ML20135A873
| ML20135A873 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/18/1997 |
| From: | Mccollum W DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEIN-96-032, IEIN-96-32, NUDOCS 9702280005 | |
| Download: ML20135A873 (40) | |
Text
ll I Dukc ibu n company Wws w k WCow y, Jk Catau ha Nudear Generation Department tice nai<h nt 4MI)Concordkoad (BW)DI,?X Offue krk,SC B76 (8!B D13I?6 nu i DUPU? POWER February 18, 1997 s
U.S. Nuclear Regulatory Commission ,
Attention: Document Control Desk l Washington, D.C. 20555-0001
Subject:
Duke Power Co.npany j Catawba Nuclear Station, Unit 1 and Unit 2 Docket Nos. 50-413 and 50-414 ,
i Request for Alternative to Examination Requirements of 10 CFR 50.55a (g) (6) (ii) ( A) ,
Augmented Examination of Reactor Vessel Unit 1. No. 97-01, Unit 2, No. 97-02 ,
l Pursuant to 10 CFR 50.55a (g) (6) (ii) ( A) (5) , Duke Power Company requests approval for alternatives to examinations required by the subject Code paragraph.
The attached Enclosure 1, Request For Alternative, Unit 1, No. 97-01, provides a detailed description and justification for Reactor Vessel Welds on Unit 1.
The attached Enclosure 2, Request For Alternative, Unit 2, '
Nc. 97-02, provides a detailed description and justification for Reactor Vessel Welds on Unit 2. 1 Com1 late coverage of welds described in these Enclosures were not obtained. Complete coverage was not possible due to part geon etry and actual physical barriers. Duke Power Company believes that with the limited coverage obtained, an acceptable level of quality and safety has been achieved and public health and safety will not be endangered by approval of the .tlternative.
This request is being submitted in response to NRC Information Notic e 96-32, Implementation of 10 CFR 50.55a (g) (6) (ii) ( A) ,
Augmented Examination of Reactor Vessel. It should be noted that Catawba has previously submitted ASME Code Relief Requests (Unit 1, 94-01 and Unit 2, 96-02). The Unit 1 request was approved February 29, 1996. The Unit 2 request remains outstanding, pending approval. g 9702280005 970218 PDR G.mvg ADOCK 05000413 PDR
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Document Control Desk Page 2 February 18, 1997 Should there be any questions concerning this request, please call D. Tower at (803) 831-3419.
Very truly yours, f llf '
William R. McCollum, Jr.
Attachments xc:
L.A. Reyes, Regional Administrator Region II R.J. Freudenberger, Senior Resident Inspector i Catawba Nuclear Station '
P.S. Tam, Senior Project Manager ONRR l
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ENCLOSURE 1 REQUEST FOR ALTERNATIVE, UNIT 1 97-01
Duke Power Company Catawba Nuclear Station Unit 1 10-YEAR INTERVAL REQUEST FOR ALTERNATIVE, NO. 97-01 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 Power Company 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 inspections. These actions are taken to eliminate and/or reduce the concerns expressed in this Information Notice.
Because of concerns regarding the scope of inspection of reactor vessels, the NRC issued, in 1992, 10 CFR
- 50. 55a (g) (6) (ii) ( A) (herein referred to as paragraph (A)]
" Augmented Examination of Reactor Vessel", which contains new requirements for an augmented examination reactor vessels.
The rule requires implementation by the licensee, 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 Table IWB- l 2500-1 means more than 90% (reference American Society of '
Mechanical Engineers (ASME)Section XI Code Case N-460) of the j examination volume of each weld, where the reduction in !
coverage is due to interference by another component, or part geometry".
Many licensees are finding that while the overall average examination coverage for reactor vessel shell welds may be more than 90%, examination coverage for individual welds may I be substantially less than 90%. Licensees unable to completely satisfy the requirements for the augmented reactor vessel examination must 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 l completed with 100% coverage then relief must be requested l l from ASME Code requirements and a request for alternatives l l
from the Code of Federal Regulations must be submitted. l l
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(
i SYSTEMS / COMPONENTS FOR WHICH RELIEF IS REQUESTED:
Reactor Vessel shell welds are specified in Item Bl.10 of l Examination Category B-A of the 1989 Code. These systems / components are ASME Section XI Code Class 1. The
! Construction Code of record is ASME Section III, 1974 Edition '
through Summer 1974 Addenda, Class 1.
- a. Name and Identification Number ASME Section XI Code Class 1 Reactor Vessel I Examination Category B-A Head-to-Shell Circumferential Weld ID Number Item Number 1RPV-WO3 B01.011.001 Shell-to-Nozzle Belt Circumferential Weld ID Number Item Number 1RPV-WO6 B01.011.004 Note Attachment 1 provides complete description of the listed welds that did not receive " essentially 100%"
examination. This information was included in the Request for Relief (Serial No. 94-01, CNS Docket 50-413) for which approval has been received.
