TMI-11-060, Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
(2 intermediate revisions by the same user not shown) | |||
Line 3: | Line 3: | ||
| issue date = 04/05/2011 | | issue date = 04/05/2011 | ||
| title = Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval | | title = Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval | ||
| author name = Helker D | | author name = Helker D | ||
| author affiliation = Exelon Corp, Exelon Generation Co, LLC, Exelon Nuclear | | author affiliation = Exelon Corp, Exelon Generation Co, LLC, Exelon Nuclear | ||
| addressee name = | | addressee name = | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:10 CFR 50.55a TMI-11-060 April 5, 2011 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No.DPR-50 NRC Docket No.50-289 | {{#Wiki_filter:10 CFR 50.55a TMI-11-060 April 5, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 | ||
==Subject:== | ==Subject:== | ||
Response to a Request for Additional Information | Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI) Interval | ||
-Relief Request RR-10-01 Concerning Control Rod | |||
Interval | |||
==References:== | ==References:== | ||
: 1) Letter from P. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Submittal of Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI) Interval," dated October 13, 2010 | |||
: 2) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Relief Request RR-1 0-01, Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval (TAC NO. ME4882)," dated March 16, 2011 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) submitted for your review a relief request associated with the third Inservice Inspection (lSI) interval for Three Mile Island Nuclear Station (TMI), Unit 1 requesting relief from Table IWB-2500-1, Examination Category B-O, Item Number B14.10, which requires volumetric or surface examination of the pressure retaining Control Rod Drive (CRD) butt welds in 10% of the peripheral CRD housings. | |||
In the Reference 2 letter, the U.S. Nuclear Regulatory Commission requested additional information. Attached is our response to this request. | |||
There are no regulatory commitments in this letter. | |||
Response to a Request for Additional Information-Relief Request RR-10-01 April 5, 2011 Page 2 If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. | |||
Respectfully, David P. Helker Manager - Licensing Exelon Generation Company, LLC | |||
==Attachment:== | ==Attachment:== | ||
Response to a Request for Additional Information - Relief Request RR-10-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI USNRC Project Manager, [TMI] USNRC | |||
Response to a Request for Additional Information | ATTACHMENT Response to a Request for Additional Information - Relief Request RR-10-01 | ||
-Relief Request RR-10-01 | |||
Response to a Request for Additional Information Relief Request RR-10-01 April 2011 Page 1 Question: | |||
data for examinations of welds"A","B", and"C" completed since 1986 identified no degradation." Response | : 1. Regarding page 2 of the relief request, paragraph 2, provide the specific type(s) of examination(s), Le., visual (VT-2), dye penetrant (PT), magnetic particle (MT), ultrasonic (UT), etc., referred to in the statement" ... six (6) CRDs not in the periphery were examined The six (6) CRDs not in the periphery examined in 2001 were examined using the dye penetrant (PT) method. | ||
