ML20244C815
| ML20244C815 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/06/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244C784 | List: |
| References | |
| NUDOCS 8906150148 | |
| Download: ML20244C815 (15) | |
Text
.
4-ENCLOSURE 2
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UNITED sT ATES f
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SAFETY EVALUATION EY TFE OFFICE OF NUCLEAR REACTOR REGULATIO
- r. ELATING TO FIPST IllTERVAL lhSERVICE IfISPECTION PROGRAM l
LOUISIANA POWER AND LIGHT COMPANY UATERFCEO STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
The Technical Specifications for the Waterford Unit 3, require that the inser-vice inspection of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Yessel Code Class 1, 2, and 3 components be performed in accor-dance with Section XI of the ASME Code and applicable Addenda as required by 10 CFR 50.55a(g), except where specific written relief.has been granted by Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 l
components (including supports) shall meet the requirements, except the design the Comr11ssion.
and access provisions and the preservice examination requirements, set forth in the ASME 5ection XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, The regulations require that and raterials of construction of the components.
inservice examination of components and system pressure tests conducted during the first ten-year interval comply with the requirements in the latest edition and addenda of ASME Section XI incorporated by reference in 10 CFR 50.55a(b) twelve months prior to the date of issuance of the operating license, subject The components (including to the limitations and modification listed therein.
supports) may meet the requirements set forth in subsequent editions of ASME Section XI reference in 10 CFR 50.55a(b) subject to the limitations and modifi-cations listed therein.
If the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for his facility, pursuant to 10 CFR 50.55a(g)(5), information shall be submitted to the Comission in support Af ter evaluation of the determination, pursuant to 10 of that determination.
CFR 50.55a(g)(6)(1), the Comission may grant relief and may impose alternative requirements that are authorized by law, will not endanger life or property or the comon defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
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2-The licensee, Louisiana Power & Light, submitted the initial Inservice Inspection (ISI) Program for Waterford Unit 3 in a letter dated May 28, 1985 to meet the requirements of ASME Section XI 1980 Edition including addenda through Winter 1981 (80W81). Revision 1 of this document was submitted on November 26, 1985. The staff sent a request for additional information (RAI) on December 3, 1985. The licensee responded in a letter dated June 16, 1986, which included Revision 2 to the ISI Program as an attachment. The staff, with the technical assistance from its contractor, Science Applications International Corporation (SAIC), has evaluated Revision 2 of the ISI Program, additional information related to the plan, and the requests for relief from certain ASHE Code requirements determined to be impractical to perform. On October 15, 1987 the licensee submitted Revision 3 based on field use during the first outage inspection and one new relief request, 151-11.
2.0 STAFF EVALUATION Revision 2 of the ISI Program has been evaluated for (a) application of the
, required Section XI Code edition and addenda} a(b) compliance with examination and test requirements of ASME Section XI, (c acceptability of the examination sample, (d) the use of system or component examination exclusion criteria, (e) comitments made during the licensing review and"(f) the adequacy of informa-tion in support of the requests for relief. The staff has determined that the licensee's ISI Program reflects compliance with the requirements listed above.
The information provided by the licensee in support of requests for relief from impractical requirements are documented in the SAIC Technical Evaluation Report (TER) number SAIC-8611634. The staff concurs with the findings and recomenda-tions contained in the TER.
In addition, the staff has evaluated relief request 151-11 submitted with Revision 3.
A detailed evaluation of the exami-nation procedure for hydrostatic tests is not a part of the NRR review of the ISI program (Reference TER paragraph 2.5).
3.0 CONCLUSION
l The staff concludes that Waterford Unit 3 First Ten-Year Interval Inservice Inspection Program, with the additional information provided and the specific written relief constitute the basis for compliance with 10 CFR 50.55a(g) and is therefore acceptable. Based on the review of the summary of major changes l
in Revision 3 provided by the licensee, the staff's conclusions apply l
conceptually to Revision 3.
Principal Contributor:
M. Hum Dated: June 6, 1989 J
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ENCLOSURE 3
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O TECilNICAL EVALUATION REPORT FIRST INTERVAL INSERVICE INSPECTION PROGRAM WATERFORD UNIT 3 O
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TECHNICAL EVALUATION REPORT FIRST INTERVAL INSERVICE INSPECTION PROGRAM WATERFORD UNIT 3 Submitted to U.S. Nuclear Regulatory Commission Contract No. 03-82-096 Submitted by Science Applications International Corporation Idaho Falls, Idaho 83402 f ye -
December 1986
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nY s
CONTENTS 1.
INTRODUCTION..........................
1 2.
EVALUATION OF INSERVICE INSPECTION PLAN 3
2.1 Introduction..........................
3 2.2 Documents Evaluated 3
2.3 Summary of Requirements 3
2.3.1 Code Requirements 4
2.3.1.1 Class 1 Requirements 4
2.3.1.2 Class 2 Requirements 5
2.3.1.3 Class 3 Requirements 5
2.3.1.4 Component Supports 5
2.3.2 Preservice Inspection Commitments 5
2.4 Compliance with Requirements..................
6 2.4.1 Applicable Code Edition 6
2.4.2 Code Requirements 6
2.4.3 Preservice Inspection Commitments 7
2.5 Conclusions and Recommendations 7
3.
EVALUATION OF RELIEF REQUESTS 8
3.1 CLASS 1 COMPONENTS.......................
8 3.1.1 Reactor Vessel.....................
8 3.1.1.it Relief Request 15I-001, Pressure Retaining Welds in Reactor Vessel, Category B-A, Item Bl.11 8
3.1.2 Pressurizer 11 3.1.2.1 Relief Request 151-001, Pressurizer Surge Nozzle-to-Bottom Head Weld, Category B-D, Item B3.110 11 1
n
L 3.1.3 Heat Exchangers.and Steam Generators..........
13 3.1.3.1 Relief Request 151-001, Pressure Retaining Steam E
Generator Primary Side Head Welds, Category B-8, Item B2.51.......................
13
'r 3.1.4 Piping Pressure Boundary.................
16 3.1.4.1 Relief Request 15I-001, Pressure Retaining Dissimilar Metal Welds, Category B-F, Items B5.40 and B5.130.......................
16 3.1.4.2 Relief Request ISI-001, Pressure Retaining Welds in Piping, Category B-J, Items 89.11, B9.12, and B9.31....................
19 7
3.1.5 Pump Pressure Boundary.................
22 3.1.5.1 Relief Request 15I-004, Reactor Coolant Pump Pressure Boundary, Categories B-L-1 and B-L-2, Items B12.10 and B12.20................
22 3.1.6 Valve Pressure Boundary................
26 3.1.6.1 Relief Request ISI-003, Valve Bodies, Category B-M-2, Item B12.50 26 3. P.
CLASS 2 COMPONENTS.......... '.............
28 3.2.1 Pressure Vessels and Heat Exchangers..........
28 3.2.1.1 Relief Request 151-001, Pressure Retaining Welds in the Shutdown Cooling Heat Exchanger Category C-A, Items C1.10 and C1.30 28 3.2.1.2 Relief Request 151-001, Pressure Retaining Welds in the Steam Generator Secondary Side.
Category C-A, Items C1.10, C1.20, and C1.30 30 3.2.1[35 Relief Request 15I-001, Steam Generator
? Pressure Retaining Nozzle Welds and Nozzle Inside Radius Sections, Category C-8, Items C2.21 and C2.22 33 3.2.2 Piping Pressure Boundary................
35 3.2.2.1 Relief Request ISI-001, Integral Attachment in the Shutdown Cooling System, Category C-C, Item C3.20 35 3.2.2.2 Relief Request 151-001, Pressure Retaining Welds in Piping, Category C-F, Items C5.11, C5.12, C5.21, and C5.22....................
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a 3.2.2.3 Relief Request 151-002, Pressure Retaining Welds in Piping, Category C-F, Items C5.11, and C5.12 40 3.3 CLASS 3 COMPONENTS.......................
42 3.3.1 Relief Request 151-005, Class 3 Integral Attachments, Categories D-A, D-B, and D-C, Items D1.20-D1.60, D2.20-D2.60, and D3.20-D3.60 42 3.4 PRESSURE TESTS (No relief requests) 3.5 GENERAL (No relief requests) 3.6 COMPONENT SUPPORTS.......................
44 3.6.1 Relief Request 151-006, Class 3 Component Supports, Category F-C, Items F3.10--F3.40.......
44 3.6.2 Relief Request 151-007, Class 2 and 3 Component Supports, Category F-C, Items F3.10--F3.40...................
47 3.6.3 Relief Request 151-008, Class 3 Component Supports, Category F-C, Items F3.10--F3.40.......
50 3.6.4 Relief Request ISI-009, Class 3 Component Supports, Category F-C, Items F3.10--F3.40.......
52 3.6.5 Relief Request ISI-010, Class 3 Component Supports, Category F-C, Items F3.10--F3.40.......
58
3.7 REFERENCES
60 ATTACHMENT 1:7 Listing of Welds Receiving a Partial Examination i
l
' Under Relief Request 151.-001 I
i j
APPENDIX A:
Requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel i
Code, 1980 Edition with Addend 6 Through Winter 1981 iii
o' TECHNICAL EVALUATION REPORT FIRST INTERVAL INSERVICE INSPECTION PROGRAM WATERFORD UNIT 3 1.
INTRODUCTION Section 50.55a of 10 CFR Part 50 defines the requirements for the Inservice Inspection (ISI) Program for light-water cooled nuclear power facilities.
Incorporated by reference in this regulation isSection XI of the Boiler and Pressure Vessel Code published by the American Society of Mechanical' Engineers (ASME), which provides the basis for implementing inservice inspection.*
Two types of inspections are required: (1) a preservice inspection conducted before commercial operation to establish a baseline and (2) peri-odic inservice inspections conducted during 10-year inspection intervals that normally start from the date of commercial operation. Separate plans for completing preservice inspection and each 10-year inservice inspection must be formulated and submitted to the Nuclear Regulatory Commission (NRC).
The plan for each 10-year interval must be submitted at least six months before the start of the interval.
During the initial 10-year interval, inservice inspection examinations must comply with the requirements in the latest edition and adderda of Section XI incorporated in the regulation on the date 12 months before the date of issuance of the operating license. The Waterford Unit 3 (Water-ford 3) operating license was issued on March 16, 1985. As such, the ISI program has been written to the 1980 Edition with Addenda through Winter 1981. The ISI program for the first interval began on the first day of commercial operation (September 24,1985) and will continue for 120 months.
Section 2 of this report evaluates the first interval ISI plan developed
~by the licensee, Louisiana Power and Light Company (LP&L), for Waterford 3 for (a) compliance with this edition of Section XI, (b) compliance with ISI-related commitments identified during the NRC's review before granting an Operating License, (c) acceptability of examination sample, and (d) exclusion criteria.
Based on'the date Waterford 3's construction permit (November 14,1974) was issued, the plant's Class 1 and 2 components (including supports) were to be designed and provided with access to enable performance of inservice examinations and tests and to meet the preservice examination requirements of the 1974 Edition of the Code with addenda through Summer 1975 (10 CFR 50.55a(g)(2)).
Paragraph 10 CFR 50.55a(g) recognizes that some requirements
- Specific inservice test programs for pumps and valves (IST programs) are being evaluated in other reports.
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of the current edition and addenda of Section XI(1980 W81) may not be e
practical to implement because of limitations of design, geometry, and materials of construction of components and systems that were designed to the older Code (1974 S75). The regulation therefore permits exceptions to impractical-examination or testing requirements of the current Code to be requested. Relief from these requirements may be granted, provided the health and safety of the public are not endangered, giving due consideration to the burden placed on the licensee if the requirements were imposed.
Section 3 of this report evaluates requests for relief dealing with inservice examinations of components and with system pressure tests.
The regulation also provides that ISI programs may meet the require-ments of subsequent Section XI editions and addenda, incorporated by.
reference in the Regulation, subject to approval by the NRC.
Portions of such editions or addenda may be used, provided all related requirements of the respective editions or addenda are met. These instances are addressed on a case-by-case basis in Section 3 of this report.
Likewise,.Section XI provides that certain components and systems may be exempted from volumetric and surface requirements.
In some instances, however, these exemptions are I
not acceptable to the NRC or are acceptable only with restrictions. As appropriate, exemptions are also discussed in Section 3 of this report.
The Preservice Inspection (PSI) program for Waterford 3, an 1100 MWe Combustion Engineering pressurized-water-reactor (PWR), is contained in References 2 through 6 and was approved by the staff. Reference 7 relates to review and approval of the PSI. The licensee agreed to perform augmented inservice inspections in Reference 1.
The ISI program for the first 10-yearinspectionintervalwhichbeganthedateofcommercial$peration, September 24, 1985, was submitted to the NRC May 28, 1985.q8 The licensee submitted Revision 1 of the ISI program on November 26,1985.(9 As a 1
result of a review of the plan, the staff requested additional informa-tion.(10) The licensee responded to the request for additional information in a letter dated June 16, 1986,llU which included Revision 2 to the ISI program as an attachment.
References 8, 9, and 11 form the primary basis for review of the Waterford 3 ISI program.
2
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2.
EVALUATION OF INSERVICE INSPECTION PLAN 2.I Introduction The approach being taken in this evaluation is to review the applicable program documents to determine the adequacy of their response to Code requirements and any license conditions pertinent to I$I activities.
The rest of this section describes the submittals reviewed, the basic requirements of the effective Code, and the appropriate license conditions.
The results of the review are then described.
Finally, conclusions and recommendations are given.
2.2 Documents Evaluated A chronology of documents on Waterford 3 PSI and ISI is given in Section 1 of this report.
These documents that impact this ISI program evaluation are (1)
Revisions 0,1, and 2 of the ISI program, (2) the licensee's response to the staff's request for additional information, (3) portions of the Safety Evaluation Report (SER) Supplements 5 and 6, and (4) to a lesser extent, the previous submittals on the PSI program.
2.3 Summary of Requirements The requirements on which this review is focused include the following:
(1) Comoliance with Acolicable Code Editions. The Inservice Inspection Program shall be based on the Code editions defined in 10 CFR 50.55a(g)(4) and 10 CFR 50.55a(b). The licensee for Waterford 3 has written the first interval program to the 1980 Edition with addenda through Winter 1981. These Code require-ments are summarized in 2.3.1 below and detailed Code require-ments are given in Appendix A.
A requirement of 10 CFR 50.55a (b)(2)(iv)(A) is that the 1974 Edition, Summer 1975 Addenda shall be used for selecting Class 2 welds in systems providing the f
functions of residual heat removal, emergency core cooling, and containment heat removal.
i (2) Ac'centab1'tv of the Examination Samole.
Inservice volumetric, surface, ano cual examinations shall be performed on ASME Code Class 1 and 2 components and their supports using sampling schedules described in Section XI of the ASME Code and 10 CFR 50.55a(b). Sample size designations are identified as part of the Code requirements given in Appendix A.
l 3
01
1 (3) Exclusion Criteria. The criteria used to exclude components from examination shall be consistent with IWB-1220, IWC-1220, and 10 CFR 50.55a(b).
(4)
PSI Commitments. The Inservice Inspection Program should address all license conditions, qualified acceptance conditions or other
-ISI-related commitments described in the SER and its supplements for the preservice examination.
2.3.1 Code Requirements The following requirements are summarized from the 1980 Edition of Section XI with addenda through Winter 1981. Many requirements call for the examination of all areas, while other requirements specify more limited examinations based on criteria such as representative percentage, components examined under other categories, material thickness, location relative to other welds or discontinuities, and component function and construction.
For detailed requirements, see Appendix A of this report or the Code itself.
i 2.3.1.1 Class 1 Requirements. The following Class 1 components are to be examined in the first interval in accordance with Table IWB-2500-1:
(1) Pressure-Retaining Welds in Reactor Vessels (2) Pressure-Retaining Welds in Vessels.0ther than Reactor Vessels (3)
Full Penetration Welds of Nozzles in Vessels (4)
Pressure-Retaining Partial Penetration Welds in Vessels (5) Pressure-Retaining Dissimilar Metti Welds (6) Pressure-Retaining Bolting, Greater than 2 in. in Diameter (7)
Pressure-Rethining Bolting, 2 in. and Less in Diameter (8)
Integral Attachments for Vessels (9) Pressure-Retaining Welds in Piping (10) Integral Attachments for Piping, Pumps, and Valves (11) Pump Casings and Valve Bodies, including Pressure-Retaining Welds (12) Interior of Reactor Vessel, including Welded Core Support Structures, Interior Attachments, and Removable Core Support Structures I
(13) Pressure-Retaining Welds in Control Rod Housings (14) All Pressure-Retaining Components - Pressure Tests (15) Steam Generator Tubing.
4 l
l 2.3.1.2 Class 2 Requirements. The following Class 2 components are to be examined in the first interval in accordance with Table IWC-2500-1:
(1) Pressure-Retaining Welds in Pressure Vessels.
(2) Pressure-Retaining Nozzle Welds in Vessels
'(3)
Integral Attachments for Vessels, Piping, Pumps, and Valves (4) Pressure-Retaining Bolting Greater than 2 in. Diameter (5) Pressure-Retaining Welds in Piping (6) Pressure-Retaining Welds in Pumps and Valves (7) All Pressure-Retaining Components - Pressure Tests.
2.3.1.3 Class 3 Requirements. The following Class 3 reactor-connected and associated systems are to be examined in the first interval in accordance with IWD-2500-1:
(1) Systems in Support of Reactor Shutdown Function (2) Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal (3) Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool.
2.3.1.4 Comoonent Sucoorts. The following component supports are to be examined in the first interval in accordance with IWF-2500-1:
(1) Plate and Shell Type Supports (2) Linear Type Supports (3) Component Standard Supports.
2.3.2 Preservice Inspection Commitments Based on a review of NUREG-0800 (formerly NUREG-75/087), Standard Review Plan (SRP) Sections 6.6 and 3.6.1, including Branch Technical Position (BTP) ASB 3-1 and Appendices A through C, and the Waterford 3 FSAR Sections 3.6.2.1.4 and 6.6.8, LP&L has developed the Augmented Program for imple-mentation at the Waterford 3 Steam Electric Station. The augmented examination program includes main steam and feedwater piping, and the two 14-in shutdown cooling lines and the four 8-in low pressure safety injection lines penetrating containment.
5
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1 A supplemental program has been established by Louisiana Power and Light in order to address concerns relative to Intergranular Stress Corrosion Cracking (IGSCC) in stainless steel piping containing stagnant borated water.
l LP&L selected approximately 10% of the total number of welds in certain j
designated lines of Safety Injection and Containment Spray systems for volu-metric examination in lieu of the required surface examinations. Every l
effort has been made to select a representative sample of weld types with i
particular emphasis placed on areas where structural discontinuities are present.
2.4 Comoliance with Requirements 2.4.1 Applicable Code Edition The initial inservice inspection interval examination program must comply (10 CFR 50.55a(g)(4)(i)) with the requirements of the latest edition and addenda of Section XI incorporated into 10 CFR 50.55a on the date 12 months before the date of issuance of the operating license. Based on a March 16, 1985, operating license for Waterford 3, the Code applicable to the first-interval program is the 1980 Edition with Addenda through Winter 1981.
The licensee prepared the first-interval program to the applicable Code.
2.4.2 Code Requirements The first interval ISI 1,and2oftheISIprogram.gogy)ofrecordiscontainedinRevisions0, The ISI program submitted in the three revisions was reviewed (exclusive of pump and valve testing) and the following observations were noted:
(1) The licensee addressed the staff's request for additional infor-mation satisfactorily, and the ISI program was revised accordingly.
(2) The Waterford 3 ISI program has been prepared in accordance with the applicable version of the Code.
(3)
Sample size and weld selection of Class 1 and 2 piping welds have been implemented in accordance with the Code.
(4)
Exemption criteria for Class 1, 2, and 3 components have been applied in accordance with the Code.
(5)
Examination of Class 1, 2, and 3 component supports have been implemented in accordance with Subsection IWF.
(6)
ISI Program Section 1.10 states that all mechanical and hydraulic snubbers are visually examined and functionally tested in ac:ordance with paragraph 4.7.8 of the Waterford 3 Technical Specifications. Paragraph 4.7.8(e) of the technical specifica-tions gives three different snubber testing plans and states that the NRC Regional Administrator shall be notified in writing 6
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of the sample plan selected for use. A review of the three plans (paragraphs 4.7.8(e)(1), (2), and (3), respectively) indicates that paragraph 4.7.8(e)(1) appears to be the only plan which meets the Code requirements. The licensee should therefore perform snubber testing in accordance with technical specification paragraph 4.7.8(e)(1).
(7) The procedures detailing hydrostatic testing and any relief requests associated with these tests were not included in the ISI program. These procedures will be developed during the second period of the first interval.
2.4.3 Preservice Inspection Commitments The commitment made in Section 6.6.8 of FSAR Amendment 33 for an augmented Inservice Inspection program to protect against postulated piping failures in at::ordance with SRP 6.6 and BTP 3-1 has been met. FSAR Section 6.6.8 also committed to a supplemental ISI program of a volumetric examina-tion of certain welds in the Safety Injection and Containment Spray systems.
This commitment was also met. However, the supplemental program is the subject of two relief requests addressed in Section 3.2 of this report.
Welds included in the augmented ISI program for which relief is requested are subject to evaluation by the staff.
2.5 Conclusions and Recommendations Based on the preceding evaluation, it is concluded that the Water-ford 3 program meets the requirements of (1) the Code and (2) NRC regu-lations, except as summarized below.
(1) Procedures detailing hydrostatic testing must be submitted before final approval of the first interval ISI program can be given.
(2) Snubber testing should be performed in accordance with paragraph 4.7.8(3)(1) of the Waterford 3 Technical Specifications.
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3.
EVALUATION OF RELIEF REQUESTS l
The following sections evaluate the 19 pending relief requests.
l The material included in the paragraphs titled Code Relief Recuest, Proposed Alternative Examination, and Licensee's Basis for Recuestino Relief is based on the licensee's relief request except for minor editorial changes such as i
removing references to figures and tables not included in this report. The l
material included in the paragraphs titled Code Requirements, Evaluation, and Conclusions and Recommendations, is written by SAIC.
3.1 CLASS 1 COMPONENTS 3.1.1 Reactor Vessel 3.1.1.1 Relief Recuest 151-001. Pressure Retainino Welds in Reactor Ve4sel.
Cateoory B-A. Item B1.11 Code Reovirements All circumferential welds in the reactor vessel shall be volumetrically examined in accordance with Figure IWB-2500-1 over 100% of their lengths in the first interval.
Examinations may be performed at or near the end of the interval.
Code Relief Recuest Relief is requested from performing a 100% volumetric exami-nation of the bottom head-to-lower shell course and the lower shell course-to-middle shell course circumferential welds.
p d?
Prooosed Alternative Examination Alternate analyses, search units, vee paths, and other tech-niques will be used to provide additional coverage where practical (see Attachment 1).
8
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f Licensee's Basis for _Recuestino Relief The bottom head-to-lower shel10},40,'85,160,205,250, couS5 "81d 15 P*rti8 7 11 o
o l
obsgructedby,corestoplugsat i
1 280, and 325. The lower shell corcse-to-middle shell course geld is partiglly ogstrucged by matgrial surveillance brackets at 83,
o 97, 104, 263, 277, and 284 Evaluation The construction permit for Waterford 3 was issued on November 14, 1974. The ASME first published rules for inservice inspection in the 1970 Edition of Section XI.
Because the plant system design and ordering of long lead time components were well under way by the time the Section XI rules became effective, full compliance with the exact Section XI access and inspectability requirements of the Code are not always practical.
In Reference 11, the licensee provided a detailed summary of the welds that will receive a limited or partial examination. A detailed description of the interference for each weld is given. The subject welds cannot be fully examined due to non-removable reactor vessel internal attachments.
