ML20196H005
| ML20196H005 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 07/10/1997 |
| From: | Barron H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEIN-96-032, IEIN-96-32, NUDOCS 9707230272 | |
| Download: ML20196H005 (39) | |
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_ Duke,
, ,Power
< Company ui Nuckar Station ng 12700 Hagers Fctry Rd. !
- l. HuntersviUe, NC 28078-9340 H. B. Barron Vice hesident, McGuire (704) 875-4800 omce Nuclear Generation Department (704) 875-4809 fax l-
! July 10, 1997 U.S. Nuclear Regulatory Commission Attention: Document Control Desk
' Washington, DC 20555 '
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369 Request for Alternative Examination, M97-002 i l
Dear Sir:
l Duke Power Company has determined that it is unable to I
completely satisfy the requirements for the augmented '
reactor vessel shell weld examination for McGuire Nuclear Station, . Unit I as specified in 1CCFR50.55a(g) (6) (ii) (A) .
Pursuant to provisions of 10CFR 50.55a(g) (6) (ii) (A) (5) ,
please find enclosed information to support the determination and a proposed alternative examination that will provide and acceptable level of quality and safety.
Should questions arise'regarding this. matter, please contact
-J.M. Washam at (704) 875-4181.
Very truly yours, f
ni H.B. Barron
{C l 9707230272 970710 l PDR ADOCK 05000369
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l U.S. Nuclear Regulatory Commission July 10, 1997 l Page 2 .
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l xc. Mr. L.A. Reyes ;
Regional Administrator, Region II I U.S.' Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 ,
Atlanta, Georgia 30323 1
Mr. Victor Nerses, Project Manager l Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l One White Flint North, Mail Stop 9H3 )
Washington, DC 20555 l
i Mr. Scott M. Shaeffer, l Senior NRC Resident Inspector, McGuire
- j McGuire Nuclear Station l l
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Duke Energy Corporation Station: McGuire Nuclear Station, Unit 1 10 Year Interval Request For Alternative No.97-002 Pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5), Duke Energy has determined that it is unable
- to conform with the examination requirements of 10 CFR 50.55a(g)(6)(ii)(A) for McGuire Nuclear Station, Unit 1. Information is therefore being submitted in support of this determination, and a request for alternative pursuant to 10 CFR 50.55a(g)(6)(ii)(A)(5) is being sought from the requirements of 10 CFR 50.55a(g)(6)(ii)(A).
Background:
In response to NRC Information Notice 96-32, " Implementation of 10 CFR 50.55a(g)(6)(ii)(A) " Augmented Examination of Reactor Vessel", Duke Energy has reviewed the information contained in this notice for applicability to its facilities and has taken action to avoid or mitigate the effects of limited examinations. These actions are taken to eliminate and/or reduce the concerns expressed in this Information Notice.
Because of concerns regarding the scope of examination of reactor vessels, the NRC issued, in 1992,10 CFR 50.55a(g)(6)(ii)(A), " Augmented Examination of Reactor I Vessel", which contains requirements for an augmented examination of reactor vessels.
The rule requires the licensee to implement, before the time required by normal updating of the inservice inspection (ISI) program, provisions in the 1989 Edition of the ASME, Boiler and Pressure Vessel Code,Section XI, to examine " essentially 100%" of the length of all reactor vessel shell welds. " Essentially 100%" examination as used in 10 CFR ,
50.55a(g)(6)(ii)(A)(2) means "more than 90% coverage of the examination volume of each weld, where the reduction in coverage is due to interference by another component, or part geometry."
In many cases, licensees have determined that the overall average examination coverage for reactor vessel shell welds may be more than 90%. Ilowever, the corresponding.
examination coverage for individual welds may be substantially less than 90%. In these cases, licensees are unable to completely satisfy the requirements for the augmented reactor vessel examination. They must therefore propose an alternative that would provide an acceptable level of quality and safety.
The licensee must expend all efforts using the latest methods and techniques to achieve acceptably adequate examinations during weld inspections. When examinations cannot be completed with " essentially 100%" coverage, then a request for alternatives from the Code of Federal Regulations must be submitted.
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- 1. System / Components For Which Alternative is Requested:
In response to the requirements of 10 CFR 50.55a(g)(6)(ii)(A) relief is requested for seven McGuire Unit I reactor pressure vessel shell welds speciGed in Examination Category B-A Item Bl.10. These welds, listed below, were examined and found to have 90% coverage or less. Attachment I provides examination data for these welds which were examined during Refueling Outage 7, and for which relief is requested from the requirement for augmented examination of the reactor vessel.
