1、NTB-1-2013Training Program ReferenceMaterial for Use with ASME/ANS RA-Sa-2009NTB-1-2013 Training Program Reference Material for use with ASME/ANS RA-Sa-2009 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Application Part 1: General Requiremen
2、ts Part 2: Internal Events at Power Part 3: Internal Flood at Power Developed in cooperation with U.S. Nuclear Regulatory Commission PWR Owners Group ASME Standards Technology LLC NTB-1-2013 Date of Issuance: March 8, 2013 This document was prepared as an account of work sponsored by the U.S. Nuclea
3、r Regulatory Commission and the Pressurized Water Reactor Owners Group through the ASME Standards Technology, LLC (ASME ST-LLC). Neither ASME, the authors, nor others involved in the preparation or review of this document, nor any of their respective employees, members or persons acting on their beh
4、alf, make any warranty, express or implied, or assume any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represent that its use would not infringe upon privately owned rights. Reference herein to any spec
5、ific commercial product, process or service by trade name, trademark, manufacturer or otherwise does not necessarily constitute or imply its endorsement, recommendation or favoring by ASME or others involved in the preparation or review of this document, or any agency thereof. The views and opinions
6、 of the authors, contributors and reviewers of the document expressed herein do not necessarily reflect those of ASME or others involved in the preparation or review of this document, or any agency thereof. ASME does not “approve,” “rate”, or “endorse” any item, construction, proprietary device or a
7、ctivity. ASME does not take any position with respect to the validity of any patent rights asserted in connection with any items mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability for infringement of any applicable letters patent, nor assume an
8、y such liability. Users of a code or standard are expressly advised that determination of the validity of any such patent rights, and the risk of infringement of such rights, is entirely their own responsibility. Participation by federal agency representative(s) or person(s) affiliated with industry
9、 is not to be interpreted as government or industry endorsement of this publication. ASME is the registered trademark of The American Society of Mechanical Engineers. No part of this document may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written per
10、mission of the publisher. The American Society of Mechanical Engineers Two Park Avenue, New York, NY 10016-5990 Copyright 2013 by THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS All rights reserved Printed in the U.S.A. NTB-1-2013 iii TABLE OF CONTENTS 1.0 INTRODUCTION 1 2.0 OBJECTIVES OF THE TRAINING
11、MATERIAL 2 3.0 SCOPE OF THE TRAINING MATERIAL . 3 4.0 DISCUSSION OF REQUIREMENTS IN PART 1 OF ASME/ANS RA-Sa-2009 . 4 4.1 High Level Requirements (Section 1-1.3.2 of the ASME/ANS Standard) . 4 4.2 Supporting Requirements (Section 1-1.3.3 of the ASME/ANS Standard) . 4 4.3 Capability Categories (Secti
12、on 1-1.4 of the ASME/ANS Standard) 7 4.4 Addressing Multiple Hazard Groups (Section 1-1.7 of the ASME/ANS Standard) . 8 4.5 Determining Whether a Requirement is Met 8 5.0 DISCUSSION OF REQUIREMENTS IN PART 2 OF ASME/ANS RA-Sa-2009 . 10 5.1 Initiating Events Analysis Section 2-2.1 of the ASME/ANS RA-
13、Sa-2009 11 5.1.1 Supporting Requirements for HLR-IE-A 12 5.1.2 Supporting Requirements for HLR-IE-B 26 5.1.3 Supporting Requirements for HLR-IE-C 33 5.1.4 Supporting Requirements for HLR-IE-D 53 5.2 Accident Sequence Analysis Section 2-2.2 of the ASME/ANS RA-Sa-2009 60 5.2.1 Supporting Requirements
