ML17300B211
| ML17300B211 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/31/1988 |
| From: | Colville J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 212-00107-JGH-T, 212-107-JGH-T, NUDOCS 8802190126 | |
| Download: ML17300B211 (44) | |
Text
ACCELEMYZD DISXKBUTJON DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) 4 ggjuz-P~
ACCESSION NBR 8802190126 DOC.DATE: 85/01/31 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION COLVILLE,J.M.
Arizona Nuclear Power Project (formerly Arizona Public Serv HAYNES,J.G.
Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Monthly operating repts for Jan 198
.W/880215 r.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR L
i SIZE:Z i TITLE: Monthly Operating Report (per Tech Specs)
NOTES:Standardized plant.
Standardized plant.
Standardized plant.
05000528 8 05000529 05000530'ECIPIENT ID CODE/NAME PD5 LA LICITRA,E INTERNAL: ACRS AEOD/DSP/TPAB NRR/DLPQ/PEB RPB REG FIL 01 EXTERNAL EG&G GROH E M NRC PDR NOTES:
COPIES LTTR ENCL 1
0 1
0 10 10 1
1 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD5 PD DAVIS,M AEOD/DOA ARM TECH ADV NRR/DOEA/EAB NRR/PMAS/ILRB RGN5 LPDR NSIC COPIES LTTR ENCL 5
5 1
0 1
1 2
2 1
1 1
1 1
1 1
1 1
1 S
A TOTAL NUMBER OF COPIES REQUIRED:
LTTR 33 ENCL 30
I l'
E c
~
Arizona Nuclear Power Project P.o. BOX 52034 '
PHOENIX, ARIZONA85072-2034 212-00107-JGH/TJB February 15, 1988 Docket Nos.
STN 50-528/529/530 U.ST Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk Gentlemen:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
January Monthly Operating Report File: 88-024-404; 88-056-026 Attached are the January Monthly Operating Reports prepared and submitted pursuant to Specification
- 6. 9. 1. 6 of Appendix A
(Technical Specifications) to the Palo Verde Nuclear Generating
- Station, Units 1,
2 and 3
Opdrating Licenses.
By copy of this letter, we are also forwarding a copy of the Monthly Operating Reports to the Regional Administrator of the Region V Office.
Due to PVNGS Unit 3
being declared commercial on January 8,
- 1988, there are two separate reports for Unit 3.
If you have any questions, please contact Mr. T. J.
Bloom, at (602) 371-4187.
Very truly yours, T Cj.)0 )VULVA J.
G.
Haynes Vice President Nuclear Production JGH/TJB/rw Attachments cc:
0.
M.
De Michele E.
E.
Van Brunt, Jr.
J.
B. Martin E.
A. Licitra A.
C.
Gehr J.
A. Amenta INPO Records Center (all w/a)
1
t t
NRC NONTHLY OPERATING REPORT
'DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50"528 PVNGS-1 02/10/88 J.N. Colville
'02-393-2679 OPERATING STATUS 1."
2.
3.
5.
6.
7 ~
8.
9.
10.
Unit Name.
Palo Verde Nuclear Generating Station~ Unit Reporting Period:
January 1988
'icensed Thermal Power (NMt): 3800 Nameplate Rating (Gross NMe): 1403 Design Electrical Rating (Net NMe>:
1270 Maximum Dependable Capacity (Gross NMe): 1303 Maximum Dependable Capacity (Net, NMe):
1221 If Changes Occur In Capacity'atings (Items Number 3 Through 7)
Since Last'eport, Give Reasons:
Power Level to Mhich Restricted, If Any (Net NMe):
NONE Reasons For Restrictions, If Any:
This Month Yr.-,t'o-Date Cumulative 12 ~
13.
14.
15.
16.
17
'8.
19.
20.
21.
22
'3
'4.
l.
