ML20067E716
| ML20067E716 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/31/1989 |
| From: | SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| Shared Package | |
| ML20067E690 | List: |
| References | |
| CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1941, NUDOCS 9102180066 | |
| Download: ML20067E716 (92) | |
Text
{{#Wiki_filter:6 O SAIC 88/1941
.i TECHNICAL EVALVATION REPORT FIRST INTERVAL INSERVICE INSPECTION PROGRAM MILLSTONE NUCLEAR POWER STATION UNIT 3 Submitted to
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U.S. Nuclear Regulatory Commission Contract No. 03-87-029 Submitted by Science Applications International Corporation - Idaho Falls, Idaho 1 l March 1989 9102100066 910200 DR ADOCK 050 3
l l CONTENTS
- 1. INTRODUCT'ON .......................... 1
- 2. EVALUA140N OF IN. SERVICE 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 License Conditions . . . . . . . . . . . . . . . . . . . 8 2.5 Conclusions and Recommendations .............. 9
- 3. REQUESTS FOR RELIEF FROM ASME CODE SECTION XI EXAMINATION REQUIREMINTS ...................10 3.1 CLASS 1 COMPONENTS . . . . . . . . . . . . . . . . . . . 11 3.1.1 Reactor Vessel ..................11 3.1.1.1 Relief Request IR-1, Pressure Retaining Welds in the Reactor Pressure Vessel, Category B-A, items Bl.12, Bl.21, and Bl.22 ............11 3.1.1.2 Relief Request IR-2, Pressure Retaining Welds in the Reactor Vessel Closure Head, Category B-A, Items Bl.21, Bl.22, and B1.40 . . . . . . . . . 14 3.1.1.3 Relief Request IR-1, Reactor Vessel NLezie-to-Vessel Welds and Nozzle Inside P.cius Sections, Category B-D, items B3.90 and B3.100 . . . . . . . . . 17 i
o . 3.1.2 Vessels Other Than Reactor Vessel . . . . . . . . . . . 19 3.1.2.1 Relief Request IR-3, Pressure Retaining Welds in the Pressurizer, Category B B, Item B2.11. . . . . 19 3.1.2.2 Relief Request IR-8, Full Penetration Nozzle-to-Vessel Welds in the Pressurizer and Steam Generators, Category B-0, Items B3.110 and B3.130 . . . . . . . . . . . . . . . . . . . . . . . . 21 3.1., Piping Pressure Boundary . . . . . . . . . . . . . . . 23 3.1.3.1 Relief Request IR-9, Pressure Retaining Welds and Dissimilar Metal Welds in Class 1 Piping, Categories B-J and B F, Items 89.11 and B5.10 . . . . . . . . . . . . . . . . . . . 23 3.1.3.2 Relief Request IR-10, Centrifuga11y Cast Stainless Steel (CCSS) Component-to-Fitting Welds, Category B J, Item B9.11 ...........26 3.1.3.3 Relief Request IR ll, Pressure Retaining Weld in Class 1 Piping, Category B-J, Item B9.11 . . . . . . . . . . . . . . . . . . . . . . 29 3.1.4 Pump and Valve Pressure Boundary . . . . . . . . . . . . 32 3.1.4.1 Relief Request IR-4, Internal Surfaces of Pump Casings and Valve Bodies, Categories B-L-2 and B M-2, Items B12.20 and B12.40 . . . . . . . 32 3.2 Class 2 Components . . . . . . . . . . . . . . . . . . 35 3.2.1 Pressure Vessels and Heat Exchangers . . . . . . . . . 35 3.2.1.1 Relief Request IR-14, Shell-to-Flange Weld in the Residual Heat Exchanger, Category C- A, Item C1.10 . . . . . . . . . . . . . . . 35 3.2.1.2 Relief Request IR-7, Full Penetration Nozzle-to-Vessel Welds in the Secondary Side of the Steam Generators, Category C-B, Item C2.21 . . . ...........37 3.2.2- Piping Pressure Boundary . . . . . . . . . . . . . . . 39 3.2.2.1 Relief Request IR-13 Integrally Welded Attachments for Piping, Category C-C, Item C3.20 . . . . . . . . . . . . . . . . . . . . . . 39 11
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- 3.2.3 Pump Pressure Boundary (No relief requests) 3.2.4 Valve Pressure Boundary (No relief requests) 3.3 Class 3 Components (No relief requests) 3.4 Component Supports (No relief requests) 3.5 Pressure Tests (No relief requests) 3.6 General (No relief requests)
- 4. REFERENCES ..........................42 APPENDIX A: Requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, 1983 Edition with Addenda through Summer 1983 iii
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TECHNICAL EVALUATION REPORT f!RST INTERVAL INSERVICE INSPECTION PROGRAM MILLSTONE NUCLEAR POWER STATION UNIT 3 1
- 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 is Section 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 intervals that ncrmally l 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 U.S. . 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 examina-
-tions normally will comply with the requirements in the-latest edition and' .
- addenda-of Section XI incorporated in the regulation on the date 12 months before the date of issuance of the operating license. The effective Code -
for.the first: interval for Millstore 3, which began April 23,--1986, would be the 1980 Edition with-addenda through Winter of 1981. The program, however, has been written to the 1983 Edition with addenda through Summer of'1983, which is permi.tted under the terms of 50.55a(g)(4)(iv).
- Section 2 of this report-evaluates the ISI Plan developed by~the licensee, Northeast Nuclear Energy Company (NNECo), for Millstone 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 Millstone 3's construction permit was issued - (August 9,1974), 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 in Section.XI Editions applied to the construction of the - particularcomponent(10CFR50.55a(g)(3)). The provisions of 10 CFR 50.55a(g)(3) also state that components (including supports) may meet
- Specific inservice test programs for pumps and valves (IST programs) are being evaluated _in other reports.
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the requirements set forth in subsequent editions and addenda of this Code which are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein. The current revision to 10 CFR 50.55a recognizes that the requirements of Section XI may not be practical to implement because of limitations of design, geometry, and materials of construction of components and systems that were designed to the older Code. The regulation therefore permits exceptions to impractical examination or testing requirements to be requested. Relief from these requirements may be granted, providad 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 current regulation also provides that ISI Programs may meet the requirements of subsequent Section XI Code editions and addenda, incorporated by reference in the Regulation, subject to approval by the NRC, Portions of such editions or addenda may te 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 its requirements. In some instances, however, these exemptions are not acceptable to NRC or are acceptable only with restric-tions. As appropriate, these instances are also discussed in Section 3 of this report. The preservice inspection (PSI) program for Millstone Unit 3, a pressurized attachments water reactor to letters dateddesigned by Westjg June 1,1983,\* andhouse, March 20,was submitted (A 1984, withreliefrequestssubmittedinprepJ minary form November 19,1985,(3) and in final form December 23, 1985.1 The NRC staff reviewed the PSI program and relief requests in the Safety Evaluation Report (SER), NUREG-1031, and regar supplements g PSI 2, 3, 4, and 5. 91 Addit 100a1correspondggqe was transmitt \ 1 May 9, 1984, \ March 7,16,1984LO)May1,1984(11) 1985,(10) M July 1, 1985,(15) 1985.
) July 2,1985,4December 13,19g}9g) January September 18, 1985,(14)ay 7, 1985, and September 30, Subsequent to completion of the reviev v relief requests in Supplemental Safety Evaluation Report (SSER) 5 W Ncensee submitted two revised PSI relief requests on April 1,1986.(16)
By letter dated May 22,1986,(17) the licensee submitted hn inservice inspection program for the first 10-year inspection interval for Millstone
- 3. A ad equest was submitted on liarch 18, 1987,18)ditionalfirst-intervalreli{9 and revised August 5, 1988. This relief reque ated by the NRC staff in a letter dated September 21,1988.l'q)wasevalu- The NRC staff requested additional informat the ISI program on August 16,1988.jgg)neededtocompletethereviewof t'2 The additional in requested was provided in a letter dated October 19,1988,yL'gation I which included Revision 1 to the ISI program as an attachment. In this submittal, the licensee added five new relief requests, revised three previously submitted relief requests, and withdrew one relief request.
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- 2. EVAL.UATION OF INSERVICE INSPECTION PLAN <
2.1 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 ISI activi-
, ties. -The rest of this section describes the submittals reviewed, the basic requirements of the effective Code edition and the appropriate preservice inspection commitments. The results of the review are then described. Finally, conclusions and recommendations are given.
2.2 Documents Evaluated A chronology-of documents on' Millstone Unit 3.is given in Section 1 of this report. These documents that impact this evaluation are (1) the latest revision of the ISI program, (2) the SER and supplements, and (3) previous submittals concerning the PSI program, h 2.3 Summary of Reauirements 5
. The requirements eq which this review is focused include the ,
following: l (1) Comoliance with Aeolicable 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 Millstone Unit 3 has written the program to the 1983 Edition with addenda through the Summer'of 1983. These Coda requirements are summarized in Section 2.3.1 and detailed Code requirements are given in Appendix , 4 A. The 1974 Edition, Summer 1975 Addenda is-to be used for selecting Class 2 welds in systems providing the functions of-residual heat , removal, emergency core cooling, and containment heat- removal. This
.is a requirement of 10 CFR 50.55a(b)(2)(iv)(A).
(2) Acceptability of the Examination Samole. Inservice volumetric, surface, and visual examinations shall be performed on AP1E Code Class 1, 2, and 3 components and their supports using sampling schedules described in Section XI of the ASME Code and 10 CFR-50.55a(b. Code requ)irements given in Appendix A. Sample size designations are identif (3) Exclusion Criter_ta. The criteria used to' exclude components from examination shall be consistent with.!WB-1220, IWC-1220, IWD 1220,
- and'10CFR50.55a(b).
- (4)--PSICommitments. The Inservice. Inspection Program should address all license conditions, qualified acceptance conditions, and other. ISI-related-commitments prescribed-by the Safety Evaluation Report, its ,
. supplements, or by NUREG requirements.
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.- . _ . . - . _ , _ _ . _ . _ - . _ _ _ _ . _ _ _ _ _ - _ _ _ _ ~._ . _ _ ._. _ . , .o .. 8 2.3.1 Code Requirements I The following requirements are summarized from the 1983 Edition of
, Section XI with Addenda through Summer 1983. Many requirements call for
, inspection of all areas while other requirements are based on criteria such 4 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.
P L 2.3.1.1 Class 1 ReoviremeqLt. The following Class 1 components are to be examined.in the first interval in accordance with Table 1WB-25001: i; (1) Pressure Retaining Welds in the Reactor Vessel
-(2) Pressure Retaining Welds in Vessels Other than Reactor Vessels (3) Full-Penetration Welds of Nozzles in Vessels (Inspection-Program B) >
(4) Pressure Retaining Partial Penetration Welds in Vessels (5) Pressure Retaining Dissimilar Metal W( Us (6) Pressure Retaining Bolting, Greater than 2 in. Diameter . (7): Pressure Retaining Bolting, 2-in. and less in Diameter
-(8) Integral Attachments for Vessels
-(9)_ Pressure Retaining Welds in Piping- l (10) Integral Attachments for Piping, Pumps, and Valves ..
.(11) Pump Casings and Valve Bodies, including Pressure Retaining Welds c (12) Interior of Reactor Vessel, including Integrally. Welded Core i Support Structures, Interior Attachments, and Removable Core Support-Structures (13)) Pressure Retaining Welds in Control Rod Housings [
(14);All'PressureRetaining' Components-PressureTests (15)SteamGeneratorTubing. L 4
- =- . . . . . - ... . .-.=-.-._.._-.--.--.--.a.a- .. , , .
o . 2.3.1.2 Class 2 Reauireminit.n 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 G'1ater than 2 in. Diameter (5) Pressure Retaining Welds in Piping (6) Pressure Retaining Welds in Pumps and Valves (7) All Fmscure Retaining Components - Pressure Tests. 2.3.1.3 Class 3 Reauirements. The following Class 3 reactor-connected and associated systems are to be examined in the first interval in accordance with Table IWD-2500-1: (1) Systems in Support of Reactor Shutdown function (2) Systems in Support of Emergency Core Cooling (ECC), Containment Heat Removal CHR , Atmosphere Cleanup, and Reactor Residual Heat Removal RHR (3) Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool. 2.3.1.4 Component Suonorts. The following component supports are to be examined -in the first interval in accordance with Table IWF-2500-1: (1) Plate and Shell Type Supports (2) Linear Type Supports - (3) Component Standard Supports. 2.3.2 Preservice Inspection Commitments Safety Evaluation Outstanding item 12 required that a sample of welds . in RHR, ECC, and CHR piping with a wall thickness less than 1/2 inch be volumetrically examined. Safety Evaluation Confirmatory Item 7 required augmented ISI of welds in containment penetrations, or the break exclusion area. 5
.c . !
Safety Evaluation Confirmatory Item 19 required demonstration of the adequacy of ultrasonic techniques used for examination of thick-wall centrifuga11y cast stainless steel piping. SSER 3 under this confirmatory ; item required selection of welds for Inservice Inspection such that those l welds inspected have the best acoustic properties among all welds of this type. 2.4 Como11ance with Reouirements 2.4.I' Applicable Code Edition NNEco has developed and-implemented an Inservice Inspection Program _ -using the 1983 Edi%n through Summer 1983 Addenda of Section XI,- ASME Code subject to the liMcations and modifications. listed in Section 50.55a(b) of 10 CFR Part 50. Tie latest edition and addenda incorporated in 50.55a(b).
-on the date 12 months before the date of issuance'of the operating license on January 31,-1986, was the 1980 Edition through Winter 1981 Addenda. The licensee notified NRC of its 1 aletterdatedApril:27,-1986.9)tgttoupdatetothelater-Codeeditionin
\31 Underthe-termsof50.55a(g)(4)(iv),
ISI examinations may meet the requirements set forth in subsequent editions and addenda incorporated by reference in parag nph 50.55a(b) subject to ' Commission approval. The 1983 Edition throu incorporated in' Federal' Register Notice Vol.gh 50, No. Summer 1983 187, dated Addenda was so September 26,.1985. for MillstoneThe Unit'3 NRC in a staff reviewed memorandum andAugust dated accepted use of this / Q10,1987.tgtedition 2.4.2 Code Requirements
. testing) The first interval is contained program in Lthe of~record.(exclusive submittal dated October of pump gg19,1988.\'g) valve The program, including its attachments, was re/iewed and-dete* mined e to be acceptable. We.have determined the following:
The Inservice Inspection Program for Millstone Unit 3 identifies ! appropriate Code classes for.each component of the power plant. -
- The design of the Code Class I components of the reactor coolant pressure boundary in Millstone 3. incorporates provisions for access for inservice examination in accordance with Section XI of the ASME Code.
