ML20235T846
| ML20235T846 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/30/1987 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 192-00246-JGH-T, 192-246-JGH-T, NUDOCS 8707220286 | |
| Download: ML20235T846 (16) | |
Text
__. _ _ _ - _
NRC MONTHLY OPERATING REPORT DOCKET NO.
59-52@_______
1 UNIT NAME PVNG@-1______
j DATE 07/09_/87______
1 1
-_-_-Hull
~
i COMPLETED BY J.L.
_552 579- ---
502 3 __2 2
TELEPHONE OP_ERATING-- ----_-----_U_S STAT -
1 1
1.
Unit Name: Pgig_ Verde _Nuglegr_Geneggting_@tgtignt_ Unit I l
2.
Reporting Period: _ June _19@7 j
3.
Licensed Thermal Power (MWt): @@gg 4.
Nameplate Rating (Gross MWe): 1493 5.
Design Electrical Rating (Net MWe):
12Z9 6.
Maximum Dependable Capacity (Gross MWe): 1393 7.
Maximum Dependable 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_________
l 10.
Reasons For Restrictions, If Any:
l t
This Month Yr.-to-Date Cumulative i
11.
Hours in Reporting Period
___Z29____
___4344____
__1245@___
I 12.
Number of Hours Reactor i
Was Critical
___@@@.g__
__@t154.7__
_@tS42.@__
13.
Reactor Reserve Shutdown Hours
_____g.Q__
______Q.g__
______g.g_
14.
Houra Generator On-Line
___@@5.2__
__3 992
__@t39@.9_
1 t
15.
Unit Reserve Shutdown l
Hours
_____g.Q__
______Q.g__
______Q.Q_
j 16.
Gross Thermal Energy I
Generated (MWH) 2 3@7 tg32 @4@t 29 924 7@9
)
t t9@l.
11 t
1 t
17.
Gross Electrical Energy l
Generated (MWH)
__@29 499
_3t@35 799 19t 3@2 @gg 3
1 t
18.
Net Electrical Energy I
Generated (MWH)
_7@l t1@5.Q
@t@g4,935.@
9t@@4 S91.@
t 19.
Unit Service Factor
___92.43__
____71.23__
____@@.73_
l 20.
Unit Availability Factor
___92.43__
____71.23__
____@@.73_
21.
Unit Capacity Factor (Using MDC Net)
___@@.93__
____@@.93__
____@3.53, 22.
Unit Capacity Factor (Using DER Net)
___@5.43__
____@5 33__
____@l.13_
t 23.
Unit Forced Outage Rate
____7.@h__
____2@.@$__
____21.@3_
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Scheduled----------------_r fo_-next_ refueling- - - _ - - - - - - - - _ s_ h u t _d o w n _- 9 / 1 _2 _/ 8 7 _ _ _ - -
date EMEatigg_gf_rgfygligg_shytdgyg_appgggigatgly_@@_dgys___
25.
If Shutdown At End of Report Period, Estimated Date of Startup:
July _2gt_1@g2____________________________________________________
26.
Units in Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 5/85 5/25/85 INITIAL ELECTRICITY
~~62@@[~
~_@2[02g@[
l COMMERCIAL OPERATION
- - - - _8 5_ _ _
_ _1 _/ 2 8 _/ 8 6_ -
11/
l 8707220286 870630 ADDCK 05000gg8 J{ pyh DR I(l
l l'
AVERAGE DAILY' UNIT POWER LEVEL l
1 DOCKET NO. ~~50-528 U N I T _ - _ _ _ - _ _ P V s_ G_ 5_ 2 5 ~ ~ ~ ~ ~
DATE 07/09/87-_--------
CO M PLE YED B Y ~J_7_ L_ _5 ~E_ u_1_ _5'_
~
TELEPHONE' 602-393-2679 l
MONTH:' ------_1987_
June DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
1 232
.17 _-------1,255 l
2
__14 18 --------_1z_255 6
l l
3
_ 1 47-----------__--
19 -------- x255 1 2 1
1 4
1243 20 - _ - - - - - - _1x255 1
5
_----_--_1t247 21 __------ z2_47 1
6 1 247 22 --------
z247-_--------------
1 z----_------_-_--
7 x247_---__--------
23 - - - - - _ _ _ _1 x 2 5 _1 1 --
8
t_251 24 _---__--1z247_------------
1 l"
9 1_5S--------------
25 -------- z2_51 1 2 1
10 1 255 2 6 _ _ _ _ _ _ _ _ _1 _. _1 9 7_ - - _ _ _ _ _ _ _ _ _ _ _
r--_____-_-_--___
11 - - _ - - _ - - _1 z _2 _4 _7 _ - - _ - - - - - - _ - -
27 _-------1 z _0_ _9_-
0 12 -------- x25_1 28 - - - - _ _ - - - _ 8 6_ 8_ _ _ _ _ _ _ _ _ _ _ - - _
1 1
13 - - - -.- - - - _1z251__-----------
29 0
l l
14 --------1 251 30 --_--_--_-_0_-____________
_z----------------
15 - - - _ _ _ - _ _1 75 ta-1 31 0
l l
16 -------- r-_5 1 25 ------_----___
REFUELING INFORMATION l~
1 1
DOCKET NO.