- a. Reactor Vessel Shell Welds Weld Numbers Item Numbers 1RPV10-442 B01.0l l.003 1RPVl-442A B01.012.001 1RPVl-442B B01.012.002 1RPVl-442C B01.012.003 1RPV3-442 A B01.012.007 1RPV3-442B B01.012.008 1RPV3-442C B01,012.009
- 11. 10CFR50 Requirement:
4 1
10 CFR 50.55a(g)(6)(ii)(A) requires' that all licensees shall augment their reactor vessel examination requirements at least once for the reactor vessel shell welds specified in Item Bl.10 of Examination Category B-A " Pressure Retaining Welds
, in Reactor Vessel"in Table IWB-2500-1 of Subsection IWB of the 1989 Edition of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code. 10 CFR 50.55a(g)(6)(ii)(A) further states that "for the purpose of this augmented examination essentially 100% as used in Table IWB-2500-1 means more than 90
% of the examination volume of each weld, where the reduction in coverage is due to interference by another component, or part geometry." The augmented examination, when not deferred in accordance with the provisions of 50.55a(g)(6)(ii)(A)(3), shall be perfonned in accordance with the related procedures specified in the Sect.on XI Edition and Addenda applicable to the inservice inspection interval in effect on September 8,1992, and may be used as a substitute for the reactor vessel shell weld examination scheduled for implementation during the inservice inspection interval in effect on September 8, 1992. 10 CFR 50.55a further states that " Licensees that make a determination that they-are unable to completely satisfy the requirements for the augmented reactor vessel shell weld examination speciGed in 10 CFR 50.55a(g)(6)(ii)(A) shall submit information to the Commission to support the determination and shall propose an alternative to the examination requirements that would provide i an acceptable level of quality and safety." !
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l Ill. Requirement for which Alternative is Requested:
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An alternative is being requested to the requirement of obtaining " essentially 100%" examination volume of weld coverage for McGuire Unit I reactor vessel Bl.10 welds listed in section I and shown in Attachment 1.
IV. Basis for requesting Alternative:
If licensees make a determination that they are unable to completely satisfy the requirements for the augmented reactoi vessel shell weld examination specified in 10 CFR 50.55a(g)(6)(ii)(A); then 10 CFR 50.55a(g)(6)(ii)(A)(5) requires the licensee to submit information to the Commission to support this determination '
and to propose an alternative to the examination requirements that would provide an acceptable level of quality and safety. The licensee may use the proposed !
alternative when authorized by the Director of the Office of NRR.
l Attachment 2 provides the calculations documenting the actual amount of Code I required examination coverage obtained. A combination of multiple angles and ultrasonic techniques was used to obtain the maximum coverage possible. The use of an alternate transducer head provided. increased coverage through optimum transducer arrangement for scanning close to obstructions. However, during the ultrasonic examhation of the welds referenced below and listed in Attachment 1 of this alternative, the greater than 90% coverage required per 10 CFR 50.55a(g)(6)(ii)(A)(2) could not be obtained due to geometry and actual physical barriers.
Reactor Vessel Lower Shell to Bottom Head Weld ( 1RPV10-442)
(Item Number B01.011.003):
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This examination was limited to 59.00%. aggregate coverage of the required weld volume. The principal limitation for this weld is six core guide lugs welded to the vessel ID just above the weld on the lower shell section, whose presence restricts the scanning surface in that area aid limits the examination coverage. These lugs are approximately 19 inches tall,27 inches wide and extend 8 inches radially toward the center of the vessel, the lugs are positioned 60 Degrees around the vessel circumference. These dimensions include the attachment weld radius which physically limited the contact transducer head travel during examination.
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i Reactor Vessel Uoper SheII Lona Seam Weld at 60 Deareel 1RPV1-442A)(Item Number 801.012.001):
This examination was limited to 90.00% aggregate coverage of the required weld volume. The principal limitation for this weld involves nozzle interference which divides the weld into two parts. The Reactor Vessel Nozzle configuration
, prevents examination of the weld at the intersection of the weld and nozzle The specific limitations are identified on drawing 1213926D. l l
Reactor Vessel Upoer Shell Lona Seam Weld at 180 Deareel 1RPV1-4428)(Item Number 801.012.002): j This examination was limited to 31.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the location of the long seam weld between the two outlet nozzles. The close proximity of the long seam weld to the outlet nozzles physically limits examination of the weld in the area between the nozzles. The specific limitations are identified on drawing 1213926D. ,
I Reactor Vessel Upper Shell Lona Seam Weld at 300 Dearee( 1RPV1-442C)(Item Number 801.012.003):
This examination was limited to 90.00% aggregate coverage of the required weld volume. The principal limitation for this weld involves nozzle interference which divides the weld into two parts. The Reactor Vessel Inlet Nozzle configuration prevents examination of the weld at the intersection of the weld and nozzle. The specific limitations are identified on drawing 1213926D.
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Reactor Vessel Lower Shell Lona Seam Weld at 60 Deareel 1RPV3-442A) (Item Number B01.012.007):
This examination was limited to 84.00% argregate coverage of the required weld l volume. The principal limitation for this weld is the presence of the core guide l lugs welded to the vessel ID above weld 10-442 on the lower shell section. These lugs are approximately 19 inches tall,27 inches wide, extend 8 inches radially toward the center of the vessel, and are positioned every 60 Degrees around the vessel circumference. The dimensions include the attachment weld radius.