The reactor vessel was examined according to the 1974 Summer 1975 Code during preservice examinations. During the first inspec-tion interval, all welds in the reactor vessel will be fully volu-metrica11y examined except the two for which relief is requested. A partial examination will be performed'on these welds.
The bottom head-to-lower shell and lower shell-to-middle shell welds should receive an ultrasonic examination to the extent practical using alternate search units and scan angles to provide maximum coverage. This examination, along with visual examinations for evidence of leakage in the areas of the lower head and shield annulus during Code-required pressure tests, will provide necessary assurance of weld integrity during this interval.
I Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, the Code requirements are impractical.
It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided l
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[j; (a) the-volumetric examinations are performed to the maximum lt' extent practical, and il
. the Code-required visual examinations are made during each (b).
system pressure test for evidence of leakage in the area of the shield annulus.
References References 8, 9, and 11.
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I, 3.1.2 Pressurizer 3.1.2.1 Relief Recuest 151-001. Pressurizer Surae Nozzle-to-Bottom Head Wold. Cateaory B-D. Item B3.110 Code Requirement All nozzle-to-vessel welds in the pressurizer shall be volumetrically examined in accordance with Figures IWB-2500-7(a),
(b), or (c) during the first interval of operation. At least 257, but not more than 507. (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection period of each inspection interval.
If examinations are conducted from inside the component and the nozzle weld is examined by straight beam ultrasonic method from the nozzle bore, the remaining examinations required to be conducted from the shell may be performed at or near the end of each inspection interval.
Code Relief Reauest Relief is requested from performing a 1007. volumetric examination of the pressurizer surge nozzle-to-bottom head weld.
Procosed Alternative Examination Alternate analyses, search units, vee paths, and cther techniques will be used to provide additional coverage where practical.
Licensee's Basis for Recuestina Relief The pressurizer surge nozzle-to-bottom head weld is partially obstructed by four pressurizer heater connections located approxi-mately.nine inches from the toe of the weld.
Evaluation In Reference 11, the licensee provided a detailed summary of welds that will receive a limited or partial examination. A detailed description of the interferences for each weld is 11
^
given.
It is agreed that the limitations noted above could inhibit the ability to obtain gaod ultrasonic results with the practices and procedures presently in use by the licensee. The licensee will perform a partial examination.
In addition, the nozzle inside radius section will be fully examined.
The surge nozzle-to-bottom head nozzle should receive an ultrasonic examination to the extent practical using alternate search units and scan angles to provide maximum coverage. This examination, along with visual examinations for evidence of leakage during Code-required pressure tests will provide necessary assurance of structural integrity. However, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize the quality of examination results.
If a method becomes available during this interval to fully examine the subject weld, this examination should be performed in lieu of the partial examination.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, the Code requirements are impractical.
It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided (a) the volumetric examinations are performed to the maximum j
extent practical, had (b) the Code-required visual examinations are made during each j
system pressure test for evidence of leakage.
Every effort should be made by the licensee to assure that the equipment and procedures used to perform the examination are among the most up-to-date that are commercially available at the time the I
examinations are performed.
If a method becomes available during this interval to fully examine this weld, this examination should be performed in lieu of the partial examination.
l A-l References References 8, 9, and 11.
I2 1
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3.1.3 Heat Exchangers and Steam Generators 3.1.3.1 Relief Reouest 151-001. Pressure Retainina Steam Generator Primary Side Head Welds. Cateaory B-B. Item B2.51 Code Requirements All circumferential head welds in the primary side of the heat exchangers as shown in Figure IWB-2500-20(e) shall be volu-metrica11y sxamined in accordance with Figures IWB-2500-1 and -3 over. essentially 100% of their length during the first inspection interval.
' Code Relief Reauest Relief is requested from performing a 100% volumetric exami-nation on the following steam generator pressure retaining head welds:
Steam Generator No. 1 (a) Bottom head hemisphere-to-tubesheet extension weld (b) Stay cylinder-to-stay cylinder base weld.
Steam Generator No. 2 l
(a)- Bottom head hemisphere-to-tubesheet extension weld (b) Stay cylinder-to-stay cylinder base weld (c) Stay cylinder-to-stay cylinder extension weld (d) Stay cylinder extension-to-tubesheet weld.
- q Pronosed Alternative Examination Alternate analyses, search units, vee paths, and other l
techniques will be used to provide additional coverage where practical.
13 1
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Licensee's Basis for Reauestina Relief The licensee gives the following reasons that 100% volumetric examination cannot be performed on the subject welds:
Steam Generator No. 1 (a) Thebottomheadhemisphere-to-tubesheetextensfonwgidis obstruegedby3/4in.instrumentnozzlesat 21, 33, 327,,
and 339, which are miocated 7-1/2 in. from the centerline of the weld.
(b) The stay cylinder-to-stay cylinder base weld cannot be completely examined due to the curvature of the stay cylinder, causing loss of contact.
Steam Generator No. 2 (a) Thebottomheadhemisphere-to-tubesheetextensjonwgidis obstrucgedby3/4in.instrumentnozzlesat.21,33,327, and 339, which are located 7-1/2 in. from the centerline of the weld.
(b) The stay cylinder-to-stay cylinder base weld cannot be completely examined due to the curvature of the stay cylinder, causing loss of contact.
(c) Thestaycylinder-to-staycylinderextensionwefdcannotbe completely examined due to foss of contact on 0 scan in the base metal above the weld caused by I.D. bevel.
(d) The stay cylinder extension-to-tubesheet weld cannot be completely examined due to loss of contact above the weld cansed by I.D. bevel.
Evaluation Mn Reference 11, the licensee provides a detailed summary of welds..that will receive a limited or partial examination. A detailed description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. The licensee does not provide an estimate of what percentage of each weld will not be fully examined; however, a partial examination will be performed on all welds for which relief is requested.
14
The subject welds should receive an ultrasonic examination to the extent practical using alternate search units, scan angles and transducer heads to provide maximum coverage and contact. This examination, along with visual examinations for evidence of leaka during Code-required pressure tests will provide necessary assur ge ance of structural integrity. Howev9r, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize the quality of enmination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, the Code requirements are impractical.
It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided (a) the volumetric examinations are performed to the maximum extent practical, and I
(b) the Code-required visual examinations are made during each system pressure test for evidence of leakage.
Every effort should be made by th.e licensee to assure that the equipment and procedures used to perform the examination are among the most up-to-date that are commercially available at the time the examinations are performed.
If a method becomes available during this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
l l
l 15 l
J
.?
'3.1.4 -
Piping Pressure Boundary 3.1.4.1 Relief Reauest 151-001. Pressure Retainino Dissimilar Metal Welds.
Cateoory B-F. Items 85.40 and B5.130 Code Requirements All dissimilar metal nozzle-to-safe end butt welds and safe end butt welds in piping 4 in. and greater are to be examined by volumetric and surface methods in accordance with Figure IWB-2500-8 during each inspection interval.
Code Relief Recuest Relief is requested from 100% volumetric examination of the dissimilar metal welds listed in Table 1.
Table 1.
DISSIMILAR METAL WELDS REQUIRING RELIEF Weld No.
Line Number / Designation 16-017 12" pressurizer surge nozzle-to-safe end weld 26-001 Pressurizer nozzle-to-8"x6" reducer safe end weld 26-006 Pressurizer nozzle-to-8"x6" reducer safe end weld 26-010 Pressurizer nozzle-to-8"x6" reducer safe end weld 25-029 4" pressurizer spray nozzle-to-safe end weld 07-002 IRC30-7RLIA
~
08-009 IRC12-37RLIA 08-014 IRC30-3RLIA 15-008 IRC14-44RLI 15-009 IRC12-11A/B
.09-016-IRC30-8RLIB 10-002, IRC30-4RLIB 10-008" IRC12-38RLIB 06-006 IRC14-45RL2 11-002 IRC30-94L2A 12-009 IRC12-39RL2A 12-012 IRC30-5RL2A 13-016 IRC30-10RL2B 14-002 IRC30-6RL2B 14-006 IRCl2-40RL2B 16
_______ _ _ _ _ _ _ _ _ _ M u
l 1
Prooosed Alternative Examination Alternate analyses, search units, vee paths, and other i
techniques will be used to provide additional coverage where practical.
Licensee's Basis for Reouestino Relief Configuration, permanent attachments, and/or structural interferences prohibit 100% ultrasonic examination coverage of the required examination area and volume.
In most cases, good root area coverage is obtained. See Attachment 1, Category B-F, Items B5.40 and B5.130.
Evaluation In Reference 11, the licensee provides a detailed summary of welds that will receive a limited or partial examination. A detailed description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. The licensee does not provide an estimate of what percentage of each weld will not be fully examined; however, a partial examination will be performed on all welds for which relief is requested.
The subject welds should receive'an ultrasonic examination to the extent practical using alternate search units, scan angles and transducer heads to provide maximum coverage and contact. This examination, along with visual examinations for evidence of leakage during Code-required pressure tests will provide necessary assur-ante of structural integrity. However, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize the quality of examination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
9 Conclusions and k'.mftwtions Based on the above evaluation, it is concluded that for the dissimilar metal welds discussed above, the Code requirements are impractical.
It is further concluded that the alternative examina-tion will provide necessary assurance of structural integrity during this interval. Therefore, relief is recommended as requested provided 17
4?[-
,1.s i
(a) 1the volumetric examinations are performed to the maximum p
extent practical, and (b) the Code-required surface examinations and visual exami-nations during each system pressure test for evidence of leakage are performed.
Every effort should be made by the licensee to assure that the equipment and procedures used to perform'the examination are among the most up-to-date that are commercially available at the time the examinations are performed.. If a method becomes available during this interval to. fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
f-
.+
,f d m
18
_________2
3.1.4.2 Relief Recuest 151-001. Prqssure Retainino Welds in Pioino.
Cateoory B-J. Items 89.11. B9.12. and 89.31 Code Requirements For circumferential (89.11) and branch pipe connection (B9.31) welds in pipe of nominal pipe size 4 in. and greater, surface plus volumetric examinations shall be performed in accordance with Figures IWB-2500-8, -9, -10, and -11 over essentially 100% of the weld length during each inspection interval. These examinations shall include the following:
(a) All terminal ends in each pipe or branch run connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
(1) primary plus secondary stress intensity of 2.4S* for ferritic steel and austenitic steel, and (2) cumulative usage factor U of 0.4.
(c) All dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steels, (b) carbon or low alloy steels to high nickel alloys, and (c) high alloy steels to high nickel alloys.
I (d) Additional piping welds so that the total equals 25% of the circumferential joints in the reactor coolant piping system.
This does not include welds excluded by IWB-1220. These additional welds may be located in one loop.
For longitudinal welds in pipe of nominal pipe size 4 in, and greater (89.12), surface plus volumetric examinations shall be performed in accordance with Figure IWB-2500-8 for at least a pipe-diameter length, but not more than 12 in., of each longitudinal weld intersecting the circumferential welds required to be examined by Examination Categories B-F and B-J.
For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need be examined for transverse reflectors.
I 19 ru
Code Relief Recuest Relief is requested from volumetric examination of.100% of the i
required area and volumes of 57 Class 1 pipe welds (52 circumferen-
['
tial, 3 branch connection, and 2 longitudinal) in piping. Specific welds, covered by this relief request and scheduled to be examined during this interval, are identified in Attachment 1, Category B-J, Items 89.11, B9.12, and 89.31.
Procosed Alternative Examination Alternate analyses, search units, vee paths, and other techniques will be used to provide additional coverage where practical.
Every effort has been made when selecting welds to minimize the selection of welds which will require a. request for relief.
Licensee's Basis for Recuestina Relief Configuration, permanent attachments, and/or structural interferences. prohibit 100% ultrasonic and surface examination coverage of the required examination area and volume. - Additional NDE techniques are employed, where practical, to achieve the Code required area and volume. See Attachment 1 (Category B-J, Items 89.11, B9.12, and B9.31) for detailed examination constrictions for each weld.
c Ev_,itlyfij_qn TLe two major reasons for requesting relief are limited physical access for inspection equipment and joint configura-tions, which limit search unit contact with the surface.
The licensee has requested relief from 100% coverage of the Code-required volume on Class 1 piping welds.
Fifty-two of the welds are circumferential piping joints, three are branch connections, and two are longitudinal seam welds in piping.
In Reference 11, the licensee provides a detailed summary of welds that will receive a limited or partial examination. A detailed description of the inter-ference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. A partial examination will-be performed on all welds for which relief is requested.
20
_______-________O
The subject welds should receive an ultrasonic examination to the extent practical using alternate search units, scan angles and-transducer heads to provide maximum coverage and contact. This examination, along with' visual examinations for evidence of leaka during Code-required pressure tests will provide necessary assur ge ance of structural integrity. However, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize
'the quality of examination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
T Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, adherence to.the Code requirements is imprac-tical.
It is further concluded that the proposed examinations will provide necessary assurance of structural reliability during this interval. Therefore, relief is recommended as requested provided (a) the volumetric examinations are performed to the maximum extent practical, and (b) the Code-required surface examinations and visual examinations during each system pressure test are performed.
Every effort should be msde by the licensee to assure that the equipment and procedures used to perform the examination are among the most up-to-date that are commercially available at the time the examinations are performed.
If a method becomes available during this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
L 21 l
._--__-____-_-__-__-___-______a
.w i
3.1.5 Pump Pressure Boundary 3.1.5.1 Relief Recuest 151-004. Reactor Coolant Pumo Pressure Boundary.
Cateaories B-L-1 and B-L-2. Items B12.10 and B12.20 Code Requirement Pumo Casina Welds. Item B12.10 Essentially 100% of the pressure-retaining welds in at least one pump in each group of pumps performing similar functions in the system shall be volumetrically examined in accordance with Figure IWB-2500-16 during each inspection interval. The examinations may be performed at or near the end of the inspection interval.
Pumo Casinas. Item B12.20 The internal surfaces of at least one pump in each group of pumps performing similar functions in the system shall be visually examined (VT-3) during each inspection interval. The examination may be performed-on the same pump selected for volumetric examination of-welds. The examinations may be performed at or near the end of the inspection interval.
Code Relief Recuest Relief is requested from conducting the required primary reactor coolant pump examinations.
Proposed Alternative Examination
- In lieu of the required examination for Category B-L-1, a 100%
visual.(VT-1) examination of the external surface (s) of all pressure-retaining welds shall be performed to the extent and frequency of Table IWB-2500-1, Category B-L-1, Item B12.10.
In the event that pump disassembly is required for maintenance purposes,100% visual (VT-3) examination of the accessible internal surfaces of all pressure-retaining welds shall be performed to the extent and frequency of Tabic IWB-2500-1, Category B-L-2, Item B12.20.
l 22
i i
licensee's Basis for Reauestino Relief The pump casings are fabricated with SA-351 CF8M austenitic stainless steel castings using Type 308 filler metal which contains 5 to 25% and 5 to 18% delta ferrite, respectively. The presence of delta ferrite provides resistance to IGSCC and improves pitting resistance. To date, the pump manufacturer and the NSSS supplier report no documented instances where repairs to pump casings were necessitated by pump casing material failure or unacceptable volu-metric examination results. Therefore, volumetric examination provides little or no additional safety margin.
The duplex microstructure of the austenitic pump casing and weld metal prevents performance of meaningful ultrasonic (UT) examination.
Even when using state-of-the-art UT examination techniques, indica-tions are effectively masked by the " noise" created from the microstructure. UT is not an acceptable method for volumetric examination.
To perform radiographic examination, complete disassembly of the pump is required. There is no requirement to disassemble the pump for any scheduled normal maintenance.
Industry experience indicates a very low probability of complete disassembly for non-routine maintenance.
Should pump disassembly be performed solely for the purpose of radiographic examination, the potential for substantial man-rem exposure is high. The man-hours expended in pump disassembly / assembly and the accompanying man-rem exposure will not provide any additional safety margin and therefore constitutes undue hardship.
The alternative examinations proposed represent the most reasonable and meaningful technique, considering the low potential for problems. A surface examination method (dye penetrant) was considered, but extensive preparation of the as-cast pump surface is required with no significant increase in the likelihood that indications would be revealed. The system leakage test and system hydrostatic test required by IWB-2500-1, Category B-P, Items 15.60 and B15.62, respectively, provide further assurance of pressure boundary integrity.
Evaluation Disassembly of the reactor coolant pumps to the extent required for' examination under Categories B-L-1 and B-L-2 is a major main-tenance effort.
Inspection of a pump on a similar plant required nearly 6000 manhours and resulted in nearly 50 man-rem exposure.
In addition, the pump inspection activity generated a large volume cf radioactive waste.
23
___ a
The performance of reactor coolant pumps in service has been good, and no significant degradation of pump internal surfaces or casing welds has been detected. Accordingly, the large expenditure of effort to disassemble and inspect the pump is not practical in view of the good performance record for primary coolant pumps. Volu-metric examination of the pump casing welds and visual examination of the pump internal surfaces would not produce an increase in plant safety commensurate with the cost of conducting the examinations.
In lieu of the required Category B-L-1 examination, the licensee has agreed to conduct a visual (VT-1) examination of the external surfaces of all pressure-retaining pump casing welds.
In lieu of the required Category B-L-2 examination, the licensee has agreed to conduct a visual (VT-3) examination of the accessible surfaces of all pressure-retaining welds if a pump is disassembled for maintenance.
The licensee should note that under Category B-L-2, a VT-3 is i
required for the entire pump casing internal surface, not just the weld internal surfaces.
Relief from the Code requirements of Examination Categories B-L-1 and B-L-2 is justified. However, the proposed alternative examination should be extended to 1 clude all Category B-L-1 and B-L-2 examination requirements if a pump is disassembled for maintenance; the Code-required visual examination for evidence of leakage during pressure tests and pump testing in IWP should also be performed.
Conclusions and Recommendations Based on the above evaluation, <t is concluded that for the examinations discussed above, adherence to the Code requirements is impractical.
It is further concluded that the licensee's proposed alternative examinations, along with the additional examination discussed in the above evaluation, will provide necessary assurance of structural reliability during this interval.
Therefore, relief is recommended as requested provided (a) volumetric examination of the pump casing welds is con-ducted in accordance with Category B-L-1 if one pump is disassembled for maintenance, (b) the required visual examinations are conducted under Category B-L-2 if a reactor coolant pump is disassembled for maintenance, and if this visual examination indicates internal degradation, a surface examination of the internal surface should be considered, (c) pump testing is performed as required by IWP, and 24 1
E________________________
l
.g (d) visual examination of the pump casing for leakage is conducted in conjunction with system leakage and hydrostatic tests under Category B-P.
References References 8, 9, and 11.
f*
25
.~
3.1.6 Valve 7; essure Boundary 3.1.6.1 Relief Reouest ISI-003. Valve Bodies. Cateoory B-M-2. Item B12.50 Code Requirement A visual (VT-3) examination of the internal surfaces must be performed on at least one valve in each group of valves exceeding 4 in. nominal pipe size which are of the same constructional design, such as globe, gate, or check valves and manufacturing method, and that are performing similar functions in the system such as contain-ment isolation and system overpressure protection. The visual examination may be performed on the same valve selected for volumetric examination of valve body welds.
Code Relief Reouest Relief is requested from visual examination of the internal surfaces of Class 1 valves in piping greater than 4 in. nominal pipe size until maintenance / disassembly is required.
Procosed Alternative Examination Perform the required VT-1 examinations in accordance with the sampling criteria of Table IWB-2500-1, Category B-M-2, Note 3, in the event the components are disassembled for maintenance or repair.
Licensee's Basis for Reouestino Relief The Code requirement to disassemble one valve from each design group for the purpose of visual examinations has a small potential for identification of service-induced flaws or degradation. The industry performance of these valves has proved their excellent ability to resist service degradation or flawing. The inapprop-riate balance of potential flaw detection and the large impact on expenditures of manpower without substantially increasing component reliability is considered impractical. Also, the substantial expenditures of man-rem without increasing component 6 tegrity is undesirable due to ALARA concerns.
26
4
)
Evaluation Disassembly of large valves to the degree necessary to examine the internal pressure-retaining surfaces is a major effort, which may involve large personnel exposures. To do this disassembly solely to perform a visual examination of the internal body is impractical.
The licensee has committed to the concept of visual exami-nation if the valve is disassembled for maintenance. The visual examination specified is to determine whether anticipated severe degradation of the body is occurring due to phenomena such as erosion j
or corrosion.
The Code-required pressure tests in accordance with Category B-P, along with periodic inservice testing of valves as required by IWV, provide an adequate level of safety.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the examinations discussed above, adherence to the Code requirements is impractical.
It is further concluded that the proposed examination will provide necessary assurance of structural reliability during this interval. Therefore, relief is recommended as requested provided (a) periodic inservice testing of the valves is conducted in accordance with IWV, (b) visual examination of the valves for leakage is conducted in conjunction with system leakage and hydrostatic tests under Category B-P, and (c) the required visual examinations are conducted under Category B-M-2 if a valve is disassembled for maintenance, and if this visual examination indicates internal degrada-tion, a surface examination of the internal surface should be considered.
I References References 8, 9, and II.
27 I
3.2 CLASS 2 COMPONr.NTS 3.2.1 Pressure Vessels and Heat Exchangers 3.2.1.1 Relief Recuest 151-001. Pressure Retainina Welds in the Shutdown Coolina Heat Exchanaer. Cateaory C-A. Items C1.10 and C1.30 Code Requirements Pressure-retaining circumferential welds in the vessel shell at gross structural discontinuities (as defined in NB-3213.2) shall be volumetrically examined in accordance with Figure IWC-2500-1 over essentially 1007. of their lengths each inspection interval.
The tubesheet-to-shell weld shall be volumetrically examined in accordance with Figure IWC-2500-2 over essentially 1007, of its length each inspection interval.
In the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchrners), the required examinations may be limited to one vessel or u.3tributed among the vessels.
The vessel areas selected for initial examination shall be reexamined over the service lifetime of the component.
Code Relief Reauest Relief is requested from performing a 1007. volumetric exami-nation of the shutdown cooling heat exchanger shell-to-flange weld and the shell-to-tubesheet weld.
Proposed Alternative Examination Alternate analyses, search units, vee paths, and other techniques will be used to provide additional coverage where practical.
l.icensee's Basis for Recuestino Relief The subject welds cannot be completely examined at 0 and all 45 scans due to flange radius and weld contour.
28
Evaluation In Reference 11, the licensee provides a detailed summary of welds that will receive-a limited or partial examination. A detailed description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. A partial examination will be conducted on all welds for which relief is requested.
The subject welds should receive an ultrasonic examination to the extent practical using alternate search units, scan angles and transducer heads to provide maximum coverage and contact. This examination, along with visual examinations for evidence of leakage during Code-required pressure tests will provide necessary assur-ance of structural integrity. However, it is clearly incumbent on the. licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize the quality of examination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
i Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, the Code requirements are impractical.
It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided (a) the volumetric examinations are performed to the maximum extent practical, and (b) the Code-required visual examinations are made during each system pressure test for evidence of leakage.
Every effort should be made by the licensee to assure that the equipment and procedures used to perform the examination are among the most up-to-date that are commercially available at the time the examinations are performed.
If a method becomes available during this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
29
_________-___________-___O
3.2.1.2 Relief Reauest IST-001. Pressure Retainino Welds in the Steam Gen-erator Secondary Side. Catecory C-A. Items C1.10. C1.20. and C1.30 Code Requirements Pressure-retaining circumferential welds in the vessel shell at gross structural discontinuities (as defined in NB-3213.2) and the head-to-shell weld shall be volumetrically examined in accordance with Figure IWC-2500-1 over essentially 1007. of their lengths each inspection interval.
The tubesheet-to-shell weld shall be volumetrically examined in accordance with Figure IWC-2500-2 over essentially 1007, of its length each inspection interval.
In the case of multiple vessels of similar design, size, and
~
service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed ameng the vessels. The vessel areas selected for initial examination shall be reexamined over the service lifetime of the component.
