ML20094K468
| ML20094K468 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 02/29/1992 |
| From: | James Fisicaro, Hayes K ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN39207, NUDOCS 9203200361 | |
| Download: ML20094K468 (7) | |
Text
. _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _..
t EntCrgy c,,i.<u o,... u a..i c.
.: =
. Operations March 16, 1992 1CANO39207 U. 5. Nuclear Regulatcry Commission Document Control Desk Mail Stop P1-137 Washington, D.C.
20555 SUluECT:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 hicense No. DPR-51 Monthly operating Report Gent icinen Monthly operating Report statistics for Arkansas Nuclear One, Unit 1 for February,1992 is attached. This report is submitted in accordance with ANO-1 Technical Specification 6.12.2.3.
Ve y truly yours, As c+
m -+.
James J. Fisicaro Director, Licensing JJF/ SAD /sjf Attachment 23000E;
((
9203200361 920229
/
,1 PDR ADOCK 05000313
\\
R PDR
\\
U. 8. NRC e
Harch 16, 1992 Pago 2 4
cc:
Mr. Robert D. Hartin Kogional Administrator U. H. Nuclear Regulatory Comminnion Region IV 611 Ryan I' lata Drive, Suito 400 Arlington._TX 76011-8064 NRC Henfor Resident innpector Arkansan Nucionr Ono - AND-1 6 2 Number 1. Nuclear Plant Road Hunnolivillo, AR 72801 Mr. Thoman W. Alexion NkR Project Hannger. Region IV/ANO-1 U. S. Nuclear Regulatory Comminnion NRR Hall Stop 13-11-3 Ono Whito Filnt North 11555 Rockville Pike Rockvillo, Maryland 20852 Ma. Sherl l'eter son NRR Project Hannger, Region IV/ANO-2 U. S. Nuclear Regulatory Comminnion NRR Hall Stop 13+11-3 One Wh1te Flini North 11555 Rockvilln Pike Rockvillo Haryland 20852 i
UPERATING DATA Kl; PORT DOCEET NO:
50-313 DATE:
Hnich 5, 1992 COMPl.ETED liY: E._ _ R._ _H a y e s _ _.
Tl;t.EPil0NE :
(501).964-5535 RIHAIINLSIAIVS 1.
Unit Name: Arkansas Nyclen.r__One.- Unit _1 2.
Reporting Pertod:
Felqua r y.. )- 2 % _.1,9 9 2 3.
1.icetised Thermal Power (MWt):
2,568._
4.
Nameplate Rating (Gross HWe):
902.74 _,__ _ _
5.
Design Electrical Rating (Not HWe):
850_ _ _
6.
Maximum Dependable Capacity (Gross HWe):
883 7.
Maximum Dependable Capacit y (Net HWe):
836 8.
If Changes Occur in Capacity Rnt ings (ltems Number 3 Thiough 7) Sinee 1.nst Report, Give Rensons:
9.
Power 1.evn! To Which Restricted.
If Any (Net HWe):
.None _, ___
10.
Reasons for Restrictinns.
If Any: None _.
MONIll R-ID.DAIL GnULA11YE 11.
llours in Keporting Period....
696.0 1,440.0 150,763,0 12.
Number of Ilours Renctor was Critical.....................
672.5 1,416.5 107,277.7 13.
Reactor Reserve Shutdown llours........................
0.0 0.0 5,044.0 14.
Ilours Generntor On-l.ine 672.I 1.416,1 105,148.9 15.
Unit Reserve Shutdown ilours 0.0 0.0 817.5 lb.
Gross Thermal Energy Genernted 1,670,188.0 3,557,599.0 238,739,037.0 (HWil) 17.
Gross Electrical Energy Generated (HWil) 576,845.0 1,225,900.0 79,504,440.0 18.
Net Electrical Energy 551,959.0 1,173,935.0 75,549,183.0 Omnernted (HWil) 19 Unit E.rvice Fnctor..........
96.6 98.3 69.7 20.
Unit Availability Factor.....
96.6 98.3 70.3 21.
Unit Capacity Factor 94.9 97.5 59.9 (Using HDC Net) 22.
Unit Captcity Factor (Uning D2C Net) 93.3 95.9 59.0 23.
Unit forced Out.nge Rate 0.0 0.0 12.3 24.
Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Enth):
1R10 Refueling Outage began at 10007 hrs)_on,Pelprunty 29 _1992;_the_ unit _
3 1s_sched_ulest to restart J0400 hrs)_Apri.1_28, 1992.
25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Opernt lon):
Forecast Achieved INITIAL. CRITICAL.lTY 08/06/74 INITIAh El.ECTRICITY 08/17/74 COMMERCIAh OPERATION 12/19/74
Avi:KAGl'.11All.Y UNIT l' owl;K 1.hYl:1.
110CKl'T NO:
50-31'i UNIT:
Onn DATl' t lin i e h 5, [ 19 0 2..
00:ll'l.ETrl) IlY : K. R. Ilnyes TI:LLi'110NI;:
(501)_964-5535 MONTil [p b r_u n t y,,19 9 2 DAY AVI;KAGE 11A11 Y l'0Wl;R !.1;VI;t.
(MWn-Net) 526 1..............
2..............
543 3..............
845 4..............
846 5..............
847 6..............
846 7
849 B..............
849 9..............
648 10.............
848 11.............
849 12.............
849 13.............
853 14.............
850 15.............
848 16 848 17.............
847 in.............
848 19.............
848 20.............
849 21 848 22.............
849 23.............
850 24.............
849 25.............
848 26.............
847 27.............
842 28.............
757 29.............
