ML20207D611
| ML20207D611 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/31/1986 |
| From: | Colville J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-38245-JGH, NUDOCS 8612310113 | |
| Download: ML20207D611 (6) | |
Text
f 4
NRC MONTHLY OPERATING REPORT DOCKET NO.
UNIT NAME
_P V _N G S _- 1_ __ -
DATE
_0 _9 _/ 0 8 / 8 _6 COMPLETED BY J2N._golv111e TELEPHONE
_692-932--5390 l
OPEltATJNG STATUS
~
~
1.
Unit Name: Pglo Vggde Ngclear_Genergting_Eggtient_Qnth_1 2.
Reporting Period:
A_u_ gust _1986 3.
Licensed Thermal Power (MWt): 3800
~-
4.
Nameplate Rating (Gross MWe): [14O[3 5.
Design Electrical Rating (Not MWe):
1231 6.
Maximum Dependable Capacity (Gross MWe): 1_303 7.
Maximus Dependable Capacity (Not NWe):
1221 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
==
9.
Power Level to Which Restricted, If Any (Not MWe): _NQNE-10.
Reasons For Restrictions, If Any:
_=---
=
This Month Yr.-to-Date Cumulative 11.
Houre in Reporting Period 744___
___4800
___4800___
12.
Number of Hours Reactor Was Critical
____518.2_
2476.4 13.
Reactor Reserve Shutdown 247@.2_
Houra
_____O O_____
_____g____
j 14.
Hours Generator On-Line
____494.5_
___2409._3__
24Q9 3, 15.
Unit Reserve Shutdown Houra O
O O
16.
Gross Thermal Energy Generatad (HWH) 1_ t74Qt@82_
_8 644,_305_
6
_8_g_44 395 g
t m
17.
Gross Electrical Energy i
Q@
Generated (MWH)
__59_3, M _
_2 9_Z6 M _
_ 2 9_ 7_6_ t3go j
t t
t l gga 18.
Net Electrical Energy
- '00 Generated (MWH)
__548,_O9_7_
_2,736 8_54_
_2 736 854 t
t t
($
19.
Unit Service Fr.ctor
___66.47E_
_ 5 9._O.1 x_ _
_ 5_Q. O_1 x l ;gg 20.
Unit Availability Factor
___G6.4Zx_
Sg.01x_
50.013
-o 21.
Unit Capacity Factor
' o@
(Uning MDC Net) l
___60 3_3x_
____46 dog 46.70x 2
l g4 22.
Unit Capacity Factor m
(Using DER Net)
__ _6_0_._33_3_
____46 dOx_
_ _ _ _ 4 6._7_ 0_ x 23.
Unit Forced Outage Rate
___33.53x
____18.343_
____18.34%
)
mar 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shutdown At End of Report Period, Estimated Date of Startup:_ _ _ _ _
26.
--- -Units _.in Test Status (Prior To Commercial Operation):- - - = =_ =
1
_-----=__
)
Forecast Achieved INITIAL CRITICALITY 5/85~~~
~~2~~O/85~~-~
l 5/25/85 INITIAL ELECTRICITY
~ ~[62 85__
_6 J
\\
COMMERCIAL OPERATION 11/85 2/13/86
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __59-52Q_________
UNIT ___
__PVNGS-1 DATE ____ _ _
_Q94QQ/86_______
C O M P L E T E D B Y J_. M_. _ C_ o l v 1 1 1_e _ _
T E L E P H O N E _ _ _ 6_ 0_ 2_ _ 9_ 3_ 2_ _ 5_ 3 0 0 _ _
_ _ _ E_ x_ t_ _. _ 6_ 5_ 9_ 3_ _ _ _ _ _ _
_MgyTH:
August 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY. POWER LEVEL 1
_14232___
17 __
___1,127
__=
.2
__12g33____
is _
___1,g12____________
3 1,233__=
19 ___
__1,314_______
4
__1,233_____
20 _=
___1,gto 5
___1,399____
21 1112g_______
6
_12Z__
22
___1,158____
_=-
7 9_____
23 ___
_1,192___ _ _ __
a
_9__=
24 ____
_1,g19
_=
=__
9 9___
25 =_
=1,g31____________
10
_=
____g____
26 __
=1,22g____________
11 _______
9___
27 _-
__1,g14______
12 _ _ _ _
_____9_===
28 ___
_1,g12--
13 ___
_9_ _ _ _ _
29 __
-_1,g19 _ _ _
14 ____
= _ 6_ = - -
30 _
_ _ _ _ _ _2_3_9- --
40_
15 _ _ ---
_9_==
31 __
_ _ _ _ _ 3 3 3 _ _ _ _ ---
16 _ _ _
_ = _
222___________
l l
I
- - ~,
REFUELING INFORMATION DOCKET NO.