Does it refer to the accessibility of the welds for examination or that there were no defects in the welds?Response | Question: | ||
Response to a Table 1 CRD Examination Summa Examination Coverage Notation Examination Results indications Response to a Request Relief RR-1 1 3 | : 2. Regarding page 2 of the relief request, paragraph 2, provide the specific type(s) of examination(s), Le., VT-2, PT, MT, UT etc., referred to in the statement, "A review of lSI | ||
45°one sided limitation (see Fiqure 2).PT No limitation noted limitation noted No limitation noted | [inservice inspection] data for examinations of welds "A", "B", and "C" completed since 1986 identified no degradation." | ||
===Response=== | |||
... | Table 1 below provides specific examination history, nondestructive examination (NDE) methods, coverage, and results data for "A", "B", and "C" CRD weld examinations completed since 1986. Drawing 1D-ISI-RC-011 (Figure 1) has been included with this response in order to provide additional information on the weld locations both in terms of elevation, azimuthal and radial location on the reactor vessel closure head. | ||
Question: | |||
: 3. Regarding page 2 of the relief request, paragraph 2, the second sentence states, "There were no examination limitations reported for these welds." Please clarify this statement. | |||
Does it refer to the accessibility of the welds for examination or that there were no defects in the welds? | |||
o Rl+-l43 | ===Response=== | ||
Table 1 has identified that examinations completed were acceptable to ASME Section XI requirements (no degradation was noted). Examination coverage was in accordance with ASME Section XI requirements with the one exception noted in Table 1 and Figure 2 for a 1987 UT examination for weld CRD-151. In this case, an accompanying liquid penetrant examination was completed providing additional NDE coverage for the small area not examined during the UT examination. | |||
Response to a Table 1 CRD Examination Summa Examination Coverage Notation Examination Results indications | |||
Response to a Request Relief RR-1 1 | |||
3 CRDID CRD lSI Weld Exam Exam Examination Coverage Notation Examination Results No.* Weld 10** 10 No. Year Method 51 A CRD-151 1987 PT No limitation noted I A 0° no limitation. 45° one sided 51 I A CRD-151 1987 UT limitation (see Fiqure 2). | |||
- | PT No limitation noted limitation noted indications No limitation noted | ||
* 1D-ISI-RC-011 CRD location identification number | |||
** 1D-ISI-RC-011 Enlargement "A" and Elevation View weld location identification | |||
Figure 1 Drawing 1D-ISI-RC-011 | |||
5 4 3 IIO-:)l:!-ISI-QI 1 8 7 6 wan | |||
= | |||
lSI ClIO 151.wELO 10."" 10. No. | |||
CllO | |||
: 11) ..... | |||
151 W£L.O | |||
,0. MOo ,r~ | |||
... | lSI wELD | ||
.......... | : 10. MOo I~R~ 10. MOo | ||
~A &4A 137 | |||
* CllO-IO'i i"6 *B ~~ e ~::;'i B B ¢FI>-IIO C CRO-I1I C CIIO*I~8 ~ <tM-,&!, C CI/l)-I92 o g .:, | |||
I~ "'-'64 5;., 0 Rh*r~l o ~~~~ | |||
ii' 0 '1&+-110 " -' | |||
I ' E Rl+-Itl R~-155 E (bi- 92 N---t-- x '291 A CRD--08~ 38 | |||
* CRO-II2 147 1 A Clll>--139 56. CRll--166 65 A CRO-I93 | |||
!l\fi III B CRXl96 I~ B CIIl-100 B CRO-' 57 e CMl-I94 | |||
