ML20215H438
| ML20215H438 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/31/1987 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 192-00190-JGH-T, 192-190-JGH-T, NUDOCS 8704200315 | |
| Download: ML20215H438 (18) | |
Text
c NRC MONTHLY OPERATING REPORT DOCKET NO.
5g-52@_______
UNIT NAME PVNGS-1______
DATE 94figf@Z_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@g2-932-5399_
Ext._@5@3____
gPERAIINg_SIAIU@
1.
Unit Name: Palg_ Verde _ Nuclear _Qenergting_@tgtignt_ Unit _1 2.
Reporting Period: March _19@7___
3.
Licensed Thermal Power (MWt): 3@gg 4.
Nameplate Rating (Gross MWe): 1493 5.
Design Electrical Rating (Net MWe):
12Zg 6.
Maximum Dependable Capacity (Gross MWe): 1393 7.
Maximum Dependable Capacity (Net MWe):
1221 6.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
9.
Power Level to Which Restricted, If Any (Net MWe):
_NgNE_________
10.
Reacons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
____Z49___
___21@g____
__192Z2___
12.
Number of Hours Reactor Was Critical
___@57.Z__
___195@.@__
_@t4<j@.Z__
13.
Reactor Reserve Shutdown Hours
_____g.g__
______g.g__
______g.g_
14.
Hours Generator On-Line
___@l@.9__
___199@.@__
___@22g.4_
15.
Unit Reserve Shutdown Hours
_____Q.g__
______9.g__
______g.g_
16.
Gross Thermal Energy 324 331.
22 21@t4Z4 Generated (MWH) 1 1@@l 757.
_33 t
t t
17.
Gross Electrical Energy Generated (MWH)
__@37t799
_1 144 599
_7t671 499 t
t 3
18.
Net Electrical Energy Generated (MWH)
__5@Z1@@5,
_ltg@gt@l3.
_Zt12gtS@g 19.
Unit Service Factor
___@2.93__
____4@.73__
____@g.@3_
20.
Unit Availability Factor
___@2.93__
____4@.73__
____@g
@3_
21.
Unit Capacity Factor (Using MDC Net)
___@4.Z3__
____4g.23__
____5@.@3_
22.
Unit Capacity Factor (Using DER Net)
___@2.23__
____3Q.73__
____54.@3_
23.
Unit Forced Outage Rate
___17.13__
____53.33__
____2@.g3_
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:
U'$~E~1n~ tee ~t~St$~~E~Ihr$or~iE~Uo~me~rc$$1 ~bper$ tion 5$~~~~~~
~~
~
26.
n t tu m
Forecast Achieved INITIAL CRITICALITY
__5(@5__
_5225fg5_
INITIAL ELECTRICITY
__g[g5__
_@flg/g5_
COMMERCIAL OPERATION
_11/95__
_1/2@fg@_
8704200315 870331
{DR ADOCK 05000528 1y PDR I
f
(
AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
__59-52e_________
U N I T _ _ _ _ _ _ _ _ P_ V_ N_G_ S_ _ _1_ _ _ _ _ _ _ _
COMPLETED BY J.L._ Hull ______
TELEPHONE _ _ _ 6 0_ 2_ _- 9_ 3 2_ _- 5_ 3_ 0_ 0_ _ _ _
l 59 NIM:
UgEgb_l@@Z____
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
____________9_____________
17 ________1 22e_____________
1 2
____________g_____________
18 ________1 212_____________
1 3
____________9_____________
19 ________1112e_____________
4
____________g_____________
20 ________1124g_____________
5
____________9_____________
21 ________1 249_____________
1 1
6
__________131_____________
22 ________1 299_____________
1 7
__________Z@g_____________
23 ________1 14g_____________
1 a
__________41g_____________
24 ________11g44_____________
9
__________435_____________
25 ________1122e_____________
10 __________6ke_____________
26 ________1,232_____________
11 __________2Z6_____________
27 ________1,223_____________
12 __________499_____________
28 ________1,25Z_____________
13 __________491_____________
29 ________1 25?_____________
1 14 __________Ee5_____________
30 ________1 24e_____________
1 15 ________11911_____________
31
________1,248_____________
16 ________1t1Ze_____________
a l
REFUELING INFORMATION k
DOCKET NO.
59-52@_______
UNIT PVNG@-1______
DATE 94/19/@7_____
COMPLETED BY J.L.
Hull
~
l TELEPHONE ggh3hhh[h[399_
Egt _@@23____
I i
1.
Scheduled date for next refueling shutdown.