Because of their location, the lugs interfered with the axial and circumferential weld scans.
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- Reactor Vessel Lower SheII Lona Seam Weld at 180 Dearee( 1RPV3-
[ 4428)(Item Number B01.012.008):
This examination was limited to 84.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the presence of the core guide lugs welded to the vessel ID above weld 10-442 on the lower shell section. These lugs are approximately 19 inches tall,27 inches wide, and extend 8 inches radially toward the center of the vessel, and are positioned every 60 Degrees around the vessel circumference. The dimensions include the attachment weld radius, because of their location these lugs interfered with the axial and circumferential weld scans.
Reactor Vessel Lower SheII Lona Seam Weld at 300 Dearee( 1RPV3-442C)(Item Number B01.012.009):
This examination was limited to 84.00% aggregate coverage of the required weld volume. The principal limitation for this weld is the presence of the core guide lugs welded to the vessel ID above weld 10-442 on the lower shell section. These lugs are approximately 19 inches tall,27 inches wide, and extend 8 inches radially toward the center of the vessel, and are positioned every 60 Degrees around the vessel circumference. The dimensions include the attachment weld radius, because of their location these lugs interferred with the axial and circumferential weld scans.
} Veld Examination Summary The reactor vessel shell welds were examined from the vessel inside surface using automated ultrasonic examination equipment. The examinations were done with various contact h:ad arrangements to optimize the max'imum exammation coverage. This allowed each transducer to scan as close as possible to any obstruction around the area examined. Although the coverage requirements of 10 CFR 50.55a(g)(6)(ii)(A) could not be met, the examinations were performed with modified equipment and tooling designed to obtain the maximum coverage possible.
As a result of inspections performed, the 100% requirernent has been determined to create a hardship for McGuire Nuclear Station. The reactor vessel welds were examined to the maximum cxtent practical to the requirements of Section V,
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Article 4 of the 1980 Edition through the Winter 1980 Addenda of the ASME Boiler and Pressure Vessel Code and the additional requirements of Regulatory Guide 1.150, To meet the 10 CFR 50.55a(g)t6)(ii)(A)(2) examination coverage requirements, design modifications would be necessary to gain access to the welds in order to obtain complete coverage. The design modifications are impractical due to the vast scope of work that would be required. Imposition of this 5
O -- ,e requirement would cause a considerable burden on Duke Energy with -no commensurate safety benefit realized.
. V. Alternate Examinations:
In addition to the- volume'tric examination that has been performed on the McGuire reactor vessel, Duke Energy has performed a visual examination of the internals and the inside of the reactor vessel as required by ASME Section XI, Table IWB-2500-1, This visual examination did not identify any rejectable conditions per ASME Section XI acceptance standards.
The use of radiography as an alternate. volumetric examination method is not feasible due to component thickness and restrictions from physical barriers which -
. prohibit access for the placement of source, image quality indicators, film, etc. In addition, the background radiation levels would not allow for a radiographic examination that would render meaningful results'.
Performing the ultrasonic examination from the outside of the reactor vessel is not a viable option.' The design of McGuire's reactor building prohibits access for the equipment and personnel from outside the vessel.
Duke Energy. Corporation will continue to perform ultrasonic examinations of all 7 reactor vessel welds to the maximum extent practical in accordance with the requirements of ASME Section V, Article 4,1989 Edition and Regulatory Guide L 1.150, Revision -1, Appendix A. The application of Code Case N-460 will be j utilized in all cases where less than 100% but greater than 90% weld coverage is l
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t obtained. In cases where weld coverage of 90% or less is obtained, a request for relief from ASME Section XI Code requirements will be submitted.
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Duke Energy Corporation proposes as an alternative to the greater than 90%
coverage requirement of 10 CFR 50.55a(g)(6)(ii)(A), that' the examination j coverage obtained on the welds listed in Attachment i be considered to provide an f acceptable level'of quality and safety.
No additional examinations will be required.
4 1 VI. .
Justification for. Granting Alternative:
10 CFR 50.55a(A)(5) states that " Licensees that make a determination that they are unable to completely satisfy the requirements for the augmented reactor vessel l shell weld examin'ation specified in 50.55a(g)(6)(ii)(A) shall submit information to the Commission to support the determination and shall propose an alternative to the examination requirements that would provide an acceptable level of quality and safety. 10 CFR 50.55a(a)(3) states that alternatives to the requirements of
. paragraph (g) may be used when. authorized by the Director of the Office of
. Nuclear Reaetor Regulation. The proposed alternative (s) must demonstrate that an acceptable level of . quality and safety, or compliance with the specified y
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! I requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.- .1 1
1 Examination of 100% of reactor pressure vessel shell welds would result in i hardship and unusual difficulty without compensatory increase in safety being -
l realized. Examination of the . accessible weld volume provides sufficient and
- l. reasonable assurance ~ of vessel integrity. The reduction in the expected l examination coverage will not endanger life or property or the common defense :
i- and security because the reactor coolant system is designed and constructed to
- have a low probability of gross rupture or significant leakage throughout its design life. Technical Specifications 3/4.4.6 for McGuire Nuclear Station places conservative limits on the amount.of reactor coolant leakage allowed during -
system operation. Any weld failure would allow additional coolant to leak from
' the system. The reactor coolant system leakage detection system is in place to
- detect any variation in the system water inventory. The purpose of the containment building is to retain any such leakage within its boundaries. If
' leakage exceeds Technical Specification 3.4.6.2, procedures are in place to assure safe shutdown of the unit within specified time limits.
