ML19276G714
| ML19276G714 | |
| Person / Time | |
|---|---|
| Issue date: | 08/31/1979 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19276G715 | List: |
| References | |
| TASK-SC-721-4 REGGD-01.XXX, REGGD-1.XXX, NUDOCS 7908270141 | |
| Download: ML19276G714 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION August 1979 i
S OFFICE OF STANDARDS, DEVELOPMENT Division 1
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DRAFT REGULATORY GUIDE AND VALUE/ IMPACT STATEMENT Task SC 721-4 i
\\ * *v f INSERVICE INSPECTION CODE CASE ACCEPTABILITY ASME SECTION XI DIVISION 1 A.
INTRODUCTION Section 50.55a, " Codes and Standards," of 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," requires; win part, that O
each operating license for a boiling or pressurized water cooled nuclear power facility and each construction permit for a utilizationffacility be subject to the conditions in paragraph (g), " Inservice Inspection Requirements," of S50.55a.
Paragraph (g) requires, in part, that Class 1, 2, and 3 components and their supportsmeettherequirementsofSectionXI,"Rulesfo[InserviceInspection of Nuclear Power Plant Components,"1 of the Amer.ican Society of Mechanical Engineers (ASME)BoilerandPressureVesselCodeor'equivalentqualitystandards.
Paragraph 50.55a(b), in part, references the. latest editions and addenda in effect of Section XI of the Code and any; supplementary requirements to that section of the Code.
Footnote 6 to $50.55a states that the use of specific CodeCasesmaybeauthorizedbytheCommisdionuponrequestpursuantto
$50.55a(a)(2)(ii), which requires that proposed alternatives to the described fequirements or portions thereof' provide an acceptable level of quality and safety.
S General Design Criterion 1,'" Quality Standards and Records," of Appendix A
" General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that structures',ysystems, and components important to safety be designed, fabricated, e'rected, and tested to quality standards commensurate m
with the importance' of, th'e safety function to be parformed. Where generally recognizedcodes[andskandardsareused, Criterion 1requiresthattheybe v
3 TCopies may bet obtained from the American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, NY 10017.
e3 This regulatory guide ano the associated value/ impact statement are being issued in draft fonn to involvt e0 the public in the early stages of the development of a regulatory position in this area. They have not c
recefved complete staff review, have not been reviewed by the NRC Regulatory Requirements Review Commit-tee, and do not represent an official NRC staff position.
10 Public coments are being solicited on both drafts, the guide (including any implementation schedule) and
>A o the value/ impact statement. Coments on the value/ impact statement should be accompanied by supoorting
/ data. Coments on both drafts should be sent to the Secretary of the Comission, U.S. Nuclear Regulatory h Comission, Washington, D.C. 20555. Attention: Docketing and Service Granch, bDCT 1 0 1979
% Requests for single copies of issued guides and dfaft gt.l des (which may be reproduced) or for placement or "an autoraatic distribution list for single copias 4f future guides and draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, Attention:
Director, Division of Technical Infonnation and Document Control.
identified and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as necessary to ensure a quality
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product in keeping with the required safety function.
l This regulatory guide lists those Section XI ASME Code Cases that are I
generally acceptable to the NRC staff for implementation in the inservice l
inspection of light-water-cooled nuclear power plants.
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i B.
DISCUSSION The ASME Boiler and Pressure Vessel Committee publishes a document entitled
" Code Case;."2 Generally, the individual Code Cases that make up this document explain the intent of Code rules or provide fer alternative requirements under special circumstances.
f Most Code Cases are eventually superseded by revision of the Code and then are annulled by action of the ASME Council.
In such cases, the intent of the annulled Code Case becomes part of the revised Code, and therefore continued use of the Code Case intent is sanctioned under the rules of the Code.
In other cases, the Code Case is annulled because it is no longer acceptable or there
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t is no further requirement for it.
A Code Case that was approved for a particular g
situation and not for a generic application should be used only for the approved i
situation because annulment of such a Code Case could result in situations that would not meet Code requirements.
The ASME considers the use of Code Cases to be optional for the user and not a mandatory requirement.
The Code Cases listed in this guide are limited to those cases applicable l
to Section XI of the Code.
All published Code Cases that are applicable to Section XI of the Code and were in effect on January 1,1979, were reviewed for inclusion in this guide.
Code Cases that are not listed herein are either not endorsed or will require supplementary provisions on an individual plant basis to attain endorsement status.
The endorsement of a Code Case by this guide constitutes acceptance of its technical position for applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides.
Contingent endorsement if applicable is indicated in regulatory position 1 for
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e specific cases.
However, it is the responsibility of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recommended limitations resulting from Code Case usage.