744 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 0~
100.0~
t 6 Months
(
ling shutdow Hours in Report.ing Period Number of Hours Reactor Mas Critical Reactor Reserve Shutdown Hours h
Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (NMH)
Gross Electrical Energy Generated'(MMH)
Net Electrical Energy Generated (MMH>
Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using NDC N'et)
Unit Capacity Factor (Using DER Net>
Unit Forced Outage Rate Shutdowns Scheduled Over Nex of Each): Currently in refue 744 17616 0.0 9 977.2 g
0.0 0.0 0.0 9 717.1 0.0 0.0 0.0 35~032~837 0.0 12~143~300 0.0
- 0. 0'c O.OR 11~327~924.6 55.2R 55.2~
0.0h 52.7R O.OR
- 50. 6.c 100.Otal 27,0A
- Type, Dat,e, and Duration n
- 25. If Shutdown At End of Report Period, Estimated Date of Startup.
03/02/88 26.
INITIALCRITICALITY INITIALELECTRICITY CONNERCIAL OPERATION 88013i 05000528 DCD 8802190126 PDR ADOCK R
Units in Test Status (Prior To Commercial Operation>:
Forecast 5/85 6/85 11/85 Achieved 5/25/85 6/10/85 1/28/86
4 4
k 4
4 4
~ )
4 g
F I 4 I
4 I(
a I
)
~I I
t,r I
~ 4 II ~
FP 4
I Jf 4
I fa>>
)I k
It )h$
( ")
.I.
I J
+4 I
4 h
p (t'*
- ~
~
I ~ )"44 1
4~,
J, ~
AVERAGE DAILY UNIT PO4IER LEVEL 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 02/10/88 J.M. Colville 602-393-2679 MONTH:
January'988 DAY AVERAGE DAILY POSER LEVEL DAY AVERAGE DAILY POSER LEVEL 17 0
0 18 0
0 19 4
20 0
0 22 0
7 0
23 8
0 24 0
0 25 10 0
0 0
28 0
13 0
29 0
14 0
30 0
15 I
16 0
0 0
, X
'(
Il e'
t.
y ~,
(y
~
~
P k
>'L
REFUELING INFORMATION DOCKET NO.
" UNIT DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 02/10/88 J.M. Colville 602-393-2679 Scheduled date for next refueling shutdown.
10/02/87 2 ~
Scheduled date for restart following refueling.
03/02/88 3 ~
Mill refueling or resumption or operation thereafter require a
Technical Specification change or other license amendment2 Yes ll P
Required Technical Specifications are as follows'.
5 ~ 3 ~ 1 ~ 3/4 ~ 1 ~ 1 2~ 3/4 1
1 ~ 3~ 3/4 ~ 2 8f 3/4 ~ 1 ~ 3 ~ 1 f 3/4 ~ 3 ~ 1 ~
3/4.1.3.6, 3/4.3.1, 2.1.1p 3/4.2', 3/4.2.1, 3/4.2.4, 3/4.2.7i 3/4.3.2 4
Scheduled date for submitting proposed licensing action and supporting information.
July 1, 1987 5.
Important Licensing considerations associated with refueling, e.g.
new or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel
- design, new operating procedures.
a) Modification of the CPCs under the CPC Improvement Program (CIP) and the Statistical Combination of Uncertainties (SCU) Program.
b)
Maximum peak pin fuel enrichment vill be 4.05 v r. U235.
c)
The fuel vendor for the following next 5 reloads vill be Combustion Engineering.
If
<< ~ "'k tl
~ I g:I)
~ "'
I tt g
~ py)
<<7'<<<<R )QQ ~ l.
