ML17265A740

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Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components
ML17265A740
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/26/1999
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9909010024
Download: ML17265A740 (65)


Text

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CATEGORY 1 I'EGULA%kY INFORMATION DISTRIQUTI SYSTEM (RIDS)

ACCESSION NBR:9909010024 DOC".DATE: 99/08/26 NOTARIZED: NO DOCKET FACIL:50-244 .Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric RECXPIENT AFFILIATION Corp,'ECIP.NAME VISSING,G.S.

SUBJECT:

Requests approval for use of relief request number 35 re use of ASME Section XI Code,1995 Edition,1996 Addenda. Code will be used to develop plant 'fourth 10-year interval ISI program on class 1,2 & 3 components.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code E

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT COPXES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 LA 1 1 VISSING,G. 1 1 INTERNA: FILE CENTER 0. 1 1 NUDOCS -ABSTRACT OGC/RF 1 0 RES/DET/ERAB RES/DET/MEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D

0 E

NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9

p 4ND ROCHESTERGASANDEIECI1CCORPORATION 89FASTAYENUEi ROCHESTERr N Y Id6d90I101 ARFA CODE716 546-27D0 ROBERT C. MECREDY Vice President August 26, 1999 Nudea r Operations U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

Inservice Inspection Program ASME Section XI Required Examinations Fourth 10- Year Interval Request for relief Regarding Request No. 35 R.ED Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

The purpose of this letter is to seek approval for the use of Relief Request number 35 concerning the use of ASME Section XI Code, 1995 Edition, 1996 Addenda. This code will be used to develop our Fourth 10-Year Interval ISX Program on Class 1, 2, and 3 components, with the exception of Containment requirements of XWE and XWL.

This relief is requested pursuant to the provisions of 10 CFR 50.55a (a) (3) (i), the use of a later ASME Section XI Code. Justification is included in the enclosed relief request.

Also included as Attachment (I) is our evaluation, analysis, and classification of differences between the 1989 Code and the 1995 Code with 1996 Addenda. We have concluded from this evaluation that our proposed use of the 1995/1996 Code provides an acceptable level of quality and safety.

Since this relief request is being used as the basis for the development of our Fourth Interval ISI program, approval is needed by December 31, 1999.

Ver uly y urs, 02 PDR 6 I Robert C. Mecredy JSM/kgb:504 Enclosure Attachment

f r

/

I.,

I

XC: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I Division of Licensing'roject Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector

XC: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector

E<nclosure 1 Rochester Gas and Electric Corporation Ginna Station Docket No. 50/244 Fourth 10- Year Interval Request for Relief No. 35 ASME Code Section XI Alternative for the Fourth Interval ISI Program System/Component(s) for which Relief is Requested:

This Relief Request is requested for Inservice Inspection of all ASME Class 1, Class 2, and Class 3 components in accordance with the rules provided in ASME Section XI Code, Division 1.

II. Code Requirement:

10 CFR 50.55a specifies that the ASME Section XI Code, 1989 Edition, should be utilize for the preparation and use of licensees Inservice Inspection Program as well as their Repair and Replacement Program. Later editions of ASME Section if XI Codes may be utilized only approved by the NRC.

III. Code Requirement from Which Relief is Requested:

R.E. Ginna Nuclear Power Plant is requesting relief from utilizing the ASME Section XI Code, 1989 Edition, and is requesting permission to use the ASME Section XI Code, 1995 Edition with the 1996 Addenda for Class 1, 2, and 3 components for our Fourth Interval ISI Program in its place.

This Relief Request does not address Containment (IWE/IWLand applicable IWA) requirements. The Containment requirements shall be performed to ASME Section XI Code, 1992 Edition with the 1992 Addenda. This year and edition of ASME Section XI Code is the basis for the EPRI/ Industry Guideline which will be used to develop and implement our Containment Inspection Program.

Request for Relief No. 35 Page 1 of 3

IV. Basis for Relief:

Relief is requested pursuant to the provisions of 10 CFR 50.55a(a)(3)(i), request for approval to use a later ASME Section XI Code. The proposed alternative will provide an acceptable level of quality and safety.

On December 3, 1997, the NRC issued a proposed change in the Federal Register to amend 10 CFR 50.55a for Inservice Inspection. The proposed rulemaking endorsed the use of ASME Section XI Code, 1995 Edition with the 1996 Addenda for the Inservice Inspection as well as Repair or Replacement of Class 1, 2, and 3 components. This later code provides clarification to those requirements specified within the currently approved Code (1989 Section XI). By utilizing the later Section XI Code for Inservice Inspection as well as Repair and Replacement of Class 1, 2, and 3 components, the number of needed relief requests that the NRC would be required to process would be minimized.

It is requested that ASME Section XI Code, 1995 Edition with the 1996 Addenda be utilized to develop R.E. Ginna Nuclear Power Plant Fourth Interval Program.

V. Alternate Examinations:

R.E. Ginna Nuclear Power Plant requests that our Fourth Interval Inservice Inspection (ISI) Program as well as our Repair and Replacement Program shall conform to ASME Section XI Code, 1995 Edition with the 1996 Addenda for Class 1, 2, and 3 components including supports.

Request for Relief No. 35 Page 2 of 3

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~h VI. Justification for the Granting of Relief:

On December 3, 1997, the NRC issued a proposed change in the Federal Register to amend 10 CFR 50.55a for Inservice Inspection. The proposed Rulemaking endorsed the use of ASME Section XI Code, 1995 Edition with the 1996 Addenda for the Inservice Inspection as well as for Repair or Replacement of Class 1, 2, and 3 components.

The use of the Code (1995 with the 1996 Addenda) provides clarification to those requirements specified within the current approved Code (1989 Section XI Code).

NRC approval to utilize the later Section XI Code for Inservice Inspection, as well as Repair and Replacement of Class 1, 2, and 3 components, would minimize the number of needed relief requests that the NRC would be required to process.

VII. Implementation Schedule:

Examinations will be performed during the Fourth 10-year Interval, starting January 1, 2000.

Request for Relief No. 35 Page 3 of3

RELIEF REQUEST ¹ 35 ATTACHMENT(1)

ROCHESTER GAS 4 ELECTRIC CORPORATION R. K. GINNA NUCLEAR POWER PLANT ANALYSIS OF ASMK CODE, SECTION XI, 19S9 TO 1996 ADDENDA May 10, 1999 9909010024

RELIEF REQUEST ¹ 35 ATTACHMENT(1)

For purposes of Inservice Inspection, Rochester Gas and Electric Corporation. (RG&E) proposes to adopt the 1995 Edition with the 1996 Addenda of American Society of Mechanical Engineers (ASME)Section XI Code, except for Subsections IWE and IWL. For IWE and IWL, RG&E will use the 1992Edition with the 1992 Addenda of ASME Section XI. ASME Section IIICode, 1989 Edition shall be used for Repairs and Replacements, as applicable.

Rochester Gas & Electric Corporation has carefully reviewed all of the changes to the ASME Section XI Code from the 1989 Edition through the 1996 Addenda to determine the impact of each revision.

To properly understand these changes, it was necessary to review the Minutes of the ASME Boiler and Pressure Vessel Committee and review each modified paragraph in the context of the change.

When ASME modifies requirements, the specific modification often includes several related paragraphs. Also, it sometimes happens that two completely independent changes will modify the same paragraph. Therefore, it is not always possible to describe any change as merely a modification to a paragraph. Because of this, the evaluation of Section XI changes (Attachment 1, Table 1) is grouped by each action that was passed by the ASME Committee. The ASME descriptions of each action in the Minutes were helpful in determining which actions were editorial and which were clarification of the then current rules.

The attached evaluation lists the following five classifications of changes:

Errata: Basically this is correction of an ASME publication error. These changes do not affect requirements, because they are retroactive to the time the error was introduced.

Editorial: These changes have no technical impact and are so simple that the ASME Main Committee and Subcommittee agree that they do not even warrant discussion at the Committee meetings.

No Significant Change: These revisions consist of clarifications or editorial changes that are discussed and voted on at the Main Committee meeting.

Less Restrictive: These changes reduce the technical requirements of the Code.

Documentation or procedural changes are not listed, as they have no technical impact.

Justification is given for each of these changes.

More Restrictive: These changes increase technical requirements and therefore need no justification for acceptance.