Attachment 2 provides detailed calculations for examination coverage for the listed welds that did not receive " essentially 100%" coverage. It is provided here to illustrate method of calculation. This information was included in the Request for Relief (Serial No. 94-01, CNS Docket 50-413) for which approval has bee received.
- b. Function:
Reactor Vessel - Houses the fuel assemblies, control rods, and vessel internals, also directs the flow of reactor coolant. ,
CODE OF FEDERAL REGULATIONS REQUIREMENT FROM WHICH ALTERNATIVE IS REQUESTED:
l l Code of Federal Regulations, Part 10, 50.55a(g) (6) (ii) (A) .
i l
l ASME CODE REQUIREMENT THAT HAS BEEN DETERMINED TO BE l IMPRACTICAL:
l Examination Category B-A, Pressure Retaining Welds in Reactor Vessel, Table IWB-2500-1, Figure No. IWB-2500-1 " Note 2:
Includes essentially 100% of the weld length."
BASIS FOR REQUESTING ALTERNATIVE:
Licensees that make a determination that they are unable to completely satisfy the requirements for the augmented reactor vessel shell weld examination specified in Section
- 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. The licensee may use the proposed alternative when authorized by the Director of '
the Office of NRR.
During the ultrasonic examination of the welds shown in Attachment 1, the minimum 90% coverage requirement of ASME Section XI, 1980 Edition through Winter 1981 Addenda, clarified by Code Case N-460, could not be obtained due to part geometry and actual physical barriers. A combination of mt:ltiple angles and UT techniques was used to obtain maximum ctverage possible. The attached examination reports document the actual amount of examination coverage obtained. ;
Although the coverage requirements of ASME Section XI could not be met, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. Based on these evaluations, the limited coverage will in no way endanger the health and safety of the :Jeneral public.
These welds were examined to the maximum extent practical in accordance with ASME Section V, Article 4 1980 Edition, Winter
'81 Addenda, and the additional requirements of Regulatory Guide 1.150.
No additional examinations will be required.
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l ALTERNATE EXAMINATIONS:
In accordance with ASME IWA-2000, the licensee is required to perform the necessary examinations and shall expend all methods and techniques possible to achieve acceptably adequate examinations during weld inspections. When examinations cannot be completed with 100% coverage then relief must be l requested from Code requirements and a request for l alternatives from CFR must be made. The alternative granted by the request, when all methods and techniques had been l exhausted, will essentially explain that the limited examination is the best available.
The use of radiography as an alternate volumetric examination method is not practical due to component thickness and geometric configurations. Other restrictions making radiography impractical are physical barriers prohibiting access for placement of source, film, number bands, etc.
Duke will continue to use the most of current ultrasonic
! techniques available for future examination of the Item Numbers shown in Attachment 1. It is the belief of Duke that the limited examination is the best available. ,
The application of Code Case N-460 will be utilized in all cases where <100% but >90% weld coverage is obtained. In ;
l cases where weld coverage of <90% is obtained, a request for relief from Code requirements will be submitted.
Duke Power Company will continue to perform an ultrasonic examination of all Reactor Vessel welds to the maximum extent practical in accordance with the requirements of ASME Section V, Article 4, 1989 Edition and Regulatory Guide 1.150, '
Revision 1, Appendix A.
JUSTIFICATION FOR GRANTING ALTERNATIVE:
Technical Specifications for Catawba Nuclear Station, Unit 1, state that the inservice inspection of the ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g) except where i specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g) (6) (I) . Section 10 CFR
- 50. 55a (a) (3 ) states that alternatives to the requirements of paragraph (g) may be used when authorized by the NRC. These proposed alternatives would provide an acceptable level of quality and safety, or compliance with the specified i
i
k requirements.would result in hardship or unusual difficulties j
without a compensating increase in the level of quality and safety.
Full utilization of IWA-2000 of the 1989 ASME Code assures.
examinations that are in compliance with the Code and will
~
provide for weld coverage possible with the methods and techniques utilized for the examinations. ( A) (5) states that licensees that make a determination that they are unable to completely satisfy the requirements for the augmented reactor vessel shell weld examinations specified in Section
- 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.
- j. Duke Power Company will continue to ultrasonically examine the
! welds to the extent practical within the limits of original
, design and construction. This will provide reasonable assurance of weld / component integrity. Thus, an acceptable level of quality and safety will have been achieved and public health and safety will not be endangered by allowing relief i from the aforementioned Code requirements.
The licensee, pursuant to 10 CFR 50.55a(g) (5) , has' determined
, that conformance with the examination requirement of Section XI of the ASME Code is not practical for its facility. It is
! not possible to obtain 100% weld coverage for the welds j described herein. The alternative granted by the request will essentially explain that the limited examination is the best available.
Request for Relief Serial No. 94-01, CNS Docket 50-413, has been previously approved.
. IMPLEMENTATION SCHEDULE:
J The alternative described will be in effect for the second 10
) year interval for Catawba Nuclear Station, Unit 1.