<<>>Ja.k)>>)
R' J>><<>>> '.) ~4>>
gV<
RG~
- P>>R<<'>>
.R, +j>>>> I ~.I, Q,," g ~ ~ l ~'tyt ~ ag>>I ) f I Ci ~ I"N 416" ~ ~ 4L ~ >> I I ~ ~ j S << ~ I a ~ 0'I R IR %ted ~ <<g I >> ~ ~ ~ i <<t t<<R "'-, ')<<ll>,"A<< t! )It,g<< " l!!>>CHIRR'N'. "<<>> t <<'! ty .I 4'* ).PSI.. h. 1 ~ .a ~! <<ja j. F R l>> ~'">>>> )4 I<< ') '!j 3 '4$ LQ <<)<<4 ~ I RC . "C'I) Il"Vfk.<<<<K, I <<S,'>>I, 'W "4 )m< ) <f/)~~ )~ XV '-ti "f~~ SC'~ '.>'~.l i'!P ">R, 5','gg . l V l Rl -)jt ) le<<I. I I*I 9 ) "," <4>> I ll'J , <<R"g, > IRa ya ~~a "5 I<I) IRI
- 0
REFUELING INFORMATION DOCKET NO. UNIT DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 02/10/88 J M Colville 602-393-2679 (Continued) 6 ~ The number of fuel assemblies. a) In'the core. 241 7 0 b) In the spent fuel storage pool. 80 Licensed spent fuel storage capacity. 1329 Intended change in spent fuel storage capacity. None 8. Prospected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity. 2006 (18 Months reloads and full core discharge capability). k II t q IV l 4 7 II ' 'h C, y I "I t I ~r >>i~>> 't l 'tl $ llll (II
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
UNIT DATE CONPLETED BY TELEPHONE 50-528 PVNGS-1 02/10/88 J.N. Colville 602-393-2679 January 1988 01/01 0000 01/08 1244 Unit in Node 5.
Entered Node 4.
01/09
'2258 01/10 3.430 Entered Moge 3.
Entered Node 4 due to eYcessive RC5 leakage.
01/11 01/16 01/19 01/21 01/23 I
01/23 01/31 0004 0058 1801 0605 0930 1330 2400 Entered Node 5 to repair 1A and 1B Reactor Coolant Pump seals.
Loss of offsite power and damage to 13.8 KV Calvert bus tie was experienced.
Bus ground fault caused the startup transformer to relay out resulting in a loss of offsite power on the A train 4.16 KV bus.
Entered Mode 4.
'I Entered Node 3.
Entered Mode 4 due to a body-to-bonnet leak on an unisolable RCS boundary valve and to repair a stuck Control Element Assembly.
Entered Node 5.
Unit in Node 5.
0 h
tt
~I
UNjT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
UNIT NAME:
DATE COMPLETED BY:
TELEPHONE:
50-528 PVNGS-1 2/lo/88 J.M. Colville 602-393-2679 Method of Duration Shutting 3
System Component No.
Date Type Hours Reason Down Reactor LER NO.
Code 4
5 Code Cause and Corrective Action to Prevent Recurrence 10 (Cont'd)
S (Cont'd)
F 281.9 462.1
~ 1 N/A N/A Unit shut down due to Refueling Outage.
Unit shutdown to repair an inoperable Control Element Assembly.
F-Forced Reason:
2 S-Scheduled A-Equipmcnt Failure (Explain)
D-Haintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training g License Fxamination F-Administrative C-Operational Error (Explain)
.If-Other (Explain)
Method:
1-Hanual 2-Hanual Scram 3-Automatic Scram 4-Continuation from Previous Honth 5-Reduction of 20X or Creator in the Past 24 llours C-0th r (ExnlnIn) 4 Exhibit F - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (IIUREC 0161) 5 Exhibit II-Same Source
1
NRC MONTHLY OPERATING REPORT OPERATING STATUS DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 02/10/88 J.M. Colville, 602-393-2679 1-
.: Unit Name.
Palo Verde Nuclear Generating Station~ Unit 2 2'.
Reporting Period:
January 1988 3
4 ~5.
6.7.
8.
9.
10.
Licensed Thermal Power (MVt): 3800 Nameplate Rating (Gross MWe): 1403 Design Electrical Rating (Net MNe):, 1270 Maximum Dependable Capacity (Gross MMe): 1303 Maximum Dependable Capacity (Net MMe):
1221 If Changes Occur In Capacity Ratings (Xtems Number 3 Through 7)
Since Last Report Give Reasons:
Power Level to Which Restricted, Xf Any (Net MVe):
NONE Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11
'2-13.
14.
15.
17.
18.
19.
20.
21.
22.
23.
24.
25.
26.
12 000 744 10 019.1 9 870.2 36~003~788
'984 300.
g r
12~645~570 927 757.
