ML20148C921
| ML20148C921 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/23/1997 |
| From: | Muench R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-97-0031, ET-97-31, NUDOCS 9705290290 | |
| Download: ML20148C921 (29) | |
Text
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4 t
W4pLF CREEK j
NUCLEAR OPERATING CORPORATION t
May 23, 1997 ET 97-0031 Richard A. Muench j
Vice President Engineering l
U. S. Nuclear Regulatory Commission l
ATTN:
Document Control Desk Mail Station Pl-137 Washington, D.
C.
20555 3
l Reference 1)
Letter WM 93-0094, dated August 11, 1993, from N.
2)
Letter Wh 34-0027, dated February 16, 1994 from 1
N.
S.
Letter WM 95-0005, dated January 26, 1995, from N.
S.
Subject:
Docket No. 50-482:
Inservice Inspection Program Relief Requests I1R-46 through I1R-49 and I2R-21 i
i Gentlemen:
l This letter transmits requests for relief from ASME Section XI requirements for the Wolf Creek Generating Station Inservice Inspection (ISI) Program in j
accordance with 10 CFR 50. 55a (g) (5) (iii).
The attachment to this letter provides Relief Requests I1R-46 and IlR-47 which are generated as a result of j
examination activities during Refuel VI and Refuel VII, respectively, with 3
supplemental examinations completed during Refuel VIII.
Reference 1
l transmitted the Wolf Creek Nuclear Operating Corporation (WCNOC) Inservice i
Inspection Report following Refuel VI.
Reference 2 transmitted an Inservice l
Inspection Program Relief Request.
Reference 3 transmitted the Inservice Inspection Report following Refuel VII.
In addition, the attachment provides i
Relief Requests I1R-48, IlR-49 and I2R-21.
The weldr identified in Relief Requests IIR-46 and IIR-47, as well as a number of other welds, were required to be re-examined when Relief Request IlR-32, which was submitted by Reference 2,
was denied.
As a result of subsequent j
examinations, only the two welds identified in I1R-46 and IIR-47 require relief from ASME Section XI requirements.
Therefore, all other welds identified by the References, for the submittal of Relief Requests, have either had relief requests approved or have been examined and satisfy ASME Section XI requirements and no longer require relief.
1 i
Relief Requests I1R-48 and IIR-49 are submitted for examinations performed on the Reactor Pressure Vessel during Refuel VIII as part of the final First 10-j Year Inservice Inspection Interval examination requirements.
Relief Request
]
I2R-21 is also submitted for other examinations performed on the Reactor Pressure Vessel during Refuel VIII.
However, this relief request is being i
j submitted for the Second 10-Year Inservice Inspection Interval.
1
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280069 pg' (
i 9705290290 970523 hk k 'gV %h.
PDR ADOCK 05000482 O
PDR a
j PO. Box 411 i Burhngton, KS 66839 ! Phone: (316) 364-8831 An Equal Opportundy Employer M F HC/ VET
i ET,*97-0031 Page 2 of 2 If you should have any questions regarding this submittal, please contact me at (316) 364-8831, extension
- 4034, or Mr.
Richard D.
Flannigan at extension 4500.
Very truly yours, Richa d A. Muench RAM /jad Attachment cc:
E.
W.
Merschoff(NRC), w/a W.
D.
Johnson (NRC), w/a J.
F.
Ringwald (NRC), w/a J.
C.
Stone (NRC), w/a l
I
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j
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i Attachment to ET 97-0031 Page 1 o'f 27 RELIEF REQUEST llR-46 Page 1 of 2 Component Identification EP-02-F021, Accumulator Safety Injection Valve 8818C to 6" Pipe Cetegory:
ASME Section XI 1980 Edition up through and including 1981 Winter Addendu, Table IWB-2500-1, Examination Category B-J, Item Number B9.11.
l Examination Requirement:
Requires the inner 1/3t of the weld plus 1/4" of the base metal beyond the weld toe be ultrasonically scanned in two directions as specified by Appendix III, paragraph 111-4420 and Figure IWB-2500-8.
