ML20214D625
| ML20214D625 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/30/1987 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 192-00206-JGH-T, 192-206-JGH-T, NUDOCS 8705210402 | |
| Download: ML20214D625 (16) | |
Text
.
j NRC MONTHLY OPERATING REPORT 4
DOCKET NO.
@g-@gq_______
UNIT NAME PVNGS-1_
DATE ggfgZf@Z_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@gg-9@g-5@gg_
Ext._@52@____
QPERATING STATUS l '.
Unit Name: Pale _ Verde _Nuglear_ Generating _gtetiont_ Unit _1 2.
Reporting Period:_Agr11_19@Z___
3.
Licensed Thermal Power (MWt): @899 4.
Nameplate Rating (Gross MWe): 149@
5.
Design Electrical Rating (Not MWe):
igZ9 6.
Maximum Dependable Capacity (Gross MWe): 1@gg 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):
N O N_ E _ _ _ __
10.
Reasons For Restrictions, If Any: _
.--=- _
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
____Zgg___
___gg80
__19223___
12.
Number of Hours Reactor Was Critical
____Zgg___
___1ZZ8.@__
_Z41@@zZ__
13.
Reactor Reserve Shutdown Hours
_____g.g__
_O.0
______g.g_
14.
Hours Generator On-Line
___729.g__
___123g.8,_
___@949 4_
15.
Unit Reserve Shutdown 16.
Gross Thermal Energy
______Q.Q_
Hours
_____Q.Q__
O. O_ _
Generated (MWH) 21299t1Z@z
_@tgggt5953 g4 2212@@g t
17.
Gross Electrical Energy Generated (MWH)
__94@tggg
._gt992t@gg.
_S @l9 499 t
3 18.
Net Electrical Energy Generated (MWH)
_@2Zt88Q1@
8 g18 454 @
132@8 Z28 @
2 3
t t
3 19.
Unit Service Factor
__199.g3__
____@g.gx__
____@ggig_
20.
Unit Availability Factor
__1gg.Qx__
_@g.Qx__
____@@z1x_
21.
Unit Capacity Factor (Using MDC Net)
__1gg.1x__
_5@tZx__
59 7x 3
22.
Unit Capacity Factor (Using DER Net)
___9@.gx__
____Q@.6x_
____5Z.4x_
23.
Unit Forced Outage Rate
____O._Ox___
____49.Qx__
____g4 94_
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):_ _ _ _ _ _ _ _ _ - - _ _ -
Forecast Achieved INITIAL CRITICALITY
__gfgp__
_gfgpfg5_
INITIAL ELECTRICITY
__@fg5__
_@ fig /gg_
COMMERCIAL OPERATION 11/85 1/28/86 pt 8705210402 870430 I
PDR ADOCK 05000528 R
PDR k
l c
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __QQ-13g _
UNIT ____
_ P_ V_ N_ G_ S_ _ _1 _ _ _ _ _ _ _ _
DATE_ ___._____.__Qg[QZ48Z______==_
COMPLETED BY J.L _Hu11______.
3 TELEPHONE ___60_2_-9_ggg-53_0_0____
32 gg g
_ e r 1 1 _ i s s 7 _ __ _ __
59BIH*
^
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
_________1 256
= - - _ _ _ _ _ _ _ -
17 __
__------A2_6_0_______
1 A
2
_=.
_ _ _1 _2 _5 _2 _ _ _ _ _ _ _ _ _ _ _ _ _
18 _________1
_256 A
4 _-
___- __==
3
________12252 19 _ _
_ _ _12 2E 4______ - -- -
4 1-56_-
20 ___-===1z262_____________
1 2 5
- - - - _ _ _ _ _1 _2 _5 _6 _ _ _ _ _ _ _ _ _ _ _ _
21 ________1 2_6_0_
1 1 _
_=__= ___
6
________i g52 22 __
_1,gg1_____________
t 7
_ _ _ _ _ _ _ _ _1 _2 _5 6 23 _________1 26_0_____________
z
_=-
=
t _
e
________1,g4g 24
--- _1 218 4
_=________
=-
_ _ = _ _ _ = _ ___=_
9
=-
._==_z_2_5_6_____-
==
25 - _ = _ = = _1 0_4_7__ _ _ = = = -- - - - =
1 z_
10 _____-_-_1 256.====-
26 _________1 2_2_2_-
==_
z--
z-11 ________12260 27 ________12260 1 2 _ _ _ _ _ _ _ _ _1 _2 _5 _2 _ _ _ _ _ - -
28 --
_ _1 2_ _5 _1 _ _ = = = =
z A
13 _________1 26_4 29 _________1 255 A__
A==
_ = = - -
14 ________1 _26_4_____=-
3 0 _ _ __ _ _ _ _ _1 2 5_1_ _ __ _ = - - = - = =
L -
L-_
15 ____
-_3z-60__
_ _ = = - - -. _ _ -
31 _ _ _
2-
_==_____
-====_____
16 ___--_-__1 25.6 t-m
i REFUELING INFORMATION DOCKET NO.