C.
11 864 639 100.0R 100.04 82.
39'02.1R Unit,s in Test, Status (Prior To Commercial Operation):
Hoursin Report,ing Period 744 744 Number of Hours'eactor Qas Crit,ical 744 Reactor Reserve Shutdown Hours 0
0 0
Hours Generator On-Line 744 744 Unit, Reserve Shutdown Hours 0
0 Gross Thermal Energy Generated (MVH) 2<796<621
~
2c796c621.
Gross Electrical Energy Generated (MVH) 984~300.
Net Electrical Energy Generated (MVH>
927<757.
Unit Service Factor 100,0E 82,3R'nit.
Availabilit Factor
'100.0h Y
Unit. Capacity Factor'Usin MDC Net) g 102.1~
81.0h Unit Capacity Factor (Vein DER Net) g 98.2~
98.2R 77.9k P
Unit Forced Outa e Rate 0.0<
O.OR 6.2M Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Scheduled Date for next Refueling Shutdown -2/21/88 Duration of refueling shutdown approximately 84 days'f Shutdown At End of Report Period, Estimated Date of Startup.
XNXTIAL CRXTXCALITY XNITXAL ELECTRICITY
'OMMERCIAL OPERATION
- Forecast, 3/86 6/86 11/86 Achieved 4/18/86 5/20/86 9/19/86
- I
~ s r
,l d
k P
1 Vt CI 1
1 L%
I n
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 02/10/88'.M. Calville 602-393-2679 MONTH January 1988 DAY AVERAGE DAILY POWER LEVEL 1
1J 270 DAY AVERAGE DAILY POWER LEVEL 17 1J 258 1~253 18 1 ~262 1~262 1~262 1~262 1~253 19 1 262 20 1~262 21 1 ~262 22 1 249 C.
10 1J262 1c258 1~262 1~258 1~258 1J 262 1J 266 1J258 1~262 23 24 27 28 30 31 1 ~020 1 ~099 1J262 1~258 1~258 1~262 1 ~262 1 ~262 1 ~258 16 1~267
C tl>>A>>>>>>
Jd~
8 eXkl~rr Pii1 rgb r>>
E
~
t ~ =
ee
~
>> e
,gt r e
e A
e e
I<<
~
e
~ =
~*>>
e
<<jail r
"ee e
e.
'8 L~,, ~ J,
- e
.A ~
eel~
~ ee:M
.ee
=e
<<<<<< 'e
REFUELING INFORMATION DOCKET NO.,
UNIT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 02/10/88 J,M, Colyille 602-393-2679 1.
Scheduled date for next refueling shutdovn.
02/21/88 2 ~
Scheduled date for restart folloving refueling.
05/15/88 3 0 Millrefueling or resumption or operation thereafter require a
Technical Specification change or other license amendments YES Shat vill these be'2 3/4 1 ~ 1 2
~ 3/4 1
1 3
~
. 3/4 2 ~ 8 p 3/4 1 ~ 3 ~ 1
~ 3/4 3 ~ 1
~
3/4 1 ~ 3 ~ 6~ '3/4 2 ~ 5
~ 3/4 2 1
3/4 2 ~ 4 p 3/4 2 3 p 3/4 3 ~ 2 2 1 1
1 Scheduled date for submitting proposed licensing action and supporting information.
12/15/87 5.
Important Licensing considerations associated vith refueling, e.g.
nev or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel
- design, nev operating procedures.
a) Modification of the CPCs under the CPC Improvement Program (CIP) and the Statistical Combination of Uncertainties (SCU) Program.
b)
Maximum peak pin fuel enrichment vill be 4.05 v 4 U235.
c)
The fuel vendor for the folloving next 5 reloads vill be Combustion Engineering.
ll
I ~
">. 'JW'vi)',
q<<
<<VgC)<<"
~ ""
r I 'I I
O ir+r K<<j Ir ~<<
"4C)f'T r
+"-'J<<I E
',V'Ml<<QCI
~
'1+.<<,
Lw L~
I I 0 i LM m<<J w'
V ~ J4 S~'
l<<') X'
'tit.DiTdg'i "v
>*3tj -)'.1 A&i r?1 "'.'<<il XQ A<?..~l' tt l'Il 1 e<<t<
~ ='
~I i I<<<<
<<I
<<-I,,
I e
o <<
t
'Y.