Due to the design of the McGuire reactor vessels and location of the physical
_ obstructions, it is not feasible to obtain the examination coverage required by 10 CFR 50.55a(g)(6)(ii)(A)(2) without placing ' undue hardship on Duke Energy. j Based on the portions of the required volumetric and visual examination that have i been completed, any existing pattern of degradation would have been detected.
l Duke Energy Company will continue to ultrasonically examine the reactor vessel Bl.10 category welds to the extent practical within the limits of original design and construction. This will provide reasonable assurance of weld / component integrity.
I Pursuant to 10 CFR 50.55a(g)(6)(i), granting this alternative for the reactor vessel !
Bl.10 category welds will provide reasonable assurance of weld / component I integrity, "is authorized by law, and will not endanger life or property or the {
common defense and security and is other wise in the public interest giving due '
consideration to the burden upon the licensee that could result if the requirement were imposed on the facility."
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Vll. Implementation Schedule:
i- The reactor vessel welds listed above will be examined during the third period of the second interval. The examinations are currently scheduled during EOC 15.
i 1-Attachments:
- 1. Listing ofinformation for welds with limited UT examination coverage
- 2. Detailed drawings of affected welds including calculation methods Onhudhn\c Date: 7[9 37 Evaluated B'Vanu Reviewed By: 1h d Date: .7 9 9'l 1
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ASME Class 1 NDE Inservice inspection Request For Alternative Serial No.97-002 - Attachment 1 For McGuire Unit i Based On ASME XI- 1980 Code 'Ihrough Winter 1980 Addenda Page1of1 Item No. Exam Category / - System Or Function - Atta To Be Reason For Request Weld ID No. Licensce Proposed Figure No. Component Examined Attemate FMnew B01.011.003 B-A Reactor Vessel Hases the fuel assembhes, controi lowerShell to Limited scan due to six core guide 1RPV10442 None IWB-2500-1 A and vessel intemals. als B u m Head lug estmcrions directs the flow of reactor coolant Weld Actual coverage obtamed = 59 00%
B01.012.001 B-A Reactor Vessel Houses the fuel assembhes, control Upper Shell Unuted scan due to nozzle gemm 1RPVI-442A None mas andvesselinternals,also long seam weld configuration.-
IWB-2500-2 directs the flow of reactor coolant at 60 Deg. Actual coverage obtained = 90.00%
B01.012.002 B-A Reactor Vessel . Houses the fuel assemblies, contml Upper Shell Unuted scan due to nozzle geometric IRPVI-442B - None
' dS.and vesselintemais,als long scam weld configuration.
IWB-2500-2 directs the flow of reactor coolant at 180 Deg. Actual coverage obtained = 31.00%
B01.012.003 - B-A Reactor Vessel Houses the fuel assembhes, control UpperShell Umtted scan due to nozzle geometrx 1RPVl-442C None IWB-2500-2 '*fS *"'I **SS*3 i"'*"*3% *l5 I"ng seam weld configuration directs the flow of reactor coolant at 300 Deg. Actual coverage obtained = 90.00%
B01.012.007 B-A Reactor Vessel Houses the fuel assembhes. control Imwer Shell Urruted scan due to core guide lug . IRPV3-442A None tais, and vesseuntemals, also W scarn weld estmction IWB-2500-2 directs the flow of reactor contant at 60 Deg. Actual coverage obtained = 84 00%
B01.012.008 B-A Reactor Vessel Houses the fuel assembues. control tower Shell Unuted scan due to core guide lug iRPV3-442B None IWB-2500-2 r ds.andvesselinternals als long seam weld obstruction -
directs the flow of reactor coolant at 180 Deg. Act sal coverage obtained = 84.00%
B01.012.009 B-A Reactor Vessel Houses the fuel assemblies, control lower Shell Umited scan due to cose guule lug . IRPV3-442C None IWB-2500-2
- 8"d **SS*U"'**^15 *lS s I""s eam weld estmetion directs the flow of reactor coolant at 300 Deg. Actual coverage obtained = 84 00%
. _ . . _ _ . . . _ _ _ _ _ _ . _ . . _ ___1.__._._.__________________________ _ _ . _ _ _ _ _ _ _ _ . > _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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-442A o o s-442s =
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Vessel Weld Layout i Figure 1 SER. NO.97-002 ATTACHMENT 2 l REACTOR VESSEL OUTLINE PAGE 10F 28
. - . . . . - . - . - ~ - . . - - . . . - - . . - . . - . . _ . - - - _ - . . - . _ . . . . - . . . . . . . . . . _ - . ~ . . . . . . .