/' I -------.::nJCl. .......... " ' " ----.. | |||
C>><AL. | |||
C ~7 CRll-113 CRO-II4 'c CRC>141 C CIlD-I68 C CRo-l9D | |||
!.?': a | |||
:!'P. ''> "'t.CS) H<.p,<r.~=-j ii RtI-0e61 0 Rt+ll,3 & 0 Rt+ 140 I~ 01+167 0 RH~I'i4 | |||
* ,E 1M0tf7 E Rt+-1I4 E* Rt+t04. -'58 E RR-I95 36 15 10 ./' | |||
t 22 58 12 I' ' | |||
g:::~ | |||
~ | |||
* CRl}-142 57 | |||
* CAl>- 95 | |||
, 41. 69 l~ 68' ~ | |||
CRIJ-oeB CRl>-115 I"ll 8 CR[)-I43 B B CRl)-197 CRD-0e9 8 CRC>-Ii 6 CRC-<l9C! ,- C CRC>-117 C CRC>-I44 C CJ:lo-i7l 10 CRn- 1~8 | |||
. - 40 39 26 2 ' 13 6 | |||
,8 ~-I-":'::"=~b-:', 1i+Oii91";:. \ X o Rl+-l43 ~ R~'170 | |||
:- 0 Rl+-197 | |||
'7. p 62 1 " 42 1 2. D 67" 9 I\ | |||
{j' | |||
~ | |||
~ ::I:~- D"'I44 .... 17 I E Rtt-196 49 44 43 11 B It y | |||
... _.. - ~ | |||
40 | |||
* CRlH 18 49 * ~'145 58 | |||
* CRD-In 67 A, ClIl-I99 w 52"~ !".s-4 :30 2 1 7- B CRll-119 8 CRQ-'.6 B CRO-I73 a CRIJ'200 | |||
!:I7 n ~ "61 2 I ~ | |||
u_\ C CRl>-120 C eRD-I.7 | |||
, C eRO-17. | |||
C CRl)- 201 It | |||
-;;-J---'-;;;;--;;="'i l~.\ b, I~ :::173 w 0 ~-200 | |||
~~ +'I 63 0 60 | |||
* r~'" 34 IT 66 '" ~ I I~ ::.!l~ I~ :::~ '" E 1lH-201 c | |||
\ .... 6 | |||
* 58' 4~" 27 '" 21 'P. 31 -,.- | |||
64"~ 3 I. 65" 33 16- | |||
~.~"~ YRD-094 41 | |||
* CRC>-121 1110 | |||
* CRD-148 ~ CRD-I75 1 68 A cRtl-202 Yl | |||
\ 5 8 CFl)-I22 8 C~149 B CR[}ol76 B c;llC>-203 | |||
~~ | |||
50"*48 .... 20 ... 32 .. * | |||
.C ¢!I)-I23 | |||
/i:J C CRll-l$O | |||
~ , C eRD-l77 C C\lI>-~ | |||
I~ ::~ ~ tt~ " | |||
R1+116 I~ | |||
0Ri+Q98 0 '1lH-I22 o;;.i;' ~. .... ,71 | |||
"" 46 51 18 E Rl-Kl9l E | |||
~ i __ | |||
. '--- 42 A *CI1O-12. 51 .A ~151 w. CRD-I?8 169 A, ~~20~ | |||
8 ~RD-1~5. 8 . !~2 | |||
, B C~179 B C'lQ-2C6 | |||
~~~~ | |||
¢ rID-126 C CRD-I53 C CRO-Ie<) 'C' CIlD-207 Z , | |||
TOP VIEW /I:~ | |||
~ ::::~~ /'\ .~ :~I~~ | |||
.:i. | |||
I~ | |||
1/H~9 | |||
...*'80 | |||
;L .0 E | |||
RI!l-206 11&-207 | |||
~N..tMI&I:Jt~~ | |||
,-" ~TIOW ... ta" TO .. -n*1-4 ........ ~ --..l *** | |||
.52 A ~::~ | |||
ClOD-roo 43 A CRO;127 61 A | |||
'CRe-IOI B CRD-I28 | |||
! CROf CRD- 55 B C ~I~ C CRD- i,(, C Cll\)ole:l eRO-l02~,~ \ | |||
~ | |||
l \ ~" | |||
1*;101 '-1-" | |||
I~ ~l~ | |||
.i-b I~ ::I~ .~ !'::~~ | |||
1*102 . | |||
CRD-,~ | |||
CI/O-I04 CI1D-IO~ | |||
. A CRD-I3C B CfW!3,1 C 'CRD-132 53 A CRl>-157 B CRl>-1~ | |||
C CRO-I5'9 62 | |||
~~:: | |||
C CRO-I96 | |||
'* 1041iX. fi:. L': ~~, | |||
~ ~;.I ~ ::::~ I~ .. ::::85 B '1lIl-105 ;' | |||
CRO-IO! 45 A CRO-I33 .~ ,. CRD-160 63.A 186 CIIl-187 | |||
~ ~ft ~ | |||
4:'ru. CRC>-IOl eRCH61 B CRO'lee CRD-152 C CltO-189 | |||
~ | |||
CRO-I08 1<1+134 /i\ 1._~ G: | |||
fi::, .~ Q RIl-l61 | |||
~ | |||
"tHO? R'Hfl>l | |||
: t. RH-IO I RH-i35 E R.<-I62 "'He9 | |||
,Ca) ,.- IIOLn CT'fP, ... ~D) | |||
: p. CJ.C rru. 'O-(:'-RC~D11_Q1 | |||
:cv...... ;n G!'1t~u::, ~,~ r...:- '<'~ ~ IS[ n ...... ~.I .... ~ | |||
~ L:~- | |||
lHl$ "5 | |||
* l __ . ~ | |||
[WATtoN -viEW I'OA ~ ~ \tI/E.~ .. ~ll'tto.. SkETCM TNI- I l .0\.T.lMQ. so:. ~Go;. ltHS1-~-O'o.. | |||
A ~ DRIVE | |||
~[c.",~ | |||
I I~ ... I jUVl.JP - | |||
c;r..GQl L | |||
"..0/ ~""~IJ ("""""-"- ~",-y,) | |||
,. U~/iP"(Il:>~' | |||
ol.l~fI'tIIOCRUK c;...... | |||
Ctl:t)loo1 HOl..l5l'W.a., | |||
~R~~ ~G. | |||
1~1 "t:eero!!~v..b bTl' 1 I IMG.-el't. | |||
DWO. NO. | |||
5 4 .1 2 8 7 6.. | |||