Some design and access provisions could not be met and specific' requests ! for relief were submitted.and are evaluated in Section:3 of this report, ,
'SAIC's technical evaluation has~ not-identified any practical method by_
which Millstone 3 can meet all the specific inservice inspection requirements of. Section XI of the ASME Code. Thus, relief has been recommended where appropriate. 1 l l 6.
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- Q Examination instructions and procedures, including diagrams or system drawings identifying the extent of areas of components subject to examina-tion, have been prepared. They are listed in the ISI program component tables, cross-referenced to weld and hanger isometrics and component identification drawings, and marked on pipe and instrument drawings I (P& ids). I E%minations and tests are to be performed and evaluated and the results recorded providing a basis for evaluation and comparison with the results of subsequent examinations as required by Code. !
Visual, surface, and volumetric examinations are defined as specified ' by Code. Exemptions from examination meet Code specifications IWB-1220, IWC-1220, and IWD-1220. Replacements are performed to IWA-7000. The licensee stated in his letter dated October 19, 1988,(22) that the system pressure test program for Millstone 3 is in development and will be submitted to_the NRC before the next refueling outage. Therefore, no conclusion can be made concerning the Code compliance of the pressure testing program at Millstone 3 as of the date of this report. The licensee states in Section 1.4 of the ISI plan that examination scheduling will comply eith IWA-2400, Program B. The examination listings provided in Section 5 of the ISI plan do not provide a breakdown by period. Therefore, no conclusion can be made concerning Code compliance of the examination scheduling program at Millstone 3 as of the date of this report. ' Examination requirements, methods, acceptance standards, inspection intervals, deferrals,. the selection of items to be examined, the number of items to be examined, and the examination fraction of each weld inspected meet the' requirements of Tables IWB-2500-1, IWC-2500-1, IWD 2500-1, and IWF-2500-2, or relief from Code as noted below has been requested and acceptable alternatives provided. For licensees applying Editions through and including the 1983-Edition, Winter 1983 Addenda, 10 CFR 50.55a(b)(2)(iv)(A) requires exami-nation of Class 2 piping welds in Residual Heat Removal (RHR) Sy:tems. Emergency Core Cooling (ECC) Systems, and Containment Heat Removal (CHR) Systems in accordance with the requiremets of paragraph IWC-1220, Table IWC-2520 Categories C-F and C-G, and partgraph IWC-2411 in the 1974 Edition and Addenda through the Summer 1975 Addenda of Section XI of the ASME Code. The licensee is not in compliance with this requirement. Rather, the licensee is performing examination of all Class 2 piping welds (including RHR, ECC, and CHR systems) in accordance with Code Case N-408. Use of Code Case N-408 results in a reduced number of welds inspected as compared with the 1974 Summer 1975 Code. In order to bring examination of RHR, ECC, and CHR systems into compliance, the licensee should do one of the following: 7
y , (1) use the 1974, Summer 1975 Code Edition for selection of welds 1 examined in Class 2 RHR. ECC, and CHR systems as required by 10 CFR 50.55a(b)(2)(iv)(A), or (2) per 10 CFR 50.55a(g)(4)(iv), the licensee should request permission to update inspection of all Class 2 piping welds to the 1983 Edition, Winter 1985 Addenda, or the 198.6 Edition. In accordance with the latest update of 10 CFR 50.55a(b)(2)(iv)(A) in Federal Register Volume 5?, No. 87, p.16053, dated May 5, 1988, licensees applying these later Code Editions need not use the 1974 Summer 1975 Code for examination of RHR, ECC, and CHR-Class 2 piping welds. 2.4.3 License Conditions There are no license conditions related to ISI. However, there were one Outstanding Item and two Confirmatory Items in the Safety Evaluation - Report related to ISI that have bean resolved during the review of the PSI program.
. Under Outstanding Item 12 in the SER,(5) the staff's main concerns were the lack of volumetric examinations planned on RHR, ECC, and CHR
- piping having a wall thickness of 1/2-inch or less and th<s absence of any volumetric examinations at all on'the 4-inch nominal pipe :i:s (NPS) HPSI
.systeb) 1984.
The licensee responded to this Outstanding Item on December 13, - RHR, ECC, and CHR systems contain approximately 1200 circumferential-welds, of which about 200 have wall' thickness of 1/2-inch or greater and were subject to both volumetric and surface examinations under ASME Code Section XI. The remaining 1000 welds have wall thickness less than 1/2 inch sd-were subject to surface examination only, according to the ; applicable Code. ,However, the licensee agreed to perform volumetric ' examinations on a 7.5 percent sample of these welds distributed _among-these three safety systems. .The inspection did not include open-ended.
- dried-out, and vented portions.of the quench spray system and recircu-
' lation spray system.
- The licensee also agreed to perform volumetric and surface examination on a 7.5 percent sample of those portions of the NPSI system-that are 4 inch NPS and a surface examination on a 7.5 percent sample of-
. those-portions of this system that are 3-inch NPS. These-examinations are ,
in excess.of the requirements of_the.ASME-Code. In addition, because of the difficulties normally experienced when performing ultrasonic examination.on thin-walled material, the -licensee r utilizing 700 longitudinal waves for these inspections. In stated SSER 2,(5 that it-will develop a the staff found-these commitments acceptable and considered the open item resolved. . l' 8
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t s o i Under Confirmato~ry item 7, the staff required augmented inservice inspection for those portions of pioing within the break exclusion region. The licensee commit )to perform tiese inspections in a letter dated September 30, 198;. .- Confirpatory item 19 required demonstration of ultrasonic excmina-tion techniques used on thick-wall centrifuDally cast stainless steel piping. Site demonstrations were performed flovember 19, 1984, and June 6, 1985. The NRC requested additional information to complete its revie o March 7,1985(12The July 1, 1985, licenseo respon i and Jaly 2, 1985. ' 9q)by letters dated May 7,1985,l I)n The NRC reviewed a exaininntion techniques and calibration blocks in SSER 3.(5)nd approved the In addition, this supplement required selection of welds for inservice inspection such l 4= that those welds inspected have the best acoustical properties among all welds of this type. 2.5 f._onclusions and Recommendat togi Based on the foregoing, we have determine? that the ISI program prcposed by Northeast Hutlear Energy Company for Millstone Unit 3 for the first 120-month inspection irterval meets the applicabTe Code with three exceptions detailed below. There are two requirements for which the licensee has not provided sufficient informatinn to perform a complete review. First, the program for hydrostatic testing of Class 1, 2, and 3 pressure boundaries is in I development, and the licensee has committed to provfde doc umentation by the start of the next refueling outage. Second, insufficient information has been provided in the 151 plan to determine the method of compliance with examinatien scheduling requirements of IWB-2412-1 and IWC-2412-1. Thirdly, the licenset. is not in ;ompliance with 10 CFR 50.55a(b)(2) (iv)(A), examination of Class 2 piping welds in RHR, ECC, and CHR welds in accordance with the 1974 Summer 1975 Code Edition. The licensee should do { one of the following: ; (1) use the 1974 Summer 1975 Code Edition for selection of welds , examined in Class 2 RHR, ECC, and CHR systems as required by 1 10 CFR 50.55a(b)(2)(iv)(A) (2) per 10 CFR 50.55a(g)(4)(iv), the licensee should request permission to update examination of r:11 Class 2 piping welds to the 1983 Edition, Winter 1985 Addenda, or the 1986 Edition. Therefore, Millstone 3 meets the requirements of the 1983 Edition through Summer 1983 Addenda of Section XI, except that a conclusion cannot be made concerning compliance with hydrostatic testing and examination scheduling requirements at this time, and that examination of Class 2 RHR, ECC, and CHR systems are not currently in compliance. , Specific requests for relief are addressed in the following section. 9 l
i se o 3.- REQUESTS FOR RELIEF FROM ASME CODE SECTION XI EXAMINATION REQUIREMENTS i The licensee requested relief from specific inservice requirements ! forMf}gtoneUnit3-intheInserviceIns)ectfonprogrqgubmittedMay22, 1986,V / as revised by letter dated Octoser 29, 1988.l'21 , Eleven relieY ' requests have been identified that require review. The following sections evaluate these pending relief requests. Where relief is recommended in the following report section,-it is done so on the assumption that the proposed alternative examination and all applicable Code examinations for which relief has not been requested will-be performed on the subject component. Where additional examinations; beyond proposed alternatives and Code requirements are deemed necessary,- these are included as conditions for recommending relief.-
}
The material included in the paragraphs titled Code _ Relief Reauest, ; Prooosed Alternative Examination, and Licensee's Basis for Reauts_tjng i Relief.is quoted directly from the relief request except for minor editorial changes such as removing references to figures and tables not. < included in this report. h.
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3.1 CLASS 1 COMPONENTS 3.1.1 Reactor Vessel 3.1.1.1 Relief Recuest IR-1. Pressure Retainina Welds in the Reactor - Pressure Vessel. Cateaory B-A. Items B1.12. Bl.21. and__Bl.22 Code Recuirement Item Bl.12 All pressure-retaining longitudinal welds in the beltline region of.the rnctor pressure vessel shall be volumet-rically examined in accordance with Figure IWB-2500-2 over essentially 100% of their lengths during th first inspection interval. Examinations may be performed at cr near the end of the interval. 11ges B1.21 and 81.22 All pres:ure-retaining circumferential and meridional head. welds in t'e reactor vessel bottom
- head shall be volumetrically examined in accordance with Figure IWB-2500 3 over the necessible portion up to 100% of the weld length during the first inspection interval. The bottom head wolds may be examined at or near the end of the intervel.
Code Relief Reauest Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from - perf_orming the-inservice volumetric examination of the inaccessible portion of the subject vessel weld;. Prooosed Alternative Examination A.- The subject welds will receive a volumetric exan. .< ion on the accessible portions 'In accordance with Section XI .,8-2500-1). B. An inservice hydrostatic test will be conducted on the Class 1 pressure boundary of which these welds are part tner aof (IWB-2500-1). C. Inservice system leakage tests will be performed per Category B-P,'IWB-2500-1. 11
>: s-Licensee's Basis for Recuestino Relief s
Geometric configuration and permanent obstructions affected the' subject welds frF performing a 100% volumetric examination. 3 The subject welds received both volumetric examination by radiography and surface examination during fabrication, in accor-dance -ith ASME Section III requirements which provide adequate assus > of the structural integrity of the welds. Evaluation The licensee has provided as an attachment to relief reque:;t IR-1 a matrix and drawings detailing the limitaticns encountered and estimating the percer.tage of examinations that can be completed for each weld in the reactor pressure vessel. For the longitudinal welds, the licensee has given the limitation as nozzle geometry in the upper shell. There are no limitations to examination of longitudinal welds in the inter-mediate or lower shell, which are adjacent to the core and subject to radiation embrittlement. Since Millstone 3 is a four-loop Westinghouse PWR, there are eight nozzles in the upper shell. The -licensee has estimated th.t 37% of longitudinal Weld 6 and 47% of lorgitudinal Welds 7 and 8 receive meaningful four-directional examination. The propose 1 alternative examination.of an ultrasonic examination on the access.ble portion will provide adequate assurance of structural integrity, along witn the Code-required
-. hydrostatic and system pressure tests.
For the lower head welds, the licensee has e:timated 95% coverage of the Torus-to-Dollar pl ;te weld,- 98% coverage of three of the meridional welds, and 93't : overage of the fourth meridional
- weld using manual technique . T:. 1 mitations-encountered are caused by instrument tubes and we,d configuration. The Code acknowledges that accessibility may be limited with respect-to w volumetric examination of head welds. -It is concluded that the -
proposed manual examination provides essentially 100% coverage, and that Code requirements are being met. Thereforc, relief is r.ot required for the reactor vessel bottom head welds. Conclusions and Recommendations Based on the above evaluation, it is concluded that 12
._ ..,__ ....~ .._ . __ . _ _ . _ . _ . . _ - _ . _ . - . . _ _ . _ _ . _ . ,,
; f 3; * ' ,
- .. t t
- l im -- -('a); For the, reactor vessel upper -shell longitudinal wc; F~ '-
the: Code requirements are impractical'.: It is furt :
-- concluded that the-proposed ultrasonic examination '
, ~ maximum extent-practical,:along with the Code requ-hydrostatic and system pressure-tests,-:will providt
. necessary assurance of structural reliability. 'Th:
fore, relief is' recommended. as requested. (b) For the reactor vessel bottom head welds, the prop examination meets the intent of-the-Code requireme-! W Therefore, relief is not required for these welds. .
~ .;
W ;'
.-References
' = Refer ( tees 17 and 22'.. l t
+ t A hf s
t
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. 2
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f-
.1, Weld No. 101-101 Head to Flance Weld Access to this weld is limited to essentially one side only due-to the forged flange configuration. Additional limita-tions from the top side of the weld are due to permanently attached head lifting lugs. Required volume not examinable:
-38%
- 2. Weld No. 103-101 Circumferential Head Weld Permanently attached head lifting lugs prevent volumetric -
- examination of -7% of the' WRV.
3.- Weld No. - 101-104D Meridional Head Weld A 2.7-inch-diameter repair area (surface concavity) on the " weld-centerline prohibited sufficient coverage of_ the WRV in 3 that area. Required volume not examinable: -2% !
, The subject welds received both volumetric examination by <
radiography and surface examinations during fabricat6:.n in accor-o dance with ASME Section1111 requirements which proviou adequate
- assurance of the struc'tural integrity of the welds. - ;
Evaluttian i For -the head circumferential and meridional welds, a small l percentage of.the Code-required-examination is rendered impractical
- - 'by ;ifting' lugs and a small repairf area. The Code acknowledges that accessibility-may be-limited with-respect to volumetric
- examination of head welds. Since the lugs and small repair area, are the only obstructions to1100% examination, the intent of the =
Code of examining essentially 100% of the weld has been fulfilled. For the reactor' vessel head to-flange weld,'significant obstructions exist due to configuration' and; lifting lugs. _ The
-licensee has estimated that_62% of'the Code-required examination '
can be completed. The licensee'has not 9rovided an estimate of the percentage of Code-required surface exan, ation-of this weld that .
- can be completed. However, the limited S 4 +lon'XI ultrasonic
- examination, along with the Code-required irface and hydrostatic and system pressure tests, will, provide-ne ssary assurance of
- , structural reliability.
l i-
-15
--[. k) -
Conclusions and Recommendations Based on the above evaluation, it is concluded that (a) For.the reactor vessel head circumferential and meridional welds, the proposed Examination meets the intent of the Code requirements. Therefore, relief is not required for these welds. (b) For the reactor vessel head to-flange weld, the Code requirements are impractical. It is further concludeo that the proposed ultrasonic examination to the maximum extent practical, along with-the Code-required surface examination to the extent prac'.ical and hydrostatic and system pressure tests, will provide necessary assurance of structural reliability. Therefore, relief is recommended as requested. References References 17 and 22. L 16
.i J3.1.1.3 Relief Reauest IR 1. Reactor Vessel Nozzle-to-Vessel Welds ,
and Nozzle inside Radius Sections. Cateoory B-D. Items 83.90 $ and B3.100; , fade Reouirement All nozzle to vessel welds and inside radius sections in the rea tor vessel-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 penetra-
-tion welds'to vessel =shell (or head)Jand integrally cast nozzles, i
~ but exclude 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.