RELIEF REQUEST 0 35 ATTACHMENT(1) assigned by the ASME Code Committee. Therefore, ~

Because these categorizations may seem to be subjective, it was decided to use the categories as change made to Section XI from 1989 to 1996 was reviewed and analyzed using the minutes from each of the ASME Main Committee meetings. (These minutes are available to the public.)

The evaluation describes why the reductions in requirements do not decrease safety. This evaluation is made by reviewing the change in requirements, using the Code Committee minutes, and considering all of the related Code requirements that must also be met.

Because Subsections IWE and IWL stand on their own merit and will not be updated to the 1996 Addenda, no evaluations have been made on the impact of changes. We have determined that other subsections are not afFected by the decision not to update these two subsections.

The evaluation shown in Table I was made to assess whether or not any of the changes made to Section XI, during the period from 1989 to 1996, reduced requirements in a way that would have a negative impact on safety.

On December 3, 1998, the Nuclear Regulatory Commission (NRC) issued a proposed rule incorporating the 1996 Addenda to Section XI into 10CFR50.55a. Five limitations to the use of the 1996 Addenda were proposed. The following addresses the acceptability of these five provisions for RG&E's next ISI interval.

1. Engineering Judgment The 1992 Addenda revision to the Foreword did not reduce or change any existing Code requirements. Rather, the change to the Foreword documented ASME's long-standing policy.

These provisions were previously endorsed by the NRC with their acceptance of the Introduction to Section XI from 1970 to 1974.

2. Quality Assurance The 1990 Addenda update to NQA-1-1989 made no substantial change in QA requirements.

Rochester Gas & Electric Corporation will apply its Appendix B QA Program to Section XI activities as required by the NRC.

3. Class 1 Piping The 1994 Addenda revision incorporating Cases N-198-1, N-322, and N-334 merely exempted from examination inaccessible welds that cannot be examined. Because these welds are inaccessible, the use of the revision reduces the number of relief requests being sent to the NRC.

It has no impact on the number of examinations being performed.

RELIEF REQUEST 8 35 ATTACHMENT(1)

4. Class 2 Piping This revision does not incorporate the provisions to which the proposed rulemaking purports to take exception. The provisions about which the proposed rulemaking expresses concern were added to IWC-1220, Table IWC-2500-1, Category C-F, and Figure IWC-2500-7, in the Winter 1983 Addenda (W83), which was adopted by the NRC on May 5, 1988, and has been used at almost every nuclear power plant in the U.S., without exception or limitation.
5. Reconciliation of Quality Requirements The NRC's concerns about the 1995 Addenda revision to IWA-4000 are based on the assumption that the revision permits an exception to 10 CFR Part 50, Appendix B, QA requirements. While RGB'elieves this conclusion to be inaccurate, RGB will implement all applicable requirements of Appendix B and will not use Section XI to take exception to Appendix B requirements.

The evaluation summarized in Table 1 shows that even though some changes to Section XI from 1989 to 1996 are classified as "less restrictive," the reductions in requirements have no impact on safety. This is the conclusion of the ASME Boiler and Pressure Vessel Committee, and our conclusion based on our extensive evaluation of every change made to Section XI from 1989 to the 1996 Edition.

RELIEF REQUEST ¹ 35, ATTACIIMENT1, TABLE 1 ROCHESTER GAS &, ELECI'RIC CORPORATION, R. E. GINNANUCLEAR POWER PLANT EVALUATIONOF REVISIONS TO ASME SECI'ION XI CODE - 1989 to 1996 Item ¹ Paragraphs AQected Description Classification Justification for Reduction 1996 ADDENDA Table IWA-1600-1, Underwater Welding - This revision adds requirements for No significant IWA4610, dry or wet underwater welding for repair/replacement change.

IWA4660 activities on of P-No. 8 and P-No. 4X materials. This change incorporates the provisions of Case N-516.

(2) IWA-2110 Terminology - This revision modifies the paragraphs to use No significant current terminology regarding repair/replacement activities change.

and programs.

(3) IWA-2315, Performance Demonstration Requirements for Eddy Current More Appendix IV Examination -, This revision adds new requirements for restrictive.

performance demonstration of eddy current examination systems and personnel and moves the existing requirements for qualification of personnel for analysis of steam generator eddy current examination date from Appendix IV to IWA-2315. The revision also incorporates the provisions of Case N-307-1 and Case N-553.

(4) IWA-2430 Inspection Intervals - This revision incorporates the No significant provisions of Case N-535. This change permits performance change.

of concurrent inspections to satisfy requirements and schedules of two successive inspection intervals.

Item 8 Paragraphs AQected Description Classification Justification for Reduction (5) IWA4132 Alternative Requirements for Items Rotated From Stock- Less There is no reduction in The revision incorporates the provisions of Case N-508-1. restrictive. safety since the removed This revision permits rotation ofpreviously installed snubber or relief valve snubbers and relief valves from stock and installed on undergoes testing to confirm components without the need for a Repair/Replacement Plan, its ability to meet design and an Authorized Inspection, or a NIS-2 Data Report, provided to detect any degradation.

the snubber or relief valve is removed from the component Expanded examinations are only for testing. required should any failure be detected, in which case; all the provisions for Repair /

Replacement would be invoked. This paragraph requires the Chvner to maintain traceability and to ensure the rotated item is used in the same design application.

(6) IWA-4160, Documentation of Repairs and Replacements - This revision More IWA-4180, adds requirements for documentation of modifications to restrictive.

IWA-4311, ensure that the configuration of the equipment is accurately IWA-4312 reflected in the design. The revision also adds a requirement that the revised record be certified in accordance with the Construction Code requirements for certification of the original records.

IWA-4221, Reconciliation of Design Requirements - This revision More IWA-4226 identifies how the Owner is to reconcile the technical aspects restrictive.

of repair and replacement work performed in accordance with a later Code Edition or Addenda than used for construction.

This change incorporates the provisions of Case N-554.

0 Item 8 Paragraphs Affected Description Classification Justification for Reduction IWAQ420, Metal Removal - This editorial revision clarifies that the No significant IWA4610 Section XI defect removal provisions are not applicable to change.

defect removal and welding performed in accordance with the applicable Construction Code.

IWA-4622, Procedure Qualification Test Assembly for Temper Bead No significant IWA-4632 Welding - This revision clarifies the dimensional change.

requirements for the procedure qualification test assembly for qualification of temper bead welding of similar materials.

(10) IWA-4634 Examination - This change relaxes the examination No significant requirements for alternative welding methods for dissimilar change.

metals. Instead of requiring radiography, and ifpractical, ultrasonic examination, any volumetric examination method may now be used.

IWB-3641, Acceptance Criteria for Austenitic Steel Piping - This Less This revision is based on ncwv C-3300 revision removes the penalties for flux welds. Service restrictive. test data which shows that the experience and additional &acture toughness data have penalty for flux welds was justified increasing the a/t max limitof 0.60 for flux welds to not justified. Therefore the 0.75 for austenitic materials. change has no impact on safety.

(12) IWB-3740, Analytical Evaluation of Operating Plant Events - Operating No significant Appendix L Plant Fatigue Assessment - This revision adds guidance for change.

evaluation of plant operating events for acceptability of components for which concern fatigue usage limits may have been exceeded or for which fatigue may bc a concern.

(13) IWC-3200, Supplemental Examinations - This revision makes No significant IWF-3200 IWC-3200 and IWF-3200 consistent with IWB-3200 and change.

IWE-3200, regarding supplemental examination. The change is editorial in nature, but makes supplemental examination optional.

Item 8 Paragraphs Affected Description Classification Justification for Reduction (14) 1-2110, Examination Requirements - This revision clarifies the No significant Table I-2000-1 examination requirements for reactor-vessel-to flange welds, change.

closure-head-to-flange welds, and reactor vessel CRD housing welds.

(15) VIII-3120, Appendix Sizing - This revision changes the length sizing acceptance No significant VIIISupplements 2, criteria, to 0.75 inch RMS (root mean square) &om the plus change.

10,11,& 12 or minus 1 inch criteria previously specified. The RMS criteria provides a better description of the sizing capability and reduces failures due to occasional inaccurate sizing. This change incorporates the provisions of Case N-538.

(16) A4300, Fatigue Crack Growth - This change provides consistency No significant A-5100, with the previous approach to fatigue crack growth, in which change.

A-5200, both the length and the depth are calculated, allowing for A-5300 fiaw shape change during growth.

