ML19221B078
| ML19221B078 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-05.2.1., NUREG-75-87, NUREG-75-87-5.2.1., SRP-05.02.01.02, SRP-5.02.01.02, NUDOCS 7907120366 | |
| Download: ML19221B078 (5) | |
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o4 U.S. NUCLEAR REGULATORY COMMISSION 9
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STANDARD REVIEW PLAN
\\ '.".. I' OFFICE OF NUCLEAR REACTOR REGULATION SECTIO, 5.2.1.2*
APPLICABLE CrcE CASES REVIEW RESPONSIBILITIES Primary - Auxiliary Systens Branch (TSB)
Secondary - Mechanical Engineering Branch (MEB)
Materials Engineering Branch (MTEB) 1.
AREAS OF REVIEW The ASB determines the acceptability of A erican Society of Mechanical Engineers (ASME) and l Americu. National Standards Institute (ANSI) ccde case interpretations speci fied in the safety analysis report (SAR). These code cases rust be approved before being aoplied to ASME Boiler and Pressure Vessel Code,Section III, Class 1 pressure-retaining corponents within the reactor coolant pressure boundary, as stated in the Codes and Standarcs Rule, Section 50.55a(a)(2)(ii) of 10 CFR Part 50.
These code cases contain requirements or special rules which ray be used for the construction of pressure-retaining corpcnents of Ouality Group Classification A.
The MEB and MTES, on a generic basis, deterrine the aceptability of A5ME and ANSI code case interpretations that may be applied to ASME Code Section III, Class 1 pressure-retain-ing components within the reactor coolant pressure boundary (Quality Group Classification A). These branches review each revision tn applicable code cases. Code cases pertaining to raterials, faerication, and nondestructive testing are evaluated by the MTES. All other areas cosered by ASME code cases a e evaluated by tre MEB.
II.
ACCEPTANCE CRITERIA 1.
10 CFR Part 50, Appendix A, General Design Cr terion 1.
This criterion requires that structures, systems, and corponents irportant to safety shall be designed, fabricated, erected, and tested to quality standards comrensurate with the importance of the safety function to be perfor ed.
2.
10 CFR, 50.55a.
This rule establishes minf rum quality stand 3rds for the design, fabrication, erection, construction, testing, and inspection of certain corponents within the reactor coolant pressure boundary of boiling and pressurized water reactor nuclear power plants by requiring conformance with appropriate editions of specified published industry codes and standards.
Fo rma l l y 5. 2.1. 4 USNRC STANDARD REVIEW PLAN se e.
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3.
10 CFR Part 50, Appendix B " Quality Assurance Criteria for Nuclear Power Plants and Fuel Peprocessing Plants." This appendix establishes quality assurance requirements for the design, construction, and operation of those structures, systems, and com-ponents of nuclear power plants that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public.
4 Regulatory Guide 1.84, " Code Case Acceptability in ASME Section III - Design and Fabrication." This guide lists those Section III ASME code cases oriented to design and fabrication which are acceptable to the staff for implementation in the licensing of nuclear power plants.
5.
Regulatory Guide 1.85, " Code Case A..eptability in ASME Section III - Materials."
This guide lists those Section III ASME code cases oriented to materials and testing which are acceptable to the staff for implementation in the licensing of nuclear power plants.
III. REVIEW PROCEDURES The table provided by the applicant identifying those ASME code cases applied to Section III, Class I pressure-retaining components within the reactor coolant pressure boundary is checked for corpliance with the list of acceptable code cases it tnti fied in Regulatory Guides 1.84 and 1.85 and Tables 5.2.1.2-1 and 5.2.1.2-2.
Code cases applicable to other sections of the ASME Boiler and Pressure Vessel Code and referenced by Section III, Division 1, are also reviewed to determine their acceptability.
Table 5.2.1.2-1 lists those ASME Sections V and IX Code Cases oriented to nondestructive examination and welding and brazing qualifications, which are acceptable to the staf f for implementation in the licensing of nuclear power plants.
Table 5.2.1.2-2 lists those ASME Section XI Code Cases oriented to inservice inspection which are acceptable to the staf f for implerentation in the licensing of nuclear power plants.
ASME Section III, Division 2, Code Cases oriented to Concrete Reactor Vessels and Contain-rents are reviewed by the SEB on a case-by-case basis for impler.entation in the licensing of nuclear power plants pending approval of Section III. Division 2 of the code and the associ3ted Code cases by the Comission.
In the event an applicant should propose the use of a code case not previously reviewed by the staff, a review of tha code case is requested of the MEB or MTEB, as appropriate.
