ML20207F133
| ML20207F133 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/31/1986 |
| From: | Richardson M ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML20207E046 | List: |
| References | |
| NUDOCS 8607220480 | |
| Download: ML20207F133 (7) | |
Text
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NRC F3NTP_Y 03ERATING REPCRT DOCKET NO.
52-gg8 UNIT NAME PyNg$-1 DATE Q3 420Zgg COMPLETED BY M p Righgrdsgn t u TELEPHONE 608-232-5890 Egit 6523 QE559IING SIBIWS 1.
Unit Name: Palo Mende Nuclegt @enerating Statigan Unit 1 2.
Reporting Period: January igg @
3.
Licensed Thermal Power (MWt): 3000 4.
Nameplate Rating (Gross MWe): 1603 5.
Design Electrical Rating (Net MWe): 1@I9 6.
Maximum Dependable Caoacity (Gross MWe): Ig be ggtgreingd 7.
Maximum Dependable Caoacity (Net MWe):
Ig be geigrelogd O.
If Changes Occur In Capacity Ratings (It erns Nummer 3 Througn 7) Since Last Report, Give Reasons: _
___-___-________ Recalculated Accorcine to cefinit ion ____
9.
Power Lovel To Which Rest ri ct oc.
If Any (Net MWe): _NQNE____
- 10. Reasons For Restrictions, If Any:
Tnis Mcmth Yr.-to-Date Cumulative 41.
Hours In Reoorting Period
___744____
____744___
__9504____
- 12. Nur.toer Cf Hours Reactor Was
- - ___3 3 5. 5__
_ __ _2 5 5. 5_ -
_,_2812. 5_ -
Cr i t i c a l-"
~~
~ ~ ~ ~ ~ " ~ ~ ~
e
- 13. Reactor Reserve Shutdown Hours C
0
____0____
- 14. Hours Generator On-Line 353.S 363.8__
__2383.6_
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Ger.erated 1,265,571_
1.265.571_
5.659.763_
(MWH)
- 17. Gross Electrical Energy Generated
__428.000_
__428.020_
1,764.70.3,
(MWH)
- 18. Net Electrical Enetgy Genetatec
__383,457
__383,457 _
1,511,10.7 - _
~~
(MWH)
- 19. Unit Service Factor
___N/A____
___N/A____
__N/A____
- 20. Unit Availability Factor
___N/A____
___N/A____
__N/A____
- 21. Unit Cacacity Factor (Usino MDC
___N/A____
___N/A,____
__N/A____
Net)
- 22. Unit Cacacity Factor (Using DER
___N/A____
___N/A____
__N/A____
Net)
- 23. Unit Forced Outage Rate
___N/A____
___N/A____
__N/A____
- 24. Shuccowns Scheduled Over Next 6 Months (Tyoe. Date, anc Duration of Eacn) : __Eyrveil,1_enge Igst Quigge - 34@gt 42 dayE______
- 25. If Shutdown At End Of Recort Period, Estimated Date of Startup ______
- 26. Units In Test Status (Prior To Commercial Coeration):
1 Forecast Achieved INITIAL CRITICCLITY
___5/85,____
___5/25/85___
INITIAL ELECTRICITY
___6/85_____
___6/10/85___
COMMERCIAL OPEHATICN
__11/85_____
_____N/A_____
8607220480 860507 DR ADOCK 05000528 PDR
-,z h, *
. e.
- REFUEL IB.G IN ORMATION
'. (
DOCXET NO._50;fa3__________
UNIT _______PVNGS1_____
DATE_______0240Afg6_____
CCMPLETED BY_M p Ric3andson u u
_ TELEPHONE 602-932-53C3
__ Ente 6523_______
1.
Scheduled date fer next refueling shutdown.
03/01/37 2
2.
Schedulec date for restart following refuel:nc.
04/19/87 3.
Wtil refueling or resumotion of oceration tneteafter rneutro a Tecnnical Specificaticn enange or other license amenenent ?
Not Yet Determinec i
What will.these be?
Not Yet Determinec 4.
Scheduled date for submitting orococed licensing action ano supcorting v
in er ca en.
4 Not Yet Determinec 5.
Imoortant Licensina consicerationc associatec with re f ueli r.g,
- e. g.
new or different fuel desi n or sucolier, unreviewed j
design or performance analysis methods, significant c1anges in j
fuel cesign, new operatir.g orococures.
4 i
Not Yet Det ortu r.oc 6.
The number of fue' assercolies.
i a) In the core._@h1_____ _____
i b) In the scent fuel storego cool._____0_______
7.