(17) G-2120, Stress Intensification Factors - This revision provides an No significant G-2214, improved method for calculating the stress intensity factor K. change.

G-2215, Appendix G is used for development of pressure-temperature G-2222 limitcurves for operating plants. The existing calculation methodology was developed in the early 1970's.

(18) J-3000 Maintenance Requiring Subsequent Tests or Examination- No significant This revision identifies that safety and relief valve set point change.

adjustment is not considered a Section XI repair/replacement activity.

Item 8 Paragraphs Affected Description Classification Justification for Reduction (19) IWA-4150, EDITORIAL IWB-2411, IWB-2411, IWB-2412, IWB-2412, IWB-2430, IWB-3122, IWB-3122, IWB-3142, IWB-3420 (20) IWA-2220, ERRATA IWAA110, IWA4120, IWA4131, IWAPI80, IWA-4221, IWA4530, IWA-4621, IWA4641, K-5220, K-5300

Item ¹ Paragraphs Affected Description Classification Justification for Reduction 1995 ADDENDA IWA-1000, Elimination of Repair, Replacement, and Modification No significant IWA-2110, Classifications - This rewrite clarifies what activities are change.

IWA-2430, required for any kind of repair, replacement, or modification IWA-2500, activity. Combining IWA-4000 and IWA-7000, in the 1991 IWA-4000, Addenda, thus combining some of the diQering requirements IWA-5120, for repair and replacement, reduced the need for the two IWA-5214, different classifications, repair and replacement, as well as IWA-5250, the third, modification.

IWA-6210, IWA-6230, IWA-9000, IWB-I100, IWB-2420, IWB-3100, IWB-3200, IWC-1100, IWC-2420, IWC-3100, IWC-3200, IWD-I100, IWF-2220, IWF-3112, IWF-3122, IWF-5100, IWF-5400, Appendix II, D-1100, Appendix J

Item 0 Paragraphs Affected Description Classification Justification for Reduction (2) IWA4110 Through-Wall Leakage - This revision provides that when No significant discrepancies (such as through-wall leakage at other than at change.

mechanical connections) are to be repaired, any repair/replacement activities are to be performed in accordance with IWA-4000.

(3) IWA-2220, Eddy Current Examination - This revision incorporates the No significant IWA-2223 provisions of Case N-485-1. The change permits use of eddy change.

current as a surface examination technique.

(4) IWA-2221, Magnetic Particle Examination of Coated Materials - This No significant IWA-2222 change allows use of the yoke method for magnetic particle change.

examination on coated ferritic materials, without removing the coating. The revision incorporates the provisions of Case N-458 by reference to Section V. The Case provisions were added to Section V, Article 7, Appendix I, in the 1992 Addenda.

(5) IWA-2310, Qualification of Nondestructive Examination Personnel- No significant IWA-2323 This revision clarifies that NDE personnel qualified to change.

IWA-2300 of any Edition and Addenda of Section XI are qualified to all earlier Editions and Addenda.

(6) IWA-4120, Applicabilityof Repair/Replacement Requirements - This No significant IWA-4132, revision adds repair/replacement activity exemptions for the change.

IWA-4530 identified support items, as well as making corrections and clarifications to the current exemption provisions.

Clarification is added to require preservice inspections and tests of snubbers following a repair/replacement activity.

Item 8 Paragraphs Affected Description Classification Justification for Reduction IWAC131, Replacement of Small Items - Prior to this revision, Section More IWA4132 XI provided an exemption, or alternative, less restrictive restrictive.

requirements for NPS 1 (makeup capacity size for Class I) and smaller replacement items and installation thereof.

Repairs were not similarly exempted. This revision removes the inconsistency by applying the alternative requirements for replacement to all repair/replacement activities. The revision incorporates the provisions of Case N-544.

IWA-4220, Evaluations of Components - This revision clarifies that the More IWA-4223, Owner is required to document an evaluation or reanalysis restrictive.

IWA-4224, when the design or configuration of an item or system is IWA4225, changed. The evaluations or analyses are required to be IWA4311 certified in accordance with requirements of the Construction Code and Owner's Requirements.

(9) IWA-4221, Code Reconciliation - In the past, some reconciliation efforts No significant IWA-4222, have concentrated on administrative and trivial change.

IWA-4223, documentation issues that have no effect on adequacy of IWA-4224, affected equipment. This revision adds specific requirements IWA-4225, for reconciliation of later Editions and Addenda of the IWA-4226, Construction Code, or revised Owner's Requirements, for IWA-9000 procurement of components, parts, and material.

(10) IWA-4311, Rerating Pressure Retaining Equipment - The Code provides More IWA4312, specific requirements for repair/replacement activities of restrictive.

IWA-9000 items, but has not provided any requirements for rerating ASME Code equipment and systems. This revision specifies requirements for rerating of existing Code items in operating plants.

Item 8 Paragraphs Affected Description Classification Justification for Reduction (11) IWAQ451 Helical Coil Threaded Inserts - This revision provides tv No significant requirements for helical coil threaded inserts. Use of these change.

inserts has previously been identified as neither required nor prohibited, with no requirements nor guidance provided for controlling design or material properties. The revision incorporates the provisions of Case N-496.

(12) IWA-5213(a) Test Condition Holding Time - This revision eliminates the No significant holding time requirements after attaining test pressure and change.

temperature for system leakage tests. Hold times were inadvertently added during the previous mvrite of IWX-5000 in the 1991 Addenda.

(13) IWA-5244 Buried Components - This revision simplifies and clarifies No significant the requirements for pressure testing buried components with change.

and without isolable valves. The provisions now address redundant systems with isolable buried components.

(14) IWA-9000, IWB-2500-1 Examination Category B-F (Pressure Retaining No significant Table IWB-2500-1 k Dissimilar Metal Welds in Vessel Nozzles) B-J (Pressure change.

Retaining Welds in Piping) - This revision adds a definition for dissimilar metal weld, and revises the tables to be consistent with the fact that the glossary now contains the definition.

(15) IWA-9000 Owner - This revision revises the definition of Owner to be No significant consistent with the definition in Section IH and other ASME change.

Nuclear Codes and Standards.

Paragraphs Affected Description Classification Justification for Reduction IWB-1100, Integrally Welded Attachments - This revision clarifies use of No significant IWB-1210, the term "integrally welded attachments" to provide change.

IWB-2500, consistency with the provision in Section IH, Subsection NF.

Table IWB-3410-1, IWB-3516, IWB-3520, IWB-3522, IWC-1100, IWC-1210, IWC-2500, Table IWC-2500-1, Fig. IWC-2500-5, Table IWC-3410-1, IWC-3512, IWD-1100, IWD-1210, IWD-2500, Table IWD-2500-1, IWF-1300, Fig. IWF-1300-1 IWB-1220 Emergency Core Cooling Systems and Makeup Capacity- No significant This revision clarifies that emergency core cooling systems change.

are excluded from calculation of makeup capacity, because they do not operate under normal plant operating conditions.

10

Item 4 Paragraphs Affected Description Classification Justification for Reduction (18) IWB-2411, Inspection Schedule - This revision incorporates the Less Industry experience IWB-2412, provisions of Case N-509. The change modifies the restrictive. demonstrates that Welded IWB-2420, examinations to be performed on welded attachments for if Attachments, even failure IWB-2430, Examination Categories B-K, C-C, and D-A. The extent of occurs, do not violate the IWB-2500, examinations for welded attachments to piping, pumps, and pressure retaining function of IWC-2411, vessels is reduced from 100% of all welded attachments to the system that it is attached IWC-2412, 10%. For Category D-A, the 10% must include those welded to. By concentrating on IWC-2420, attachments most susceptible to corrosion. Welded Attachments most IWC-2430, susceptible to corrosion and Table IWC-2500-1, sampling 10% within each IWD-2411, system, adequate assurance IWD-2412, of detection of degradation is IWD-2420, maintained. Additionally, the IWD-2430, thickness exemption is Table IWD-2500-1 eliminated so more welded attachments are in the pool for selection. Further examination for cause is required whenever a failure of the attachment is discovered.

(19) Table IWD-2500-1 Examination method - This revision incorporates the More provisions of Case N-509. For Examination Category D-A, restrictive.

the required examination of a welded attachment is now a VT-1. Previously, a VT-3 was required.

