ML20137X911
| ML20137X911 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/31/1986 |
| From: | Richardson M ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML20137X865 | List: |
| References | |
| NUDOCS 8603120036 | |
| Download: ML20137X911 (7) | |
Text
.
t NRC MONTHLY OPERATING REPORT DOCKET NO.
50-528 UNIT NAME PVNGS 1 DATE 02200286 COMPLETED BY M. P._ R ghardggn i
TELEPHONE 603-93Rr530@
Ent 6s93 t
OEEE911NG SIBIUS 1.
Unit Name: Palo Verde Nucleat Genergting Stgt iggt Unit 1 2.
Reporting Period: January 1286 3.
Licensed Thermal Power (MWt): 3800 4.
Nameplate Rating (Gross MWe): 1403 3.
Design Electrical Rating (Net MWe): 122@
6.
Max t raum Dependable Capacity (Gross MWe): Tg be ggtermined 7.
Maxitaum Dependable Capacity (Net MWo):
To be determined 8.
If Changes Occur In Capacity Ratings (I tems Nuraber 3 Throuch 7) Since Last Report, Give Reasons: __________________
________________ Recalculated According to definition _________
9.
Power Level To Which Restricted. If Any (Net MWe)
_NONE____
10.
Reasons For Restrictions, If Any This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period
___744____
____744___
__9504____
- 12. Number Of Hours Reactor Was Critical
___385.5__
____385.5_
._ 2812.5
- 13. Reactor Reserve Shutdown Hours
_____0____
_____0____
____0____
14 Hours Generator On-Line
___363.8__
_.__363.8__
__2383.6_
- 15. Unit Reserve Shutdown Hours
_____0____
_____0____
____0____
- 16. Gross Thermal Energy Generated 1,065,571_
1,065,571_
5,659,760_
(MWH)
- 17. Gross Electrical Energy Generated
___428,000,
__428,000_
1,764,700_
(MWH)
- 18. Net Electrical Energy Generated
__413,700_
__413,700_
1,541,350_
(MWH)
- 19. Unit Service Factor
___N/A____
___N/A____
__N/A____
- 20. Unit Availability Factor
___N/A____
___N/A____
__N/A____
- 21. Unit Capacity Facter (:Using MDC
___N/A____
_ _ _ N / A,_ _ __
N/A___,
Not)
- 22. Unit Ca paci t y Factor (Using DER
___N/A____
___N/A____
__N/A,_
Net)
- 23. Unit Forced Outage Rate
___N/A____
___N/A____
,_N/A____
24.
Shutdowns Scheduled Over Next 6 Months (Tyoe, Date, and Duration of Each): __Syrveillance [egt Ogtage : J/85t 42 d3yn,_____
250 If Sh ut down At End Of Report Period, Estimated Date of Startuos______
- 26. Units In Test Status (Prior To Commeretal Operation):
Forecast Achieved INITIAL CRITICALITY
_.,5/85_____
___5/25/05___
INITIAL ELECTRICITY
___6/85__..__
___6/10/85.,__
COMMERCIAL OPERATION
__11/85_____
_ _,_ _ _ N / A _ _._ _
8603120036 860304 PDR ADOCK 05000528 R
r-e s
REFb2 LING INFO.9x AT I ON DOCKET NO._QO;533__________
UNIT _______PVNOS;1_____
DATE_______0gf004@@_____
COMPLETED BY_M.P Ric3ardsgn
_ n TELEPHONE __60s-23s-5300____
__Entu 6523_______
1.
Scheduled date fer next refueling shutdown.
03/01/S7 2.
Scheduled date for rectart following r e.f u e l i n g.
04/13/S7 3.
Will refueling or resumotion of coeration tnereafter recuire a Tecnnical Soecifica: 1cn change or other license amer.cnent?
Not Yet Determinec What will these be?
Not Yet Determinec 4
Scheduled date for s ubtr i t t i ng orococed licensing action and succorting infcrYation.
Not Yet Determinec 5.
Important Licensing consicerations associated with refuelir.0,
- e. g.
new or different fuel design or suco11er, unreviewed design or performance analysic methods, significant c1ar.g e s in fuel cesign, new oceratir.g crocacures.
