ML20214L563
| ML20214L563 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/30/1986 |
| From: | Colville J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-37405-JGH, NUDOCS 8609100272 | |
| Download: ML20214L563 (7) | |
Text
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NRC MONTHLY OPERATING REPORT DOCKET NO.
5_0 - 5 2 9_
UNIT NAME Phlps,-2 2DATE OJ/9pf35 COMPLETED BY J.M _9olyilly
.3 TELEPHONE 592-932-3300 E331_6D93 99 ERB 11N9_ SIBluS.
1.
Unit' Nane : P_a_1 o__V_e_td e _N u_c l_e a_n _Ge_ne r a t_i_ng._S t_a_t_i_onu _U_n 1_t_,_2_
2.
Re port i ng Period: J_u ne__19,86_
3.
Licensed Thermal Power.(MWt): 3@00 4.
Nameplate Rating (Gross MWe): 1403 0
5.
Design Electrical Rating (Net MWe):
J23J 6 '.
Maximum Dependable Capacity _ (Gross MWe) :. Tso_ bg_ d et ermired e
'7.
Maximum Dependable Capacity (Net MWe):
To_be_determiped e
8.
If Changes Occur.In Capacity Ratings (It ems Number 3 Through 7)
Since Last Re port, Give Reasons:
9.
Power Level to Which Restricted, If.Any (Net MWe): _ N O,N_E,_ _ _ _ _ _ _ _ _
10.
Reasons For: Restrictions, If Any -
This Month Yr. -t o-Dat e Cumulative 11.
Hours in Reporting Period
.__Z20__.___
__j]SjzgD_,_
_5409 25__
5 3
12.
Number of Hours Reactor Was Critical
__5 31._8 _ _ _
_ _ _ 9 6_4_._ 5 _ _ _
_ _ 9 6,4._ 5 _ _ _
13.
Reactor-Reserve Shutdown Hours
_____0___
_____0_____
_____0____
14.
Hours Generator On-Line
__483._3___
_ _.6 7.,6._ 4,_ _,
__,,6_Z6._4____
15.
Unit Reserve Shutdown Hours
_,.,_ _ _ 0 _ _ _ _
__.__0_____
_____0___
16.
Gross Thermal Energy Generated.(MWH)
_148.,Z9_4__
_9_2Zs_252___
_92Zu252___
s 17.
Gross Electrical Energy
_ 2 1_4_ t _0 0 _,_
_245 dOO____
_ 2_4_ 5 d O_ 0 _ _
8 Generated ( MWH) 18.
Net E lect rica l Energy Generated (MWH)
_1_Z3,_239__,
_1,7Z,.,196_,, __
_1 ZZo296___
19.
Unit Service Factor
_ _ __N/_8__ _
_ _,_ _N_(Q _ _ __
NLA___
20.
Unit Availabi1ity Factor
__ _ _N_(A _ _ _
_ _ _ _N (A _ _, __
__ __N LA __ _
21.
Unit Capacit y Factor (Using MDC Nit)
_ _ _ _N_(A _ _ _
____NLQ____
____NLA___
22.
Unit Capacity Factor (Using DER Net )
____N(@___
____N(@____
____Nf@___
- 23.. Unit Forced Outage Rate
___ N_(A___
_ _ _ _N_(A _ _ __
__ _, _N_(A __ _
24.
Shutdowns Schedu!cd Over Next 6 Months (Type, Date, and Durat ion j
flo_ s i_go i f i cppt_ o ut a_g e_.pl pnred_ untfj_ a f t er_ warrppty_rur_
of Each):
o e
25.
If Shutdown At End of Reoort Period, Estimated Date of Startup:
____BIL8__________________________________.___________________________
26.
Units in Test St at us (Prior To Commercial Operat ion) :
Forecast Achieved INITIAL CRITICALITY
__3/36__
_4/jpf#b_
INITIAL ELECTRICITY
__b/#6__
5/20/96_
COMMERCIAL OPERATION
_J1195__
i
~
$c-/]
8609100272 860630 Cv PDR ADOCK 0500052*/
I R
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-529 UNIT PVNGS-2 DATE 07/06/86 COMPLETED BY J. M.
Colville~~
EEE~93E~5,500 TELEPHONE ------------ -----
Ext. 6593 MOllTil:
June.1986 T
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
0 17 484 2
0 18 395 3
__-_-----_266_--------_-----
19 --_----------_1 54 4
236 20 367 5
- _ - _ --- _ -_3 2 1 21 416 6
173 22 541 7
143 23 541 8
369 24 ---- ------- _4 9 4 9
426 25 149 0
10 439 26 ----_=
11 0
27 0
12 0
28 0
13 213 29 0
14 108 30 0
15 -___----__5_4_8__._-----_----
16 523
+-%,
y
.-_.p-_.7 m
9 REFUELING INFORMATION DOCKET NO.
50-529________
UNIT PyNjS-2______
DATE 07/05/86_____
COMPLETED BY J.M.__Qolyillg 502-932--5_300_
0 3
TELEPHONE Ertz b@31----
1.
Scheduled date for next refueling shutdown.
01/02/88 2.
Scheduled date for restart following ref.ueling.
02/20/88 3.
Will refueling or resumption or operation thereaf ter require a Technical Specification change or other license amendment?
Not Yet Determined Wh at will these be?
Not Yet Determined 4.
Scheduled date for submitting proposed licensing action and supporting information.
Not Yet Determined 5.
Im port ant Licensing considerat ions associated with refueling,
- e. g.
new or dif ferent fuel design or supolier, unreviewed design or performance analysis methods, significant enanges in fuel design, new operating procedures.