1 09/26/87 2.
Scheduled date for restart following refueling.
12/15/87 3.
Will refueling or resumption or operation thereafter require a Technical Specification change or other license amendment?
Yes What will thene be?
Not Yet Determined 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 dealgn or supplier, unreviewed design or performance analysta 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 Uncertaintion (SCU) Program.
b) Maximum peak pin fuel enrichment will be 4.05 w % U235.
c) The fuel vendor for the following next 5 reloads will be Combuntion Engineering.
.s REFUELING INFORMATION DOCKET NO.
59-52@_______
UNIT pVNG@-1______
DATE 94/19/@7_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@g_2-932-5399_
Egt._@59@____
(Continued) 6.
The number of fuel assemblies.
a)
In the core.
____241____
b)
In the spent fuel storage pool.
______Q______
7.
Licensed spent fuel storage capacity.
___1329___
Intended change in opent fuel storage capacity.
___Ngge___
8.
Pro 3ected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2002 (w/ annual reloads and full core discharge capability).
4
-y
,--,_.-..m..
-..m 2
,.m r--r-
.-,.v.r.___w_.
-m.,-___,_,,r,
-,y-.-, -
7_
__n---,e,
,w
t
SUMMARY
OF OPERATING EXPERIEWCE FOR THE MONTH DOCKET NO.
59:52@_______
UNIT PVNGS;1______
DATE 94/1g/g7_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@g2;932:5399_
Ext._@52]____
MARCH 1987 03/01 0000 Reactor Mode 5 due to Maintenance Outage 03/01 1604 Entered Mode 4 03/03 0637 Entered Mode 3 03/04 1417 Reactor Critical, Entered Mode 2 03/04 2340 Entered Mode 1 03/05 1200 Entered Mode 2 Reactor Power '5%
03/06 0050 Reset Main Turbine 03/06 0231 Entered Mode 1 03/06 0517 Synchronized to Grid 0306 0550 Reactor Power 19%
03/06 1520 Turbine trip due to MSR high level 03/06 1640 Reset Main Turbine 03/06 1712 Resynchronized to Grid 03/06 2140 Commenced power increase to 100%
03/07 0516 Reactor power 100%
03/07 1103 Commenced power reduction to 40% due to condenser tube leak 03/07 1330 Reactor power at 40%
03/09 1620 Condenser tubos repaired 03/09 2210 Commenced increasing power 1
03/10 0524 Holding reactor power at approximaely 75%
03/10 1314 Commenced power reduction to 40% due to possible circulating water leak into hotwell 1
_ _ _ ~,.
L
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
gg-g_2g_______
UNIT PVNGD-1______
DATE 94figfgZ_____
COMPLETED BY J.L._ Hull ____
TELEPHONE gg2-932-9399_
Egt._@@@@____
MARCH 1987 Q3/10 1408 Reactor power at 50%
03/10 1430 Stabilized reactor power at 37%
03/10 1745 Reactor power less than 25%
03/11-1700 Power increasing, reactor power 40%
03/13 1346 Secured reactor power at 49%
03/14 1140 Commenced reactor power increase to 100% at approximately 10% per hour 03/14 1445 Reactor power 70%
03/15 0305 Reactor power at 80%
O3/15 1830 Increasing reactor power to 100%
03/17 0526 Reactor Power at 100%
03/23 1430 Commenced power reduction due to Chemistry resin problems, reactor power at 85%
03/23 2018 Reactor power at 68%
Cf3/24 0318 Reactor power at 85%
03/25 0328 Reactor power at 1004 03/26 2148 Reactor power decrease to 85% due to condensate demineralizers 03/27 0400 Reactor Power at 100%
03/31 Reactor power at 100%
'dNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NOz 50-528 UNIT NAME: ONE DATE: 04/10/87 COMPLETED BY: J.L. Hull TELEPHONE: 932-5300 ext 6593 Method of 1
Cause and Corrective Duration Shutting System Component Action to g
2 3
4 5
No.
Date Type
. Hours Reason Down Reactor LER NO.
Code Code Prevent Recurrence (CONTINUATION FROM FEBRUARY) 2 03/01 F 127.1 B
1 n/a n/a n/a Maintenance outage to repair steam generator tube leak.
3 03/07 F n/a A
5 n/a n/a n/a Repair Condenser t'ube leak.