Licensed s oer.t fuel storage cacacity.____13@2______
Intended change in ncont fuel storage cacacity.__Nogg______
t 8.
ProJocted date of last refueling that can be diccharged to scent fuel storage cool assuming present caoncity.
2002 (w/ annual re loc.cs.ar.c f ull core discharge cacability).
4 1
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AVERA3E DAILY UNIT.PCWER LEVEL DOCKET NO.
_5 0_ _- 5 2.3 _ _ _ _ _ _ _
UN I T ___ _ _ _ _P UN _G S_ _1_-_ __--_
J i
D A T E _ _ _ _ _ 0_ 2 / 0 8 _/ _0 _6 _ _ _ _ _ - _ _
i I
COMPLETED B Y _ M _. D _. _R _i c _h _a r_ _d s _o _n
'r T E L E P H O N E _ 6_ _0 2 _- 9 _3 _2 _ _5 _3 _2 _0 Ext
_6 5 _9 _3 _ _ _ _ _
4 M_O_N_TH_:
January 1986 j.
DAY AVERA3E DAILY POWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (MWe-Neb)
(MWe-Net) i 1
-===1*253_-
--=__
17 __________(72) ____________
2
_-______1,256-
- -=-
IS _________-(72) 3 1,180____-
==
19 __________(66) l 4
_ _ __1, 2 6 3 _ _ _ _ _ _=_____
23 _________ 855_____________
f 5
________1,266__,,,,_________
21 _________1.122____________
6
____-___1,161 S:*
7
__-_____1,147___-_-_______
23 ____-____1,199____________
8
________1,236_____________
24 ___________564____________
i 9
--________65S__.__.
25 -___-_---__ 7a)
(
4 j
10 ___--_____(75) 26 _________--(74) 11
_ _ _ _ - (77) 27 ___________(61)
,t 12 __-_ = =_ - -- ( 7 9 )
28 ___________(55) i 13 -____-____ 76) 29 ___________(63)
(
4 14 ________--(72) 30 ___________581____________
15 __________(72) 31 _ _ _ _ _ _ _ _ _ 1, 0 7 a _ _ _. _ _ _. _ _ _ _ _
i i
16 __________(72) t l
f r
t d
e g-+----
_m-v-ny....v..
y----
,em...
-.. -,,, -w
--em.
....y-
- +---.- +---.----
,w--,.mwr m e-_v.,- - - -. - - ~ < *.
st 1-
/.
,s ELJ5t9BY -CE c2E3s:Ite g3Eg3Igec3 Egg Igg EQ3Is DOCKET NO.___;9-52G___________
UNIT _________Py205-1__________
DATE_________92LC92SS__________
COMPLETED BY_5sgu Bigbargggn__
TELEPHONE __ggg-233-5390_______
__Entz $523__________
01/01 0000 - Reactor-ocwer-at 100%, raa in turbine 1307 MWe.
01/03 1125 - Corci.ioncac ocwer-decrease for surve:11ar.ce t e c : : r.c.
01/03 1132 - Reacter-cower at S5%.
01/03 1202 - Reacter ocwer at 71%
f
.01/03 1219 - Cora.1onced power-i r.crea s e to 95%
l 01/03 1220 - Reactor ocwer.at 94.9%. main turo:ne 1245 W.se.
01/06 1026 - Transferred house leacs fror.: aux 11:ary tt ors for.:ern to staa
.;o trarnf ort.:ers in cre3 ara;;:n r ot-
. : s s.- ?
~
f ee c w a t er-curto t est.
01/06 1228 - Reacter-cower-a: 50% ccwer.
I 01/hk 1314 - Transferred house 1cacs frora start uo trar.sfor'ders i
to auxiliary trar.sfortaers in recovery frer.1 loss of i
f eedwat er-ourao test.
i 01/06 1455 - Reacter cower at ~100%.
i 01/07 1523 - Perfov::ec renence cower cut:Acx tes fer lead tGject.
T*103GC r.1a l n generatCr.
l
-01/07 1546 - Placed t.:a t n generator on line.
01/07 1656 - Reactor-c ower-at 47% due to can strioter-raa l f unc t i c n.
i l
j 01/07 185'3 - Reactor oower-at 96%.
01/09 1325 - Initiatec Load Ru!act Test. raa t r. turnir.e ttto via racs t o r-tri s.
ba ct ct-tvin on.o DNDR caused bv 9 e a c t e.t-Coolarit P o r.to c o r.s t d o w n en 13.0 XV load shea due to t
i fai u f*O Of f.*i s t I r a n s.' Ol'.
