ML20135B446
| ML20135B446 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/30/1985 |
| From: | Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-33016-EEVB, NUDOCS 8509110059 | |
| Download: ML20135B446 (9) | |
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NRC MONTHLY OPERATING REPORT DOCKET NO.50:528 UNIT NAMEPVNGS 1 DATE748/85 COMPLETED BYM.P.
Righardson TELEPHONE 602:932:5300 Egt 6593 e
OPEg@IING SIBIUS 1.
Unit Name: Palg Verde Nuclear Gegeogting Statign Unit 1 t
2.
Reporting Period: June 1985 3.
Licensed Thermal Power (MWt): 3800 4.
Nameplate Rating (Gross MWe): 1304 5.
Design Electrical Rating (Net MWe): 1270 6.
Maximum Dependable Capacity (Gross MWe):Tg be cetermiged 7.
Maximum Dependable Capacity (Net MWe):
Tg be detgrmiged 8.
If Chances Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: __________________
______________________Nf6________________________________
9.
Power Level To Which Restricted, If Any (Net MWe):NfA 10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative i
- 11. Hours In Reporting Period
___720____
___4344___
_4344___
- 12. Number Of Hours Reactor Was Critical
___695____
____839___
__839___
13.
Reactor Reserve Shutdown Hours
_____0____
______0____
____0___
14 Hours Generator On-Line
___375.52_
___375.52_
_375.52_
- 15. Unit Reserve Shutdown Hours
____0_.___
_____0____
____0___
- 16. Gross Thermal Eneroy Generated
_.128820.8_
_328820.8_
_328820.8 (MWH)
- 17. Gross Electrical Energy Ger;-ite 8
__60,200__
__60,200__
_CO,200_
(MWH)
- 18. Net Electrical Energy Generatad
__16,292__
__16,292__
_16,292_
(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 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 (Type, Date, and Duration of Each):
25.
If Shutdown At End Of Reoort Period, Estimated Date of Startuo: _____
__N/A_______________
- 26. Units In Test Status (Prior To Commercial Operation)-
Forecast Achieved INITIAL CRITICALITY
___5/85_____
___5/25/85___
INITIAL ELECTRICITY
___6/85_____
___6/10/85___
COMMERCIAL OPERATION
__11/85_____
_ _._ _ _ N / A _ _ _ _._
8509110059 850630
'ERAGE DAILY UNIT POWER LEVEL fg2y PDR ADOCK 05000528 R
PDR 1,l1
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[
DOCKET NO.
- 50>-52-------------
UNIT-------------.-----_--
PVNGS-1 DATE---------------------
7/08/85 COMPLETED BY M_.P
_R i chard s.on s
602-932-5300 TELEPHONE
- - - - - - -.9.. 3-----
Ext. 65
-QNTH:
June 1985-M 4
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
=_
---0 17 ----------800'-------------
2 0
18 ---------3700------..------
3 0
19 __
--_3600 ----_--_-_---
4 0
o20 3000 5
0 21 ___--____4200 6
0--------------
22 3800 i
7 0
23 -----
<4300 8
0 24 ---------2400-------------
_...---n i
s 7
9
0 25 1500----.
1 10 100 26 --
2800~
t 11 500 27 4300 -
12 -~----- 3100 28 4100 n--
13 -------.3300_
C 4700- - -. _--___-_
-14 1800
---=
30 ---------6600 15
--O A
16 -------- 200
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4 Y
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1 s
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=
g REFUELING INFORMATION DCCKET NO._g0:525__________
UNIT _______pyNGS;1_____
DATE_______Z(0848Q_____
COMPLETED BY_McE. Richardson 3
TELEPHONE __602:932:53Q0____
__Egts 6553_______
1.
Scheduled date for next refueling shutdown.
03/01/87 2.
Scheduled date for restart following refuelina.
04/19/87 3.
Will refueling or resumption of ooeration thereafter recuire a Technical Specification 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._?di___________
b) In the scent fuel storage pool._____0_______
7.
Licensed spent fuel storage capacity,____13sg______
i Intended change in, pent fuel storage acity._,None______
8.
projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2002.(w/ annual.relcars and full core discharge capability).
~
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1 595d881 QE QEEgeIIN@.EKEESIENGE EQB IHE MQNIU l
i DOCKET NO.___50:52@___________
UNIT _________PVNG@-I__________
i DATE_________ZLO8485__________
COMPLETED BY_M.P._ Richardson __
TELEPHONE __602-232:5300_______
__ Ext._ 6523 ----------
6/1 Unit in Mode 2 6/1 Continued with CEA worth measurements by exchange.
6/1 Completed low power physics testing.
6/2 Began CpC' verification test and COLSS initialization.
6/5 Completed Mode change checklist for Mode 1,
entered Mode 1.
6/7 1327 - Completed shell warming for the turbine, closed main steam stop valve #2 bypass.
6/8 Continued turbine generator startup.
6/8. 1532 - Turbine at rated speed of 1800 rpm.
6/8 1650 - Turbine was at 1800 rpm for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 20 minutes and then tripped on Hi vibration on the #8 bearing.
6/9 1150 - Turbine at rated soeed of'1800 rom.
6/9 1433 - Tripoed. Main Turbine manually due to Hi vibration on
- 7 bearing.
6/10 2226 - Approximately 20 min after the main generator was loaded CPC D DNBR started cycling causing a channel D trip. During.the investigation, the main' turbine had to be tricoed on high vibration. When the turbine was unloaded and tricoed, the DNBR cycling on CPC D
. stopped.
