IR 05000293/1987015
| ML20215L132 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/27/1987 |
| From: | Harris R, Kerch H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215L109 | List: |
| References | |
| 50-293-87-15, NUDOCS 8705120110 | |
| Preceding documents: |
|
| Download: ML20215L132 (17) | |
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-293/87-15 Docket No.
50-293 License No.
DPR-35 Licensee: Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Nuclear Power Station Inspection At:
Plymouth Massachusetts Inspection Conducted:
March 2-13, 1987 Inspectors:
%N i
7 Harry W.' Kerch, Lead Reactor Engineer 4 ate dd
//M /?7 N1/h rd H ris, NDE Tech 11cian
' ' dath f[' 27[/7 Approved by: _ s Strosnider, Chief, M&PS, DRS, EB date Inspection Summary:
Inspection on March 2-13, 1987 (50-293/87-15)
Areas Inspected: A special announced NRC independent measurements inspection was conducted at the Pilgrim Nuclear Power Station, by Regional NDE personnel assisted by two NRC contracted NDE personnel.
The NRC Mobile Nondestructive Examination Laboratory was utilized during the inspection.
Nondestructive examinations were performed on a sample of pipe weldments, pipe supports and
'
miscellaneous pipe materials which were selected from the Core Spray System, High Pressure Coolant System, cascading drain line and Recirculation system.
Inspections were performed to applicable codes, standards and procedures.
Results:
Two violations were observed concerning an inadequate magnetic par--
ticle examination and an inadequate procedure for visual inspection personnel qualification.
8705120110 870505 PDR ADOCK 05000293 G
,
.
DETAILS 1.
Persons Contacted Boston Edison Company (BECO)
K. Roberts Nuclear Operations Manager F. Famulari QC/ISI Group Leader R. Grazio Field Engineering Manager J. Mattia QA Surveillance Leader B. Perkins Sr. QC Engineer N. Desmond Sr. QC Engineer C. Hamilton Sr. Compliance Engineer t_
NRC J. J. Lyash Resident Inspector 2.
Independent Measurements-Nondestructive Examination and Records Review of Safety Related Systems During the period of March 2 through March 13, 1987 an onsite inspection was conducted at the Pilgrim Nuclear Power Station utilizing the NRC Mobile Nondestructive Examination (NDE) Laboratory. This inspection was conducted by-region based personnel in conjunction with NRC contracted Nondestructive Examination (NDE) personnel.
The purpose of this inspection was to verify the adequacy of the licensee's inservice inspection plan and quality control program. This was accomplished by duplicating those examinations required of the licensee by NRC Regulations, applicable industry codes and FSAR commit-ments. The NRC Inspector made a random selection of pipe hangers, pipe weldments and pipe systems. These were intended to provide a represen-
tative sample of components, pipe size, material and weldments examined in accordance with specific site requirements. The items selected were ASME Class 1 and 2 weldments from'the Core Spray, Recirculation, High Pressure Coolant Injection (HPCI) and Residual Heat Removal Systems. Also, exam-inations for erosion / corrosion of material were made on the cascading
,
drain line and the drywell liner plate. The visual and thickness exam-i inations of-the feedwater cascading drain lines and drywell liner plate l
are not an NRC or ASME Code requirement; however, these inspections were conducted in light of the December,1986, feedwater line rupture at Surry Unit No. 2 and the thinning of the Drywell discovered at Oyster Creek in the Fall of 1986.
2.1 Nondestructive Examinations:
Examinations were performed using NRC procedures in conjunction with
!
the licensee's procedures, specifications and applicable drawings.
l The following examinations were performed.
l
-
_ - _ _ - _ _ _ _______ - ____ ___-_____ ___
_ _ _
_ _ _ _ _ _ _ _ _
_
_ _ _ _.
.
.
.
Magnetic Particle Examination Five (5) weldments in safety related piping and adjacent base material (1/2 inch on either side of the weld) were examined using I
the dry magnetic particle technique per NRC procedure, NDE-6, rev. O.
Included in this examination were ASME Class 2, carbon steel piping weldments selected from the High Pressure Coolant Injection (HPCI)
and the Residual Heat Removal (RHR) systems.