Sg 52g_______
j
' UNIT-PVNG@-1______
DATE 97/99f@7_____
COMPLETED BY J.L._ Hull ____
TELEPHONE
@g2-393-2@79, 1.
Scheduled date for next refueling shutdown.
(
09/12/87 2.
Scheduled date for restart following refueling.
11/20/87 3.
Will refueling or resumption or operation thereafter require a l
Technical Specification change or,other: license amendment?.
l t
Yes j
l
\\
\\
Required Technical Specifications are as follows.
5.3.1, 3/4.1.1.2, 3/4.1.1.3, 3/4.2.8, 3/4.1.3.1, 3/4.3.1, 3/4.1.3.6, 3/4.3.1, 2.1.1, 3/4.2.5, 3/4.2.1, 3/4.2.4, 3/.4.2.7, J
3/4.3.2 i
i 4.
Scheduled date for. submitting proposed licensing action and j
supporting information.
3 July 1,
1987 5.
Important Licensing considerations associated wIth refueling, e.g.
new or different fuel design or supplier, unreviewed design er 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 will be 4.05 w P. U235.
c) The fuel vendor for the following'next.5 reloads will be Combustion Engineering.
l l
I J
i a
I REFUELING INFORMATION j
DOCKET NO.
59-52@_______
i UNIT
_P _V _N _G _S _ _1 _ _ _ _ _ _
DATE 9?fg9f@Z_____
COMPLETED BY J.L.
Hull TELEPHONE hgh[~3hj3hh h~
)
1 f
(Continued) 1
.i 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___
{
'i Intended change in spent fuel storage capacity.
___None___
1 l
J 8.
Projected date of last refueling that can be discharged to spent H
fuel storage pool assuming present capacity.
2006 (18 Months reloads and full core discharge capability).
l 1
i 1
1 1
i l
1 l
u 1
)
l
.l 1
1 i
a a
SUMMARY
-OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
59-52g_______
UNIT PVNGS-1______
DATE 92/99/@Z_____
COMPLETED BY.
.J.L._ Hull ____
TELEPHONE
@g2-393-2@Z9_
Jung_19gz 06/01 0054 Synchronized Main. Turbine to Grid 06/01
.1255 Reactor power at 40N 106/02 1818 Reactor Power at 70%
l 06/03 0347 Reactor Power at 100%
l testing 06/26 2035 Reactor power reduced to 80% due to scheduled 06/28 1700 Reactor Power at 100%
06/28 1957 Following a power reduction for CEA/JEAC testing a major pipe rupture occurred on the circulating water ayatem.
l Subsequent review has determined that the root.cause of the event, circulating water line rupture, was that condenser circulating water outlet valve CWN-HV-10 failed closed.
06/30 Unit I Mode 3 l
- N / L.
rt r 1 g d at qt aas 0V7 0
5P0J 6 r
r n
em e
l h o onu mi r
nst utl C oc ot aob ac c
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I 1
. g NRC MONTHLY OPERATING REPORT l
DOCKET NO.
59-@29_______
j i
UNIT NAME
_P _V N _G S _- 2_ _ _ _ _ _ _
\\
DATE 0_ 7 _/ 0 9 _/ 8 7 _ _ _ _ _.
i
_\\
COMPLETED BY J.L._ Hull ____
TELEPHONE 6 0_ _2 _- 3 _9 _3 _- 2 6 7 9 _
O_ P_ E R _A T _I N _G _ S _T _A _T _U S_.
1 1.
Unit Name: Palo Verde Nuclear Generatina Station Unit 2 l
~~
~~~~~~~~~~~~~~~~~~~~~ ~~~~~~~
2.