Code Relief Reauest Relief is requested from performing a 1007. volumetric examination on all Code-required steam generator secondary side pressure-retaining welds (top head torus-to-top head dome, upper shell-to-top head torus, conical section-to-upper shell, inter-mediate shell-to-conical section, upper extension ring-to-lower shell, tubesheet-to-upper extension ring, and tubesheet-to-stay cylindercap).
l Procosed Alternative Examination Alternate analyses, search units, vee paths, and other techniques will be used to provide additional coverage where I
practical.
f J
)
Licensee's Basis for Reauestino Relief For each weld for which relief is requested, the licensee gives the following reasons for requesting relief:
30
.______________ - _ A
i c
l'..
t (a) Thetopheadtorus-to-topheaddomewefdis,partiglly obsgructegbyigstrumgntnozzlegat 40, 80, 120, 160,,
200, 240, 280, 320, and 360 located 6 in. from the centerline of the weld.
(b) The upper shell-to-top head torus weld is partially obstructed by two 5-in. x 5-in. insulation pads on the bottom side of the weld.
(c) The conical section-to-upper shell weld is partially obstructed by two 5-in. x 5-in. insulation pads on the top side of the weld.
(d) The intermediate shell-to-conical section weld is parti-ally obstructed by two 5-in. x 5-in insulation pads on the i
bottom side of the weld.
~
(e) The upper extension ring-to-lower shell weld and the tubesheet-to-upperextensionringgeldarepartially n
obstructed by 6-in handholes at 0 and 90 and the blow-o down nozzle at 270 located approximately 4 in. and 9 in.,
respectively, from the toe of the weld.
(f) Thetubesheet-to-staycylindercapgeldreceivesapproxi-mately 5% loss of contact for the O scan due to I.D.
cap-to-tubesheet weld configuration.
i Evaluation In Reference 11, the licensee provides a detailed sunmary of welds that will receive a limited or partial examination. A detailed description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. A partial examination will be performed on all welds for which relief is requested.
The subject welds should receive an ultrasonic examination to the extent practical using alternate search units, scan angles and transducer heads to provide maximum coverage and contact. This examination, along with visual examinations for evidence of leakage during Code-required pressure tests will provide necessary assur-ance of structural integrity. However, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools that are among the most up-to-date commercially available to maximize the quality of examination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
31
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds discussed above, the Code requirements are impractical.. It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief fs recommended as requested provided (a) the volumettic examinations are performed to the maximum extent practic.tl, and (b) the Code-required visual examinations are made during each system pressure test for evidence of leakage.
Every effort should be made by the licensee to assure that the equipment and procedures used to perform the examination are among the,most up-to-date that are commercially available at the time the examinations are performed.
If a method becomes available during this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
I q
32 l
lI
3.2.1.3 Relief Recuest 151-001. Steam Generator Pressure Retainino Nozzle Welds and Nozzle Inside Radius Sections. Cateoory C-B. Items C2.21 and C2.22 Code Requirements All nozzle-to-shell (or head) welds of all nozzles in vessels over 1/2 in in nominal thickness at terminal ends of piping runs shall be surface and volumetrically examined in accordance with 1
Figure IWC-2500-4(a) or -4(b) over 100% of their lengths during each inspection interval.
Nozzle inside radius sections of welded or integrally cast nozzles in vessels over 1/2 in. in nominal thickness that connect to piping runs shall be volumet-rically examined in accordance with Figure IWC-2500-4(a) or -4(b) over essentially 100% of their lengths during each inspection interval.. In the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels. The vessel areas selected for initial examination shall be reexamined over the service lifetime of the component.
Code Relief Recuest Relief is requested from performing a 100% volumetric examina-tion on the nozzle-to-vessel welds and nozzle inside radius section of the main steam and feedwater nozzles.
Procosed Alternative Examination Alternate analyses, search units, vee paths, and other techniques will be used to provide additional coverage where practical.
Licensee's Basis for Recuestino Relief Ultrasonicscansonthegainsfeamngzzlegreobgtructgdby g
insgrument nozzles at 45, 90, 135, 180, 225, 270, 315, and 360 located 6 in. from the centerline of the weld. Ultrasonic scans on the feedwater nozzle are obstructed by a 5-in. x 5-in insulation pad below the nozzles.
3'3
o.-.
Evaluation In Reference 11, the licensee provides a detailed summary of A detailed welds that will receive a limited or partial examination.
description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. A partial examination will be performed on all welds for which relief is requested.
The subject welds should receive an ultrasonic examination to the extent practical using alternate search units, scan angles and transducer heads to provide maximum coverage and contact. This examination, along with visual examinations for evidence of leaksge during Code-required pressure tests will provide necessary assur-ance of structural integrity. However, it is clearly incumbent on the licensee to keep up with and use volumetric examination tools
~
that are among the most up-to-date commercially available to maximize.
the quality of examination results.
If a method becomes available during this interval to fully examine any of the above welds, this examination should be performed in lieu of the partial examination.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for theIt is welds discussed above, the Code requirements are impractical.
further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided (a) the volumetric examinations are performed to the maximum extent practical, and the Code-required nozzle-to-vessel weld surface examina-(b) tions and visual examinations are performed during each system pressure test for evidence of leakage.
Every effort should be made i che licensee to assure that the equipment and procedures used to perform the examination are among the most up-to-date that are commercially available at the time the If a method becomes available during l
examinations are performed.
this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
References References 8, 9, and 11.
t 34
3.2.2 Piping Pressure Boundary 3.2.2.1 Relief Recuest 151-001. Inteoral Attachment in the Shutdown Coolino System. Cateoory C-C. Item C3.20 Code Requirements Integrally welded attachments whose base material design thickness is 3/4 in. or greater in piping shall be surface examined in accordance with Figure IWC-2500-5 over 100% of their areas each inspection interval.
Examinations are limited to attachments of those components required to be examined under Categories C-F and C-G.
The areas selected for the initial examination shall be reexamined over the service lifetime of the component.
Code Relief Reauest Relief is requested from performing a 100% surface examination on integrally welded attachment 51-WS-4 in the shutdown cooling system.
Procosed Alternative Examination Surface examination to the extent practical shall be performed.
Licensee's Basis for Recuestino Relief The subject weld cannot be completely surface examined due to bleedout caused by a carbon steel shim positioned flush with the support lug.
Eval $ation Portions of the subject weld cannot be ext. mined due to bleed-out caused by a carbon steel shim positioned flush with the support lug.
Bleedout of penetrant by the shim will result in incomplete penetrant removal in this area. When developer is applied, a bogus indication will appear at the shim-support lug contact point. The 35 n
.+
licensee has committed to performing a surface examination to the extent practical. This best effort examination, along with Code-required general visual examinations during each system pressure test, will provide necessary assurance of structural integrity during this interval.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the weld discussed above, the Code requirements are impractical.
It is further concluded that the alternative examination will provide necessary assurance of structural integrity during this interval.
Therefore, relief is recommended as requested provided (a) the surface examinations are performed to the maximum extent practical, and (b) the Code-required visual examinations are made during each system pressure test.
References References 8, 9, and 11.
36
___-______-___a
f l
3.2.2.2 Relief Recuest 151-001. pressure Retainino Welds in pioine.
)
Catecory C-F. Items C5.11. C5.12. C5.21. and C5.22 Code Requirements One hundred percent of each circumferential weld over 1/2 in.
nominal wall thickness shall be surface and volumetrically examined in accordance with Figure IWC-2500-7 during each inspection inter-val. Circumferential welds less than or equal to 1/2 in. wall thickness shall receive a surface examination in accordance with IWC-2500-7.
(a) all welds at locations where the stresses under the loadings resulting from Normal and Upset plant conditions as calculated by the sum of Equations 9 and 10 in NC-3652 exceed the speci-fied values; (b) all welds at terminal ends (see (e) below) or piping or branch runs; (c) all dissimilar metal welds; (d) additional welds, at structural discontinuities (see (f) below) such that the total number of welds selected for examination includes the following percentages of circumferential piping welds:
1.
none of the welds exempted by IWC-1220; 2.
none of the welds in residual heat removal and emergency core cooling systems; 3.
107 of the main steam system welds 8 in. nominal pipe size and smaller; 4.
257. of the welds in all other systems.
(e) terminal ends are the extremities of piping runs that connect to structures, components (such as vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints or provide at least two degrees of restraint to piping thermal expansion; (f) structural discontinuities include pipe weld joints to vessel
" nozzles, valve bodies, pump casings, pipe fittings (such as, elbows, tees, re:'uters, and flanges conforming to ANSI Standard B16.9), and pipe branch connections and fittings.
Longitudinal welds over 1/2 in. nominal wall thickness shall be surface and volumetrically examined in accordance with Figure IWC-2500-7, and longitudinal welds less than or equal to 1/2 in. wall thickness shall be surface examined (2.5 t at the intersecting circumferential weld) during each inspection interval.
37
__-_____-_-_____2
1 Code Relief Recuest Relief is requested from surface and volumetrically examining 100% of the required area and volumes of certain Class 2 pipe welds (circumferential, branch connection, and longitudinal) in piping.
Specific welds, covered by-this relief request and scheduled to be examined during this interval, are identified in Attachment 1, Category C-F, Items C5.11, C5.21, and C5.22.
Proposed Alternative Examination Alternate analyses, search units, vee paths, and other techniques will be used to provide additional coverage where practical.
Every effort has been made when selecting welds to minimize the selection of. welds which will require a request for relief.
Licensee's Basis for Recuestina Relief
. Configuration, permanent attachments, and/or structural interferences prohibit 100% ultrasonic and surface examination coverage of the required examination area and volume. Additional NDE techniques are employed, where practical, to achieve the Code required area and volume. See Attachment 1 (Category C-F, Items C5.11, C5.21, and C5.22) for detailed examination constrictions for each weld.
Evaluation The two major reasons for requesting relief are limited physical access for inspection equipment and joint configurations, which limit search unit contact with the surface or limit the use of all scan angles.
The licensee has requested relief from 100% coverage of the Code-required volume on Class 2 piping welds. Of these welds, 108 are circumferential piping joints, and 2 are longitudinal seam welds in piping. Some of the Class 2 piping welds for which relief is requested are part of the licensee's augmented ISI programs in high energy piping systems and in.the safety injection and containment spray systems.
38 A
c,.
In Reference 11, the licensee provides a detailed summary of l
welds that will receive a limited or partial examination.- A detailed I
description of the interference for each weld is given.
It is agreed that the limitations noted above could inhibit the ability to obtain good ultrasonic results with the practices and procedures presently in use by the licensee. A partial examination will be performed'on all welds for which relief is requested.
The subject welds should receive an ultrasonic examination to l
the extent practical using alternate search units, scan angles and l
transducer heads to provide maximum coverage and contact. This examination,- along with visual examinations-for evidence of leakage during Code-required pressure tests will provide necessary assur-1 ance of structural integrity. However, it is clearly incumbent on
.i the licensee to keep up with and use volumetric examination tools that.are among the most up-to-date commercially available to maximize i
the quality of examination results.
If a method becomes available -
during_ this interval to fully examine any of the above welds, this i
examination should be performed in lieu of the partial examination.
l Conclusions and Recommendations 4
l
_ Based on the above evaluation, it is concluded'that for the welds discussed above, adherence to the Code requirements is impractical.
It is further concluded that the proposed examina-tions will provide necessary ass'irance of structural reliability
'during this interval. Therefore, relief is recommended as requested i
provided I
(a) the volumetric and surface examinations are performed to the maximum extent practical, and l'
(b) the Code-required system pressure tests are performed.
l Every effort should be made by the licensee to assure that the
' equipment and procedures used to perform the examination are among i
the most up-to-date that are commercially available at the tinie the i
examinations are performed.
If a method becomes available during l
this interval to fully examine any of the above welds, this exami-nation should be performed in lieu of the partial examination.
C i
J References References 8, 9, and 11.
q l
l l
39 0
._- - _-____ - _ _ __ l
3.2.2.3 Relief Recuest ISI-002. Pressure Retainino Welds in Pinino.
Cateoory C-F. Items C5.11 and C5.12 (Cateoories C-F and C-G.
Item C2.1 in 75575)
Code Requirements The licensee is required (10 CFR 50.55a(b)(2)(iv)) to use the 1974 Edition of the Code, Summer 1975 Addend: to determine the extent of residual heat removal, emergency core cooling, and containment heat removal piping examinations under Category C-F.
This Code requires that the examinations cover 100% of the weld.
The areas shall include:
(a) circumferential butt welds at structural discontinuities, (b) circumferential butt welds in piping within three pipe diameters cf the centerline of rigid pipe anchors, or anchors at the penetration of the primary reactor containment, or at rigidly anchored components, (c) longitudinal weld joints in pipe fittings (i.e.. in tees, elbows, reducers),
(d) branch connection weld joints, and (e) pump casing and valve body weld joints.
This includes the weld metal for one wall thickness beyond the edge of the weld.
The 1980 Winter 1981 Code requires that the surfaces of 100% of each circumferential weld 1/2 in. or less nominal wall thickness shall be examined in accordance with Figure IWC-2500-7 during each inspection interval.
Longitudinal welds less than or equal to 1/2 in. wall thickness shall be surface examined (2.5 t at the intersecting circumferential weld)~during each inspection interval.
Code Relief Recuest Relief is requested from surface examination of certain welds in Class 2 piping with a wall thickness of 1/2 in. or less.
40
___ _ ___ __ _ ____JL
Proposed Alternative Examination Perform ultrasonic examinations on 10% of the welds on certain Safety Injection and Containment Spray lines in lieu of the required surface examinations.
Licensee's Basis for Reauestina Relief LP&L selected approximately 10% of the welds in certain suction lines of Safety Injection and Containment Spray systems for ultra-sonic examinations in lieu of surface examinations.
Every effort was made to select a representative cross-section of weld types with particular emphasis placed on areas where structural discontinuities were present.
Evaluation The licensee has committed to an augmented inspection program, consisting of supplemental volumetric examination by UT techniques of certain welds in suction lines of Safety Injection and Containment Spray systems using procedures that are capable of detecting IGSCC.
The subject lines have wall thicknesses of less than one-half inch and have design and maximum operating temperatures of 2500F and 2400F, respectively. These lines would normally, by Section XI Code rules, require only surface examinations.
In cases where IGSCC is a possible mechanism of degradation in thin wall pipe, it is possible that indications will have propagated from the inside surface through the pipe wall, and leakage will occur before the indications are detected by the required surface examina-tion methods. The examination proposed by the licensee is therefore equivalent or superior to the code required examination.
Further-more, the licensee has committed to perform the required surface examination on welds outside of the suction side in these systems.
Relief is therefore warranted provided the ANII is satisfied per IWA-2240 that the ultrasonic exami. nation methods used by the licensee are effective in detecting IGSCC.
Conclusions and Recommendations Based on the a%ve evaluation, it is concluded that the examination proposed will provide necessary assurance of structural reliability during this interval. Therefore, relief is recommended provided the ANII is satisfied per IWA-2240 that the ultrasonic examination methods used by the licensee are effective in detecting IGSCC.
References References 8, 9, and 11.
4I
_-_-___ l
3.3 CLASS 3 COMPONENTS 3.3.1 Relief Reauest 151-005. Class 3 Intearal Attachments.
Cateaories D-A. D-8. and D-C. Items D1.20-01.60. 02.20-D2.60, and D3.20-03.60 Code Requirement Integral attachments shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection intarval.
Integral attachments include component supports and restraints, mechanical and hydraulic snubbers, spring type supports, constant load type supports, and shock absorbers. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The. integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
The VT-3 examination shall be performed at the frequency specified in Table IWD-2500-1.
Code Relief Reauest Relief is requested to perform the required Class 3 integral attachment examination in conjunction with the required component support examinations under Subsection IWF.
Prooosed Alternative Examination In lieu of the examination boundaries of IWF-1300-1, the entire support, including the integral attachment, is classified as an IWF support examination boundary.
Licensme's Basis for Reauestino Relief Performing the required IWD integral attachment examination under IWF does not affect the number of supports selected, the examination method, or the extent of the examination. However, categorization and scheduling is performed under the requirements of one article (IWF-2000) negating the undue hardship of implementing both Articles IWD and IWF.
42
__-____-______Q
i.-
l 1
1 Evaluation The licensee's relief request does not result.in any difference in examination method,. extent of examination, or schedule require-
{
ments for Class 3 integral attachment supports. Therefore, the subject relief is not necessary. Note, however, that any relief granted for supports under IWF does not relieve the licensee of the responsibility of examining the' integral attachments.
Conclusions and Recommendations Based on the above evaluation, it is concluded that the licensee is meeting the Code requirements and relief is not necessary, and therefore, should not be granted.
References References 8, 9, and 11.
f "A
43
____________--______5
L 1
1 3.4 PRESSURE TESTS No relief requests.
3.5 GENERAL.
No relief requests.
3.6 COMPONENT SUPPORTS 3.6.1 Relief Reauest ISI-006. Class 3 Component Succorts. 'Cateaory F-C.
Items F3.10--F3.4Q Code Requirement Component supports shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first inspection interval.
For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
Code Relief Reauest Relief is requested from the Code-required visual examination of the supports listed in Table 3.
Pronosed Alternative Examination None.
Licensee's Basis for Reauestina Relief Component support access is completely blocked by permanent non-removable insulation. Supported lines operate at temperatures substantially below ambient and are, therefore, subject to severe condensation. The type of insulation used has a permanently sealed 44
_____-_ - _ A
vapor barrier to' exclude moisture, and removal of the insulation in the support area results in vapor contamination of the surrounding insulation. Possible alternate removable type vapor barrier insulation is not acceptable due to fluoride / chloride content.
The requirement for a vapor barrier necessitates non-removable insulation. During the construction pl*ise, examinations were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes.
TABLE 3.
SUPPORTS REQUIRING RELIEF Succort No.
Line No.
Code Class ACR-513 3AC8-7A, 14A 3
ACR-515 3AC8-7A, 14A 3
ACR-1034 3AC10-15A 3
ACR-561 3AC6-288, 29B 3
ACR-563 3AC6-28B, 298 3
ACR-551 3AC6-40A 3
ACR-408 3AC6-41A, 42A 3
ACR-410 3AC6-41A, 42A 3
ACR-419 3AC6-41A, 42A 3
ACR-1036 3AC6-42A 3
ACR-1131 3AC6-43B 3
ACR-523 3AC6-52A 3
ACR-522 3AC6-53A 3
ACR-1058 3AC6-40A 3
ACR-570 3AC6-43B 3
ACR-1087 3AC6-40B 3
Evaluation The subject component supports are inaccessible for examina-tion due to non-removable insulation. Removal of insulation in the support area would result in unacceptable vapor contamination of the surrounding insulation. The supports were examined during the construction phase in accordance with the applicable construction 45 l
___-_-_-_-__A
l l.*
codes which provide some assurance of support integrity. However, l
to provide additional assurance of support integrity for each support for which relief is requested, the licensee should, to the extent possible, examine. additional similar supports. The Code-required-system pressure tests should also be performed.
Conclusions and Recommendations l-Based on the above evaluation, it is concluded that for the supports discussed above, adherence to the Code requirements is impractical.
It is further concluded that the proposed examinations discussed in the above evaluation will provide necessary assurance of structural reliability during this interval. Therefore, relief is recommended as requested provided (a) the Code-required system pressure tests are performed, and (b) the licensee examine an additional similar support, to the extent possible, for each support for which relief is requested.
References References 8, 9, and 11.
x 46 i
i 3.6.2 Relief Reauest 15I-007. Class 2 and 3 Comoonent Sucoorts.
Cateaory F-C. Items F3.10--F3.40 1
Code Requirement Component supports shall be visually examined (VT-3) in accordance with Article.IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first inspection interval.
For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
Code Relief Reauest Relief is requested from the Code-required visual examination of the supports listed in Table 4.
Procosed Alternative Examination
- None, licensee's Basis for Reauestina Relief Component supports are in penetrations which are closed off by permanently installed fire seals.
Fire seal material is pumped into the penetration in semi-liquid state and solidifies into a non-removable mass.
Fire seal integrity is a Limiting Condition for Operation, as identified in W-3 Technical Specification paragraph 3.7.11.
This constitutes undue hardship in conducting examinations.
During the construction phase, examinations were conducted to verify acceptability of the component support installations in accordance with the applicable construction code (s).
Evaluation The subject component supports are inaccessible for examina-tion due to permanently installed fire seals. Removal of the fire seal material would be a violation of a Limiting Condition for 1
47 L
o i
l
.]
l f
TABLE 4.
SUPPORTS REQUIRING RELIEF-l-
Suncort No.
Line No.
Code Class ACR-413 3AC6-41A 3
ACR-600 3AC6-41B 3
'ACR-412 3AC6-42A 3
ACR-601 3AC6-428 3
CCRR-781 3CC20-2B 3
CCRR-712 3CC20-3B 3
CCRR-932 3CC6-6A 3
CCRR-465 3CC6-71A
~3 CCRR-471 3CC6-71A 3
CCRR-119 3CC10-83A 3
CCRR-1072 3CC6-106A 3
CCRR-1111 3CC6-106A 3
CCRR-1091 3CC6-106B 3
CCRR-37 3CC6-144A/B 3
LCRR-420 3CC16-202B 3
CCRR-1121 3CC10-289A 3
CCRR-1122 3CC10-2908 3
CSRR-361 2CS10-78 2
CSRR-372 2CS10-98 2
CSRR-334 2CS10-11A 2
SIRR-391 2SI8-113RLIA 2
SIRR-939 2SI8-130RL2A' 2
CCRR-621 3CC16-203A 3
FWCR-262 3FW4-76A 3
Operation as identified in the Technical Specification, paragraph 3.7.11.
The supports were examined during the construction phase in accordance with the applicable construction codes which provide some assurance of support integrity. Howevar, to provide additional assurance of support integrity for each support for which relief is requested, the licensee should examine, to the extent possible, additional similar supports. The Code-required system pressure tests should also be performed.
48
j L
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the l
supports scussed above, adherence to the Code requirements is J
impracti It is.further concluded that removal of the fire seal to enable examination of the supports would be violation of the plant i
technical specifications. Therefore, relief is recommended as requested provided (a) the Code-required system pressure tests are performed, and (b) the licensee examine an additional similar support, to the extent possible, for each support for which relief is requested.
References References 8, 9, and 11.
49
_____-____--____-_-_-_--2
3.6.3 Relief Reouest 151-008. Class 3 Comoonent SuoDorts. Cateaory F-C.
Items F3.17--F3.40 Code Requirement C mponent supports shall be visually examined (VT-3) in accorda..ce with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first 17spection interval.
For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
Code Relief Reovest Relief is requested from the Code-required visual examination of the supports listed in Table 5.
TABLE 5.
SUPPORTS REQUIRING RELIEF Succort No.
Line No.
Code Clati ACR-586 3AC6-41A 3
ACR-587 3AC6-42A 3
CCRR-715 3CC20-28 3
CCRR-526 3CC20-107A 3
CCRR-445 3CC20-201B 3
Procosed Alternative Examination bone.
Licensee's Basis for Reouestina Relief Component supports are in penetrations such that supports are s empletely inaccessible for examination. During the construction piase, examinations were conducted to verify acceptability of the component support installations in accordance with the applicable construction code.
50 1
q Evaluation The subject component supports are inaccessible for examination due to being in penetrations. Removal of the fire seal to enable examination of the supports would be a violation of the plant tech-nical specifications. The number of supports for which relief is requested is small compared with the total number of supports examined.
The supports were examined during the construction phase in accordance with the applicable construction codes which prov'-de some assurance of support integrity. However, to provide addi-tional assurance of support integrity for each support for which-relief is requested, the licensee should, to the extent possible, examine additional similar supports. The Code-required system pressure tests should also be performed.
