Shopping Cart

No products in the cart.

ASME RA S 1.4 2013

$98.04

ASME RA-S-1.4 – 2013 Probabilistic Risk Assessment Standard for Advanced Non-LWR Nuclear Power Plants

Published By Publication Date Number of Pages
ASME 2013 501
Guaranteed Safe Checkout
Category:

If you have any questions, feel free to reach out to our online customer service team by clicking on the bottom right corner. We’re here to assist you 24/7.
Email:[email protected]

None

PDF Catalog

PDF Pages PDF Title
4 FOREWORD
6 PREPARATION OF TECHNICAL INQUIRIES TO THE
JOINT COMMITTEE ON NUCLEAR RISK MANAGEMENT
8 CONTRIBUTORS TO THE PROBABILISTIC RISK ASSESSMENT STANDARD FOR ADVANCED NON-LWR NUCLEAR POWER PLANTS
12 Section 1: Introduction
Contents
13 SECTION 1
INTRODUCTION
25 [1-1] ASME RA-S-2002, “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,” American Society of Mechanical Engineers.
[1-2] ASME/ANS RA-Sa-2009, “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,” Addendum A, American Society of Mechanical Engineers.
[1-3] ASME/ANS RA-Sb-2013, “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,” Addendum B, American Society of Mechanical Engineers.
26 Section 2: Acronyms and Definitions
Contents
27 SECTION 2
ACRONYMS AND DEFINITIONS
53 Section 3: Risk Assessment Application Process
Contents
54 SECTION 3
RISK ASSESSMENT APPLICATION PROCESS
63 Example:
Continuing with the previous TS example, the SSCs and plant activities related to the systems impacted by the proposed change in the SW, and that contribute to the change in RCFs (i.e., RCPB breach mitigation system, diesel generators, feedwater, and …
68 Section 4: Risk Assessment Technical Requirements
Contents
69 SECTION 4
RISK ASSESSMENT TECHNICAL REQUIREMENTS
77 [4-1] ASME/ANS RA-Sb-201x, “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications” (as revised in 2010 draft of Addendum B), American Society of Mechanical Engineers.
133 [SC-1] NUREG/BR-0167, “Software Quality Assurance Program and Guidelines,” U.S. Nuclear Regulatory Commission.
293 [FI-8] ASTM E119-07a, “Standard Test Methods for Fire Tests of Building Construction and Materials,” ASTM International.
482 SECTION 5: PRA CONFIGURATION CONTROL
CONTENTS
483 PRA CONFIGURATION CONTROL
485 SECTION 6: PEER REVIEW
CONTENTS
486 SECTION 6
PEER REVIEW
ASME RA S 1.4 2013
$98.04