50-528-
- UNIT PVNGg-1______
DATE
-99f9Zfg?_____
COMPLETED BY J.L _ Hull ____
g TELEPHONE
-@g2-9}2-g!QQ_
4
. ggt _6593____
1.
Scheduled date for next refueling shutdown.
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 these be?
Not Yet Determined 4.
Scheduled date for submitting proposed-licensing action and supporting information.'
-July 1, 1987-i i
5.
Important Licensing considerations ~ associated'with refueling,~
e.g.
new or different: fuel' design ~or supplier, unreviewed design or performance analysis methods,rsignificant changes ~inEfuel-design, new operating procedurea'.
j 1-a) Modification of'the CPCa'under~the CPC' Improvement. Program' (CIP) and the' Statistical Combination'of Uncertainties ~
(SCU) Program.'
b) Maximum peak pin fuel = enrichment will tun 4.05 w.*'U235.
c) The fuel-' vendor for the following next 5 reloads will be' Combustion Engineering.~
i f
7-,-
.y.._.-
.,.v._
,,,,.,,,.,,m,.
4
REFUELING INFORMATION DOCKET NO.-
50-528
[55G5_E "(([_~[
UNIT
_1 DATE ~ ' ~
05/07/87_-
+-
' COMPLETED ~BY' J L._ Hull;___
2 TELEPHONE 692-932-5399_
Egt _@59];__',
2 (Continued) 6.
The. number of' fuel anaemblies.
a)
In the core.-.
_241;___
b)
In the spent fuel storage pool. __ __ ;O 1____
7.
Licensed spent ~ fuel" storage capacity.~-_
1@29___
J Intended change:innspent fuel. storage capacity.
___Ngge___
l 8.
Pro 3ected date of'last refueling.that can be discharged to spent fuel storage pool' assuming'present capacity.
i 2002 (w/ annual reloads ~and full core discharge capability).
i J
l i
i i
4 e
4 4
l
l
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH i
DOCKET NO.
50-528' UNIT PVNGE-1______
COMPLETED.BY
~ 05/07/8Z_____
DATE-J L._Hu11____
3 TELEPHONE-
@gg-9@2-Q@gg_
Egtz_@}____ April __1987_ q 04/01 0000 Reactor Power at 100* 04/24 1951 Reactor Power at 85% due to surveillance testing for CEAs per 41ST-1SF01 04/26 1225 Reactor Power at 100% 04/30 -2400 Reactor Power at 100% i l i )
_. _ _. =.. 8, UNIT SHUTDOWNS AND POWER REDUCTIONS I DOCKET'NO: 50-s28' UNIT NAME: ONE 'DATE: 05-04-87 COMPLETED BY: Joy Hull TELEPHONE:- 932-5300 ext 6593 Method of Cause and Corrective-ration Shutting System Component Action to 1 2 3 4 5 No. Date Type ' -Hours Reason Down Reactor LER NO. Code Code Prevent. Recurrence NO UNIT SHUTDOWNS OR POWER REDUCTIONS FOR THE MO.THI 0F APRIL 3 t j t 3 P I 2 3 F-Forced g,,,,,, Method Exhibit F - Instructions S-Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licensee-for Preparation of Data B-Maintenance or Test-2-Manual Scras C-Refueling 3-Automatic Scram Event Report (LER) File. 4 A Regulatory Restriction 4-Continuation from (NUREC 0161) E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 201 5 . 7 xhibit h h ce C-Operational Error (Explain) or Creater in the H-Other (Explain) Past 24 Hours'. 9-Other (Evninin)'
NRC' MONTHLY OPERATING REPORT DOCKET NO. gg-239_______ UNIT-NAME
_S-2 ~_____
PVNG DATE g5f07/87 COMPLETED BY J L._Hu11_____ 2 TELEPHONE 602-932-5300 .c Est3=_g593_=== 4 OPERATING STAT _US -- -=- -
- i 1.