~ _
If examinations are conducted from inside the component andJthe'. nozzle-weld .is axamined by straight beam: ultrasonic- method. from the nozzle bore,1the remaining examinations required to be conducted
=from the shell may be performed at or near the end of each i
# ' inspection. interval.. 3 i
i LCode Rel'ief Reouest 1
> Pursuant-tot 10 CFR 50.55a(g)(5)(iii),-relief is requested from performing thexinservir.e- volumetric examination of thet inaccessible- '
. .. portioniof-the subject-vessel welds.
l
~, ,
i Proposed Alternative Examination. o 1 f A. :The subject welds will receive-a volumetric examination on the
~
. i
,l accessible. portions. in accordance with Section XI (IWB-2500 -
w . 1). s B. -An inservise hydrosteticttest-willbeconductedontheClass.lf ; pressure boundary of which these welds are a part thereof i (IWB-2500-1). 'r
-C. Inservice system leakage tests will be performed per Category j
'B-P, IWB-2500-1.- <
o ,
-t
\
?- ' Licensee's Basis for Raouestin'a Relief m - D Geometric. configuration and permanent obstructions affected
'~ ,
the subject welds from performing a 100% volumatric examination. : l[ , ! i e y o
< ,,e. + - + c - s a -s . < . . .~,s.. . - - -
. o The subject welds received both volumetric examination by radiography and surface examinations during fabrication, in accordance with ASME Section III requirements which provide adequate assurance of the structural integrity of the welds. Evaluati2D for the nozzle-to-vessel welos, the licensee has estimated that 30% of the required volume for the outlet nozzles and 15% of the required volume for the inlet nozzles is r.ot examinable. The basis given for the impracticality is nozzle radius configuration. A minimum of 70% of the code-required volume will be examined. This limited examination, along with hydrostatic and system pressure tests will provide necessary assurance of structural reliability. For the nozzle inside radius examination, the licensee has committed in relief request IR-1 to attempt to perform the exami-nation on a best-effort basis, and if the examination is found to be imn-sctical, to request relief at that time. TFerefore, relief shot .d se delayed at this time pending the licensee's further review of this examination. Conclusic9s and' Recommendations
^
Based on the above evaluation, it is concluded that (a) For the nozzle to-vessel weld discussed above, the Code requirements are impractical. It is further concluded that the proposed alternative examination will provide adequate assurance of structural reliability. Therefore, relief is recommended as requested. (b) For the nozzle inside radius examination discussed above, there is not sufficient justification for declaring the Code requirements impractical at thic time. The licensee should attempt-the examination and request relief at that time, if required. References References 17 and 22, 18
- .~ ., - .- - .- .- . - . . . . . . -- . . . . - .
s: . .~ 13.1.21 Vessels Other Than Reactor Vessel w
.- .- . I
- 3.1;2.1 Relief Reouest-IR-3. Pressure Retainino Welds in the Pressurizer, j Cateoory'B-B; Item B2.11 t Code Reauirement
- 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.
l Code' Relief Reauest-Pursuant to 10 CFR 50.55a(g)(5)(iii).. relief is requested from : performing the inservice volumetric examination of the' inaccessible
- portions of_the subject vessel welds, s
Proposed' Alternative Examination A. ?The subject welds will receive a volumetric. examination on the -
-accessible areasiin accordance with Section XI (IWB-2500-1).-
B.. ..A Section III hydrostatic ~ test will be conducted on the Class
.I-pressure boundary of-which these welds are a part thereof (IWB-2500-1).-
C.- Inservice system leakageLtests will be performed per Category B-P,"IWB-2500-1. n; Licensee's Basis for Reauestino Relief-Geometric configuration and'permaner.t; obstructions limited the , volumetric examination of the following listed welds. Examination data sheets and limitation sketches depict the affected areas.
= Relief is~therefore requested on complying with the 100% WRV i coverage.of the welds. %.= Pressurizer-
- 1. 03-007-SW-J: Shell-to Upper: Head Weld Permanently installed ;nsulation support ring obstructed .':
part of the requirc anning a,n. Required volume not - -
-examinable: -9%
L
- 19 i
, s ',N
..; &~,,
. o l
- 2. 03-007-SW-F: Shell-to-Lower-Head Weld Permanent obstructions (alignment target pads and instru-mentation lines) and the geometric configuration--weld transition between plate thickness variations prohibited complete coverage. Required volume not examinable: -30%
Evaluation Geometric configuration and permanent obstructic..s prevent 100% volumetric examination of the subject welds. The licensee has provided percentages of examinations rendered impractical. Exami-nation data sheets and sketches have been provided that detail the impracticality of performing :he required examinations. In all cases, at least 70% of the Code-required volume will be examined. This examination, to the maxi'aum extent practical, along with the Code-required hydrostatic ant system pressure tests, will provide necessary assurance of structural reliability. Conclusions and Recommendations Based on the above evaluation, it is concluded that for the welds d' : cussed abr a. th* Code "w;uirements are impractical . It is ftr ~ concludel at thi proposed alternative examination, alang .a.a the Code-required hydrostatic and system pressure tests, will pr vida necessary assurance of structural reliability. Refereiset References 17 and 22. 20
= _ - - _ _ _ _ _ _ _
i y e 5 4
~3f1'.2.2 Relief Renuest-IR-8I Full: Penetration Nozzle-to-Vessel Welds in the Pressurizer and Steam Generators.--Cateaory B-D.-Items B3.110.
4 and B3 11Q-' Code Reauirement All nozzle-to-vessel welds in the primary side of- the steam-
- generator and pressurizer shall be volumetrically examined in
- accordance with' Figures IWB-2500-7(a)-through (d) during the first '
l interval of operation. Examinations-shall includa nozzles with' full penetration welds to vessel shell' (or hea's).and integrally cast nozzles,- but exclude' manways- and handho'es either yelded 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. Code Relief Reouest
' Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from-performing the inservice volumetric examination on the' inaccessible portions of'the nozzle-to-shell welds of the steam generator and -
pressurizer. . Prooosed A1_t.ernative examination-
- 1. Volumetric = examination on the accessible portions will be:
performed as required by ASME-Section XI (IWB-2500). Any advances in UT technology. will be. evaluated to -determine its p application for achievir.g maximum volume coverage-and results.
- 2. A-system hydrostatic test will be performed once each '
inspection interval as required by Table _IWB-2500-1, Category B-P. L 3. An' inservice system J1eakage test will. be performed once each refueling outage per Category B-P, IWB-2500-1. 1 Licensee's ~ Basis for Reouestino Relief Geometric: configuration of the below listed nozzle-to-shell. -
.weldsLand their close proximity to one another limits the volume that can be' examined.- Scanning is limited to one side only with a 1/2-V technique. Axial' scan is restricted due to the close- ,
proximity of the welds to each othsr.
.21 L
u .- .. _
l Pressurizer
- 1. 03-007-SW A 4. 03-007-SW-D
- 2. 03-007-SW-B 5. 03-007-SW-E (Spray Nozzle)
- 3. 03-007-SW-C 6. 03-007-SW-S (Surge Nozzle)
Approximately 80% of the weld required volume (WRV) received an examination from one direction. Approximately 30% of the WRV was covered in two directions. Steam Generators Coverage is from both sides of weld with 1/2-V technique. Restriction on axial scan due to the steam generator supports integral extensions. 03-003-SW-V Inlet 03-005-SW-V Inlet 03-003-SW-LL Outlet 03-005-SW-LL Outlet 03-004-SW-V Inlet 03-006-SW-V Inlet I 03-004-SW-LL Outlet 03-006-SW-LL Outlet Required volume not examinable: -10% Evaluation It is agreed that the limitations noted by the licensee could limit the examinations. performed on these welds. Sketches have been provided which detail the impracticality of performing the required examinat . As indicated in a letter submitted December 1,1988,)sgi the subject nozzles have been analyzed for thermal fatigue mechanisms. The licensee has evaluated all available ultrasonic testing techniques and has found them to be impractical for performing these examinations. The licensee has additionally agreed to keep up with and use the most up-to-date ultrar.onic technology available for these examinations. The proposed examination to the maximum extent practical, along with the Code-required hydrostatic and system pressure tests, provide necessary assurance of structural reliability for this interval. 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 proposed alternative examination, along with the Code-required hydrostttic and system pressure tests, will provide necessary assurance of structural reliability. Therefore, relief is recommended as requested. References References 17, 22, and 25. ) l 22
r , -. Al ( t 13.1.3 _ Piping: Pressure' Boundary: 3.1=.3.1 Relief Recuest IR 9. Pressure Retainino-Welds and Dissimilar Metal-
-Welds -in Class 1- Pioina. Cateoories B-J and B-F. Items 89.11 and-B5.10
' Code Reauirements item R9.11; For circumferential. welds and' intersecting longitudinal welds .in pipe of nominal pipe: size 4 in . and greater, ,
. surface-plus volumetric examinations shall be performed in accor- '
. dance with Figure IWB-2500-8 over essentially 100% of the weld'
. length during each-inspection interval. The examinations shall
- include-the following:
, (a)' Alliterminal inds in each pipe or ~ branch run connected to vessels.
-(b): Al_1 terminal ends and joints in each )ipe or branch run
, connected to other components where tie stress levels exceed the following limits under loads associated with specific seismic events and operational ~ conditions.
'(1): primary plusisecondary stress intensity of 2.4S. p for ferritic steel and austenitic steel,;and
;(2):-cumulative usage factorLU ofLO.4, (c) All dissimilar metal welds- between combinitions' of -c (a carbo ~n or: low allow steels' to- high alloy steels;
-(b 7 carbon or low alloy steels to high nickel alloys; r.ad (c high alloyisteels to high . nickel alloys, m
(d)EAdditional piping' welds so- that the total number of circum-ferentialibutt welds- selected for examination. equals:25% ofi o
. the- circumferential butt' welds ~ in theireactoricoolant: piping -
system. ;This: total;does not; include' welds excluded by
~
.IWB 1220 cThese" additional: welds may. be located in one loop -
4(one' loop is currently defined for both PWR and BWR plants in the 1977 Edition).
, For welds in carbon or_ low alloy-' steels,> only those welds
.show i ng reportable preservice transverse indications need be.
cexamined for. transverse reflectors. , i Q Item B5.10'. 'All, nozzle-to-safelend butt-:weldst in nominal pipe . n
- size 4 in.nand greater in the' reactor vessel shall be' surface and j
, volumetrically, examined in accordance with Figure IWB-2500-8 during , 1 the first1 inspection interval. 'The examinations may:be performed
, 1 23 w
- l. s , , :. s
e a 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. Code Relief Reouest Pursuant to 10CFR50.55a(g)(5)(iii), relief is requested from performing the inservice surface examination of the nozzle-to-safe end and safe-end to pipe butt welds greater than 4-inch NPS on the reactor vessel. Proposed Alternetive Examination (a) The subject welds will receive a full volume volumetric examination from the ID surface in accordance with ASME Section XI and Section IWA-2240. This will include a 45-degree refracted longitudinal wave examination for the bottom 2/3 volume (from the ID surface). The near surface
.(ID) and upper 1/3 volume will be examined with a 65-degree refracted longitudinal wave examination.-
(b) The OD surfaces.shall be visually examined during the reactor-coolant system hydrostatic test, in accordance with Category B-P, Table IWB-2500-1. (c) Inservice system leakage tests will be performed per Category B-P, IWB 2500-1. Licensee's Bases fur Reouestina Relief The Millstone Unit 3 reactor vesssi is a four-loop PWR. There are eight' nozzle-to-safe ends and eight safe-end to pipe butt welds for. Items B5.10 and 89.11 in the inservice inspection program. The purpose of this relief is to perform a full volumetric ultrasonic examination in lieu of a surface examination in order to reduce exposure. The ultrasonic examination of these welds will be performed from the 10 surface using the remote immersion method. NNECO believes that any failure of the weld will be induced from the ID l surface and that the ultrasonic examination from this surface shall be sufficient to detect any indications. 24 1
_ _ _. - . . . _ . . _ ._ __ _. _.. .- _. _ _ . ~ . ._ , t ->
- NNEr0 believes that the proposed ultrasonic c:%e nation is adequate sto. detect flaws in the listed ' items. NNECO >elieves that u
the ultrasonic examination will assist in reducing th rexposure rates, without . losing the ability to detect flaws in ;he reactor vessel nozzle-to-safe .end and safe-end to pipe welds. Evaluation-The: licensee has proposed to eliminate the' surface examination but expand the required volumetric examination to cover 100Y. af the : weld. This expanded-volume would cover the cross-section bounded i by ACFEDB shown in Figure IWB-2500-8 of-the 1983' Edition, Summer - 1983 Addenda, and the examination would be_ conducted from the' -> inside diameter. This alternative volumetric examination from the 70 inside diameter is not, however, sufficient- in itself to-provide the de will l' gree e detected. of assurance.necessary The increase in safety that outside achieveddiameter (00) flaws by. performing the required surface examination,-or an equivalent alternative, outweighs the inpracticalities cited by the licensee. The licensee should either (1) demonstrate by the next refueling outage that OD flaws can be detected using ths proposed alternative volumetric ' examination or (2) perform ~the Lurface-examination as required during the next refueling outage.. If the; licensee chooses the first option, he.should clearly demonstrate that-the actual-procedure'and instrument that would be used.in the examinationiwould detect OD flaws in the existing configuration. Reliefirom the surface examination should be granted for the subject welds only if-either of the conditions above is met. L Conclusions- and Recommendations - . Based onLthe above evaluation, it is concluded that interim. relief- should!be granted but only if-the licensee meets either of: the-following conditions: a (a) ' Demonstrates hy.the next' refueling outage that the actual
- proceduretand instrument used in:the propnsed. examination woull 6etect OD flaws -in the existing configuration. ,
(b) Lrefueling' outage. Performs the surface examination requirement durin i References' Refe ence-22. , t 25 4
.v-- ,e. + = v , , -.+ > > ~ + -
en se e
.y ,
-- 3.1.3;2 Relief Reouest IR-10. Centrifuoally Cast Stainless Steel'(CCSS)
~
Comoonent-to Fittina Welds. Cateoory B-J. Item B9.11 l Code Recu'irement LFor circumferential welds and intersecting 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 over essentially-100% of the weld length-during each inspection interval. The examinations shall include the following:
s (a)? - All terminal- ends in each pipe or branch run-connected -to vessels. (b) Alll terminal ends and joints in ear" nipe or branch run
; connected -to other components wher. Sne . 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 ; E(2)-icumulative-usage factor U of 0.4. , -(c): All dissimilar metal welds betweenicombinations of (a) ~ carbon or-low 'allowfsteels to high al'sy steels; (b) fearbon orilow alloy steels-to high nickel alloys; and (c) high alloy' steels to high nickel: alloys. (d): Additional; piping weldsEso :that the: total : number of circum-
'ferential butt welds selected 1for examination equals 25%-of
, the' circumferential butt welds 'in .the reactor coolant 1 piping. ,
. system.E LThis totalidoes not include welds excluded by . !
