NRC INSPECTION MANUAL Inspection Procedure 62709 IIPB CONFIGURATION RISK ASSESSMENT AND RISK MANAGEMENT PROCESS

01.01 The objective of this procedure is to independently assess the extent of conditions of a licensee’s implementation of Maintenance Rule (a)(4) requirements after significant problems associated with the licensee’s configuration risk assessment and risk management process have been identified. This procedure can also be used to independently assess the licensee's use of probabilistic safety assessment (PSA) and risk assessment tools for implementing the Maintenance Rule 10 CFR 50.65(a)(4) requirements. 62709-02 INSPECTION REQUIREMENTS The scope of the inspection is focused on those specific requirements listed below that are necessary to assess the adequacy of the licensee’s implementation of the Maintenance Rule (a)(4) requirements. The inspection may involve an in-depth review of the licensee’s use of PSA and risk assessment tools for the configuration risk assessment and risk management process. Due to the variation of PSA methodologies and analytical tools used by licensees, this inspection shall be performed by Regional Senior Reactor Analysts (SRAs), or Headquarters risk analysts supported by personnel who are qualified inspectors and have Maintenance Rule training. This procedure is to be used in conjunction wit

NRC INSPECTION MANUAL Inspection Procedure 71841 HUMAN PERFORMANCE

01.01 To assess the adequacy of the licensee’s root cause evaluation and corrective actions with respect to human performance. 01.02 To independently assess the extent of condition associated with the identified human performance root causes. 71841-02 INSPECTION REQUIREMENTS This inspection will substantiate that the licensee has adequately identified in their evaluation, the root cause(s)or contributing causes(s) and taken appropriate corrective actions for each human performance related issue. This inspection will also independently assess extent of condition(s) with respect to human performance such that each human performance identified problem has been evaluated for potential impacts on other plant equipment, programs or processes. In completing this inspection procedure it is not expected that NRC inspectors perform a full evaluation of each causal factor listed below. However, the inspectors should assure themselves that they have independently reviewed the underlined topic areas to determine their applicability to the human performance issue(s) of concern. The inspector should check each topic area for possible applicability and if the area is applicable should then review each causal factor within that section of the table. Questions to address each causal factor are provided in the specific guidance area of this procedure

NRC INSPECTION MANUAL IRIB INSPECTION PROCEDURE 37060 10 CFR 50.69 RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS INSPECTION

incorporated the license amendment under Title 10 of the Code of Federa

(2) Code of Federal Regulations

contents of this Appendix were merged from Inspection Manual Chapter (IMC) 124

Tests, Analyses and Acceptance Criteria (ITAAC).

that meets the acceptance criteria as stated in the licensee’s HED Resolution Inspections

a. Self-Study and On-the-Job Training (1) NRC Orientation (2) Code of Federal Regulations (3) Office Instructions

Note: The Decommissioning Project Managers/Technical Reviewers is a qualification i

93804-01 INSPECTION OBJECTIVE

The objective of the risk based team inspection effort is to assess the operational readiness of a commercial nuclear power plant utilizing risk information presented in a reactor plant's site specific probabilistic risk assessment (PRA), or other generic risk information. The inspection focuses on safety significant components and potential accident mitigation and recovery actions. Inspections conducted in accordance with this procedure are to determine that: 01.01 Plant challenges are minimized. 01.02 Safety systems, equipment, and components will be available, reliable, and operable. 01.03 Plant operators are capable of recognizing and responding appropriately to plant challenges, and capable of conducting timely and effective accident mitigation and recovery actions. 01.04 The licensee has appropriately factored available ris

INSPECTION OF THE ITAAC-RELATED DESIGN AND FABRICATION REQUIREMENTS

01.01 To verify that design and fabrication have been completed in accordance with applicable specifications, drawings, and approved procedures. 01.02 To determine whether licensee records establish an adequate basis for the acceptance of Inspection, Test, Analysis and Acceptance Criteria (ITAAC) with design and fabrication attributes. 01.03 To determine whether design and fabrication activities have been performed by qualified personnel. 01.04 To assess the implementation of the portion of the quality assurance (QA) program specific to design and fabrication activities and to assure problems are entered into the corrective action process. 65001.F-02 INSPECTION REQUIREMENTS AND GUIDANCE This inspection is performed to demonstrate that materials, components, and systems are designed and fabricated in conformance with requirements in the facility license, applicable Codes and standards, licensing commitments, Final Safety Analysis Report (FSAR), and regulations. All dimensions and related tolerances of the components must be in accordance with design drawings and specifications. ADesign/Fabrication Requirements @ includes specific ITAAC that refer to Codes and standards (e.g. American Society of Mechanical Engineers [ASME]) requirements for the fabrication of materials and components or discuss the adequacy of design by reference to analyses, calculations, bounding condition checks, functional assessments, engineering evaluations, and other design reports. Licensee reports that analyze the functional capabilities of the system and components should be reviewed to confirm compliance with the applicable documents including Codes and standards referred to in this paragraph

¶ 61,050).Rules of Procedure of the North American Electric Reliability Corporation TABLE OF CONTENTS

Appendix 4D is subject to further revisions to comply wit