4 03/10 F n/a A
5 n/a n/a n/a Repair Condenser tube leak.
l i
l h
I 4
I j
l I
2 3
F-Forced Reason:
Method:
Exhibit F - Instructions J
S-Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee j
C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREX: 0161)
))
E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%
5 Exhibit H-Same Source C-Operational Error (Explain) or Greater in the II-Other (Explain)
Past 24 Ilours 9-Other (Erniain)
-t NRC MONTHLY OPERATING REPORT DOCKET NO.
50-529 i
UNIT NAME
_P_V_NG5_25~~~~~~
DATE' 0 4 _/ 1 0_ / 8 7_------
-.L.- Hull COMPLETED BY J
TELEPHONE E552 52:5555-
-~9 E_ t__E_ 55_ 5-~ ~-
9PE86I1Ng_gI@IUg 1.
Unit Name: Palg_ Verde _ Nuclear _Qenerating_gtationt_ Unit _2 2.
Reporting Period: _ March _19Q7__
3.
Licensed Thermal Power (MWt): 3800 4.
Nameplate Rating (Gross MWe): 1493 5.
Design Electrical Rating (Not MWe):
1_279 6.
Maximum Dependable Capacity (Gross MWe): 1393 7.
Maximum Dependable Capacity (Not MWe):
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 (Net MWe):
_NgNE_________
10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
____744___
___21@g____
___4@5@___
12.
Number of Hours Reactor 5__
___gg34.4_
Was Critical
____42Z.__
____@44 1 E
13.
Reactor Reserve Shutdown Hours
_____g____
_____9_____
_____g____
14.
Hours Generator On-Line
____3@3.@_
____5gg.2__
___2@47.2, 15.
Unit Reserve Shutdown Hours
_____g____
_____g_____
_____9____
16.
Gross Thermal Energy 1 6
- L 54.892------
99 Generated (MWH) 843 2
- L 59 886.
L 81.---
L----
17.
Gross Electrical Energy Generated (MWH)
__27g12gg.
___5@Z15gg.
_3 495 @79 t
t 18.
Not Electrical Energy Generated (MWH)
__239 72@.
___599 @54.
_3 25@t492 3
t 1
19.
Unit Service Factor
___4@ 93__
___2@.93___
___@l.23__
20.
Unit Availability Factor
___4gt93__
___2@t93___
___@l 23__
t 21.
Unit Capacity Factor (Using MDC Net)
___2@.43,_
___19.33___
___57.33__
22.
Unit Capacity Factor (Using DER Net)
___25.43__
___1@.@3___
___55113__
23.
Unit Forced Outage Rate
___2ZtZ3__
___1gt43___
___11153__
24.
Shutdowns Scheduled Over Next 6 Montha (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):
a l
Forecast Achieved INITIAL CRITICALITY
__3fg6__
_4flegg@_
INITIAL ELECTRICITY
__@fgk__
_5/29fg@_
COMMERCIAL OPERATION
_11ggk__
_gfl9/0@_
s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-529 UNIT PV G52E~~~~~~
DATE 64716757~~~~~
COMPLETED BY J.L.
Hull 562 552 5565~
2 2
TELEPHONE 5_ s_ _E- ~ 5_55_ _5_-"_-
--_rc_--_--_7198_-
M O _N T _H :
Ma_ h DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
0 17 O
2 0
18 O
3 0
19 O
4 O
20 0
5 O
21 230 6
O 22 529 7
0 23 533 8
O 24 537 9
0 25 545 10 386 26 554 11 94 27 562 1 12 12 -_--------_0 28 ------- r--_0 13 0
29 ------- z279 1
14 483 30 ------- 1 95 1 0 15 695 31 ------- z250 1
16 _------ 6_5_0 1
k i
i d
A 4
h i
I i - -
.m
,t REFUELING INFORMATION DOCKET NO.
59:529_______
UNIT
. PVNGg;_2______
DATE 94/19/@7_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@g2;932-5399_
Ext._@593____
1.
Scheduled date for next refueling shutdown.
02/20/88 2.
Scheduled date for restart following refueling.
05/10/88 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 j
aupporting information.
Not Yet Determined 5.
Important Licensing considerationa associated with refueling, e.g.
new or different fuel design or supplier, unreviewed design or performance analysia methoda, significant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The number of fuel anaemblies, a)
In the core.
____241____
b)
In the apont fuel storage pool.
______g______
7.
Licensed opent fuel atorage capacity.
___1329___
i Intended change in apent fuel storage capacity.
___Ngne___
8.
Projected date of last refueling that can be discharged to spent
]
fuel storage pool assuming present capacity.
2003 (w/ annual reloads and full core diacharge capability).
i
i t.