- IWB 1220.fsThese additional _ welds may be located in lone_ loop
- (one loop is currently definedLfor both PWR and BWR plants:in the1977_ Edition).J For welds in carbon or low: alloy steels, only those welds
- showing reportable preservice transverse indications need be examined foritransverse1 reflectors. ,
' Code Relief Reouest n
Pursuant.to 10CFR50.55(a)(g)(5)(lii), relief is requested from1 ' performing the' inservice volumetric examination of the. inaccessible - portions of Welds'LP4-EC-2-SW B, RCS-20-FW-37, RCS-20-FW;38, and RCS-20-FW-39.
.I n
f a 'g 26 ,
.- , ..,c - . - , . .
J-o . . , . . ~ . - , - ,, _, , ~. 4 -- -- -- --
l L Proposed Alternative Examination (a) Volumetric and surface examinations on the accessible portions will be performed as required by ASME Saction XI, IWB-2500. (b)- An inservice hydrostatic test will be conducted on the Class 1 pressure boundary, of which these welds are a part thereof, per IWB-2500-1 requirements. (c) Inservice system leakage tests were performed per Category B-P, IWB-2500-1. Licensee's Basis for Reouestina Relief Geontric configuration or permanent obstructions prohibit 100% vd umetric examination coverage of the Code required exami-natimi volume. Relief is therefore requested from performing inservice examination on the inaccessible portions of the volume required.- A 0-degree longitudinal becm examinatioa was conducted on all CCSS welds, dtrina pr"ervice inspection, to map ID geometry contours. This was dem l'1 addition to Sect on XI requirements to aid in the performance and evaluation of anr,le beam examination resul ts. Evaluation The four welds for which relief is requested are in reactor coolant loop 4 and are shown on drawing number 25212-20913. Along with Relief Request IR-10, the licensee provided a table indicating v the weld identification-numbers for the four welds for which relief f is requested, detailing the. impracticality and indicating the esti-mated percentage of the Code volumetric examination that can be completed. Beiween 75% and 93% of the Code-required volume can be examined uring a 45-degree examination angle and a 1/2 V axial and circumferential technique. The proposed limited ultrasonic examination, along with the required surface examination and the hydrostatic and system pressure tests, will provide necessary assurance of structural reliability. Conclusior,s and Recommendations Based on the above evaluation, it is concluded that the Code requirements are impractical. It is further concluded that the 27 l
. o proposed alternative examination, along with the Code required serface examination and hydrostatic and system pressure tests, will provide necessary assurance of structural reliability. Therefore, relief is recommended as requested.
Referenqek Reference 22. 1 e 1 j 28
. . c.' ,
.e.
3.1.3.3 Relief Reouest IR-11. Pressure Retainino Weld in- Class 1 Pinina; Cateoory B-J. Item B9 2 - . Code Reouirement
- For,circumferential and intersecting longitudinal welds ~in pip) of nominal pipe size 4 in, and-greater, surface plus' volu-metric 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 or branch run connected te vessels, j (b) 'All terminal ends and joints in each pipe or branch run connected to other componerts where the stress levels exceed the following limits under loads associated with specific-seismic events and operational conditions. a (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 { (1) carbon or low allow steels to high alloy steels;
..(2)' ' carbon or. low alloy- steels to high nickel, alloys; and (3) high alloy steels to high nickel alloys, t (d)=' Additional piping welds so that the'totalLnumber'of circum-ferential: butt welds selected for examination equals :25%.of-
~
the circumferential: butt welds in the reactor coolant piping 4
-system. This total does not include _ welds excluded by IWB ' t 1220.. These additional welds may.be located in:one loop (one ,
L.
. loop is currentlyfdefine'd:for both PWR and BWR plants in the M 1977 Edition)'..
. For.weids in carbon or low alloy steels,'only those welds' "
showing' reportable preservice transverse indications'need be examined for transverse reflectors. Code Relief Reouest L ,~ Pursuant to-'10 CFR 50.55a(g)(3)(iii), relief is requested from
-performing;the inservice volumetric' examination of the inaccessible-portionLof o:se 8-in. Class 1 piping weld,- SIL-6-6-SW-B.
7 3 ls
-29 i - _ . ._ _ _ _ .
4
Er130 sed Alternative Examination l' ' foe subject weld will receive both a volumetric and surface examination on the accessible portions inservice in accordance with ASME Section XI (IWB-2500-1). B. An inservice hydrostatic test will be conducted successfully on the Class 1 Preservice Boundary, of which this weld is a part thereof, per IWB-2500-1 requirements. C. Inservice System Leakage Tests will be performed per Category B-P, IWB-2500. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage and results. Licensee's Basis for Reauestina Relief Permanent structural interferences prohibit 100% volumetric examination coverage of the Code Required Volume (CRV). Relief is therefore requested from performing inservice examinations on the inaccessible portions of the volume required. The subject weld received both volumetric examination by radiography and surface examinations during fibrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject weld is provided. Evaluation
. Along with Relief Request IR-11 in the October 19,1988,(22) submittal, the licunsee provided a table which indicates the weld identification number for tne weld for which relief is requested, l
details the structural interference, and indicates the estimated percentage.of the Code volumetric examination' that can be completed. The licensee has estimated that 90.5% of ~the Code-required volume can be examined using 45-degree examination angle with the 3/2 Vee shear technique. The proposed limited ultrasonic examination, along with the required surface examination to the i maximum extent practical and the hydrostatic and system pressure tests, will provide necessary assurance of structural reliability. Conclusions and Recommendations L Based on the above evaluation,. it is concluded that the Code I requirements are impractical. It is further concluded that the proposed alternative examination, along with the Code-required . 30
i surface examination and hydrostatic and system pressure tests, will provide necessary assurance of structural reliability. 'Therefore, relief is recommended as requested. Refereqqn References 17 and 22. I 4 h 31
-3.1.4 Pump and Valve Pressure Boundary 3.1.4.] Relief Recuest IR-4. Internal Surfaces of Pumn Casinos and Valve Rodies. Cateaorier B-L-2 and B-M-2. Items 812.20 and B12,40 Code Reouirement Item B12.20 The internal surfaces of at least one pump in each group of pumps performing similar functions in the system (e.g., recircu-lating 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 examina-nations may be performed at or near the end of the inspection interval.
Item 812.40 The internal surfaces of at least one valve 11n 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 in, 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 . . amination of welds. The examinations may be per-formed at or near the end of the inspection interval. Code Relief Recuest Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from performing an inservice visual examination (VT-3) on the pumps and valves listed in relief request IR-4. Proposed Alternative Examin,ali2D Class 1 pumps and valves will receive'a visual examination L (VT-3) when they are disassembled. for maintenance or purposes other l than ISI. l 4 I 32
- - . - . ~ _ ~ . - - . - - - - -- . . . . . .._
,ies y Licensee's Basis for Reauestina-Relief
- i
- For the reactor coolant pump casings and 35 valve bodies-U in the, reactor _ coolant, pressurizer, safety. injection, and residual heat: removal' systems, relief is requested from disassenibly of an operable valve or pump for the performance of an inservice visual
, examination ~(VT.-3)..
The requirement to disassemble an operable valve or pump for
'the sole purpose of performing a visual examination (VT-3) .of the internal- pressure-retaining boundary is impractical and not commensurate with the increased safety achieved by this inspection.
-To disassemble-these-items would provide a very_~small potential for-increasing plant safety margins with a disproportionate. impact on extenditures of. plant manpower and resources.
- Class _I valves and pumps are subjected to numerous types of nondestructive testing in;accordance with ASME Section III and a
_ rigorous quality assurance program during :all stages of fabrica-tion,_ storage, and installation.- These valves end pumps have been found acceptable by the manufacturer, the ASME ~ Authorized Nuclear _ Inspector,- and Northeast Util_ities' ~ Quality Assurance. > EvaluationL
- . ,- The visual examination is to determine whether unanticipated severe' degradation of the casing is occurring:due to phenomena such as erosion,-corrosion, or cracking. However, previous experience
~during ext.minations of_ pumps at other_ plants has not shown any.
significt.nt degradation of_ casings.
; Disassembly of'large valves to +he degree necessary to examine Jthe intarnal- pressure-retaining surtaces is a major effort, which may-.inve' alarge personnel: exposures. ETo do thiscdisassembly solely to perform a visual: examination of the internal body-is-
- impractical'. -
c 1 A list' of-all Class 1 pumps and valves has been provided - with: relief ; request IR-4. Although not -all: are required to'.be inspected,ce.significant number to require disassembly and
*. inspection 7 The licensee has committed to the concept of visual-
' examination if theLpump or valve is disassembled-for maintenance. '
sThe. visual examination specified. is to determine whether anti-cipatedl severe degradation 1of the body is occurring 1due to phenomena such as erosion or corrosion.' iThe alternate. tests proposed by the licensee, along with . . visual examination for leakage during system pressure tests under Category- B-P and periodic testing of pumps and valves- in accordance with IWP and;IWV,1wi.ll provide an adequate level of safety. u e 33-
*b .,r._o - -.-, s-g , a., ,,4 , , ,- - -
- vr-t k 1 m v
Conclusions and Recommendations Based on the above evaluation, it is concluded that for the examinations discussed above, the Code requirements are imprac-tical. It is further concluded that the proposed examinations, l
. along with the Code required hydrostatic and system pressure tests '
and pump and valve testing required by IWP and IWV, will provide necessary assurance of structural reliability. Therefore, relief l is recommended as requested. l EifEREli References 17 and 22. . l [ d 6 1 34-
- .~ . . .. . - . - - ..
. - . = . . -. -.
- ... .w ,
3.2' CLASS 2idOMPONENTS r3.2.1 Pressure Vessels'a.nd Heat.Exchangers 3.2.1.1 Relief-Recuest IR-14. Shell'-to-Flance Weld in the Residual Heat
> Exchancer. Cateoory C-A. Item C1.10 4
. Code Reouirement Essentially:100% of the shell circumferential. welds at= gross
, structural discontinuities shall be_ volumetr_icallyL examined .in accordance with Figure IWC-2500-1 during-each inspection interval. A gross structural discontinuity is defined in NB 3213.2. Examples are junctions between: shells' of different thicknesses, cylindrical- i shell-to-conical shell junctions, and shell--(or head)-to-flange welds,t 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. ,
~ Code Relief-Recuest- >
Pursuant to 10CFR50.50(a)(g)(5)(iii), relief is requested from j performing the inservice volumetric examination of the inaccessible
' portion of the subject vessel weld, q
q ~ Prooosed - Alternative Examination-l L(a)iThe subject weld will receive a volumetric. examination on the-- accessible' portion -in 'accordance~ with SectionLXI (IWC-2500-1). 4
*T -(b)~ The -inaccessible' area 'of the subject weld ist access'ible' to a- I surface examination _and will receive:a liquid-penetrant exami-nationcin.accordance with Section XI,.IWC-2500-1. 3 (c) -An: inservice hydrostatic test will be.eenduct'ed on the: Class 2 pressure boundary of which these weldsx are a- part ithereof-1
.(IWC-2500-1).
(d) Inservice system leakage tests:will be performed per Category y C-H, IWC-2500-1. e a
-l 11 s-
?h g .
c - 2 . -. _ - ., , _ . , ,, .i
4; 6 x Licensee *s Basis for Reauestino Relief i Geometric configuration and permanent obstructions affected )
.the referenced weld from performing a 100% volumetric examination. l The subject weld received both volumetric examination-by radiography and surface examinations during fabrication, in accor- ?
dance with ASME Section III requirements which provide adequate , assurance' of< the structural integrity of the welds. ; Evaluaiion As shown on a sketch provided with Relief Request IR-14, pipe to-vessel weld reinforcing saddle plates-adjacent'to the . shell-to-flange weld restrict-ultrasonic examinationLon 25-1/2 i inches of the required length. The licensee has proposed'to _ perform an ultrasonic examination- on the accessible portion'of ' >
; the weld along with~ a surface examination on that portfon not accessible to ultrasonic examination. The proposed alternative examination,talong with the Code-required hydrostatic and system- + ,
pressure tests,.Will provide necessary assurance of structural i 4 reliability. 7 : Conclusions and Recommendations Basti on the above evaluation, it is concluded that:for the
- shell-to-flange weld discussed above. the Code requirements are s
K ' impractical. It is further concluded that the proposed . alternative . examination will- provide necessary assurance of -structural reli-ability. <Therefore, relief is recommended as requested. References Reference 22.-
- y i
l e 4 i 7 ii
';- b 36 a y
- g/j hM E- <
o .- 3.2.1.2 Relief Recyest IR-7. full Penetration Nozzle-to-Vessel Welds in the Secondary Side of the Steam Generators. Cateaorv C-B. Item CL21 f_2dalt.QP.irement s 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 (manways and handholes are excluded). Only those piping runs selected for examination under Examination Category C-F are included.
I Code Relief Request N Pursutnt to 10CFR50.55a(g)(5)(iii), relief is requested from g-performing the inservice volumetric and surface examination and surface examination of the inaccessible portions of the subject vessel welds. ]- I Proposed Alternative Examination
! O' ,
(a) The subject welds will receive a volumetric and surface } examination on the accessible areas in accordance with Section L XI (IWC-2500-1). U l l (b) A hydrostatic test will be conducted on the Class 2 pressure )l , boundary, per Category C-H, of which these welds are part I thereof (IWC-2500-1). (c) Inservice system leakage tests will be performed per Category & C-H, IWC-2500-1. d pl hj H Licensee's Basis for Reauestino Relief l Permanent obstructions limited the volumetric and surface examination. of the following listed welds. Examination data sheets O and limitation sketches depict the affected areas. Relief is L therefore requested on complying with the 100% WRV coverage of the L i welds, f I 37
Ei is i St'eam Generators: Required Volume Wold- Examination Not Examinable 03-003-SW-R S/G A UT. 12% MT 19% ; 03-003-SW-T S/GA UT. 16% MT 0%
, -Permanent obstructions--permar;ent _mcunted-insulation supports for the subject generator restricted scans.
Evaluation It is agreed that the limitations noted:by the licensee could limit;the examinations performed on these welds. Sketches have
. been provided that-detail the impracticality of. performing the required examinations. The licensee has evaluated all available ultrasonic testing _ techniques and has found them to be~ impractical for performing these examinations. The' licensee has additionally agreedEto keep up with and use the most.up-to-date ultrasonic -
technology available for these examinations. The proposed examination to the maximum extent -practical, along with the
. Code; required hydrostatic and system pressure tests, provide
.necessary assurance of structural reliability for this interval.