6/10 1149 ~ A; set speed of 1800 rpm on Turbine.
6/10 1850'- Reactor power at 12*A 6/10 2226 - Tripped Main Generator due'to high vibration on bearing #7 6/11 0630 - Main turbine.st 3800 rom.
~
6/11 0651.- Tripoed Main' Turbine rather th'an having it spin unloaded during LPC testir.g.
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---et' c-t
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y e-t-t--p y
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3 6/12 1600 - Reactor at 20% cower.
6/14 1156 - FWpT "B"
tripoed on low suction pressure, tricoed Main Turbine, Reactor tripped on high Local Power Density (LpD).
NO7E:
On further investigation it was found the reactor trio was due-to hi oressurizer cressure.
6/16 1323 - Criticality achieved on Unit i reactor.
6/17 Main turbine generator trio caused by oscillations in the feedwater control system. This caused a main feedwater pumo tria.
6/18 1215 - Lowered turbine generator load down to 101 MW to cycle Atmospheric dump valve ADV SGA-184 6/18 1259 - Raised turbine generator load to 175 MW SGA-184 cycled 5 times (sat).
6/22 1611 - Increased surveillance frecuency on CEA positions oue to reouirements of T.S.
4.1.3.6 with the PDIL auctioneer circuit inocerable.
6/23 Inserted Group 5 rods to 12" withdrawn for Rx Engineering in preparation for delta temperature and delta power testino.
6/24 1404 - Tricoed turbine, began reducing power to 13% cower Note:
The turbine shutdown was required because pressure point isolation valves MTN-V243 and MTN-V244 were blown off the main steam lines downstream of MTN-UV2002 causing a 1"
hole in the steam line.
6/24 1610 - Rx power 11%.
6/25 0250 - Steam line break recaired, reset main turbine, commence:1 chest-warming.
6/25 2338 - Rx cower 14.9%
6/26 1255 - Performed Automatic Economizer /Downcomer feedwater control valve transfer, transferred at 16.5% power.
Initial test results are satisfactory.
6/27 Completed final economizer /downcomer valve testing, returned reactor cower to 19.8% cower.
6/27_1258 - Entered action statement on pressurizer safety valve position indication (3.3.3.6). for removal o? temporary test eouioment, 6/27 1430 - Exit ed action statement for pressurizer safety valve position indication.
6/28 RRS auto CEA insertion and withdrawal were tested satisfactory, (at low rate), following CEDMCS repairs.
6/29 2340 - Rx power 22%
+
6/29 0300 - Tavg dropped low due to inadvertant boration of the RCS.
This boration was due to makeup mode selector switch in dilute position causing a boration vice dilution.
Attemoted to duplicate, problem could not be duplicated.
6/30 0356 - COLSS (CMC) ceclared operable 6/30 0430 - Began oower ascension to 30% F.P.
6/30 2206 - Rx at 40% power generator load at 405 MWe.
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UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO.
90A?A UNIT NANC PVN L I DATE
//0 4/85 COMPLETED BY M. I'. Richardqng T[t.[ Pit 0NC ~ 9 U-5 300 Pye A%n3 Hathod or Shutting Down System Component Cause & Corrective 3
1.ER 88 5
Action to 2, Reactor 1
Duration No.
Codo Code Prevent Recurrence No.
Date Type
( flou rs )
Reason 1
6/14/85 F
25 A
3 85-019 HBG Valvo;.
See Attached' I
2 3
4 T-Fo rced Reason:
Hethod:
Exhibit F = Instructions S-Scheduled A-Equipment re f luro (Explain) 1-Ha nisa l for Prnparation of Data n-Maintenance or Test 2-Hanost Scram.
[ntry Shcots for Licensee C-Rc resc l ing 3-Automa t ic Scrain.
[ vent Report (LER) File D-Regula tory Rest riction 14-Continua tion f rom (NUREC 0161)
E-Opnra tor T ra ining & t.lconse Examina tion Prnvious Month F-Admi n i s t ra t ive 5-neduction or 20%
5 C-Ope ra t i ona l Error (Explain) or creator in the Exhibit H-Seme Source H-Other (Explain)
Past 2fs llours 6-Other (Explain) 2960u 4
O
- *(.NRC Monthly Raport - Juns t
W The "A" Main Feedwater Pump Mini-Flow Control Valve did not control properly, allowing excessive condensate flow back to.the condenser.
This in conjunction with improper operation of Condensate Pump Mini-Flow Control Valves caused a low suction pressure trip of the "B" Main Feedwater Pumo at 1155. The reactor operators manually i
tripped the turbine-generator, started auxiliary feedwater and began manually reducing reactor power by insertion of CEA's attempting to reduce. power to within the capability of the Auxiliary feedwater System. At 1156 the reactor tripped on high pressurizer a
~^
- pressure, i
i
.Carse of the. trip was improper operation of the "A". Main Feedwater Pump Mini-Flow Control Valve.
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Arizona Nuclear Power Project P.O. BOX $2034 e PHOENIX, ARIZONA 85072-2034 Learned W. Barry, Director ANPP-33016-EEVB/GEC Office of Resource Management July 15, 1985 U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528, License No. NPF-41 June Monthly Operating Report File: 85-056-026; C.I.01.10
Dear Mr. Barry:
Attached please find the June 1985 Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) zo 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 or concerns, pleae contact me.
Very truly yours, ErwFM/rgE E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVBJr/GEC/sih Attachments cc:
J. B. Martin (all w/a)
R. P. Zimmerman E. A. Licitra A. C. Gehr d
V T
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