ML20154S548
| ML20154S548 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/31/1985 |
| From: | Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-34656-EEVB, NUDOCS 8604010316 | |
| Download: ML20154S548 (8) | |
Text
. -
NRC MONTHLY OPERATING REPORT DOCKET'NO.
50-528 UNIT NAME PVNGS-1 DATE 01/08/86 COMPLETED BY M.
P.. Richardson TELEPHONE 602-932-5300 Ext. 6593 OPERATING STATUS 1.
Unit Name Palo Verde Nuclear Generating Station, Unit 1 2.: Reporting Period December 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):To be determined 7.
Maximum Dependable Capacity (Net MWe):
To be determined 8.
If Changes Occur Above Since Last Report, Give Reasons: ___
____-_--_ N / A _ _ _ _ _ _ _ _ __
=_
9.
Power Level To Which Restricted, If Any (Net MWe):____N/A________
- 10. Reasons for Restrictions, If Any:________N/A________________ _ _
_ _ = _
_ _ = _ _ _ _
Month Year Cumulative
- 11. Report Period Hrs
_______744__
_____4898__
_____8760__
- 12. Hours Reactor Crit ical
_____583.8__
_____2427__
_____2427__
- 13. Rx Reserve Shtdwn Hrs
_______,,_0__
___0__
O__
- 14. Hrs Generator On-Line
_____465.3__
___2019.8__
___2019.8__
- 15. Unit Reserve Shtdwn Hrs
___0__
________0__
0__
- 16. Gross Therm Ener (MWH)
_1,460,729__
4,394,189__
4,394,189__
- 17. Gross Elec Ener ( MWH.)
___478,600__
1,336,700__
1,336,700__
- 18. Net Elec Ener (MWH)
___430,781__
1,127,650__
1,127,650__
- 19. Unit Service Factor
_______N/A__
______N/A__
__N/A__
- 20. Unit Avail Factor
_______N/A__
______N/A__
_N/A__
. 21. Unit Cao Factor (MDC Net)
_______N/A__
______N/A__
______N/A__
- 22. Unit Cap Factor (DER Net)
__N/A__
______N/A__
= __
N/A__
- 23. Unit Forced Outage Rate
_______N/A__
______N/A__
______N/A__
- 24. Shutdowns Sched Over Next 6 Months (Tyou,Date, Duration): __
SurveillaDer Tesi 991ese : JZaSt 49 dayn_______________________
- 25. If Shutdown At End Of Report Period, Est imat ed Date of Startuos____
- 26. uni E ii. Tesi siains iE Isr TE E;;;; EI;i 5pe aii;Eii--
Forecast Achieved INITIAL CRITICALITY 5/85 5/25/85 INITIAL ELECTRICITY 6/85 6/10/85 COMMERCIAL OPERATION 11/85 N/A
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8604010316 851231 PDR ADOCM 05000528 R
REFUELING INFORMATION DOCKET NO._g@-Qgg__________
UNIT _______PVNGH-1_____
DATE_"______0140gfg@_____
COMPLEiED BY_M P Richandsgo c t TELEPHONE __@0g-Egg-gge0_
+
__Ent-_ 6223__
1.
Scheduled date for next refueling shutdown.
03/01/87 2.
Scheduled date for restart following refueling.
04/19/87 3.
Will refueling or resumption of operation thereafter require 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 S.
The number of fuel assemblies, a) In the core._g41___________
b) In the spent fuel storage pool._____0_______
- 7. Licensed spent-fuel storage capacity.____18@H______,
Intended change in spent fuel storage capacity.
Ngge______
8.
projected date of last refueling tha't can be discharged to spent fuel storage pool assur6ing present capacity.
A 2002 (w/ annual reloads and full core discharge capability).
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
@0-Qg@
UNIT ______EMNQ@ 1________
DATE______0140@L@@________
COMPLETED BY_Mu2n Righandggn TELEPHONE _60g-23@-D300
_ggi._ @Q23 MONTH:
December 19E5 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
=-
0 17
_0 2
___596___
18 _____ ____
0___
3
__ 7 8 0 _ _ __ __
19
_319___
4
_ __ _ __ ___6 0 4_ _ ___ _
20 ____
_ _ __.___ 4 1 _ _ _ _ _ _ _ _ _ _ _ _ _
5
_0 -
21 __________124_
6
= _ _ _ _ _ __ __ 6 4 _ ____ _ _ _ _
22 _ _
_ _7 4 3____ _
7
__ __ __ __,,4 73 23 __
___1,166_ _
8
_964_ _
24 ____
_1,174_ __
9
_900_ _ _ -
25 - --_ - - - - -
__1, 17 4 10 _______1,136_
26 ________1,174_ _
11 _________468______________
27 _ _ _
__1,133_____
12 ______
O_
28
_1,114_
13 __. __ _
_0
__ _ _ _ _ _ _==
29
___ 1,118 14 __ z 0
30
__ _ 1, 1 4 8 __ _ _ f _ _
15==
_____ _ 0 _ _ _
31 ________1,170..
- - =
16 _________368____--
==
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EWM50BX QE QEEBBIINE EKEEBigNQg EQB IMg [QNIH DOCKET NO.___@0-Eg@__
UNIT ______
PVNQg-1_
DATE_
___014@@4g6 COMPLETED BY_Mtpu Bichandsgn TELEPHONE __6Qg-23g-3300
__Entt 6523__________
12/01 0048 - Increased Rx power to 5%, entered Mode 1.
12/01 2309 - Syne Main Generator on line.
12/02-9108 - Increased Main Generator load to 164 MWe, Reactor power at 18.5%.
12/02 1250 - Reactor power at 80%, Main Generator at 1027 MWe.