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
50-529_______
UNIT PVNGS-2______
DATE 04/10/87 I
COMPLETED BY
}$[$[hh((((_~[
TELEPHONE 992-932-5399_
i Ext.,@593____
j MARCH 1987 03/01 0000 Unit 2 in Mode 5 due to Maintenance Outage i
03/05 0607 Entered Mode 4 03/05 2252 Entered Mode 3 03/09 163P' Reactor-Critical Entered Mode 2 03/09 2630
. Entered Mode 1 03/10 0118 Synchronized to Grid 03/10 0803 Started reducing power to Mode 3 for repair of condenser tube 03/10 1530 Reactor power 40%
i 03/11 0908 Tripped Main Turbine 03/11 0917 Entered Mode 2 i
l 03/11 0931 Entered Mode 3 O3/12 0650 Reactor Critical Mode 2 03/13 1117 Reactor power 34 03/13 1819 Entered Mode 1 03/13 2343 Synchronized to grid 1
1 03/14 0224 Reactor power 19x assending approximately 10% per hour 03/14 2340 Reactor power 724 i
03/15 0922 Began power reduction due to condenser tube leak reducing down to 40% power 03/15 1045 Stabilized at 404 power 03/16 0915 Commenced raining reactor power 1
j 03/16 1030 Reactor power 50%
i 03/16 2040 Commenced power decrease to 40N from 90% due to condenser tube leak.
4' 03/16 2112 Reactor 70%
i
t
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
99-929_______
UNIT PVNGg-2______
DATE 94flgggZ_____
COMPLETED BY J.L._ Hull ____
TELEPHONE gg_2-932-93g9_
Egt._gggg____
MARCH 1987 03/16 2148 Reactor Power 40%
03/16 2330 Commenced power decrease due to condenser tube leak 03/17 0014 Entered Mode 3 03/20 1515 Reactor Critical, Mode 2 03/20 1815 Entered Mode 1 03/21 0431 Synchronized to Grid 03/21 0610 Reactor power 20%
03/22 0848 Reactor power 48%
03/28 1420 Reactor power 100%
03/30 1613 Reduced reactor power to 65%, due to feedwater pump maintenance 03/31 0456 Reactor power 85%
03/31 2329 Reactor power 100%
l n..
-...~.
UNIT SHIRDOWNS AND POWER REDUCTIONS DOCKET NO: 50-529 UNIT NAME: Th'O DATE: 04/10/87 COMPLETED BY: J.L. Hull TELEPHONE: 932-5300 ext 6593 Method of Cause and Corrective Duration Shutting System Component Action to y
2 3
4 5
No.
Date Type IIours Reason Down Reactor LER NO.
Code Code Prevent Recurrence (CONTINUED FROM FEBRUARY) 1 03/01 S
217.4 B
1-n/a n/a n/a Planned Maintenance Outage
{
2 03/11 F
62.6 A
1 n/a n/a n/a Repair of Condenser Tube Leak.
3.
03/17 F
100.4 A
1 n/a n/a n/a Repair of Condenser Tube Leak.
1 4
03/14 F
n/a A
5 n/a n/a n/a Repair of Condenser Tube Leak.-
l 5.
03/16 F
n/a A
5 n/a n/a n/a Repair of Condenser Tube Leak.
6 03/30 F
n/a A
5 n/a n/a n/a Repair of Feedwater Pump l
l I
2 3
' Exhibit F - Instructions F-Forced Reason:
Method:
S-Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREC 0161)
]
E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%
5 Exhibit H-Same Source G-Operational Error (Explain) or Creater in the Il-Other (Explain)
Past 24 Ilours 4-Ot tier (Evnlain) e
e1 0
NRC MONTHLY OPERATING REPORT DOCKET NO.
59-539_______
UNIT NAME PVNGS__3__---_
DATE 0_ 4_ / _1 0 _/ _8 7 _ _ _ _ _
COMPLETED BY J.
L.
Hull 562 552 5566~
2 2
TELEPHONE Est_ 5555~~~~
O_ P _E _R _A T _I N G _ S_ T_ _A T_ _U S_
1.
Unit Name: Palg_Verdg_Nuglegr_ Generating _Statignt_ Unit _3 2.
Reporting Period: _Margh_19@Z__
3.
Licensed Thermal Power (MWt): 3@gg 4.
Nameplate Rating (Gross MWe): 1493 5.
Design Electrical Rating (Net MWe):
1229 6.
Maximum Dependable Capacity (Gross MWe): 1393 7.