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the supports discussed above, adherence to the Code requirements is impractical. Therefore, relief is recommended as requested provided (a) the Code-required system pressure tests are performed, and (b) the licensee examine an additional similar support, to the extent possibie, for each support for which relief is requested.
t References References 8, 9, and 11, 51
.n-
c 3.6.4 Relief Reauest 351-009.' Class 3 Comoonent Sucoorts. Catecory F-C.
Items F3.10--F3.40 j
i Code Requirement Component suppoets shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, and IWD during the first inspection interial.
For multiple components within a system of similar design, function, and service, the supports of only one of the mu~.tiple components are required to be examined.
Code Relief Reauest Partial relief is requested from the Code-required visual examination of the supports listed in Table 6.
Procosed Altern,ative Examination The accessible portions of the affected supports are examined to the frequency and extent specified in IWF-2500-1 and IWF-2510.
Licensee's BasiJ for Reauestino Relief Component support access is partially blocked by permanent non-removable insulation. Supported lines operate at temperatures substantially below ambient and are, therefore, subject to severe condensation. The type of insulation used has a permanently sealed vapor.. barrier to exclude moisture, and removal of the insulation in the support area results in vapor contamination of the surrounding insulation. Possible alternate removable-type vapor barrier insu-lation is not acceptable for use due to high fluorida/ chloride content. The requirement for a vapor barrier seal necessitates y
non-removable insulation. During the construction phase, examina-(-
tions were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes.
52
.____._._____._____m_.__m
~
.1 1 TABLE 6.
SUPPORTS REQUIRING RELIEF Sucoort No.
Line No.
Code Class ACR-453 3AC6-1A/B 3
ACR-442 3AC6-1A, 76, 14B 3
.ACR-459 3AC6-1A,lA/B,28, 3
19A,19b,19A/B i
ACR-445 3ACS-1B 3
ACV-446 3AC6-1B 3
ACH-475 3AC6-1B 3
ACR-457 3AC6-2A/B,19A/B 3
ACR-462 3AC6-2A, 2B, 19A, 19B 3
ACR-444 3AC6-2A, 2A/B, 14B, 3
19A, 19A/B ACR-444 3AC6-278, 92B 3
ACR-444 3AC10-6A, 6B, 15A, ISB 3
ACH-403 3AC6-28, 19B 3
3 ACR-1041-3AC10-6A 3
r ACR-1042 3AC10-6A 3
ACR-1064 3AC10-6B 3
ACR-455 3AC8-7A 3
ACH-639 3AC8-7A 3
ACR-512 3AC8-7A, 14A 3
ACR-514 3AC8-7A, 14A 3
ACH-640 3AC8-7A, 14A 3
ACH-534 3AC6-78 3
ACR-476 3AC6-78, 14B 3
ACR-497 3AC6-7B, 14B 3
ACR-499 3AC6-78, 14B 3
53 x
.__-___._______________________lb
TABLE 6 (Continued)
Sucoort No.
Line No.
Code Class ACR-535 3AC6-78, 14B 3
ACR-536 3AC6-78, 148 3
ACR-454 3AC8-14A 3
ACR-533 3AC6-14B 3
ACR-1040 3AC10-15A 3
ACH-460 3AC6-19A/B 3
ACR-452 3AC6-19A/B,22A/B 3
ACR-470 3AC6-21A 3
ACR-450 3AC6-21A/B 3
ACR-471 3AC6-20B 3
ACR-443 3AC6-22A 3
ACR-458 3AC6-22A 3
ACV-472 3AC6-22A 3
ACR-4B0 3AC6-22A 3
ACV 447 3AC6-22A/B 3
ACR-448 3AC6-22A/B 3
ACR-449 3AC6-22A/B 3
ACV-451 3AC6022A/B 3
ACR-1100 3AC6-22A/B 3
ACR-441 3AC6-22B 3
ACV-473 3AC6-22B 3
ACR-474 3AC6-22B 3
ACR-478 3AC6-22B 3
ACR-479 3AC6-22B 3
ACR-516 3AC6-28A, 29A 3
ACR-517 3AC6-28A, 29A 3
ACR-540 3AC6-28B', 298 3
ACH-541 3AC6-288, 298 3
ACR-543 3AC6-288, 29B 3
ACR-544 3AC6-28B, 29B 3
ACR-560 3AC6-288, 29B 3
ACR-562 3AC6-288, 298 3
ACR-564 3AC6-2BB, 29B 3
54 I
9
b,..;
TABLE 6 (Continued)
Sucoort No.
Line No.
Code Class ACR-565 3AC6-288, 29B 3
ACR-566 3AC6-288, 29B 3
ACH-542 3AC6-29B 3
ACR-1093 3AC6-29B 3
ACR-550 3AC6-40A, 53A 3
ACR-568 3AC6-408 3
ACR-1088 3AC6-40B 3
ACR-569 3AC6-408, 438, 49B 3
ACR-406 3AC6-41A, 42A 3
ACR-407 3AC6-41A, 42A 3
ACR-409 3AC6-41A, 42A 3
ACR-417 3AC6-41A, 42A 3
ACR-421 3AC6-41A, 42A 3
ACR-435 3AC6-41A, 42A 3
ACR-1027 3AC6-418 3
ACR-425 3AC6-41B, 42B 3
ACR-426 3AC6-41B, 428 3
ACR-427 3AC6-419, 42B '
3 ACR-431 3AC6-41B 3
ACH-432 3AC6-41B,~428 3
ACR-422 3AC6-42A 3
ACR-430 3AC6-42A 3
ACH-434 3AC6-42A 3
ACR-1037 3AC6-42A 3
ACR-428 3AC6-42B 3
AFA-429 3AC6-42B 3
AbR-1019 3AC6-42B 3
ACR-1060 3AC6-42B 3
.ACR-559 3AC6-43A, 209A 3
ACR-589 3AC6-209A, 210A 3
ACH-609 3AC6-43A, 209A 3
ACR-612 3AC6-43A, 209A 3
55 r '
n.
rr TABLE 6 (Continued)
Suonort No.
Line No.
Code Class ACR-520 3AC6-52A 3
ACR-524 3AC6-52A, 53A 3
ACR-525 3AC6-52A, 53A 3
ACR-526 3AC6-52A, 53A 3
ACR-552 3AC6-52A, 53A 3
ACR-521 3AC6-53A 3
ACR-607 3AC6-209A, 210A 3
ACR-58B 3AC6-209A, 210A 3
ACH-573 3AC6-209B 3
ACR-574 3AC6-209B 3
ACR-595 3AC6-209B 3
ACR-596 3AC6-209B 3
ACR-597 3AC6-209B 3
ACR-575 3AC6-2098, 210B 3
ACR-576 3AC6-2108 3
ACR-604 3AC6-210B 3
ACR-605 3AC6-210B 3
ACH-461 3AC6-1A/B 3
ACR-1149 3AC6-1B 3
Evaluation The subject component supports are partially inaccessible for examination due to non-removable insulation. Removal of insulation in the support area would result in unacceptable vapor contamination of the/ surrounding insulation. The supports were examined during the construction phase in accordance with the applicable construction codes which provide some assurance of support integrity. The accessible portions of the subject supports will be examined to the frequency and extent specified in IWF-2500-1 and IWF-2510. However, to provide additional assurance of support integrity for each support for which relief is requested, the licensee should, to the extent possible, examine additional similar supports. The Code-required system pressure tests should also be performed.
56 L
Conclusions and Recommendations Based on' the above evaluation, it is concluded that for the supports discussed above, adherence to the Code requirements is impractical.
It is further. concluded that the proposed examina-tions discussed in the above evaluation will provide necessary assurance of structural reliability during this interval. There-
-fore. relief is recommended as requested provided (a) the visual (VT-3) examinations of the supports are performed as if the support boundary extends from the surface of the insulation, (b) the licensee examine an additional similar support, to the extent possible, for each support.for which relief is requested, and (c).the Code-required system pressure tests are performed.
References References 8, 9, and 11.
r i
d f
% Y
~
57 u
_ - =
(
3.6.5 Relief Reouest 151-010. Class 3 Comoonent Sucoorts. Cateaory F-C.
Items F3.10--F3.40 Code Requirement
' Component supports shall be visually examined (VT-3) in
-accordance with /eticle IWF-1300 and Figure IWF-1300-1 during each inspection intern 1.
Component supports telected for examination shall be the-supports of those components that_are required to be examined under IWB, IWC, and IWD during the first inspection interval.
For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
Code Relief Reauest Partial relief is requested from the Code-required visual examination.of the supports listed in Table 7.
TABLE 7.
SUPPORTS REQUIRING RELIEF Suocort No.
Line No.
Code Class CCRR-467 3CC6-71A 3
CCRR-468 3CC6-71A 3
CCRR-469 3CC6-71A 3
CCRR-470 3CC6-71A 3
CCRR-1068 3CC6-71A 3
CCRR-529 3CC6-718 3
4 i.CCRR-530 3CC6-71B 3
CCRR-531 3CC6-71B 3
Proposed Alternative Examination The accessible portions of the affected supports are examined to the frequency and extent specified in IWF-2500-1 and IWF-2510.
58 u
,7 jc
- Licensee's Basis for Reauestina Relief Component support access is partially blocked by fire / heat 1".
resistant-insulation applied to protect supporting structural steel.
The-insulation is applied by spraying Flamastic or Pyrocrate over a wire mesh support. The insulation solidifies into a non-removable mass 'approximately 3 to 5 in. thick.
Fire barrier integrity is a Limiting Condition for Operation as identified in W-3 Technical Specification, paragraph 3.7.11.
This constitutes undue hardship in-conducting examinations. During the construction phase, exami-nations were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes.
Evaluation The subject component supports are partially inaccessible for-m examination due to permanently installed fire / heat resistant insu-lation.
Removal of the insulation material would be a violation of a Limiting Condition for Operation as identified in the Technical Specification, paragraph-3.7.11. The supports were examined during-the construction phase in accordance with the applicable construc-tion codes which provide some assurance of support integrity. -The accessible portions of the subject supports will' be examined to the frequency and extent-specified in IWF-2500-1 and IWF-2510. However, to provide additional assurance of support integrity for each support for which relief is requested, the licensee should, to the extent possible, examine additional simililar' supports. The Code-required system pressure tests should also be performed.
?
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the support discussed above, adherence to the Code requirements is impractical.
It is further concluded that removal of the fire seal
. to enable examination of the supports would be a violation of the
~ lant technical specifications. Therefore, relief is recommended as p
requested provided (a) the Code-required visual examination of the subject l
supports'are performed to the extent possible, (b) the licensee examine an additional similar support, to the extent possible, for each support for which relief is requested, and (c) the Code-required system pressure tests are performed.
References References 8, 9, and 11.
59
._--_______________n
' 3.7 '
REFERENCES 1.
L..V. Maurin (LP&L) to T. M. Novak (NRC), December 22, 1982; augmented inservice inspection program for main steam and feedwater piping and safety injection piping.
2.
L. V. Maurin (LP&L) to H. R. Denton (NRC), April 4,1982; submits general preservice inspection relief requests.
3.
F. J. Drummond (LP&L) to H. R. Denton (NRC), July 25, 1983; preservice inspection relief requests.
4.
K. W. Cook (LP&L) to G. W. Knighton (NRC), February 10, 1984; preservice inspection relief requests.
5.
K. W. Cook (LP&L) to G. W. Knighton (NRC), October 30, 1984; preservice inspection report with inspection program for Class 1, 2, and 3 components included.
6.
K. W. Cook (LP&L) to G. W. Knighton (NRC), March 13, 1985; preservice inspection report with inspection program for supports included.
7.
Safety Evaluation Report, NUREG-0787, Supplement No's. 5 and 6, June 1983 and June 1984, respectively.
8.
K. W. Cook (LP&L) to G. W. Knighton (NRC), May 28, 1985; inservice inspection program, Revision 0.
9.
K. W. Cook (LP&L) to G. W. Knighton (NRC)', November 26, 1985; inservice inspection program, Revision 1.
10.
G. W. Knighton (NRC) to R. S. Leddick (LP&L) December 3, 1985; request for additional information on the Waterford 3 inservice inspectio:1 program.
11.
K. W. Cook (LP&L) to G. W. Knighton (NRC), June 16, 1986; response to request for additional information, inservice inspection program, Revision 2 attached.
60
_---____--________-_-_a
l 10 YEAR INSERVICE INSPECTION PROGRAM Request for Relief No. ISI-001 Rev. 2 Page 1 of 23
(..
Weld / Item Exam Code Partial
)
resignation PT MT UT Category Item Description Comments I
)01-008 X
B-A Bl.11 Core stop lugs at 10', 40*, 85*,
160', 205*, 250*, 280', 325'01-012 X
B-A Bl.11 Material surveillance brackets at l
83', 97*, 104', 263', 277*, 284*
~
03-008 X
B-B B2.31 3/4" instrument nozzles at 21',
Located 7 " from 33', 327*, 339' centerline of weld 03-032 X
B-B B2.31 Partial due to curvature of stay cylinder causing loss of contact.04-008 X
B-B B2.31 3/4" instrument nozzles at 21',
Located 74" from 33', 327*, 339' centerline of weld I
04-024 X
C-A C1.30 6" handholes at O*, 90' Located approx. 9"
.)
Blowdown nozzle at 270' from toe of weld 04-025 X
C-A C1.10 6" handholes at 0*, 90' Located approx. 4" Blowdown nozzle at 270' from toe of weld 04-026 X
C-A C1.10 Two (2) 5" x 5" insulation pads on bottom side of weld obstructing scan 04-027 X
C-A C1.10 Two (2) 5" x 5" insulation pads on top side of weld obstructing scan 04-028 X
C-A C1.20 Two (2) 5" x 5" insulation pads on bottom side of weld obstructing scan 04-029 X
C-A C1.20 Instrument nozzles at 40*, 80*
120', 160', 200*, 240', 280',
Located 6" from 320', 360*
c6nterline of weld 04-030 X
C-A C2.21 Instrument nozzles-at 45*, 90' 135*, 180*, 225', 270*, 315*,
Located 6" from 7
360*
centerline of weld 04-031 X
C-B C2.21 5" x 5" insulation pad below nozzle obstructing scan 04-032 X
B-B B2.31 Partial due to curvature of stay cylinder causing loss of contact.04-033 X
B-B B2.31 0' scan had loss of contact on base metal above weld, 134"-14" and 50"-15" from datum.
Obstructed by I.D. bevel.04-034 X
B-B B2.31 0' scan had loss of contact above weld 1
"-2" and 50"-15" from datum. Obstructed by I.D. bevel.
I y
04-035 X
C-A C1.10 Approximately 5% loss of contact for O' scan due to I.D. cap to tube sheet configuration.04-063 X
C-B
. C2.22 Instrument nozzles at 45*, 90*,
135*, 180', 225', 270', 315',
Located 6" from I
360' centerline of weld 04-064 X
C-B C2.22 5" x 5" insulation pad below
.j nozzle obstructing scan.05-009 X
B-D B3.110 Partial due to (4) Pressurizer Located approx. 9" heater connections from toe of weld l
W340076E g
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.. -.it
r_____.
1 1
ti '
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. 151-001 Page 2 of 23 I
Weld / Item Exam Code Partial Designation PT MT UT Ca te go ry Item Description Comments06-001 X
B-J B9.11 Partial for all 45' and 60* scans due to support lug and radius of nozzle or upstream side of weld and by 0.D. mismatch at weld 06-002 on the downstream side of weld. Adequate root area coverage cannot be obtained when scanning in downstream direction.06-002 X
B-J lb?.11 Partial for all 0*, 45' and 60*
scans due to 0.D. mismatch between nozzle and pipe causing
)
loss of contact.06-006 X
B-F B5.130 Partial for all 45* scans due to slope of nozzle on upstreams side and small amount of shrink-age on downstream side.06-011 X
B-J B9.11 Due to weld contour and bevel, base metal scan cannot be performed on approx. 20% of required area.
0* scan cannot be performed on 10% of required area.
45' scan has a loss of approx. 5% coverage in I
)
the upstream direction, anj 7%
loss in the downstream direction.
Approx. 40% of 60* scan in the upstream direction and 25% in the downstream direction cannot be examined.07-001 X
B-J B9.11 Partial for all 45' scans due to 0.D. mismatch. Scanning on the downstream side of weld is restricted by a 1" nozzle.
The 45' circumferential scans are limited by approx. 15% for the coverage area.07-002 X
B-F B5.130 Partial for 45* circumferential scans due to 0.D. mismatch.
Circumferential scans are limited by about 15% for the J
07-004LB X
B-J B9.12 Partia for6b*axialscansdue to elbow intradese, loss of approx. 15%.07-017 X
B-J B9.11 Partial for all 45* & 60* scans due to 0.D. geomet ry causing loss of contact. Loss of approx.
70% in the upstream direction, j
50% in the downstream direction,
(
and 10% in the circumferential directions.
W340076E
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10 YEAR INSERVICE INSPECTION PROGRAM p ') '
Rev. 2 i
Request for Relief No. ISI-001 L Page 3 of 23 y,
.]
Weld / Item Exam Code Partial i
')
Designation PT MT UT Category Item Description Comments08-001 X
B-J B9.11 0' scan of the base metal and heat-affected zone is totally obstructed by a support lug on j
the downstream side from 36" to
{
75" and loss of contact caused j
i by the radius of the nozzle for j
l..
2" of base metal on the down-
{
stream side for rest of the cir-I cumference. The 45' and 60'
{
scans also have intermittent loss
)
of contact on the downstream side Q.
due to radius of nozzle.08-002 X
B-J B9.11 Only 6" of base metal can be examined using O' on the down-stream side of weld due to a support lug from 36" to 75".
Another lug on the upstream side Q
restricted the O' to only 7" of base metal from 59" to 64" and from 108" to 113".08-008 X
B-J B9.31 Base metal scan on upstream side of weld runs off screen because nozzle is approx. 5" thick.
O'
,.)
scan runs off screen because of radius causing increased metal path and nozzle thickness. 45*
and 60* axial scans are partial due to nozzle radius on both sides of weld.
Y ')
084009
- X B-F B5.130 Partial on all 45* scans due to 0.D. mismatch and slepe of nozzle 08-014 X
B-F B5.130 Partial on all 45' scans due to 0.D. mismatch. Circumferential scans are limited by about 30%
for the coverage area.08-015 X
B-J B9.11 Partial on all 45' scans due to f
0.D. mismatch. Good root area coverage is obtained while scan-j ning in the upstream direction.
Marginal root area coverage is obtained while scanning in i
4 1
downstream direction. Circum-ferential scans are limited by approx. 20% for the coverage area.
2 4
W340076E J
l i
,4.,.'.,
- l'0 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 4 of 23 j.
. Weld / Item.
Exam Code Partial Designation PT NT UT Ca tego ry Item Description Comments09-001 X
B-J B9.11 Partial on all 45* & 60* scans due tc o D. surface geometry.
The rc.) area cannot be examined using 4.2 For 60* scans there is a loss of coverage of approx.
50% in the upstream direction, 70% in the downstream direction, and 10% for the circumferential scans.
09-015LA X
B-J ~ B5712 Partial 60* axial scans due to intermittent loss of contact as
').
a result of elbow intradose.
Loss of approx.15% coverage.09-016 X
B-F B5.130 Partial on all 45* scans due to 0.D. mismatch. Good root area coverage was 6btained for axial scans. Circumferential scans have loss of coverage of approx.
15%.09-017 X
B-J B9.11 Partial on all 45* scans due to 0.D. mismatch, also there is a 1" nozzle on the upstream side.
Good root area coverage is ob-
)
tained with the axial scans. Cir-cumferential scans are-limited by about 15% for the ceverage area.10-001 X
B-J B9.11 All 45' scans are restricted by 0.D. mismatch. Good root area coverage is obtained with the
- )
downstream direction scan. Mar-ginal root area coverage is ob-tained with the upstream direc-tion scan. The circumferential scans are limited by about 20%
for the coverage area.10-002 X
B-F B5.130 All 45' scans restricted by 0.D.
mismatch. Good root area cover-age is obtained with the up-stream direction scan. Marginal root area coverage is obtained with the downstream direction
?)
scan. The circumferential scans are limited by about 30% for the coverage area.
I J
l W340076E k_amm.m...--.-
10 YEAR INSERVICE INSPECTION PROGRAM
.n.
Rev. 2 Request for Relief No. ISI-001 Page 5 of 23 i
Weld / Item Exam Code Partial Designation PT MT UT Cate go ry Item Description Comments "10-007 X
B-J B9.31 0* scan had a partial due to nozzle radius causing loss of contact and increased metal path from 0* (datum) to 60' and 300' to 360'.
Base metal scan had
- ).
partial on the upstream side due to nozzle configuration. Partial in all directions with 45' scans due to nozzle coming off 30" pipe at 60'.
The root was off screen because of radius causing in-c) creased metal path from approx.
0' (datum) to 60' and from 300' to 360*.
Partial for the axial directions only for 60' scans.
i 10-008 X
B-F B5.130 All 45' scans are partial due to 0.D. mismatch and shrinkage on the upstream side of weld, and slope of nozzle on the downstream side of weld. Good root area coverage is obtained.
l 10-012 X
B-J B9.11 'All 45' scans are limited due to l
0.D. mismatch. Loss of coverage
- j is approx. 10% in the upstream direction scan, 5% in the down-stream direction scan, and 10%
for the circumferential direction scans. The upstream direction scan for 60* is obstructed by a i ;
support lug for a loss of 10%
coverage and 0.D. mismatch for a loss of 10% coverage. The down-stream direction 60* scan is obstructed by a lug for a loss of 2% coverage and 0.D. mismatch for a loss of 5% coverage. The circumferential 60' scans are limited due to 0.D. mismatch for a loss of 10% coverage.10-013 X
B-J B9.11 The upstream direction scan and the circumferential scans for 45' JJ and 60' scans are restricted by radius of nozzle, 0.D. mismatch, and a support lug. The upstream direction is totally obstructed by the support lug for a length
~
of 39" for a loss of 34% for 45' J
and 70% for 60'.
The circum--
ferential scans for both angles has a loss of 10%.
l W340076E 2
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 6 of 23
?
Weld / Item Exam Code Partial 3
'Designatica PT MT UT Category Item Description Comments11-001 X
B-J E9.11 All 45' scans are partial due to 0.D. mismatch. The downstream side of weld also has a 1" line attached to pump nozzle. Good root area coverage is obtained
)
with the axial scans. The cir-cumferential scans are limited by about 15% for the ceverage area.11-002 X
B-J E9.11 All 45* scans are partial due to 0.D. mismatch. Good root area
.3 '
coverage is obtained with the axial scans. The circumferential scans were limited by about 15%
for the coverste area.
11-003LB X
B-J B9.12 Partial on 60* axial scant at intersection of weld 11-002 due J-to 0.D. acometry.
l 11-017 X
B-J B9.11 Partial on 45' axial scans due to 0.D. geometry for approx. 10%
i loss of coverage. All 60' scans are partial due to nozzle radius. The downstream direction I J scan has a loss of approx. 70%,
j the upstream direction scan has a loss of 55%, and the circum-ferential scans has a loss of of 10%.12-001 X
B-J B9.11 The upstream 45' and 60' scans are totally obstructed by a support lug for a length of 39" for a loss of 34% for 45* and 75%
for 60'.
The downstream scan for 60' is limited by 0.D. mismatch on weld 12-002 for a 10% loss and by radius of nozzle and support lug for IS%. Good root
. area coverage cannot be obtained using 45*.
Circumferential scans are limited due to radius of
)
nozzle and support lug for a loss J
of 10% coverage for 45' and 15%
l coverage for 60*.
I J
L 6340076E
')
1 g-
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10 YEAR INSERVICE ZNSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 t Page 7 of 23
[
Weld / Item Exam Code Partial Designation PT MT UT Category Item Description Comments12-002 X
S-J B9.11 All 45' scans have approx. 10%
loss of coverage due to int.ermit-tent loss of contr.ct as a result of 0.D. geometry. The 60' up-stream direction scan is partial j
due to radius of nozzle and sup-port lug for a loss of 10% and by 0.D. mismatch for a loss of 5%.