IV.
EVALUATION FINDINGS The staf f review snould verify that only acceptable ASME and ANSI code cases are specified in the SAR in order to arrive at conclusions of the following type, which are to be in-cluded in the staff's safety evaluation report:
Rev. 1 5.2.1.2-2 147 049
"The specified ASME and ANSI code cases whose requirements will be applied in the construction of pressure-retaining ASME Code Section III, Class 1 components within the reactor coolant pressure boundary (Quality Group Classification A), are accept-able to the staff. The staff corrludes that compliance with the requirements of these code cases will result in a component quality level commensurate with the importance of the safety function of the reactor coolant pressure boundary and is acceptable."
V.
REFERENCES 1.
10 CFR Part 50, Appendix A, General Design Criterion 1, " Quality Standards and Records."
2.
10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants."
3.
10 CFR S 50.55a, " Codes and Standards Rule."
4 ASME Boiler and Pressure Vessel Code,1977 Edition,Section III, " Nuclear Power Plant Components," Anerican Society of Mechanical Engineers (1977).
5.
ASME Boiler and Pressure Vessel Code, 1977 Edition, " Code Cases, Boilers and Pressure Vessels," American Society of Mechanical Engineers (1977).
6.
ASME Boiler and Pressure Vessel Code,1977 Edition, " Code Cases, Nuclear Components,"
American Society of Mechanical Engineers (1977).
7.
Regulatory Guide 1.84, " Code Case Acceptability in ASME Section III - Design and Fabrication.'
8.
Regulatory Guide 1.85, " Code Case Acceptability in ASME Section III - Materials."
347 050 S.2.1.2-3 Rev. 1
TAElE 5.2.1.2-1 CODE CASE ACCEPTABILITY, ASME SECTION 7-hT)MMThifCTIVE[EXAKI 4MliO{4XD]A_S"E_ S.ECT101 IX WELDING AND BRAZING QUALIFICATIONS Date of Code Council Cay Approval Title 1400 9-20-68 Welder Performance Qualification Tests for Joints of Non-ferrous Material,Section IX 1452 2-27-70 Use of Brazing Filler Material bag-Za,Section IX 1632 3-2-74 Peferencing the 5 Percent Nickel (P-llA Subgroup 2) Materials in Par. Q-10(b) of Section IX in Addition to the 9 Percent Nickel (P-llA Subgroup 1) Materials.
1693 8-11-75 Welding Procedure Qualification of Dissimilar Metal Welds when " Buttering" with Alloy Weld Metal and Heat Treatment May be Involved,Section IX N-92 6-30-75 Waiver of Ultrasonic Transfer Method, Seutions III, V and (1968)
VIII, Division 1.
Code Case 1693 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case. The rethod used to demonstrate actual correlation of the basic calibration block with production testing should be demonstrated and justified for each UT application.
1707 11-30-75 Alternate Perfarnance Qualifications,Section IX ( Applicable to 011 Sections, Including Section III, Division 1) 1816 3-23-77 Use of Irrersier Technique in Ultrasonic Examination per SA-388, Sections I, II, V, and VII, Divisions I and 2 Rev. 1 S. 2.1. 2-4 f
TABLE 5.2.1.?-2 CODE CASE ACCEPTABILITY, ASMF SECTION XI-TK5IrTFCl TNslTC'TToiiB~ IJTC'llTR Y6d'R' 'PL A iT YOMF0ht}iTS' "
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Date of Code Council Case Appr_ ova l Title 4-34 (1 551) 11-6-72 Inservice Inspection of Welds on Nuclear Corponents,Section XI N-72 (1646) 8-12-74 Partial Postponerent of Section XI Category B-C Examinations for Class 1 Components N-73
'1647) 8-12-74 l.rtial Postponement of Section XI Category B-D Examinations for Class 1 Components N-98 (1705-1) 3-1-75 Ultrasonic Examination - Calibratior Block Tolerances, Secticn XI N-il2 (1730) 11-3-75 Acceptance Standards for Section XI, Division 1, Class 2 and 3 Components N-ll3 (1731) 11-3-75 Sasic Calibration Blocks for Secticn XI, Division 1 -
Ultrasonic Examination of Welds 10 in, to 14 in. Thick N-ll8 (1738) 12-2-75 Acceptance Standards for Surface Indicationr, in Cladding, Sec+. ion XI N-167 (1804) 1-14-77 Minimum Section Thickness Requirenents for Repair of Nozzles,Section XI, Division 1
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- 5. 2.1. 2 -5 Rev. I