Maximum Dependaole Capacity (Net MWe):
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 (Net MWe):
_NQNE_________
10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
___1gg____
___1ge_____
___199____
12.
Number of Hours Reacter Was Critical
_____g____
_____g_____
_____g____
13.
Reactor Reserve Shutdown Hours
~~~~~O
~~~~~O
~~--~O 14.
Houro Generator On-Line
--___6~~~~
_-___5__-~---
_____5__~~-~
15.
Unit Reserve Shutdown Hours
_____g____
_____g_____
_____Q____
16.
Groan Thermal Energy Generated (MWH)
_____g____
_____Q_____
_____g____
17.
Gross Electrical Energy Generated (MWH)
_____g____
_____g_____
_____g____
18.
Net Electrical Energy Generated (MWH)
_____g____
_____g_____
_____g____
19.
Unit Service Factor
_____g____
_____Q_____
_____Q____
20.
Unit Availability Factor
_____g____
_____g_____
_____g____
21.
Unit Capacity Factor (Uning MDC Net)
_____g____
_____g_____
_____g____
22.
Unit Capacity Factor (Using DER Net)
_____g____
_____g_____
_____g____
23.
Unit Forced Outage Rate
_____g____
_____g_____
_____Q____
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): _______________________________________________________
25.
If Shutdown At End of Reoort Period, Estimated Date of Startup:
26.
Unita~~ In~T$$t"5 t$ tu A~IPrIS~r ~io~US$ $$~rci $I 6~per$ tionii ~ ~ ~ ~~ ~~ ~~~~ ~
~
~
Forecast Achieved INITIAL CRITICALITY
~07/87 INITIAL ELECTRICITY
_6_3__/8_E__~~
~~~~~~~~~
09/87 COMMERCIAL OPERATION
,e 1 o
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-530 UNIT PV U525~~~~~~
DATE 04/10/87
.-Hull------
COMPLETED BY J.
L TELEPHONE 552-955 5555-5_ E_ - 5 5 5_ 5 _- - - -
MONTH:
March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
__--_-_--_0__---_-____-___
17 -_---__ -__0_--_-----_-___-
2 0
18 ---___-__-_O_____---_-_-__
O 3
0 19 --------------------------
er 4
0---.-------------
20 --------------------------
0 5
O 21 0
0 6
0 22 --------------------------
7 O
23 0
8 O
24 --------------------------
O 0
9 O
25 --------------------------
O 10 __---_---
0-------
26 ---------.-----------------
11 0
27 O
O 12 0
28 ----------- --------------
13 0
29 ----..---------------------
O 14 0
30 --------------------------
0 15 0
31 0
16 _-------- 0 I
4
.c>
REFUELING INFORMATION DOCKET NO.
59-539_______
UNIT PVNGS-3______
DATE 94/19/g7_____
COMPLETED BY J._L._ Hull ___
TELEPHONE gg2-932-5399_
Ext._@S9@____
1.
Scheduled date for next refueling shutdown.
02/1989 2.
Scheduled date for restart following refueling.
04/1989 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 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.
____241____
b)
In the spent fuel storage pool.
______g______
7.
Licensed spent fuel storage capacity.
___1329___
Intanded change in spent fuel storage capacity.
___Noge___
8.
Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2003 (w/ annual reloads and full corc' discharge capability).
i
a s 9
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
99-939_______
UNIT PVNG@-g______
DATE 94/19/g7_____
COMPLETED BY J.L._ Hull ____
TELEPHONE gg2-932-gggg_
Egt3_@ggg____
03/25 0000 Unit 3 Low Power 5% License granted 03/28 1809 Commenced loading Fuel 03/28 1840 Entered Mode 6
./
Arizona Nuclear Power Project P O. box 52034 e PHOENIX, ARIZONA 85072-2034 192-00190-JGII/TRB April 13, 1987 NRC Document Control Desk U.S. Nuclear Regulatory Comission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN 50-528 License Nos. NPF-41 STN 50-529 NPF-51 STN 50-530 NPF-65 March Monthly Operating Report File: 87-024-404
Dear Sirs:
Attached please find the March, 1987, Monthly Operating Reports prepared and submitted pursuant to Specification 6.9.1.6 of Appendix (Technical Specifications) to the Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Operating 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.
If you have any questions, please contact me.
Very tru y yours, 6
J. G. Ilaynes Vice President Nuclear Production JGil/TRB/cid cc:
O. M. DeMichele (all w/a)
E. E. Van Brunt, Jr.
J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr J. A. Amenta INPO Records Center b
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