Not Yet Determinec 6.
The number of fuel assenblies.
a) In the core._@41 b) In the scent fue' storage cool._____0_______
7.
Licensed soor.t fuel storage capacity.____1322______
Intended change in scent fuel ctorace cacacity.__Ngge______
8.
Projected date of last refueling that can be discharged to scent fuel storage cool assuming present caoacity.
2002 (w/ annual reloces anc full core discharge capability).
g t
s
. \\.,
AVERA3E DAILY UNIT POWER LEVEL DCCKET NO.
_5 0_ _- 5_ 2 8_ _ _ _ _ _ _
U N I T _ _ _ _ _ _ _P _V _N G_ S _ _1 _ _ _ _ _ _ _ _
D A TE_ _ ____0_2 / 08_/ 0 6_______ _
COMPLETED B Y _ M _. _D.-
_R _i c h _a r_ d s o _n T E L E P H O N E _ G_ O
- _9 _3 _2 _ _5 3 _? 0
_w_
_E_ _x _t _. 6 5_ _9 3 _ _ _ _ _
M_ O_ N _T H_ :
January 1986 DAY AVERA3E DAILY POWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (MWe-Nat)
(MWe-Net) 1
________1,253_____________
17 __________(72) 2
________1,256_____________
18 __________(72) 3
________1,180_____________
19 __________(66) 4
________1,263_____________
20 __________055_____________
5
________1,266__-__-_______
21
_________1,122____________
6
________1,161_____________
22 _________1,221____________
7
________1,147_____________
23 _________1,199____________
8
________1,236_____________
24 ___________564____________
9
__________658 25 _______--_-(74) ----___-__-
10 ____-_____(75) _________
26 ___-_______(74) 11 __________ 77) 27 _______-___(61)
(
12 ___--_____(79) 28 (55) 13 _____-__--(76) 29 ___________(63) _____._____
14 _-___-----(72) 30 ___________5G1 -___________
15 __-._____.(72) 31 _ _ _ _ _ - _ _ _ 1, 0 7 8. _ - _ _ _ - - - - - --
16 __________(72)
ELJMt9Bv GE O2E39Ilhe E3EESIENCE EQB IEg [Q$IS DOCKET NO.___50-52O___________
UNIT _________oVNQS-1__________
DATE_________02fg3405__________
COMPLETED BY_M.P Richardgog__
t TELEPHONE __692-232-5399_______
__Ents 6523__________
01/01 0000 - Reactor ocwer at 100%, main turbine 1307 MWe.
01/03 1126 - Commenced power decrease for surveillance t est i r.p.
01/03 1132 - Reacter power at 85%.
01/03 1202 - Reactor ocwer at 71%
01/03 1219 - Commenced power increase to 95%
01/03 1320 - Reactor ocwer at 94.9%, main turbine 1245 MWe.
01/06 1026 - Transferred house loacs from auxiliary trarsformers to startuo trarsformers in crocaration for icss cf feecwater oumo test.
01/06 1238 - Reactor power at 60% cower.
01/06 1314 - Transferred house leacs from startuo trar.sformers to auxiliary trar.sformers in recovery from locs of feedwater oumo test.
01/06 1455 - Reactor power at ** 10 0%.
01/07 1533 - Performed reactor oower cutback test for load reject.
Tri s aec raa in generator.
01/07 1546 - Placed main generator on line.
01/07 1656 - Reactor cower at 47% due to can strioter malfur.cticn.
01/07 1850 - Reactor ocwer at 9 6 /..
01/09 1325 - Initiated Load Reject Test. main turoine trio via master tr:3. R? actor trio en lo DNDR caused by %cactor Coolant Pumo coastdown en 13.8 KV load shed due to failure of fast transfer.
O r.e main steam safetv valve liftec.
r NRC Porthly Coera: Ing Reo:r:
Page 2 01/09 1327 - MSIS on low Steam Generator cressure.
01/09 1229 - Started ocenirg Steam Generator atmosoherie duma valves.
01/09 1920 - Plant in roce 3.