Results:
One of the five weldments examined (weld DB-23-2-IC) was found to have an indication approximately 3/4 inch in length starting at the toe of weld and propagating at an angle into the base material. This component was previously inspected and accepted by the licensee as indicated by Magnetic Particle Data Sheet #1351. This data sheet reads, in part, " accept no relevant recordable indications... com-ponent meets ASME Section XI acceptance criteria." Contrary to this, NRC independent inspection found that the Class 2 component did have a recordable indication and did not meet the acceptance criteria of ASME Section XI.
The licensee issued nonconformance report NCR 87-99 describing the unacceptable condition of weld DB-23-2-IC as identi-fied by the NRC magnetic particle examination.
This item is considered a violation (50-293/87-15-01) in that the licensee failed to effectively complete an ASME Code required examination and did not identify or disposition a rejectable linear surface indication.
Liquid Penetrant Examination Four weldments in safety related piping and the adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye penetrant technique per NRC procedure NDE-9, rev. O.
ASME Class 1, stainless steel to Inconel weldments from the Reactor Water Level Instrumentation System were included in this sample.
Results:
No violations were identified.
Visual Examination Eleven (11) safety related pipe weldments were visually examined in accordance with NRC procedure NDE-10, Rev. O, Appendix A.
The exam-j inations were completed specifically to identify any cracks or linear
'
indications, gouges, leakage, or arc strikes with craters or corrosion, all of which may infringe upon the piping minimum wall thickness Mirror, lights and weld gauges were used to assist in the inspection and evaluation of the weldments. See attachment No. I for a list of the weldments examined and the results of these inspections.
____
_ _ _ _ _ _ _ _ _ _
.
.
Results:
Visually, one (1) weldment was found visually to have a linear indi-cation.
This deficiency was also found during the magnetic particle examination noted in section 2.1.
This weld is identified as DB-23-2-1C and does not meet the visual acceptance criteria.
No other violations were identified.
Ultrasonic Examination ISI The inspector selected six (6) pipe weldments for independent ultra-sonic inspection. Those weldments selected were from the Recircu-lation System, Core Spray and High Pressure Coolant Injection (HPCI)
Systems.
The ultrasonic examinations were performed using a Sonic Mark 1 flaw detector and in accordance with NRC procedure NDE-1, Rev. 0; Boston-Edison Company procedures QCI No. 50.70, QCI-No. 50.71, TP 86-130; and associated ultrasonic data reports.
Instrument calibration
_
(linearity verification) was performed using NRC procedure NDE-2, Rev. O.
A distance amplitude correction curve was constructed (DAC)
using the licensee's calibration blocks, PIL-68 and PIL-84, to ensure repeatability of ultrasonic examinations.
Instrument settings and search units (transducers) were matched as nearly as possible to those indicated by the licensee's ultrasonic data reports.
ASME Class I stainless steel and Class 2 carbon steel piping samples were included in this examination.
The stainless steel pipe weld-ments were also ultrasonically examined for intergranular stress cerrosion cracking (IGSCC) in accordance with NRC Generic Letter 84-11, Augmented Inspection Program.
Those carbon steel pipe weld-
.
ments selected were included in the licensee's inservice inspection program.
Results:
Geometric reflectors and root conditions which were noted in licensee's ultrasonic inspection reports were verified by this inspection. No violations were identified.
3.0 Review of Reactor Water Level Instrumentation Lines Modification / Installation PDC #85-07)
During this inspection a walk down of a Reactor Water Level Instrumen-tation Line was performed. The walkdown consisted of a visual inspection of pipe hanger supports and repair and installation of the 2" hot tap drain nozzles.
In addition to the visual examination, a dye penetrant inspection was performed on the 2" hot tap drain nozzle welds. A review of the radiographs for these 4 welds was also performed.
.
_
_
_
.
.
The following hanger components were examined per NRC procedure #NDE-10, Rev. 0., Appendix B, and the associated Isometric drawings M1002 124 Rev. H:
Hanger No.
Detail Dwg./Rev.
Comments H-2-1-7 H-2-1-7 B
ACCEPTABLE H-2-1-8 H-2-1-8 C
ACCEPTABLE H-2-1-9-H-2-1-9 C
ACCEPTABLE H-2-1-10 H-2-1-10 ACCEPTABLE H-2-1-11 H-2-1-11 ACCEPTABLE H-2-1-12 H-2-1-12 ACCEPTABLE H-2-1-24 H-2-1-24 ACCEPTABLE H-2-1-25 H-2-1-25 B ACCEPTABLE H-2-1-26*
- Hanger was not installed.