Cr er ma t re s t atira safotv 1
l valvo itftoc.
i w
CNRCPorthlyCoera01ng Re o.r Page 2 01/09 1327 - MSIS on low Stoc*a Genet-etor crassure.
01/09 1329 - Stat-ted ocenir.g Steara Generator atmosoheric._ durac valves.
01/09 1920 - Plant in roce 3.
01/14 0205 - Corcolet ea clant cooldewn/cooressuri:stion to accroximately 400 decrees F/523 osia to allcw recairs to the isolation valves to the cresnut iner coray vs.ves.
01/15 3120 - Plant in oce 2.
v 01/19 '0834 - Reac:ct- :s
- -
- ::ta1.
01/19 1042 - Enterec Xoce 1.
01/19 2247 - Main Turcir.a on l i r.e.
01/19 2250 - Cortaer.cac ec.1 1r h ::..er to 19 P..
t 01/21 0700 - Plar: I r. Voc-1 x ' cewer-s: 9 0%.
asm
'.n a i r.e a:
1157
.%.e.
01/22 1930 - Rx cower at 93. f M.
raain tur= ire at 1259 %e.
01/24 1130 Petforcoc Loss of Load without Reactor-Power
- Cut =acs. S yst e.v.
% triocea on Hi orossur t:ar oressure.
All four RCPs tric=ec for Natural Circu;a ~ :r: 0 5o cc.an Test.
D ur i r.*:
tn : tos a
seconcacy sefa y lif;es.
01/24 2225 - EnterOc roce 4 01/25 0115 - A steara voic was :r;;snt:enally drawn in the Rx vessel head c ur : r.q RCS deoressurination.
The stearn void was col.noisec with use of tne t eactot* coolant cas ven svsten ventsno fr ora the vessel head to the RD7.
01/29 0250 - Entered Focs 3.
01/29 1508 - Rotered Voco 2.
01/00 i$16 - :iaar t or-cr1tical.
01/09 1950 - Entered voce 1.
s
r-
.s, s
NRC Monthly Coera: 1 r.g 5ccer:
Page 3 01/29 2213 - Main Turnine on line a: 40 Mbe.
01/20 0700 - Moce 1,
Reactor' oower' at 40%, Main generator at 438 MWe, 01/30 1520 - Reactor oower at 69%.
01/31 2425 - Stabili:ec Reactor power at 99%.
01/31 0822 - Started the 120 hour0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> continuous run for the Arizona Corporation Commission.
01/31 1523 - Started berating to '63% cower cue to Ht virre.tten on B FWPT.
01/31 1555 - Stos ec =ower cecrease at '70%.
01/31 1928 - Moce 1,
Reactor ocwer at 72%. P'at n Generator at 911
.%.?.
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'untT suuTocuns suo. in accu;tions vaCutt No.
sn c;n
,,5 IJ41T HAHC PWNM-I i
3 DATC h b.
10 19do
- COMrLETED Dy ii. e Richar@ nrg TEL[Pil0NC 9 O-5 WO t' f e (1543 Hethod or
- Shutting Down System Componont Cause & Corrective 1
Duration 2
- 3 f.ER f4 5
Action to No.
Dsto Type
( flou rs ]
Reason Rosctor lio.
Codo Codo Prevent Recurrence 29 01/03/66 S 0
B 5
Surveillance' testing.
30 01/06/86 S 0
B 5
- Loss o.f feedwater p6mp test.
31 01/07/86 S
.2 S
N/A Reactor power cutback test.
32 01/07/86 F 0
A N/A CB DCS Cas stripper malfunction.
33 01/09/86 S 249.3 B
3' l-86-0006 EA 78 Load' Reject Test.'
34 01/24/86 S 130.7 B
3 1-86-015 Performed Loss of Load without Reactor Power Cutback System.
35 01/31/86 F 0
A 5
S.)
P Decrease power due to 111 vibration on B Ft.'PT. Fixed pump.
I 1
2 3
4 T-Fo rce d Reason:
It-thod:
[whibit F - Instructions 5- $ c t.c::a led A-Cauipment failuro (Explain)
I-tt.s nu a l for renparatinn or Datn it-tta inten:ince or Ic.tt 2-itanua l Scrart.
[ntry Sticcts for Licensoo C-frerueling J-Autot.itic Scram.
Event neport (LCR) File D-Regulatory Des t riction ta-Cont ino.i t lan f rom-(t40ttCC 0161) t-Onora tor tra ining & I.f conse Expreins t ion rrnvlous Month T-Admini s t ra t ivo 3-fleduction of 207.
5 con-ar.,sanse r.cn e t rv t. t a t er rea.*ar te eh.
r *.tst* u.e.-- e...-o