14、for HLR-AS-A 61 5.2.2 Supporting Requirements for HLR-AS-B . 75 5.2.3 Supporting Requirements for HLR-AS-C . 84 5.3 Success Criteria Analysis Section 2-2.3 of the ASME/ANS RA-Sa-2009 . 90 5.3.1 Supporting Requirements for HLR-SC-A . 91 5.3.2 Supporting Requirements for HLR-SC-B . 100 5.3.3 Supportin
15、g Requirements for HLR-SC-C . 107 5.4 System Analysis Section 2-2.4 of the ASME/ANS RA-Sa-2009 . 112 5.4.1 Supporting Requirements for HLR-SY-A 113 5.4.2 Supporting Requirements for HLR-SY-B . 139 5.4.3 Supporting Requirements for HLR-SY-C . 156 5.5 Human Reliability Analysis Section 2-2.5 of the AS
16、ME/ANS RA-Sa-2009 . 163 5.5.1 Supporting Requirements for HLR-HR-A 165 5.5.2 Supporting Requirements for HLR-HR-B 169 5.5.3 Supporting Requirements for HLR-HR-C 172 5.5.4 Supporting Requirements for HLR-HR-D 176 NTB-1-2013 iv 5.5.5 Supporting Requirements for HLR-HR-E 184 5.5.6 Supporting Requiremen
17、ts for HLR-HR-F . 189 5.5.7 Supporting Requirements for HLR-HR-G 193 5.5.8 Supporting Requirements for HLR-HR-H 203 5.5.9 Supporting Requirements for HLR-HR-I 207 5.6 Data Analysis Section 2-2.6 of the ASME/ANS RA-Sa-2009 . 213 5.6.1 Supporting Requirements for HLR-DA-A 214 5.6.2 Supporting Requirem
18、ents for HLR-DA-B 219 5.6.3 Supporting Requirements for HLR-DA-C 223 5.6.4 Supporting Requirements for HLR-DA-D 242 5.5.5 Supporting Requirements for HLR-DA-E 255 5.7 Quantification Section 2-2.7 of the ASME/ANS RA-Sa-2009 . 260 5.7.1 Supporting Requirements for HLR-QU-A 261 5.7.2 Supporting Require
19、ments for HLR-QU-B 268 5.7.3 Supporting Requirements for HLR-QU-C 279 5.7.4 Supporting Requirements for HLR-QU-D 283 5.7.5 Supporting Requirements for HLR-QU-E 291 5.7.6 Supporting Requirements for HLR-QU-F 298 5.8 LERF Analysis Section 2-2.8 of the ASME/ANS RA-Sa-2009 . 307 5.8.1 Supporting Require
20、ments for HLR-LE-A . 308 5.8.2 Supporting Requirements for HLR-LE-B . 314 5.8.3 Supporting Requirements for HLR-LE-C . 319 5.8.4 Supporting Requirements for HLR-LE-D . 335 5.8.5 Supporting Requirements for HLR-LE-E . 347 5.8.6 Supporting Requirements for HLR-LE-F . 352 5.8.7 Supporting Requirements
21、for HLR-LE-G . 356 6.0 PART 3: INTERNAL FLOOD SECTION 3.2 OF THE ASME/ANS RA-Sa-2009 365 6.1.1 Supporting Requirements for HLR-IFPP-A 367 6.1.2 Supporting Requirements for HLR-IFPP-B 373 6.2.1 Supporting Requirements for HLR-IFSO-A . 377 6.2.2 Supporting Requirements for HLR-IFSO-B . 384 6.3.1 Suppo
22、rting Requirements for HLR-IFSN-A . 389 6.3.2 Supporting Requirements for HLR-IFSN-B . 408 6.4.1 Supporting Requirements for HLR-IFEV-A . 413 NTB-1-2013 v 6.4.2 Supporting Requirements for HLR-IFEV-B . 423 6.5.1 Supporting Requirements for HLR-IFQU-A 428 6.5.2 Supporting Requirements for HLR-IFQU-B
23、440 LIST OF TABLES Table 1 IE-D2-1 SR Examples 56 Table 2 IE-D2-2 Documentation Mapping . 57 Table 3 AS-C2-1 SR Examples 86 Table 4 AS-C2-2 Documentation Mapping 87 Table 5 SC-C2-1 SR Examples . 109 Table 6 SC-C2-2 Documentation Mapping 110 Table 7 SY-C2-1 SR Examples 159 Table 8 SY-C2-2 Documentati
24、on Mapping 160 Table 9 HR-I2-1 SR Examples . 209 Table 10 HR-I2-2 Documentation Mapping . 210 Table 11 DA-E2-1 SR Examples 257 Table 12 DA-E2-2 Documentation Mapping 258 Table 13 QU-F2-1 SR Examples 301 Table 14 QU-F2-2 Documentation Mapping 302 Table 15 LE-G2-1 SR Examples 358 Table 16 LE-G2-2 Docu
25、mentation Mapping 359 Table 17 IFPP-B2-1 SR Examples 375 Table 18 IFPP-B2-2 Documentation Mapping . 375 Table 19 IFSO-B2-1 SR Examples . 386 Table 20 IFSO-B2-2 Documentation Mapping 386 Table 21 IFSN-B2-1 SR Examples . 410 Table 22 IFSN-B2-2 Documentation Mapping 411 Table 23 IFEV-B2-1 SR Examples .