R e p o r t i n g P e r i o' d i ~ d u[ n[ e[ [ _1 h @ Z 3.
Licensed Thermal Power (MWt):
_3 _8 0_ 0 l
1 4.
Nameplate Rating (Gross MWe): 1493 5.
Design Electrical Rating.(Net MWe):
'1279 6.
Maximum Dependable Capacity (Gross MWe): 1393 1
l 7
Maximum Dependable Capacity (Not MWe):
1221
)
8.
If Changes Occur In Capacity Ratings (Items' Number.3 Through 7)
)
Since Last Report, Give Reasons:
I I
\\
9.
Power Level to Which Restricted, If Any (Net MWe):
_NQNE_________
l 10. -
Reasons For Restrictions. If Any:
This Month Yr.-to-Date Cumulative l
i 1
11.
Hours in Reporting Period
___Z29____
.___ggg4____
___@899___
{
12.
Number of Hours Reactor j
l Was Critical
_ _ _ 6_ 9_ 1 _. _1 _ _
___2_6_5_9__.3___
_ _ _ 4_ 9_ 4_ 9_ _. 2_ _
i 13.
Reactor Reserve Shutdown 1
I Hours O
O O
14.
Hours Generator On-Line
~ ~ ~5_5_4_ _75_ ~ ~__
~ ~ ~ 5_ 5_ 5_ _7 5_ _~ ~
___4_5_55_75_~__
~~~
___2_
15.
Unit Reserve Shutdown Hours
_____Q____
_____Q_____
_____g____
1 16.
Gross Thermal Energy Generated (MWH) 2 3Zgt4Zg.
_@cZZ1t4Z9.
12tg@@t4@5 t
17.
Gross Electrical Energy l
._3 g71 tigg.
_S 999t279 l
Generated (MWH)
__@29 @gg.
t t
t 18.
Net Electrical Energy
)
i Generated (MWH)
_ _7_7_8_ L _4_2_ _.
2
_2_ L _5_6_ L _8_5_ _.
8 7
_ 5_ L _ 0_ 3_ L _ 2_ 3 1
6 6 _
y 19.
Unit Service Factor
___92.3%__
___5@.7%___
___Zg.53__
- 20. - Unit Availability Factor
_ _ _ 9_ 2_ _. 3_ %_ _ _
_ _ _ 5_ 8_ _. 7_ %_ _ _ _
_ _ _ 7_ 0_ _. 5_ %_ _ _
j 21.
Unit Capacity Factor
]
\\
_ _ _ 8_ 8_ _. 5_ %_ _ _
_ _ _ 5_ 3_ _. 9_ %_ _ _ _
___6_7__._1%___
(Usino MDC Net) l 22.
Unit Capacity Factor l
(Using DER Net)
___@5.1%__
___51.@3___
___@4.53__
23.
Unit Forced Outage Rate
____Z.Z3__
.___12.13___
___19.@g__
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:
l 26.
Units in Test Status (Prior To Commercial Operation):
1 I
o l
1 Forecast Achieved INITIAL CRITICALITY
__3f@@__
_4f1@f@@_
INITIAL ELECTRICITY
__@f@@__
_5f29f@@_
COMMERCIAL OPERATION
_11f@@__
_9fl9f@@_
j l
t l
l l
l i
AVERAGE' DAILY UNIT POWER LEVEL J
i l
DOCKET NO.
50-529
--_NG5_~2_-_--_~~~~~~
i UNIT PV -_ _
DATE.