Figure 2 Weld CRD-151 45 Degree Examination Coverage Sketch}} |
Latest revision as of 05:12, 11 March 2020
ML110960228 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
Issue date: | 04/05/2011 |
From: | David Helker Exelon Corp, Exelon Generation Co, Exelon Nuclear |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RR-10-01, TMI-11-060 | |
Download: ML110960228 (9) | |
Text
10 CFR 50.55a TMI-11-060 April 5, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI) Interval
References:
- 1) Letter from P. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Submittal of Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI) Interval," dated October 13, 2010
- 2) Letter from P. Bamford (U.S. Nuclear Regulatory Commission) to M. Pacilio (Exelon Generation Company, LLC), "Three Mile Island Nuclear Station, Unit 1 - Request for Additional Information Regarding Relief Request RR-1 0-01, Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval (TAC NO. ME4882)," dated March 16, 2011 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon) submitted for your review a relief request associated with the third Inservice Inspection (lSI) interval for Three Mile Island Nuclear Station (TMI), Unit 1 requesting relief from Table IWB-2500-1, Examination Category B-O, Item Number B14.10, which requires volumetric or surface examination of the pressure retaining Control Rod Drive (CRD) butt welds in 10% of the peripheral CRD housings.
In the Reference 2 letter, the U.S. Nuclear Regulatory Commission requested additional information. Attached is our response to this request.
There are no regulatory commitments in this letter.
Response to a Request for Additional Information-Relief Request RR-10-01 April 5, 2011 Page 2 If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, David P. Helker Manager - Licensing Exelon Generation Company, LLC
Attachment:
Response to a Request for Additional Information - Relief Request RR-10-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI USNRC Project Manager, [TMI] USNRC
ATTACHMENT Response to a Request for Additional Information - Relief Request RR-10-01
Response to a Request for Additional Information Relief Request RR-10-01 April 2011 Page 1 Question:
- 1. Regarding page 2 of the relief request, paragraph 2, provide the specific type(s) of examination(s), Le., visual (VT-2), dye penetrant (PT), magnetic particle (MT), ultrasonic (UT), etc., referred to in the statement" ... six (6) CRDs not in the periphery were examined The six (6) CRDs not in the periphery examined in 2001 were examined using the dye penetrant (PT) method.
Question:
- 2. Regarding page 2 of the relief request, paragraph 2, provide the specific type(s) of examination(s), Le., VT-2, PT, MT, UT etc., referred to in the statement, "A review of lSI
[inservice inspection] data for examinations of welds "A", "B", and "C" completed since 1986 identified no degradation."
Response
Table 1 below provides specific examination history, nondestructive examination (NDE) methods, coverage, and results data for "A", "B", and "C" CRD weld examinations completed since 1986. Drawing 1D-ISI-RC-011 (Figure 1) has been included with this response in order to provide additional information on the weld locations both in terms of elevation, azimuthal and radial location on the reactor vessel closure head.