(20) Table IWB-2500-1 Inspection of Nozzle to Vessel Welds - This revision No significant incorporates the provisions of Case N-521. This change change.

permits deferral of PWR reactor vessel nozzle welds and inside radius sections to the end of the interval. It applies to all but the first inspection interval.

11

Item 4 Paragraphs Affected Description Classification Justification for Reduction (21) Table IWB-2500-1 Examination of Control Rod Housing Bolting - This revision Less A Code required VT-2 incorporates the provisions of Case N-547. The revision restrictive. examination willbe eliminates the requirement for VT-1 visual examination of performed in accordance with CRD housing bolting. IWB-5220 in lieu of the VT-I visual examination. The elimination of the visual examination of the CRD housing bolting is not significant because any indication of boric acid residue in the area requires the bolting to be evaluated and corrective action taken.

(22) Table IWB-2500-1, Examination of Longitudinal Welds - This revision Less Experience has shown that Table IWC-2500-1 incorporates the provisions of Case N-524. The revision restrictive. reduction in length of reduces the extent of inservice examination of longitudinal longitudinal weld to be piping welds in Class 1 and 2 piping from the lesser of one examined does not affect pipe diameter or 12 inches to the portion of the longitudinal safety because the area most weld within the examination boundary of the intersecting vulnerable to problems is at circumferential weld required to be examined. the intersection of the longitudinal and girth welds, which is the area to be investigated.

(23) Fig. IWB-2500-15, Examinations Around Supports - This revision adds a Less Experience has shown that Fig. IWC-2500-5, footnote to permit examination of welded attachments restrictive. welded attachments can be Fig. IWD-2550-1 without removing any support member covering part of the properly examined without surface area to be examined. removing support members covering part of the surface area to be examined, because any cracks would be initiated at the attachment weld, not under the support member.

12

Item 8 Paragraphs Affected Description Classification Justification for Reduction (24) Table IWB-3410-1, Category B-E - This revision corrects the provisions to No significant IWB-3522 reflect deletion of Examination Category B-E in the 1993 change.

Addenda.

(25) Table IWC-2500-1, Examination Requirements - This revision incorporates the No significant Fig. IWC-2500-1, provision of Case NQ35-I. This revision permits surface change.

Fig. IWC-2500-2 examination in lieu ofvolumetric examination for thicknesses I/5 in. or less.

(26) Table IWC-2500-1 Dissimilar Metal Attachments - This revision clarifies the No significant provisions regarding examination of dissimilar metal change.

attachments.

(27) IWF-1230, Support Exemptions - This revision clarifies that supports on No significant IWF-2510 piping that is exempted &om volumetric, surface, or VT-1 or change.

VT-3 visual examination are also exempted &om examination.

(28) Appendix III-2300 Written Procedure Requirements - This change clarifies that No significant it is not necessary for the ANIIto approve NDE procedures. change.

(29) Appendix III-3410 Alternative Requirements for Piping Calibration Block No significant Thickness - This revision incorporates the provisions of Case change.

N461. The change permits a piping calibration block thickness tolerance of plus or minus 25%.

(30) Appendix VIIA310 Examination Questions and Test Specimens - This revision No significant clarifies that a random selection process controlled by the change.

employer's written practice may be used to ensure that no individual takes the same examination more than once. The revision also clarifies that "grading units" may be considered a test specimen for the practical examination.

13

Item 8 Paragraphs AQected Description Classification Justification for Reduction (31) Table VIII-3110-1 Component Qualification Supplements - This revision No significant includes a reference to coordinated implementation of piping change.

weld qualifications using Supplement 12 and vessel qualifications using Supplement 13.

(32) Appendix VIII; Qualification Requirements for Wrought Austenitic Piping No significant Supplements 2 k 3 Welds - This revision simplifies the specimen requirements change.

for wrought austenitic piping welds, by adding a tolerance on wall thickness.

(33) Appendix VIII; Qualification Requirements for Wrought Austenitic Piping No significant Supplements 2 k 12 Welds - This revision changes the length size sample set change.

selection criteria to reflect the requirements of the detection test set requirements in Supplement 2, and to allow combination of test sets in Supplement 12. This change reduces the overall number of demonstrations that candidates must perform.

(34) Appendix VIII; Conduct of Performance Demonstration - This revision No significant Supplement 4 k 6 incorporates the provisions of Case N-541. The revision change.

deletes the requirement (carried over from piping qualification) to obscure the inside surface and specimen identification for the "blind test," because some vessel examinations must be performed from the inside surface and some sample identification must be known by the individual to verify information regarding thickness, configuration, and geometry.

(35) Appendix VIII, Nozzle Inside Radius Section - This revision incorporates the No significant Supplement 5 provisions of Case N-542. This revision eliminates length change.

sizing demonstration requirements of Appendix VIII, Supplement 5 for the inside corner region. The acceptance criteria in Table IWB-3512-1 for the inside corner region are based on depth, not length; therefore there is no need to perform length sizing demonstration.

14

Item 0 Paragraphs Affected Description Classification Justification for Reduction (36) K-1200, K-1300, Assessments of Reactor Vessels - This revision modifies the No significant K-2200, K-2300, method for evaluating the reactor coolant pressure boundary change.

K-2400, KC 100, for continued service when the predicted upper shelf impact K-4210, K-4220, energy level, as defined in ASTM E 185, decreases below a Table K-4320-1, specified value. The change also adds requirements for Fig. K-4320-1, evaluating Level C and Level D service loadings. The K-4321, K-4332, revision incorporates the provisions of Case N-512.

K-5000, K-5100, K-5200, K-5300, K-5400 (37) IWA-2110, EDITORIAL IWB-2200, IWB-2412, IWC-2412, IWD-2412, IV-2000, VII-4223 (38) IWC-1223 ERRATA 1994 ADDENDA IWA-2420, Substitute Examinations and Tests - This change deletes the No significant IWA-6220 reference to substitute examinations and tests. change.

(2) IWA4150 Verification of Acceptability - This paragraph has been No significant changed to exempt modifications and like-for-like change.

replacements, which are not associated with service induced failures, from the verification requirements of IWA-4150.

The change incorporates the provisions of Case N-556.

15

I Paragraphs Affected Description Classification Justification for Reduction IWA-4170 Alternative Rules for Repairs, Replacements and No significant Modifications - This revision requires that when specific change.

provisions of later Editions and Addenda of Section XI are used for performing repair, replacement, and modification activities, all related requirements are to be met. The revision incorporates the provisions of Case N-389-1.

IWA-4810, Examination and Preservice Inspection - This revision No significant IWA4820 clarifies the examination and preservice inspection change.

requirements for both repairs and installation of replacements may be performed concurrently with the preservice inspections required by IWA-4820.

IWA-7000, Repair and Replacement - The 1991 Addenda consolidated No significant IWB-4000, repair and replacement rules into IWA-4000. This revision change.

IWB-7000, deletes the above Articles, which are no longer needed.

IWC4000, IWC-7000,
IWD4000, IWD-7000, IWF-4000, IWF-7000 IWA-9000 Definition of Owner - This revision modifies the definition of No significant "Owner" to be consistent with other nuclear Codes and change.

Standards.

16

Item 8 Paragraphs AQected Description Classification Justification for Reduction (7) IWB-1220, Exemption &om Examination - This revision exempts welds Less The provisions exempt welds IWC-1223, or portions of welds, which are located inside penetrations, restrictive. inside penetrations &om IWD-1220 &om examination. The change incorporates the provisions of examination. The welds are Case N-198-1, Case N-334, and Case N-322. inaccessible and could never be examined without major modification and/or redesign.

There is no impact on safety because the welds are inaccessable and could never be examined. Therefore, the change has no safety/technical impact.

(8) IWB-2411, Inspection Programs - This change clarifies the requirements No significant IWB-2412, for partial deferral of items &om the inspection program. change.

Table IWB-2500-1 (9) IWB-2412, Inspection Program B - This revision provides requirements More IWC-2412, for adding items or welds to the inspection schedule. restrictive.

IWD-2412 (10) Table IWB-2500-1 Examination Categories - This revision changes the tables to No significant clarify provisions and provide consistency. change.

(11) Table IWB-2500-1 Pump and Valve Internal Surface VT-3 Examination - This More revision continues to allow partial exanunation of pump and restrictive.

valve casing internals when only partial disassembly is performed, but requires full examination to be made at a later date when disassembly of the component permits a full examination.

