Document: NUREG-0800
Document ID: 2adccc8f-d828-4baf-b696-6ee4f776837b
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070416.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
ed Evaluation Findings, subsection IV. upon NUREG-0313, Rev. 2 and Generic Letter 88-01, which are more restrictive than RG 1.44. 437 Revise the SRP to address staff positions for Evaluation Findings, subsection IV. stainless steel weld metal which are more restrictive than RG 1.31. 438 Add Review Procedures for review of the acceptability Review Procedures subsection of nickel-chromium-iron alloys as control rod drive III.5. materials. 439 Revise the SRP to address staff positions No changes in this proposed draft supplementing EPRI Evolutionary Plant Utilities revision. Requirements Document (URD) requirements for control of impurities/contaminants to which NSSS materials could be exposed. 440 Revise the SRP to address staff positions related to Areas of Review, subsection I avoiding IGSCC in BWR austenitic stainless steel EMCB Review Interface 2 and materials, based upon NUREG-0313, Rev. 2 and Acceptance Criteria, subsection Generic Letter 88-01. II.4. 441 Revise the SRP to cite ANSI/ASME NQA-2 in and RG No changes in this proposed draft 1.37 for cleanliness controls. Also consider revising revision. RG 1.37 to cite ANSI/ASME NQA-2. 442 Evaluate the latest versions of AWS A4.2 and AWS No changes in this proposed draft A5.4 for regulatory endorsement (in RG 1.31). revision. 443 Revise the SRP to address staff positions related to Evaluation Findings, subsection IV. abrasive work (e.g. grinding) on austenitic stainless steel which are more restrictive than RG 1.37. 444 Evaluate the latest version of ASTM A-262 for No changes in this proposed draft regulatory endorsement (in RG 1.44). revision. 1305 Revise the SRP to address alternatives to RG 1.44 Acceptance Criteria, subsection guidance to use ASTM A-262 Practices A or E for II.4 and Review Procedures, verification of nonsensitization. subsection III.4. 1328 Revise RG 1.70 to cite ASME B&PVC NG-2000 for No changes in this proposed draft materials for reactor internals. revision.