0
<<L
~ <<
'R
~
v<<
E, <<.
5
~
I Ill&.L,+
< 9',, <<4 j 1?1) s l vg I fw.v it "<<f?Wi'<<1'l
<<'i <
pw'k ~.'<<r<<
I,'I, v tgyt ~ 1
?"
l')?,I J, <<<<1<<+
".'w<<'
I< ~ WQ
".,'",, N "r<<1<<,v'.ll
~ -'<<
<<<<'.= lL" <<<<<<3 r l;I,:>~. Wl'?..
C)f<<
gr k <<.
i
<<1 1+1<<
"1.-)
v w<<
I ~
r P
1 r "'I Ar <<2 a. <<ll 1 IPl
~
'1 l= <<
J<<Q<<.
<<C
~.
W r<<
. t l'<<"')<<<1<<='Kr,<<
kl
'll'S v'?
<1 '1l
REFUELING INFORMATION DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 02/10/88 J.M. Colville 602-393-2679 (Continued) 6.
The number of fuel 'assemblies.
a)
In the core.
241 b)
Zn the spent fuel storage pool.
0 7 ~
8 ~
Licensed spent fuel storage capacity.
1329 Intended change in spent fuel storage capacity.
None Prospected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2006
<18 Months reloads and full core discharge capability).
II 0
r >1,,xe, h
'I
~N
't e
I f it/
~ll 4 lL j
k g
'\\
j"I j )
S 1
I}
d 3
I
~ )
~ 1 i) f g
~
g
)a J "I
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NQ.
UNIT DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 02/10/88 J.M. Colville 602-393-2679 January 1988 01/01 0000 01/22 1800 01/24 2100 01/31 2400 Unit in Mode 1 - Reactor Power 100k.
Power reduction to approximately 75'or CEAC Testing.
Reactor Power 100'.
Reactor Po~er 100'.
4 n
lI e
V l,
"II l
"P ~
~ 1C,.I a II
,l l
k1t 1
"f
~
I yl l'I
UHlT SllUTDOMNS AND POMER REDUCTIONS DOCKET NO:
UNIT NAME:
DATE:
COi'PLETED BY:
TELEPHONE:
50-529 PUNGS-2 3.M. Colville 602-393-2679 Duration No.
Date Type llours Reason Hethod of Shutting Down Reactor System<
Component>
LER NO.
Code Code Cause and Corrective Action to Prevent Recurrence 1
1/22 S
N/A N/A N/A N/A Power reduction to approx-imately 75X for CEAC testing.
1 F-Forced Reason:
2 S-Scheduled A-Equipment Failure (Explain) 8-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 4 License Examination F-Administrative G-Operational Error (Explain)
.fl-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20X or Greater in the Past 24 llours a-Otbr r (Fxnlnln) 4 Exh'ibit F - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit Il-Sama Source
I
NRC MONTHLY OPERATING REPORT OPERATING STATUS DOCKET NO.
50-530 UNIT NAME PVNGS-3 DATE 02/10/88 COMPLETED BY J.M. Colville TELEPHONE 602-393-2679 1.
2.
3.
4.
5 ~
6.7.
8.
9.
10.
Unit Name'.
Palo Verde Nuclear Generating Station~ Unit 3 Reporting Period:
January 1988 Licensed Thermal Power (MWt): 3800 Nameplate Rating (Gross MWe): 1403 Design Electrical Rating (Net MWe):
1270 Maximum Dependable Capacity (Gross MWe): 1303 Maximum Dependable Capacity (Net MWe):
1221 Xf Changes Occur "In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons.
Power Level to Which Restricted, If Any (Net MWe'):
NONE Reasons For Restrictions.
Xf Any.
This Month Yr.-to-Date Cumulative
'1.
'2.
13.
14.
15.
16
'7.