Question:
- 3. Regarding page 2 of the relief request, paragraph 2, the second sentence states, "There were no examination limitations reported for these welds." Please clarify this statement.
Does it refer to the accessibility of the welds for examination or that there were no defects in the welds?
Response
Table 1 has identified that examinations completed were acceptable to ASME Section XI requirements (no degradation was noted). Examination coverage was in accordance with ASME Section XI requirements with the one exception noted in Table 1 and Figure 2 for a 1987 UT examination for weld CRD-151. In this case, an accompanying liquid penetrant examination was completed providing additional NDE coverage for the small area not examined during the UT examination.
Response to a Table 1 CRD Examination Summa Examination Coverage Notation Examination Results indications
Response to a Request Relief RR-1 1
3 CRDID CRD lSI Weld Exam Exam Examination Coverage Notation Examination Results No.* Weld 10** 10 No. Year Method 51 A CRD-151 1987 PT No limitation noted I A 0° no limitation. 45° one sided 51 I A CRD-151 1987 UT limitation (see Fiqure 2).
PT No limitation noted limitation noted indications No limitation noted
- 1D-ISI-RC-011 CRD location identification number
- 1D-ISI-RC-011 Enlargement "A" and Elevation View weld location identification
Figure 1 Drawing 1D-ISI-RC-011
5 4 3 IIO-:)l:!-ISI-QI 1 8 7 6 wan
=
lSI ClIO 151.wELO 10."" 10. No.
CllO
- 11) .....
151 W£L.O
,0. MOo ,r~
lSI wELD
- 10. MOo I~R~ 10. MOo
~A &4A 137
- CllO-IO'i i"6 *B ~~ e ~::;'i B B ¢FI>-IIO C CRO-I1I C CIIO*I~8 ~ <tM-,&!, C CI/l)-I92 o g .:,
I~ "'-'64 5;., 0 Rh*r~l o ~~~~
ii' 0 '1&+-110 " -'
I ' E Rl+-Itl R~-155 E (bi- 92 N---t-- x '291 A CRD--08~ 38
- CRO-II2 147 1 A Clll>--139 56. CRll--166 65 A CRO-I93
!l\fi III B CRXl96 I~ B CIIl-100 B CRO-' 57 e CMl-I94
/' I -------.::nJCl. .......... " ' " ----..
C>><AL.
C ~7 CRll-113 CRO-II4 'c CRC>141 C CIlD-I68 C CRo-l9D
!.?': a
- !'P. > "'t.CS) H<.p,<r.~=-j ii RtI-0e61 0 Rt+ll,3 & 0 Rt+ 140 I~ 01+167 0 RH~I'i4
- ,E 1M0tf7 E Rt+-1I4 E* Rt+t04. -'58 E RR-I95 36 15 10 ./'
t 22 58 12 I' '
g:::~
~
- CRl}-142 57
- CAl>- 95
, 41. 69 l~ 68' ~
CRIJ-oeB CRl>-115 I"ll 8 CR[)-I43 B B CRl)-197 CRD-0e9 8 CRC>-Ii 6 CRC-<l9C! ,- C CRC>-117 C CRC>-I44 C CJ:lo-i7l 10 CRn- 1~8
. - 40 39 26 2 ' 13 6
,8 ~-I-":'::"=~b-:', 1i+Oii91";:. \ X o Rl+-l43 ~ R~'170
- - 0 Rl+-197
'7. p 62 1 " 42 1 2. D 67" 9 I\
{j'
~
~ ::I:~- D"'I44 .... 17 I E Rtt-196 49 44 43 11 B It y
... _.. - ~
40
- CRlH 18 49 * ~'145 58
- CRD-In 67 A, ClIl-I99 w 52"~ !".s-4 :30 2 1 7- B CRll-119 8 CRQ-'.6 B CRO-I73 a CRIJ'200
!:I7 n ~ "61 2 I ~
u_\ C CRl>-120 C eRD-I.7
, C eRO-17.