Relief Requested Pursuant to 10 CFR 50.55a(g)(5) (iii), reliefis requested for the first inspection interval on the basis that conformance with the code requirements is impractical.
i Reliefis requested from the requirement to volumetrically examine this weld per ASME Section XI and Section V, due to limitations associated with the piping design and configuration.
Brsis for Relief:
As a resull. of geometry and metallurgical properties, the piping configuration does not provide an adequate examination surface to allow a complete examination from two directions (i.e., pipe to valve). 28.6% of the weld required volume received coverage from the axial scans in both beam directions and 28% of the weld required volume did not receive any coverage in either direction from the axial scans (Reference Figure 1).
Extended angle beam path ultrasonic techniques and higher angled beams (70 ) were utilized to obtain the maximum coverage possible. The subject weld did receive full coverage from the circumferential scans in both beam directions. A significant portion of the required volume was examined which provides for detection of significant patterns of degradation. In addition, the required surface examination was performed satisfactorily and the ASME.Section XI visual examination VT-2 was performed as required.
l Based on this information, reasonable assurance of the continued inservice structural integrity of the subject weld is achieved without performing a complete Code examination. Compliance with the applicable Code requirements can not be achieved.
t l
1 r
w
i j
Attachment to ET 97-0031 Pap 2 o'f 27 RELIEF REQUEST IIR-46 Page 2 of 2 Proposed Alternative Examination:
None. Extended angle beam path ultrasonic techniques and higher angled beams (70 ) were utilized to obtain the maximum coverage possible.
FIGURE 1 EP-02-F021 Scan Limitations (Not to scale) y Scan Limits\\
Pipe Clamp b
h
/
WRV for EP-02-F021 1
Portion of WRV receiving no coverage - 28%
Portion of WRV receiving two directional coverage - 28.6%
l
. _ ~ _ _ _ _
i i
Attachment to ET 97-0031 I~
Page 3 oT 27 RELIEF REQUEST 11R-47 Page1of2 Component Identification EP-02-FW303, Accumulator Safety Injection Valve 8808B to 10" Pipe Category:
ASME Section XI 1980 Edition up through and including 1981 Winter Addenda, Table IWC-2500-1, Examination Category C-F, Item Number C5.21.
Examination Requirement:
Requires the inner 1/3t of the weld plus 1/4" of the base metal beyond the weld toe be ultrasonically scanned in i
two directions as specified by Appendix III, paragraph 111-4420 and Figure IWC-2500-7.
Relief Requested Pursuant to 10 CFR 50.55a(g)(5) (iii), reliefis requested for the first inspection interval on the basis that conformance with the code requirements is impractical.
Reliefis requested from the requirement to volumetrically examine this weld per ASME Section XI and Section V, due to limitations associated with the piping design and configuration.
l Basis for Relief:
As a result of geometry and metallurgical properties, the piping configuration does not provide an adequate examination surface to allow a complete examination from two directions (i.e., pipe to valve). 34.4% of the weld required volume received coverage from the axial scans in both beam directions (Reference Figure 1). The remaining portion of the weld required volume received coverage from the axial scans in one beam direction.
Extended angle beam path ultrasonic techniques and higher angled beams (70 ) were utilized to obtain the maximum coverage possible. The subject weld did receive full coverage from the circumferential scans in both beam directions. A significant portion of the required volume was examined which provides for detection of significant patterns of degradation. In addition, the required surface examination was performed satisfactorily and the ASME Section XI visual examination VT-2 was performed as required.
Based on this information, reasonable assurance of the continued inservice structural integrity of the subject weld is achieved without performing a complete Code examination. Compliance with the applicable Code requirements can not be achieved.
l
At tach:ncht to ET 97-0031 Pacye 4 o'f 27 RELIEF REQUEST llR-47 Page 2 of 2 Proposed Alternative Examination:
None. Extended angle beam path ultrasonic techniques and higher angled beams (70 ) were utilized to obtain the maximum coverage possible.