Further investigation revealed this hanger was being re-designed and would be installed at a later date.
.All hangers were inspected for evidence of wear, corrosion, cracks, extraordinary movement, correct dimensions and proper installation.
Results: No violations'were identified.
4.0 Ultrasonic Thickness Measurements of the Drywell Wall The licensee examined twelve 6 inch by 6 inch areas on the Drywell liner plate in response to NRC Information Notice 86-99, and General Electric Company Rapid Information Communication Services Information Letter (RICSIL) No. 09. These documents alerted utilities of possible corrosion of the drywell wall based on experience at the Oyster Creek Nuclear Power Plant.
The NRC Inspectors performed independent measurements of the drywell wall thickness. No degradation of the drywell wall material was detected.
Thickness measurements were performed using a Nova D100 digital thickness gage in conjunction with NRC, Nondestructive Examination procedure, NDE II Rev. O.
Attachment No. 2 is a comparison of the licensee and the NRC Inspection results (high and low thickness measurements).
Results: No violations were identified.
4.1 Ultrasonic's Thickness Measurements of Feedwater Cascading Drain Lines Three hundred sixteen (316) thickness measurements were taken on three (3) carbon steel 90 degree elbow to pipe components. The
'
thickness measurements were performed to determine if wall thinning had occurred due to erosion / corrosion. This was accomplished by laying out a 1 or 2 inch grid (determined by pipe size) on the com-ponent and recording the measurements obtained by use of a NOVA D-100
'
thickness-gauge.
...--
. -
--
. - _.
. -
.
--
_
.
.
Measurements were taken in areas where erosion / corrosion might' occur. The areas selected consisted of two (2) elbows to the feedwater heater and one (1) elbow to the heater drain cooler. Attachment 4 presents a tabulation of the NRC wall thickness measurements.
Result: No violations were' identified.
5.0 Review of Procedures The procedures listed in attachment number three were reviewed to verify their technical adequacy and conformance to regulatory and code requirements.
Results:
The inspector reviewed the ISI contractor's procedure QC-7 revision 3, titled " Qualification and Certification of ASME Section XI Visual Exam-ination Personnel". The inspector noted the contractor's procedure no.
QC-7, revision 3, section 8.0 requires only four months experience for VT2, VT3 and VT4 level II qualification. ANSI N45.2 and licensee proce-dure QC 10.6 require 4 years experience for visual inspector certifica-tion. The' contractor's four month time period for experience is inappro-priate and does not conform with NRC or Code requirements and is considered a violation 50-293/87-15-02.
The licensee took several actions with regard to this subject during the inspection.
Procedure QC-7 was revised to include the ANSI experience requirements. The licensee audited the personnel visual qualification records of all personnel who performed visual examinations at this facility and indicated by letter dated March 9, 1987 that examination personnel had exceeded the experience requirements of ANSI 45.2.6.
The inspector also reviewed the visual personnel training records and did not identify any personnel that did not meet ANSI N45.2.6 experience requirements.
6.0 Review of the Inservice Inspection-ISI Program The Ptigrim ISI Program was prepared and is implemented by the licensee.
The plan for this outage meets the requirements of ASME Section XI 1980 edition including addenda through Winter, 1980. This outage was the 2nd in the second 10 year interval of the ISI program.
(1) Staffing of ISI Program Based on this review, the inspector concluded that the Pilgrim nuclear facility staff, comprised of site personnel augmented by contract personnel, was adequate to properly execute the ISI progra,_.
.
i
.
(2) ISI Personnel Record Review The inspector reviewed the qualifications and certification records for 15 examination personnel. No violations were identified.
(3) Quality Assurance Audits and Surveillances The inspector reviewed the documents listed below to ascertain that ISI and modification contractors are audited by the QA department prior to their being considered a qualified supplier of services.
Also, the on site QC surveillance of contractor performance to assure procedure compliance was reviewed.
- Boston Edison Audit Report #86-73 conducted at King of Prussia, Pennsylvania, General Electric Nuclear Field Services Division. This audit covered modifications, maintenance, repair and replacement capabilities.
Boston Edision Audit Report #87-1 Preaward of ISI Contractor (GE)
for ISI/IST.