-26 AVGS:
793
.I_N.S_TR_UC_T_I O_N_
On this format, list the average daily unit power levnl in MWe-Net for each day in report ing mont h.
Compute to t he nenrest whole megowntt.
oi
1 110NTill.Y OPERATING KEP0H1 OIT.KATING SlHMARY IT.l' KU AR Y, 1992 UNIT ONC Unit 1 began the moi.th operatitig at full power.
At 0104 hourn on the first, the lond wns reduced to 601 power at the requent of the syntem dJapatcher. During this power ieduction, the turbine throttic and goversior valves were tected, the E84 feedwater henter was nepnited, and the condenser wat erboxen were cientied.
The utilt returned to full power at 2358 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.97219e-4 months <br /> on the second.
On t h e twenty-seventh at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, the unit load was reduced to 981 to perfor m scheduled testing of the multi steam Hafety valves.
Power was returned to 100'. on the same day at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.
On t he twenty-eighth at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, the unit lond was decreased to 981 to complete T5c unit returned to full power testing of the main steam nnfoty valves.
i at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on the same day.
At 1926 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.32843e-4 months <br /> on the twenty-eighth, the unit commenced a ramp down to begin the scheduled 1K10 refueling outnge.
The unit went off line at 0007 houts on the twenty-ninth.
l 1
-~
lll IIljill lll4ll!
rs d
e n
2 e
e p'r e
9 v
c 9
5 i
n e
k e 1
3 t
e nh ah 5
cor oc tt g
, s 5 et r it n
e(
1 4
e r
u t a sri s
e v-4 rnc cp aol nase e
t y a 6 ooe us wf e ot nl c
i r H 9 CiR di u
i aei r
3 n a t
ed.
t ef tDcT u
1 U u
. )
&ct r
t ine.
c i
o 3
r R 1
An ms niR e ufL)
S ro snom O b 0
e e
ree ul g
t r
e 0
N e
. 5 s
v et u 0 a m
5 AFK(
u e
wsq ef1 t a
r oye hfRu nof(
a C
P Psr ToI O I i S
t st Y
- at r B
reo Gaep I
- u. NE t
ph e 0E r
n t eSR t
NM i r i
A A C eS i
- t. H ne bPyt) b
- w. N LP od A
i rn2 i
TEPE po
/
h rt e2 h
ITML mC N
r onv0 x
ONAOE o
= T FEE 1 S E DUDCT C
m ma n
e 'e A
.r o
tsd
/
mcni yo N
aS ot SC r
i c cct u S
Si ad N
t ue O2 ll anR I9
- aami r
T9 e
C1 e
d uuotd e U
s' t
onnt nah nt r haaseot D
EY eno A
A tM5ACLO RR cep
/
/
e-A i ve N
N s M123459 RU LER ER
)
)
iiB OE n
n i
i PF a
a DR r
l l
NO o
p s
p AF t
x c
x f
c E
i E
n
(
ST oga
( t t&o c
NR ne s
iO diR A
ee i gi r
0P ot
/
1 rT rnt o
i E
ht n N
u ti a r) wR t uw l r snnern u
eh o io eiivEi u
MSD a
R ami a
S Fe ratll c
yT x a a p t ngr Ernx T
nanor t oE I
N 2
enit oesi(
U n
mel at sit o
- pt el annar s
ninuureire a
H C
ouif gecmeh e
s q a e e pi d pt R
aEMRROLAOO e-2 RABCDE FGH no) i s t r au A '
9 ro
/
uH N
3 D(
2 de l
e du p
ed y
ce T - S 5
rh oc FS
- 1 9
e 0
2 1
FS t
2 2
a 0
0 D
2 2
9 9'
1 2
+
0 0
N- - 9 9
o 2
2 a
1:iii!'1i!l}i iji i4 fI' i:1I 1.
.It
{[I,]
!tl,!33 ll;;
jj i i
- i!:
4.
l l
1 l
- 1) ATE:
February, 1992
{
l l
RE}'UELING INFORMATION
{
1.
Name of facility:
Arkansas Nucicar Ono - tinit t l
2.
Scheduled date for next refueling shutdown.
Februnty_22,_1992 3.
Scheduled dato for restart following refueling. 6prijJLl992
)
=
4.
Will refueling or resumpt.fon of operation thoroaf ter requito a technical specification chango or other 11conne amendment?
If answor i
is-yes, what, in general, will thare bo? If answer is no, has the reload fuel design and core configuration bocn reviewed by your plant Safety Review Committen to dotormine whether any unroviewed safety l
quest ions are associated with the core roload (Ref.10 CPR Section l
I 50.$9)?
Yes. TechnicalSpeci ficat ion - changenor _01, 88-16 incorporating _uso_of a, Corn Operating 1.im_its Repott_UA' kRLwas_submitt ed t o_the NRC.
i Scheduled dato(s) for submitting proposed licenNing action and supporting information.
The COLR Technical Specification-chango_ teflunst
= was__ submitted to the NRC November 7, 1991.
r 6.
Important licensing considerations associated with refueling, e.g.,
new
-or different fuel design or supplier, unroviewed design or performanco analysis methods, significant changes in fuel design, new operating proceduros.
Nono.
7.
The number of fuel assemblics (a) in the coro and (b) in the spent fuel storago pool, a)' 177.
.b) 565 8.
Tho-present Ilconsed spent fuel pool-storage capacity and the size of.
any increaso in licensed storago capacity that has been requested or is plannod, in number of fuel assomblics.
present 968 increase sizo by O_
9.
Tho projected'date of the last refueling that can bo discharged to the spent fuel = pool assuming the present licensed capacity.
DATE1 1995 (boss of fu11 core offload capability) l
.