FIGURE 1 EP-02-W303 Scan Liraitations (Not to scale) toe Scan Limit C/L Scan Limit I
l Portion of WRV receiving two directional coverage - 34.4%
. - - -. ~.
Attachment to ET 97-0031 Page 5 o'f 27 RELIEF REQUEST llR-48 Page1of13 Component Identification Class 1-Reactor Pressure Vessel Shell and Bottom Head Welds f
Weld ids:
l-RV-101-122A, -122B, -122C, 1
l l-RV-101-141, 1-RV-102-151, 1-RV-101-154 A, -154B, -154C, -154D l
Examination Requirements I
ASME Section XI,1980 Edition through Winter 1981 Addenda, Table IWB-2500-1, Examuation Category B-A, Item Nos., Bl.12, Bl.21, and Bl.22 requires 100% volumetric examination of the weld plus 1/2 the wall thickness of adjacent base metal on each side of the weld crown.
ASME Section V,1980 Edition through Winter 1981 Addenda, Article 4, T-441.4, specifies that this volume is to be examined with two angle beam scans (i.e.,45 and 60 nominal) for reflectors transverse to the weld seam, with two angle beam scans for reflectors parallel to the weld seam, and with a straight (0 ) beam scan for planar and laminar reflectors.
An additional 70 angle beam examination was performed for near surface (ID) coverage.
Relief Requested Pursuant to 10 CFR 50.55a(g)(5)(iii), reliefis requested for the first inspection interval on the basis that conformance with the code requirements is impractical.
Reliefis requested from the requirement to volumetrically examine the following welds per ASME Section XI and Section V, due to limitations associated with the vessel design and configuration.
Item Number Weld ID Reference Sketch Composite CRV Achieved Bl.12 1-RV-101-122A(Weld 6)
Figure 1 66.7 %
Bl.12 1-RV-101-122B (Weld 7)
Figure 1 69.9 %
Bl.12 1-RV-101-122C (Weld 8)
Figure 1 74.4 %
Bl.21 1-RV-101-141 (Weld 4)
Figures 1 & 2 65.3 %
Bl.21 1-RV-102-151 (Weld 5)
Figure 3 48.2 %
Bl.22 1-RV-101-154A (Weld 15)
Figures 1,4, & 5 74.8 %
B l.22 1-RV-101-154B (Weld 16)
Figures 1,4, & 5 74.8 %
Bl.22 1-RV-101-154C (Weld 17)
Figures 1,4, & 5 74.8 %
Bl.22 1-RV-101-154D (Weld 18)
Figures 1,4, & 5 74.8 %
l NOTE: Weld numbers shown in parenthesis are in the reference sketches only.
1
Attachment to ET 97-0031 Pag.e C 6f 27 RELIEF REQUEST IIR-48 Page 2 of 13 Basis for Relief Reactor Vessel design and configuration prevents 100% ultrasonic (UT) examination of the code required volume (CRV) for the subject welds. The specific limitations for each weld examination are discussed below and detailed on the applicable attachments and figures. Calculation of the CRV Achieved Percentages is based on a conservative approach which employs the UT central ray data only; beam spread was not taken into account.
1.
Bl.12 Longitudinal Welds 1-RV-101-122A, B & C Limitations Physical limitations for all three welds are due to nozzle geometry and location in the upper shell course i
relative to the longitudinal weld location as well as flange to shell weld ID taper as shown on Figure 1.
Composite coverage of the UT scans was calculated to be 66.7%,69.9%, and 74.4% for Weld A, B, and C, respectively. Attachments 1,2, & 3 provide a summary of the inspection coverage.
2.
Bl.21 Circumferential Weld 1-RV-101-141 Limitations Physical limitations of the UT scans of this circumferential weld were due to the six (6) core support lugs as depicted on Figure 2 attached. Composite coverage of the UT scans was calculated to be 65.3%.. Attachment 4 provides a summary of the inspection coverage.
3.
