ML20199D384
| ML20199D384 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/31/1997 |
| From: | Mims D, Whitt M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| OCAN119704, NUDOCS 9711200325 | |
| Download: ML20199D384 (14) | |
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1449 S R 333 RJaMc. AR 72831 101501 858 5000 November 17,1997 0CANI19704 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OPI 17 Washington, DC 20555
Subject:
Arkansas Nue' ear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 Licente Nos. DPR 51 and NPF-6 Monthly Operating Report Gentlemen:
Arkansas Nuclear One (ANO), Units 1 and 1 Technical Specifications 6.12.2.3 and 6.9.1.6, respecti":ly, require the submittal of a Monthly Og rating Repon. The purpose of this letter is to complete the reporting requirement for October 1997.
Very truly yours, gkf gw' wipr.Mims Dire t
, Nuclear Safety DCM/eam
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U. S. NRC N:vember 17,1997 OCAN119704 Page 2 cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 760118064 NRC Senior Resident inspector Arkansas Nuclear One P.O. Box 310 l
London, AR 72847 i
Mr. George Kalman NRR Project Manager Region IV/ANO 1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13 II 3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 4
T
Arkansas Nuclear One Unit 1 Monthly Operating ae,, ort
OPERATING DATA REPORT DOCKET NO:
50 313 DATE:
Novemter 17,1997 COMPLETED BY: M. S. Whitt TELEPilONE:
(50l) 858 5566 QERATING STA'!US 1.
Unit Name:
Arkansas Nuclear One Unit i 2.
Reporting Period:
Octoter 131 3.
Licensed Thermal Power (MWI):
2.568 4.
Nameplate Rating (Gross MWe):
903 5.
Design Electrical Rating (Net MWc): 850 6.
Maximum Dependable Capacity (Gross MWe): 883 7.
Maximum Dependable Capacity (Net MWe): 836 8.
If Changes Occur in Capacity Ratings (llems Number 3 Through 7) Since Last Report. Give Reasons:
9.
Ewcr Level To Which Restricted. if Any (Net MWe):
10.
Reasons For itestrictions. If Any:
MONTil YR-TO-DATE CUMULATlVE 11.
Ilours in Reporting Period 745.0 7,296 0 200,467.0 12.
Number ofliours Reactor Was Critical 745.0 7,296.0 151,791.6 13.
Ructor Reserve Shutdown 11ours 0.0 0.0 5,044.0 14.
Ilours ucncrator On-Line 745.0 7,259.7 149,355.0 15.
Unit Resene Shutdownlloers 07 0.0 817.5 16.
Gross Thermal Energy Generated (MWil) 1,869,352 18,105,383 349,633,173 17.
Gross Electncal Energy Generated (MWII) 648,194 6,260,300 117,409,676 18.
Net Electrical Energy Generated (MWil) 620,900 5,994,182 111,779,414 19.
Unit Service Factor 100.0 99.5 74.5 20, Unit Availability Factor 100.0 99.5 74.9 21.
Unit Capacity Factor (Using MDC Net) 99.7 98.3 66.7 22.
Unit Capacity Factor (Using DER Net) 98.0 96.7 65.6 23.
Unit Forced Outage Rate 0.0 0.5 9.5 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling outage IR14 scheduled to commence March 21,1998, with an expected duration of 50 days _
25.
If Shut Down At End of Report Period. Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY OR/06n4 INITIAL ELECTRICITY 08/17n4 COMMERCIAL OPERATION 12/19n4 I
AVERAGE DAILY UNTT POWER LEVEL i
DOCKET NO:
30-313
- UNIT:
One DATE:
Newsaber 17.1997 COMPLE1ED BY: M. S. Winst TELEPHONE:
(50l) 858 5560 4
4.
MON'IH OstglgrJ222.
DAY AVERAGE DAILY POWER LEVEL (MWe-Neo I.............................
850 2.....
851 j
3.............................
851 4.....
851 i
5:
850
=...........
6..............................
850 7..............................
85I 8..............................
851 9..............................
852 10.............................
851 i
Ik.............................
851 12............................
852 I3............................
853 14...
853 15............................
853 16..........................
853 4
17...........................,
843 18.............................
853 2
I9.............................
855 f
20............................
854 2I.........................-...
739 22...........................
351 3
23.........................
854 24...........................
856 25............................
P57 26...........................
858 i
27............................
859 28..
859 2 9.....
859 30............................
859 3I...........................