18.
19
'0.
'1.
22.
23.
"24.
Hours in Reporting Period Number of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)
Gross Electrical Energy Generated (MWH)
Net Electrical Energy Generated (MWH)
Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)
Unit Capacity Factor (Using DER Net)
Unit Forced Outage Rate Shutdowns Scheduled Over of Each):
168 168.0 168.0 626 362.
C 218 600.
~
213 599.
g
~
N/A N/A I'/A Next 6 Months 168 6216 168.0 168.0 1 113.9 C
0 788. 7 0
626 362.0 218 600.
g
~
213 599.
g
~
N/A N/A 870 549.
L L
583 900.
533 260.
N/A N/A N/A N/A N/A 0
0 (Type, Date, and Duration
- 25. If Shutdown At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior To Commercial Operation):
INITIALCRITICALITY
, INITXAL ELECTRXCITY COMMERCIAL OPERATION Forecast 07/87 07/87 09/87 Achieved 10/25/87 11/28/87 01/08/88
F t
NRC MONTHLY OPERATXNG REPORT COMMERCXAL OPERATION
'PERATING STATUS DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-530 PVNG5-3 02/10/88 J.M. Colville 602-393-2679 1.
2.
3 8 4 ~5.6.7.
8.
9.
10.
Unit Name.
Palo Verde Nuclear Generating Station~ Unit 3 Reporting Period:
January 1988 Licensed Thermal Power'MMt): 3800 Nameplate Rat,ing (Gross'Qe)':
1403 Design Electrical Rating (Net MVe):
1270 Maximum Dependable Capacity (Gross MMe): 1303 Maximum Dependable Capacity (Net We):
1221 If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons.
Power Level to which Restricted, If Any (Net MÃe):
NONE Reasons For Restrictions, If Any.
This Month Yr.-to-Date Cumulative 11.
12.
13
'4.
15.
16.
17.
18.
19.
20.
21.
22.
23-24.
25.
26.
Hours in Reporting Period 576 Number of Hours Reactor Has Critical 576.0 Reactor Reserve 5hutdown Hours 0
Hours Generator On-Line 576.0 Unit Reserve 5hutdown Hours 0
Gross Thermal Energy Generated (MMH) 2p 173@ 1 13 r Gross Electrical Energy Generated (MNH) 764~900.
Net Electrical Energy Generated (MVH) 724~533.
Unit 5ervice Factor 100.0E Unit Availability Factor 100.0r.
Unit Capacity Factor
'(Using MDC Net) l03,04 Unit Capacity Factor (Using DER Net)
- 99. Or.
Unit Forced Outage Rate 0.0r-Shutdowns Scheduled Over Next 6 Months of Each):
If Shutdown At End of Report Period, Es 576 576 576.0 576.0 0
5Z6.0 576.0 0
0 2 173 113 '
Z.
2 173 '113.0
/
C 764 900.
764 900.
g
~
724 533.
724 533.
g 100.0h 100.0h 100.0g.
100.0%
103. Oh 103.0A 99.0<
99.0r-
. 0.04 0.0z (Type, Date, and Duration timated Date of Startup:
Units in Test Status (Prior To Commercial Operation):
INITIALCRITICALITY INITIALELECTRICXTY COMMERCXAL OPERATION Forecast 07/87 07/87 09/87 Achieved 10/25/87 11/28/87 01/08/88
K It II 1t, 1
t C
I. D,.
I 1
1E I,
CC p ~
II tt I
C
AVERAGE DAILY UNIT POMER LEVEL DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3 02/10/88 J.M. Colville 602-393-2679 MONTH:
January 1988 DAY AVERAGE DAILY POMER LEVEL 1~276 2
268 1~246 1~242 1~234 1@271 1~269
,y 4>
~
4 ',,
I
'I L
4
~
k
'f Fc)
~~'
4'i'34
~."
l
" a ~
E o
AVERAGE DAILY UNIT POMER LEVEL DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE E
50-530 PVNGS-3 02/10/88 J. M. Colvi 1 1 e 602-393-2679 COMMERCIAL OPERATXON MONTH:
Januaz'g 1988 DAY AVERAGE DAILY 'PO'4)ER LEVEL DAY AVERAGE DAXLI POQER LEVEL 10 273 1 273 1 g 277 1 g 273 20 21 1~265 1 ~252 1~261 1~265
'2 13 14 1~265 14261 1&269 1~265 1~265 25 265 26 1 ~269 1~261 17 19 14 240 1~256 1~256 1~265 28 30 31 1 261 1~248 1~244 1~256
~
~
,'.pe;
~i I
'P Iv a
S' t
I
REFUELING INFORMATION DOCKET NO.