- Bechtel No.87-136 radiographs procedure
- General Electric No.87-124, 86-264, 87-59 Magnetic Particle Procedure
- General' Electric No. 87-59 Ultrasonic Procedure
- General Electric No.86-239, 86-206 Liquid Penetrant Procedure The audit and surveillance reports indicated that various aspects of the ISI Program were examined, audit findings were properly closed out,-and the licensee's ISI vendor was properly qualified as a sup-plier of ISI services. This inspection identified a weakness in that the deficiency discussed in Section 5.0 in the ISI contractor's procedure for Qualification and Certification of ASME Section XI Visual Examination Personnel (QC-7 Revision 3) was not identified during the above audits.
(4)
Inservice Inspection (ISI) Data Review During this inspection the inspector reviewed the ultrasonic data
'
listed below.
System 16.2 Recirculation Volume
- System 16.3 Recirculation Drywell
- System 7.1 BV.111.1 Volume System 10.2 RHR Volume
.
.
The inspector verified that the examinations were done in compliance with governing procedures and that applicable regulatory and ASME code requirements were met. A review also was performed to verify that' the licensee had properly recorded the evaluations. A licensee employee with-a Level III NDE certification reviewed all NDE ISI data and his signature on each of the NDE data reports was required for acceptance of those reports. Overall, the inspector found that the Inservice Inspection Program at Pilgrim was being performed ade-quately and the objectives of the ISI program are being met.
How-ever, a weakness in the ultrasonic examination documentation was identified in that cross references for the automatic ultrasonic examination and the supplemental manual ultrasonic examination did not exist on the ultrasonic examination data report. Also, their were several -cases of incomplete ultrasonic examination data record-ing on the examination data records.
The inspector determined that the data was available elsewhere, although not documented on the official ultrasonic examination record.
During this inspection the licensee revised and corrected all the documentation deficiencies on the ultrasonic examination data reports for this outage. To prevent reoccurrence the licensee has issued instruction No. 01 Rev. 0
" Review of Data" to ensure all the required data is recorded on the ultrasonic examination record. The inspector has no further concerns with this item and considers this issue closed.
. 7.0 Attachments:
f
'
Attachment No. 1 is a tabulation of specific piping weldments inspected and results. Attachment No. 2 is a sketch of specific areas of the pri-mary containment drywell liner plate tested for wall degradation and comparisons to licensee measurements. Attachment No. 3 is a list of specific procedures reviewed during this inspection. Attachment No. 4 is a sketch indicating thickness measurements and areas inspected for erosion / corrosion.
8.0 Exit On March 13, 1987, the NDE Van personnel had an exit meeting with the licensee's staff. The findings of this inspection were described at.that meeting.
No written material was provided to the licensee during this inspection.
.
.
,
.
..
'
Attachment No. 3 List of Procedures & Manuals Reviewed-Boston Edison Company (BECO) Procedures:
Ultrasonic Examination-General Requirements No. 50.70
Ultrasonic Examination of Class 1, 2 and 3 Pressure Retaining Welds No. 50.71
Manual Ultrasonic Examination of Austenetic Metal Welds for IGSCC. No.
- TP86-130, P86-130, UTM-002. Rev.0 Quality Assurance Dept. No. 4.06
- -
. Procurement of items and services Quality Assurance Dept. No. 4.01
Review of Preliminary Procurement Documents Quality Assurance Manual, Section 2 and 15
Quality Control Instruction QCI 10.06 Rev. 4
Training and Certification of QAD Personnel for Inspection and testing activities General Electric (GE) Procedures:
Procedure No. QC-7 Rev. 3 Qualification and Certification of-ASME Se: tion XI Visual Inspection: Personnel s
.,,,.,. _
., -
,
, _
._
-.,. _,.,.._
_
_
.
lI l
.
N N
N N
O O
O O
I I
I I
T T
T T
A A
A A
L L
L L
L L
L L
A A
A A
N N
N T
T T
T O
O O
S S
S S
RI I
Rl N
N -
l I
N N
OS RS OS I
I
/E
/E
/E
/E
R FR R
NL NL NL NL R
OZ OZ OZ OZ
-
.R R
.
SOW SOW SOW IZ IZ IZ IZ 8D ACO ACO ACO T0 T0 T0 T0 E/B E/B E/B AN AN AN AN S
.E T
MNL MNL MNL C
C C
C K
.