Bl.21 Circumferential Weld 1-RV-102-151 Limitations Physical limitations of the UT scans of this bottom head circumferential weld were due to bottom mounted instrumentation (BMI) tubes. Fifty-eight total; of which, approximately 29 interfere with scan coverage as shown on Figures 3 & 4 attached. Composite coverage of the UT scans was calculated to be 48.2%. Attachment 5 provides a summary of the inspection coverage.
4.
Bl.22 Meridional Welds 1-RV-101-154A, B, C & D Physical limitations of the UT scans of the four bottom head meridional welds were due to the location of BMI tubes and the core support lugs as shown on Figures 1,3 & 4. Composite coverage of the UT scans was calculated to be 74.8%. Attachment 6 provides a summary of the inspection coverage.
The Reactor Vessel was designed and fabricated in accordance with the stringent quality controls of ASME Section III; subsequent volumetric and surface examinations as well as pressure testing was perfonned on these welds with acceptable results. A significant portion of the required volume was examined which provides for detection of significant pattems of degradation Based on this information, reasonable assurance of the continued inservice structural integrity of the subject welds is achieved without performing a complete Code exa:nination. Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Reactor Vessel. WCNOC deems this course of action impractical.
At tachmerit to ET 97-0031 j
Page 7 Of 27 1
l RELIEF REQUEST IlR-48 l
Page 3 of 13 Proposed Alternative Examinations No additional volumetric examinations will be performed. The RPV welds have been examined to the maximum extent practical.
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Attachment to ET 97-0031 Pacje 8 o'f 27 RELIEF REQUEST 11R-48 Page 4 of13 i
1 f
ATTACHMENT 1 i
Weld # l-RV-101-122A Reactor Vessel Shell Longitudinal Weld i
3 1
l Examination Limitation:
4 Inlet nozzle radii and flange ID taper i
Composite Coverage: 66.7 %
Inspection Volume Coverage Summary:
Parallel (2 angles): 82.9 %
Parallel (2 angles + 2 directions): 69.7%
i Perpendicular (2 angles): 50.5%
,j Perpendicular (2 angles + 2 directions): 50.5 %
^
Zero Degree: 60.5 %
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Attachment to ET 97-0031 Page;9 df 27 RELIEF REQUEST llR-48 Page 5 of 13 ATTACIIMENT 2 Weld #1-RV-101-122B Reactor Vessel Shell Longitudinal Weld Examination Limitation:
Outlet nozzle protrusion and flange ID taper
?
Composite Coverage: 69.9 %
Inspection Volume Coverage Summary:
i Parallel (2 angles): 62.6 %
i Parallel (2 angles + 2 directions): 33.1 %
1 Perpendicular (2 angles): 77.1 %
Perpendicular (2 angles + 2 directions): 77.1%
Zero Degree: 77.1 %
Attachment to ET 97-0031 Pa'ge 10 of 27 RELIEF REQUEST IlR-48 l
Page 6 of 13 4
4 ATTACIIMENT 3
.i Weld #1-RV-101-122C l
Reactor Vessel Shell Longitudinal Weld j
Examination Limitation:
i I
Outlet nozzle protrusion and flange ID taper l
1 Composite Coverage: 74.4 %
j Inspection Volume Coverage Summary:
4 Parallel (2 angles): 61.2%
Parallel (2 angles + 2 directions): 41.3%
Perpendicular (2 angles): 87.6 %
Perpendicular (2 angles + 2 directions): 87.6 %
I Zero Degree: 87.6 %
l l
Attachment to ET 97-0031 i
Pdge 11 of 27 RELIEF REQUEST IlR-48 Page 7 of 13 ATTACIIMENT 4 Weld #1-RV-101-141 Reactor Vessel Bottom IIcad-to-Shell Weld Examination Limitation:
Core Support obstruction Composite Coverage: 65.3 %
Inspection Volume Coverage Summary:
Parallel (between lugs): 100 %
Parallel (under lugs,2 angles): 19.3 %
Parallel (weighted average): 66.0 %
Perpendicular (between lugs): 100 %
Perpendicular (under lugs,2 angles): I?.8%
Perpendicular (weighted aveage): 64.6 %
Zero Degree: 59.4 %
I
Abtachment to ET 97-0031 Pdge 12 of 27 RELIEF REQUEST IlR-48 Page 8 of 13 ATTACHMENT 5 Weld #1-RV-102-151 Reactor Vessel Hottom Head Circumferential Weld Examination Limitation:
l Bottom mounted instrumentation (BMI) tubes (58 tubes total--approximately 29 interfere with scan coverage)
Composite Coverage: 48.2 %
Inspection Volume Coverage Summary:
Parallel (2 angles,2 directions): 25.2 %
Parallel (2 angles): 35.0%
Perpendicular (2 angles): 61.3 %
Zero degree: 38.4 %
Attachment to ET 97-0031 Pdge 13 of 27 RELIEF REQUEST 11R-48 Page 9 of 13 ATTACIIMENT 6 Weld #1-RV-101-154A Weld #1-RV-101-154B Weld #1-RV-101-154C Weld #1-RV-101-154D Reactor Vessel Lower IIcad Meridional Welds
)
Examination Limitation:
Location of BMI tubes and the core support lugs Composite Coverage: 74.8 %
Inspection Volume Coverage Summary:
Parallel (2 angles): 51.2 %
Parallel (2 angles + 2 directions): 27.2 %
Perpendicular (2 angles): 98.4%
Perpendicular (2 angles + 2 directions): 93.6 %
Zero Degree: 93.6 %
I
Attachment to ET 97-0031 I
Page 14 of 27 RELIEF REQUEST IIR-48 Page 10 of 13 FIGURE 1 i
Reactor Pressure Vessel Rollout View (Not to scale)
A B
C D
E F
C H
OUTLET #1 RET.1 KET.2 OUTLET.2 CUTLET.3 KET.3 R ET.4 OUTLET.4 22' 67' 113' 15 8*
202*
247' 293*
338
- 14.5 0*
90' 18 0 '
270*
36&
l 4 F ll-R v-101-121 N l
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46.60 95'.66 I 42.63 71.00 k
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- 14 11-RV Oi 141 1 16.8 0 15.67'NOW 44,33* NOW 46.98' NOW 13.02' NOW SUPPORT 8 UTTERING BUTTERING,
WT TEM
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At[tachment to ET 97-0031 Page 15 of 27 i
l RELIEF REQUEST IIR-48 Page11of13 l
FIGURE 2 Lower Shell to Bottom Head Circumferential Weld 1-RV-101-141 (Not to scale) i l
Core Support Lugs Typical of six (6) l1-RV-101-141 l l
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a Att a chment to ET 97-0031 Page 30 of 27 RELIEF REQUEST 11R-48 Page 12 of 13 FIGURE 3 Bottom IIcad Torus 1-RV-101-141 (see Figure 2) 1-RV-101-154-A 1-RV-101-154-B l-RV-101-154-C 4 meridional welds 90 1-RV-101-154-D degrees around bottom head torus (see Figure 4)
\\
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ttom Head Penetration (s)
/
l-RV-102-151 s
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Attachment to ET 97-0031 Pdge 17 of 27 RELIEF REQUEST 11R-48 Page 13 of 13 FIGURE 4 Reactor Vessel Bottom licad l
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l-RV-101-154-A j
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1 Attachment to ET 97-0031' Page 18 of 27 RELIEF REQUEST 11R-49 Page 1 of 5 Component Identification:
Class 1 - Reactor Pressure Vessel Inlet Nozzle Welds Weld ids:
1-RV-105-121 A, -121 B, -121C, and -121 D l
Examination Requirements:
ASME Section XI,1980 Edition through Winter 1981 Addenda, Table IWB-2500-1, Examination Category B-D, Item No. B3.90 requires 100% volumetric examination of the weld plus 1/2 the wall thickness of adjacent base metal on each side of the weld crown.