Unit Name: Polo-Verdg;Nugiggg_Ggggggting_gigtiggg_Mait;2 2. Reporting Period:~;Agg11;198Z_;o 3. Licensed Thermal. Power:(MWt-):^3999 7 2 4. Nameplate Rating:(Gross'MWe):51493"~" 1 5. Design Electrical Retingz(Not-MWe): 12ZQ: 1 6. Maximum Dependable Capacity"CGross'MWe): 1393 7. Maximum-Dependable Capacity"(Net'MWe):' 1331 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: _ _ _ - - - - - - _ = 9. Power Level to Which Restricted,__ __=====-- _NgNE_________ If Any (Net MWe): r 10. Reasons For Restrictions,"If'Any:~ This Month. Yr'.-to-Date' Cumulative 11. Hours in-Reporting Period-729___ ___2999____ ___ggZg___ 12. Number of Hours Reactor Was Critical - ____Zgazg_ ___1ggZ9__ ___g6aZ.8_ 13. Reactor Reserve Shutdown 1 Hours ~"~ ~~ _;;_;O- ___ 14. Hours Generator On-Line * ~~ -~~-697;5 _ _ _ _ _ _ _O ____ ____ O _ __ 1277.7 3544.7 15. Unit Reserve Shutdown' ~~~~~~~~~~ ~~~ ~~~~~~~~~~ Hours ' - ~;____g__;; _Q_____ _Q____ 16. Gross Thermal Energy Generated (MWH)
- -: 2iS2gt594.
_4 183 g99 12 4Z8 @96 t t g g 17. Gross Electrical Energy ? j Generated (MWH) .;;g93iggg. _1 469,599 _4 @88 gZg - - ; t t t i 18. Net Electrical Energy ? Generated (MWH)- '~~;_g4Qg652. _1 359t!Q63 _4 g9Zgi44 t g 19. Unit Service Factor - ~ 't"" _';;96. 94_ _ ___4 3 44_ __ _ ___65 94__ 1 3 20. Unit Availability Factor ~~~ m' 96 947 -- 44.44-65 '. 9s ~" 1 J 21. Unit Capacity Factor 1 (Using MDC Net) "'*"_';;95.64__ ___38. 4 4_ _ ___62 44__ 1 3 22. Unit Capacity Factor (Using DER Net) ___91 94__ ___36.94___ ___69 94__ 3 23. Unit Forced Outage Rate ____3.1*__ ___11.2*___andDuration ____9.94__ 24. Shutdowns Scheduled Over Next 6 Months-(Type, Date, of Each): l 25. If Shutdown At End of Report Period, Estimated Date of Startup:
===- - - = = = = = = - - - - - _ 26. Units in Test Status'(Prior'To-Commercial Operation): i ~ Forecast ~ Achieved INITIAL CRITICALITY ~~__gfgg__ _sfigfgg_~ i l INITIAL ELECTRICITY __gfg6__ _3/39/gg_ COMMERCIAL" OPERATION' ~ ^;11/8@;_
- 9fl9fgg_" ' '
l i C
' AVERAGE' DAILY UNIT POWER LEVEL DOCKET NO. Eg-ggg_______ UNIT PVNGS-2 DATE ggggZ/87 COMPLETED BY J_.L._ Hull TELEPHONE _6 0 _2 _ _9 3 2 - 5 3_ 0_ 0_ - = - Egt3_693g____ MONTH: _ April 1987_ DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 _--____1z2__7_1 17 __ .-_30 _=== ==-_ 2 2 ___--__1 _271 18 - - _ _ _ _ _ - _ 8 _1 3- =_====--- z 19 - _ _-_- _ _1 z 0_3_8_ -_ _ - = = _ - - - = - 3 _______1 275 1 4 _---- 12275 20 _ 11g6g_______
==
5 ---____1 z _ 7 5 21 _--. 4265_-__________-- 2 1 6 -_-_-- z__71 22 __ 12 . = -- z 2 6 5_ _ ----- _ _ _ __ _ _ 1 ___ __===____ 7 ______ z279 23 _---_-_1z265_-__---_---_-__ 1 - 8 _---_- z263 24 -= 1 -_ z269_ - - - - =_ =-__- 1 - = - - - - 9 ___--_ z_275 25 - _ - _ _ _ _ _1 2_ _1 9 1 1 _ _ _ _ = _ _ - _ = _ _ _ 10 ____--1z2_75 26 --______1z _14 0__--___ ___===--- 1 1 _ _ - - _ - _1 z 2 7 _1 _ _ - = 27'___--___1z_140 154 -28 _______~_1z144__________--__ 12 ____--_11 - _ _ - _ = = = - - = 13 1 279 ~~~" __-__- 2 9 _~ _ _ ___ _' _l ~z 14 0_ _ _ = = _ _ _ _ _-- __ -_-_-_ z 14 ---_--_1z _2 7_ 1 ~ 30 _____ " 1z136 ' 15 _-__-_112_83 31 16 _ ___--- _71. 4 ---=_ ,g