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1 APPROVALS: j Evaluated By: , -
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, NDE Level III Review: adr<#w l'k a Date: 9//dlfd l l '
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- Reviewed By:
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ATTACHBENT 1 Duke Power Company Catawba Nuclear Station Unit 1 10-YEAR INTERVAL REQUEST FOR ALTERNATIVE, NO. 97-01 i
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1 ATTACHMENT 2 l Duke Power Cosqpany Catawba Nuclear Station Unit 1 10-YEAR INTERVAL REQUEST FOR ALTERNATIVE, NO. 97-C1 1
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- Total Exam Area = 53.32 ina (Near Surface + Weld + T/2) a
- Near Surface Area = 8.37 in' (Cross-Section)
Weld Area = 6.37 inz (Cross-Section) ,
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} T/2 Area = 38.58 in z (Cross-Section)
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BETWEEN LUGS CIRC 70* Gets 6.24 in* of Near Surface Area (74.6 %)
O' Gets 9.07 in8 of Total Exam Area (17.0 %)
45' & 60* Get 31.79 in* of T/2 Area, .44 in2 of Weld Area Total Coverage = 31.79 + 0.44 + 0.44 = 63.7 %
38.58 + 6.37 + 6.37 AXIAL 70' Gets 8.24 in' of Near Surface Area; however due to the Full-Node Exam, 100 % Coverage of the Near Surface Area is obtained by the 45' & 60*. .
45' Gets 100 % of Weld and T/2 Area i 60' Gets 100 % of Weld and T/2 Area i
BELOW LUGS AXIAL Due to the Full-Node Exam, 7.58 in* of the Near Surface Area is obtained by the 60' (90.6 %). ,
45' Gets 3.79 in8 of T/2 Area. (0 % Wald Area)
Total Coverage = 3.79 + 0_00 + 0.00 - 7.4 %
38.58 + 6.37 + 6.37 60' Gets.9.11 in8 of T/2 Area and 1.23 in2 of Weld Area Total Coverage = 9.11 + 1.23 + 0.00 = 20.1 % '
38.58 + 6.37 + 6.37
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There are six (6) Segments Between Lugs, each 31.60* covered by the center of the head (0* and 60* Circ) . The outside transducers each cover an additional 2.06* which results in 35.72* covered by .
7 0* , 60* & 45' Axial and 70* & 45' Circ.
There are also six (6) s Segments Below Lugs, each covering the remaining 24.28' for Axial i
Scans. - ;
l O' & 60* Circ Coverage = 189.60 x % Between 100 x 360 l
l 70* & 45* Circ Coverage = 214.32 x % Between
- 100 x 360 Axial Coverage =
214.32 x % Between + 145.68 x % Below 100 x 360 l 1
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AXTAL CIRC 1 1 1 70 ,,_g.,g,,,, 1 0 96.2 67.7 62.5 44.4 33.5 37.9 9.0 Aggregate Coverage =
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[ 96.2 x 8.37 + (67.7 + 62.5) x (38.58 + 6.37 + 6.37)
+ 44.4 x 8.37 + $ (33.5 + 37.9) x (38.58 + 6.37 + 6.37)
+ 9.0 x 53.32 ] /.
- [ 8.37 x 2 + (38.58 + 6.37 + 6.37) x 4 + 53.32 ] =
Aggregate Coverage = 43.6 % drrAcwmEdTf Bot.ett. cot
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ALPHA = 1I.89 A i.. ' , .
WELD REFERENCE LINE ALPHA = 13.17 ', , 'h' -
T2/2 ALPHA = 13.98 %.
4 .- M l ALPHA = 15.18- .