~
r m Conclusions and Recommendationi BasedLon the above e'raluation, it is concluded that for -the I welds discussed above, the Code requirements are impractical. It ! is further~ concluded that.the proposed = alternative examination, along= with< the Code-required .hydrostaticiand system pressure
< tests,- will provide necessary assurance of' structural reliability.
CTherefore,- relief is recommended-as~ requested. L L- , -References-
, Reference 22.
l 4 38
r ., 3.2.2 Piping Pressure Boundary 3.2.2.1 Relief Reouest IR-13. Intearally Welded Attachments for Pinina. > Cateaory C-C. Item C3.20 Code Reauirements The weld joints for integrally welded attachments to piping shall be surface examined-over essentially 100% of their lengths in accordance with Figure IWC-2500-5 during the first interval. Examination is limited to those integrally welded :.ttachments that meet the following conditions:-(a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attach-ment base mhterial design thickness is 3/4-inch or greater; and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations are also limited to attachments of those components required to be examined under Examination Categories C-F and C-G. Code Relief Recue.Lt Pursuant to 10CFR50.55a(g)(5)(iii), relief is requested from performing the surface examination of the inaccessible portions of the subject weld. Proposed Alternative Examination (a) The subject welds will receive a surface examination on the-accessible pori. ions in accordance with Section XI (IWC-2500-l 1). (b) An inservice hydrostatic test will be conducted on the Class 2 pressure boundary of which these welds are part thereof (IWC-2500-1). l l (c) Inservice system leakage tests will be performed per Category ! C-H, IWC-2500-1, 1 Licensee's Basis for Reauestino Relief l Permanent obstruction limited the surface examination of the above listed weld. The examination data sheet depicts the affected areas. Relief is therefore requested on complying with the 100% weld required volume (WRV) coverage of this weld. l , 39
> s
- Weld No. 3-SIL-4-pSR 040: i Access to this weld Jallowed examination of essentially 100% of ;;
the weld: volume.- The heat affected zone for each welded attachment-was partially inaccessible due to-the snug fit of the pipe clamp about the pipe. - Evaluation - Weld No. 3-SIL-4-PSR 040 consists of eight pipe lugs that fit snug against-a pipe clamp as shown onLDrawir.g No. 25212-20865.. -
-Three of the four sides of the pipe lugs are accessible for surface examination, the side against the pipe clamp being not accessible.
- The licensee calls the clamp a " permanent obstruction" in his basis for requesting relief; it is therefore assumed that the pipe clamp cannot be removed without great difficulty. Surface exami-nation of three of the four sides of theLsubject lug-to-pipe welds
- would detect- a service induced crack before f,ailure occurred.
Therefore, relief is recommended as . requested. 3 Conclusions and Recommendations Based.on the above evaluation, it is concluded that for the-
~
integrally welded attachments discussed above, the Code require- i ments'are impractical. It is further1 concluded that the proposed alternative examination will provide necessary assurance of structural reliability. Therefore, relief-is recommended-as requested.. . i References Reference 22. l II
- 3.2.3 Pump Pressure Boundary No relief requests, p
3.2.4 Valve Pressure Boundary < No relief requests. , l 40
- a ei- w -r m .,--a v- --e..rr*+-w
- ee- * *- s- " - - - e m u e a v- f-- e - ww f aT-e ti rv=&9--*W " ---=y--w t-?-- +-uy --g( 'twY
3.3 CLASS 3 COMPONENTS No relief requests. 3.4 COMPONENT SUPPORTS No relief requests. 3.5 PRESSVRE TESTS No relief requests. 3.6 GENERAL No relief requests. I li D i l l 1 41
- 4. REFERENCES
- 1. NNEco to NRC, June 1, 1983; preservice inspection program.
- 2. NNEco to NRC, March 20, 1984; preservice inspection program, Revision 2.
- 3. J. F. Opeka (NNECo) to B. J. Youngblood (N November 19, 1985; proposed requests for relief from preservi inspection.
- 4. J. F. Opeka (NNEco) to V. S. Noonan (NRC), December 23, 1985; formal submittal of requests for relief from preservice inspection.
- 5. U.S. Nuclear Regulatory Commission, Safety rvaluation Report Related to the Operation of Millstone Nuclear Power Station. Unit No. 3, NUREG-1031, July 1984; Supplement 2, September 1985; Supplement 3, November 1985; Supplement 4, November 1985; Supplement 5, January 1986.
- 6. B. J. Youngblood (NRC) to W. G. Counsil (NNECo), January 16, 1984; request for additional information.
- 7. W. G. Counsil (NNECo) to B. J. Youngblood (NRC), May 1,1984; response to request for information concerning recording and investigation of crack indications.
- 8. W. G. Counsil (NNEco) to B. J. Youngblood (NRC), May 9,1984; response to request for information concerning compliance with Regulatory Guide 1.150.
- 9. 'W. G. Counsil (NNEco) to B. J. Youngblood (NRC), December 13, 1984; response to request for information concerning volumetric examination of Class 2 piping welds.
- 10. B. J. Youngblood (NRC) to W. G. Counsil (NNECo), March 7,1985; request for additional information.
- 11. J. F. Opeka (NNECo) to B. J. Youngblood (NRC), May 7,1985; response to request _for additionai information concerning ultrasonic inspection technique for centrifugally cast pipe.
- 12. J. F. Opeka (NNECo) to B. J. Youngblood (NRC), July 1,1985; provides additional information concerning ultrasonic inspection technique for centrifugally cast pipe,
- 13. J. F. Opeka (NNECc) to B. J. Youngblood (NRC), July 2,1985; provides additional information concerning ultrasonic inspection technique for centrifugally cast pipe.
- 14. J. F. Opeka (NNECo) to B. J. Youngblood (NRC), September 18, 1985; request for exemption from Code volumetric examinations for embedded containment recirculation spray system piping.
l l 42
- 15. J. F. Opeka (NNEco) to B._J. Youngblood (NRC), September 30, 1985; preservice inspection of piping walds in the break exclusion area.
16.- J. F. Opeka'(NNECo) to V. S. Noonan (NRC), April 1, 1986; revised preservice inspection relief requests PR-4 and PR-12 identifying additional welds requiring relief.
- 17. J. F. Opeka (NNEco) to V. S. Noonan (NRC), May 22, 1986; 'irst interval inservice inspection program. I
- 18. E. J. Mroczka (NNECo) to NRC, March 18, 1987; request for relief f rom inservice inspection requirements for integrally welded attachments to vessels.
- 19. E. J. Mroczka (NNEco) to NRC, August 5,1988; revised request for relief from inservice inspection requirements for integrally welded attachments to vessels.
- 20. J. F. Stolz (NRC) to E. J. Mroczka (NNECo), September 21, 1988; Safety Evaluation of relief request from inservice inspection reanirements for integrally welded attachments to vessels.
- 21. D. H. Jaffe-(NRC) to E. J. Mroczka (NNEco), Auscst 16, 1988; request for additional information on the inservice inspection program.
- 22. E. J. Mroczka'(NNECo) to NRC, October 19, 1988; response-to request for additional information, revised inservice inspection program attached.
- 23. J. F. Opeka (NNEco) to S. D. Ebneter (NRC), April 27, 1986; licensee's interpreta' ion of 10 CFR 50.55a(g)(4)(iv) and clarification of use of the ASME 1983 Edition, Summer 1983 Addenda Code for the first interval at Millstone 3.
- 24. NRC-Memo, C. Y. Cheng and L. B. March to J. P. Durr, August 10, 1987; review of licente's interpretation of 10 CFR 50.55a(g)(4)(iv) in applying the ASME-1983 Edition, Summer 1983 Addenda Code to the first interval inservice inspection program for Millstone 3, 25.. E. J. Mroczka -(NNEco) to NRC, December 1,1988; thermal fatigue mechanisms in steam generator and pressurizer nozzles.
l 43 1
6 , l l
> APPENDIX A Requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code 1983 Edition with Addenda through Summer 1983 A.1 CLASS 1 REQUIREMENTS A.1.1 CATEGORY B A, PRESSURE-RETAINING WELDS IN REACTOR VESSEL A.1.1.1 Shell Welds, Item Bl.10 A.1.1.1.1 Circumferential and Longitudinal Welds, Items Bl.11 and B1.12 All pressure-retaining circumferential 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.1.1.2 Head Welds, Item Bl.20 ' A.1.1.2.1 Circumferential and Meridional Head Welds, Items Bl.21 and Bl.22 All pressure-retaining circumferential and meridional head welds in the reactor vessel head shall be volumetrically examined in accordance with Figure IWC-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-Flange 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 the 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. The examination of the shell-to-flange weld may be performed during the first and third inspec-tion periods in conjunction with the nozzle examinations of Examination Category B-D (Program B). At least 50% of shell-to-flange welds shall. be examined by the end of the first inspection period, and the remainder by the end of the third inspection period. 1 A-1
s o i I
'A.I.l.4 Head to Flange Weld, Item Bl.40 Essentially 100% of the length of the head-to flange weld shall be volumetrically and surface examined in accordance with Figure IWB-2500-5 during the first inspe'etion interval. If the 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.I.l.5 Reoair Welds. Item Bl.50 A.I.1.5.1 Repair Welds in the Beltline Region, Item Bl.51 All base matal weld repair areas in the beltline region where repair 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, iA.I.2 CATEGORY B-8, PRESSURE-RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS A.I.2.1 Shell-to-Head Welds in Pressurizer, item B2.10 A.1.2.1.1 Circumferential Shell-to-Head Welds, Item B2.ll 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.I.2.1.2 Longitudinal Shell Weld, Item B2.12 One. foot of all selected longitudinal shell welds in the pressurizer intersecting the examined circut3erential 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. A.I.2.2 Head Welds in Pressurizer Vessels. Itam B2.20 A.I.2.2.1 Circumferential and Meridional Head Welds, Items 82.21 and 82.22
' All circumferential and meridional head welds in the pressurizer shall be volumetrically examined in accordance with Figure IWB-2500-3 over essentially 100% of their lengths during the first inspection interval.
A-2
-1A.I.2.3- Head Welds in the Primary Side of the Steam Generators. item B2.30 A.I.2.3.1 : Circumferential and Mer.idional Head Welds, Items _ B2.31 and B2.32-All circumferential and meridional head welds in the primary--side of the :
steam generators _ as shown in Figure IWB 2500-20(c) shall be volumetrically examined-in-accordance with Figure IWB 2500-3 over essentially 100% of their length during the first inspection interval.- A.1.2.4 : Tubesheet-to-Head Weld. Item B2.40 q The tubesheet-to-head weld in the primary side of the steam generators i shall be volumetrically examined in accordance with Figure IWB-2500-6 over essentially 100% of its length during the first inspection interval. A.I.2.5' Head and Shell Welds in the Primary Side of the Heat-Exchanaers. Item B2.50 A.1.2.5.1 Circumferential and Meridional Head Welds, Items 82.51 and 82.52
. . . All circumferential and meridional head welds in the primary side of the-heat exchangers as-shown in Figure IWB-2500-20(e) shall be volumetrically
, examined in:accordance with Figures IWB-2500-1 and -3 for circumferential welds-and Figure IWB-2500-3 for meridioaal= welds over essentially 100% of their length during the first inspection interval.
..A.1.2.5.2 >Tubesheet-to-Head Welds, Item B2.60-The tubesheet-to-head welds as shown in Figure IWB-2500-20(g) sh'all be
.. volumetrically examined in accordance with Figure LIWB-2500-6 over essentially.
100% of,their length during the first interval,
' A'.1.2'.5.3. Longitudinal Shell Welds, Item B2.70
- One_. foot of all, longitudinal welds in the primary side of the heat u :exchangers intersecting the examined-circumferential .tubesheet-to-shell weld ,;
l at each end of the heat exchanger as shown-in Figure IWB-2500-20(g) shall be p volumetrically examined in accordance with Figure IWB-2500-2 during.the first. L . inspection interval. l A.1.2.5.'4. Tubesheet-to-Shell Welds, Item B2.80 The.tubesheet-to-shell welds at each end of the heat exchanger as shown
.in Figure IWB-2500-20(g) shall be volumetrically examined in accordance with Figure 'IWB-2500-6 over essentially 100% of their length during the first' interval .
A-3 l i
4 LA.1.31 CATEGORY B-D,l FULL PENETRATION-_ WELDS 0F N0ZZLES IN VESSELS * (INSPECTION'PROGRAMB): ,
- A;1.3.1 Reactor Vessel Nozzle-to-Vessel Welds. Items 83.90 and B3.100 '
All nozzle-toWessel' welds: and inside radius-sections .in the reactor. vessel:shall be volumetrically examined in accordance with Figure IWBt 2500-7(a) through-(d) during the first interval of1 operation.. Examinations-
- shall include nozzles with full penetration welds to vessel shell (or head)
-and integrally cast nozzles; but exclude manways and handholes either
~
welded to or integrally cast in_ vessel. At least 25% but not more than 50% L(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. If examina-tions 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 inside diameter may be performed at or near the end of-each-inspection interval. A.1.3.2 Pressurizer Nozzle-to-Vessel Welds. Items B3.110 and B3.-120 All nozzle-to-vessel welds- and-inside radius sections in the pressurizer shallibe volumetrically examined in accordance with Figure 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. integrally cast nozzles, but exclude manways and handholes either welded to
- or integrally cast in vessel. At least-25% but not more than.50%'(credited) of the nozzles shall beLexamined by the end of the first inspection period L andithe remainder by..the end of the. inspection interval =. If: examinations are l conducted from'inside the component and the nozzle weld is examined by-straight beam ultrasonic method from the nozzle bore, the remaining exami-L. nations required to be conducted from the shell inside diameter may be L
performed-at or near the end of each inspection interval'. l-l - A.1.3.3 = ' Steam Generator Nozzle-to-Vessel Welds; Items 83.130 and B3.140 L
; All nozzle-to-vessel welds- and inside radiu'st sections in the steam
- ' generator, shall be ' volumetrically examined in, accordance with Figure;IWB .
