Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
Verification of Added titles associated with the referenced sections of References, Editorial the ASME Boiler and Pressure Vessel Code. 135. Integrated Impact 973. Added reference to ASTM A-262 which was incorporated into Acceptance Criteria II.4. 136. Integrated Impact 975, SRP-UDP Consideration should be given to updating the citation standards citation update of ASTM A262-1970 pending the review and approval of the associated standard comparison. SRP Draft Section 5.3.1 Attachment A - Proposed Changes in Order of Occurrence Item Source Description DRAFT Rev. 2 - April 1996 5.3.1-34 137. Integrated Impact 1413. Added the applicable date to the reference for standard ASTM A708. 138. Integrated Impact 973. Added reference to ASTM A-708 which was incorporated into Acceptance Criteria II.4. 139. Editorial Moved and renumbered the reference for ASTM standard E-185 to be consistent with SRP-UDP guidance on the ordering of references and to accommodate the addition of other references. 140. Integrated Impact 1412 Revised the reference citation of ASTM E185 to cite the applicable version of the standard. 141. Integrated Impact 825. This is a placeholder integrated impact for ASTM E- 185. The cited version of this standard is not current. The latest version of this standard is ASTM E-185 1994. There are currently no plans to perform a comparison for this standard. 142. Integrated Impact 974. Added reference to WCAP-8678 which was incorporated into Acceptance Criteria II.4 SRP Draft Section 5.3.1 Attachment B - Cross Reference of Integrated Impacts 5.3.1-35 DRAFT Rev. 2 - April 1996 Integrated Issue SRP Subsections Affected Impact No. 811 Revise Acceptance Criteria and Review Procedures II, III, IV, and VI to reflect requirements of 10 CFR 50, Appendix G, and to use Regulatory Guide 1.99 as guidance relative to the effects of irradiation on reactor vessel material fracture toughness. 812 Revise Review Procedures for review of the II, III, IV, and VI adequacy of austenitic