The downstream direction scan is limited by a lug for a 4% loss and 0.D. mismatch for a 5% loss.
c)
The circumferential scans are limited by 0.D. mismatch for a 15% loss.12-008 X
B-J B9.31 The 0* scan is partial due to nozzle radius causing loss of contact and increased metal path
~,
from O' (datum) to 60* and 300*
to 360'.
Partial on upstream side on base metal due to nozzle configuration. All 45' scans are also partial due to nozzle radius. Root area can be scanned in the upstream direction but contact is lost before beam can pass completely through weld.
Contact for circumferential scans can only be maintained on the downstream side of weld. Partial
.y coverage of the heat affected zone and root area is obtained by directing the beam at a tangent to the weld. The down-stream direction 45' scan cannot be performed because the beam is directed away from the weld and heat affected zone. The 60' axial scans are also partial due to nozzle radius.12-009 X
B-F B5.130 Partial on all 45' scans due to slope of nozzle, 0.D, mismatch j
and shrinkage on upstream side of weld. Good root area coverage is obtained.
)
V340076E
')
.30 YEAR INSERVICE INSPECTION PROGRAM 1")*
Rev. 2 Request for Relief No. ISI-001
' Attachment 1 Page 6 of 23 I
Weld / Item Exam Code Partial i
. Designation PT MT UT Cate go ry Item Description Comments12-012 X
B-F B5.130 All 45' scans are restricted by 0.D. sismatch. Good root area coverage is obtained with the downstream direction scan. Mar-ginal root area coverage is obtained with the upstream direction scan. The circum-ferential scans are limited by about 30% for the coverage area.
i 12-013 X
B-J B9.11 All 45' scans are restricted by 0.D. mismatch. Good root area y
coverage is obtained with the upstream direction scan while only marginal root area coverage is obtained with the downstream direction scan. The circum-ferential scans are limited by
.j about 20% for the coverage area.13-001 X
B-J B9.11 The axial scans for 45' and 60*
I are partial due to 0.D.
geometry. The root area can not be examined by 608 13-016 X
E-F B5.130 All 45' scans are partial due
,j to 0.D. sismatch. The circum-ferential scans are limited by approx. 15%.13-017 X
B-J E9.11 All 45' scans are partial due to 0.D. mismatch. Also, the downstream scan was restricted by l 3 a 2" line. The circumferential scans are limited by about 15%.14-001 X
B-J B9.11 All 45* L scans are limited by 0.D. mismatch at the pump-to-safe end weld, and the safe end-to-pump weld. The circumferential scans are limited by about 30%
for the coverage area.14-002 X
B-F B5.130 All 45' L scans are 12mited by 0.D. mismatch at the pipe-to-safe end weld, and the safe end-to-pump weld. The circumferential
.)
scans are limited by about 30%
for the coverage area.14-006 X
B-F B5-130 All 45' scans have a small limit-ation from weld 20-001 and slope of nozzle.14-011 X
B-J B9.11 The 45' and 60' s ans in the up-stream direction are partial due to 0.D. geometry causing loss of contact.
I W340076E Q
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10 YEAR INSERV1CE INSPECITON PROGRAM
.r Rev. 2
-Request for Relief No. ISI-001 Page 9 of 23
, Weld / Item Exam Code Partial i)
Designation'PT HT UT Catego ry Item Description Comments15-008 X
B-F B5.130 The 45' scan in the downstream direction is partial due to slope of nozzle. Good root area coverage is obtained.15-009 X
B-F B5.130 All 45' scans are limited by
~3 weld 16-001. Good root area coverage is obtained.15-015 X
B-J B9.11 The O' scan is partial due to slope of nozzle. The 45' and 60' scans in the upstream and cir-cumferential directions are 3
limited by the 0.D. slope of nozzle at the Steam Generator.
The circumferential scans are limited by approx.10% but has good coverage of the root area with 45'.
The upstream scan is limited by approx. 30%.16-017 X
B-F B5.40 Approx. 10% loss of contact on O' scan due to 0.D. geometry.
Axial scans for 45' are partial due to small amount of shrinkage 360' at toe of weld. Good root area coverage is obtained.
I 17-032 X
B-J B9.11 Partial on 0* scan and upstream and circumferential direction 45' scans due to tee configuration and weld contour.18-018 X
B-J E9.11 Partial on O' scan and downstream
)
and circumferential direction 45' i
scans from 0" (datum) to 75" and 31" to 40" due to tee geometry.
.18-019 X
B-J B9.11 Partial O' scan due to tee body on downstream side of weld and i
weld contour. No 45' scan can be performed in the upstream r,i direction due to tee body.18-020 X
B-J B9.11 Partial 0* scan due to weld con-I tour and valve body on upstream side of weld. No 45' scan can l
be performed in the downstream
)
direction due to valve body.
')
6340076E
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 l Page 10 of 23 l
I
)
Welo/ Item Exam Code Partial Designation PT MT UT Ca tego ry Item Description Comments18-025 X
B-J B9.11 0* scan partial due to tee body configuration on upper half of tee on the downstream side cf weld. Also partial due to weld transition for a total 10% loss of volumetric examination area coverage. The 45' scans in the upstream and circumferential directions are also partial due to this condition. Approx. 25%
)
loss of volumetric examination area coverage.18-059 X
C-F C5.21 Partial on O' scan and 45* cir-cumferential scans due to weld crown. Loss of approx. 10%
coverage 360*.19-006 X
B-J B9.11 Valve on upstream side of weld
~
g causing partial for O' scan and 45' scans in the downstream and circumferential directions.19-026 X
B-J B9.11 Valve on downstream side of weld causes a partial for O' scan and 45' circumferential scans.
No 45' scan can be performed in the upstream direction.19-027 X
B-J B9.11 Valve on upstream side of weld causes a partial for O' scan and 45' circumferential scans. No 45' scan can be performed in the downstream direction.19-055 X
C-F C5.21 Approximately 10% loss of con-tact for O' scan and 45' cir-cumferential scans due to 0.D.
B-J B9.11 Valve on upstream side and 0.D.
weld geometry causes loss of approx. 50% coverage for O' scan and 45' circumferential scans.
No 45' scan can be performed in the downstream diree; ion.
3 20-029 X
B-J E9.11 Valve on downstream side and 0.D.
weld geometry causes loss of approx. 50% coverage for O' scan and 45' circumferential scans.
No 45' scan can be performed in the upstream direction.
l
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3 W340076E
10 YEAR INSERVICE INSPECT 30N PROGRAM
.y Rev. 2 Request for Relief No. ISI-001 Page 11 of 23 Weld / Item Exam Code Partial
-)
Designation PT MT UT Ca te go ry Item Description Comments20-032 X
B-J B9.11 Valve on upstream side of weld causes approx. 10) loss of cover-age 360' for O' scan and approx.
40% loss of coverage 360' for 45' circumferential scans. No 45' scan can be performed in the downstream direction.20-034 X
B-J B9.11 Intermittent loss of contact as a result of 0.D. geometry and tee.
C' scan has loss of approx.
35% coverage of weld area, and
')
25% coverage of base metal. The 45' upstream scan is of obstructed by tee for a loss of approx. 50% ceverage. The 45' circumferential scans have a loss of approx. 35% coverage due to
-)
0.D. weld geometry and tee.20-043 X
B-J B9.11 Approx. 10% loss of coverage 360' on O' scan due to partial loss of contact as a result of 0.D. weld geometry on both sides of weld.20-044 X
B-J B9.11 Approx. 10% loss of coverage 360' on O' scan due to partial loss of contact as a result of 0.D. weld geometry on both sides of weld.20-045 X
B-J B9.11 Approx. 10% loss of coverage 360' on O' scan due to partial loss of contact as a result of 0.D. weld J
geometry on both sides of weld.20-046 X
B-J B9.11 0' scan has partial loss of con-tact with the surface due to 0.D.
weld geometry on both sides of weld. Approx. 10% loss of coverage 360*.20-056 X
B-J B9.11 Valve on upstream side of weld and weld contour causes partial for O' scans and 45% loss of coverage 360* for 45' scans in the circumferential direction.
No 45' scan in the downstream V
direction can be performed.21-066 X
B-J B9.11 Valve on downstream side of weld and weld crown causes approx.
45% loss of coverage for O' scan and 45' circumferential scans.
No 45' scan can be performed in J
the upstream direction.
l l
W340076E
c 10 YEAR INSERVICE INSPECTION PROGRAM
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Rev. 2 Request for Relief No. ISI-001 Page 12 of 23
{
. Weld / Item Exam Code Partial Designation PT MT UT Category Item Description Comments i
21-068 X
B-J B9.11 Valve on upstream side of weld and weld crown causes approx.
i 45% loss of coverage for 0' scan and 45' scans in the downstream and circumferential directions.22-053 X
B-J B9.11 Valve on downstream side of weld I
and weld contour causes approx.
10% loss of coverage 360' for O' scan and approx.10% loss of coverage 360' for 45' circum-ferential scans. No 45' scan i
)
can be performed in the upstream direction.25-021 X
B-J B9.11 Tee on downstream side of weld causes 2% loss of contact with 45' scan when scannieg in upstream direction.25-022 X
B-J B9.11 Tee on upstream side of weld
,d causes approx. 5% loss of contact with 45' scan when scanning in the downstream direction.25-023 X
B-J B9.11 0* scan has approx. 20% loss of contact due to 0.D. weld geometry 360'.
'J l
25-024 X
B-J B9.11 Weld crown causes approx. 10%
loss of contact 360' for O' scan and 45' circumferential scans.25-026 X
B-J E9.11 Approx.-25% loss of contact for 45' scan in the upstream direc-3 tion due to intradose of elbow on downstream side of weld for approx. 90'.25-027 X
B-J B9.11 Approx. 25% loss of contact for 45' scan in the downstream direction due to intradose of elbow on upstream side of weld for approx. 90*.25-028 X
B-J B9.11 Approx. 10% loss of contact for O' scan and 45' scan in the up-stream and circumferential direc-tions due to weld crown and nozzle configuration 360*.25-029 X
B-T B5.40 Approx. 10% loss of contact for O' scan and all 45' scans due to weld crown and nozzle configuration 360'.25-030 X
B-J E9.11 Approx. 2% loss of contact for
.j 45' scan in the upstream direc-tion due to tee branch on down-stream side of weld.
W340076E
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0 30 YEAR INSERVICE INSPECTION PROGRAM H+
Rev. 2 Request for Relief No. ISI-001 Page 13 of 23 Weld / Item Exam Code Partial
- )
Designation PT MT UT Category Item Description Comments26-001 X
B-F B5.40 Approx. 20% loss of contact for 45' scan in the upstream direc-tion due to nozzle configuration 360'.26-006 X
B-F B5.40 Approx. 25% loss of coverage for S
45* and 60' scans in the upstream direction due to nozzle con-figuration 360'.26-009 X
B-J 39.11 Approx. 10% loss of contact at toe of weld 360' for 0* and 45*
scans. 45' axial scans also g
limited due to flange bevel on.
downstream side and weld 26-008 1 " away on upstream side.26-010 X
B-F B5.40 Approx. 25% loss of coverage for 45' and 60* scans in the upstream direction due to nozzle config-
)
uration 360'.41-001 X
C-F C5.21 Approx. 10% loss of coverage for 0* scan due to weld transition 360'.41-002 X
C-F C5.21 Approx. 10% loss of contact for O' sean due to weld crown 360'.41-003 X
C-F C5.21 Approx. 10% loss of contact for 7
O' scan due to weld crown 360'.41-006 X
C-F C5.21 Approx. 10% loss of contact for l
' ~
O' scan due to 0.D. weld geometry 560*.
,,_41-008 X
C-F C5.21 Approx. 10% loss of contact for 9
0' scan due to weld crown 360'.
l 41-010 X
C-F C5.21 Approx. 8% loss of contact for 0' scan due to 0.D. weld geometry 360'.41-011 X
C-f C5.21 Approx. 10% loss of coverage for O' scan due to 0.D. weld
,,3 geometry 360'.41-016 X
C-F C5.21 Approx. 10% loss of coverage for O' scan due to 0.D. weld l
geometry 360'.
l 41-019 X
C-F C5.21 Approx. 10% loss of coverage for O' scan due to weld crown 360*.
g Partial coverage for all 45' scans due to numerous laminations from 62 3/4" to 124 1/4" on up-stream side side of weld.41-020 X
C-F C5.21 Loss of approx. 25% coverage 360' on 45' scan in the upstream j
j direction due to face of penetra-tion on downstream side of weld.
W340076E G
O' 10 YEAR TNSERVZCE INSPECTZON PROGRAM Request for Relief No. ISI-001 Rev. 2 Page 14 of 23
[
Weld / Item Exam Code Partial 3
DesignationPTMTUT Category Item Description Comments41-022 X
C-F C5.21 Approx. 10% loss of coverage for O' and 45' scans due to weld 42-001 transition 360'.
X C-F C5.21 Approx. 10% loss of coverage for O' and all 45* scans due to weld transition 360'.42-005 X
C-F C5.21 Approx. 25% loss of coverage for O' scan and 45' scan in the up-stream direction due to slope of reducer 360'.42-011 X
C-F C5.21 Approx. 10% loss of coverage for j
O' scan and 45' circumferential scans due to weld crown 360'.42-019 X
C-F C5.21 Approx. 10% loss of coverage for O' scan and 45' scans in the up-stream and circumferential directions due to branch connec-
)
C-F C5.21 Approx. 10% loss of coverage for O' scan and all 45* scans due to weld transition 360'.43-001 X
C-F C5.21 Partial due to 2" pipe pprox.
.9" from toe of weld on down-y stream side of weld 180' from datum. This condition causes approx. 15% loss of coverage for 0* scan and limits the 45' up-stream and circumferential scans.43-002 X
C-F C5.21 Approx. 10% loss of contact for j
O' scan due to weld crown 360'.43-004 X
C-F C5.21 Approx.10% loss of coverage for 45* circumferential scans due to pipe schedule change.43-035 X
C-F C5.21 Approx. 10% loss of coverage for O' scan and 45' circumferential scans due to weld contour 360'.43-048 X
C-F C5.21 Approx. 10% loss of contact at toe of weld for O' scan and 45' circumferential scans due to weld contour 360'.43-079 X
C-F C5.21 Approx. 50% loss of contact for j
0* scan and approx. 40% loss of contact for 45' downstream and circumferential scans due to s
bevel on upstream side of weld.43-082 X
C-F C5.21 Approx. 40% loss of coverage 360*
for O' scan and 45' circumfer-ential scans due to valve on downstream side of weld. No 45' scan can be performed in the upstream direction.
W340076E J
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Rev. 2 Request for Relief No. 151-001 Page 15 of 23
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Weld / Item Exam Code Partial J)
Designation PT MT UT Catego ry Item Description Comments43-089 X
N/A N/A Approx. 40% loss of coverage 360' for O' scan and 45' circumfer-ential scans due to valve on downstream side of weld. No 45' scan can be performed in the.
)
upstream direction.44-003 X
C-F C5.21 Appro:;.10% loss of contact at toe of weld for O' scan and 45' circumferential scans due to weld crown 360'.44-005 X
C-F C5.21 Approx.10% loss of contact at
- )
toe of weld for 0* scan and 45' circumferential scans due to weld crown 360'.44-007 X
C-F C5.21 Approx.10% loss of contact at toe of weld for 0* scan and 45' circumferential scans due to weld
.)
erown 360'.44-008 X
C-F C5.21 Approx. 10% loss of contact at toe of weld for O' scan and 45' circumferential scans due to weld crown 360'.
44-01DLA X
C-F C5.22 Partial for 0* and all 45' scans
- ).
due to saddle support beginning at 12" and ending at 18" from datum.
44-C55 LA X
C-F C5.22 Partial for all 45' scans due to
- welded support.75" from center-line of weld.
)44-087 X
C-F C5.21 Approx. 10% loss of coverage at toe of weld for O' scan and 45' circumferential scans due to weld crown 360'.
c 44-089 X
C-F C5.21 Approx. 10% loss of coverage for O' scan and 45' circumferential
.)
scans due to 0.D. weld geometry
?
3608 44-093 X
N/A N/A Approx. 40% loss of coverage for O' scan and 45' circumferential scans due to valve on upstream side of weld. No 45' scan can
()
be performed in the downstream direction.45-002 X
C-F C5.21 Approx. 10% loss of coverage for O' scan and 45' circumferential scans due to weld crown 360*.45-003 X
C-F C5.21 Approx. 20% loss of coverage for all 45' scans due to 0.D.
mismatch.
W340076E J
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10 YEAR INSERVICE INSPECTION PROGRAM Request for Relief No. ISI-001
~
Attachment i Page 16 of 23
{
Weld / Item Exam Code Partial Designation PT MT UT Categorv Item Description Comments45-010 X
C-F C5.21 Approx. 40% loss of coverage for O' scan and 45' circumferential scans due to valve on downstream side of weld. No 45' scan can be performed in the upstream direction.45-019 X
C-F C5.21 Approx. 5% loss of coverage for 45' scan in downstream direction due to 3" branch connection on bottom of pipe.45-023 X
C-F C5.21 Approx. 50% loss of coverage for
)
O' scan and 45' scans in the downstream and circumferential directions due to nozzle radius 360'.
No 45' scan can be per-formed in the upstream direction.46-012 X
C-F C5.21 Approx. 12% loss of coverage for 0* scan and 45' circumferential scans due to 0.D. weld geometry 360'.46-014 X
C-F C5.21 Approx. 10% loss of contact for O' scan due to weld transition 360'.46-015 X
C-F C5.21 Approx. 10% loss of contact for j'
0' scan due to weld transition 360'.46-016 X
C-F C5.21 Approx. 10% loss of contact for O' scan due to weld transition 360*.46-021 X
C-F C5.21 Nozzle radius caused approx. 50%
loss of coverage 360' for O' scan and approx. 75% loss of coverage 360* for 30' RL scans in the downstream and circumferential directions. No O' scan on the downstream side of weld can be performed. No 30' RL scan in the upstream direction can be pe rfo rmed.47-001 X
C-F C5.21 Approx. 10% loss of coverage 360*
for O' scan due to weld crown.47-002 X
C-F C5.21 Approx. 10% loss of coverage 360*
j for O' scan due to weld crown.
1 W340076E
)
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A
10 YEAR INSERVICE INSPECTION PROGRAM 3*
Rev. 2 Request for Relief No. ISI-001 Page 17 of 23 Veld / Item Exam Code Partial
) ~
Designation PT MT UT Cat e go ry Item Description Comments67-005 X
C-F C5.21 Approx. 40% loss of coverage for O' scan due to valve on upstream side, sweepolet on downstream side, and weld crown. Partial for 45' scan in the upstream
_3 direction due to sweepolet.
Partial for 45* circumferential scans due to valve. No 45' scan can be performed in the down-stream direction due to valve.47-007 X
C-F C5.21 Partial for 0* scan due to weld
-)
crown 360' and valve on down-stream side of weld. Partial for 45' circumferential scans due to valve. No 45' scan can be performed in the upstream directica due to valve.47-009 X
C-F C5.21 Partial for O' scan due to veld crown 360' and valve on upstream side of weld. No 45' scan in the downstream direction and partial 45' circumferential scans due to valve.
,)47-034 X
N/A N/A Partial for O' scan due to weld crown 360* and valve on down-stream side of weld. No 45' scan in the upstream direction and partial 45* circumferential scans for a total loss of approx.
40% coverage due to valve.
i 47-036-900 X
C-F C5.21 Approx. 15% loss of coverage for 0* scan due to sweepolet on up-stream side of weld and weld crown. Approx. 5% loss of coverage for 45' scan in the downstream direction due to sweepolet.47-037 X
N/A N/A Approx. 10% loss of coverage for O' scan due to weld crown 360'.48-001 X
C-F C5.21 Partial for 0* scan due to weld transition on downstream side of j
C-F C5.21 Partial coverage for 0* scan due to valve on upstream side of weld. No 45' scan in the down-stream direction and partial 45*
circumferential scans for a total J
loss of 40% coverage due to valve.
U340076E
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 18 of 23 r
L(.
Weld / Item Exam Code Partial L
D=eignation PT MT UT Category Item Description Comments48-007 X
C-1 C5.21 Approx. 30% loss of coverage 360* due to valve on downstream j
side of weld. No 45' scan in the upstream direction and partial 45* circumferential scans for a total loss of 40% coverage due to valve.48-009 X
C-F C5.21 Partial for O' scan due to weld contour 360* and valve on up-stream side of weld. No 45' scan in the downstream direction and 3
partial 45' circumferential scans for a total loss of 40% coverage i
due to valve.
I 48-035 X
C-F C5.21 Approx. 10% loss of coverage for O' scan and 45' circumferential scans due to weld crown 360'.48-036 X
N/A N/A Partial for 0* scan due to weld crown and valve on dovnstream side of weld. No 45' scan in the upstream direction and partial 45' circumferential scans for a total of 40% loss of cover-J-
age 360' on downstream side of weld.48-037 X
N/A N/A Approx 10% loss of coverage 360' for O' sean due to weld crown.50-072 X
C-F C5.11 Partial due to welded support limiting accessibility; area J
approx. 26" thru 33" from datum.51-004 X
C-F C5.21 Partial for 0* scan and 45' cir-cumferential scans due to tee configuration on downstream side of weld. No 45' scan can be performed in the upstream J
direction due to tee.51-009 X
C-F C5.21 Partial for O' scan and 45' cir-cumferential scans due to tee configu. ration on upstream side of weld. No 45' scan can be performed in the downstream kJ direction due to tee.51-010 X
C-F C5.21 Partial due to 6 welded lugs on upstream side of weld, 3/4" from weld, 2 k" wide. Approx. 5% of O' scan of weld and HAZ, and 20%
of O' scan of base metal not
~
covered. Also, approx. 70% of area in front of lugs cannot be covered with the 45' scan in the downstream direction.
W340076E
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10 YEAR INSERVICE INSPECT 10N PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 19 of 23 Weld / Item Exam Code Partial
'}
Designation PT MT UT Ca tego ry Item Description Comments51-013 X
C-F C5.21 Approx. 10% loss of coverage 360' for O' scan due to weld transition.
51-014-900 X
C-F C5.21 Approx. 15% loss of contact 360*
for O' scan due to weld toe.
51-016-900 X
C-F C5.21 Approx.10% loss of contact for O' scan due to weld transition.
Also, loss of back reflection for O' scan and partial for 45' scan in the downstream direction due L3 to slope from penetration on up-stream side of weld beginning approx. 1" from toe.51-017 X
C-F C5.21 Approx.10% loss of coverage for O' sean due to weld transition.
51-018-900 X
C-F C5.21 Valve on downstream side of weld causes partial for O' scan and J
45' circumferential scans. No 45' scan can be performed in the upstream direction due to valve.
51-WS-4 X
C-C C3.20 Partial exam due to bleedout caused by carbon steel shim s.).
positioned flush with support lug.52-004 X
C-F C5.21 Partial for 0* scan and 45' circumferential scans due to tee configuration on downstream side of weld. No 45' scan can be
'J performed in the upstream direction due to tee.52-009 X
C-F C5.21 Approx. 10% loss of contact due to weld transition for O' scan.
Also, partial for O' scan and 45' circumferential scans due to J
tee configuration on upstream side of weld. No 45' scan can be performed in the downstream direction due to tee.52-010 X
C-F C5.21 Approx. 10% loss of contact for O' scan due to weld transition.
i3 52-015-900 X
C-F C5.21 Approx. 25% loss of coverage for 0* scan due to weld toe.
52-017-900 X
C-F C5.21 Partial for 0* scan and 45* scan in the downstream direction due to penetration bevel on upstream side of weld,1" from toe of weld 2
52-018 X
C-F C5.21 Approx. 10% loss of coverage for 45* circumferential scans due to loss of contact at toe of weld 360'.