Acceptance or endorsement by the NRC staff applies only to those Code Cases or Code Case revisions with the date of " Council Approval" as shown in the regulatory position of this guide.
Earlier or later revisions of a Code Case are not endorsed by this guide.
New Code Cases will require evaluation by the NRC staff to determine if they qualify for inclusion in the approved list.
Because of the continuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revision of existing Code Cases.
C.
REGULATORY POSITION 1.
The Section XI ASME Code Cases 2 listed below (by number, date of Council approval, and title) are acceptable to the NRC staff for application in the inservice inspection of components and their supports for water-cooled nuclear power plants.
Their use is acceptable within the limitations stated i
in the " Inquiry" and " Reply" sections of each individual Code Case, within the limitations of such NRC or other requirements as may exist, and within the additional limitations recommended by the NRC staff and given with the individual Code Case in the list.
1551 11/6/72 Inservice Inspection of Welds on Nuclear N-34 11/20/78t Components,Section XI 1646 8/12/74 Partial Postponement of Category B-C N-72 11/20/78t Examination for Class 1 Components,Section XI Code Case 1646 (N-72) is acceptable subject to the following condition in addition to those conditions specified in the Code Case:
If a flaw indication lies within or extends beyond the volume specified for examination, the volume examined shall be expanded as necessary to completely define the indication.
LA numerical listing of the Code Cases appears in the appendix.
tThe date on which the ASME Council reaffirmed the Code Case.
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1647 8/12/74 Partial Postponement of Category B-D N-73 11/20/78t Examination for Class 1 Components,Section XI
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i Code Case 1647 (N-73) is acceptable subject to the following condition f
in addition to those conditions specified in the Code Case:
If an indication is found within the volume examined, all the required l
examinations shall be performed to assist in evaluation of the overall j
condition.
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1705-1 3/1/76 Ultrasonic Examination - Calibration Block N-98 11/20/78t Tolerances,Section XI 1730 11/3/75 Acceptance Standards for Class 2 and 3 l
N-112 Components,Section XI, Division 1 i
i 1731 11/3/75 Basic Calibration Block for Ultra:onic I
N-113 11/20/78t Examination of Welds 10 in. to 13 in. Thick,Section XI, Division 1 1738 12/22/75 Examination - Acceptance Standards for N-118 11/20/78t Surface Indications in Cladding,Section XI Code Case 1738 (N-118) is acceptable subject to the following condition in addition to those conditions specified in the Code Case:
Replace
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the last sentence of the " Reply" with the following:
The provisions of this Code Case may not be applied for the examination of clad surfaces of nozzles, including the inner surface of the nozzle-to-Q vessel insert welds.
1804 1/14/77 Minimum Section Thickness Requirements for l
N-167 Repair of Nozzles,Section XI, Division 1 i
I N-210 3/20/78 Exemption to Hydrostatic Tests After Repairs, i
Section XI, Division 1 Code Case N-210 is acceptable subject to the following condition in l
addition to those conditions specified in the Code Case:
Replace l
paragraph (3) of the " Reply" with the following:
Repairs to piping, pumps, and valves where the depth of the repaired cavity does not exceed 25% of the wall thickness.
N-211 3/20/78 Recalibration of Ultrasonic Equipment Upon Change of Personnel,Section XI, Division 1 N-216 3/10/78 Alternate Rules for Reactor Vessel Closure Stud Examination,Section XI, Division 1 tThe date on which the ASKE Council reaffirmed the Code Case.
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2.
Code Cases that are not on the approved list of this guide (paragraph C.1) or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis.
D.
IMPLEMENTATION The purpose of this section is to provide information to applicants regarding the use of this regulatory guide.
1.
Except for those Code Cases that have been annulled by action of the ASME Council, the NRC staff will authorize appropriate use of the Code Cases listed in this guide under regulatory position 1 upon specific request by the applicant in accordance with footnote 6 to S50.55a, the Codes and Standards rule.
2.
The established procedures to be applied during an inspection interval or the established procedures for a preservice inspection need not be changed because a subsequent revision of the Code Case is listed as the approved version in this guide.
3.
The established procedures to be applied during an inspection interval or the established procedures for a preservice inspection that were previously approved for use need not be changed because the Code Case has been subsequently annulled.
4.
Code Cases on the approved list may be applied to procedures for an inspection interval and procedures for the inservice inspection that were estab-lished prior to the effective date of the Code Case within the limits specified in the Ccoe Case and applicable regulations or recommended in other regulatory guides.
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APPENDIX Numerical Listing of Code Cases 1551 (N-34) 1738 (N-118) 1646 (N-72) 1804 (N-167) 1647 (N-73)
N-210 1705-1 (N-98)
N-211 1730 (N-112)
N-216 1731 (N-113) 1 6
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