01/14 0205 - Comoletac clant coolcewn/cearecsurt:ation to accroximately 4C0 ce:rees F/523 osia to allow recairs to the -isolation valves to the pressuri er scray valves.
01/19 3120 -
P. ant in Voce 2.
01/19 0834 - Reactor is cr tical.
01/19 1C42 - Enterec roco 1.
01/19 2247 - rain Turoine on l i r.e.
01/19 225? - Cormlencad ra:stre ;x :oser to 19%.
01/21 0700 - Plar: I r. xece 1,
Rx ocwor at 90%. main turaire a 1 1 6 7 M'.,e.
01/22 1930 - Rx cower at 99.5%, rnain t uroine at 1289 MWe.
01/24 1130 - Performed Locs of Load without Reactor Power CutcacW. System. Rx tricoed on H1 oressuri er oressure.
All four RCPs tricoec for Natural Circula:lon Coo'.down Test.
During this test a seconcary safety lifted.
01/24 2225 - Entercc roce 4 01/25 0115 - A steam vote was intentionally drawn an the Rx vessel heac c ur i r.n RCS deoressurtratior..
The st nara void was co;.a3Gec with use of the reactor coolant gas ven: svst a a ventino from the vessel head to the RDT.
.01/29 0250 - Entered roce 3.
01/29 1508 - Entered Moce 2.
01/29 1526 - Reactor critical.
01/29 1953 - Entered Poce 1.
e s
NRC Monthly Goera: Ing Seccet Page 3 01/29 2213 - Main Turbine on line a: 40 MWe.
01/30 0700 - Moce 1,
Reactor oower at 40%, Main generator at 438 MWo.
G1/30 1520 - Reactor power at 69%.
01/31 0425 - Stabili:ed 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 Art:ona Corooration Commission.
01/31 1520 - Started borating to '60% cower due to Hi Vieration on D FWPT.
01/31 1555 - Stoo=ec power cecrease at ' 7 0Y..
01/31 1928 - Foce 1,
Reactor oewer at 7 2%.. vain Generator at 911 MWo.
1 e
. *. - ' UNIT SHUTDOWNS AN3 POWCR ACDUCTIONS DOCKET No.
Mn s9A UNIT CAHC PVfffM-I
- 1 g
DATE Ieb. III. 1986 COMPLETED BY H.F R i c ha rrimrt
- " l TELEPliONC 4 U-51f tfl
- *.?
PvP A%Q3 Hethcd or Shutting
(
Cown Systent Cornponent cause ar Corrective 1
Dura t ion 2
' ~ 3 1 ER 4
5 Action to No.
Date Type (stours) ftesson Rosetor
_ rio.
Code Code '
Prevent flecurrence
/
29 01/03/86 S 0
_B 5
Surveillance testing.
30 01/06/86 S 0
B 5
Loss of feedwater pdmp test.
31 01/.07/86 S
.2 S
N/A Reactor power cutback test.
32 01/G7/86 F 0
A N/A CB DGS Cas stripper malfunction.
- d
)
33 01/09/S6 S 249.3 B
3' l-86-0006 EA 78 Load}ejectTest.' '
~
34 01/24/86 S 130.7 8
3 1-86-015 Performed Loss of Load without Reactor Power Cutback System.
35 01/31/86 F 0
A 5
SJ P
Dccrease power due to 111
^ '
vibration on 3 FWPT. Fixed pump.
1 1
f I
l r
's I
2 3
ta r-rorced
- caton
Hethod:
[=hlblt T - Instructions S-Schoculed A-to u i pa'en t fallpro (Cwplain) l-tonual for Prnparation or Da ta D-t'a intenance or T est C-fterveling 2-tunnal Scra9 (ntry slicets for Licensee 3-Aistees t ic Scraw.
(vent Report (LCR). file D-Degtst a tory fles t rf etion ia-continuation from (hun [C 0161)
E-opara tor E rm inin't h License twanine tlen ernwfous Ponth i-Administrative 5-Cedvetion or 2c c cporational Error (Explain) or creator in the ~ 5 Exhibit H-Seme Source it*Cther (Explain) o rast 24 Stours
- Cther (EmpialnD_
,.