I
.
I
.
I
.
A NI KI KI KI FR FR FR FR m
M M
E RB IOP IOP IOP DS DS DS DS r
R CU HRI HRI HRI ON ON ON ON NS TEP TEP TEP MI MI MI MI lg l
i l
i i
L P
A U
C C
C J
C C
A A
A C
C C
C C
S C
C C
E C
C
/
/
/
C C
C C
C E
I A
A A
R A
A N
N N
A A
A A
A T
V I
S S
S E
N F-D A
A A
A A
A A
A A
A A
A A
A O
R
/
/
/
/
/
/
/
/
/
/
/
/
/
/
A N
N N
N N
N N
N N
N N
N N
N S
H TL
UM SA A
A A
A A
A A
A A
C C
C C
A ER
.
/
/
/
/
/
/
/
/
/
C C
C C
/
RC T.
DR P
'
N N
N N
N N
N N
A A
A A
N O
N NP A T DN 1EE
.
C C
C C
C C
A A
A A
A A
A A
NM T.
C C
C C
C C
/
/
/
/
/
/
/
/
TIE NMR U
A A
A A
A A
N N
N N
N N
N N
EAU MXS i
HEA l
C E ASM A
A A
A A
A A
A A
A A
A A
A TM
.
/
/
/
/
/
/
/
/
/
/
/
/
/
/
TET T.
ATN N
N N
N N
N N
N N
N N
N N
N IE R
D FN
,I I
I OEP A
A C
J C
C A
A A
A A
A A
C NE
.
/
/
C E
C C
/
/
/
/
/
/
-/
C OD T.
IN N
N-A R
A A
N N
N N
N N
N A
TI M
'
UB
-
A K
T C
A A
A A
A A
C C
C A
A A
A A
I
/
/
/
/
/
/
C C
C
/
/
/
/
/
H N
N'
N N
N N
A A
A N
N N
N N
T
-
l ll
_
.
E T
I A
A A
A A
A A
A A
A A
A A
A R
/
/
/
/
/
/
/
/
/
/
/
/
/
/
R N
N N
N N
N N
N N-N N
N N
N
/
E
-
.
F f
I o
-
Y.
/
OL A'
A A
A A
A A
A A
A A
A A
A
-
.
LA
/
/
/
/
/
/
/
/
/
/
/
/
/
/
-
e LN N
N N
N N
N N
N N
N N
N N
N
!
g AA a
P i1 il H
L
8 S
S P
P P
A
O O
O L
2
2
B B
B
1
1
,
C
l
l 1I u
l l
lI
,ll IiI
'
B'
-
-
l
R
-
1
2 E
BA A-
-
-
-
h B
Y B
C B
E 2 E 2 E 2 5S 5A AA BA B 0 c
MO A
1
3 N
-
N
-
N
-
1 -
1S 6S 6S
r US
R
-
-
-
-
I
I
I
N.
N-1 -
1 -
P9-a MNI
-
P0
2
F L 2 L 2 L 2 P
O P O PNO PNO OF1 M
E /CA S2
-
-
-
-
5
ASN ASN A N A N O- -
TDERI
-
3
3 N
-
N
-
N
-
TN TN TN-TN-L01
SLNINB EB1 I25 I25 I25 I25 I
I
I
IS IS IS IS 1 -
E YEIC- -
R-
-
C-
-
C- -
C-
-
C-
-
AE0 AE0 AE0 TAC TAC TAC TAC RI T
SWLERR O44 PB3 PB3 PB3 PB3 R31 R41 R81 ORP ORP ORP ORP HLS A
R22 C11 HD2 HD2 HE2 HE2 D5M D5M D6M HDS HDS HDS HDS RHI D
..
.
.
.
ilLTl?A S0WI C Th iC l(NESS
'
'
0# OR Y k/6L L k/ Al'-
gM g 2
/ 4/ g o'
,
N
.
I g
.
.
J G
~ _
_
'@
go.
---
Cwww w tau,
-
,
($", [_J_ [3;g 3 f
3 g R g y; gy g g..$'.&L.
g
<-
.
h E 9 Pau V,w
.
180*
-
l
.
.
.. -.
_ __
.
.
.
'.
Veur-
$6 d}f 2
.
..