DUKE POWER COMPANY MC GUIRE UNIT 1 REACTOR VESSEL EXAMINATION i
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3-445E-SE(22 degrees)) 7-442 3-445F-SE (158 degrees)1 -
3-4450-SE (202 degrees)'] / '
5-445AR (67 degrees) 3-445H-SE (338 degrees) jer*l
. 1-442A (60 degrees ;
1-4428 (180 degrees b if fB r es 1NC1F-1-1 (22 degrees) ,I == 1-442C (300 degrees.,' - 5-445DR (293 d'8rees) 1NC1F-2-1 (158 degrees) s -v y i f3-445A-SE (67 degrees 1NC1F-3-1 (202 degrees) 7: ," '
3-445B-SE (113 degree 1NC1F-4-1 (338 degrees)
, e OUTLET N0ZELE
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UPPER SHELL g 3-445C-SE (247 degree
.3-445D-SE (293 degree 454-01 INLET N0ZZLE /
5-445ER (22 degrees) _
- /1NC1F-1-8 (67 degrees 5-445FR (158 degrees N 1NC1F-2-8 (113 degree :
5-4450R (202 degrees) 8-442 '
' 5-445HR (338 degrees) ; ,
I,INC1F-3-8 1HC1F-4-8 (293 (247 degree degree
!~ , f 5-445A (67 degrees)
,2-442A (0 degrees I5-445B (113 degrees) 5-445E 5-445F (158 (22 degrees)'(
degrees) *-t2-442B (120 degrees 5-445C (247 degrees) 5-445G (202 degrees) 1 2-442C (240 degrees
- i 5-445D (293 degrees) 5-445H (338 degrees) ,
I MIDDLE SHELL ,
454-02 l l
9-442 g 3-442A (60 degrees 3-4425 (180 degrees 3-442C (300 degrees)
LOWER SHELL 454-03
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g] 0-H2 g { 1 1-202A (30 degrees) -
TRANSITION RING 1-2025 (90 degrees) 469-01 1-202C (150 degrees) 4-469 g 1-202D (210 degrees) 1-202E (270 degrees) 1-202F (300 degrees), LOWER HEAD i
l I SER. NO.97-002 Figure 2 ATTACHMENT 2 REACTOR VESSEL OUTLINE PAGE 2 OF 28
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SER. NO.97-002 i ATTACHMENT 2 !
REACTOR VESSEL OUTLINE ;
PAGE 3 OF 28
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! EXAMINATION COVERAGE FOR WELD: 10-442
,. LWR SHELL TO LWR HEAD CIRC WELD i AGGREGATE COVERAGE OBTAINED: 69%
j SCAN PLAN DRAWING:12139290 02 i Zone Coverage Obtained Weid: 63% Adjacent Base Metat 59% Near(ID) Surface: 60 %
- Weld Length 544 872 Irt Area Measurement Volume Calculation
] Weld 7.51 sq. in. Weld 4091.989 cu.in
) Adjaant Base Metal 43.88 sq. in. Adjacent Base Metal 23908.98 cu. in.
- Near Surface 8.58 sq. in. Near Surface 4675.002 cu. in.
! . _... . . .. = 1 ---9.-aw' L T D mW . . . i.' l ii . . .
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Exam. Area Length Volume Volume
- Angle Beam Examined Examined Examined Required Percent
- Entry # (deg.) Drection (sq. in.) (in.) (cu. in.) (cu. in.) Examined
! 1 0 n/a 7.5 361.3 2713.0 2713.0 100%
4 2 0 n/a 0.0 183.6 0.0 1379.0 0%
i 3 45 1 7.5 334.1 2509.1 2509.1 100%
! 4 45 2 7.5 334.1 2509.1 2509.1 100 %
i 5 45 1 0.0 210.8 0.0 1583.0 0%
f 6 45 2 0.0 210.8 0.0 1583.0 0%
7 45 3 7.5 300.0 2258.8 2258.8 100 %
8 45 4 7.5 300.8 2258.8 2258.8 100 %
9 45 3 0.0 244.1 0.0 1833.2 0%
10 45 4 0.0 244.1 0.0 1833.2 0%
i 11 60 1 7.5 334.1 2509.1 2509.1 100 %
4 12 60 2 7.5 334.1 2509.1 2509.1 100%
13 60 1 7.5 210.8 1583.1 1583.1 100%
i 14 60 2 0.0 210.8 0.0 1583.1 0%
! 15 60 3 7.5 300.8 2258.8 2258.8 100 %
i 16 60 4 7.5 300.8 2258.8 2258.8 100 % !