UNIT DATE COMPLETED BY TELEPHONE 50-530 PVNGS-3 02/10/88 J. M. Colvi 1le 602-393-2679 Scheduled date for next refueling shutdovn.
02/25/89 2.
Scheduled date for restart folloving refueling.
05/05/89 3.
Mill refueling or resumption or operation thereafter require a
Technical Specification change or other license amendment2 Not, Yet Determined 4lhat vill these be2 Not Yet, Determined 4 ~
Scheduled date for submitting proposed licensing action and supporting information.
Not Yet Determined Important Licensing considerations associated vith refueling, e.g.
nev or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel,
- design, nev,operating pr'ocedures.
6.
Not Yet, Determined The number of fuel assemblies.
a)
In the core.
241 b)
In the spent fuel storage pool.
0 7.
Licensed spent fuel storage capacity.
1329 Intended change in spent fuel storage capacity.
None 8.
f Progected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2007 (18 Months reloads and full core discharge capability).
'*IIt'
't
',-;,, p4 ><."
II, II4 I'I
. II ~
I' to 44
,I
- ~
I r C
I.
IKV*,
I k 4
~
I 4
~
Pd 4 EA,I II UPI, I, i" 4 ~
II XG if
~ Il-4".Q I
r e
<<C,:A Qa'I' 0,I
'I Jr 4,IN I'II44.',II P 4'P 4I I
+ C,g"i
"* II
~
~
e) '
I~'
'i,,
I III
$r
~
'\\I I
~,,"
I
~,
r I
~ 4 P
3g-
~, a,.
I i
+ f Il II I
<1
~
tk 4
~
I'l E A4 'I 4f'f '~C
~,
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
UNIT DATE UUNPLh'I'j U 8Y
'LELKYkfUNC 50-530 PVNGS-3 02/ 10/88 J
~ Pl ~
L' kv 3.lLe hVZ-4J4-44/J January 1988 01/01 0000 01/06 1710 01/07 2400 Unit in Mode 1 - Reactor Power 100'.
Started 100 Hour Marranty Run.
Unit in Mode 1 - Reactor Power 100'.
~
~
e
~
~
Ib t bfK
SUMMAR~F OPERATXNG EXPERlENCE FO HE MONTH DOCKET, NO-
, UNET DATE COMPLETED BY ThLPYHUNE 50-530 PVNGS-3 02/10/88 J.M. Colville 602-393-26/9 COMMERCIAL OPERATION January 1988 01/08 0001 01/10 2115 01/31 2400 Commercial Operation declared.
100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> completed for 41arranty Run.
Unit in Mode 1
Reactor Power 100'.
0 0
n II I'
1 Tf
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-530 PVNGS-3 2 10/88 J.M..Colville 602-393-2619 Method of Duration Shutting 3
System<
Component No.
Date Type
. Hours Reason Down Reactor LER NO.
Code Code 5
Cause and Corrective Action to Prevent Recurrence JANUARY No Unit Shutdowns or Power Reductions 1 F-Forced S-Scheduled 2 Reason:
A-Equipment Failure (Explain)
D-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Fxamination F-Administrative G-Operational Error (Explain)
.Il-Other (Explain)
Method:
1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Rcductiott of 20X or Grcatcr in the Post 24 Ilours tt-Other (ExnlttIn) 4 Exhibit F - Instructions for Preparation of Data Entry Shccts for Licensee Event Rcport (LER) File (NUREG 0161) 5 Exhibit ll-Same Source