'
O
.
ios L** #
n r<.aos, tu.
l'
I. ld
_.I'L H b)R.L SITE g, g-i,1o L
E
!
L
.
1muaws.
.
/s x %:6ae
,
o n
'/v'ef; Wi b a s
}
.
.
....
i..+
- . : :.;-
2=
r;
..a....:p;' '
.,.
' ' '
.
.
.
.
' '
a
-.
.
-
'
-
.-
'
'
-
-*- ss.
ss*-+
,o n
.
.
.
N Rt. [ g.
/.'/ o.
y ' i. t o".
H l' 16
' /* /M
'
/.od-L; g
t f, o g L
i. ici t i. id'
d s
.
'
L
.
-
O 2neuwew
^
fys (- w
- 6
-
.e-
.
eree- -
,
_
_ _;
~_.,.-
w..,. n w n r.r. :
~
-
.
..
e.~
..:
.
-
,,_,a.
, r -, m --
,
~
J:
112 "
l
_
iz
.
ga FH I:Id H fT N%
-
L
.16" L 1 oA
,
-
,
i
.
!
- 3
!
+
,
-v
_
-
i e se'- -ua*-+ z.
l
- r y /.f( y i:19.Lsrnz.
H.L.'Ld N l#'
-
' NR ('-
i oge
.
L /,og t JR L I;td, 1,.1.o81 l
_
,
-
'
..
-.
-
V'"'~
- \\
ggQg2
'
-
.
eJa
.O O*.D4
- );
.
-
-
<
n.
L.e. 9 i
__
h Floor Eu.
H ' II H Lll -
gge
.
srre.
L 1.1o L 4 oB
-
'
-
.
J L_
J
-
- 2+
.
j
.
.
.
+ 60'
~6Y*-+7 y
bH NN i. %, i H I16 t-NRClef 1,'tt y
L 1.of L I-16 L 1.16 r-o7-L u
u
.
O t
- 4
<
-
_
., ~.a,
.,.,:-.
,,.. -..,,., w,
.
g...
.p.
.
.-
'
u.,
g4 gi ; 4.;gpi,4g 4 g,,,,g.g;'
,
~..
,4 :
,,.
i
,.
, _, _ ;gg.
-
lld
-
to
.
'
s,gl H sId H J.'I 5 ) HRC.
l L Iici L l oh
.
.
!
!
.
,
i
+
,
,
.
I l
l r
V
-
,
7 +- #2*
Vf'4 8 H' u Rc
' H
10
. u 1:16 In2 e / L ls, M H s' to ',
yge
.
Las, s.oyty t. r.oco e
'
=
..
.--
.
._
.
-.- -
_-
...
.
Attachment No. 3 List of Procedures & Manuals Reviewed Boston Edison Company (BECO) Procedures:
_ Ultrasonic Examination-General Requirements No. 50.70
-Ultrasonic Examinationlof Class 1, 2 and 3 Pressure Retaining Welds No. 50.71
Manual Ultrasonic Examination of Austenetic Metal Welds for IGSCC. No.
- TP86-130, P86-130, UTM-002. Rev.0 Quality Assurance Dept. No. 4.06
Procurement of items and services
. Quality Assurance Dept. No. 4.01
Review of Preliminary Procurement Documents Quality Assurance Manual, Section 2 and 15
Quality Control Instruction QCI 10.06 Rev. 4
Training and. Certification of QAD Personnel for-Inspection and testing activities General Electric (GE) Procedures:
Procedure No. QC-7 Rev. 3 Qualification and Certification of ASME Section XI Visual Inspection Personnel
.
--.
,4 rrwi n e~n.e i q
ULTR A SONi C. ThiCKorss
'
mea 2 uREine^ns
-
A 6 0 0 G P~
G H T J K L M i
I Ao7.Yn.ya.Vn.Y/t so&,vic 29.Yo
SVETCH
%l 2.Yn.YN.sie 3st..sez.3it, 3 14.4V.s x
)
3.9nmi.31).h91.3n.312
.vn.m Y VI4,W69.bbS.31l 1 14AhDANG.16/ HM
.h 5. gig ns 5 90.bs3.ye.m 3 99.19p
,
b.Yst.39/ Jo3.Ve 3 92 AN.Yb.Mf.4C
- '~
I 7. Yrs,1er.M.be.foo.%o Vs/sW42
-
-
-
-
&
-
,
6.ysc../e.gs:.yog.3sy_ygt y,b.g g,99
,
9.h.Vo9.Yss.3%.Ys3 foo.bs I
.3E.m to de nn.ve.vo9.ssc.styyso.sro.m
-
_
,
//
/2
.