(12) IWB-3710 Analytical Evaluation of Plant Operating Events - This More revision changes the scope statement to include operational restrictive.

integrity issues.

17

e Item 8 Paragraphs Affected Description Classification Justification for Reduction (13) IWF-2410 Inspection Programs - This revision adds rules to provide for More adding items or welds to the inspection schedule. restrictive.

(14) Appendix I, Calibration Blocks for Examination of Parts with Curved More Supplement 3 Surfaces - This revision reinstates requirements previously restrictive.

specified in the 1986 Edition of Section XI regarding calibration blocks for examination of parts with curved surfaces.

(15) VII-6000 Authorized Nuclear Inspector - This paragraph has been No significant deleted because it is redundant with the provisions contained change.

in IWA-2100.

(16) Appendix VIH, Qualification Requirements for Bolts and Studs - This No significant Supplement 8 revision permits the qualification notch of a stud or bolt to be change.

located within one diameter of the end opposite the search unit. The ultrasonic technique qualification can still be demonstrated with such a notch location. The change incorporates the provisions of Case N457.

(17) Appendix VIII, Requirements for Coordinated Implementation of Selected No significant Supplement 13 Aspects of Supplements 4, 5, 6 and 7 - This revision adds change.

Supplement 13, which provides specific performance demonstration requirements for ultrasonic examination, personnel, equipment and procedures.

(18) A-3000 Method for K, Determination - This revision modifies Less The less conservative A-3000 to allow the user to use a more accurate and less restrictive approach is acceptable conservative formulation for determining stress intensity because it has been verified to factors for any gradient stress distribution over the Qaw face. be more accurate based on published studies. Also, these provisions are nonmandatory.

(19) C-3220 EDITORIAL 18

Item 4 Paragraphs AQected Description Classification Justification for Reduction (20) IWA-5250, ERRATA IWF-2500, H-1300, Table H-5310-1, Table H-5310-2, H-5420, Table H-5410-1, Table H-6310-1, Table H-6310-2, K-4210 1993 ADDENDA IWA-1400, Terminology, Nuclear Power Plant - This revision changes No significant Footnote 1 the term 'power system'o 'nuclear power plant', for change.

consistency with other changes to 'nuclear power plant'n the 1991 Addenda and the 1992 Edition.

(2) Table IWA-1600-1, Referenced Standards and Specifications - The reference to No significant Appendix A, A4400 ASTM E 185 is clarified to be to the 1982 Edition, and the change.

title is corrected to "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels."

(3) IWA-2216 Remote Visual Examination - This change adds requirements More for color resolution for remote visual examination. When restrictive.

using remote visual examination, it is necessary to detect conditions such as corrosion. With black and white cameras, corrosion byproducts could be missed.

(4) IWA-2233, Eddy Current Examination - This revision references Section No significant Appendix IV V, Article 8, Appendix II for eddy current examination change.

because the Section XI, Appendix IV provisions were added to Section V in the 1992 Addenda.Section XI, Appendix IV still contains additional personnel requirements.

19

Item 8 Paragraphs Affected Description Classification Justification for Reduction (5) IWA-2430, Interval Extensions - This revision clarifies that inspection No significant IWB-2411, periods may be adjusted by up to one year to coincide with change.

IWB-2412, plant outages.

IWF-2410 (6) IWA-4130 Responsibilities, Repair Organization's Quality Assurance More Program - This revision adds requirements for a Quality restrictive.

Assurance Program for a repair organization when the organization is other than the Owner.

IWA-4130, Definition of Construction Codes - Previously,Section XI No significant IWA-4140, defined Construction Code in such a way that many people change.

IWA-4150, interpreted Construction Code to include the Design IWA-4170, Specifications or Owner's Specifications. This revision IWA-4310, clarifies that the Design Specifications and Owner's IWAA422, Requirements, although required by some Construction IWA-4423, Codes, are not part of the Construction Code.

IWA-4424, IWA-4425, IWA-4512, IWA-4542, IWA-4621, IWA-4910, IWA-9000 (8) IWA-4140 Repair/Replacement Program and Plan - This revision No significant clarifies that reference points are required to be recorded for change.

repairs only when required by IWA-2600.

(9) IWA-4180 Material - This revision deletes IWA-4180 because the No significant provisions are redundant and unnecessary. change.

20

Item 8 Paragraphs Affected Description Classification Justification for Reduction (10) Table IWA-5210-1, System Leakage Test Boundary - This revision provides for a Less The purpose of the test is to IWA-5221, system leakage test in lieu of a system hydrostatic test for restrictive. assure leak tightness, not to Table IWB-2500-1, Class 1 and 2 systems once during each inspection interval. overstress the components, IWB-5210, The change incorporates the provisions of Case N-498. which could cause problems.

IWB-5220, The new test willstill IWB-5230, demonstrate leak tightness, so Table IWB-5230-1, there is no impact on safety.

IWB-5240, Table IWC-2500-1, IWC-5210, IWC-5210, IWC-5220, IWC-5230, IWC-5240, IWD-5240 IWA-5211, System Pressure Tests, System Pneumatic Tests - This No significant IWC-5210, revision clarifies that a pneumatic test may be performed in change.

IWD-5210 lieu of a system leakage test or a system hydrostatic test for Class 2 or 3 steam systems, after repair, replacement, or alteration.

(12) IWA-5250 Corrective Action - This revision clarifies that the No significant requirement to remove a bolt and perform a VT-3 inspection change.

when leakage is found at a bolted joint does not apply to gaseous systems.

(13) IWA-9000 Glossary - This revision deletes definitions for "full stroke No significant time," "functional pressure differential (valve)," and change.

"operating convenience."

(14) Table IWB-2500-1, Weld Examinations - This revision clarifies that welds must No significant Table IWC-2500-1 be examined, to the extent practical, in the same sequence in change.

successive intervals as the sequence in which they were examined in the first interval.

21

'4 l'

Item 8 Paragraphs Affected Description Classification Justification for Reduction (15) IWB-2500, Examination Categories - This revision changes the No significant IWC-2500 identification lettering on the outside surfaces of the figures change.

to make them consistent.

(16) IWB-3730, Fracture Toughness Criteria for Protection Against Failure- Less The Code revision allows an Appendix K This change provides acceptance criteria and evaluation restrictive. evaluation to demonstrate procedures for assessment of reactor vessels when the equivalence with vessels predicted upper shelf Charpy impact energy level is below 50 which have Charpy impact ft-lbs. energy levels above 50 ft-lbs.

The new method is based on more advanced technology and therefore there is no reduction in safety.

(17) IWF-2420, IWF-2430 Successive Inspections, Additional Examinations - This No significant revision clarifies when successive inspections and additional change.

examinations are required for supports by providing more specific cross-references and expanding the description of the conditions that require these examinations.

(18) Appendix H Data Report Forms - This revision adds guidance for No significant completing the NIS-I and NIS-2 Owner's Report Forms, change.

similar to that provided in other sections of the Code.

(19) Appendix VH, Qualification of NDE Personnel for Ultrasonic Examinations No significant VH-3300, VH-4240 - This revision clarifies the intent of 'outside agency'or large change.

companies administering the examinations required by VHA342 and clarifies that no examination is required to meet the requirements for annual training.

(20) Appendix VH, Training Course Content and Duration - This revision More VH-4220 provides requirements for training of ultrasonic examination restrictive.

personnel previously qualified under a mitten practice not meeting the additional requirements of Appendix VH.

22

Item 8 Paragraphs Affected Description Classification Justification for Reduction (21) VIH-3110, VHI-3120, Performance Demonstration for Ultrasonic Examination No significant VHI-3130, Table VIH- Systems - This revision adds three new supplements for change.

3110-1, VHI-4120, performance demonstration requirements, including Fig. VHI-S1-2A, requirements for dissimilar metals (Supplement 10) and weld Supplements 2, 3, 4, overlays (Supplement 11). Supplement 12 provides some 6, Table VHI-S7-1, reduction in performance qualification requirements when Supplements 8, 9, 10, one individual is qualified for more than one method. The 11, 12 flaw depth sizing acceptance criteria is changed use a root mean square basis instead of linear regression. Many editorial revisions are also included.

(22) A4300 Fatigue Crack Growth Rate - The current provisions for More fatigue crack growth procedures do not clearly specify how restrictive.

compressive loads are to be handled. The revision adds a reliable method to account for compressive loads by accounting for crack closure effects.