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RADIUS = 88.189 *
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ALPHA = 19.48 (GUIDE. LUG LIMIT) ,' g
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Total Exam Area = 93.65 inz (Near Surface + Weld + T/2) )
Near Surface Area = 10.47 inz (Cross-Section) 1 Weld Area = 11.38 inz (Cross-Section)
T/2 Area = 71.80 in" (Cross-Section) -
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I CIRC 70' Gets 3.82 in* of Near Surface Area (36.5 %) i 1
0' Gets 6.08 inn of Total Exam Area (6.5 %)
l 45' & 60' Get 28.50 in* of T/2 Area (0 t Weld)
Total Coverage = 28.50 + 0.00 + 0.00 = 30.1 %
71.80 + 11.38 + 11.38 AXIAL 70* Gets 5.40 in 2of Near Surface Area (51.6 %)
4 5 Gets 63.34 inn of T/2 Area l
45'-UP Gets 11.10 in2 of Weld Area I
45'-DOWN Gets 4.74 in* of Weld Area Total Coverage = 63.34 + 11.10 + 4.74 n 93.7 tr 71.80 + 11.38 + 11.38 6 0', Gets 67.39 in2 of T/2 Area 60*-UP Gets 9.87 in8 of Weld Area
- 60*-DOWN Gets 9.34 in of Weld Area Total Coverage = 67.39 + 9.87 + 9.34 - 91.6 %
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w-0g AXIAL CIRC 70 ,_ R _,,,4, .5._,, 70 60 ,,,,15._ o 51.6 91.6 83.7 36.5 30.1 30.1 6.5 Aggregate Coverage =
[ 51.6 x 10.47 + (91.6 + 83.7) x (71. 8 0 + 11. 3 8 + 11. 3 8 )
+ 36.5 x 10.47 + (30.1 + 30.1) x (71.80 + 11.38 + 11.38)
+ 6.5 x 93.65 ] /
[ 10.47 x 2 + (71.80 + 11.38 + 11.38) x 4 + 94.65 ] =
Aggregate Coverage = 48.2 %
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.ANGE SUFFACE "
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ENCLOSURE 2 REQUEST FOR ALTERNATIVE, UNIT 2 97-02
1 Duke Power Cosepany Catawba Nuclear Station Unit 2 10-YEAR INTERVAL REQUEST FOR ALTERNATIVE NO. 97-02 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 Power Company has reviewed the information contained in this notice for applicability to its' facilities and has taken action to avoid or mitigate the effects of l limited inspections. These actions are taken to eliminate ;
and/or reduce the concerns expressed in this Information
- Notice.
1 Because of concerns regarding the scope of inspection of reactor vessels, the NRC issued, in 1992, 10 CFR
- 50. 55a (g) (6) (ii) ( A) [herein referred to as paragraph (A)],
" Augmented Examination of Reactor Vessel", which contains new 4
requirements for an augmented examination of welds reactor s 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 4
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 Table
+
IWB-2500-1 means more than 90% (reference American Society of Mechanical Engineers (ASME)Section XI Code Case N-460) of the j examination volume of each weld, where the reduction in coverage is due to interference by another component, or part geometry".
i Many licensees are finding that while the overall average examination for reactor vessel shell welds may be more than 90%, examination coverage for individual welds may be substantially less than 90%. Licensees unable to completely satisfy the requirements for the augmented reactor vessel examination must 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 100% coverage then relief must be requested from ASME Code requirements and a request for alternatives from the Code of Federal Regulations must be submitted.
3
SYSTEMS / COMPONENTS FOR WHICH RELIEF IS REQUESTED:
Reactor Vessel shell welds are specified in Item Bl.10 of l Examination Category B-A of the 1989 Code. These
! systems / components are ASME Section XI Code Class 1 and Class l 2. The Construction Code of record is ASME Section III, 1974 i
Edition through Summer 1974 Addenda, Class 1.
- a. Name and Identification Number ASME Section XI Code Class 1 Reactor Vessel Examination Category B-A Lower Head-to-Shell Circumferential Weld ID Number Item Number 2RPV-101-141 B01.011.001 Lower Shell Longitudinal Seams ID Number Item Number 2RPV-101-142A B01.012.007 2RPV-101.142B B01.012.008 2RPV-101-142C B01.012.009 Note See the Attachment for weld identification and detailed examination results. coverage This information was included in the Request for Relief (Serial No. 96-02) which has been submitted to the NRC for approval.
- b. Function:
Reactor Vessel - Houses the fuel assemblies, control rods, and vessel internals, also directs the flow of reactor coolant.
CODE OF FEDERAL REGULATIONS REQUIREMENT FROM WHICH ALTERNATIVE IS REQUESTED:
Code of Federal Regulations, Part 10, 50. 55a (g) (6) (ii) ( A) .
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ASME CODE REQUIREMENT THAT HAS BEEN DETERMINEC TO BE IMPRACTICAL:
l Examination Category B-A Pressure Retaining in l Reactor Vessel - Figure No. IWB-2500-1 and IWB-2500-2.
" Note 2: Includes essentially 100% of the weld length."
BASIS FOR REQUESTING ALTERNATIVE:
Licensees that make a determination that they are unable to completely satisfy the requirements for the augmented reactor vessel shell weld examination specified in Section
- 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. The licensee may use the proposed alternative when authorized by the Director of the Office of NRR.
During the ultrasonic examination of the welds shown in the attachment to this alternative, the minimum 90% coverage requirement of ASME Section XI, 1980 Edition through Winter 1981 Addenda, clarified by Code Case N-460, could not be obtained due to part geometry and actual physical barriers. A combination of multiple angles and UT techniques was used to obtain maximum coverage possible. The attached geometric examination reports document the actual amount of examination coverage obtained.
Although the coverage requirements of ASME Section XI could not be met, methods the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. Based on these evaluations, the limited coverage will in no way endanger the health and safety of the general public.
These welds were examined to the maximum extent practical in accordance with ASME Section V, Article 4 1980 Edition with Winter 1981 Addenda and the additional requirements of Regulatory Guide 1.150.