W340076E g
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10 YEAR INSERV3CE ZNSPECTION PROGRAM Request for Relief No, ISI-001 Rev. 2 Page 20 of 23
. g.-
Weld / Item Exam Code Partial Y
Designation PT MT UT Ca tego ry Item Description Comments 52-019-900 X
C-F C5.21 Valve on downstream side of weld causes partial for O' scan and 45' circumferential scans. No 45' scan can be performed in i
the upstream direction due to j
valve.54-074 X
C-A C1.10 Partial for O' and all 45' scans due to flange radius and weld contour.54-075 X
C-A-C1.'30 Partial for O' and all 45' scans due to flange radius and weld I
61 Contour.55-040 X
C-F~
C5.11 Valve on upstream side of weld, 1" drain line at-bottom of pipe on downstream side of weld, reducer configuration 360', and loss of contact at toe of weld J
i 360' causes partial for O' scan and 45' scans in the upstream and circumferential directions.
No 45* scan can be performed in the downstream direction due to valve.
C).
,55-042 X
C-F C5.21 Partial for O' scan and 45' scan in downstream direction due to 1" drain line at bottom of pipe on upstream side of weld.
45' scan in downstream direction was also limited by 0.D. weld taper.
- )55-043 X
C-F C5.21 Partial for O' scan and 45' scan in the upstream direction due to 0.D. taper on downstream side of weld.
l 55-050 X
C-F C5.21 Partial for O' scan due to weld transition causing loss of contact.
f5-051 X
C-F C5.21 Valve on downstream side of weld causing partial for O' scan and 45' circumferential scans. No 45' scan can be performed in the upstream direction due to J
valve.55-068 X
C-F C5.11 Valve on upstream side of weld, reducer configuration 360*, and loss of contact at toe of weld 360' causes partial for 0* scan
~
and 45' scans in the upstream and circumferential directions.
No 45* scan can be performed in the downstream direction due to valve.
W340076E
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10 YEAR INSERVZCE INSPECTZON PROGRAM
'Y 3
Rev. 2
{
Request for Relief No. ISI-001
' Page 21 of 23 Weld / Item j
Exam Code Partial 3
Designation PT MT UT Category Item Description Coenents55-070 X
C-F C5.21 Partial for O' scan and 45* scan i
in downstream direction due to 1" drain line at bottom of pipe on upstream side of weld.
45' i
scan in downstream direction is also limited by 0.D. weld taper.55-075 X
C-F C5.21 Partial for 0* scan and 45* scan in the upstream direction due to 0.D. taper on downstream side of weld.55-077 X
C-F C5.21 Partial for O' scan due to weld g
transition causing loss of contact.55-078 X
C-F C5.21 Valve on downstream side of weld causes partial for O' scan and 45* circumferential scans. No 45' scan can be performed in the g
upstream direction due to valve.56-040
' X C-F C5.11 Valve on upstream side of weld, 1" drain line at bottom of pipe on downstream side of weld, re-ducer configuration 360*, and loss of contact at toe of weld
,)
360* causes partial for O' scan and 45' scans in the upstream and circumferential directions.
No 45' scan can be performed in the downstream direction due to valve.
)56-042 X
C-F C5.21 1" drain line at bottom of pipe on upstream side of weld causes partial for 0* scan. All 45' scans are partial due to drain j
line and reducer on upstream side of weld, and weld crown 360'.56-047 X
C-F C5.21 Approx. 10% loss of contact for O' scan due to weld transit 5.
No 45' scan can be performed in the upstream direction due to penetration on downstream side of weld.
l 3
56-049 X
C-F C5.21 Approx. 10% loss of contact for O' scan due to 0.D. weld geometry.56-050 X
C-F C5.21 Valve on downstream side of weld causes partial for O' scan and 45' circumferential directions.
.)
Nc 45' scan can be performed in I
the upstream direction due to valve.
W340076E 3
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 22 of 23 i
Weld / Item Exam Code Partial Y
Designation PT MT UT Cate go ry Item Description Comments56-070 X
C-F C5.11 Valve on upstream side of weld, 1" drain line at bottom of pipe on downstream side of weld, re-ducer configuration 360', and loss of contact at toe of weld 360' causes partial for O' scan and 45' scans in the upstream and circumferential directions.
No 45' scan can be performed in the downstream direction due to valve.
J 56-072 X
C-F C5.21 1" drain line at bottom of pipe and reducer on upstream side of weld causes partial for 0* scan and 45' scan in the downstream direction.56-077 X
C-F C5.21 Partial on 0* scan and 45' in the J
upstream direction due to pene-tration on downstream side of weld.56-080 X
C-F C5.21 Valve on downstream side of weld and weld crown causes partial for O' scan and 45' scans in the J
downstream and circumferential directions. No 45' scan can be performed in the upstream direction due to valve.61-041 X
C-F C5.11 Approx. 10% loss of contact at J -
45' circumferential scans.
toe of weld 360* for O' scan and 61-042 X
C-F C5.11 Approx.10% loss of contact at toe of weld 360* for 0* scan and 45' circumferential scans.61-046 X
C-F C5.11 Approx. 5% loss of contact at toe of weld 360' for 0* scan.
J 61-047 X
C-F C5.11 Approx. 5% loss of contact at toe of weld 360' for O' scan.61-051 X
C-F C5.11 Approx. 30% loss of contact for O' scan and 45' circumferential scans due to tee configuration i
on upstream side of weld. No 45' l ;J scan can be performed in down-stream direction due to tee.61-071 X
C-F C5.11 Approx. 40% loss of coverage for O' scan and all 45' scans due to ell-to-flange weld configuration 360*.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 2 Request for Relief No. ISI-001 Page 23 of 23
./
,)
Weld / Item Exam Code Partial Designation PT MT UT Cate go ry Item Description Comments61-073 X
C-F C5.11 Approx. 5% loss of coverage for O' scan and 45' circumferential scans due to tee and weld con-figuration. No 45u scan can be performed in the downstream direction due to tee on upstream side of weld.61-080 X
C-F C5.11 Approx. 5% loss of contact at toe of weld 360* for O' scan.
Approx. 5% loss of coverage for 45' circumferential scans due to
- )
weld configuration and tee on upstream side of weld. No 45' scan can be performed in the downstream direction due to tee.62-047 X
C-F C5.11 Tee on upstream side of weld causes partial for O' scan. No j
, 45* scan can be performed in the downstream direction due to tee.62-075 X
C-F C5.11 Tee on upstream side of weld causes partial for O' scan and 45' circumferential scans. No 455 scan can be performed in downstream direction due to tee.
62-CiB X
C-F C5.11 Valve on downstream side of weld and weld crown causes approx.
30% loss of contact at toe and on surface of weld for O' scan, and approx. 30% loss of coverage
- j
.g for 45' circumferential scans.
1 l
No 45' scan can be performed in the upstream direction due to valve.62-089 X
C-F C5.11 Flange on downstream side of weld causes partial for O' scan and 45' circumferential scans. No 45' scan can be performed in the J
upstream direction due to flange.
l 62-094 X
C-F C5.11 Partial for O' scan due to 1" line on downstream side of weld.62-098 X
C-F C5.11 Partial on O' scan and approx.
y 30% loss of contact for 45' scans in the downstream and circum-ferential directions due to tee on upstream side of weld.
J t
e up W340076E
l i
APPENDIX A Requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Code,
-1980 Edition with Addenda through Winter 1981 A.1 CLASS 1 REQUIREMENTS A. l.1 CATEGORY B-A, PRESSURE-RETAINING WELDS IN REACTOR VESSEL A.1.1.1 Shell Welds;-Item B1.10 A. l.l.l.1 Circumferential and Longitudinal Welds, Items 81.11 and Bl.12 All pressure-retaining circunferential and longitudinal shell welds in the reactor vessel shall be volumetrically examined in accordance with Figures IWB-2500-1 and -2 over essentially 100% of their lengths during the first inspection interval. Examinations may be performed at or near the end of the interval.
A. l.l. 2 Head Welds, Item B1.20 A.1.1. 2.1 Circumferential and Meridional Head Welds, Items Bl.21 and Bl.22 All pressure-retaining circunferential and meridional head welds in the reactor vessel head shall be volumetrically examined in accordance with Figure IWB-2500-3 over the accessible portion up to 100% of the weld length during the first inspection interval. The bottom head welds may be examined at or near the end of the interval.
A.1.1. 3 Shell-to-Fianoe Weld, Item Bl.30 Essentially 100% of the length of the shell-to-flange weld shall be volumetrically examined in accordance with Figure IWB-2500-4 during the first inspection interval.
If partial. examinations are conducted from the flange face, the remaining examination required to be conducted from the vessel wall may be performeci at or near the end of each inspection in terval. The examination of the shell-to-flange weld may be performed during the first and third inspection periods in conjunction with the nozzle examinations of Examination Category B-D (Program B).
At least 50%
of shell-to-flange weld shall bq examined by the end of the first inspection period, and the remainder by the end of the third inspection per iod.
l i
A-1 l
n'
A.l.l.4 Head-to-Flange Weld, Item Bl.40 Essentially 100% of the length of the head-to-flange weld shall be volumetrically examined in accordance with Figure IW8-2500-5 during the first inspection interval.
If partial examinations are conducted from the flange face, the remaining examination required to be conducted from the vessel wall may be performed at or near the end of each inspection interval.
A.1.1.5 Repair Welds, Item Bl.50 A.1.1.5.1 Repair Welds in the Beltline Region, Item Bl.51 All base metal weld repair areas in the beltline region where rep 6ir depth exceeds 10% nominal of the vessel wall shall be volumetrically examined in accordance with Figures IWB-2500-1 and -2 during the first inspection interval. Examinations may be performed at or near the end of the interval. The beltline region extends for the length of the vessel thermal shield, or in the absence of a thermal shield, the effective length of reactor fuel elements.
If the location of the repair is not positively and accurately known, then the individual shell plate, forging, or shell course containing the repair shall be included.
A.l.2 CATEGORY B-B, PRESSURE-RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS A. l.2.1 Shell-to-Head Welds in the Pressurizer, Item B2.10 A.1 s 2.1.1 Circumferential Snell-to-Head Welds, Itsa B2.11 All circumferential shell-to-head welds in the pressurizer as shown in Figure IWB-2500-20(a) shall be volumetrically examined in accordance with Figure IWB-2500-1 over essentially 100% of their length during the first inspection interval.
A.1.2.1.2 Longitudinal Shell Weld, Item B2.12
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One foot of. all longitudinal shell welds in the pressurizer inter-i secting the examined circumferential shell-to-head weld as shown in Figure IWB-2500-20(a) shall be volumetrically examined in accordance with Figure IWB-2500-2 during the first inspection interval.
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A.1. 2. 2 Head Welds in Pressurizer Vessels, Item B2.20 A.l.2.2.1 Circumferential and Meridional Head Welds, Items B2.21 and B2.22 All circumferential and meridional head welds in the pressurizer shall be volumetrically examined in accordance with Figure WS-2500-3 over essen-tially 100% of their lengths during the first inspection interval.
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A. l.2. 3 Head Welds-in the Primary Side of the Steam Generators, Item B2;30 A.1.2.3.1 Circumferential and Meridional Head Welds, Items 82.31 and B2.32 All.circunferential and meridional head welds in the primary side of the steam generators as shown in Figure IWB-2500-20(c) shall be volu-l metrically examined in accordance with Figure IWB-2500-3 over essentially 100% of their length during the first inspection interval.
A. l. 2. 4 Tubesheet-to-Head Weld; Item B2;40 The tubesheet-to-head weld in the primary side of the steam generatcrs shall be volumetrically examined in accordance with Figure IWB-2500-6 over.
essentially 100% of its length during the first inspection interval.
A.1. 2. 5 Head Welds in-the Primary Side of the Heat Exchangers; Item B2.50 A.1. 2. 5.1 Circumferential Welds, Items B2.51 and B2.52 All circunferential and meridional head welds in the primary side of the heat exchangers as shown in Figure IWB-2500-20(e) shall be volumet-rically examined in accordance with Figures IWB-2500-1 and -3 for circumferential welds and Figure IWB-2500-3 for meridional welds over essentially 100% of their length during the first inspection interval.
A.1 2.5.2 Longitudinal Welds, Item B2.53 One foot of. all longitudinal welds in the primary side of the heat exchangers intersecting the examined circumferential tubesheet-to-shell
. weld as shown in Figure IWB-2500-20(g) shall be volumetrically examined in accordance with Figure IWB-2500-2 during the first inspection interval.
A.1.2.6 Tubesheet-to-Shell-(or Head) Welds; Items B2.60 and-B2.61 The tubesheet-to-shell (or head) welds as shown in Figures IWB-2500-20(e) and IWB-2500-20(g) shall be volumetrically examined in accordance i
with Figure IWB-2500-6 over essentially 100% of their ler>gth during the first interval.
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p A.l.3 CATEGORY B-D, FULL PENETRATION WELDS OF N0ZZLES IN VESSELS (INSPECTIONPROGRAMB)
A.I.3.1 Reactor Vessel Nozzle-to-Vessel Welds, Items B3.90 and B3.100 All nozzle-to-vessel welds and inside radius sections in th's reactor i
vessel shall be volumetrically examin(! in accordance with Figures IWB-l 2500-7(a) through (d) during the first interval of operation. Examinations shall include nozzles with full penetration welds to vessel shell (or head) and integrally cast nozzles, but exclude manways and handholes either weided to or integrally cast in vessel. At least 25% but not more than 50%
(credited) of the nozzles shall be examined by the end of the first inspec-tion period and the remainder by the end of the inspection interval.
If examinations are ' conducted from inside the component and the nozzle weld is examined by straight beam ultrasonic method from the nozzle bore, the remar..ing examinations required to be conducted from the shell may be performed at or near the end of each inspection interval.
A.I.3.2 Pressurizer Nozzle-to-Vessel Welds, Items B3.110 ana B3.120 All nozzle-to-vessel welds and inside radius sections in the pressurizer shall be volumetrically examined in accordance with Figures IWB-2500-7(a) through (d) during the first interval of operation. Exami-nations shall include nozzles with full penetration welds to vessel shell (or head) and integrally cast nozzles, but excludes manways and handnoles either welded to or integrally cast in vessel. At least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval.
A.l.3.3 Steam Generator Nozzle-to-Vessel Welds, Items B3.130 and B3.140 All nozzle-to-vessel welds and inside radius sections in the primary side of the steam generator shall be volumetrically examined in accordance with Figures IWB-2500-7(a) through (d) during the first interval of operation. Examinations shall include nozzles with full penetration welds to vessel shell (or head) and integrnlly cast nozzles, but excludes manways and handholes either welded to or integrally cast in vessel. At least 25%
but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval.
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A. l. 3. 4 Hect Exchanger Nozzle-to-Vessel Welds, Items B3.150' and B3.160, All nozzle-to-vessel welds and inside radius sections in the primary side of the heat exchanger shall be volumetrically examined in accordance with Figures IWB-2500-7(a) through (d) during tne first interval of operation. Examinations shall include nozzles with full penetration welds to. vessel shell (or head) and integrally cast nozzles, but excludes manways and handholes either welded to or integrally cast in vessel. At least 25%
but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval.
A.1.4 CATEGORY B-E, PRESSURE-RETAINING PARTIAL PENETRATION WELDS IN VESSEL 5 A.l.4.1 Reactor Vessel Partial Penetration Welds, Item B4.10 A.l.4.1.1 Vessel Nozzles, Item B4.ll The external surfaces of partial penetration welds on 25% of reactor vessel nozzles shall be visually examined (VT-2) during the first inspec-tion interval. The examinations shall cumulatively cover the specified percentage among each group of penetrations of comparable size and function.
A.l.4.1.2 Control Rod Drive Nozzles, Item B4.12 The external surfaces of partial penetration welds on 25% of the control rod drive nozzles shall be visually examined (VT-2) during the first inspection interval. The examinations shall cumulatively cover the specified percentage among each group of penetrations of comparable size and function.
A. l. 4.1. 3 Instrumentation Nozzles, Item B4.13 The external surfaces of partial penetration welds on 25% of the instrumentation nozzles shall be visually examined (VT-2) during the first l
inspection interval. The examinations shall cumulatively cover the specified percentage among each group of penetrations of comparable size l
and function.
A.1.4. 2 Heater Penetration Welds on the Pressurizer, Item B4.20 The external surfaces of 25% of the heater penetration welds on the pressurizer shall be visually examined (VT-2) during the first inspection interval. The examinations shall cumulatively cover the specified per-centage among each group of penetrations of comparable size and function.
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A.l.5 CATEGORY B-F, PRESSURE-RETAINING DISSIMILAR METAL WELDS A.1.5.1 Reactor Yessel-Nozzle-to-Safe End Butt Welds, Item B5.10 All nozzle-to-safe end butt welds in nominal pipe size 4 in, and greater in the reactor vessel shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval.
The examinations may be performed coincident with the vessel nozzle exami-nations required by Examination Category B-D.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steels, (b) carbon or low alloy steels to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5. 2 Reactor Vessel Nozzle-to-Safe End Butt Welds, Item 85.20 The surfaces of all nozzle-to-safe end butt welds in nominal pipe size less than 4 in. in the reactor vessel shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. The examinations may be performed coincident with the vessel nozzle examinations required by Examination Category B-D.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steels, (b) carbon or low alloy steels to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.l.5.3 Reactor Vessel Nozzle-to-Safe End Socket Welds, Item B5.30 1
The surfaces of all nozzle-to-safe end socket welds in the reactor vessel shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. The examinations may be performed coincident with tne vessel nozzle examinations required by Examination Category B-D.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steels, (b) carbon or low alloy steels to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.4 Pressurizer Nozzle-to-Safe End Butt Welds, Item B5.40 All nozzle-to-safe end butt welGs in nominal pipe size 4 in, and greater in the pressurizer shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval.
Dissimilar metal' welds between combinations of (a) carbon or low alloy steels to high: alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.5 Pressurizer Nozzle-to-Safe End Butt Welds, Item B5.50 The surfaces of all nozzle-to-safe end butt welds in nominal pipe size less than 4 in. in the pressurizer shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal A-6
welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.6 Pressurizer Nozzle-to-Safe End Socket Welds, Item B5.60 The surfaces of all nozzle-to-safe end socket welds in the pressurizer
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shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.7 Steam Generator Nozzle-to-Safe End Butt Welds, Item B5.70 All nozzle-to-safe end butt welds in nominal pipe size 4 in, and greater the steam generator shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.8 Steam Generator Nozzle-to-Safe End Butt Welds, Item B5.80 The surfaces of all nozzle-to-safe end butt welds in nominal pipe size less than 4 in, in the steam generator shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.9 Steam Generator Nozzle-to-Safe End Socket Welds, Item B5.90 The surfaces of all nczzle-to-safe end socket welds in the steam generator shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.-
i A.1.5.10 Heat Exchanger Nozzle-to-Safe End Butt Welds, Item B5.100 l
All nozzle-to-safe end butt welds in nominal pipe size 4 in, and greater the heat exchangers shall be surface and volumetrically examined I
in accordance with Figure IWB-2500-8 during the first inspection interval.
Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
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A.l.5.ll Heat Exchanger Nozzle-to-Safe End Butt Welds, Item 85.110 All nozzle-to-safe end butt welds in nominal pipe size less than 4 in'.
in the heat exchangers shall be surface and volumetrically examined in ac-cordance with Figure IWB-2500-8 during the first inspection interval. Dis-similar metal welds between combinations of (a) carbon or low alloy steels to high alloy st' eel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.l.5.12 Heat Exchanger Nozzle-to-Safe End Socket Welds, Item B5.120 All nozzle-to-safe end socket welris in the heat exchangers shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 l
during the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) i carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.l.5.13 Piping Safe End Butt Welds, Item B5.130 All dissimilar metal safe end butt welds in piping 4 in, and greater shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, i
I (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.l.5.14 Piping Safe End Butt Welds, Item B5.140 All dissimilar metal safe end butt welds in piping less than 4 in.
shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 duririg the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.
A.1.5.15 Piping Safe End Socket Welds, Item B5.150 All dissimilar metal safe end socket welds in piping shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between combinations of steel to high nic.kel alloys, and (c)gh alloy steel, (b) carbon or low alloy (a) carbon or low alloy steels to hi high alloy steel to high nickel alloys are included.
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.A.1.6 CATEGORY B-G-1, PRESSURE-RETAINING BOLTING LARGER ThAN 2 INCHES IN DIAMETER A. l.6.1 Reactor Closure Head Nuts, Item B6.10 The surfaces of all reactor closure head nuts larger than 2 in. in diameter shall be examined during the first inspection interval.
Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval.
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A. l.6. 2 Reactor Closure Studs, in Place, Items B6.20 and B6.30 l
All closure studs in the reactor vessel larger than 2 in. in diameter shall be volumetrically examined in accordance with Figure IWB-2500-12 during the first inspection interval. A surface examination is also required when the studs are removed. Examinations may be performed at or near the end of the inspection interval.
A.l.6.3 Threads in the Flange in the Reactor Vessel, Item B6.40 l
All threads in the flange in the reactor vessel shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Examination includes threads in base metal and is required only when the connection is disassembled. Examinations may be performed at or near the end of the inspection interval.
A.1.6.4 Reactor Closure Washers and Bushings, Item B6.50 The surfaces of all closure washers and bushings on bolting larger than 2 in. in diameter in the reactor vessel shall be visually examined (VT-1) during the first inspection interval.
Bushings in base material of flanges are required to be examined only when the connections are disassembled; bushings may be examined in place. The examinations may be performed at or near the end of the inspection interval.
l A.1.6.5 Pressurizer Bolts, Studs, and Flange Surfaces, Items 86.60 and 56.70 All bolts' and studs larger than 2 in. in diameter in the pressurizer shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Bolting may be examined (a) in place under ten-sion, (b) when the connection is disassembled, or (c) when the bolting is removed. The flange surfaces shall also be visually examined (VT-1) when the connection is disassembled. The examination includes 1 in. of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval.
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A.l.6.6 Pressurizer Nuts, Bushings, and Washers, Item B6.80 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter shall be visually examined (VT-1) during the first in-spection intervala Bushings in the base material of flanges are required to be examined only when the connections are disassembled; bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
Examinations may be performed at or near the end of the inspection interval.
A.1.6.7,Bol ts, Studs, and Flange Surf aces in Steam Generators, Items 86.90 ano B6.100 All bolts and studs larger than 2 in. in diameter in steam generators shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Bolting may be examined (a) in n::ce under tension, (b) when the connection is disassembled, or (c) e.. the bolting is removed. The flange surfaces shall also be visually exnined (VT-1) when the connection is disassembled. The examination includes 1 in. of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval.
A.1 6.8 Nuts, Bushings, and Washers in Steam Generators, Item B5.110 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter in steam generators shall be visually examined (VT-1) during the first inspection interval. Bushings in the base material of flanges are required to be examined only when the connections are dis-assembled; bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval.
A.1.6.9 Bolts. Studs, and Flange Surfaces in Heat Exchangers, Items B6.120 ano B6.130 All bolts and studs larger than 2 in. in diameter in heat exchangers shall b? volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. The flange surfaces shall also be visually examined (VT-1) when the connection is disassembled. The examination includes 1 in. of l
the annular surface surrounding each stud. Examinations may be performed I
at or near the end of the inspection interval.
Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.
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A.l.6.10 Nuts, Bushings, and Washers in Heat Exchangers, Item B6.140 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter in heat exchangers shall be visually examined (VT-1) during the first inspection interval. Bushings in the base material of flanges are required to be examined only when the connections are dis-assembled; bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval.
Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-8, B-J, B-L-1, znd B-M-1, as applicable.