i 17 60 3 0.0 244.1 0.0 1833.2 0%
! 18 60 4 0.0 244.1 0.0 1833.2 0%
4 Totals
- 23367.6 36828.4 63% l l Adjacent Base Metal Exam. Area Length Volume Volume j Angle Beam Examined Examined Examined Required Percent
- Entry # (deg.) Drection (sq. in.) (in.) (cu. in.) (cu. in.) Examined i
1 0 n/a 43.9 361.3 15851.7 15851.7 100 %
2 0 n/a 0.0 183.6 0.0 8057.2 0%
3 45 1&2 43.9 334.1 14660.3 14660.3 100 %
4 45 1&2 0.0 210.8 0.0 9249.0 0%
1 5 45 3 43.9 300.8 13197.8 13197.8 100 %
! 6 45 4 43.9 300.8 13197.8 13197.8 100 %
} 7 45 3 0.0 244.1 0.0 10711.1 0%
8 45 4 0.0 244.1 0.0 10711.1 0%
9 60 1&2 43.9 334.1 14660.3 14660.3 100 %
10 60 1&2 0.0 210.8 0.0 9249.9 0%
11 60 3 43.9 300.8 13197.8 13197.8 100 %
12 60 4 43.9 300.8 13197.8 13197.8 100 %
13 60 3 0.0 244.1 0.0 10711.1 0%
14 60 4 0.0 244.1 0.0 10711.1 0%
Totals: 97963.4 167364.0 50%
Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry 4 (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 70 axial 8.6 296.6 2544.8 2544.8 100 %
2 70 axiat 0.0 248.3 0.0 2130.2 0%
3 70 cire 8.6 361.3 3099.5 3099.5 100 %
4 70 cire. 0.0 183.6 0.0 1575.5 0% SER. NO. 97 002 Totals: 5644.3 9350.0 60% ATTACHMENT 2 B01.011.003 1RPV10-442 PAGE 4 OF 28
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EXAMINATION COVERAGE FOR WELD: 1-442 A,C UPPER LONGITUDINAL WELD AGGREGATE COVERAGE OBTAINED: 90%
SCAN PLAN DRAWING:1218936D 02 Zone Coverage Obtained Weid: 89% Adjacent Base Metal 90% Near(ID) Surface: 88%
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Area Measurement Volume Calculation Weld. .
14.78 sq. in. Weld . 364.1792 cu. in.
Adjacent Base Met 124.08 sq. in. Adjacent Base Metal 3057.331 cu. in.
Near Surface 12.23 sq. in. Near Surface 301.3472 cu. in.
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Exam. Area Length Volume Volume Angle Beem Examined Examined Examined Required Percent Entry # - (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 14.8 24.6 364.2 364.2 100 %
2 45 1 14.8 18.7 276.5 276.5 100 %
3 45 2 14.8 18.7 276.5 276.5 100 %
4 45 1 0.0 59 0.0 87.6 0%'
5 45 2 0.0 5.9 0.0 87.6 0%
6 45 3 14.8 24.6 364.2 364.2 100 %
7 45 4 14.8 24.6 364.2 364.2 100 %
8 60 1 14.8 18.7 276.5 276.5 100 %
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9 60 2 14.8 18.7 276.5 276.5 100 %
10 60 1 0.0 5.9 0.0 87.6 0%
11 60 2 0.0 5.9 0.0 87.6 0%
12 60 3 14.8 24.6 364.2 364.2 100 %
13 60 4 14.8 24.6 364.2 364.2 100%
Totals: 2927.0 3277.6 89%
Agacent Base Metal i Exam. Area Length Volume Volume 4 Angle Beam Examined Examined Examined Required Percent 1 Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 124.1 24.6 3057.3 3057.3 100 %
2 45 1&2 115.7 18.7 2164.0 2321.5 93%
3 45 1&2 0.0 5.9 0.0 735.8 0%
4 45 3 124.1 24.6 3057.3 3057.3 100 %
5 45 4 124.1 24.6 3057.3 3057.3 100 %
6 60 1&2 115.7 18.7 2164.0 2321.5 93 %
7 60 182 0.0 5.9 0.0 735.8 0%
8 60 3 115.7 24.6 2849.9 3057.3 93 %
9 60 4 115.7 24.6 2849.9 3057.3 93 %
Totals: 19199.7 21401.3 90%
Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (r.q. in.) (in.) (cu. in.) (cu. in.) Examined 1 70 axial 12.2 18.7 228.8 228.8 100 %
2 70 axial 0.0 5.9 0.0 72.5 0%
3 70 cire. 12.2 24.6 301.3 301.3 100 %
Totals: 530.2 602.7 88% SER. NO.97-002 ATTACHMENT 2 '
B01.012.001, B01.012.003 -
1RPVI-442A,1RPVI-442(
I PAGF.13 OF 28 L..... .
