ML20203E028
| ML20203E028 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/31/1986 |
| From: | Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-35132-EEVB, NUDOCS 8604240064 | |
| Download: ML20203E028 (8) | |
Text
&
1 NRC MONTHLY OPE 9ATING REPORT DOCKET NO.
50:52@
sl t
UNIT NAME PVN@@-1 DATE 0 2 / 0 _8 _/ _8 6
_--_ Richardsgg L.
COMPLETED BY M p u u TELEPHONE
@02-232-5300 Ent 6523 u
QEEBBIING SIBIUS 1.
Unit Name: Palg Vgtdg Nuglgar Ggegrating Station Unit 1 t
2.
Reporting Period:Jaguary 19@6 3.
Licensed Thermal Power (MWt): 3@00 4.
Nameplate Rating (Gross MWe): 1403 5.
Design Electrical Rating (Net MWe): 1220 6.
Maximum Dependable Capacity (Gross MWe) :Tg bg dgtgrr ingd a
7.
Maximum Dependable Capacity (Net MWe):
Tg bg dgtgrmingd O.
If Changes Occur In Capacity Ratings (Items Number 3 1
Through 7) Since Last Report, Give Reasons: _____
________________ Recalculated According to definition _
1 9.
Power Level To Which Restricted, If Any (Net MWe):_NgNE l
- 10. Reasons For Restrictions, If Any:
i 1
- - - - - - - - - - _ =
=-
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period
___744____
____744___
__9504____
- 12. Number Of Hours Reactor Was Critical
___385.5__
___2812.5_
__2812.5_
- 13. Reactor Reserve Shutdown Hours
_____0____
_____0____
____0____
14 Hours Generator On-Line
___363.8__
__2383.6__
__2383.6_
)
- 15. Unit Reserve Shutdown Hours
_____0____
_____0____
____0_
- 16. Gross Thermal Energy Generated 1,265,571_
5,659,760_
5,659,760_
(MWH)
- 17. Gross Electrical Energy Generated
__428,000_
1,764.700_
1,764,700_
(MWH)
- 10. Net Electrical Energy Generated
__413,700_
1,541,250_
1,541,350_
(MWH)
- 19. Unit Service Factor
___N/A____
___N/A____
__N/A____
- 23. Unit Availability Factor
___N/A____
___N/A____
__N/A____
- 21. Unit Capacity Factor (Using MDC
___N/A____
___N/A____
[_N/A_.,__
Net)
- 22. Unit Capacity 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 (Tvoe, Date, and Duration of Each): __Sgtvgillaneg Tgst Qgtagg - 3/@@u 39 days ______
l
- 25. I f Shutdown At End Of Reoort Period, Estimated Date of Startup:______
- 26. Units In Test Status (Priot-To Commercial Ooeration):
Forecast Achieved INITIAL CRITICALITY
___5/85_____
___5/25/85___
INITIAL ELECTRICITY
___6/85_____
___6/10/85___
COMMERCIAL OPERATION
__11/85_____
_____N/A_____
h O
R
}\\
t s,
REFUELING INFORMATION DOCKET NO._QO QRQ_ _
UNIT _______pyNGE 1_____
DATE_______0g20@fg@_____
COMPLETED BY_M p Richardson u u TELEPHONE __60@23R:5300____
__Ent._ 6523_______
1.
Scheduled date for next refueling shutdown.
03/01/87 2.
Scheduled date for restart following refueling.
04/19/87 3.
Will refueling or resumotion of operation thereafter recuire a Technical Soecification change or other license amendment?
Not Yet Determined What will these be?
Not Yet Determined 4.
Scheduled date for submitting proposed licensing action and supporting information.
Not Yet Determined
- 5. Important Licensing considerations associated with refueling,
- e. g.
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The number of fuel assemblies.
a) In the core._241___________
b) In the scent fuel storage pool.
0
- 7. Licensed soent fuel storage capacity.____1329______
Intended change in spent fuel storage caoacity.__None______
8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present caoacity.
2002 (w/ annual reloads and full core discharge capability).