A.1.6.ll Bolts, Studs, and Flange Surfaces in Piping, Items B6.150 and Bo. loo All bolts and studs larger than 2 in. in diameter in piping shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval.
Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is re-moved. The flange surfaces shall also be visually examined (VT-1) when the connection is disassembled. The examination includes 1 in. of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval.
Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-8, B-J, B-L-1, and B-M-1, as applicable.
A.l.6.12 Nuts, Bushings, and Washers in Piping, Item B6.170 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter in piping shall be visually examined (VT-1) during the first inspection interval. Bushings in the base material of flanges are required to be examined only when the connections are disassembled; bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval.
Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B B-J, B-L-1, and B-M-1, as applicable.
A.l.6.13 Bolts, Studs, and Flange Surfaces in Pumps, Items B6.180 and B6.190 All bolts and studs larger than 2 in. in diameter in pumps shall be volumetrically examined in accordance with IWB-2500-12 during the first
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inspection interval.
Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is re-moved. The flange surfaces shall also be visually examined (VT-1) when the connection is disassembled. The examination includes 1 in. of the annular surface surrounding each stud.
Examinations may be performed at or near A-11 n
the.end of the inspection interval. Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.
A.l.6.14 Nuts, Bushings, and Washers in Pumps, Item B6.200 The surfaces of all nuts, bushings, and washers in boltin 2 in. in diameter in pumps shall be visually examined (VT-1) g larger than during the first inspection interval.
Bushings in the base material of flanges are required to be examined only when the connections are disassembled; bushings may be inspected in place.
Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
Examinations may be performed at or near the end of the inspection interval. Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.
A.l.6.15 Bolts, Studs, and Flange Surfaces in Valves, Items B6.210 and B6.220 All bolts and studs larger than 2 in. in diameter in valves shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is re-moved. The flange surfaces shall also be visually examined (VT-1) when the connection is disassembled. The examination includes 1 in. of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval.
Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.
A.l.6.16 Nuts, Bushings, and Washers in Valves, Item B6.230 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter in valves shall be visually examined (VT-1) during the first inspection interval. Bushings in the base material of flanges are required to be examined only when the connections are disassembled, but bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval. Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.
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A.l.7 CATEGORY B-G-2, PRESSURE-RETAINING BOLTING 2 INCHES AND SMALLER IN DIAMETER 1
A.l.7.1 Bolts, Studs, and Nuts in Reactor Vessel, Item B7.10 The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in the reactor vessel shall be visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
A.l.7.2 Bolts, Studs, and Nuts in Pressurizer, Item B7.20 The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in the pressurizer shall be visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension,
'(b) when the connection is disassembled, or (c) when the bolting is removed.
A.l.7.3 Bolts, Studs, and Nuts in Steam Generators, Item B7.30 The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in the steam generators shall be visually examined (VT-1) during the first inspection interval.
Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is rem 0ved.
A.l.7.4 Bolts, Studs, and Nuts in Heat Exchangers, Item B7.40 The surfaces of all bolts, studs, and nuts 2 in, or less in diameter in the heat exchangers shall be visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
A.l.7.5 Bolts, Studs, and Nuts in Piping, Item B7.50 The surfaces of all bolts, studs, and nuts 2 in, or less in diameter in piping shall be visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
A.l.7.6 Bolts, Studs, and Nuts in Pumps, Item B7.60 The surfaces of all bolts, studs, and nuts al. or less in diameter in pumps shall be visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
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A.l.7.7 Bolts, Studs, and Nuts in Valves, Item B7.70 The surfaces of all bolts, studs, and nuts 2 in, or less in diameter in valves shall be visually examined (VT-1) during the first inspection inter-val. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.
A.l.7.8 Bolts, Studs, and Nuts in Control Rod Drive Housings, Item B7.80 The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in control rod drive housings shall be visually examined (VT-1) during the first inspection interval when disassembled.
A.l.8 CATEGORY B-H, VESSEL SUPPORTS A.l.8.1 Integrally Welded Attachments in Reactor Vessel, Item B8.10 The attachment weld joining the reactor vessel support to the pressure-retaining membrane of the reactor vessel where the support base material design thickness is 5/8 in or greater shall be surface or volumetrically examined, as applicable, in accordance with Figures IWB-2500-13, -14, and
-15 during the first inspection interval. Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100%
of the length of the weld to the reactor vessel and the integral attachment weld to a cast or forged integral attachment to the reactor vessel, as applicable. One hundred percent of the welding of each lug on the vessel is included in the examination.
A.l.8.2 Integrally Welded Attachments in Pressurizer, Item B8.20 The attachment weld joining the pressurizer vessel support to the pressure-retaining membrane of the reactor vessel where the support base material design thickness is 5/8 in. or greater shall be surface or volu-metrically examined, as applicable, in accordance with Figures IWB-2500-13,
-14, and -15 during the first inspection interval. Wald buildups os nozzles that serve as supports are excluded. The examination includes essentially 100% of the length of the weld to the pressurizer and the integral attachment weld to a cast or forged integral attachment to the pressurizer, as applicable. One hundred percent of the welding of each lug on the vessel is included in the examination.
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4 A.l.8.3 Inteorally Welded Attachments in $ team Gsnsrators, Item B8.30 The attachment weld joining the steam generator support to the pressure-retaining membrane of the generator where the support base material design thickness is 5/8 in. or greater shall be surface or volumetrically examined, as applicable, in accordance with Figures IWB-2500-13, -14, and -15 during the first inspection interval. Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100% of the length of the weld to the steam generatu and the integral attachment weld to a cast or forged integral attachment to the steam generator, as applicable. One hundred percent of the welding of each lug on the vessel is included in the examination. The examination is limited to the attachment weld on one steam generator.
A.l.8.4 Integrally Welded-Attachments in Heat Exchangers, Item B8.40 The attachment weld joining the heat exchanger support to the pressure-retaining membrane of the heat exchanger where the support base material design thickness is 5/8 in. or greater shall be surface or volumetrically examined, as applicable, in accordance with Figures IWB-2500-13, -14, and
-15 during the first inspection interval. Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100%
of the length of the weld to the heat exchanger and the integral attachment weld to a cast or forged integral attachment to the heat exchanger, as applicable. One hundred percent of the welding of each lug on the heat exchanger is included in the examination. The examination is limited to the attachment weld on one heat exchanger.
A.l.9 CATEGORY B-J, PRESSURE-RETAINING WELDS IN PIPING A.l.9.1 Nominal Pipe Size 4 In. and Greater, Item B9.10 A.l.9.1.1 Circumferential Welds, Item B9.ll l
l For circumferential welds in pipe of nominal pipe size 4 in, and i
greater, surface plus volumetric examinations shall be performed in ac-l cordance with Figure IWB-2500-8 over essentially 100% of the weld length during each inspection interval. The examination shall include the following:
(a) All terminal ends in each pipe or branch run connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
A-15 1
i
(i) primary blut secondary stress intensity of 2.4Sm for ferritic steel and austenitic steel, and (2) cumulative usage factor U of 0.4.
(c) All dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steels; (b) carbon or low alloy steels to high nickel alloys; and (c) high alloy steels to high nickel alloys.
(d) Additional piping welds so that the total number of circumferential butt welds selected for examination equals 25% of the circumfer-ential butt welds in the reactor coolant piping system. This total does not include welds excluded by IWB-1220.
These addi-tional welds may be located in one loop (one loop is currently defined for both PWR and BWR plants in the 1980 Edition).
For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need be examined for transverse reflectors.
A.1.9.1.2 Longitudinal Welds, Item B9.12 For longitudinal welds in pipe of nominal pipe size 4 in. and greater, surface plus volumetric examinations shall be performed in accordance with Figure IWB-2500-8 for at least a pipe-diameter length, but not more than 12 in. of each longitudinal weld intersecting the circumferential welds re-quired to be examined by Examination Categories B-F and B-J., For welds in carbon or low alloy steels, only those welds showing reportaole preservice transverse indications need be examined for transverse reflectors.
A.l.9.2 Nominal Pipe Size Less Than 4 In., Item 89.20 A.I.9.2.1 Circumferential Welds, Item B9.21 For circumferential welds in pipe of nominal pipe size less than 4 in.,
surface examinations shall be performed in accordance with Figure IWB-2500-8 over essentially 100% of the weld length during each inspection interval. The examination shall include the following:
(a) All terminal ends in each pipe er branch run connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
j l
i A-16
. q (1) primary plus secondary stress intensity of 2.45m for ferritic steel and austenitic steel, and (2) cumulative usage-factor U of 0.4 (c) All dissimilar metal welds between combinations of:
(a) carbon or low alloy steels to high alloy steels; I
(b) carbon or low alloy steels to high nickel alloys; and-(c) high alloys steels to high nickel alloys.
(d) Additional piping welds so that the total number of circumfer-ential butt welds selected for examination equals 25% of the circumferential butt welds in the reactor coolant piping system.
This total does not include welds excluded by IWB-1220.
These additional welds may be located in one loop (one loop is currently defined for both PWR and BWR plants in the 1980 Edition).
1 A.l.9.2.2 Longitudinal Welds, Item B9'.22 For longitudinal welds in pipe of nominal pipe size less than 4 in.,
surface examinations shall be performed in accordance with Figure IWB-2500-8 for at least a pipe-diameter length, but not more than 12 in. of each longitudinal weld intersecting the circumferential welds required to be examined by Examination Categories B-F and B-J.
A.l.9.3 Branch Pipe Connection Welds, Item B9.30 A. l.9. 3.1 Nominal Pipe Size 4 Inches and Greater, Item B9.31 For welds in branch connections 4 in, and greater, surface plus volumetric examinations shall be performed in accordance with Figures IWB-2500-9, -10 and -11 over essentially 100% of the weld length during l
each inspection interval. The examinations shall include the following:
(a) All terminal ends in each pipe or branch run connected to vessels.
l (b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
l (1) primary plus secondary stress intensity of 2.4Sm for ferritic I
steel and austenitic steel, and (2) cumulative usage factor U of 0.4.
A-17 I
7.,.
(c) All dissimilar metal' welds between combinations of:
(a) carbon or low alloy steels to high alloy steels; (b) carbon or low alloy steels to high nickel. alloys; and
-(c) high allo.y steels to high nickel alloys.
(d) Additional piping welds so that the tota 1 number of circumfer-ential bett welds selected for examination equals 25% of the -
circumferential butt welds in the reactor. coolant piping system.
This total does not include welds excluded by IWB-1220. These additional welds may be located in one loop (one loop is currently defined for both PWR and BWR plants in the 1980 Edition).
For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need be examined for transverse reflectors.
A.1.9.3.2 Nominal Pipe Size Less Than 4 Inches, Item 89.32 For welds in branch pipe connections less than 4 in., surface examinations shall be performed in accordance with Figures IWB-2500-9,
-10, and -11 over essentially 100% of the weld length during each inspection interval.. The examinations shall include the following:
(a) ' All terminal ends-in each pipe or branch run connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
(1) primary plus secondary stress intensity of 2.45m for ferritic steel and austenitic steel, and l
(2) cumulative usage factor U of 0.4.
(c) All dissimilar metal welds between combinations of:
i (a) carbon or low alloy steels to high alloy steels; (b) carbon or low alloy steels to high nickel alloys; and (c) high alloy steels to high nickel alloys.
(d) Additi'onal piping welds so that the total nunber of circumfer-i ential butt welds selected for examination equals 25% of the j-circumferential butt welds in the reactor coolant piping system.
l This total does not include welds excluded by IWB-1220. These I
additional welds may be located in one loop (one loop is currently l
defined for both PWR and BWR plants in the 1980 Edition).
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' A.l.9.4 Socket Welds, Item B9.40 A
Socket welds shall be surface examined in accordance with Figure IWB-2500-8 over essentially 100% of the weld length during each inspection interval. The examinations shall include the following:
(a) All terminal ends in each pipe or branch run connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components.where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions.
(1) primary plus secondary stress intensity of 2.4Sm for ferritic steel and austenitic steel, and (2) cumulative usage factor U of 0.4.
(c) All dissimilar metal welds between combinations of:
(a) carbon or low alloy steels to high alloy steels; (b) carbon or low alloy steels to high nickel alloys; and (c) high alloy steels to high nickel alloys.
(d) Additional piping welds so that the total number of circumfer-ential butt welds selected for examination equals 25% of the circumferential butt welds in the reactor coolant piping system.
This total does not include welds excluded by IWB-1220.
These additional welds may be located in one loop (one loop is currently defined for both PWR and BWR plants in the 1980 Edition).
A.l.10 CATEGORY B-K-1, INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES A.l.10.1 Integrally Welded Attachments on Piping, Item B10.10 Volumetric or surf ace examinations, as applicable, per Figures IWB-2500-13, -14, and -15 of essentially 100% of the weld length are required for all integrally welded support attachments of piping.
Includes the welded attachments of piping required to be examined by Examination Category B-J and the weld attachments of associated pumps and valves in-tegral to such piping. Includes those attachments whose base material design thickness is 5/8 in. or greater.
A.1.10.2 Integrally Welded Attachments on Pumps, Item B10.20 Volumetric or surface examinations, as applicable, per Figures IWB-2500-13, -14, and -15 of essentially 100% of the weld length are required for all integrally welded support attachments of pumps.
Includes the welded attachments of piping required to be examined by Examination A-19
.?
Category B-J and the weld attachments of associated pumps and valves in-tegral to such piping.- Includes those attachments whose base material design thickness is 5/8 in, or greater.
A.l.10.3 Integrally Welded Attachments on Valves Item B10.30 Volumetric or surf ace examinations, as applicable, per Figures IWB-2500-13, -14, and -15 of essentially 100% of the weld length are required for all integrally welded support attachments of valves.
Includes the welded attachments of piping required by Examination Category B-J and the weld attachments of associated pumps and valves integral to such piping.
Includes those attachments whose base material design thickness is 5/8 in.
or greater.
.A.1.11 CATEGORIES B-L-1 AND B-M-1, PRESSURE-RETAINING WELDS IN PUMP CASINGS AND VALVE BODIES, AND B-L-2 AND B-M-2, PUMP CASINGS AND VALVE BODIES A.1.11.1 Pump Casing Welds, Item B12.10 Essentially 100% of the pressure-retaining welds in at least one pump in each group of pumps performing similar functions in the system (e.g.,
recirculating coolant pumps) shall be volumetrically examined in accordance with Figure IWB-2500-16 during each inspection interval. The examinations may be performed at or near the end of the inspection interval.
A.1.ll.2 Pumo Casings, Item B12.20 The internal surfaces of at least one pump in each group of pumps per-forming similar functions in the system (e.g., recirculating coolant pumps) shall be visually examined (VT-3) during each inspection interval. The examination may be performed'on the same pump selected for volumetric examination of welds. The examinations may be performed at or near the end of the inspection interval.
A.l.ll.3 Valve Body Welds Nominal Pipe Size Less than 4 in., Item B12.30 The surfaces of essentially 100% of the body welds (nominal pipe size less than 4 in.) in at least one valve in each group of valves with the same construction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions in the system (e.g., containment iso-lation and system overpressure protection) shall be examined in accordance with Figure IWB-2500-17 during each inspection interval. The examinations may be performed at or near the end of the inspection interval.
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A.1.11.3.1 Valve Body Welds, Nominal Pipe Size 4 In. and Greater, Item B12.40 Essentially 100% of the body welds (nominal pipe size 4 in, and greater) in at least one valve in each group of valves with the same con-struction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions in the system (e.g., containment isolation and system over-pressure protection) shall be volumetrically examined'in accordance with Figure IWB-2500-17 during each inspection interval. A supplementary surface examination may be perforned as required inIWB-3518.1(d). The examinations may be performed at or near the end of the inspection interval.
A.1.11.4 Valve Body Exceeding 4 In. Nominal Pipe Size, Item B12.50 The internal surfaces of at least one valve in each group of valves with the same construction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions that exceed 4-inch diameter in the system (e.g., containment isolation and system overpressure
. protection) shall be visually examined (VT-3) during each inspection interval. The examination may be performed on the same valve selected for volumetric examination of welds. The examinations may be performed at or near the end of the inspection interval.
A.l.12 CATEGORIES B-N-1, INTERIOR OF REACTOR VESSEL; B-N-2, INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSELS; and B-N-3, REMOVABLE CORE SUPPORT STRUCTURES A.1.12.1 Reactor Vessel Interior, Item B13.10 The accessible areas of the reactor vessel interior, including the spaces above and below the reactor core that are made accessible by' removing components during normal refueling outages, shall be visually examined (VT-3) during the first refueling outage and subsequent refueling outages at approximately 3-year intervals.
A.l.12.2 Boiling Water Reactor Vessel Interior Attachments Within Beltline Region, Item 813.20 The accessible welds in the reactor vessel interior attachments within the beltline region shall be visually examined (VT-1) during each inspec-tion interval. The examinations may be perforned at or near the end of the inspection interval.
A-21
A.l.12.2.1 Boiling Water Reactor Vessel Interior Attachments Beyond Beltline Region, Item B13.21 The accessible welds in the reactor vessel interior attachments be.)ond the beltline region shall be visually examined (V -3) during each inspec-tion interval.. The examinations may be performed at or near the end of the-inspection interval.
A.l.12.2.2 Boiling Water Reactor Core Support Structure, Item B13.22 The accessible surfaces of the core support structure shall be visually examined (VT-3) during each inspection interval. The examinations may be performed at or near the end of the inspection interval.
A.1.12.3 Pressurized Water Reactor Interior Attachments Within Beltline Region, Item B13. 30 The accessible welds in the reactor vessel interior attachments within
.the beltline region shall be visually examined (VT-1) during each inspec-tion interval. - The examinations may be performed at or near the end of the inspection interval.
i A.1.12.3.1 Pressurized Water Reactor Interior Attachments Be,)ond Beltline Region, Item B13.31 The accessible welds in the reactor vessel interior attachments be)cnd the beltline region shall be visually examined (VT-3) during each inspec-tion interval. The examinations may be performed at or near the end of the inspection interval.
A.1.12.3.2 Core Support Structure for Pressurized Water Reactor Vessels, Item B13.32 The accessible welds and surfaces of the core support structure shall be visually examined (VT-3) each inspection interval. The structure shall be removed from the reactor vessel for examination.
The examinations may be performed at or near the end of the inspection ' interval.
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e
'A.1.13 CATEGORY B-0, PRESSURE-RETAINING WELDS IN CONTROL R0D HOUSINGS A l.13.1 Welds in Control Rod Drive Housings, Item B14.10 The welds in 10% of the peripheral control rod drive housings shall be surface or volumetrically examined in accordance with Figure IWB-2500-18 during each inspection interval. The examinations may be performed at or near the end of the inspection interval.
i A.l.14 CATEGORY B-P, ALL PRESSURE-RETAINING COMPONENTS A.1.14.1 Reactor Vessel Pressure-Retaining Boundary, Item B15.10 The reactor vessel pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydro-static test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.1.14.1.1 Reactor Vessel Pressure-Retaining Boundary, Item B15.11 The reactor vessel pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accor-dance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations may be performed at or near the end of the inspection interval. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
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I 1
i A.l.14.2 Pressurizer Pressure-Retaining Boundary, Item B15.20 The pressurizer pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests for the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure-tests for repaired, replaced, or altered components shall be i
governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup.
The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system 1
hydrostatic test (IWB-5222) and the accompanying VT-2 examination are i
acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.l.14.2.1 Pressurizer Pressure-Retaining Boundary, Item B15.-21 The pressurizer pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary.
The examinations may be performed at or near the end of the inspection interval. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
A.1.14.3 Steam Generator Pressure-Retaining Boundary, Item B15.30, The steam generator pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test perfcrmed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the ncrmal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.I.14.3.1 Steam Generator Pressure-Retaining Boundary, Item B15.31 examined (VT-2 generator pressure-retaining boundary shall be visually The steam
, during the system hydrostatic test performed in accordance with IWB-5222 during each refueling outage. The examinations may be A-24 o
l l
performed at or near the end of the inspection interval. The pressure-l retaining boundary during the test shall incluoe all Class I components l
within the system boundary. System pressure tests of the reactor coolant l'
system shall be conducted in accordance with IWA-5000.
System pressure L
tests for repaired, replaced, or altered components shall be governed by l
IWA-5214(c).
1 A.l.14.4 Heat Exchanger Pressure-Retaining Boundary, Item B15.40 The heat exchanger pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
L System pressure tests for repaired, replaced, or altered components shall l
be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant s'ystem boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydro-static test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.l.14.4.1 Heat Exchanger Pressure-Retaining Boundary, Item 815.41 The heat exchanger pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations may be performed at or near the end of the inspection interval. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
A.l.14.5 Piping Pressure-Retaining Boundary, Item B15.50 The piping pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup.
The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydro-static test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
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A.l.14.5.1 Piping Pressure-Retaining Boundary, Item B15.51 The piping pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations may be perfcmed at or near the end of the inspection interval. System pressure tedts of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
A.l.14.6 Pumo Pressure-Retaining Boundary, Item B15.60 The pump pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage.
System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 exami-nation shall, however, extend to and include the second closed valve at the boundary extremity.
A system hydrostatic test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.1.14.6.1 Pump Pressure-Retaining Boundary, Item B15.61 The pump pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations may be performed at or near the end of the inspection inter-val. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
A.l.14.7 Valve Pressure-Retaining Boundary, Item B15.70 The valve pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage.
System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.
System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).
The pressure-retaining boundary during the system leakage test shall A-26 1
0-
correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup.
The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.
A.1.14.7.1 Valve Pressure-Retaining Boundary, B15.71 The valve pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations may be performed at or near the end of the inspection interval.
System pressure tests of.the reactor coolant system shall be conducted in accordance with_IWA-5000. System pressure tests for repaired; replaced, or altered components shall be governed by IWA-5214(c).
A.1.15 CATEGORY B-Q, STEAM GENERATOR TUBING A.l.15.1 Steam Generator Tubing, Straight Tube Design, Item B16.10 The examination requirements, examination method, and the extent and frequency of examination shall be governed by the plant technical s specifications.
A.l.15.2 Steam Generator Tubing, U-Tube Design, Item B16.20 The examination requirements, examination method, and the extent and frequency of examination shall be governed by the plant technical s specifications.
I l
A-27 l
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A.2 CLASS 2 REQUIREMENTS A.2.1 CATEGORY C-A, PRESSURE-RLTAINING WELDS IN PRESSURE VESSELS A.2.1.1 Shell-Circumferential Welds, Item C1.10 Essentially 100% of the shell circumferential welds at gross structural discontinuities shall be volumetrically examined in accordance with Figure IWC-2500-1 during each inspection interval. A gross structural discon-tinuity is defined in'NB-3213.2. Examples are junctions between shells of.
differcnt thicknesses, cylindrical shell-to-conical shell junctions, and shell'(or head)-to-flange welds and head-to-shell welds. For multiple vessels with similar design, size, and service (such as steam generators and heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
A.2.1.2 Head Circumferential Weld, Item C1.20 Essentially 100% of the circumferential head-to-shell weld shall be volumetrically examined in accordance with Figure IWC-2500-1 during each inspection interval. For multiple vessels with similar design,' size, and service (such as steam generators and heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
A.2.1.3 Tubesheet-to-Shell Weld, Item C1.30 Essentially 100% of the tubesheet-to-shell weld shall be volumetrically examined in accordance with Figure IWC-2500-2 during each inspection inter-val. For multiple vessels with similar design, size, and service (such as steam generators and heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
A.2.2 CATEGORY C-B, PRESSURE-RETAINING N0ZZLE WELDS IN VESSELS A.2.2.1 Nozzles in Vessels 1/2 In. or Less in Nominal Thickness, Item C2.10 A.2.2.1.1 Nozzle-to-Shell(orHead) Weld,ItemC2.ll All nozzles in vessels 1/2 in. or less in nominal thickness at terminal l
ends of piping runs shall be surf ace examined in recordance with Figure IWC-2500-3 during each inspection interval. Terininal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (man-ways and handholes are excluded). Only those piping runs selected for
- examination under Examination Category C-F are included.