No additional examinations will be required.
l I
i ALTERNATE EXAMINATIONS:
In accordance with ASME IWA-2000, the licensee is required to perform the necessary examinations and shall expend all and techniques possible to achieve acceptably adequate i examinations during weld inspections. When examinations l cannot be completed with 100% coverage then relief must be
! requested from Code requirements and a request for alternatives from CFR must be made. The alternative granted by the request, when all methods and techniques had been exhausted, will essentially explain that the limited examination is the best available.
The use of radiography as an alternate volumetric examination [
method is not practical due to component thickness and configurations. Other restrictions making radiography impractical are physical barriers prohibiting access for placement of source, film, number bands, etc.
Duke will continue to use the most current ultrasonic techniques available for future examination of the Item Numbers shown in the attachment to this alternative. It is the belief of Duke that the limited examination is the best available.
The application of Code Case N-460 will be utilized in all i cases where <100% but >90% weld coverage is obtained. In j cases where weld coverage of <90% is obtained, a request for l relief from Code requirements will be submitted.
Duke Power Company will continue to perform an ultrasonic examination of all Reactor Vessel Welds to the maximum extent practical in accordance with the requirements of ASME Section V, Article 4, 1989 Edition and Regulatory Guide 1.150, Revision 1, Appendix A.
I JUSTIFICATION FOR GRANTING ALTERNATIVE: 1 1
Technical Specifications for Catawba Nuclear Station, Unit 2, state that the' inservice inspection of the ASME Code Class 1, 2, and 3 components shall be performed in accordance with i Section XI of the ASME Boiler and Pressure Vessel Code and !
applicable Addenda as required by Title 10 of the Code of ;
Federal Regulations (10 CFR) Section 50.55a(g) except where !
specific written relief has been granted by the Commission I pursuant to 10 CFR 50.55a(g) (6) (I) . Section 10 CFR
- 50. 55a (a) (3 ) states that alternatives to the requirements of paragraph (g) may be used when authorized by the NRC. These proposed alternatives would provide an acceptable level of
quality and safety, or compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Full utilization of IWA-2000 of the 1989 ASME Code assures examinations that are in compliance with the Code and will provide for weld coverage possible with the methods and techniques utilized for the examinations. (A)(5) states that licensees that make a determination that they are unable to i completely satisfy the requirements for the augmented reactor i vessel shell weld examinations specified in Section 50.55a (g) (6) (ii) ( A) shall submit information to the Commission i to support the determination and shall propose an alternative to the examination requirements that would provide an acceptable level of quality and safety.
Duke Power Company will continue to ultrasonically examine the welds to the extent practical within the limits of original 1 design and construction. This will provide reasonable assurance of weld / component integrity. Thus, an acceptable level of quality and safety will have been achieved and public j health and safety will not be endangered by allowing relief '
for the aforementioned Code requirements.
The licensee, pursuant to 10 CFR 50.55a(g) (5), has determined that conformance with the examination requirement of Section XI of the ASME Code is not practical for its facility. It is not possible to obtain 100% weld coverage for the welds described herein. The alternative granted by the request will essentially explain that the limited examination is the best available.
Request for Relief Serial No. 96-02, CNS Docket 50-414 has been submitted to the NRC for approval. ,
IMPLEMENTATION SCHEDULE:
The alternative described will be in effect for the second 10 year interval for Catawba Nuclear Station, Unit 2. ;
2 l
~~~1 1
l Approvals:
Evaluated By: . Ad* Lh- Date: l o so y \
NDE Level III Review: .moA 4 Date:
y,, -
.f. I. k. [ h Reviewed By: I Date: 1 2b b
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. ATTACHMENT i i i
Duke Power Company '
Catawba Nuclear Station Unit 2 ,
10-YEAR INTERVAL REQUEST FOR ALTERNATIVE NO. 97-02 l l
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~ . _ _
Item No. Exam System Or Area To Be Reason For Request Licensee Category - Component Examined Proposed
/ Figure No. Alternate Examination B01.011.001 B-A Reactor Vessel Lower Head to . Core Guide Lugs None IWB-2500-1 Shell Weld Actual Coverage Obtained - 57%
B01.012.007 B-A Reactor Vessel' Lower Shell Long. Core Guide Lugs None IWB-2500-2 Seam Actual Coverage Obtained - 81%
B01.012.008 B-A Reactor Vessel Lower Shell Long. Core Guide Lugs None IWB-2500-2 Seam Actual Coverage Obtained - 81% '
B01.012.009 B-A Reactor Vessel Lower Shell Long. Core Guide Lugs None IWB-2500-2 Seam Actual Coverage Obtained - 81%
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- EXAMINATION COVERAGE FOR WELD: W13 !
AGGREGATE COVERAGE OBTAINED: 57 %
Zone Coverage Obtained 1 l Weld: 57% Adjacent Base Metal 57% Near(10) Surface: 57 % l
- - - I
- -==mmanonwc --- :leninon -- -
Weld Length: 543.5 :n.