J
/3
/Y
/5 il.,
E c e o w S 3 It lo e/s p.es
,
'
Deatusng Muco-t 2.4-zeev El System Cascading hn line Component Etsou) To Wre oc coorg a-ios
[nstrument idova D too Exmninene J A+ ras D. hn Commants O//mL au a i 7klea n44, mL J/ds-l l
2 ' & l19 Rev n a.wa Y f6f'
Date.
3/t-/87 SuFs
%.yum Un, t I
Attlic H m En s Y rd o. y pg, opy
. _..
,
Q
..
.-
A 6 0 D E'f G H T J K L M SNETCH
'
!.2%.2%.n2.213.2s1.11z. 2 ro.zrt. ex
2.Mb.122 18y.2sy.MD.tn.1%.111.1 71
249 2%.211 214,287.271. 2 11.211 212 C., l
'
t Y
246 21L.218.ht9.296.772 27'l,11I.5M i
'
O i
.213. gn.m. hts
.gro,2gy
,2 n
.183 13;
N'
b
.29D.1t4.K1.224.2n.2 71.31 2 82.213
.1 A *-
)
7.291.2rg.z13.krc.29z.2re,z19.2ry.m
-
--
-
S~
B.2N 2tc.214.216. 294.89.2s'c 2rc.no S.1'?4 286.271 29/.296. 2B.2r7,29{ 77l
'
@
l0 794. gy. 1 94,ggj,zt,.y n,gg7.yyy,254
___
__
//.29L.224.29V.29).72 1.21 2.in',216.219
/2 7/7.2N i191.301.305.21.30.2t').213
_
1 92 2 94.299.%y.%.291. 717.2 74.217
-
_.
IS
/b EL bold * 69 E to' 0/s Pn e e
Drawing n too - 624-2 fav. EI Systa:rn Cascadung Dram Lme.
Component araou) To FW HTR-8-/45'
Instrurnent Nova V-ioo kxaxninu ts) J has D. h m Commants GMAAn on u -6_ % <s ad/,
4,a af P L.
l
/ "CLIO Rev,a.wa YA,A//fa oare.M Vr7 S4 TItanm und i
Attupmmr No. y Aru2of3
-...
@
.
_ f) is 0 O I:
l~
C-,
H T'
J K L M
/
.%9 97.de 92.519 349. %r.3n
SKETCH
'
2 909 312.9/3.n3. set.sss.w.xs
,
'
3 db 3 19.M7.51o.314.sts.397.579
-
]},
4.
{
A *-
- -)
y./ss'. 7 91.Wo.39 r.s74.M.M.314
-
5.vil $1s (s).591.373.3gz gg, sig
__
_)
,
b.YiY./i./s 7.%c.srs.%9 3gs 32)
7.%Vder.Yo3.sn.sg:.w 3n. 5 76
--
-
'"'"*****'d
-
'
'
B.va.+o.sz.3n.3n.m.x,;.ua y
.%&.'lio 397.399.398.s13 362.st1
-
[,
to.%3.90 9.%.s99.str.sx.w.n3
//
.Ys3 dio 3 71.%3.379.m an af4
/2 VooM
./03 Ms4.377.sn.%6 3m
/3.391.Yot.sc. S7?.nv.sr9.sry.sss
/Y 379 h/sbi. 3 12.s9s.sec.374. 3 71
/5
ELGou.)
68 E.
lo'*ch Piet-Dratulng Mod 626-2
$2/ El Sy st ern fascadino Prain Linci,
"
65G Component ne*; To ra/-iha d-to</
-
[nstrurn ent Navn' Tl' loo
'E mnin e ns) 1 4 ees D.L Kn Com man +-s O//c/wzwao<? ai >><-es:Le N.a_x.M.
sh'a of E#'ex
/"CA/D to~cLs se.6 vo b
. g l
D a t a.
3/W/7 Rev, a.w r
.
.
S d.c.
7m Uni t i
p@anmanr No.4
/4cs 3 of ~3
. -.