REFUELING INFORMATION DOCKET NO. 50-529____ UNIT PVNCE-2 DATE hh2hZf82____[ COMPLETED BY J L._ Hull ____ 2 TELEPHONE @O2-932-5300_ Ext _@@9@____ 4 z l. Scheduled date for next refueling shutdown. 02/20/88 4 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 supporting information. Not Yet Determined 1 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. i 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___' Intended change in spent fuel storage' capacity'. ___Ngge___ 8. Pro 3ected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity. 2003 (w/ annual reloads and full core discharge capability). l .t,
i
SUMMARY
OF OPERATING. EXPERIENCE'.FOR THE MONTH DOCKET NO. 50-529 UNIT PVNGE-2 _ ____, 1 DATE gg/07/gZ______ j COMPLETED BY J L _Hu11____ 2 2 -TELEPHONE $92-933-5399_ Egt _gggg____ t 2 April-1987 i i 04/01~ 0000 Ranctor Power 1004 04/16 1346 Reactor. Trips due to Hi LPD. Electrical maintenance was troubleshooting a ground cm 2E-PNB-D26. When CEAC #1 was-J re-energized, it generated lerge LPD penalty factors' j causing the trip. J [ 04/17 0622 Unit II Reactor Critical entered Mode 2 4 d 04/17 0934 Entered Mode 1 3 04/17 1215 Synchronized to Grid 1 04/25 1451 Began power reduction to 90*'due to the isolation of a low pressure feedwater heater train. caused by a tube leak. 04/25 1600 Reactor power 904 04/30 0000 Reactor Power at 904 4 1 4 't l t 1 i i t i i
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-529-UNIT NAME: WO
- ~
DATE: 05-04-87 4 COMPLETED BY: Joy Hull TELEPHONE: -932-5300 ext 6593 Method of Cause and Corrective. Duration Shutting ystem4 "P "*"'S Action to 3 2 3 No. Date Type -Hours Reason Down Reactor LER.NO. Code Code Prevent Recurrence 07 04-16 F 22.5 B 3 2-87-004 JC CPU Reactor trip due to Hi LPD.. Electrical maintenance _was troubleshooting a ground on 2E-PNB-D26. When CEAC'#1-was re-energized, it generated large LPD penalty factors-i causing the trip. Corrective action will include review of Class IE Instrument AC power supplies for their 4 specific effect on plant operation'with results of the. review factored into cperations and maintenance procedures. 4 'I '3 F-Firced Reason: Method: Exhibit F - Instructions 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 (NUREG 0161) E-Operator Training & License Examination Previnus Month F-Administrative 5-Reduction of 20% 5 Exhibit H-Same Source C-Operational Error (Explain) or Creater in the Il-Other (Explain) Past 24 Ilours 4-Orber (Erniain)
NRC MONTHLY OPERATING REPORT DOCKET NO. '50-530 UNIT NAME PVNGE-@_ DATE -99/9Z/8Z_ ___ COMPLETED BY J._L._ Hull ___ TELEPHONE @g2-233-9999_ Ext._gggg____ QPERATING__gTATUg 1. Unit Name: Palo_ Verde _Nuclogr_Generatigg_Qtgtiont_9 git _@ 2. Reporting Period: _Agg{l_lg@Z__ 3. Licensed Thermal Power (MWt): 380Q 4. Nameplate Rating (Gross MWe): 149@ 5. Design Electrical Rating (Not MWe): 12Z9 6. Maximum Dependable Capacity (Gross MWe): 1@9@ 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 Rastricted, If Any (Not MWe): _NQNE______ j 10. Reasons For Restrictions, If Any: ___ _ __ _=____________ This Month Yr.