(23) A-5200,A-9000 Flaw Analysis - This revision accommodates possible flaw More shape change due to fatigue crack growth and clarifies the restrictive.

plastic zone correction for fatigue growth analysis. The definition of 'end-of-period flaw size's clarified.

(24) Appendix F Inspection Plan Contents, Substitute Examinations or Tests- No significant This revision deletes the provisions for addressing substitute change.

examinations or tests in the inspection plan. The provisions were deleted because substitute examinations or tests are not permitted by Section XI.

(25) F-2500 Inspection Plan Contents, Co'ntainment Examinations - This No significant revision adds a new Supplement 5 to specifically address change.

containment vessels and containment liners.

(26) G-2215 Low Temperature Overpressure Protection Systems - This No significant revision adds guidance for low temperature overpressure change.

protection systems. The revision incorporates the provisions of Case N-514 into Appendix G.

23

Item 8 Paragraphs AQected Description Classification Justification for Reduction (27) Fig. IWA4546-1, EDITORIAL Fig. IWA4546-2, IWA-5250, IWB-3132, IWC-3122, IWF-3122,A-1100 (28) IWA-4412, ERRATA IWA-4910, Fig.

IWB-3641-1, A-4300, C-3210, C-3320, C-3420, C-3420 1992 ADDENDA Table IWA-1600-1, Qualification and Certification ofNDE Personnel - This More IWA-2310, revision adopts a new ASNT Standard CP-189 for restrictive.

IWA-2320, qualification and certification of nondestructive examination IWA-2330, personnel.

IWA-2350, IWA-2360, IWA-2370, IWA-2380, Appendix VH (2) Table IWA-1600-1, Referenced Standards and Specifications - This change No significant IWF-5200, clarifies the references the OM Part 4 (1987+ OMa-1988 change.

IWF-5300 Addenda) and adds reference to ASTM D974-1987.

24

Item 8 Paragraphs Affected Description Classification Justification for Reduction (3) Table IWA-1600-1, Essential Variable Tolerances - This revision incorporates No significant=

VIH4110, VIH-4120, the provisions of ASTM E 1324-1990, for measuring change.

Supp. 1 including electronic characteristics of ultrasonic instruments, and Figs. updates reference to ASTM E 1065, to the 1987A edition. In addition, the tolerances are modified on the basis of recent data. The change also permits system characterization as opposed to characterization of individual components. In addition, the revision provides for more control of sensitivity for narrow bandwidth systems.

(4) IWA-2216 Visual Examination Cleaning Requirements - IWA-2216 was No significant deleted because the requirements for cleaning prior to visual change.

examination have been added to Section V.

(5) IWA-2350 Limited Certification - This revision clarifies the definition of No significant limited certification and permits deletion of training topics change.

with corresponding reductions in training hours, examination content, and required experience. The change incoiporates the provisions of Case N-503.

(6) IWA-4110, Repairs and Replacements - This revision expands and No significant IWA-4120 clarifies the exemptions &om the scope of the repair and change.

replacement rules.

(7) IWA-4111, Alternative Requirements for Small Items - This revision More IWA-4120, deletes the exemption from the provisions of IWA-4000 for restrictive.

IWA4710 NPS 1 and smaller items, and replaces it with an alternative requirement to provide assurance that the item willfunction as designed. The reduced provisions are no longer applicable to Class 1 items larger than the makeup capability limitfor the plant, nor for heat exchanger tubing or sleeves or welded tube plugs for heat exchanger tubing.

25

Item 8 Paragraphs Affected Description Classification Justification for Reduction IWA4412, Tube and Tubesheet Hole Plugging - This revision combines No significant IWA-4413 the two paragraphs, because they contain similar change.

requirements for applicability, qualification and performance for Class I welded tube and tubesheet hole plugging.

(9) IWA-4512, Gas Tungsten-Arc Welding - This change involves lowering No significant IWA-4513, the postweld temperature maintenance for the gas change.

IWA-4522, tungsten-arc temperbead weld repair process &om a range of IWA-4532 450 F to 550 F to a minimum temperature of 300 F.

(10) IWA-5265 Location of Pressure Measuring Devices - This revision No significant clarifies that the 106 percent overpressurization limittakes change.

priority over achieving the minimum pressure throughout the system.

IWA-9000, Definition - This revision moves the definition of "belt line No significant Table IWB-2500-1 region", Rom Table IWB-2500-1 to IWA-9000. change.

(12) IWA-9000 Glossary - This revision adds definitions of "post No significant tensioning," "prestressed concrete," "reinforced concrete," change.

"tendon," "structural integrity test," and "unbonded tendons" and deletes "active valve," "exercising," "maintenance,"

"passive valve," "routine servicing," and "system resistance."

(13) IWB-1220 Scope and Responsibilities - This revision deletes the No significant reference to 10CFR50 for definition of the reactor coolant change.

pressure boundary and changes the definition of "in piping" to agree with Subsections IWC and IWD.

(14) Table IWB-2500-1 Examination Categories - The table was revised to clarify No significant that Examination Categories B-H and B-K-I are never change.

required to have volumetric examinations.

26

Item 8 Paragraphs Affected Description Classification Justification for Reduction (15) IWD-5222 System Hydrostatic Test - This revision exempts safety or No significant safety relief valve piping that discharges into a containment change.

pressure suppression pool from any kind of pressure test.

The previously required pneumatic test did not provide a meaningful test of this piping.

I-2500 Ultrasonic Thiclmess Measurements - Section XI does not More include provisions for measuring thichiess using ultrasonic restrictive.

equipment. This change provides guidance for performing any UT thickness measurements required by Section XI.

(17) Appendix VI Ultrasonic Examination of Bolts and Studs - The Appendix No significant has been deleted because its provisions have been change.

incorporated into Appendix VIII.

(18) A-4200, Kic Curves This revision modifies the Kic curve in Fig. No significant Fig. A4200-I A-4200-1 to agree with the source equations in Section III, change.

Appendix G.

(19) IWA-9000, ERRATA Fig. IWB-2500-20, IV-2700, A-9000, H4221, Fig. J-1000-1 1992 EDITION (I) Table IWA-2210-1 Visual Examinations - The units for character height were No significant changed from mils to inches for consistency with other Code change.

dimensional units.

(2) Table IWB-2500-1 Dissimilar Metal Welds - This revision clarifies that No significant Category B-F applies to dissimilar metal welds only in vessel

't change.

nozzles, not in piping.

27

Item 8 Paragraphs Affected Description Classification Justification for Reduction 1991 ADDENDA IWA-2110, Examination and Inspection - This revision adds coverage for More IWA-2200, concrete containments under the general provisions for restrictive.

IWA-2430 examination and inspection.

(2) Table IWA-1600-1, Qualification of Authorized Inspection Agencies - This No significant IWA-2120 revision updates the reference to ASME N626 to the 1991 change.

Addenda and makes accreditation of the Authorized Inspection Agency in accordance with the new provisions of ASME N626 mandatory.

(3) IWA-2321, Vision Tests - This revision changes the eye examination test No significant IWA-2322, requirements for near vision &om Jaeger J-1 to Snellen 20/25 change.

IWA-2323, and provides qualification requirements for the required IWA-2324, near-distance test chart. This revision incorporates the IWA-2325 provisions of Case N-490-1.

(4) IWA-2323, Level III Personnel; Inspection Program - This revision No significant IWB-2411, clarifies the provisions for recertification of Level IIINDE change.

IWB-2412 personnel and corrects the term "inspection period" to "inspection interval" in IWB-2411 and IWB-2412.

(5) IWA-2410 Code Edition and Addenda for Inservice Inspection - This No significant revision deletes paragraphs that conflicted with NRC change.

requirements in IOCFR50.55a.

28

Item 8 Paragraphs AQected Description Classification Justification for Reduction (6) IWA-4000, Repairs and Replacements - This revision consists of a No significant IWA-5120, complete rewrite of IWA-4000 and IWA-7000 into one change.

IWA-5250, Article, IWAA000. Provisions from IWB-4000 and IWA-6340, IWF4000 regarding repairs are also moved into the new IWA-7000, Article.