2500 7(a):through (d).during:the first interval of operation. Examinations l shall include nozzles with full . penetration welds' to vessel'.shell (or head) r and integrally cast _ nozzles, but- exclude manways and handholes either welded I to or integrally cast in vessel. At least 25% but 'not more :than 50% of the
. nozzles shall-be examined by the end of the first inspection period and the
. remainder-by the end of the>1nspection interval. !If' examinations are con-
' ducted from inside theLeomponent 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 inside diameter may be performed at
~
R or.near:the end of each inspection-interval. 1 A-4 7 g g - . - - - , , , , - - , , , . , - - - , ,
A.1.3.4 Heat Exchanoer Nozzle-to-Vessel Welds. Items 83.150 and B3.160 All nczzle-to-vessel welds and inside radius sections in the primary side of the heat exchanger shall be volumetrically examined in accordance with Figure 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 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. 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 inside diameter may be performed at or near the end of each inspection interval. A.1.4 CATEGORY B-E, PRESSURE-RETAINING PARTIAL PENETRATION WELDS IN VESSELS A.1.4,1 Reactor Vessel Partial Penetration Welds. Item B4.10 A.1.4.1.1 Vessel Nozzles, Item B4.11 The external surfaces of partial penetration welds on 25% of reactor vessel 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. Examina-tions may be performed at or near the end of the interval. A.1.4.1.2 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. Examinations may be performed at or near the end of the interval. A.I.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. inspection interval. The examinations shall cumulatively cover the specified percentage among each group of penetrations of comparable size and function. Examinations may be performed at or near the end of the interval. A.1.4.2 Heater penetration Welds on the Pressurizer, item B4.20 The external surfaces of all heater penetratio's welds on the prc:;Jrizer shall be visually examined (VT-2) during the first inspection '.nterval. Examinations may be performed at or near the end of the intervai. A-5
l A.I.5 CATEGORY B-F, PRESSURE-RETAINING DISSIMILAR METAL WELDS A.I.5.1 Reactor Vessel 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 accor-dance 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 combi-nations 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 B5.20 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 steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included. A.1.5.3 Reactor Vessel Nozzle to-Safe End Socket Welds, item B5.30-The surfaces of all nozzle-to-safe end socket welds in the reactor vessel shall be examined in eccordance with Figure IWB 2500-8 during the first inspection interval. The examinations may be performed coincident with the vessel notzle examinations required by Examination Category B-D. 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 includea. A.1.5.4 Pressurizer Nozzle-to-Safe End Butt Welds. Item B5.40 All nozzle-to-safe end butt welds 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.l.5.5 Pressurizer Nozzle-to-Safe End Butt Welds, item 85.50 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 welds A-6
. - . . . . - -- ~ . - . - - -_ .
.; . j l 3
)
between combination's 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.liS.6 - P_rmyntt_er Nozzle to-Safe End Socket Welds. Item B5.60-The surfaces of all _ nozzle-to-safe end socket welds in the pressurizer shall' be= examined in' accordance with Figure IWB-2500-8 during the first - , inssection interval. Dissimilar. metal welds between combinations of (a)- caraon 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.
l 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
-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.l.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. 'a the pressurizer shall. be examined in accordance with Figure IWB-2500-8 durirg the first inspection interval. - Dissimilar metal welds l between combinacions of (a) carbon or low alloy steels to high. alloy steel,
! -(b) carbon oriow alloy steel to high nickel alloys, and'(c) high alloy steel q-to high nickci alloys are included. A.1.5.9 Steam Generator Nozzle-to-Safe End Socket Welds. Item B5.90 - k' - The surfaces of all nozzle-to-safe end socket welds in the steam generator shall'be examined in' accordance with Figure-IWB-2500 8 during the first: l inspsction interval. -Dissimilav metal welds between combinations of (a) u 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.1.5.10 Heat Exchancer Nozzle-to-Safe End Butt Welds. Item 85.100 All nozzle-to-safe end butt welds in nominal pipe size *. in. 'and greater
-in the heat exchangers shall be surface and volumetrically examined in
. Eaccordance 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 I (c) high' alloy steel to high nickel alloys are included. A-7
- . . - _. _.. ._ _~ _. . _ _ . _ . . . . . _ . _ _- . _
7 A.1.5.11 Heat Exchancer Nozzle-to-Safe End Butt Welds. Item B5.110 r The . surfaces of all nozzle-to-safe end butt welds in nominal pipe size less than 4 in. in the heat exchangeers 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.1.5.12 Heat Exchanaer Nozzle-to-Safe End Socket Welds. Item B5.120 The surfaces of all nozzle-to-safe end socket welds in the heat exchangers shall be examined in accordance with Figure IWB-2500-8 during the first ins >ection interval. Dissimilar metal welds between combinations of (a) caraon 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.1.5.13 Pioino Dissimilar Metal End Butt Welds. Item 85.110 All dissimilar metal 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. For reactor vessel nozzle safe ends, the~ examinations may be performed coincident with the vessel nozzle examina-tions required by Examination Category B-D. 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.I.5.14 Pioino Dissimilar Metal Butt Wolds. Item B5.140 The surfaces of all dissimilar metal butt welds in piping less than 4 in. shall be examined in accordance with Figure IWB-2500-8 during the first i inspection interval. For reactor vessel nozzle safe ends, the exwinations 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 steel, (b) carbon or low alloy l steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included. i A.].5.15 Pinina Dissimilar Metal Socket Welds. Item B5.150 The surfaces of all dissimilar metal socket welds in piping shall be o examined in accordance with Figure IWB-2500-8 during the first inspection l interval. For reactor vessel nozzle safe ends, the examinations may be
- performed coincident with the vessel nrzzle examinations required by i Examination Category B-D. 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-8
A.I.6 CATEGORY B-G-1, PRESSURE-RETAINING BOLTING LARGER THAN 2 INCHES > IN DIAMETER A.I.6.1- Reactor Closure Head Nuts. Item 86.10 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 necr the end of the inspection interval. A.I.6.2 Reactor Closure Studs, in Placed or When Removed. Items B6.20 and B6.30 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.I.6.3 Threads in the Flance in the Reactor Vessel. Item B6.40 All threads in the flange in the reactor vessel shall be volumetrically examined in accordance with Figure 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, i A.1.6.4 Reactor Closure Washers and Bushinos. 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 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 Flance Surfaces. Items 86.60 l and B6.70 All bolts and studs larger than 2 in, in diameter in the pressurizer shall be volumetrically examined in accordance with Figure IWB-2500-12 during'the c first inspection interval. Bolting m3y be examined (a) in place under l tension, (b) when the connection is disassembled, or (c) when the bolting is l . 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. A-9
.' .: j l
d A.1.6.6 pressurifer Nuts. Bust 10.os, 1 and Washers. Item B6.80 1
. i 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 inspec-tion 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. Bushings and threads in base material of flanges are required to be examined only when the
- connections are disassembled. Examinations may be performed at or near the end of the inspection interval.
A.I.6.7 B'olts. Studs. and F1gJsp Surfaces in Steam Generators. Items B6.90 -! and B6.100 All bolts and studs larger than 2 in. in diameter in steam generators _
- shall be volumetrically examined in accordance with Figure 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 the annular surface surrounding each stud. . Examinations may be performed at or near the
.end of the inspection interval.
A.I.6.B N_uts. Bushinos. and Washers in Steam Generators. Item B6.110 The surfaces of. all nuts, bushings, and washers -in bolting larger than . !
'2Lin in diameter in steam generators shall be visually examined (VT-1) during the first inspection interval. Bushings in the base material of flanges are '
L required.to-be examined only when the connections are disassembled; bushings l may be' inspected in place. -Bolting may be examined (a) in place under - L tension, (b).when the connection is disassembled, or (c) when the bolting is , removed. . Bushings and threads in base materials of-flanges are required to be-L examined only when the connections- are disassembled. Examinations may be-( performed at or near the end of the inspection interval. A.I.6.9 Bolts, Studs and Flanae Surfaces in Heat-Exchanaers. Items B6.120 and 86.130 , All bolts and studs larger than 2 in. in diameter in. heat exchangers shall P - be volumetrically-examined in accordance with Figure IWB-2500-12 during the first inspection-interval =. Bolting may be examined (a) in pla .e under tension, _(b) when the connection is disassembled,, or_ (c)_,< hen the bolting is removed.- - The' flange surfaces shall also be visually-examinec. (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. Examir.ations 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-10
e . l
.A.1.6.10 Nuts. Bushinas. and Washers in Heat Exchanaers. Item B6.140 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in in diameter in heat exchanges 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 ins)ected in place. Bolting may be examined (a) in place under tension, (3) 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.I.6.ll Bolts. Studs. and Flance Surfaces in Pinina. Items. B6.150 and B6.160 All bolts and studs larger than 2 in, in diameter in piping shall be volumetrically examined in accordance with Figure 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 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.1.6.12 Nuts. Bushinas. and Washers in Pioino. 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 insaection interval. Bushings in the base material of flanges are required to se 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.1.6.13 Bolts. Studs, and Flanae Surfaces in Punos. 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 Figure 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 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. t A-11
e- . l A.I.6.14 Nuts. Bushinos, and Washers in Pumos. Item B6.200 i l The surfaces of all nuts, bushings, and washers in bolting larger than 2 in. in diameter in pumps shall be visually examined (VT-1) during the first ins)ection interval. Bushings in the base material of flanges are required to ae 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.).6.15 Bolts. Studs, and Flance Surfaces in Valves. Items B6.210 and 86.220 All bolts and studs larger than 2 in. in diameter in valves shall be volumetrically examined in accordance with Figure 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 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.1.6.16 Nuts.-Bushinos, 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; 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 comonents selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable. A-12
e . A.1.7 CATEGORY B-G-2, PRESSURE-RETAINING BOLTING 2 INCHES AND SMAll.ER IN DIAMETER A.1.7.1 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, l (b) when the connection is disassembled, or (c) when the bolting is removed.
-A.I.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 I 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. l A.1.7.3 Bolts. Studs. and Nuts in Steam Generators. Item B7.3_Q 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 removed.
A.1.7.4 Bolts. Studs, and Nets in Heat Exchanaers. 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.I.7.5 Bolts. Studs, and Nuts in Pioina. 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 Pumos. Item B7,60 l The surfaces of all bolts, studs, and nuts 2 in. 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 i the connection is disassembled, or (c) when the bolting is removed. A-13
A.I.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 shali 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.7.8 Bolts. Studs. and Nuts in Control Rod Drive Housinas. 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.I.8 CATEGORY B-H, INTEGRAL ATTACHMENTS FOR VESSELS A.I.8.1 Intearally Welded Attachments in Reactor Vessel. Item B8.10 The weld joints for integrally welded attachments to the reactor vessel shall be surface or volumetrically examined as-applicable over essentially 100% of their lengths in- accordance with Figures IWB-250013. -14, and -15 4
during the first interval.- For the configuration shown in Figure IWB 2500-14,. a.v'olumetric examination of volume A-B-C-D from one. side (B-C) of the circumferential weld may be performed in lieu of the surface examination. Weld buildup on nozzles that is-in compression under normal conditions and provides only component support is excluded from examination. Examination is limited to those-integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component;_(b)-the attachment provides-component support as defined in NF-1110;- (c) the attachment base material design thickness is 5/8-in. or greater; and (d)-the attachment weld joins the attachment either directly-to
-the. surface of the vessel, or to an integrally cast or-forged attachment to the' vessel.
l A.I.8.2 Inteardiv Welded Attachments in Pressurizer. Item B8.20
. The. weld joints for integrally welded attachments to the pressurizer L shall be surface or volumetrically examined as applicable over essentially
'100% of their lengths in accordance with Figures IWB-2500-13, -14, and -15
- during the first . interval. For the configuration shown.in Figure IWB-2500-14,
.a volumetric examination of volume A-B-C-D from one side (B-C) of'the t circumferential weld may be performed in lieu of the surface examination.
Weld buildup on nozzles that is in compression under normal conditions and 4 ' provides only component -support is excluded from examination. Examination-is limited to those _ integrally welded attachments that meet the following conditions:1(a) the attachment is on the outside surface ofLthe pressure-
-retaining component;- (b) the, attachment provides component support as defined in NF-ll10;-(c) the attachment base material design thickness is 5/8-in. or greater; and (d) the attachment weld joins the attachment either directly to the surface of the vessel, or to- an integrally cast or forged attachment to the ves:el.
,A-14
A.I.8.3 Inteorally Welded Attachments in Steam Generators, item BB.30 The weld joints for integrally welded attachments to the steam generator shall be surface or volumetrically examined as applicable over essentially 100% of their lengths in accordance with Figures IWB-2500-13, -14, and -15 during the first interval. For the configuration shown in Figure IWB-2500 14, a volumetric examination of volume A-B-C-0 from one side (B C) of the circumferential weld may be performed in lieu of the surface examination. Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination. Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NT-1110; greatei and(c) (d) the the attachment attachmentbase weldmaterial joins thedesign thickness attachment is 5/8-in, either directlyorto the surtcce of the vessel, or to an integrally cast or forged attachment to the vessel. In the case of multiple vessels of similar design, size, and service, the examination is limited to the attachment welds of one vessel. A.I.8.4 Intearally Welded Attachments in Heat kehanaers. Item B8.40 The weld joints for integrally welded attachments to the heat exchangers shall be surface or volumetrically examined as applicable over eentially 100% of their lengths in accordance with Figures IWB-2500-13, -14, and -15 during the first interval. For the configuration shown in Figure IWB-2500-14, a volumetric examination of volume A-B-C-D from one side (B-C) of the circumferential weld may be performed in lieu of the surface examination. Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination. Examination is limited to those integrally welded attachments that meet the following conditions: (a the attachment is on the outside surface of the pressure-retaining compo)nent; (b) the attachment provides component support as defined
-in NF-1110;= -(c) the attachment base material design thickness is 5/8-in, or greater; and (d) the attachment weld joins the attachment either directly to the surface of the vessel, or to an integrally cast or forged attachment to the vessel. In the case of multiple vessels of similar design, size, and service, the examination is limited to the attachment welds of one vessel. -A.1.9' CATEGORY B-J, PRESSURE-RETAINING WELDS IN PIPING A.I.9.1 Nominal Pine Size 4 In. and Greater. Item 89.10 A.I.9.1.1 Circumferent.al Welds, Item 89.11 For circumferential 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-over essentially 100% of the weld length during each inspection interval. The examinations shall include the following:
A-15
l (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
.ther components where the stress levels exceed the following limits e 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 alloys 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 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 1977 Edition). For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need be examined for trans-verse reflectors. A.1.9.1.2 Longitudinal Welds, Item B9.12 For longitudinal welds in pipc: 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 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. A.1.9.2 Nominal Pine Size less Than 4 In. . Item B9.20 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 examinations shall include the following: A-16
-v v
(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 avents 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 metcl 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 c',rcumferential 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-1977 Edition).
'A.1.9.2.2 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-cach n longitudinal weld , intersecting the circumferential welds requireci to be i examined by Exa'nination Categories B-F and B-J.
-A.I.9.3 Branch Pioe Connection Welds. Item 89.30 L : A.1.9.3.1- Nominal Pipe Size 4 Inches and Greater, Item 89.31 For welds--in branch connections 4 in, and greater, surface plus volumetric l
examinations shall be performed in accordance with Figures .IWB-2500-9, -10 and p wil over essentially 100% of the weld length during each inspection interval, p The' examinations shall include the following:
-(a) - All = terminal ends in each pipe or branch run connected to vessels.
i m (b) : All terminal ends and' joints in each pipe or branch run connected to
~o ther' components where the stress levels exceed the following limits
, under loads associated with specific seismic events and operational b conditions ~. t , e k A-17 ,
Qof w
-l
.(1)1_ primary plus secondary stress intensity of 2.45, for ferritic steel and austenitic steel, and (2)-. cumulative usage factor U of 0.4.
