ML20058N306
| ML20058N306 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 07/31/1990 |
| From: | Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-90-780, NUDOCS 9008140040 | |
| Download: ML20058N306 (5) | |
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General Offaces e Selden Street. Berlin, Connecticut -.
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P.O. BOX 270 7,(('((70."" ".,,,
HARTFORD CONNECTICUT 06141-0270
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-J (203) 665-5000 August 9, 1990'-
U.S. Nuclear Regulatory Commission -
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- Document Control Desk Washington, D.C. 20555 l
Reference:
Facility Operating License No. NPF Docket No. 50-423
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 90-08 covering opera-tion for the month of July is hereby forwarded.:
- Very trulyyours, NORTHEAST NUCLEAR ENERGY COMPANY -
'y h
h Stephdn E. cace -
Director, Millstone Station 1;
Attachment cc: T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident Insr,ector, Millstone Unit Ilos.1,2 & 3 D.H. Jaffe, NRC Project Manager, Millstone Unit No. 3
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~ 11 Ii88 NRC OPERAi!NG STATUS REPORT COMPLETED PY REACIDR ENBlNEERINS Itti1i8 '
l.. DOCKET....50-423
.0PERAi!NSStATUS-2.'
REPORilNG PERIOD... JULY? 1990 OUTASE
- ONLINE HOURS.. c 0.0 + 744.0,= 744.0
- 3. ' UTILITY CONT ACT................. A. L. ELRS 203-444 5368 8 : :*II 8 -
- 4. LICENSED THERMAL P0tER.........................................
3411=
$ MILLSTONE 5,. NAMEPL ATE RAllN6 ( 6ROSS ME )................................... 1,253 M t UNil 3 8
tIit8i Ittttt :
- 7. MAI! MUM DEPEND ABLE C APAtliY (6ROSS ME)........................ 1,104.2
- 8. ; MA!! MUM DEPENDABLE CAP AC11Y (NET ME )........................... 1,137.0
- 9. 1F CHANGES DCCUR AB0VE SINCE LAST REPORT, REASONS ARE............
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- 10. P0llt Lit!L 10 VilCI !!$f!!Cf!).11 Alf _(Ilt 5W1)...............I/1 i
- 11. Ills 0510*!!$111C1101,!!Alf...5/1 80171
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.l 12.1001511 IIP 0lflIGPill0D 144.0 5.081.0 A463.0 '
13,1981110F10615til!!!C101IASCliflCAL T44.0 4,243.6
-29,915 14.!!!Cf01IISilft$11TDOWIB0115 0.0 191.6
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-6 15.80015G11111101011,111-f44.0 4.134.9 29,299.9 16.-0111 IISill!S111001110015 0.0 -
0.0 0.0
. If.610S$ fill 3&i,IlllGiGilitif!D(Ill) 2,536.291.0-
-13.201.048.0
. 96.416.457,4 :
- 18. G10SS II,1CfilCAL 1111Gi Gilitif!D (IWI) 812,412.0 4.547.992.5
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~19, lif ILICfilCll, IlllGi G11111110 (IWH) 831,223.3 4,312,8916-131.668.260.3 4
-j 20.011f5111101FACf01 100.0 81/3
'f8.2 21.VilfAIAILABILiffiltf01 100.0 81.3 18.2 a
'22.011fCAPAClf! FACTOR (C5130EDCIlf):
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- 1 SHUfD0VIS$C31101.1D0111I!!!$1110lflS(ffit. Daft,AIDDillfl0101IICl).....a.......
Refuel Outage - February 1-1991 (suHect to C0lf!!~appront) - 56 days.
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4 DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE ~ 3 DATE 3-4 COMPLETED BY A.
EIMS TELEPHONE (203) 444-5388 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 NONE 1: F: Forced 2: Reasons:
3: Method 4: Exhibit G - Instructions A-Egyipment FailureB-Maintenance or Test (Explain)
.S: Scheduled 1-Manual for Preparation of, Data 2-Manual Scram Ent y Sneets for Licensee-
-C-Refueling 3-Autolpatic Scram Event Report (LER) File D-Regulatory sustriction -
4-Continued from (NUREG-Ol61)
E-Op pator Training & License Exam previous month F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source G-Operational Error (Explain)
.(Duration ~= Q)
H-Other 9-Other.(Explain)
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REFUELING INFORMATION REOUEST '
. JULY 1990 I
1.
Name of facility: Millstone 3.
2.
' Scheduled date for next refueling shutdown: February 1.1991 (awaitinn CONVEX :
BUDT2'All
- 3.'
Scheduled date for restart following refueling:- March 29.' 1991 1
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendments?.
As a result of the new ft el desinn. Technical Specifications channes to the Axial Flux.
Difference. Heat Plux F ot Channel Fac"or. and Refueling Water Stora:te Tank sec-
' tions vill be recuired. Furthermore. the Pue: Storane section of Desian ?eatures will-be channed to hilow continued renlonalizecl storane of spent fuel iri the sne at fuel <
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0001. Also. the instrumentation sect'on will be charined to reflect a new Hinh Plux at -
Shutdown setpoint.
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L 5.
Scheduled date for submitting licensing action and supporting information.
September 15.1990.
6.
Important licensin considerations associated with refueling, e.g., new' or different fuel design or su ier, unreviewed design of performance analysis methods, signifi-cant changes in f design, new operating procedures:
Cycle 4 fuel asse'mblies will be of the Westinnhouse Vantane SH desinn. TMs desinn" J
includes debris filter bottom nozzles. intermediate flow mixinn erids. intenra fuel rod ;
burnable absorbers. and axial blankets.
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7.
The number of fuel assemblies (a)in the core and (b)in the spent fuel storage pool:
(a): 193 (b): 160 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capachy that has been requested or is planned, in number of fuel 1
assemblies:
i 1
Present size - 756.
-No increase reauested.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool j
assummg the present licensed capacity:
End of cycle 5.
.