-to-Date Cumulative 11. Hours in Reporting Period ___Z29____ 88@____ 12. Number of Hours Reactor l Was Critical _____9____ _____9_____ _____O 13. Reactor Reserve Shutdown I Hours _____O_____ _____O_____. __-__O----- 14. Hours Generator On-Line _____O_____ _____O______ _ _ - - - - O 15. Unit Reserve Shutdown Hours O O O ~~ ~ ~~~~~~~~~~ 16. Gross Thermal Energy Generated (MWH) O _____O. _ __9____ 17. Gross Electrical Energy Generated (MWH) _____9____ _____9_____ ___=_0_ 18. Not Electrical Energy Generated (MWH) 19. Unit Service Factor __O____ 9_____ _____9____ _____Q_ __Q _____g____ 20. Unit Availability Factor _____Q_____ Q____= _____9____ 21. Unit Capacity Factor (Using MDC Net) _____g____ _____0_____ _____g____ 22. Unit Capacity Factor (Using DER Net) ______O_ _9_____ _____9____ 23. Unit Forced Outage Rate _____9____ _ __9_____ O
==_
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): Forecast Achieved INITIAL CRITICALITY _9Zf@Z__ INITIAL' ELECTRICITY ~07/87 COMMERCIAL OPERATION O9787~~ ~ ~ ~~ g.._., ,, ~. ~. g. r %.
'1 1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 99,129_______ UNIT PVNgg-g______ DATE ggfg7297_____ COMPLETED BY J._L._ Hull ___ TELEPHONE gg2-pg2-5ggg_ Egg __g}2g____ MONTH: _Agril__1987__ DAY AVERAGE DAILY POWER LEVEL. DAY AVERAGE DAILY POWER LEVEL 1 0 17 .. _ _ __ J O _ 2 0 18 __ O______________ 3 0 1 9 _-- --- = _ _ 0 _ _ _ _ _ _ _ - 4 0 20 _ __ O 5 0 21 O 6 _ _ 0_ _ 22 ..O - _ _ _ _ _ _ _ _ _. 7 __0 23 O_____ 8 0 24 __ _ ____ _ _ O_ 9 _O 25 O 10 __ 26 __ _______Q____ 0 11 -=- -0 27 0 ___ ____- . _ _ = - - - - 12 __ __ 0 28 _ 0 _ _ = _ _ _ - 13 __ o 29 ~_ O 14 - - = 0 _ = _ _ _ 30 ____- --0_________ = 15 __ 0 31 O____ _ ________ 16 __ O i l l
\\ ~ ~ + i G-6 3 .l 't-REFUELING'INFORNATION i DOCKET NO. '59:5}Q_______ UNIT- 'PVNGS;}______ DATE~ 95/07/87_ _ _ _ CONPLETED BY' J. L._ Hull ___ TELEPHONE-692-932-5399_ Ext _6593___ l. 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 ofzfuel> assemblies.- a) In the core. 241 b) In the spent fuel storage pool.'____ ~ 10 -~ - _;_ _ 7. Licensed spent fuel' storage capacitys ___1329__[" Intended change'in'apent'fuelEstorage capacity. _';;Nggg;__4 R 8. Pro 3ected-date of last refueling that.can be discharged to spent j fuel. storage pool' assuming present capacity. o 2003 (w/ annual reloads and full core ~ discharge capability). 4 1 i i i I 1 + u.
e' e
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH f DOCKET NO. .gg-ggg_______ UNIT .PVNQg-@______ DATE gggg7/87_____ COMPLETED BY J L._ Hull ____ 2 TELEPHONE- @gg-9@g-Q@gg_ Ent _@$2}____ z i 04/02 1834 Fuel Load Completed 04/09 1719 Entered Mode 5 i l l l
M. - Arizona Nuclear Power Project P.o. Box 52034
- PHOENIX, ARIZONA 85072-2034 192-00206-JGH/TRB May 12, 1987 NRC Document Control Desk U.S. Nuclear Regulatory Commission 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 ~ April Monthly Operating Report File: 87-024-404
Dear Sirs:
Attached please find the April,1987, 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 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 truly yours, A J. G. Haynes Vice President Nuclear Production JGH/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 L w ~}}