26、 425 Table 24 IFEV-B2-2 Documentation Mapping 425 Table 25 IFQU-B2-1 SR Examples 442 Table 26 IFQU-B2-2 Documentation Framework 442 NTB-1-2013 vi INTENTIONALLY LEFT BLANK NTB-1-2013 1 1.0 INTRODUCTION Since 1998, ASME and ANS have been working on developing standards for a probabilistic risk assessm
27、ent (PRA) for nuclear power plants. Their combined efforts resulted in joint publication of ASME/ANS RA-S-2008, “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications” and the subsequent publication of ASME/ANS RA-Sa-2009 on February 2,
28、 2009. This standard “sets for the requirements for probabilistic risk assessment (PRAs) used to support risk-informed decision for commercial light water reactor nuclear power plants” and “establishes requirements for a Level 1 PRA of internal and external events for all plant operating modes.” (At
29、 this time, requirements addressing low power and shutdown conditions are not yet included.) The requirements established in this standard, however, are not prescriptive. The standard establishes requirements that are defining “what” needs to be in a technically acceptable baseline PRA; the requirem
30、ents do not define “how” to perform a technically acceptable baseline PRA. This document provides the reference material that supports the training program (jointly developed by ASME, NRC and PWROG) on understanding and using the ASME/ANS PRA Standard. NTB-1-2013 2 2.0 OBJECTIVES OF THE TRAINING MAT
31、ERIAL The objective of this training material is to help clarify the intent and purpose of the requirements in the ASME/ANS RA-Sa-2009 Standard. Specifically, this document provides additional explanation for each technical requirement of the ASME/ANS PRA Standard. The material generated in this eff
32、ort is intended to be used in the development, review and application of the ASME/ANS PRA Standard. This standard is being used to support risk-informed activities, some of which are regulatory activities. For some of the requirements, the NRC staff has taken objection; that is, for each requirement
33、, the staff has provided either “no objection,” “no objection with clarification” or “no objection subject to the following qualification,” and has defined these terms as: No objection. The staff has no objection to the requirement. No objection with clarification. The staff has no objection to the
34、requirement. However, the staff believes that the requirement, as written, is either unclear or ambiguous, and therefore the staff has provided its understanding of the requirement. No objection subject to the following qualification. The staff has a technical concern with the requirement and has pr
35、ovided a qualification to resolve the concern. To help the user, the staff position and resolution is also provided for each requirement. NTB-1-2013 3 3.0 SCOPE OF THE TRAINING MATERIAL ASME/ANS Standard is divided into ten parts as follows. Part 1: General Requirements for a Level 1 PRA, including
36、Large Early Release Frequency Part 2: Requirements for Internal Events At-Power PRA Part 3: Requirements for Internal Flood At-Power PRA Part 4: Requirements for Fires At-Power PRA Part 5: Requirements for Seismic Events At-Power PRA Part 6: Requirements for Screening and Conservative Analysis of Ot
37、her External Hazards At-Power Part 7: Requirements for High Wind Events At-Power PRA Part 8: Requirements for External Flood Events At-Power PRA Part 9: Requirements for Other External Hazards At-Power PRA Part 10: Seismic Margin Assessment Requirements At-Power At this time, the training material o
38、nly covers Parts 1, 2 and 3. NTB-1-2013 4 4.0 DISCUSSION OF REQUIREMENTS IN PART 1 OF ASME/ANS RA-Sa-2009 The majority of Part 1 of the standard is self-explanatory and it is believed that further explanation is not necessary to understand the intent. In Part 1, Section 1-2 of the standard, definiti