?-
AVERAGE DRILY UNIT POWER LEVEL DOCKET NO.
50-5gg_______
UNIT ______PVNGQ-1________
DATE______0gfegfg6___
COMPLETED BY_M p._ Ricbardson u
T E L E P H O N E _ 6_ _0 _2 _- 9 _3 _2 _ _5 _3 _0 0 3
_Estu 6523_____
MQNTU:
January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
____1,253_
17 (72) 2
___1,256__
18 _
(72) 3 1,180___ _ _ _ _ _
19
_ _ _ 66) __
(
4
_1,263_
20 _ _
___855__
5
__1,266______
21 1,122_
6 1,161______
22
_ __ _ _ 1, 2 2 1 _ __
7
___1,147____
23
_ _1, 19 9_
t O
1,236________
24 _
564_
/
9
__658_____
25 (74) 10
__ 75) __
26 ___________(74) _
(
11 (77) _ _ _
27
________ 61) =_
_ _ _ __ =
(
12 _
=_
___ (79) 28 (55) n 13
__ (76) 29 ___________(63) _
14 ______
(72) 30_______
__581 s
15 __________(72) 31 _________1,078____________
16 __________(72)
O
- &a"*
BuddOBY 9E OPERSIING gfpg31ENCE EQR IME MONIH
.);
DOCKET NO.
50-5gg__
'N '
~
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UNIT
- - - _ = _ _ _ pV_NGS-1
- Lii, DATE_.
?.ss.
02/@Bf BS___ _ _
'<@S y COMPLETED BY_McP Richardson __
t e.<
1,.]{.,;
TELEPHONE __602:23grg300_______
__Egt 6523__________
s c
C1/01 0000 - Reactor power at 100%, main turbine 1307 MWe.
C1/03 1126 - Commenced power decrease for surveillance testing.
01/03 1132 - Reactor power at 85%.
G1/03 1202 - Reactor power at 71%
01/03 1219 - Commenced power increase to 95%
C1/03 1320 - Reactor power at 94.9%, main turbine 1245 MWe.
01/06 1026 - Transferred house loads from auxiliary transformers to startup transformers in preparation for loss of feedwater pump test.
01/06 1238 - Reactor power at 60% power.
01/06 1314 - Transferred house loads from startup transformers to auxiliary transformers in recovery from loss of feedwater pump test.
01/06 1455 - Reactor power at *100%.
01/07 1538 - performed reactor power cutback test for load
/,
reject.
Tripped main generator.
01/07 1546 - placed main generator on line.
01/G7 1656 - Reactor power at 47% due to gas strioper malfunction.
01/97 1850 - Reactor power at 96%.
01/09 1325 - Initiated Load Reject Test, main turbine trip via master trio. Reactor trio on lo DNBR caused by Reactor Coolant pumo coastdown on 13.8 KV load shed due to failure of fast transfer.
One main steam safety valve l i f t ed.
~
4,.
' NRC Monthly Operating Report Prge 2
'l
,Rd.-
,01/09 1327 - MSIS on low Steam Generator pressure.
.01/09 1329 - Started opening Steam Generator atmospheric dump-valves.
.l.01/09 1930 - Plant in Mode 3.
01/14 0205 - Comoleted plant cooldown/depressurization to approximately 400 degrees F/500 psia to allow repairs to the isolation valves to the pressurizer spray valves.
01/19 0130 - Plant in Mode 2.
01/19 0804 - Reactor is critical, 01/19 1042 - Entered Mode 1.
01/19 2247 - Main Turbine on line.
01/19 2250 - Commenced raising Rx power to 19%.
01/21 0700 - Plant in Mode 1, Rx power at 90%, main turbine at 1167 MWe.
01/22 1930
,Rx power at 9 9. 5 /., main turbine at 1289 MWe.
01/24 1130 - Performed Loss of Load without Reactor Power Cutback System, Rx trioped on Hi cressurizer pressure.
All four RCPs tripped for Natural Circulation Cooldown Test.