Area Measurement Volume Calculation ;
Weld 7.93 sq. in. Wald 4309.955 cu. in. !
Adjacent Base Metal 32.71 sq. in. Adjacent Base Metal 17777.89 cu. in.
Near Surface 7.33 sq. in. Near Surface 3983.855 cu. in.
- ~=nunanoncoveragessiculanon~
Wold Exam. Ara: 1.cngth Volume Volume Angle Beam Eramined Exarnined Examined Required Percent Entry # (deg.) Direction (sq. in.) (ir..) (cu. in.) (cu.in.) Examined 1 0 n/a 7.9 308.0 2442.4 2442.4 100 %
2 0 n/a 0.0 235.5 0.0 1867.5 0%
3 45 1 7.9 308.0 2442.4 2442.4 100 %
4 45 2 7.9 308.0 2442.4 2442.4 100 %
- 5 45 1 0.0 235.5 0.0 1867.5 0%
6 45 2 0.0 235.5 0.0 1867.5 0%
7 45 3 7.9 308.0 2442.4 2442.4 100 %
4 8 45 4 7.9 308.0 2442.4 2442.4 100 %
~
9 45 3 0.0 235.5 0.0 1867.5 0%
10 45 4 0.0 235.5 0.0 1867.5 0%
11 60 1 7.9 308.0 2442.4 2442.4 100 %
12 60 2 7.9 308.0 2442.4 2442.4 100 % -
13 60 1 1.0 235.5 242.0 1867.5 13 % !
a 14 60 2 0.0 235.5 0.0 1867.5 0%
%** 15 60 3 7.9 308.0 2442.4 2442.4 100 % 4 I 60
'16 -
4 7.9 308.0 2442.4 2442.4 100%
17 60 3 0.0 235.5 0.0 1867.5 0%
18 60 4 0.0 235.5 0.0 1867.5 0%
Totals: 22223 9 38789.6 57%
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 32.7 308.0 10074.7 10074.7 100 %
2 0 n/a 0.0 235.5 0.0 7703.2 0%
3 45 1&2 32.7 308.0 10074.7 10074.7 100 %
4 45 1&2 0.0 235.5 0.0 7703.2 0%
5 45 3 32.7 308.0 10074.7 10074.7 100 %
6 45 4 32.7 308.0 10074.7 10074.7 100 %
7 45 3 0.0 235.5 0.0 7703.2 0%
8 45 4 0.0 235.5 0.0 7703.2 0%
9 60 1&2 32.7 308.0 10074.7 10074.7' 100 %
10 60 1&2 0.0 235.5 0.0 7703.2 0%
11 60 3 32.7 308.0 10074.7 10074.7 100 %
12 60 4 32.7 308.0 10074.7 10074.7 100 %
13 60 3 0.0 235.5 0.0 7703.2 0%
14 60 4 0.0 235.5 0.0 7703.2 0%
Totals: 70522.8 124445.2 57%
Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.)
1 70 axial 7.3 (in.)
308.0 (cu. in.) (cu. in.) Examined 2257.6 2257.6 100 %
/%A7 A/C.
., 2 70 axial 0.0 235.5 0.0 1726.2 0% O/[, OO/
3 70 cire 7.3 308.0 2257.6 2257.6 100 %
4 70 cire. 0.0 235.5 0.0 1726.2 0%
Totals: 4515.3 7967.7 57%
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WELD AREA : 7.93 50 IN.
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T/2 AREA : 32.7! 50 IN. ' I * =
N 2:5.375 0 73.00
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NEAP SURFACE : 7.33 50 IN. I j
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(100% COVERAGE) 4 " D DIA T/2 AiEL : 32.7! SO IN. 't BMiz:s.37s ei73.co
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\EL: EL ACE : 7.33 S0 IN.
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T/2 4REA : 32.71 SO IN. \
h,ELR SJ9 FACE : 7.33 S0 IN. p ', " 2375 m t 3:A:
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l EXAMINkTION COVERAGE FOR WELD: WOS AGGREGATE COVERAGE OBTAINED: 81 %
Zone Coverage Obtained Weld: 81% Adjacent Base Metal 81% Near(ID) Surface: 81 %
Weld ength: 97h7 in.
Area Measurement Volume Calculation Weld 11.86 sq. in. Weld 1155.994 cu.h Adjacent Base Metal 74.44 sq. in. Adjacent Base Metal 7255.667 cu. in.
Near Surface 10.01 sq. in. Near Surface 975.6747 cu. in.
