 |
| From: | Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-92-742, NUDOCS 9207150174 | |
| Download: ML20101Q955 (5) | |
Text
jf l-e NOitTHEAST UTILiflES l
a.ner.i ovi,ce.. somen sueet. B.<nn. Conn cucut l
I Ur E 2 $ E N cI'~*
P.o. box 270
$w.NEI$2 rye 1, HARTFORD. C,oNNECTICUT 06141-0270 k
k 2
m ua v.,m.3.
(203) 665-5000 July 10. 1992 MP-92-742 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Reference:
Facility Operating License No. NPF-49 Docket No. 50-423
Dear Sir:
In accordance with reporting requirements of technical specifications Section 6.9.1.5, the
, Millstone Nuclear Po.ver Station - Unit 3 Monthly Operating Report 92-07 covering opera-tion for the month of June is hereby forwarded.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: Stephen E. Scace Director, Millstone Station C8
~)
s.
4 BY:
Fred R. Dacimo Millstone Site Services Director Attachment -
cc; T.T. Martin, Region i Mm:n;strator W.J. Raymond, Senio Rsdent Inspector, Millstone Unit Nos.1,2 & 3 V. L. Rooney, NRC Proje,.t Manager, Millstone Unit No. 3 9207is'[7'4'9j0630 ~
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- NRC OPERATING STATUS REPDAT CGAPIETED DY REACTOR ENGINEERING *******
1.
DOCKET.... 50 423 OPERATING STATUS
.2.
REPORTING PERIOD... JUNE 1992 OUTAGE + ONLINE HOURS.. 87.6
+ 632.4
- 720.0 3.
UTILITY CONTACT.................A.
L. Elms 203 444 5388 4.
LICENSED THERMAL P0WER.........................................
3411
- MILLSTONE
- 5.
N AME PL ATE RA T I N G ( GROSS MWE )................................... 1,253 MW
- UNIT 3 6.
DE S I GN E L2CTR I CAL R AT I FG (NET MWE )............................. 1,153.6 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MV2)........................
1,184.2
- 8.
M AX I MUM DEPENDABLE CArACI TY ( NE T MWE ).......................... 1,13 7.0 9.
I F CHANGE S DCCUR ABOVE $ 1 N CE L AST RE POR f, RE A SON S AR E...........
N/A
- 10. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)..
............N/A
- 11. REASON FOR REsfRICTION, IF ANY....N/A MONTH YEAR TO DATE CUMULATIVE TO DATE
.===
==
=======seness=mssa
- 12. HOURS IN REPORflNG PERIDO 720.0 4,367.0 54,263.0
- 13. NUMBER OF HOURS THE REACTOR WAS CRITICAL 669.9 2,987.9 39,535.2
- 14. REACTOR RESERVE SKUTDOWN HOURS 0.0 828.1 6,466.5
- 15. HOURS GENERATOR ONLINE 632.4 7,879.1 38,696.9 l
- 16. UWIT RESERVE SHUTDOWN HOUR 9 0.0 0.0 0.0 i
i
' 17. CROSS THERMAL ENERGY GENERATED (HWH) 2,009,608.0 9,282,225.0 126,226,371.0
)
i
- 18. GROSS ELECTRICAL ENERGY GENERATED (MWH) 714,684.0 3,233,f>02.5 A3,584,864.0 l
19.~ NET ELECTRICAL. ENERGY GENERATED (MWH) 476,745.4 3,050,775.7 41,464,?37.5
- 20. UNIT-SERVICE FACTOR 87.8 65.9 71.3
- 21. UNIi AVAILABILITY FACTOR 87.8 65.9 71.3
- 22. UNIT CAPACITY FACTOR (USING MOC NET) 82.7 61.4 67.0
.23. UNIT CAPACITY -FACTOR (USING DER NET) 81.5 60.6 66.2
- 24. UNIT FORCED OUTAGE RATE 0.0 26.2 18.4
- 25. UNIT FORCED OUTAGE HOURS 0.0 1,020.4 0,749.5 SHUTDOWNS SCSEDULED DVER NEXT SIX MONTHS (TYPE,- DATE, A!40 DURATION OF EACH).........
N/A IF CURRENTLY SHUTDOWN, ESTIMATED STARTUP DATE......N/A l
-r AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50423 UNIT hiLLSTONE UNIT 3 DATE lulv8.1222 COMPLETED BYA. L. Ums 203444-5168
- MONTH lune 199; DAY AVERAGE DAILY POWER LEVEL DAY AVERAGr. D AILY POWER LEVEL (MWE - NET)
(MWE - NET) 1 0
16 1123 2
0 17 1123 3
0 18 1115 4
53 19 1123 5
623' 20 1118 6
1090 21 1118 7
1098 22 1122 8
1125 23 1122 9
1127 24 1083 10' 1125 25 1073 11 :.
1126 26 1068 12 1126 27 1071
- 13 1118 28 1069 14 1128 29 1064 15' 1122 30 1063 L
.:s
-]
DOCKET NO. 50-423 UdIT'SHUYDOWNS AND POWER REDUCTIONS UNIT NAME MILw' TONE 3 DATE M-8-92
~
COMPLETED BY A.
L.
Elns TELEPHONE (203) 444-5388 Noe Date Type Dyra-Reason Method of ~
Licensae System Conponent Cause and Corrective (1)'
tion (2)
Shut cown Event Code Code Action to. Prevent Hours Reactor (3)
Rept No.
Prevent Recurrence ci Manually shutdown the 92-04 06/01/92 S
87.6 B-4 N/A AB RV reactor for planned pressurizer PORV and safety valve repair.
1: P: Forced 2: Reasons:
3: Method 4: Exhibit'G - Instructions A-Equipment FailureB-Maintenance or Test (Explain) 1-Manue.1 for Preparation of, Data S: Scheduled 2-Manual Scram Ent y Sneets for Licensee C-Refueli.ng-3-Automatic Scram Event Report (LER) File D-Reguletory Restriction 4-Continued'from (NUREG-0161)
E-Operator Training & License Exam revious month F-Administrative 5 Oower Reduction 5: Exhibit 1 - Same Source G-O,erational Error (Explain) iDuration = Q)
H-0.her 9-Other (Explain)
p
'e REFUELING INFORMATION REOUESI June 1992 I
I r'
1.
Name of facility:-Millstone 3.
l 2.
Scheduled date for next refueling shutdown: lune 5.1993 3.
Scheduled date for restart following refueling: Auc.ust 14.1993 4.
Will refueling or resumption of operation thereafter require a technica! specification change or other license amendm%i N/A 5.
Scheduled date for submitting licensing action and supporting information.
Ulh 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design of performance analysis methods, signifi-cant changes in fuel design, new operating procedures:
Ulh 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a):.111 (b): 24fl 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 nurnber of fuel assemblies:
Present size - 756.
No increase reauestst 9.
The projected date of the last refueling t:iat can be discharged to the > pent fuel pool assuming, the present licensed capacity:
End of cyclel u
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