IWB-3113, IWB-3123, IWB-3133, IWB-3143, IWB-4100, IWB-4200, IWB-4300, IWB-7100, IWB-7300, IWC-3113, IWC-3124, IWC-3133, IWC-7100, IWD-7100, IWF-4100, IWF-4200, IWF-4300, IWF-4400, IWF-5400, IWF-7100 (7) IWA-4110, Guide to Section XI Repair and Maintenance Activities- No significant Appendix J This revision adds a new Nonmandatory Appendix J to change.

provide guidelines for distinguishing plant maintenance work from Section XI repair and replacement activities.

(8) IWA-4120 Exemptions - This revision clarifies that heat exchanger No significant tubing, and sleeves and welded plugs used for heat exchanger change.

tubing, are not exempt from the requirements of IWA-4000 for replacement items.

29

Item 8 Paragraphs Affected Description Classification Justification for Reduction (9) IWAP310 Defect Removal Procedure - After defect removal, No signiGcant IWA-4310 allows the resulting reduced section thickness to change.

be evaluated. This revision clarifies that the evaluation techniques given in some of the Section XI Appendices may be used. The change also removes the requirement for surface examination of the removal cavity when the full thickness of the weld is removed and the back side of the joint is inaccessible.

(10) IWA-4500 Temperbead Weld Repair - This revision incorporates the No significant provisions of Case N-432. The changes include addition of change.

the GTAW temperbead repair techniques and additional limits on the permissible depth and area of tempeibead repairs.

(11) Fig. IWA-4513.1-1 Temperbead Weld Repair - This revision adds a figure that No significant should have been included when IWA-4500 was revised in change.

the 1990 Addenda.

30

Item ¹ Paragraphs Affected Description Classification Justification for Reduction (12) IWA-5110, System Pressure Tests - This revision clarifies the system No significant IWA-5120, pressure test requirements for Class 1, 2, and 3 systems and change.

IWA-5210, components. Most of the changes are editorial, but this IWA-5220, revision replaces the system functional test and the system IWA-5246, inservice test with the system leakage test.

IWA-5250, IWA-5260, IWA-5300, Table IWB-2500-1, IWB-5210, IWB-5222, IWB-5240, Table IWC-2500-1, IWC-5210, IWC-5220, IWC-5240, Table IWD-2500-1, IWD-5210, IWD-5220, IWD-5240 (13) IWA-5240 VT-2 Visual Examination - This revision makes the No significant terminology for VT-2 visual examination consistent. change.

(14) IWA-9000 Glossary - This revision adds de6nitions for "design life" and No sigmficant "design lifetime." change.

(15) IWB-1220, Inaccessible Integral Attachments - This revision adds No significant IWC-1223, provisions to exempt integral attachments that are change.

IWC-1230, inaccessible for inspection.

IWD-1210, IWD-1220, Table IWD-2500-1 31

Item ¹ Paragraphs Affected Description Classification Justification for Reduction (16) IWB-2411, Inspection Programs - This revision clarifies that under No significant IWB-2412, Inspection Program B it is permissible to defer inspections to change.

Table IWB-2500-1, the end of the interval as allowed by the footnotes in the IWC-2412, 2500-1 Table and clarifies the associated percentage IWD-2412 requirements.

(17) IWB-2420, Successive Inspections - This revision corrects the No significant IWC-2420, terminology in IWB-2420 and IWC-2420 to be consistent change.

IWD-2420, with IWB-3000 and IWC-3000. In addition, similar F-2200 provisions for successive examinations are added for Class 3 components.

IWB-2430, Additional Examinations - This revision changes and No.significant IWC-2430, clarifies the extent of additional examinations to be change.

IWD-2430 performed upon discovery of a flaw or relevant condition that exceeds the acceptance criteria. The change also adds requirements for additional examinations when flaws or relevant conditions are found in Class 3 components.

(19) IWC-1220 Components Exempt From Examination - This revision No significant clarifies the exemptions for components within the RHR, change.

ECC, and CHR systems.

(20) IWC-5222 System Hydrostatic Test - This revision adds provisions for No significant combining the hydrostatic test of the Class 2 portion of the change.

BWR Main Steam System with the hydrostatic test of the Class 1 portion of the Main Steam System, when the Class 2 portion cannot be isolated. The change incorporates the provisions ofN-479.

(21) IWC-5222 Exemptions to System Hydrostatic Tests - New paragraph Less This change eliminates a test (g) exempts open ended vent and drain lines and open ended restrictive. that really was meaningless safety and relief valve discharge lines &om a flow path test. because the piping must be These lines were required to be subjected to a flow path test, examined by other means in lieu of a hydrostatic test, beyond the last shutoff valve. during installation.

32

Item 8 Paragraphs AIfected Description Classification Justification for Reduction (22) IWD-1210, Examination Requirements - This revision eliminates No significant.

IWD-1220, Examination Category D-C, Systems in Support of Residual change.

IWD-2200, Heat Removal &om Spent Fuel Storage Pool. The IWD-2500, requirements of Category D-C have been incorporated within Table IWD-2500-1 Categories D-A and D-B.

(23) IWF-2200 Adjustment, Repair, and Replacement - This revision adds More new requirements for examination of component supports restrictive.

following adjustment, repair, or replacement. This revision also permits preservice examination of some component supports prior to initial heating.

(24) III-1100 Ultrasonic Examination Calibration Blocks - This revision No significant clarifies that calibration block materials need not be the same change.

grade as the material to be examined, as required by III-3411, provided the provisions of IWA-2240 are met.

(25) Appendix VIII, Performance Demonstration for Ultrasonic Examination No significant Supplements 4, 5 k7 Systems - This revision clarifies the Appendix and permits a change.

10 percent tolerance on the thickness of the flawed specimens used for evaluation.

33

Item 8 Paragraphs Affected Description Classification Justification for Reduction (26) Table IWA-1600-1 ERRATA IWA-2110, IWA-2430, Fig. IWA4513.1-1, Table IWB-2500-1, IWB-3112, IWB-3132.1, Table IWC-2500-1, IWC-3112, IWC-3122.1, IWF-2410, IWF-2420 1990 ADDENDA IWA-1400, Records and Reports - This revision clarifies the Oxvner's No significant IWA-6100, responsibilities for preparation of plans, schedules, summary change.

IWA-6210, reports, and Form NIS-1 and NIS-2 Oxvner's Reports. It also IWA-6220, adds requirements for the content of the abstract of IWA-6230, examinations required for the Form NIS-1.

IWA-6240, IWA-6340 (2) IWA-1400, Inspection Reports, Schedules and Plans - This revision No significant IWA-2420, changes the provisions for the preparation and submittal, to change.

IWA-2440, the regulatory and enforcement authorities, of preservice and IWA-6230, inservice inspection reports, schedules and plans to clarify IWA-6240 that schedules are required to be prepared but not submitted.

34

Item 8 Paragraphs Affected Description Classification Justification for Reduction (3) IWA-1400 Chvner's Responsibilities for Flaw Evaluation - This revision No significant adds provisions to indicate that the Owner is responsible for change.

flaw evaluation calculations. IWA-1400(p) provides that the Owner is responsible for maintaining permanent records of flaw evaluations when the flaw exceeds the acceptance criteria of Section XI.

(4) IWA-2210 Qualifications for Visual Examination - This revision No significant replaces the provisions in Section XI regarding qualification change.

of personnel for visual examination with reference to the provisions in Article 9 of Section V, with supplementary provisions for Section XIuse.

(5) IWA-2322, Practical Examination Provisions for Level IH NDE No significant VH4322, Personnel - SNT-TC-1A provides for practical examinations change.

VH-4330, of NDE Level I and Level H qualifications. This change VH4342 requires practical examinations for quali6cation and recertification of Level IH NDE personnel for Section XI.

This revision incorporates the provisions of Case N-489.

IWA-4500, Repair Welding - This revision updates the temperbead No significant Fig. IWA-4513-1, welding requirements and replaces half bead welding with change.

Fig. IWA-4531.1-1, temperbead welding, for greater consistency with the welding Fig. IWA-4532.1-1 requirements in Section HI.

(7) IWA-5250 Corrective Action to be Taken for Leaks in Bolted No significant Connections - This revision changes the requirements to be change.

more specific as to which bolts should be examined when evidence of leakage is found in a bolted connection during the system pressure test.

(8) IWC-3513 Allowable Flaws for Volumetric Examination of Studs and No significant Bolts - This revision clarifies that for subsurface flaws in change.

studs and bolts, the standards of Table IWC-3513-1 apply.

