ML20099F871
| ML20099F871 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/31/1992 |
| From: | Elms A NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20099F868 | List: |
| References | |
| NUDOCS 9208130263 | |
| Download: ML20099F871 (4) | |
Text
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- "*" NRC OPERA 11NG $f ATUS REPORT COMPLf1ED BY RE ACTOR INGINEERING ""*"
1.
DOCKET.... 50 423 OPERAtlNG $1ATUS 2.
RENeilNG PERIOD... JULY 1992 OUTAGE + DNLlWE HOUR $..
16.3
+ 727.7 e 744,0 3.
U11Liff CONTACT.................A. L. Elas 203 444 5358 4 L I CE NSE D T H( RMAL P0WE R......................................... 3411
- MILL $f0NE
- 5.
W AME PL AT E R A f l NG (CROS $ MWE )................................... 1,25 3 MW
- UN11 3 6.
DE $ 1 GN ( L f CT R I CAL R All NG ( NE T MWE )............................. 1,153.6 7.
max l MUM DEP( ND ABLE CAPAC l f Y ( CROS$ MWE )........................ 1,184. 2 8.
MAXIMUM DEPENDABLE CAPACITY (Nti MWE)........................... 1,137.0 9.
I F CHANGE S DCCUR ABOVE S I NCE L Alf REPOR T, PE ASONS ARE...........
N/A
- 10. POWER LEVEL 10 WHICH Rf t1RICitD, IF ANY (kEl MWE)...............W/A
- 11. REASON FOR RE$1RIC1104, if ANY....N/A
- h. " 4 YEAR 10 DATE CUMULATIVE 10 DATE wwe
.eusnsnes masses ussn essu e
- 12. HOUR $ IN REPOR11NG PERICO 744.0 5,111.0 55,007.0
- 13. WOMBER OF HOUR $ THE REACTOR WAS CRiflCAL 744.0 3, 731.9 40,279.2
- 14. react 0R RESERVE $HUIDOWN HOURS 0.0 828.1 6,466.5 15, HOUR $ GENERATOR ONLINE 727.7 3,606.8 39,424.6
- 16. UNIT RESERVE $HUTDOWN HOURS 0.0 0.0 0.0
- 17. GROSS THERMAL (NERGY GENERATED (MWM) 2,418,929.0 11,780,778.1 128,724,924.0
- 18. GROS $ ELECTRICAL ENERGY GENERATED (MWH) 828,472.5 4,062,075.0 44,413,336.5 I
l
- 19. NET (LECTRICAL ENERGY GENERATED (MWH) 787,460.2 3,838,235.9 42,251,697.7 1
- 20. Unit SERVICE FACTOR 97.8 70.6 71./
- 21. UNIT AVAILABILITY FACTOR 97.3 70.6 71.7
- 22. UNIT CAPAC11Y FAttoR (USING MDC NET) 93.1-66.0 67.4
- 23. UWli CAPACITY FACTEnt (UstWG DER NET) 91.7 65.1 66.6
- 24. UN11 FORCED OUTAGE RATE 2.2 22.3 18.2
- 25. UNIT FORCED OUTAGE HOURS 16.3 1,036.7 8,765.8 SHUTDOWNS $CHEDULED OVER NEXT S I X MONT H$ ( T Y PE, D AT E, AND DUR AT I ON OF E ACH ).............
N/A l
IF CURRENTLY SHUTDOWN, ESilMATED STARTUP DATE......N/A 9208130263 920811 PDR ADOCK 03000423 R
PDR V
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
EL423 UNIT MILLSTONE UNIT 3 DATE Aurust 8.1922 COMPLETED BYA. i. Elms 203 444 5388 j
l MONTH luly 1992
' DAY AVERAGE DAILY POWER ((VLL DAY AVIRAGE DAILY POWER LEVEL (MWL N[T)
(MW[. NET) 1 1028 16 1122 2
9DB 17 1126 3
39 18 1125 4
606 19 1058 5
1102 20 1113 6
1117 21 1118 7
-1120 22 1102 8
1119 23 1124 9
-1118 24 1126 10 1114 25 1127 11 1113 26 1126 12~
1116 27 1126 13 1115 28 1121 14 1115 29 1124
'15 1114-30 1121 31 1122
v DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE.3 DATE 08-10-92 COMPLETED BY A.
Elms TELEPHONE (20 44-5368 f
i No.
Date Type Dura-Reason Method of Licensee System Component Cause and Corrective (1),
tion (2)
Shut down Event Code Code Action to Prevent Hours Reactor (3)
Rept No.
Prevent Recurrence l
Manually shutdown the 92-05 07/03/92 F
16.3 A
N/A N/A EL XFMR turbine due to high hot side bushings on the main transformer. Reactor remained critical.
l 1
1: F: Forced 2: Reasons:
3: Method 4: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Ent W Sneets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-Ol61)
E-Operator Training & License Exam previous month F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source G-Operational Error (Explain)
(Duration = 0)
H-Other 9-Other (Explain)
REFUlllNG INFORMATION REOUf_S1 July 1992 1.
Name of facility: hiillstone 3.
2.
Scheduled date for next refueling shutdown: lune 5.1991 3.
Scheduled date for restart following refueling: August 14.1993 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendmentst bl/h 5.
Scheduled date for submitting licensing action and supporting information.
Nih 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): 123 (b): 2_48 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 size _ZM, Np increase reapested.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licnnsed capacity:
f nd of cycle 5.
2
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