0 7 / 0 _9 _/ 8 7 i
i COMPLETED BY
_J_._L_.- - _ _l _l _ _ _ _
1 Hu I
TELEPHONE 6_ _0 2_ _- 3_9_3_- 2_67 9_---
' MONTH:
J_ _u n e_ _19_ _87 DAY AVERAGE' DAILY POWER LEVEL DAY' AVERAGE' DAILY POWER LEVEL-
_- L 67_--_--_--____
1 2--
______ t 6_3___________-__-
17 1
1 2_
z_6_32_ --_ __--_-_----
18 __-_---_1z255___________---
2
_ - _ _ _ _ _1 z_63_'___----_-_-___
19 z-_59__________---_
1 2 -
1 2--
3 i
z2_59_------_______-
1 4
- - _ - _ _ _ _ 6_ _6 7_ _ - - - _ _ _ _ _ _ _ _ _ _ _
20 1
i 1
z_6_3__----________
5 0
21 1
2_
i i
I 6
-____-__46_2_____--_---__--
22
,259_____--__-____
i 1 ---
j I
7
_----_---_9__-_---_-______
23 ______-_13255----____________
5-l 8
_ _ _ - - - _ _ 6_ 7_ 6 _ _ _ - - _ _ - - _ - _ _ _ -
24 1
2_
2_6_3_________--___
1 I
1_59_--___________
l 9
____85__3____________-__
25 ________1 2--
j i
1 59______________
l 10 _ _ --_ _ - _' 9_ _9 5 26 1
2--
i 11
_1z _2 5_9_--_-__-_____---
27 __----__1z2_47_______-______
28 _______1 059______________
12 ______1,263_______________
2 l
z_5_5____---__--_---
29 _______1z259 2_
13 ____--_1 z_5_9_________--____
-30
______-_1z 2_ _4 7_ _ _ _ - _ _ _ _ _ _ _ _ _ _
2-14 _---_-1 15 _-----_1r259____--____---__
31 --------_0_--____-_-_____-_
t z_63____--_______--
2_-
16 ______1 I
1,-
i l
4 1
REFUELING INFORMATION l
DOCKET NO.
50-529__;____
)
UNIT pVNGS-2______
j DATE 07/09/87 i
COMPLETED BY
}$h[~hh(((([~
TELEPHONE 602-393-2679, i
i 1.
Scheduled date for next refueling shutdown.
02/21/88 2.
Scheduled date for restart following refueling.
04/30/88
- l 3.
Will refueling or resumption or operation thereafter require a-l Technical Specification change or other license amendment?
Not Yet Determined What will these be?
Not Yet Determined l
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
)
i 1
6.
The number of fuel assemblies.
]
a)
In the core. ____241____
]
i b)
In the spent fuel storage pool.
______0______
I 7.
Licensed spent fuel storage capacity.
___1329___
Intended change in spent fuel storage capacity.
___Nggg___
1 8.
pro;octed date of last refueling that-can be discharged to spent.
)
fuel storage pool assuming present capacity.
i l
2006 (18 Months reloads and full core discharge capability).
i
v L.
i
SUMMARY
OF OPERATING. EXPERIENCE FOR THE MONTH DOCKET NO.
59-529_______
UNIT PVNGS-2______
DATE-92/99/@Z_____
COMPLETED BY-1J.L._ Hull ____
TELEPHONE
@92-393:2@Z9_
JMDe_19g?
06/01 0000 Reactor Power 100%
06/04 1259 Reactor trip on low' steam generator level.
'The low level was the result of sporadic.Feedwater Control-System j
output.
.A digital voltmeter on the test panel for'the j
Feedwater Control System cabinet was being used to check' l
control signal voltages.
Two of the pushbuttons for I
separate variables were inadvertently pushed in at the same time.
The interlock that would have normally only i
l allowed one button to be pushed at a time failed.
The I
two buttons pushed in caused a sporadic-control signal from the FWCS to the system valves.
level oscillations resulted and led to the trip.
06/05 1755 Reactor critical Mode 2 06/05 2222 Entered Mode 1 06/06 0400 Synchronized to Grid 06/06 0903 Reactor power 19%
1 06/07 0059 Commencing power reduction from 89% due to excessive EHC leak on main control valve, tripped main trubine.
1 06/07 0125 Entered Mode 2 06/07 0246 Entered Mode 1 06/07 1721 Synchronized to Grid l
l 06/08 1400 Reactor Power 65%
^
1 06/10 1740 Reactor Power 100%
l i
06/30 Reactor Power 100%
l
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FS I
NRC MONTHLY OPERATING REPORT DOCKET NO.
59-5gg_______
-UNIT NAME PyNGg-@______
DATE 9?fg9/gZ_____
COMPLETED BY J.L._ Hull ____
TELEPHONE 602 _39__3_-2_679_
OPERATING STATUS 1.
Unit Name: Palg_yerde_Nuclegr_Generatigg_gtatignt_ Unit _@
2.
Reporting Period: June _19@7 3.
Licensed Thermal Power (MWt): gggg 4.
Nameplate Rating-(Gross MWe): 149@
l 5.
Design Electrical Rating (Net MWe):
1229 6.
Maximum Dependable Capacity (Gross MWe): Iggg 7
Maximum Dependable Capacity-(Net MWe):
1231 l
8.