C CRl)- 201 It
-;;-J---'-;;;;--;;="'i l~.\ b, I~ :::173 w 0 ~-200
~~ +'I 63 0 60
\ .... 6
- 58' 4~" 27 '" 21 'P. 31 -,.-
64"~ 3 I. 65" 33 16-
~.~"~ YRD-094 41
- CRC>-121 1110
- CRD-148 ~ CRD-I75 1 68 A cRtl-202 Yl
\ 5 8 CFl)-I22 8 C~149 B CR[}ol76 B c;llC>-203
~~
50"*48 .... 20 ... 32 .. *
.C ¢!I)-I23
/i:J C CRll-l$O
~ , C eRD-l77 C C\lI>-~
I~ ::~ ~ tt~ "
R1+116 I~
0Ri+Q98 0 '1lH-I22 o;;.i;' ~. .... ,71
"" 46 51 18 E Rl-Kl9l E
~ i __
. '--- 42 A *CI1O-12. 51 .A ~151 w. CRD-I?8 169 A, ~~20~
8 ~RD-1~5. 8 . !~2
, B C~179 B C'lQ-2C6
~~~~
¢ rID-126 C CRD-I53 C CRO-Ie<) 'C' CIlD-207 Z ,
TOP VIEW /I:~
~ ::::~~ /'\ .~ :~I~~
.:i.
I~
1/H~9
...*'80
- L .0 E
RI!l-206 11&-207
~N..tMI&I:Jt~~
,-" ~TIOW ... ta" TO .. -n*1-4 ........ ~ --..l ***
.52 A ~::~
ClOD-roo 43 A CRO;127 61 A
'CRe-IOI B CRD-I28
! CROf CRD- 55 B C ~I~ C CRD- i,(, C Cll\)ole:l eRO-l02~,~ \
~
l \ ~"
1*;101 '-1-"
I~ ~l~
.i-b I~ ::I~ .~ !'::~~
1*102 .
CRD-,~
CI/O-I04 CI1D-IO~
. A CRD-I3C B CfW!3,1 C 'CRD-132 53 A CRl>-157 B CRl>-1~
C CRO-I5'9 62
~~::
C CRO-I96
'* 1041iX. fi:. L': ~~,
~ ~;.I ~ ::::~ I~ .. ::::85 B '1lIl-105 ;'
CRO-IO! 45 A CRO-I33 .~ ,. CRD-160 63.A 186 CIIl-187
~ ~ft ~
4:'ru. CRC>-IOl eRCH61 B CRO'lee CRD-152 C CltO-189
~
CRO-I08 1<1+134 /i\ 1._~ G:
fi::, .~ Q RIl-l61
~
"tHO? R'Hfl>l
- t. RH-IO I RH-i35 E R.<-I62 "'He9
,Ca) ,.- IIOLn CT'fP, ... ~D)
- p. CJ.C rru. 'O-(:'-RC~D11_Q1
- cv...... ;n G!'1t~u::, ~,~ r...:- '<'~ ~ IS[ n ...... ~.I .... ~
~ L:~-
lHl$ "5
- l __ . ~
[WATtoN -viEW I'OA ~ ~ \tI/E.~ .. ~ll'tto.. SkETCM TNI- I l .0\.T.lMQ. so:. ~Go;. ltHS1-~-O'o..
A ~ DRIVE
~[c.",~
I I~ ... I jUVl.JP -
c;r..GQl L
"..0/ ~""~IJ ("""""-"- ~",-y,)
,. U~/iP"(Il:>~'
ol.l~fI'tIIOCRUK c;......
Ctl:t)loo1 HOl..l5l'W.a.,
~R~~ ~G.
1~1 "t:eero!!~v..b bTl' 1 I IMG.-el't.
DWO. NO.
5 4 .1 2 8 7 6..
Figure 2 Weld CRD-151 45 Degree Examination Coverage Sketch