- - .c.. _ _ _
vveld i Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Requwod Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. h) (cu.h) Examined 1 0 n/a 11.9 79.0 936.3 936.3 100 %
2 0 n/a 0.0 18.5 0.0 219.6 0%
t 3 45 1 11.9 79.0 936.3 936.3 100 %
l 4 45 2 11.9 79.0 936.3 936.3 100 %
5 45 1 0.0 18.5 0.0 219.6 0%
6 45 2 0.0 18.5 0.0 219.6 0%
7 45 3 11.9 79.0 936.3 936.3 100 %
8 45 4 11.9 79.0 936.3 936.3 100 %
9 45 3 0.0 18.5 0.0 219.6 0%
10 45 4 0.0 18.5 0.0 219.6 0%
l 11 60 1 11.9 79.0 936.3 936.3 100 %
l 12 60 2 11.9 79.0 936.3 936.3 100 %
13 60 1 0.0 18.5 0.0 219.6 0%
.. 14 60 2 0.0 18.5 0.0 219.6 0%
15 60 3 11.9 79.0 936.3 936.3 100%
~16 60 4 11.9 79.0 936.3 936.3 100 %
i 17 60 3 0.0 18.5 0.0 219.6 0%
i 18 60 4 0.0 18.5 0.0 219.6 0%
l Totals: 8427.1 104019 81%
l Adjacent Base Metal Length Volume Volume Exam. Area l Angle Beam Examined Examined Examined Required Percent l
Entry # (deg.) Direction (sq. in.) (in.) (cu. h) (cu.in.) Exammed 1 0 n/a 74.4 79.0 5877.0 5877.0 100 %
, 2 0 n/a 0.0 18.5 0.0 1378.6 0%
3 45 1&2 74.4 79.0 5877.0 5877.0 100 %
! 4 45 1&2 0.0 18.5 0.0 1378.6 0%
! 5 45 3 74.4 79.0 5877.0 5877.0 100 %
6 45 4 74.4 79.0 5877.0 5877.0 100 %
7 45 3 0.0 18.5 0.0 1378.6 0%
l 8 45 4 0.0 18.5 0.0 1378.6 0%
l- 9 60 1&2 74.4 79.0 5877.0 5877.0 100 %
l 10 60 1&2 0.0 18.5 0.0 1378.6 0%
11 60 3 74.4 79.0 5877.0 5877.0 100 %
12 60 4 74.4 79.0 5877.0 5877.0 100%
13 60 3 0.0 18.5 0.0 1378.6 0% l 14 60 4 0.0 18.5 0.0 C78.6 0%
Totals: 41139.3 50789.7 81%
Near Surface Exam. Area Length Volume Volume 4
Angie Beam Examined Examined Exammed Required Percent i Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu.in.) Examined 1 70 axial 10.0 79.0 790.3 790.3 100 %
2 3
70 70 axial circ 0.0 10.0 18.5 79.0 0.0 790.3 185.4 790.3 100 %
0% /fgg gg, f
4 70 cire. 0.0 Totals:
18.5 1580.6 0.0 185.4 1351.3 0%
81%
g/g,@[
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EXAMINATION COVERAGE FOR WELD: W10 AGGREGATE COVERAGE OBTAINED: 81 %
Zone Coverage Obtained Weld; 81% Adjacent Base Metal 81% Near(10) Surface: 81 %
~~~nauonMous* wc ::-
Weld Length: 97.47 . 7 Area Measurement Volume Calculation
- Weld 11.86 sq. in. Weld 1155.994 cu. in.
l Adjacent Base Metal 74.44 sq. in. Adjacent Base Metal 7255.667 cu. in.
3 Near Surface 10.01 sq. in. Near Surface 975.6747 cu. in.
3
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Wed
, Exam. Area t.ength Volume Volume Angle Beam Examined Examined Examined Required Percent
- Entry # (deg.) Directs (sq. in.) (in.) (cu. in.) (cu.in.) Examined J
1 0 n/a 11.9 79.0 936.3 936.3 100 %
l 2 0 n/a 0.0 18.5 0.0 219.6 0%
3 45 1 11.9 79.0 936.3 936.3 100 %
4 45 2 11.9 79.0 936.3 936.3 100 %
5 45 1 0.0 18.5 0.0 219.6 _0%
6 45 2 0.0 18.5 0.0 219.6 0%
7 45 3 11.9 79.0 936.3 936.3 100 %
8 45 4 11.9 79.0 936.3 936.3 100 %
9 45 3 0.0 18.5 0.0 219.6 0%
10 45 4 0.0 18.5 0.0 219.6 0%
11 60 1 11.9 79.0 936.3 936.3 100%
12 60 2 11.9 79.0 936.3 936.3 100 %
13 60 1 0.0 18.5 0.0 219.6 0%
14 60 2 0.0 18.5 0.0 219.6 0%
%.. 15 60 3 11.9 79.0 936.3 936.3 100 % +
16 60 4 11.9 79.0 936.3 936.3 100 %
17 60 3 0.0 18.5 0.0 219.6 0%
13 60 4 0.0 18.5 0.0 219.6 0%
Totals: 8427.1 10403.9 81%