If Changes Occur In Capacity Ratings (Items Number.3 Through 7)
Since Last Report, Give Reasons:
l 9.
Power Level to Which Restricted, If Any (Net MWe):
NONE 10.
Reasons For Restrictions, If Any:
l This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
___Z29____
___g252____
___2g52___
12.
Number of Hours Reactor Was Critical
_____g____
_____Q_____
_____g____
l 13.
Reactor Reserve Shutdown l
Hours O
O O
l 14.
Hours Generator On-Line
_____g____
_____g_____
_____Q____
15.
Unit Reserve Shutdown l
Hours
_____g____
_____g_____
_____g____
16.
Gross Thermal Energy Generated (MWH)
O O
O l
17.
Gross Electrical Energy Generated (MWH)
_____Q____
_____g_____
_____g____
18.
Net Electrical Energy Generated (MWH)
_____g____
_____Q_____
_____g____
19.
Unit Service Factor
_____g____
_____9_____
_____Q____
20.
Unit Availability Factor
_____Q____
_____g_____
_____g____
21.
Unit Cspacity Factor (Using MDC Net)
_____g____
_____g_____
_____g____
22.
Unit Capacity Factor (Using DER Net)
_____9____
_____Q_____
_____g____
23.
Unit Forced Outage Rate
_____9____
_____g_____
_____g____
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.
UnitA~5n~EE$t~StEtuS~iPrIo~r~To CommercIE5~b~pEr$ tion 5I'~~~~~~~~~~~
~
~~
~
Forecast Achieved INITIAL CRITICALITY 07/87
~62~g!((
[~~_~~~[~[
INITIAL ELECTRICITY f
COMMERCIAL OPERATION
_g9f82__
m l c 1
l AVERAGE DAILY UNIT POWER LEVEL
\\
I l
DOCKET NO.
50-530 UNIT P V _ G _5_2 5_~ ~ ~ ~ ~
DATE 0 7 _/ 0 _9 _/ _8 7 _ _ _ _ _
COMPLETED BY J.L.
Hull TELEPHONE 50__2_-5_5525_5_~/_5_~
i M_O__NT__H:
J u _n e_ _ _1_987 l
l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
1
___________0_______________
17 ___________O_'_____________
2
__________0_________
18 ___________O______________
3
__________0________________
19 ___________0___-__________.
4
__________0________________
2 0 _._ _ _ _ _ _ _ _ _ _ O_ _ _ _ _ _ _ _ _ _ _ _ _ _ _
5
__________0_______________
21
__________0_______________
6
__________0_______________
22 ___________0______________
7
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23 ___________0_________.._____
8
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24 _____._____.O.______________
9
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23 ___________0______________
10 ________..__0_______________
26 _________ _O______________
11 __________0_______________
27 ___________O_______________
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1 12 _________ 0_______________
28 ___________0_______________
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29 ___________O_______________
14 ___________0________
30 ___________0_______________
15 ___________0_______________
31 ____________0______________
16 __________O________________
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1 I
l REFUELING INFORMATION 1
DOCKET NO.
50-530_______
UNIT PVNG@-@_,____
DATE
_0 _7 _/ 0_ _9 _/ 8 7 _ _ _ _ _
f 4
COMPLETED BY J.L._ Hull ____
j TELEPHONE
@O2-@93-2@79_
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.1 1.
Scheduled date for next refueling shutdown.
I
.02/25/89 2.
Scheduled date for restart following refueling.
05/05/89 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..______0______
7.
Licensed spent fuel storage capacity.
___1329___.
1 Intended change in spent fuel storage capacity.
___None___
8.
Pro]ected 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).
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH x
DOCKET NO.
50_-530 UNIT PVNGS-3 DATE 07/09/87 l
COMPLETED-BY.
J.L._ Hull ____
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TELEPHONE
@O2-323-2@72_
j 1999_120Z H
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06/01' 0000 Unit in Mode 5.
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Arizona Nuclear Power Project P.O. BOX 52034 e PHOENIX, ARIZONA 85072-2034 192-00246-JGH/TRB July 14, 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 SIN 50-529 NPF-51 STN-50-530 NPF-65 June Monthly Operating Report File: 87-024-404
Dear Sirs:
Attached please find the June, 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 tru y yours, b
/YL&g----
J. G. Hay es a
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 l
J. A. Amenta 1NPO Records Center j
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