Not Yet Det ermi ned 6.
The number of fuel assemblies.
a)
In the core.
____241____
b)
In the spent fuel st orage pool.
______0______
7.
Licensed spent fuel storage capacity.
___1329___
I nt end ed change in spent fuel storage capacity.
___Nopp___
8.
Project ed date of last refueling t hat can be discharged to scent fuel storage pool assuming present capacity.
2003 (w/ annual reloads and full core discharge capability).
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-529_______
e UNIT PyNDSrg______
DATE 0]/05/j5_____
COMPLETED BY J.M _Colyjjle 3
TELEPHONE 502-933--5300_
0 Eytz_b59}____
06/01 0000 Plant in Mode 3.
06/02 1634 Reactor Crit ical - Mode 2.
06/03 0015 Plant in Moon 1 - Reactor Power at 5%.
06/03 0317 Synchroniced Main Generator to grid.
06/03 0515. Reactor power raised to 25%.
06/04 0652 React or power at 50%.
06/04 0900 Reactor power lowered to 25% due to Steam Generator chemintry.
06/05 1340 Reactor power at 50%.
06/06 0202 React or power reduced to 25% due to chemistry problems in SG's #1 and #2.
06/08 1403 React or power at 50%.
06/10 0420 Turbine trip due to Excitat ion Protective Trip.
React or trio on high pressurizer pressure - Mode 3.
Li f t ed Main Steam Safety Valves.
06/11 0232 React or Cr it ica l - Mode 2.
06/11 1022 Entered Mode 1.
06/11 2340 Synchroniced Main Generator to grid.
06/13 1700 Stabilized reactor power at 50%.
06/20 1750 Shutdown due to inability to recover drooped part Length Control Rod (CEA) #48 within Technical Spec i fi cat ion 3.1. 3.1 act ion req uirement s.
Entered Mode 3.
L.
a 5
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH (Continued)
DOCKET NO.
50-529 UNIT PytJSS-2 DATE 01/05/36_____
COMPLETED BY-J. M _Colyilj e 3
' TELEPHONE-
' #02-933--j_300_
2 E.2!.. 6593 t
1 06/20 2312. Reactor critical - Mode 2.
06/21 0033 Entered-Mode 1.
06/21 0305 Synch roni z ed Main Generator to grid.
06/21 0623 React or power at - 50%.
06/25 1110 Tripped Main Turbine for Load Rejection Test.
React or trio on Low DNBR - Entered Mode 3.
Lif t ed a Main Steam Safety Valve.
106/30 0514 Reactor crit ical - Mode 2.-
06/30 1541 Entered Mode 1.
3 1.
(
1
o
' UNIT SNUTDOWNS AND F0WER ACDUCTl!NS DOCKET NO.90-99R b
UNIT NAHC ~ PVNCS-2
\\.
}
DATE 7-R-86 COMPLETED DY
.T M cnivilia TELEPit0NC ~ 9 U-s mo re A rA 3 Hethod or Shutting Down System Component Cause Ir Corrective 1
Du ra t ion 2
3 f.ER 4
5 Action to No.
Date Type (llou rs )
Reason Roactor No.
Code Code Prevent Recurrence I
. 3 6-l-86 F
40.5 A
4 2-86-027 EL 51 High pressurizer pre'ssure, 3
Negative se.quence trip on the main generator caused a turbine trip,, Turbine, bypass valves did not fuick open.resulting in a j
l reactor trip on high pressurizer
- pressure, 4
6-4-86 F
0 F
5 N/A Reduction in power due to Steam Generator chemistry, 5
6-6-86 F
0 F
5 N/A Reduction in power due to Steam Generator chemistry, 6
6-10-86 F 0
A N/A 2-86-034 EL RJX Main Turbine trip due to Excitation Protection Trip.
7 6-10-86 F 22.2 A
3 2-86-034 JI Reactor trip on high pressurizer pressure.,
8 6-20-86 F 5.5 A
9 2-86-36 AA TMR Shutdown due to inability to recover dropped Part Length Control Rod (CEA)
- 48 within Tech. Spec, 3.1,3.1 action requirements.
9 6-25-86 S 0
B N/A N/A,
Main Turbine trip due to Load Rejection Test.
10 6-25-86 S 114 B.
,3 N/A._ -
Reactor trip on Lo DNBR.
1 2
3 4
T-rorced Renson:
Hethod:
Exhibit T - Instructions S-Schoduled A-Eauipment re f luro (Expla in) 1-Manual for Prnparation or Data n-ttaintenance or Test 2-Hanual Scram.
Entry sheets for Licensoo C-Itc rue l ing 3-Automa tic Scram.
Event Report (LER) File D-neguintory Restriction 4-Continuation from-(NUREC 0161)
E-Opnrator training & License Examination rrnvious Month T-Adm i n i s t ra t ivo c-oporational Error (Explain)
- 5-neduction or 20%
5 or Creator in the Exhibit H-Some source if-Other (Explain) 9 0 thor (Explain)
Past 28 Hours g.
9 a t.n..
W Arizona Nuclear Power Project P.O. box 52034 e PHOENIX, ARIZONA 85072-2034 L
-June 15,1986 ANPP-37405-JGH/PGN/98.05 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 2 Docket No. STN 50-529 (License NPF-51)
June Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the June, 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 2 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, T.C.,i 3 qy J. G. Haynes Vice President Nuclear Production JGH/PGN/rw Attachment cc:
J. B. Martin (all w/a)
R. P. Zimmerman E. A. Licitra A. C. Gehr E. E. Van Brunt, Jr.
INPO Records Center I