ASME Section V,1980 Edition through Winter 1981 Addenda, Article 4, T-441.4, specifies that I
this volume be examined with two angle beams scans (i.e.,45* and 60 nominal) for reflectors transverse to the weld seam, with two angle beam scans for reflectors parallel to the weld seam, and with a straight (0 ) beam scan for planar and laminar reflectors.
I An additional 70 angle beam examination was utilized for near surface (ID) coverage, up to a depth of 1" or 1/4t, whichever is greater.
Relief Requested:
l l
Pursuant to 10 CFR 50.55(g)(5)(iii), reliefis requested for the first inspection interval on the basis that conformance with the code requirements is impractical.
Reliefis requested from the requirement to volumetrically examine the subject welds per ASME Section XI and Section V due to limitations associated with the vessel design and configuration.
Basis for Relief:
Reactor Vessel design and configuration prevents 100% ultrasonic (UT) examination of the code required volume (CRV) for the subject welds. The specific limitations for each weld examination are discussed below and detailed on the applicable attachments and figures.
Calculation of the CRV achieved percentages is based on a conservative approach which employs the UT central ray data only; beam spread was n_ot taken into account.
I Physical limitations of the UT scans of the Inlet Nozzle to Vessel Welds were doe to the nozzle radius configurations which prevented full coverage as shown on Figures 1 and :. Composite coverage of the UT scans was calculated to be 73.2% for each weld. A' 3chment 1 provides a i
summary of the inspection coverage.
l
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Attachment to ET 97-0031 Page 19 of 27 l
RELIEF REQUEST IIR-49 l
Page 2 of 5 l
Basis for Relief (continued).
The Reactor Vessel was designed and fabricated in accordance with the stringent quality controls of ASME Section Ill; subsequent volumetric and surface examinations as well as pressure testing l
was performed on these welds with acceptable results. A significant portion of the required volume was examined which provides for detection of significant patterns of degradation.
Based on this information, reasonable assurance of the continued inservice structural integrity of the subject welds is achieved without performing a complete Code examination. Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Reactor Vessel. WCNOC deems this course of action impractical.
b Proposed Alternative Exams No additional volumetric examinations will be performed. The RPV welds have been examined to the maximum extent practical.
u i
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Attachment to ET 97-0031 Pdge 20 of 27 j
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RELIEF REQUEST 11R-49 Page 3 of 5 i
ATTACilMENT 1 i
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Welds #1-RV-105-121 A, H, C, D
)
Reactor Vessel Inlet Nozzle-to-Shell Welds Examination Limitation:
Nozzle radius section configuration Composite Coverage: 73.2 %
Inspection Volume Coverage Summary:
Parallel (2 angles): 56.3%
Perpendicular (2 angles): 81.9 %
Zero Degree: 56.3 %
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Attachment to ET 97-0031 1
Page 21 of 27 l
l RELIEF REQUEST IIR-49 l
Page 4 of 5 i
l FIGURE 1 Reactor Pressure Vessel Rollout View l
(Not to scale) i l
l r
A B
C D
E F
C H
OUTLET #1 KET #1 INLET #2 OUTLET #2 OUTLET #3 INLET e3 lNLET #4 OUTLET e4 22' 67*
113 '
15 8*
202*
247' 293" 338*
14.5 j
O' 90' 18 0 '
270' 360"
^
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11-RV 101 121N l
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99.63 l
46.60 95.66 I 42.63 71.00 i
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l1.Rv.mt.124 ::
lg.py.es.g7, i
- 3 Il-Rv 101-142 BH l
11-Rv-101-14 2-A:
gg.gy. 01-14 2 -C W SUPPORT LUCS AT4
- '2 0*.60*.120'.160' l
- 14 l
240* 6 300' NOW \\
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e Attachment to ET 97-0031 Page 22 of 27 RELIEF REQUEST IlR-49 Page 5 of 5 FIGURE 2 1
Inlet Nozzle Exam Areas
]
(Not to scale)
]
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1 l-RV-105-121-A l-RV-105-121-B g
l-RV-105-121-C
+ rop s.
l-RV-105-121-D f*
/
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e Attachment to ET 97-0031 Page 23 of 27 RELIEF REQUEST 12R-21 Page 1 of 5 Component Identification:
Class 1 - Reactor Pressure Vessel Outlet Nozzle Welds Weld ids:
1-RV-107-121 A, -121 B, -121 C, -121 D Examination Requirements:
ASME Section XI,1989 Edition, Table IWB-2500-1 Examination Category B-D, Item No.