EXAMINATION COVERAGE FOR WELD: 1-442 B UPPER LONGITUDINAL WELD AGGREGATE COVERAGE OBTAINED: 31 %
SCAN PLAN DRAWING:12139360 02 Zone Coverage Obtained Weld: 28% Adjacent Base Metal: 31% Near(10) Sur'ics: 43%
,,gsgo m p, w m amspeerm & = - ~~-~= 9' =_- ;-- Z : _ _ _ r-~._ _7 Weld .ength: 74.265 in.
Area Measurement Volume Calculation Weld 14.78 sq. in. Weld 1097.637 cu. in.
Adjacent Base Metal 124.08 sq. in. Adjacent Base Metal 9214.801 cu. in.
Neat Surface 12.23 sq. in. Near Surface 908.261 cu. in.
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Wold Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 14.8 20.4 302.0 302.0 100 %
2 0 n/a 0.0 53.8 0.0 795.7 0%
3 45 1 14.8 20.4 302.0 302.0 100 %
4 45 1 0.0 53.8 0.0 795.7 0%
5 45 2 14.8 20.4 302.0 302.0 100%
6 45 2 0.0 53.8 0.0 795.7 0%
7 45 3 14.8 20.4 302.0 302.0 100 %
8 45 3 0.0 53.8 0.0 795.7 0%
9 45 4 14.8 20.4 302.0 302.0 100%
10 45 4 0.0 53.8 0.0 795.7 0%
11 60 1 14.8 20.4 302.0 302.0 100 %
12 60 1 0.0 53.8 0.0 795.7 0%
13 60 2 14.8 20.4 302.0 302.0 100%
14 60 2 0.0 53.8 0.0 795.7 0%
15 60 3 14.8 20.4 302.0 302.0 100 %
16 60 3 0.0 53.8 0.0 795.7 0%
17 60 4 14.8 20.4 302.0 302.0 100 %
18 60 4 0.0 53.8 0.0 795.7 0%
Totals: 2113.7 7683.5 26%
Adjacent Base Metal Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direc6on (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 124.1 20.4 2535.0 2535.0 100 %
2 0 n/a 0.0 53.8 0.0 6679.8 0%
3 45 1&2 124.1 20.4 2535.0 2535.0 100 %
4 45 1&2 04 53.8 0.0 6679.8 0%
5 45 3 124.1 20.4 2535.0 2535.0 100 %
6 45 3 0.0 53.8 0.0 6679.8 0%
7 45 4 129.1 20.4 2535.0 2535 0 100%
8 45 4 0.0 53.8 0.0 6679.8 0%
9 60 1&2 124.1 20.4 2535.0 2535.0 100 %
10 60 1&2 0.0 5'l.8 0.0 6679.8 0%
11 60 3 124.1 20.4 2535.0 2535.0 100 %
12 60 3 0.0 53.8 0.0 6679.8 0%
13 60 4 124.1 20.4 2535.0 2535.0 100 % j 14 60 4 0.0 53.8 0.0 6679.8 0% j Totals: 17744.7 57623.8 31% !
Near Surface ,
Exam. Area Length Volume Volume )
Angle Beam Exaenined Examined Examined Required Percent j Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined i 1 70 axial 12.2 20.4 249.9 249.9 100%
2 70 axial 0.0 53.8 0.0 658.4 0%
3 70 circ 12.2 20.4 249.9 249.9 100%
4 70 dre 0.0 53.8 0.0 658.4 0% SER. NO.97-002 Totals: 400.7 11se.s 43%
ATCACHMENT 2 B01.012.002 1RP 1-442B PAGE 14 OF 2R a
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EXTENSION ROIATION INDEX SCAN FIGURE NO. WELO NO. FILE NAME INCHES DEGREES INCREMENT Ol_RECTION SETUP CHANNEL B01.012.005 iRPV 2-442B MIOLONGlY 138.29 2 225.12 113.42 0 126.58 .37* AXlAL 4 1 - 8 B 0 s . ') i 2. 00 5 IRPV 2-442B MIOLONGIX 136.87 2 .226.48 114.70 0 125.30 .56" CIRC 4 8 6 Bot.0 2.006 IRPV 2-442C M10LONG2Y 138.29 2 225.12 233.42 0 246.58 .37' AXIAL 4 l 8 80s.012.006 1RPV 2-442C MIOLONG2X 136.87 Z 226.48 234.70 0 245.30 .56" CIRC 4 1 6 BOI.Ol2.004 1RPV 2-442A MIOLONG3Y 138.29 2 225.12 353.42 0 366.58 .37' AXIAL 4 i &
B08.012.004 tRPV 2-442A M10LONG3X 136.87 2 226.48 354.70 0 365.30 .56" CIRC 4 - 8 B01.082.001 IRPV l-442A UPPRLONGlYA 43.06 2 59.33 52.68 8 67.32 .37' AXIAL 2 i 8 801.012.001 IRPV l-442A UPPRLONGlXA 38.90 2 59.33 53.09 0 66.91 .56" CIRC 2 1 - 8 80s.082.00s IRPV l-442A UPPRLONGlYB 111.92 I 14.36 52.68 0 67.32 .37' AXIAL 2 8 8 B01.012.004 IRPV t-442A UPPRLONGlXB Ill.92 Z 116.13 53.09 0 66.91 .56" CIRC 2 I - 8 80s.012.002 tRPV l-4428 UPPRLONG2YA *43.06 Z 52.10 172.68 9 187.32 .37' AXIAL 2 l . 8 308.012.002 IRPV l-442B UPPRLONG2XA 38.90 Z 52.10 173 19 0 186.91 .56" CIRC 2 i b B01.012.003 IRPV l-442C UPPRLONG3YA 43.06 2 59.33 292.60 0 307.32 .37* AXIAL 2 I O 801.0e2.003 IRPV l-442C UPPRLONG3XA 38.90 Z 59.33 293.09 0 306.91 .56" CIRC 2 # . 8 .