-l
-(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 alloys 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 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 intthe 1977 Edition). i'
.For' welds in carbon or low alloy steels, only-those welds- showing
. reportable ~ preservice transverse indications need to examired for trans-verse reflectors.-
A.I.9.3.2 Nominal Pipe Size less Than 4 Inches, Item B9.32 l 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. ,
4 (1) primary plus secondary stress intensity of 2.45, for- ferritic
-steel and auste'nitic 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 alloys 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 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 ror both PWR and BWR plants in-the 1977 Edition).
A-18 l l . . . . .- . -.. --. -. ,
p, . t A.I.9.4- Socket Welds. Item B9.40~ q
' ~
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 includ,e 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 (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: alloys 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 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 1977 Edition).. 1 A.I.10 1 CATEGORY B-K-1, INTEGRAL ATTACHMENTS-FOR' PIPING, PUMPS, AND VALVES A.1.10.1 'Inteorally Welded Attachments on Pioina. Item B10.10 The weld joints for integrally welded attachments to piping shall. be-L surface or volumetrically examined as applicable over essentially 100% of-li their lengths in accordance with Figures IWB 2500-13, -14, 'and -15 during the first interval. For the configuration shown in Figure IWB-2500-14, a volumetric examination of volume A-B-C-D from one side -(B.C) of the cir-cumferential weld may be performed in lieu' of the surface examination. Examination 'is' limited to those integrally welded attachments that meet the i following conditions: (a) the attachment is on the outside surface of the pressure retaining' component; (b) the attachment provides component support as defined in NF-1110;- (c) -the attachment base material design thickness is , 5/8-inch or greater; and (d) the attachment weld joins the' attachment either-E directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations include the welded attachments >
.of piping required to be examined by Examination Category B-J.
A-19
9 D
'A.1.10.2 Inteorally Welded Attachments on Pumos. Item B10.20 The weld joints for integrally welded attachments to pumps shall be surface or volumetrically examined as applicable over essentially 100% of their lengths in accordance with Figures IWB-2500-13, -14, and -15 during the first interval. For the configuration shown in Figure IWB-2500-14, a volumetric examination of volume A-B-C-D from one side (B-C) of the cir-cemferential weld may be performed in lieu of the surface examination.
Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the press;'e retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attachment base material design thickness is 5/8-inch or greater; and (d) the attachment weld joina the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations include the welded attachments of the associated pumps integral to piping required to be examined by Examination Category B-J. A.1.10.3 Intearally Welded Attachments on Valves. Item 810.30 The weld joints for integrally welded attachments to valves shall be surface or volumetrically examined as applicable over essentially 100% of their lengths in accordance with Figures IWB-2500-13, -14, and -15 during the first interval. For the configuration shown in Figure IWB-2500-14, a volumetric examination of volume A-B-C-D from one side (B-C) of the cir-cumferential weld may be performed in lieu of the surface examination. Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attachment base material design thickness is 5/8-inch or greater; and (d) the attachment weld joins the attachment either ,< directly to the surface of the component or to an integrally cast or forged L attachment to the component. Examinations include the welded attach: tents of the associated valves integral to piping required to be examined by l Examination Category B-J. l l l ! -A.I.ll CATEGORIES B-L-1 and B-M-1, PRESSURE-RETAINING WELDS IN PUMP l CASINGS AND VALVE BODIES, AND B-L-2 and B-M-2, PUMP CASINGS AND VALVE BODIES A.1.11.1 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 (e.g., recirculating coolant pumps) shal'1 be volumetrically examined in accordance with Figure IWB 2500-16 during each inspection interval. Supplementary surface examinations may be-performed on interior and/or exterior surfaces to assist in determining the location of indications detected by volumetric examinations [see IWB-3518.1(d)). The examinations may be performed at or . near the ~end of the inspection interval. A-20
e r .- A.I.11.2 Pumo Casinos. Item B12.?Q 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 1) 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 intervel. A.1.11.3 'alve Body Welds Nominal pioe Size less than 4 in.. Item B12.30 Th. s. faces of essentially 100% of the body welds (nominal )ipe size less than 4 , in at least one valve in each group of valves with tie same con-struction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions iri the system (e.g., containment isolation and system overpressure protect %n) shall be examined in accordance with Figure l e IWB-2500-17 during each 4spection interval. The examinations may be l l performed at or near the end of the inspection interval. l A.1.11.3.1 Valve Body Welds. Nominal P_ioe Size 4 in, and Greater s
]_ty, B12.40 l l- Essentidly 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 construction I design (e.g., globe, gate, or check valve) and manufacturing method that erform similar functions in the system (e.g., containment isolation and , _ system over-pressure protection) shall be volumetrically examined in accor- l dance with Figure IWB-2500-17 during each inspection interval. Supplementary l' surface examiantion may be performed on interior and/or exterior surfaces to I assist in determining the location of indications detected by volumetric examinations [see IWB-3518.1(d)). The examinations may be performed at or near the end of.the inspection interval. I A.1.11'.4 Valve Body Exceedina 4 In. Nominal pioe Size. Item B12.50 L 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 overpresstre 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 l- -of the inspection interval. l A-21
1
,- o A.I.12 CATEGORIES B N-1, INTERIOR OF REACTOR "ESSEL; B-N 2, INTEGRALLY WELLED CORE SUPPORT STRUCTURES AND IN1;A10R ATTACHMENTS TO REACTOR VESSELS; and B-N 3, REMOVABLE CORE SUPPORT STRUCTURES i
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 com- ' ponents 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.I.12.2 Boilina Water Reactor Vessel interior Attachments Within Beltline Reuion item B13.20 The accessible welds in the reactor vessel interior attachments within the boltline region shall be visually examined (VT-1) during each inspection interval. The examinations may be performed at cr near the end of the inspection interval. A.I.12.2.1 Boiling Water Reactor Vessel Interior Attachments Beyond Beltline Region, Item B13.30 The accessible welds in the reactor vessel interior attachments . beyond the beltline region shall be visually examined (VT 3) during each .nspection ' interval. The examinations may be perforaed at or near the end of the inspection interval. A.1.12.2.2 Boiling Water Reactor Core Support Struct.ure, Item B13.40 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.I.12.3 fressurized Water Reactor Interior Attachments Within Beltline f:eaion. Item B13.jp,
.The accessible welds in the reactor vessel interior attachments within ;
the baltine region shall be visually. examined (VT-1) during each inspection interval. The examinations may be performed at or near the end of the inspection interval. - I ' i L A-22
V e ! A.I.12.3.1 Pressurized Water Reactor Interior Attachments Beyond Beltline Region, item B13.60 The accessible welds in the reactor vessel interior attachments beyond
-the belo te region shall be visually examined (VT-3) during each ins)ection interval. The examinations may be performed at or near the end of tie ,
inspection interval. A.I.12.3.2 Core Support Structure for Pressurized Water Reactor Vessels, Item B13.70 The accessible welds and surfaces of the core support structure shall be visually examined (VT-3) each inspection interval. Tle structure shall be removed from the reactor vessel for examination. The examinations may be performed at or near the end of the inspection interval. A.1.13 CATEGORY B-0, PRESSURE-RETAINING WELDS IN CONTROL ROD HOUSINGS A.1;13.1 Welds in- Control Rod Drive Housinas. Item B14.10 The welds in 10% of the peripheral control rod drive housings shall surface or volumetrically examined in accordance with Figure IWB 250018 . during each inspection interval. The examinations may be performed at or near - the end.of the inspection interval. A.I.14 CATEGORY B-P, ALL PRESSURE-RETAINING COMPONENTS A.I.14.1 Reactor Vessel Pressure-Retainina Boundary. Item B15.10 The reactor vessel prenure 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 aitcred 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, hcwever, extend to and include the second closed valve at the boundary extremity. A system. hydrostatic test (IWB 5222) and the c: companying VT-2 examination are acceptable in lieu of the system 11akage test (IWB-5221) and VT-2 examination. l N l . A-23 L< __ _ - _ ._ _ _ _ _ . _ _ _ . .. -
w . A.l.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 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 rear the end of the inspr ion 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.14.2 pressurizer Pressure Retainino Boundarv. Item B15.20 The pressurizer pressure retaining boundary shall be visually examined
-(VT2)duringthesystemleakagetestperformedinaccordancewithIWB5221
,during each refueling outage. System pressure tests for the reactor coolant 4
system shall be conducted in accordance with IWA 5000. System pressure tests for repaired,- replaced, or aitered components shall be governed by IWA-5214(c).- The prer,sure 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 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 A.I.14.2.1 Pressurizer Pressure Retaining Boundary, Item 015.21 l The pr(isurizer pressure rotaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-
- Sk22 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. Pressure tests for repaired, replaced, or altered components shall be governed _ by IWA 5214(c). A.I.14.3 Steam Generator Pressure-Retainino Boundarv. Item B15.30 .
-The steam generator 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 governed by IWA- 1 5214(c). -The pressure-retaining boundary during the system leakage test shallicorrespond 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 T A 24 e.-..-..- . . . ~ . . . . - - . m, . ,_...-.-.m .,w... ,__,nmm____-..m.,, ,,c_.--,_--..-._,,.._ __-.----,,,,m., 4..w,y--
e e 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.l.14.3.1 Steam Generator Pressure-Retaining Boundary, Item B15.31 The steam generator pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 during each refueling outage. The examinations may be performed at or near the end of the inspection interval. The pressure-retaining boundary during the test shall include all Class I components within the system boundary. 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.1.14.4 Heat Exchanaer pressure Retainina Boundary, item B15.40 The heat exchanger pressure retaining boundary shall be visually examined (VT-2) during the system leakage test performed in cecordance 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 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 cxamination 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.1.14.4.1 Heat Exchanger Pressure-Retaining Boundary, Item B15.41 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 I 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 sh,all be governed by IWA 5214(c). i A-25
r , A.I.14.5 Pipina Pressure-Retainino Boundary. Item B15.50 The siping pressure-retaining boundary shall be visually examined (VT-2) during tie 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 governed by IWA-5214(c). The pressure-retainiig 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 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.1.14.5.1 Piping Pressure Retaining Boundary, Item B15.51 The piping pressure retaining ooundary 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 I 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.I.14.6 Pumo Pressure-Retainino Boundarv. 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 tets 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 eactor 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, l i
- A.1.14.6.1 Pump Pressure Retaining Boundary, Item B15.61 l .The pump pressure-retaining boundary shall be visually examined (VT-2) l during the system hydrostatic test performed in accordance with IWB-5222 once l per inspection interval. The pressure-retaining boundary during the test shall include all Class I 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 . l accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c). A-26
3 I O 1.14.7 Valve Pressure-Retainina Boundarv. 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 tets 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 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 t per inspection interval. The pressure-retaining boundary during the test shall include all Class I 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.1.15.1 Steam Generator Tubina. Straiaht Tube Desian. Item B16.10 The examination requirements, examination method, and the extent ar.d frequency of examination shall be governed by the plant technical specifi-cations. A.1.15.2 Steam Generator Tubina. U-Tube Desian. Item B16.20 The examination requirements, examination method, and the extent and frequency of examination shall be governed by the plant technical specifi-cations. 2 A 27
s s A.2 CLASS 2 REQUIREMENTS A.2.1 CATEGORY C-A, PRESSURE-RETAINING WELDS IN PRESSURE VESSELS A.2.1.1 Shell Circumferential Welds. Item (1410 Essentially 100% of the sheli circumferential welds at gross structural discontinuities shall be volumetrically examined in accordance with Figure IWC-2500-1 during each inspection interval. A gross structural discontinu-ity is defined in NB 3213.2. Examples are junctions between shells of different 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 heet 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-2520-1 during each inspection interval. For multiple vessels with similar design, size, and service (such as steam generators and heat exchangers), the required exami-nations may be limited to one vessel or distributed among the vessels. A.2.1.3 Tubesheet-to Shell Weld. Item Claq Essentially 100% of the tubesheet to.shell weld shall be volumetrically examined in accordance with Figure IWC 2520 2 during o ch inspection interval. For multiple vessels with similar design, size, and service (such as steam generators and heat exchangers), the requirud examinations may be limited to one vessel or distributed among the vessels. A'2.2
. CATEGORY C-B, PRESSURE-RETAINING N02ZLE WELDS IN VESSELS A.2.2.1 Nozzles in Vessels 1/2 In. or less in Nyinal Thickness. Item C2.10 A.2.2.1.1 Nozzle-to Shell (or Head) Weld, Item C2.11 All nozzles in vessels 1/2 in. or less in nominal thickness at terminal ends of piping runs shall be surface examined in accordance with Figure IWC-2520-3 during each inspection interval. Torminal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (manways and handholes are excluded). Only those piping runs that connect to vessels.