39、ons of terms used in the standard are provided. Additional explanation of these definitions is not provided; however, it is important to note that these definitions apply to each part of the standard. The technical requirements are established for different “hazard groups,” and organized by the tech
40、nical elements defining the PRA for each hazard group. The technical requirements are provided as “high level requirements” (HLRs) that are expanded with associated supporting requirements.” These supporting requirements may be defined to different “PRA Capability Categories.” This information is di
41、scussed in Section 1-1 of the standard, and additional explanation is provided in this chapter. 4.1 High Level Requirements (Section 1-1.3.2 of the ASME/ANS Standard) A set of objectives and related HLRs are provided for each PRA technical element for each hazard group. The intent of the HLRs is to
42、define the minimum requirements (at a high level) that are needed to meet the objectives of the technical element. Therefore, the HLRs also define the minimum requirements for meeting the ASME/ANS standard; as such, all PRAs based on the standard need to satisfy each of the HLRs. These HLRs are defi
43、ned in general terms, need to be met regardless of the capability category, and accommodate different approaches. The HLRs are written as “shall” statements. 4.2 Supporting Requirements (Section 1-1.3.3 of the ASME/ANS Standard) A set of associated SRs are provided for each HLR. The intent of SRs is
44、 to define the minimum requirements needed to meet the associated HLR. Therefore, for a given HLR, if the SRs are satisfied then the HLR will have been met. That is, determination of whether an HLR is met is based on whether the associated SRs are met. Whether or not every SR is needed for an HLR is
45、 application-dependent and is determined by the application process requirements. The SRs are written as “action statements.” That is, instead of writing an SR, for example, as “any dependency between the HFEs shall be,” the SR is written as “ACCOUNT for any dependency between the HFEs.” The action
46、verb provides the intent of the requirement and the verb is denoted in the standard in all capital letters. In understanding the SRs, it is helpful to keep these verbs in mind and the intended general meaning within the context of the standard. A list of the action verbs used in the standard with a
47、definition of their intent/meaning is provided below. NTB-1-2013 5 Action Verb Meaning ACCOUNT To give an explanation (usually fol. by for) ADDRESS To deal with or discuss: to address the issues ANALYZE To examine carefully and in detail so as to identify causes, key factors, possible results, etc.
48、ASSESS To estimate or judge the value, character, etc., of; evaluate BASE To make or form a base or foundation for CALCULATE To determine or ascertain by mathematical methods; compute CHARACTERIZE To describe the character or individual quality of CHECK, CONFIRM, ENSURE (CHECK) to investigate or ver
49、ify as to correctness: She checked the copy against the original. (CONFIRM) to establish the truth, accuracy, validity or genuineness of; corroborate; verify: This report confirms my suspicions. (ENSURE) to make sure or certain: measures to ensure the success of an undertaking COLLECT To gather together; assemble: The professor collected the students exams. COMBINE, INTEGRATE (COMBINE) to bring into or join in a close union or whole; unite (INTEGRATE) to bring together or incorporate (parts) into a whole. CONDUCT To direct in action or course; manage; carry on: to conduct a meetin