859 AVOS:
833 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for cach day in reporting month Complete to the nearest whole megawatt.
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UNITSHUTDOWNS AND POWER REDUCTIONS f
REPORT FOR OCTOBER 1997 I
'ACKET MO.
50-313 I
UNITNAME ANO Usat 1 DATE W 17,1997 CORWIETED BY M. S. Whset TurmsgOME 501-855-5560 1
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METHOD OF IJCENSEE.
DURATION SHUT 11NG DOWN EVENT SYSTEM CODEPONENT CAUSE A CORRECTIVE ACTION 10 j
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M' GIOURS)
REASON 8 REACTOR 8' REPORT #
CODE' CODE' FREVENT RECURRENCE i
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5 N/A SJ CAP A poner sedersine se 40% escurred due i
to e erly et menisi $sedpummy eartime K-29.
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I-M emeal ser Freyereelse etDean B h of Test 2 - Mammel scrosa.
Emery h for IJessene C-ReGesEng 3 - Asemusmeic Scream.
Event Report (LER) FRe (NUREG4961)
D-Reguistory Reserkelse 4 - Ceedmemelse l
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NRC MONTIILY OPERA' LING REPORT OPERATING
SUMMARY
OCTOBER 1997 UNIT ONE i
The unit began the month operating at 100% power.
At 2129 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.100845e-4 months <br /> on the r,cventeenth, a power reduction to 85% was commenced to allow the turbine governor valve test to be performed. Following the completion of the test, the unit was retarned to 100% power at 0026 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> on the eighteenth. At 1902 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.23711e-4 months <br /> on the twenty first, a i
power reduction to 40% occurred due to a trip of main feedpump turbine K-2B, The feedpump trip was caused by a capacitor failure on a controller card. The card was replaced on the twenty seced, allowing the unit to return to full power on the twenty-third at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
There were no challenger to the primary system code safeties nor automatic actuation of:he electromatic relief valve during this reporting period.
Reporting Period: October 1997 REFUELING INFORMATION 1.
Name of facility: Arkansa.1 Nuclear One - UniLL 2.
Scheduled date for ricxt refueling shutdown: March 21.1998 3.
Scheduled date for restart following refueling: hjay 10.1998 4.
Will refueling or resumption of operation thereafter requ;te a technical specification change or other license amendment? If answer is yes, what, in general, will there be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?
No. No 3.
Scheduled date(s) for submitting proposed licensing action and supporting information:
MM 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysk ncthods, significant changes in fuel design, new operating procedures.
McMIlaantd 7.
The number of fuel assemblics (a) in the core, (b) in the spent fuel storage pool and (c) dry cask storage:
a)112 b)216 c) 48 8.
'Ihe present licensed spent fuel pool storage capacity end the size of any increase in licensed stcrage capacity that has been rcquested or is planned, in nurnber of fuel assemblies:
present Pf6_5 increase size by 9 9.
The projected date of the last refueling that can be riischarged to the spent fuel pool assuming the present licensed capacity:
Full core off-ind.rapability no lonner available until a sufficient amaunt of spent fuel can be placed in on-site dry storagg.
Arkansas Nuclear One Unit 2 Monthly Operating Report n
E Y
l OPFAATING DATA REPORT DOCKETNO:
50 368 DATE:
November 17,1997 COMPLETED BY: M. S. Whitt TELEPHONE:
g 858 5560 OPERATING STABli 1.
Unit Name:
Arka'inas Nuclear One Unit 2 2.
Reporting Period-Octater I.31 -
3.
Lloonsed Therinal Power (MWt):
2,815 4.
Nameplete Rating (Gross MWe):
942.57 5.
Design Electrical Rating (Not MWe): 3%
6.
Maximen Dependable Capacity (Gross MWe): 897 7,
Maximan &"': Capacity (Not MWe): 858 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Peer Level To Which Restricted If Any (Not MWe):
10.
Reasons For Restrictions. If Any:
h'ONTH YR 10-QAIE 5lJ)ldlL.ATIVE I1.
Hours in Reporting Period 745.0 7,296.0 154,296.0 12.
Number of Hours Rector Was Critical 745.0 6,579.6 122,114.0 13.
Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14.
Hours Generator On-Line 745.0 6,550.3 I I 9,t 78.3
~
15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 i
16.