During this test a secondary safety lifted.
01/24 2225 Entered Mode 4.
01/25 0115 - A steam void was inter.tionally drawn in the Rx vessel head during RCS deoressurination.
The steam void was collaosed with use of the reactor coolant gas vent system venting from the vessel head to the RDT.
01/29 0050 - Entered Mode 3.
01/29 1508 - Entered' Mode 2.
01/29 1526 - Reactor critical.
01/29 1950 - Entered Mode 1.
n m
NRC Monthly Operating Report page 3 01/29 ~ 2213 - Main Turbine on line at 40 MWe.
.;iO1/30 0700 - Mode 1,
Reactor power at 40%, Main generator at 438 MWe.
- r-61/30 1520 - Reactor power at 69%.
01/31 0425 - Stabilized Reactor power at 99%.
01/31 0822 - Started the 180 hour0.00208 days <br />0.05 hours <br />2.97619e-4 weeks <br />6.849e-5 months <br /> continuous run for the Arizona Corporation Commission.
01/31 1520 - Started borating to '60% power due to Hi Vibration on B FWPT.
01/31 1555 - Stopped power decrease at '70%.
01/31 1928 - Mode 1,
Reactor power at 72%, Main Generator at 911 MWe.
1 6=
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s
, #' ' UNIT SHUTDOWNS AND POWER REDUCTIONS..'
- DOCKET NO.
Mn-99A UNIT NAHC PVNChi
'g 8
l j
DATC b b.
- 10. 1986 COMPLETED SY Pl. t'. Richa rrf nnn
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TELEPil0NE - Q U-5 31)O I:'v e 6 4 0 't Hethod of Shutting
. Cause & Corrective Down System Component 1
Dura t ion 2
3 f.ER 4
5 Action to No.
Date Type (frours)
Reason Rosctor No.
Code Code '
Prevent Recurrence 29 01/03/86 S 0
B 5
Survei11anch testing, e
30 01/06/86 S 0
B 5
Loss o.f feedwater p6mp test.
~
31 01/07/86 S
,0 S
N/A j
Reactor power ' cutback test.
32 01/07/86 F 0
A N/A CB DGS Gas stripper malfunction.
33 01/09/86 S 234.5 B
3' 1-86-006 EA 78 Load
- Reject T'est.'
34 01/24/86 S 124 B
3 1-86-015 Performed Loss of Load without Reactor Power Cutback System.
)
35 01/31/86 F 0
A 5
SJ P
Decrease power due to Hi vibration on B FWPT. Fixed pump.
4 1
i 1
I 1
s
,i.
1 2
3 4
i F-Fo rced Reason:
Method:
Exhibit F - Instructions S-Scheduled A-Eculpment Fellpro (Explain) l-Hanual for Prnparation of Data D-Haintenaneo or Test 2-Hanual Scram.
Entry Slincts for Licensee C-Acructing J-Aistoma tic Scram.
Event Report D-Regulatory Restriction ti-enntinuation from-(HUREC C161) (LER) FI,le E-Dnnrator Training h License Examination Provfous Month F-Admini s t ra t ive 5-Reduction or 20%
5 c-Dporational Error (Explain) or creator in the Exhibit H-Seme Source H-Other (Explain) rast 2ta llours n
o 7
Arizona Nuclear Power Project P o. Box 52034
- PHOENIX, ARIZONA 85072-2034 February 14, 1986 ANPP-35132-EEVB/LJM/98.05 Mr. Ronald M. Scroggins, Director Office of Resource Mar.agement U.S. Nuclear Regulatory Comission Bashington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 (License NPF-41)
January Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the January,1986, Monthly Operating Report prepared and sub-mitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 1 Operating License. By copy of this letter, we are also forwarding a copy of the Monthly Operating Report to the Regional Administrator of the Region V office.
If you have any questions, please contact me.
Very truly yours,
~
$5hh t
t E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/LJM/rw Attachments cc: J. B. Martin (all w/a)
R. P. Zimmerman E. A. Licitra A. C. Gehr 7 ((
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