J A'-28
)
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A.2.2.2 Nezzles Without Reinforcing Plate in Vessels Over 1/2 In. in nominal inicKness, item L,z.cu A.2.2.2.1 Nozzle-to-Shell(orHead) Weld,ItemC2.21 l
The nozzle-to-shell (or head) welds of all nozzles in vessels over 1/2 in. in nominal thickness at terminal ends of piping runs shall be surface and volumetrically examined in accordance with Figure IWC-2500-4(a) or (b) during each inspection interval. Terminal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (man-ways and handholes are excluded). Only those piping runs selected for examination under Examination Category C-F are included.
A.2.2.2.2 Nozzle Inside Radius Section, Item C2.22 The inside radius sections of all nozzles in vessels over 1/2 in. in nominal thickness at terminal ends of piping runs shall be volumetrically examined in accordance with Figure IWC-2500-4(a) or (b) during each inspec-tion interval. Terminal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (manways and handholes are excluded).
Only those piping runs selected for examination under Examination Category C-F are included.
A.2.2.3 Nozzles With Reinforcing Plate in Vessels Over 1/2 In. Nominal Ifi1CKness, Item C2.30 A.2.2.3.1 Reinforcing Plate Welds to Nozzle and Vessel, Item C2.31 The reinforcing plate-to-nozzle and vessel welds of all nozzles in vessels over 1/2 in. nominal thickness at terminal ends of piping runs shall be surf ace examined in accordance with Figure IWC-2500-4(c) during each inspection interval. Terminal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (manways and hand-holds are excluded). Only those piping runs selected for examination under Examination Category C-F are included.
A.2.2.3.2 Nozzle-to-Shell (or Head) Welds, Item C2.32 If the nozzle bore is accessible from inside the vessel, the nozzle-to-shell (or head) welds in vessels over 1/2 in nominal thickness at l
terminal ends of piping runs shall be volumetrically examined in accordance with Figure IWC-2500-4(c) during each inspection interval.
If the nozzle bore is not accessible from inside the vessel, the telltale hole in the reinforcing plate shall be examined for evidence of leakage while the vessel is undergoing the system pressure test (IWC-5221 or IWC-5222) as required by Examination Category C-H.
Terminal ends include nozzles welded i
A-29 I
1
l l.
I to or integrally cast in vessels that connect to piping runs (manways and han& olds are exluded). Only those piping runs selected for examination under Examination Category C-F are included.
A.2.3 CATEGORY C-C AND C-E, SUPPORT MEMBERS A. 2. 3.1 Integrally Welded Support Attachments in' Pressure Vessels; item u.to The surfaces of 100% of each integrally weloed attachment in pressure vessels shall be surface examined in accordance with Figure IWC-2500-5 during each inspection interval. Examination is limited to integrally welded attachments whose base material design thickness is 3/4 in. or greater. For multiple vessels of similar design and service, the required examinations may be conducted on only one vessel.
Were multiple vessels are provided with a number of similar supporting elements, the examination of the support elements may be distributed among the vessels.
A.2.3.2 Integrally-Welded Attachments-in Piping, Item C3.20 The surfaces of 100% of each integrally welded. attachment in piping shall be surface examined in accordance with Figure IWC-2500-5.
Exami -
nation is limited to integrally welded attachments whose base material design thickness is 3/4 in. or greater.
In addition, examinations are limited to attachments of those components required to be examined under Examination Categories C-F and C-G.
A.2.3.3 Inteorally Welded Puno-Attachments; Item C3.30 The surfaces of 100% of each integrally welded attachment in pumps shall be examined in accordance with Figure IWC-2500-5.
Examination is limited to integrally welded attachments whose base material design thickness is 3/4 in, or greater.
Examinations are limited to attachments of those conponents required to be examined under Examination Categories C-F and C-G.
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A.2.3.4 Integrally Welded Valve Support Attachments, Item C3.40 The surf aces of 100% of each integrally welded valve attachment shall be examined in accordance with Figure IWC-2500-5 during_each inspection interval. Examination is limited to integrally welded attachments whose base material design thickness is 3/4 in. or greater. Examinations are limited to attachments of those components required to be examined under Examination Categories C-F and C-G.
7 A.2.4 CATEGORY C-D, PRESSURE-RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMETER A.2.4.1 Bolts and Studs in Pressure Vessels, Item C4.10 For bolts and studs'in pressure vessels, 100% of the bolts and studs at each bolted connection of components required to be inspected shall be volumetrically examined in accordance with Figure IWC-2500-6 during each inspection interval. Bolting may be examined on one vessel in each system required to be examined that is similar in design, size, function, and service.
In addition, where the vessel contains a group of bolted connec-tions of similar design and size (such as flange connections and manway covers), only one bolted connection among the group need be examined.
Bolting may be examined in place under load or upon disassembly of the connection.
A.2.4.2 Bolts and Studs in Pioing, Item C4.20 One hundred percent of the bolts and studs at each bolted piping connection snall be volumetrically examined in accordance with Figure IWC-2500-6. The examination of flange bolting in piping systems required to be examined may be limited to the flange connections in pipe runs selected for examination under Examination Category C-F.
Bolting may be examined in place under load or upon disassembly of the connection.
A.2.4.3 Bolts ~and Studs in Pumps, Item C4.30 For pumps, 100% of the bolts and studs at each bolted connection of pumps shall be volumetrically examined in accordance with Figure IWC-2500-6. Bolting on only one pump among a group of pumps in each system required to be examined that have similar designs, sizes, functions, and A-31 A
service is required to be examined.
In addition, where one pump contains a group of bolted connections of similar design and size (such as flange connections and manway covers), the examination may be conducted on one bolted connection among the group. Bolting may be examined in place under load and upon disassembly of the connection.
A.2.4.4 Bolts and Studs in Valves, Item C4.40 For valves, 100% of the bolts and studs at each bolted connection of valves shall be volumetrically examined in accordance with Figure IWC-2500-6. Bolting on only one valve among a group of valves in each system required to be examined that have similar designs, sizes, functions, and service is required to be examined.
In addition, where one valve contains a group of bolted connections of similar design and size (such as flange connections and manway covers), the examination may be conducted on one bolted connection among the group. Bolting may be examined in place under load and upon disassembly of the connection.
A.2.5 CATEGORY C-F, PRESSURE-RETAINING WELDS IN PIPING A.2.5.1 Pioing Welds 1/2 In. or less Nominal Wall Thickness, Item C5.10 l-A.2.5.1.1 Circumferential Welds, Item C5.ll The surfaces of 100% of each circumferential weld 1/2 in. or less nomi-nal wall thickness shall be examined in accordance with Figure IWC-2500-7 during each inspection interval. The welds selected for examination shall include a.
all welds at locations where the stresses under the loadings resulting from Normal and Upset plant conditions as calculateo by the sum of Equations 9 and 10 in NC-3652 exceed the specified value; b.
all welds at terminal ends (see (e) below) of piping or branch runs; '
c.
all dissimilar metal welds; d.
additional welds, at structural discontinuities (see (f) below) such that the total number of welds selected for examination in-cludes the following percentages of circumferential piping welds; 1
l A-32 l
l 1
l l..
j For boiling water reactors:
l 1.
none of the welds exempted by IWC-1220; 2.
none of the welds in resideal heat removal and emergency core cooling systems (see (g) below);
3.
50% of the main steam system welds;
- 4. ! 25% of the welds in all other systems.
l For pressurized water reactors:
1 L
1.
none of the welds exempted by IWC-1220; 2.
none.of the welds in residual heat removal and emergency core cooling systems; 3.
10% of the main steam system welds L in. nominal pipe size i
and smaller; 4.
25% of the welds in all other systems.
e.
terminal ends are the extremities of piping runs that' connect to structures, components (suchas vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints or provide at least two degrees of restraint to piping thermal expansion; f.
structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as, elbows, tees, reducers, and flanges conforming to ANSI Standard B16.9), and nine branch connections and fittings; 1
l g.
examination requirements are under development.
For welds in carbon or low alloy steels, only those welds showing l
reportable preservice transverse indications need to be examined for transverse reflectors.
A.2.5.1.2 Longitudinal Welds, Item C5.12 Longitudinal welds 1/2 in. or less nominal wall thickness shall be surface examined in accordance with IWC-2520-7 (2.5 t at the intersecting circumferential weld) during each inspection interval.
A.2.5.2 Piping Welds Over 1/2 In. Nominal Wall Thickness, Item C5.20 A.2.5.2.1 Circumferential Welds, Item C5.21 One hundred percent of each circumferential weld over 1/2 in. nominal wall thickness shall be surface and volumetrically examined in accordance with Figure IWC-2500-7 during each inspection interval. The welds selected for examination shall include A-33 n
L a.
all welds at locations where the stresses under the loadings resulting from Normal and Upset plant conditions as calculated by I
the sum of Equations 9 and 10 in NC-3652 exceed the specified value; b.
all welds at terminal ends (see (e) below) of piping or branch runs; c.
all dissimilar metal welds; d.
additional welds, at structural discontinuities (see (f) below) such that the total number of welds selected for examination in-cludes the following percentages of circumferential piping welds; For boiling water reactors:
1.
none of the welds exempted by IWC-1220; 2.
none of the welds in residual heat removal and emergency core cooling systems (see (g) below);
3.
50% of the main steam system welds; i
4 25% of the welds in all other systems.
For pressurized water reactors:
1 none of the welds exempted by IWC-1220; 2.
none of the welds in residual heat removal and emergency core cooling systems; 3
10% of tne main steam system welds 8 in. nominal pipe size and smaller; 4
25% of the welds in all other systems.
e.
terminal ends are the extremities of piping runs that connect to structures, components (such as vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints Or provide at least two degrees of restraint to piping thermal expansion; f.
structural discontinuities include pipe weld joints to vessel nozzles,valvebodies,pumpcasings,pipefittings(suchas, elbows, tees, redu~cers, and flanges conforming to ANSI Standard B16.9), and nine branch connections and fittings; I
g.
examination requirements are under development.
For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need to be examined for trans-verse reflectors.
A.2.5.2.2 Longitudinal Welds, Item C5.22 Longitudinal welds over 1/2 in. nominal wall thickness shall be surf ace and volumetrically examined in accordance with Figure IWC-2500-7 (2.5 t at the intersecting circumferential weld) during each inspection interval.
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A.2.5.3 Pipe Branch Connections Greater than 4 In. Nominal Branch Pioe dize, Item C5.30 A.2.5.3.1 Circumferential Welds, Item C5.31 The surfaces of 100% of each circumferential weld in pipe branch connections shall be examined in accordance with Figures IWC-2500-9 to
-13, inclusive, during each inspection interval. The welds selected for examination shall include all welds at locations where the stresses under the loadings a.
resulting from Normal and Upset plant conditions as calculated by the sum of Equations 9 and 10 in NC-3652 exceed the specified value; b.
all welds at terminal ends (see (e) below) of piping or branch runs; c.
all dissimilar metal welds; d.
additional welds, at structural discontinuities (see (f) below) such that the total number of welds selected for examination in-cludes the following percentages of circumferential piping welds; For boiling water reactors:
1.
none of the welds exempted by IWC-1220; 2.
none of the welds in residual heat removal and eeergency core cooling systems (see (g) below);
3.
50% of the main steam system welds 8 in; 4.
25% of the welds in all other systems.
For pressurized water reactors:
1.
none of the welds exempted by IWC-1220; 2.
none of the welds in residual heat removal and emergency core cooling systems; i
3.
10% of the main steam system welds 8 in. nominal pipe size I
and smaller; 4
25% of the welds in all other systems.
e.
terminal ends are the extremities of piping runs that connect to l
structures, components (such as, vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints or provide at least two degrees of restraint to piping thermal expansion; f.
structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as, elbows, tees, reducers, and flanges conforming to ANSI Standard B16.9), and nine branch connections and fittings; g.
examination requirements are under development.
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For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need to be examined for trans-verse reflectors.
A.'2.5.3.2 Longitudinal Welds, Item C5.32 Longitudinal welds in pipe branch connections shall be surface examined in accordance with Figures IWC-2500-12 and -13 (2.5 t at the intersecting circumferential weld) during each inspection interval.
A.2.6 CATEGORY C-G, PRESSURE-RETAINING WELDS IN PUMPS AND VALVES A.2.6.1 Pump Casing Welds, Item C6.10 One hundred percent of all pump casing welds in each piping run examined under Examination Category C-F shall be surf ace examined in accordance with Figure IWC-2500-8 during each inspection interval. For multiple pumps of similar design, size, function, and service in a system, only one pump among each group of multiple pumps is required to be examined.
The examination may be performed from either the inside or outside surface.
A.2.6.2 Valve Body Welds, Item C6.20 One hundred percent of all valve body welds in each piping run examined under Examination Category C-F snall be surface examined in accordance with Figure IWC-2500-8 during each inspection interval. For multip'e valves of similar design, size, function, and service in a system, only one valve among each group of multiple valves is required to be examined. The examination may be performed from either the inside or outside surface.
A.2.7 CATEGORY C-H, ALL PRESSURE-RETAINING COMPONENTS A.2.7.1 Pressure Vessels, Item C7.10 Pressure vessel pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examine: (VT-2) during the system leakage test performed in accordance with IWC-5221 during each inspec-tion. No components within the pressure retaining boundary are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. Where portions of a system are subject to system pressure tests associated with two different system functions, the VT-2 examination need only be performed during the test conoucted at the higher of the test pressures of the respective system 1
A-36 l
function. The pressure retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A system hydrostatic test (IWC-5222) and accompany-ing VT-2 examination are acceptable in lieu of the system pressure test (IWC-5221) and VT-2 examination.
A.2.7.1.1 Pressure Vessels, Item C7.20 Pressure vessel pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWC-5222 during each inspec-tion period.
No components within the pressure retaining boundary [as defined by Note (7)] are exempt or excluded from the examination require-ments, except as specified in IWA-5214(c) for repairs and replacements.
The system hydrostatic test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B.
The pressure retaining boundary includes only those portions of the system required to operate or support the safaty system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.
A.2.7.2 Piping, Item C7.30 Piping pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system leakage test performed in accordance with IWC-5221 during each inspection period. No components within the pressure-retaining boundary are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. Where portions of a system are subject to system pressure tests associated with two different system functions, the VT-2 examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capsble of automatic closure when the safety function is required. A system hydro-static test (IWC-5222) and accompanying VT-2 examination are acceptable in lieu of the system pressure test (IWC-5221) and VT-2 examination.
A.2.7.2.1 Piping, Item C7.40 systems) g pressure-retaining boundaries (other than open-ended portions of Pipin shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWC-5222 during each inspection period.
No components within the pressure-retaining boundary [as defined by Note (7)] are exempt or excluded from the examination requirements, except as A-37 A
4 specified in IWA-5214(c) for repairs and replacements. The system hydro-static test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B.
The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including)the first normally closed valve (including a safety or relief valve or valve capable of automatic closure when the safety function is required.
A.2.7.3 Pumps, Item C7.50 Pump pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system leakage test performed in accordance with IWC-5221 during each inspection period. No components within the pressure-retaining boundary are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. Where portions of a system are subject to system pressure tests associated with two different system functions, the VT-2 examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A system hydro-hydrostatic test (IWC-5222) and accompanying VT-2 examination are acceptable in lieu of the system pressure test (IWC-5221) and VT-2 examination.
A.2.7.3.1 Pumps, Item C7.60 Pump pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWC-5222 during each inspection period.
No components within the pressure-retaining boundary [as defined by Note (7)] are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. The system hydrostatic test (IWC-5222) shall be conducted at or near the end of each I
inspection interval or during the same inspection period of each inspection j
interval of Inspection Program B.
The pressure-retaining boundary includes only those portions of the systen required to operate or support the safety system function up to and including)the first normally closed valve (including a safety or relief valve or valve capable of automatic closure when the safety' function is required.
A.2.7.4 Valves, Item C7.70 Valve pressure-retaining boundaries other than open-ended portions of systems) shall be visually examined (VT-2) during the system leakage test in accordance with IWC-5221 during each inspection period. No components within the pressure-retaining boundary are exempt or excluded from the l
A-38
__JU
1 i
examination requirements, except as specified in IWA-5214(c) for repairs l
and replacements. Where portions of a system are subject to system pressure tests associated with two different system functions, the VT-2 l
examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A system hydro-static test (IWC-5222) and accompanying VT-2 examination are acceptable in lieu of the system pressure test (IWC-5221) and VT-2 examination.
A.2.7.4.1 Valves, Item C7.80 Valve pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system hydrostatic test perfarmed in accordance with IWC-5222 during each inspection period.
No components within the pressure-retaining boundary [as defined by Note (7)] are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. The system hydrostatic test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B.
The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (in-cluding a safety or relief valve) or valve capable of automatic closure when the safety function is required.
A-39 A
g F
(
A.3 CLASS 3 REQUIREMENTS A.3.1 CATEGORY D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION A.3.1.1 Pressure-Retaining Components, Item D1.10 The pressure-retaining components in.the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test IWA-5000/
IWD-5221 each inspection period. A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspec-tion period of each inspection interval for Inspection Program B.
The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system function. There are no exemptions or exclusions from these requirements except as specified in IWA-5214(c).
A.3.1.2 Integral Attachment--Component Supports and Restraints, Item D1.20 Component supports and restraints shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall l-correspond to those component supports selected by IWF-251G(b).
A.3.1.3 Integral Attachment--Mechanical and Hydraulic Snubbers, Item 01.30 Mechanical and hydraulic snubbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.1.4 Integral Attachment--Spring Type Supports, Item 01.40 Spring type supports shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
i A-40 i
L l
A.3.1.5 Integral Attachment--Constant Load Type Supports, Item D1.50 Constant load type supports shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For
)
multiple components within a system of similar design, function, and j
service, the integral attachment of only one of the multiple components shall be examined.. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
1 A.3.1.6 Integral Attachment--Shock Absorbers, Item D1.60 Shock absorbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond,to those component supports selected by IWF-2510(b).
A.3.2 CATEGORY D-B, SYSTEMS IN SUPPORT OF EMERGENCY C0RE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERIC CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL A.3.2.1 Pressure-Retaining Components, Item D2.10 The pressure-retaining components in the pressure-retaining boundary shall De visually examined (VT-2) during the system pressure test IWA-5000/
IWD-5221 each inspection period. A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval for Inspection Program B.
The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system function. There are no exemptions or exclusions from these require-ments except as specified in IWA-5214(c).
A.3.2.2 Integral Attachment--Component Supports and Restraints Item D2.20 Component supports and restraints shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachments Selected for examination shall correspond to those component supports selected by IWF-2510(b).
1 A-41
.J
A.3.2.3 Integral Attachment--Mechanical and Hydraulic Snubbers, Item D2.30 Mechanical and hydraulic snubbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.2.4 Integral Attachment--Spring Type Supports, Item D2.40 Spring type supports shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.2.5 Integral Attachment--Constant Load Type Supports, Item D2.50 Constant load type supports shall be visually examined (VT-3) in accor-dance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.2.6 Integral Attachment--Shock Absorbers, Item D2.60 Shock absorbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.3 CATEGORY D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE P0CL A.3.3.1 Pressure-Retaining Components, Item D3.10 The pressure-retaining components in the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test IWA-5000/
IWD-5221 each inspection period. A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the systern pressure test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection i
A-42 1
4-period of each inspection interval for Inspection Program B.
The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system function. There are no exemptions or exclusions from these require-mentsexceptasspecifiedinIWA-5214(c).
A.3.3.2 Integral Attachment--Component Supports and Restraints, Item 03.tu Component supports and restraints shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.3.3 Integral Attachment--Mechanical and Hydraulic Snubbers, item 03.30 Mechanical and hydraulic snubbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.3.4 Integral Attachment--Spring Type Supports, Item D3.40 l
Spring type supports shall be visually examined (VT-3) in accordance l
with Figure IWD-2500-1 during each ir.spection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components snall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A.3.3.5 Integral Attachment--Constant Load Type Supportg, Item D3.50 Constant load type supports shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
A-43
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A.3.3.6 Integral Attachment--Shock Absorbers, Item D3.60 Shock absorbers shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 during'each inspection interval. For multiple components-within a system of similar design, function, and service, the integral attachment of only one of the multiple componer,ts shall be examined. The
- integral attachments' selected for examination shall correspond to those -
component supports selected by IWF-2510(b).
I' 6
l 1
A-44 I
. TO
3 i
J-A. 4 COMPONENT SUPPORTS l
1 l
A.4.1 CATEGORY F-A, PLATE AND SHELL TYPE SUPPORTS
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A. 4.1.1 Mechanical Connections to Pressure-Retaining Components and Building Structure, Item Fl.10 i
Mechanical connections to pressure-retaining components and the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval.
Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A. 4.1. 2 Weld Connections to Building Structure, Item F1.20 Weld connections to the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A. 4.1. 3 Weld and Mechanical Connections at Intermediate Joints in Multi-connected Inteoral and Nonintegral Supports, Item Fl.30 Weld and mechanical connections at intermediate joints in multiconnected integral and nonintegral supports shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspec-tion interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A.4.1.4 Component Displacement Settings of Guides and Stops, Misalignment j
of Supports, Assembly of Support Items, Item Fl.40 Component' displacement settings of guides and stops, misalignment of supports, and assembly of support items shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF 1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those :omponents that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multip1a components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
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f A.4.2 CATEGORY F-B, LINEAR TYPE SUPPORTS l
A.4.2.1 Mechanical Connections to Pressure-Retaining Components and Building Structure, Item F2.10 Mechanical connections to pressure-retaining components and the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval.
Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A.4,2.2 Weld Connections to Building Structure, Item F2.20 Weld connections to the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A.4.2.3 Weld and Mechanical Connections at Intermediate Joints in Multi-connected Integral and Nonintegral Supports, Item F2.30 Weld and mechanical connections at intermediate joints in multiconnected integral and nonintegral supports shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspec-tion interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar designt function, and service, the supports of only one of the multiple components are required to be examined.
A.4.2.4 Comoonent Displacement Settings of Guides and Stops, Misalignment of Supports, Assably of Support Items, Item F2.40 Component displacement settings of guides and stops, misalignment of support and assembly of support items shall be visually examined (VT-3) s in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
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A.4.3 CATEGORY F-C, COMPONENT STANDARD SUPPORTS A.4.3.1 Mechanical Connections to Pressure-Retaining Components and Building Structure, Item F3.10 Mechanical connections to pressure-retainin building structure shall be visually examined (g components and theVT-3) in accordance wi Article IWF-1300'and Figure IWF-1300-1 during each inspection interval.
Component supports selected for examination shall be the supports of those canponents that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A.4.3.2 Weld Connections te Building Structure, Item 3.20 Weld connections to the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
A.4.3.3 Weld and Mechanical Connections at Intermediate Joints in Multi-connected Integral and Nonintegral Supports, Item F3.30 l
Weld and mechanical connections at intermediate joints in multiconnected integral and nonintegral supports shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspec-tion interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple canponents are required to be examined.
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A.4.3.4 Component Displacement Settings of Guides and Stops, Misalignment l
of Supports, Assembly of Support Items, Item F3.40 Component displacement settings of guides and stops, misalignment of i
supports, and assembly of support items shall be visually examined (VT-3) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspection interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only 19 of the multiple components are required to be examined.
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A.4.3.5 Spring Type Su 3 ports _ Constant Load Type Supports, Shock Absorbers, Hydraulic and Mechanical Type Snunners, Item F3.50 Spring type supports, constant load type supports, shock absorbers, and hydraulic-and mechanical type snubbers shall be visua.ly examined (VT-4) in accordance with Article IWF-1300 and Figure IWF-1300-1 during each inspec-tion interval. Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For multiple components within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
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