Gross Thermal Energy Generated (MWH) ;
2,096,422 17,928,768 320,264,185-i
.17. _ _ Gross Electrical Energy Generated (MWH)'-
688,140-5,933,236 105,684,481
- 18. _ Not Electncal Energy Generated (MWH) 657,606 5,658,692 100,603,256 19.
Unit Service Factor 100.0 89.8 77.7 20._
Unit AvailaNiity Factor 100.0 89.8 77.7 21, Unit Capacity Factor (Using MDC Net) 102.9 90.4
- 76.0 22.
Unit Capacity Factor (Using DER Net) 96.8 85.0 71.5 23.
Unit Forced Outage Rate 0.0 0.0 9.6 24.
Shutdowns Scheduled Over Next 6 Months (T3pe, Date, and Duration of Each):
Steam senerator inspection outase whoduled to commence Februaty 20,1998, with an W duration of 22 days
- 25. ' If Shut Down At End of Report Period. Estimated Date of Startup:_
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved
- 26. :
INITIAL CRITICALITY
- 12/0$n8 INITIAL ELECIRICITY 12/26ns COMMERCIAL OPERATION 03/26/80 wyn - Mc 9 gr e
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
$0 368 UNIT:
Two DA'IE:
November 17.1997 COMPLE'ITR BY: M. S. Whitt i
'IELEPHONE:
(50l) 858-;'560 MONTH Q1t@L1222 i
DAY AVERAGE DAILY POW!!R LEVEL (MWe-Not) 1.............................
asi 2.............................
as1 3.............................
s79 4..........................
379 5..............................
s79 6...........
s78 7............................
377 s.............................
87s 9.............................
s79 to.............................
s77 11...........................
s7:
12.......
878 I 3.......
ad i
14.........................
886 15...........................
sus 16.............................
885 17............................
886 is.........................
a86 19............................
sa5 20........................
881 21............................
_ sus 22...........................
as7 2 3.......
886 24.......................
884 2s.............................
s84 26.........................
a86 27...........................
886 2a.............................
886 o
29............................
886 30............................
883 3I.............................
883 AVGS:
883 INSTRUCTION On this l'ormat, list the average daily unit power level in MWe Net for each by iri reporting month Complete to the nearest whole megawstt.
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UNIT SHUTDOWNS AND POWER REDUCTIONS l
REPORT FOR OCTOBER 1997 DOCKET NO.
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UNITNAME ANO Und 2 DAll Novaeber 17,1997 L
COMPIETED BY M. S. Whett TEIEPHONE 501-858-5560 METHOD OF IJCLMSEE
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DURATION SHUTTING DOWN EVLNT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO E
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REN' REAC_ TOR
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Entry h ser IJesesse C-Refeetleg 3 - Amesessaic Screes.
Event Report (LER) FIIe (NUREG4MI)
D-N '.JRestricties 4 ch E-Operecer Training & IJeemse Es%
5 -Imed Reducelme F-A h 9 - Other 5
G - Operstkael Error Enhlhit I-Senne Seerse H - Other (Emplete)
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NRC MONTIILY OPERATING REPORT OPERATING
SUMMARY
OCTOBER 1997 UNIT TWO The unit operated the entire month at 100% power.
There were no challenges to the primary system code safeties nor automatic acutation of the low temperature overpressure protection valves during the reporting period.
6 O
Reporting Period: October 1997 REFUELING INFORMATION 1.
Name of facility: &kanadv1br One Unit 2 2.
Schcduled date for next refueling shutdown: January 8.1999 3.
Scheduled date for restait following refueling: EthnianlL1222 4.
Will refueling or resumption of operation thereafter ruquire a technical specification change or other license amendmmt? If answer is yes, what, in general, will there be? If answer is no, has the reload fuel de:ign and core configuration bcen reviewed by your Plant Safety Rniew Committee to detennine whether any unreviewed safety questions are associated with the core reload (Ref.10CFR Section 50.59)?
N9Jia 5.
Scheduled date(s) for subrnitting proposed licensing action and supporting infornation:
N%
6.
Important licensing considerations associated with refueling, e.g., ww or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Ngns.pjanned 7.
The number of fuel assemblics (a) in the core (b) in the spent fuel storage pool and (c) dry cask storage:
a) 1?]
b) 142 c) 48 8.
Ec 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 9]L8 increase size by 9 9.
He projected date of the last refueling ' hat can be discharged to the spent fuel pool assuming the present licensed capacity:
Full core off-load capability no lonter available until a sufficient amount of spent fuel can be placed in on-site dry storans.
6