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 74.4 79.0 5877.0 5877.0 100%
2 0 n/a 0.0 18.5 0.0 1378.6 0%
3 45 1&2 74.4 79.0 5877.0 5877.0 100 %
4 45 1&2 0.0 18.5 0.0 1378.6 0%
5 45 3 74.4 79.0 5877.0 5877.0 100 %
6 45 4 74A 79.0 5877.0 5877.0 100 %
7 45 3 0.0 18.5 0.0 1378.6 0%
8 45 4 0.0 18.5 0.0 1378.6 0%
9 60 1&2 74.4 79.0 5877.0 5877.0 100%
10 60 1&2 0.0 18.5 0.0 1378.6 0%
11 60 3 74.4 79.0 5877.0 5877.0 100 %
12 60 4 74.4 79.0 5877.0 5877.0 100%
13 60 3 0.0 18.5 0.0 1378.6 0%
14 60 4 0.0 18.5 0.0 1378.6 0%
Totals: 41139.3 50789.7 81%
Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu.in.) Examined 1 70 exial 10.0 79.0 790.3 790.3 100%
2 70 axial 0.0 18.5 0.0 185.4 0%
3 70 cire 10.0 79.0 790.3 790.3 100 % / TEM A/O-
+
4 70 cire. 0.0 18.5 Totals:
0.0 1580.6 185.4 1951.3 0%
81%
h,g/f,88[
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i EXAMINATION COVERAGE FOR WELD: W11 AGGREGATE COVERAGE OBTAINED: 81 %
Zone Coverage Obtained Weld: 81% Adjacent Base Metal 81% Near (ID) Surface: 81 %
w=mmasonsvosume.uennmon c
} We d Length: 97.47 m.
- Area Measurement Volume Calculation Weld 11.86 sq. h Wold 1155.994 cu.in.
j Adjacent Base Metal 74.44 sq. h Adjacent Base Metal 7255.667 cu. in.
Near Surface 10.01 sq. in. Near Surface 975.6747 cu. in.
==~nacon coverage saicuiscons-Wold
- Exam. Area Length Volume Volume i Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. h) (cu.h) Examined 1 0 n/a 11.9 79.0 936.3 936.3 100 %
2 0 n/a 0.0 18.5 0.0 219.6 0%
1 3 45 1 11.9 79.0 936.3 936.3 100 %
. 4 45 2 11.9 79.0 936.3 936.3 100 %
S 45 1 0.0 18.5 0.0 219.6 0%
6 45 2 0.0 18.5 0.0 219.6 0%
4 7 45 3 11.9 79.0 936.3 936.3 100 %
8 45 4 11.9 79.0 936.3 936.3 100 %
9 45 3 0.0 18.5 0.0 219.6 0%
10 45 4 0.0 18.5 0.0 219.6 0%
11 60 1 11.9 79.0 936.3 936.3 100 %
12 60 2 11.9 79.0 936.3 936.3 100 %
13 60 1 0.0 18.5 0.0 219.6 0% ,
l 14 60 2 0.0 18.5 0.0 219.6 0%
"'" 15 60 3 11.9 79.0 936.3 936.3 100 %
16 60 4 11.9 79.0 936.3 936.3 100 %
17 60 3 0.0 18.5 0.0 219.6 0%
18 60 4 0.0 18.5 0.0 219.6 0%
Totals: 8427.1 10403.9 81%
A$ cent 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 b n/a 74.4 79.0 5877.0 5877.0 100 %
i 2 0 n/a 0.0 18.5 0.0 1378.6 0%
3 45 1&2 74.4 79.0 5877.0 5877.0 100 %
4 45 1&2 0.0 18.5 0.0 1378.6 0%
j 5 45 3 74.4 79.0 5877.0 5877.0 100 %
6 45 4 74.4 79.0 5877.0 5877.0 100 %
7 45 3 0.0 18.5 0.0 1378.6 0%
. 8 45 4 0.0 18.5 0.0 1378.6 0%
0 60 1&2 74.4 79.0 5877.0 5877.0 100 %
4 10 60 1&2 0.0 18.5 0.0 1378.6 0%
11 60 3 74.4 79.0 5877.0 5877.0 100 %
12 60 4 74.4 79.0 5877.0 5877.0 100 %
13 60 3 0.0 18.5 0.0 1378.6 0%
14 60 4 0.0 18.5 0.0 1378.6 0%
Totq%: 41139.3 50789.7 81%
Near Surface Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (cu in.) Examined 1 70 axiat 10.0 79.0 7S0.3 790.3 100 %
i 2
3 70 70 axial cire 0.0 10.0 18.5 79.0 0.0 790.3 185.4 0%
790.3 100 %
/[6M A/8
- 4 70 circ. 0.0 18.5 0.0 185.4 0% ,8d/,8/2+ 88 f
- Totals
- 1580.6 1951.3 81 %
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'/2 AREA : 74.44 SO IN.
. NEAR SURFACE : 80.01 SQ IN. ~ 800% COVERAGE ADTEi Ls9 SHELL HAS CORE OWDE N - . n LU3 OBSTRUCTIONS.
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