Only those piping runs selected for examination under Examination Category C-F are included. . A-28
A.2.2.2 Nozzles Witbnut Reinforcina plate in Vessels Over 1/2 in. in' Nominal Tb M ness. Item C2.20 A.2.2.2.1 Nozzle to Shell (or Head) Weld, Item C2.21 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 (manways and handho'es are excluded). Only those piping runs selected for examination under Exami-nation 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) durina each inspection 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 C4 are included. A.2.2.3 Nozzles With Reinforcina Plate in Vessels Over 1/2 in. Nominal Thickness. 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. in nominal thickness at terminal ends of piping runs shall be surface examined in accordance with figure IWC-2500-4(c) 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.2.2.3.2 Nozzle to Shell (or Head) Welds, item C2.32 If the nozzle bore in accessible from inside the vessel, the nozzle-to- ! shell (or head) welds in vessels over 1/2 in, nominal thickness at terminal l ends of piping runs shall be volumetrically examined in accordance with Figure IWC-2500-4 If the nozzle bore is not accessible (c) during each inspection interval.from inside the vessel, the telltale hole i 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 to or integrally cast in vessels that connect to piping runs (manways and handholes are excluded).
r Only those piping runs selected for examination under Examination Category C-F are included. l l l A-29 f
I A.2.3 CATEGORY C C, SUPPORT MEMBERS A . 2. 3.1 Intearally Welded Surnort Attachments in Pressure Vessels. Item C3.10 The weld joints for integrally welded attachments to pressure vessels shall be surface examined over essentially 100% of their lengths in accordance with Figure IWC-2500-5 during the first interval. Examination is limited to those integrally welded attachmentt that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NF 1110; (c) the attachment base material design thickness is 3/4-inch or greater; and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. In the case of multiple vessels of similar desian and service, the required examinations may be conducted on only one vessel. Where multiple vessels are provided with a number of similar attachments, the examination of the attachments may be distributed among the vessels. A.2.3.2 101eara11v Welded Attachments in Pinino. Item C3.iQ The weld joints for integrally welded attachments to piping shall be surface examined over essentially 100% of their lengths in accordance with Figure IWC-2500-5 during the first interval. Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attachment base material design thickness is 3/4-inch or greater; and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations are also limited to attachments of those components required to be examined under Examination Categories C-F and C-G. A.2.3.3 Inteorally Welded Pump Attachments. Item C3.30 The weld joints for integrally welded attachments to pumps shall be surface examined over essentially 100% of their lengths in accordance with Figure IWC 2500-5 during the first interval. Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attachment base material design thickness is 3/4-inch or greater; and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations are also limited to attachments of those components required to be examined under Examination Categories C-F and C-G. 1 A-30
e e A.2.3.4 Inteo* ally Welded Valve . Attachments. Item C).dQ , The weld joints for integrally welded attachments to valves shall be surface examined over essentially 100% of their lengths in accordance with Figure IWC 2500 5 during the first interval. Examination is limited to those integrally welded attachments that meet the following conditions: (a) the attachment is on the outside surface of the pressure-retaining component; (b) the attachment provides component support as defined in NF-ll10; attachment base material design thickness is 3/4-inch or greater; (d) and(c) the the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component. Examinations are also limited to attachments of those components required to be examined under Examination Categories C-F and C-G. , 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 04.10 . 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 component contains a group of bolted con-nections of similar de. Ign 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 Pioina. Item C4.20 One hundred percent of the bolts and studs at each bolted piping connection shall 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 Pumos. Item C4.30 i l 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. LBolting on only one pump among a group of pumps in each system required to-be examined that have similar designs, sizes, functions, and-service is required to be examined. -In addition, where one pump contains a group of bolted conne tions 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 or upon disassembly of the . I connection. L A-31 L~ I m.,_ _ . , . _ . . _ . . _ , . , . . , . _ , , . . _ . . , _ . _ _ . , - . _ . , - . _ . . , . _ . _ . . . -
m
> a 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 the 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 or upon disassembly of the connection. A.2.5 CATEGORY C-F, PRESSURE-RETAINING WELDS IN PIPING A.2.5.1 Pipina Welds 1/2 In. or less Nominal Wall Thickness, item C5.10 A.2.5.1.1 Circumferential Welds, item C5.11 b - wallOne hundred thickness sbercent of each circumferential weldwith 1/2Figure in, or IWC-2500-7 less nominal all be surface examined in accordance 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 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 includes 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;
- 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; A-32
y , i
- 3. 10% of the main steam system welds 8 in, nominal pipe size !
-and smaller; ,
4, 25*' of the welds in all other systems. I
- 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, reducers, and flanges conforming to ANSI Standard B16.9), and pipe branch connections and fittings; i
- g. examination requirements are under development.
For welds in carbon or low alloy steels, only those welds showing 3
-reportable preservice transverse indications need to be examined for transverse reflectors, j
i A.2.5.1.2 Longitudinal Welds, Item C5.12 i Longitudinal welds 1/2 in. or less nomintl wall thickness shall be surface examined in accordance with Figure IWC-2520 7 (2.5 t at the inter-secting circumferential weld) during each inspection interval. A.2.5.2 'Eioino Welds Over 1/2 in. Nominal Wall Thickness. Item C5.20 l A.2.5.2.1 Circumferential Welds, Item C5.21 i One hundred )ercent of each circumferential weld over 1/2 in, nominal wall ' thickness shall 3e surface and volumetrically examined in accordance with 4 Figure IWC-2520-7 during each inspection interval. The welds selected for i examination shall include l
- a. all welds at locations where the stresses under the loadings -i' 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; ! o- c. all dissimilar metal welds;
- d. additional welds, at- structural discontinuities (see (f) below) such l
that the total number of welds selected for examination includes the following percentage: of circumferential piping welds; A 33
e , For. boiling water resctors: none of the welds exempted by !WC 1220;
~
1.
- 2. none of the welds in residual heat removal and emergency core
- 3. cooling 50% of the systems (seesystem main steam (g) below)ldst we
- 4. 25% of the welds in all other systems.
For pressur'ized water reactors:
- 1. 'none-of the welos 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 8 in. nominal pipe' size and smaller ,
- 4. 25% of. the welds in all ot* .tystems.
e.. terminal ends are thel 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, reducers, and flanges conforming to AtJSI Standard B16.9), and pipe branch connections and fittings; .
9 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 .
- transverseL reflectors.-
A.2,5.2.2 ' Longitudinal' Welds, Item C5.22 Longitudinal welds over_1/2-in, nominal wall thickness shall be surface - and volumetrically examined in accordance with Figure IWC 2520-7 (2.5 t at the intersecting circumferential weld) during each inspection interval. 5.- A-34 e m . ._ _ . _ . _ . _ _ . . . _ _ ._,._.._u_._..__.._. _ - . . - _ _ _ , .
I i A.2.5.3 Pioe Branch Connections Greater Than 4 in. Nominal Branch Pine Size. 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 Figure IWC-2520-9 to -13, inclusive, during each inspection interval. The welds selected _for examination shall include
- a. all-wet ; 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 specified value;-
- b. all welds at-terminal ends (see (e) below) of piping or branch runs;
- c. all dissimilar metal-weldst.
- d. additional welds, at structural discontinuities-(see (f) below) such that the total number of welds selected for examination includes-the c 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;
- 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 the 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,1 valve bodies, pump casings, pipe fittings (such as, elbows, tees, reducers, and flanges conforming to ANSI Standard B16.9), and pipe branch connections and fittings; A-35 ,
- ~ . a .- , __ _, _ - . . _ _._.___.....u.
. _- .- - . - _ = . . _ _ _ - - - . - - . .-- _ - - - . . > 3 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 transverse 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 Pumo Casina Welds, item C6.1_Q One hundred percent of all pump casing welds in each piping run examined under Examination Category C-F shall be surface 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 pumas is required to be examined. The examination may be performed from either tie 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 shall be surface examined in accordance with Figure IWC 2500-8 during each inspection interval. For multiple 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.'l' Pressure Vessels. Item C7.10 Pressure vessel 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. 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 A-36 ,
- e. ,
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 rcquired. A system hydrostatic test (IWC 5222) and accompanying VT ? 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 I 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 Giiid 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 (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A.2.7.2 Pioina. Item C7.30 Piping pressure-retaining boundaries (other than open ended sortions of systems) shall be visually examined (VT-2) during the system lea < age 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 ruplacements. 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 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.2.7.2.1 Piping, Item C7.40 Piping pressure-retaining boundaries (other than open-ended portions of systems)- shall be visually examined (VT-2) during the system hydrostatic test performed ".n 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 A-37 i w - r- w-3w.- p% y. yvv -wi., -
- i during ?he some inspection period of each inspection interval of Inspection Program B. The pressure retaining boundary includes only those portions of the systen rsquired to operate or support the safety system function up to and incirding 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 P_unt s . I t em C 7. 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 ccmponents 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 hydrostatic test (IWC-5222) and accompanying VT-2 examination are acceptable in lieu of the system pressuretest(IWC-5221)andVT2 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 Are components exempt or excluded within the pressure-retaining from the examination requirements, boundary [as except definedasbyspecified Note (7)]in IWA 5214(c) for repairs and replacements. The system hydrostatic test (IWC-5222) : hall 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 m1ve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. L A.2.7.4 Valves. Item C7.70 Valve >ressure retaining boundaries other than open-ended portions of l systems) s1all be visually examined (VT 2) during the tyttom leakage test in accordance with IWC-5221 during each inspection perico. 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. l Where portions of a system are subject to system pressure tests associated l l A 38 1
o s 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 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.2.7.4.1 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 performed in accordance with IWC-5222 Juring 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 (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A-39
o s I A.3 CLA ' REQUIREMENTS A.3.1 CATEGORY D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION A.? l.1 Ergssure-Retainina Comoonents. Item D1.10 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 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 requirements except as specified in IWA-5214(c). A.3.1.2 Intearal Attachment--Comoonent Sucoorts 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 correspond to those component supports selected by IWF-2510(b). A.3.1.3 Intearal Attachment--Mechanical and Hydraulic Snubbers. Item D1.30 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 Inteoral Attachment--Sorina Tvoe Supports. Item D1.40 Spring type supports shall be visually examined (VT-3) in accordance with Figure IWD-2500-1 durine each inspection interval. For multiple components within a system of simitar 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). l A-40
- O l
A.3.1.5 Intearal Attachmert--Constant load Tvoe Suonorts. Item D1.50 Constant load type supports shall be visually examined (VT-3) in accor-dance with figure IWD-25001 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.3.1.6 Intearal 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). t A.3.2 CATEGORY D B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERIC CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL A.3.2.1 Pressure-Retainino Components. Item D2.10 The pressure-retaining components in the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test (IWA-5000/ IWD-5222) each inspection period. A system hydrostatic test (IWD 5223) and accompanying VT-2 examinativa 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 seriod of each inspection interval for Inspection Program B. The system soundary 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.3.2.2 Intearal Attachment--Comoonent Suonorts and Restraints. Item 02.20 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). A-41
-- - o A.3.2.3 intearal Attachment--Mechanica11and 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 Intearal Attachment--Soriho Tvoe Supports. Item D2.40 in accordance with Figure IWD 2500-1 during each inspection interval. Spring type supports shall be v For mu within a system of similar design, function, and service, the integral i attachment of only one of the multiple components shall L,e examined. The
' integral attachments selected for examination shall correspond to those componentsupportsselectedbyIWF-2510(b).
A.3.2.5 Inteoral Attachment--Constant load Tvos Suonorts. Item D2.50 ! 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 ! tothosecomponentsupportsselectedbyIWF-2510(b). A.3.2.6 Inteoral Attachment--Shock Absorbert. Item D2.60 Shock absorbers shall be visually examined (VT-3) in accordance with i 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 examinatior, shall correspond to those component-supports selected by IWF-2510(b).
l l A.3.3 CATEGORY D-C SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM ' L SPENT FUEL STORAGE POOL A.3.3.1 Pressure-Retainino Comoonents. Item D3.10 The pressure retaining components in the pressure-retaining boundary shallbevisuallyexamined(VT-2)duringthesystempressuretestIWA5000/ IWD 5221 each inspection period. A system hydrostatic test (IWD-5223) and accompanying VT-2 examination ere 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 A-42 :
e e i boundary extends up to and including the first normally closed va1ve or valve capable of automatic closure as required to perform the safety related system , function. There are no exemptions or exclusions from these requirements I except as specified in IWA 5214(c). l A.3.3.2 1pteoral Attachment- Comoontnt Succorts and Restraints. Item D3.20 l Component supports and restraints shall be visually examined (VT-3) in ) accordance with figure IWD 25001 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 Inteoral Attachment--Mechanical and Hydraulic Snubbers. Item D3.30 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 Inteoral Attachment--Sorina Tvoe Sucoorts. Item D3.40 Spring 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 examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF 2510(b). i.3.3.5 Inteoral Attachment--Constant load Tvoe Suonorts. Item D3.50 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 examined. The integral attachments selected for examination shall correspond to those l componentsupportsselectedbyIWF-2510(b). i A.3.3.6 Inteoral Attachment--Shpek 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 components shall be examined. The integral attachments selected for examination shall correspond to those . componentsupportsseiectedbyIWF2510(b). l A-43
A.4 COMPONENT SUPPORTS A.4.1 CATEGORY F-A,' PLATE AND SHELL TYPE SUPPORTS A.4.1.1 Mechanical Connections to Pressure-Retainino Components and Buildina Structure. Item F1.10 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.4.1.2 Weld Connections to Buildina 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, tie 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 Intearal afd Nonintearal Suonorts. Item F1.30 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 inspection interval. Component supports selected for examination shall be the supports of those com)onents that are required to be examined under IWB, IWC, IWD, and IWE during tie 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 Disolacement Settinas of Guides and Stoos. Misalianment of Suonorts. Assembiv of Suonert items. Item F1.40 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 I interval. Component supports selected for examination shall be the supports of those com)onents that are required to be examined under IWB, IWC, IWD, and IWE during tie first interval. For multiple compont.nts within a system of similar design, function, and service, the supports of only one of the ! multiple components are required to be examined. l A 44 l.
i l 1 A.4.2 CATEGORY F B, LINEAR TYPE SUPPORTS ; A.4.2.1 tischanical Connections to Pressure-Retainino Comnonents and Buildina Structure, item F2.10 Mechanical connections to pressure rotaining components and the building structure shall be visually examined (VT-3) in accordance with Article IWF-1300 and Fioure IWF 1300-1 during each. inspecticle interval. Component supports selected for examination Gall be the supports of those components i that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For mutliple 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 Buildina 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 su) ports selected for examination shall be the su) ports of those components tlat are required to be examined under IWB, IWC, IWD, and'IWE.during the first interval. For mutliple components within a system of similar design, function, and service, the supports of only one of the multiple compov.9 .:re required to be examined. A.4.2.3 Weld and Mechanical Connections at Intermediate Joints in Multi- , connected Inteoral and Nonintearal Suooorts.-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 inspection interval . Component supports selected for examination shall be the supports of those com>onents that are required to be examined under IWB, IWC, IWD, and IWE during-tie first interval. For mutliple 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.4.2.4 Component Disolacement Settinas of Guides and Stons. Misalianment g[ Suocorts. Assembly of Sucoort items. Item F2.40 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 components that are required to be examined under IWB, IWC, IWD, and IWE during the first interval. For mutliple 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-45 t
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A.4.3 CATEGORY F-C, COMPONENT STANDARD SUPPORTS A.4.3.1 Mechanical Connections to Pressure-Retainino Components and_ l Buildina Structure. Item F3.10 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 l first interval. .For mutliple components within a system of similar design, ; function, and s9rvice, the supports of only one of the multiple components are required to be examined. I A.4.3.2 Weld Connections to Buildina 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-13001 during each inspection interval. Component supports selected for examination shall be the supports of those com)onents that are required to be examined under IWB, IWC, IWD, and IWE during t.1e first interval. For mutliple 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 Intearal and Nonintearal SuDDorts. Item F3.30 Weld and mechanical connectiens 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) inspection interval. Component supports selected for examination shall be the supports of those com)onents that are required to be examined under IWB, IWC, IWD,-and IWE_during tie first interval. For mutliple 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.4.3.4 Couonent disolacement settinas of Guides and Stoos. Misalianment of Suocorts. Assemb y of Sucoort items. Item F3.40 L Component displacement settings of guides and stops, misalignment of l 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 com)onents that are required to be examined under IWB, IWC, IWD, and
-IWE during tie first interval. For mutliple 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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3 y j A.4.3.5 forino Tvoe Supports. Conslant load Tvoe Suonorts. Shock Absorberb Hydraulic and Mechanical Tvoe Snubbers, item F3,50 Spring type supports, constant load type supports, shock absorbers, and hydraulic and mechanical type snubbers shall be visually examined (VT-4) 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 mutliple 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-47
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