B3.90 requires 100% volumetric examination of the weld plus 1/2 the wall thickness of the adjacent base metal on each side of the weld.
ASME Section V,1989 Edition, Article 4,'1441.3.2.1, specifies that this volume be examined J
with three angle beams having nominal angles of 45",60*, & 70* for reflectors transverse and parallel to the weld seam. A straight beam scan (0 ) is also required for planar and laminar reflectors. The 70 angle beam examination is utilized for near surface (ID) coverage, up to a l
depth of 1" as required by ASME Section XI,1989 Edition, Appendix 1.
I Relief Requested:
1 Pursuant to 10 CFR 50.55(g)(5)(iii), reliefis requested for the second inspection interval on the
)
basis that conformance with the code requirements is impractical.
4 i
Reliefis requested from the requirement to volumetrically examine the subject welds per ASME Section XI and Section V due to limitations associated with the vessel design and configuration.
Basis for Relief:
Reactor Vessel design and configuration prevents 100% ultrasonic (UT) examination of the code required volume (CRV) for the subject welds. The specific limitations for each weld examination are discussed below and detailed on the applicable attachments and figures.
Calculation of the CRV achieved percentages is based on a conservative approach which employs the UT central ray data only; beam spread was not taken into account.
Physical limitations of the UT scans of the Outlet Nozzle to Vessel Welds were due to the outlet i
nozzle protrusion on configurations which prevented full coverage as shown in Figures 1 and 2.
Composite coverage of the UT scans was calculated to be 71.5% for each weld. Attachment 1 provides a summary of the inspection coverage.
l 1
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Attachment to ET 97-0031 3
Page 24 of 27 2
RELIEF REQUEST 12R-21 l
Page 2 of 5 1
Hasis for Relief (continued) i The Reactor Vessel was designed and fabricated in accordance with the stringent quality controls of ASME Section III; subsequent volumetric and surface examinations as well as pressure testing was performed on these welds with acceptable results. A significant portion of the required l
volume was examined which provices for detection of significant pattems of degradation, t
Based on this infi rmation, reasonable assurance of the continued inservice structural integrity of the subject welds is achieved without performing a complete Code examination. Compliance with the applicable Code requirements can only be accomplished by redesigning and refabricating the Reactor Vessel WCNOC deems this course of action impractical.
4 l
Proposed Alternative Exams:
l No additional volumetric examinations will be performed. The RPV welds have been examined to the maximum extent practical.
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Attachment to ET 97-0031 Phge 25 of 27 RELIEF REQUEST 12R-21 Page 3 of 5 ATTACHMENT 1 Welds #1-RV-107-121 A, B, C, D Reactor Vessel Outlet Nozzle-to-Shell Welds Examination Limitation:
Outlet nozzle protrusions Composite Coverage: 71.5 %
inspection Volume Coverage Summary:
Parallel (2 angles): 43.2%
Perpendicular (2 angles): 99.7 %
Zero Degree: 43.2 %
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=.. e Attschment to ET 97-0031 Page 26 of 27 RELIEF REQUEST 12R-21 Page 4 of 5 FIGURE 1 Reactor Pressure Vessel Rollout View
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Att achment to ET 97-0031 Page 27 Of 27 RELIEF REQUEST 12R-21 Page 5 of 5 FIGURE 2 Outlet Nozzle Exam Areas (Not to scale) a 1-RV-107-121 A 1-RV-107-121 B gggV
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