12/04 1430 - Initiated Load Reject Test, satisfactory.-
12/04 1700 - Reactor power at 25%, Main Generator at 250 MWe.
12/04 1627 - Syne Main Generator on line at 60~MWe.
12/04 1996 - Reactor trip at 56% power.
Trip due to a high penalty factor being inserted by the CEACs due to dropping Subgroup 12 (part lengtn CEAs).-
All equipment functioned as designed.
12/05 0143 - plant in Mode 3.
12/05 2107.- Reactor is critical, entered Mode 2.
12/05 2247 - Entered Mode 1.
12/06 0433 - Sync Main Generator.
12/06 0458 - Main Generator tripped due to high vibration.
12/06 0653 - Sync Main Generator.
12/06 1158 - Main Turbine trip due to a generator exciter trip.
12/07 0521 - Syne Main Generator.
. 12/07 1543 - Reactor power at '80% power.
12/07 2220 - Commenced power ascension to 90% power.
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NRC Monthly Report - December Page 2 12/10 0025 - Reactor power at 90% power.
12/10 1408 - Comeenced power ascension to 100% power.
12/10 1743 - Reactor power at 100% power.
12/11 0754 - Borated to reduce reactor power to '70% due to suspected condenser tube leak.
12/11 1105 - Entered Mode E 12/11 1108 - Main Ger.orater of f line.
12/11 1630 - Reactor power at *1% power.
12/12 1545 - Plant in Mode 3.
12/12 1559 - Reactor is in a shutdown condition due to ammonia concentration chemistry in the primary.
12/15 0340 - Reactor critical, entered Mode 2.
12/15 2224 - Entered Mode 1, reactor at 9 5% power.
12/16 0310 -- Main generator on line.
12/16 1533 - Reactor at 52.2% power, Main generator 552 MWe.
12/16 2315 - Main turbine trip.
12/16 2332 - Reactor trip due to Lo S/G 1evel on all~4 channels, entered Mode 3.
12/18 2152 - Reactor is critical, entered Mode 2.
12/19 0156 - Entered Mode 1.
12/19 0407 --Main generator on line.
from 40% 'ower on high pressurizer 12/20 0243 - Reactor trip p
pressure after a reactor power cutback signal initiated a turbine runback and SBCS auick open i
block.
plant response was normal no ESFAS actuations.
12/21 0630 - Reactor critical, entered Mode 2.
12/21 1028 - Entered Mode 1.
12/21 1415 - Main generator on line.
l 12/22 2055 - Began 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run at 95% power er greater.
1 E
NRC Monthly Operating Report page 3 12/23 9845 - Reactor power at 100%.
12/25 9800 - Plant in Mode 1, reactor power at 99.6%, rnain generator at 1312 MWe.
12/27 0153 - Completed 190 hour0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br /> run ct ) 95% power.
12/38 9415 - Rearctor power at 100%.
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,*,, ' UNIT SHUTDOWNS AND POWER REDUCTIENS-DOCKET NO.k, ' Mn-49A
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UNIT MANC ~PVHG9-1
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I DATE - 0I110/86 COMPLETED BY __ H. t'. Kachardenn TELEPal0NC ~ 9 U-5100 rve Asni Hethod of g
Shutting
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Down System Component Cause & Corrective a
1 Duration 2
3 1.ER I:
5 Action to No.
Dsto Type lifours)
Resson Roactor No.
Code Code Prevent Recurrence 20 12/04/85 S 0
B N/A Load. reject test.
21 12/04/85 F 26' A
3 1-85-088-00 AA 25 liigh pena'It'y factor being inserted by the
~
CEACs.duetto. dropping subgroup 12 (part length)., Rep 1' ace phase synchronizer card.
22
,12/06/85 F D
A N/A liigh.vi.br a t f or). Reset.
23
}2/06/85 F 0
A N/'A Generator exciter trip., Vented nornal chilled water to co11petor housing.
24 12/11/85 F 0
A
,5 Reduction in power due to suspected
- s condenser tube 1e.ik.' Plugged tubes.
25
,42/12/85 F 60 A
1 Reactor shutdown due to ammonia I
con, centration chemistry in primary.
26
~12/16/85 F 0
11 N/A i 083-00 BOP ESFAS sequencer failed, entered Tech. Spec. LCO 3.0.3 27 12/16/8,5 F 46 A
3 1-85-090-00 JK LIC Low steam generator level on all 4 channels. Revised setpoints to FWCS.
28
'12/20 /65 F 28-A 3
1-85-O tiO-00 JI PMC liigh pressurizer pressure af ter turbine runback.
Revised setpoints.
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1 2
3 4
T-Forced.
Reasont Method:
Exhibit T - Instructions S-schoduled A-Coulptncnt railuro (Expla in) 1-nanssa l for Prnparation or Data i
D-Naintenance or Test C-Rcrucilng 2=Hanpal Scram.
[ntry Sliccts for Licensee 3-Automati: Sc ra m, twent Report (LCR) File D-negulatory nostriction ts-Continus t lan f rom-(NURCC 0161)
E-Opera tor Tra ining k l.icense Examina tion Prnvious Month
'e d.g T-Administrativo 5-nedvetion or 20%
5
,C-opo ra t iona _l Error (Explain) or creerne en enn r~ M M * " * = - - * - - - -
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2.
Arizona Nuclear Power Project P.O. Box $2034 e PHOENIX, ARIZONA 85072-2034 January 15, 1986 ANPP-34656-EEVB/LJM/98.07 Mr. Ronald M. Scroggins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 (License NPF-41)
December Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the December, 1985, Monthly Operating Report prepcred and submit-ted 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 alsa 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, l%
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 INPO Records Center 8
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