B01.012.003 tRPV l-442C UPPRLONG3YB 111.92 Z !!4.36 292.60 0 307.32 .37' AXIAL 2 : - 8 ,
80s.012.003 IHPV l-442C UPPRLONG3XB 111.92 2 116.13 293.09 0 306.91 .56" ClHC 2 i e 80t.012.007 IRPV 3-442A LOWRLONGlY 247.13 2 336.66 53.42 9 66.58 .37* AXIAL 4 i - A B08.012.007 IRPV 3-442A LOWRLONGlX 245.78 Z 313.69 54.70 0 65.30 .56" CIRC 4 s 9 80s.012.000 IRPV 3-442B LOWRLONG2Y 247.13 Z i,6.66 173.42 0 186.58 .37* AXIAL 4 1 - 8 Bol.082.000 tRPV 3-442B LOWRLONG2X 245.7B Z 333.69 174.70 0 185.30 .56" CIRC 4 : . 8 !
B08.012.009 IRPV 3-442C LOTRLONG3Y 247.13 Z 336.66 293.42 0 306.58 .37* AXIAL 4 - 8 Bot.082.009 .liiPV 3-442C LOWRLONG3X 245.78 Z 333.69 294.70 0 305.30 .56" CIRC 4 : . 8 SER. NO.97-002 ATTACHMENT 2 B01c012.001, B01.012.002, B01.012.003 1RPV1-442A,1RPV1-442B, IRPVI-442C PAGE 16 OF 28
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!, LOWER LONGITUDINAL WELD AGGREGATE COVERAGE OBTAINED: 84 %
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SCAN PLAN DRAWING:1213926042 Zone Coverage Obtained Weld: 84% Adjacent Base Metat 84% Near(10) Surface: 84 %
-omettWith;4sN t l M Area Measurement Volume Calculation Weld 11.86 sq. in. Wold 1144.846 cu. in. ~
Adjacent Base Metal 78.69 sq. in. Adjacent Base Metal 7595.946 cu. in.
Near Surface 10.06 sq. in. Near Surface 971.0918 cu. in.
t*m ems:4.**sece"emina= wC "=: : . . _- - - -____._._ 3 "" w/ h cc e r Weld Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a . 11.9 80.8 957.7 957.7 100 %
2 0 n/a 0.0 15.8 0.0 187.2 0%
3 45 1 11.9 80.8 957.7 957.7 100 %
4 45 2 11.9 80.8 957.7 957.7 100 %
5 45 1 0.0 15.8 0.0 187.2 0%
6 45 2 0.0 15.8 0.0 187.2 0%
7 45 3 11.9 80.8 957.7 957.7 100 %
8 45 4 11.9 80.8 957.7 957.7 100 %
9 45 3 0.0 15.8 0.0 187.2 0%
10 45 4 0.0 15.8 0.0 187.2 0%
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12 60 2 11.9 80.8 957.7 957.7 100 %
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15 60 3 11.9 80.8 957.7 957.7 100 %
16 60 4 11.9 80.8 957.7 957.7 100 %
17 60 3 0.0 15.8 0.0 187.2 0% 1 18 60 4 0.0 15.8 0.0 187.2 0%
Totals: 8619.3 10303.6 84 %
Adjacent Base Metal Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined 1 0 n/a 78.7 80.8 6354.2 6354.2 100 %
2 0 wa 0.0 15.8 0.0 1241.7 0%
3 45 1&2 78.7 80.8 6354.2 6354.2 100 %
4 45 1&2 0.0 15.8 0.0 1241.7 0%
5 45 3 78.7 80.8 6354.2 6354.2 100 %
6 45 4 78.7 80.8 6354.2 6354.2 100 %
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9 60 1&2 78.7 80.8 6354.2 6354.2 100 % *%
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Angle Area Length Volume Volume Beam Examined Examined Examined Requimd Percent dh 9A Entry # (deg.) Direction (tq. in.) (in.) (cu. in.) (cu. in.) Examined N i 1 70 axial 10.1 80.8 812.3 812.3 100 % $ g m* Af. N ri 2 70 axial 0.0 15.8 0.0 158.7 0%
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