35

Item 8 Paragraphs AQected Description Classification Justification for Reduction (9) IWF-1210, Sampling Plans for Inspection of Component Supports - This Less This revision allows a IWF-1230, revision adds a sampling plan for inspection of component restrictive. sampling of supports, rather IWF-2200, supports. In most cases, this change willcause a decrease in than a 100% examination, IWF-2410, the number of piping supports to be examined, and an based on the results of IWF-2420, increase in the number of other component supports to be evaluations made in the past.

IWF-2430, examined. This revision incorporates the provisions of Case There have been no IWF-2500, N-491. significant problems with the IWF-3112, supports and sampling IWF-3122, provides a realistic means to IWF-3410 provide appropriate evaluations.

(10) Appendix IV Eddy Current Examination ofNonferromagnetic Steam No significant Generator Heat Exchanger Tubing - This revision is a rmvrite change.

ofAppendix IV which incorporating latest multilrequency techniques for eddy current examination. This revision incorporates the provisions of Case N401-1.

A-1100, Definition of Terms Relating to Flaw Evaluation - This No significant A-5200, revision adds and modifies definitions relating to flaw change.

A-5300, evaluation and acceptance.

A-9000 (12) A4300 Fatigue Crack Growth Rate - This change provides fatigue Less The new methodology crack growth curves for ferritic steel in an air and water restrictive. provides an equivalence with environment. This revision incorporates the provisions of the current procedures.

Case N-463-1.

(13) Fig. AA400-I Effect of Fast Neutron Fluence and Copper Content Shift on No significant RT~ - This revision deletes the figure which was noted, "In change.

Course of Preparation."

(14) IWA-9000, EDITORIAL IWB-4332, Table IWD-2500-1 36

Item 8 Paragraphs Affected Description Classification Justification for Reduction (15) IWA-2110, ERRATA IWA-5214, IWA-7210, Fig. IWB-3610-1, IWB4241, IWB-4242, Table IWC-2500-1, Table IWC-3510-1, Table IWC-3511-1, Fig. G-2210-1, H-1300, H-3210, Table H4211-1, H4221, Table H-5310-1, Table H-5310-2, H-5420, Table H-5410-1, Table H-5410-2, H-6310, H-6320, Table H-6310-2 37

Item 8 Paragraphs Affected Description Classification Justification for Reduction 1989 ADDENDA IWA-1400, Repair Program - This revision adds new rules that require More IWA-4130, the Owner to have both a Repair Program and Repair Plans. restrictive.

IWA-6220 The Repair Program contains managerial and administrative (QA) controls, while the Repair Plans contain requirements and procedures specific to each repair.

(2) Table IWA-1600-1 Referenced Standards - Updated ANSVASME N626 to No significant 1988. change.

(3) Table IWA-1600-1, Ultrasonic Examination Requirements - This revision adds a No significant I-2000, Appendix VIII new mandatory appendix which requires performance change.

demonstration for qualification of procedures, equipment, and personnel used for ultrasonic detection and sizing of flaws in vessels, bolting, and piping welds. This addition incorporates the provisions of Case N409-2.

(4) IWA-2110 Duties of the Inspector - This revision deletes the reference to No significant the Inspection Specialist, because this designation is no change.

longer used in ANSVASMEN626. This change deletes the requirement for the Inspector to obtain assistance in reviewing technical content of NDE procedures.

IWA-2200 Examination Methods - This revision adds a reference to No significant Nonmandatory Appendix D for surface preparation prior to change.

NDE.

(6) IWA-2340 Level IIIEducation - This revision provides that a high No significant school equivalency examination need not be a federal or state change.

administered standardized test.

IWA-2430, Inspection Intervals - This revision clarifies the definition of No significant IWA-9000 "commercial service" for determining the start of each change.

inspection interval.

Item 8 Paragraphs AGected Description Classification Justification for Reduction (8) IWA-2431, Inspection Program - This revision deletes the 40 year limit No significant IWA-2432, on Inspection Programs A and B. The deletion of this limit change.

IWB-2411, provides continuing inservice inspection requirements for Table IWB-2412-1, plants aAer they have been operating for 40 years.

Table IWB-2500-1, IWC-2411, Table IWC-2412-1, IWD-2411, Table IWD-2412-1 (9) IWA-4322 Removal of Burned Surfaces - This revision clarifies that No significant when metal is thermally cut, removal of the burned surface change.

must be by mechanical means.

(10) IWA4700, Pressure Testing of Seal Welds - This revision exempts seal No significant IWA-9000 welds &om the system hydrostatic test requirements change.

following repair by welding.

IWA-4700 Pressure Testing of Half-bead Weld Repairs - This revision No significant provides an exemption from the hydrostatic test for vessel change.

repairs of up to 10 percent of the design thiclmess made by the half-bead welding technique.

(12) IWA-7320, Installation - This revision adds provisions for the More IWA-9000 installation and testing of replacements that are attached to restrictive.

the pressure boundary by mechanical means.

(13) IWA-9000 Glossary - Definitions are added for "oveipressure No significant protection" and "safety function". change.

(14) IWB-2500, Category B-D - This revision clarifies that the examination No significant IWB-3512, provisions apply to the specified areas of full penetration change.

Table IWB-2500-1, welded nozzles in vessels and are not restricted to only the Table IWB-3410-1 welds.

39

Item 8 Paragraphs Affected Description Classification Justification for Reduction (15) Table IWB-2500-1, Pressure Retaining Dissimilar Welds In Vessel Nozzles- No significant Fig. IWB-2500-8, This revision clarifies that Examination Category B-F change.

Table IWB-3410-1, applies to dissimilar metal welds only in vessel nozzles, not IWB-3514 lilplplllg.

(16) Table IWB-2500-1 Pressure Retaining Bolting Greater Than 2 Inches In No significant Diameter - This revision replaces the surface examination change.

requirement for reactor vessel closure head nuts (item B6.10) with a VT-1 visual examination meeting the acceptance criteria of IWB-3517. Prior to this revision, there was no acceptance criteria given for the surface examination.

(17) Table IWB-2500-1, Examination of Pressure Retaining Welds in Piping - This No significant Table IWC-2500-1 revision clarifies that pressure retaining welds in carbon and change.

low alloy steel piping are to be examined by ultrasonic examination for transverse indications only when reportable transverse indications were found during the preservice examination.

(18) IWB-3650, Acceptance Criteria for Flaws in Ferritic Piping - This Less The new methodology Appendix H revision provides evaluation techniques and acceptance restrictive. provides an equivalence with criteria for evaluating flaws in ferritic piping that exceed the the current procedures.

acceptance standards of IWB-3514.2. This revision incorporates the provisions of Case N-463.

IWB-4300 Heat Exchanger Tubing - This revision adds provisions for More repair of heat exchanger tubing by sleeving. The sleeving restrictive.

methods include explosive welding, fusion welding, brazing, and mechanical, hydraulic, or explosive expansion.

40

Item 8 Paragraphs Affected Description Classification Justification for Reduction (20) IWC-1221, Components Exempt From Examination - This revision was Less The revision incorporates the IWC-1222, intended to clarify the existing provisions regarding restrictive. provisions of Case N408-2 IWD-1220 exemptions &om examination for Class 2 and 3 piping which has been accepted by systems. However, the revision expanded the exemption to the NRC. The change merely include vessels of all sizes in exempt piping. provides that components in an exempt piping system are also exempt &om the inservice examinations. This change does not reduce safety.

(21) IWF-5400 Repairs and Replacements for Snubbers - This revision No significant deletes reference to ORM-1987, Part 4 (Rev. I) for repair change.

and replacement of snubbers because the repair and replacement requirements of ORM Part 4 are not consistent.

with Section XI requirements.

(22) Appendix F Valve Test Tables - This revision adds a new Footnote to No significant reference ANSVASME OM, Part 10, 5210 and 5320 for change.

identifying valves required to be exercised.

41

Item 4 Paragraphs Affected Description Classification Justification for Reduction (23) IWB-3641.3, ERRATA IWB-7100, IWB-7300, IWB-7400, IWB-7600, IWC-7200, IWC-7300, IWC-7600, IWD-7200, IWD-7300, IWD-7600, IWF-7100, IWF-7300, IWF-7310, IWF-7400, IWF-7600 file: rr35tb-i.wpd 42

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