50-528_______
UNIT pVNgS-1 _ ____
DATE 09/08/_89_____
COMPLETED BY J N ___Colv_iM e 2 2 TELEPHONE gO2,-932-5_300_
2
'Eyt.__6593;___
1.
Scheduled date for next refueling shutdown.
03/13/87 2.
Scheduled date for restart following refueling.
04/19/87 3.
Will refueling or resumption or 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 eupporting information.
Not Yet Determined 5.
Importent Licensing considerations associated with refueling, e.g.
new or different fuel desic or supplier, unreviewed design or performence analysis methods. aignificant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The number of fuel assemblies.
a)
In the core. ____241 b)
In the spent fuel storage pool.
O_
7.
Licensed spent fuel storage capacity.
1329___
l Intended change in spent fuel storage cepacity.
___yone___
l 8.
Pro 3ected date of last refueling that can be discharged to spent 1
fuel storage pool a==iming present capacity.
2002 (w/ annual reloads and full core discharge capability).
O
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET MO.
39 --}23__ __ _ _ _
UNIT Pyugg-1______
DATE 09/95/_83_____
j COMPLETED BY L N._Co_1 vim e TELEPHONE GOO 2_-932-5_3pO_
E iz__6593 __ __
2f l
l 08/01 0000 Reactor Power et 1004 - Mode 1.
08/06 0412 Reactor Trip due to loss of offsite power source when Startup Transformer NAN-XO3 relayed out - Entered Mode 3.
08/13 1132 Reactor
- a..itical Entered Mode 2.
08/13 1608 Entered Mode 1.
C8/13 1955 Synchronized Main Generator to Grid.
08/14 0300 Reactor Power at 404.
t 08/15 0035 Tripped Main Turbine to test operation of Fast Bus Transfer - Reactor Trip on Hi Pressurizer Pressure.
Entered Mode 3.
08/16 0510 Reactor Critical - Entered Mode 2.
08/16 0639 Entered Mode 1.
l 08/16 104O Synchronized Main Generator to Grid.
08/16 1422 Reactor Power at 203 08/17 0650 Reactor Power at 1004.
08/30 0518 Reactor Trip on SG #1 Low RC Flow - Entered Mode 3.
08/31 0312 Reactor Critical - Entered Mode 2.
l 08/31 0608 Entered Mode 1.
08/31 1300 Synchronized Main Generator to Grid.
08/31 1654 Reactor Power at 45x.
' O ' UNIT SHUTDOWNS NO POWER REDUCTIONS 2.e; DOCKET NO.
Mn-99A
~'
UNIT NANC PVNf.S-l COMPLETE olvltle TELEPif0NC OU-5 mo
_Fve MG3 i
Hethod or Shutting Down System Component Cause & Corrective n
1 Dura t ion 2
3 f.ER 4
5 Action to No.
Dste Type
( flou rs )
Reason Reactor No.
Code Code
- Prevent Recurrence 6
8/6/86 F
183.7 A
3 1-86-003 EA XCT Reactor trip due to loss of offsite power source whe'n Startup Transformer NAN-XO3 relayed out.
~
7 8/15/86 S
,0 B
N/A N/A Tripped Main Turbine to test operation of Fas't Bus Tr'a.hsfer.
8 8/15/86 F
34.1 A
3 1-86-045 JI FCV Reactor trip on Hi Pre,ssurizer Pressure.
9 8/30/86 F
31.7
.A 3
1-86-033 JC PDT Reactor trip on SG #1 Low RC Flow.
a
- i I
' t 1
2 3
is
~
F-forced Reason:
Method:
Exhibit T - Instructions S-Scheduled A-[Quipment reiluro (Explain) 1-Hanpal for rrnparation of Datn
/
D-tfaintenance or Test 2-Hanoni Scram.
Entry slicets for Licensee C-ncruceIng J-Automa tic Scram.
Event Report (LER) File D-negulatory Restriction 4-continuation from-(NUREC 0161)
[-onorator training & License Examination ernvious Month r-Administrativo q
C-operational Error (Explain)
- 5-nedoction or 20%
5 or Creator In the Exhibit H-Same Source H-Other (Explain)
Past 2's flours g.
9.other (Exp osin)
Onhnes
?
l
r-7' #
C Arizona Nuclear Power Project P.O. BOX 52034 e PHOENIX, ARIZONA 85072-2034 September 15, 1986 ANPP-38245-JGH/PGN/98.05 Mr. Ronald M. Scroggins, Director Office of Resource Fbnagement 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)
August Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the August, 1986, Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifica-tions) 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, NV J. G. Hay es Vice President Nuclear Production JGH/PGN/rw Attachment cc:
O. M. De Michele (all w/a)
E. E. Van Brunt, Jr.
J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr INP0 Records Center
% 62-I r
I;l