The Status of the Series 5 Regulatory Guide

The Status of the Series 5 Regulatory Guide Revisions Steven L. Ward Material Control and Accounting Branch Division of Fuel Cycle Safety and Safeguards Office of Nuclear Material Safety and Safeguards NMMSS Users’ Meeting May 20, 2010 1

Overview • • • What is a regulatory guide? Overview of Series 5 Revisions Update process Questions & Answers 2

What is a regulatory guide? Regulatory guides (RGs) provide guidance on: (1) implementing specific parts of the NRC's regulations (2) techniques used by the NRC staff for evaluating specific problems or postulated accidents (3) data needed by the NRC staff for review of applications for permits or licenses (4) the preferred standard format and content for information submitted for NRC's approval of a specific program, license, permit, or certificate. 3

What is a regulatory guide? • 10 Divisions 1. Power Reactors 2. Research and Test Reactors 3. Fuels and Materials Facilities 4. Environmental and Siting 5. Materials and Plant Protection 6. Products 7. Transportation 8. Occupational Health 9. Antitrust and Financial Review 10. General 4

Overview of Series 5 • 25 guides for physical security • 31 guides for MC&A – 19 updated in the 70’s – 10 updated in the early 80’s – 2 updated in the 90’s 5

Revisions • Provide current information – Match current threat environment – Reflect current regulations – Incorporate current technology • Guidance for new fuel cycle facilities – GCEP – Laser 6

Revisions • Use best practices from past 40 years • Consolidate – Reduce overall number – Eliminate redundancy – Cut down on cross-referencing – Make more user friendly 7

Revisions • • Nondestructive Assay Techniques Designing to Minimize Residual Holdup Statistics Inventory Shipping, Receiving and Transfers Tamper-Indicating Seals 8

Revisions • 5. 26 Selection of Material Balance Areas and Item Control Areas • 5. 27 Special Nuclear Material Doorway Monitors • 5. 51 Management Review of Nuclear Material Control and Accounting Systems • 5. 67 MC&A for Uranium Enrichment Facilities (Cat III) 9

Revisions 5. 4 - Standard Analytical Methods for the Measurement of Uranium Tetrafluoride (UF 4) and Uranium Hexafluoride (UF 6) 5. 5 - Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets Nondestructive Assay Techniques for Special Nuclear Materials / Destructive Assay Techniques for Special Nuclear Materials 5. 9 - Guidelines for Germanium Spectroscopy Systems for Measurement of Special Nuclear Material 5. 11 - Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste 5. 21 - Nondestructive Uranium-235 Enrichment Assay by Gamma Ray Spectrometry 5. 23 - In Situ Assay of Plutonium Residual Holdup 5. 34 - Nondestructive Assay for Plutonium in Scrap Material by Spontaneous Fission Detection 10

Revisions 5. 37 - In Situ Assay of Enriched Uranium Residual Holdup 5. 38 - Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma Ray Spectrometry Nondestructive Assay Techniques 5. 39 - General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic for Special Nuclear Distribution, and Impurity Determinations Materials / Destructive Assay Techniques for Special Nuclear 5. 48 - Design Considerations- Systems for Measuring the Mass of Liquids Mater 5. 53 - Qualification, Calibration, and Error Estimation Methods for Nondestructive Assay 5. 58 - Considerations for Establishing Traceability of Special Nuclear Material Accounting Measurements 11

Revisions 5. 8 - Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations Design Considerations for Minimizing 5. 25 - Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Residual Holdup of Equipment for Wet Process Operations Special Nuclear Material 5. 42 - Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations 5. 3 - Statistical Terminology and Notation for Special Nuclear Materials Control and Accountability Statistical Concepts for 5. 18 - Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control Special Nuclear Material Control & 5. 22 - Assessment of the Assumption of Normality Accounting 5. 36 - Recommended Practice for Dealing with Outlying Observations 12

Revisions Material Control & Accounting Inventory Procedures 5. 13 - Conduct of Nuclear Material Physical Inventories 5. 33 - Statistical Evaluation of Material Unaccounted For 5. 28 - Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials Procedures for Shipping, Receiving & Internal Transfers 5. 49 - Internal Transfers of Special Nuclear Material 5. 57 - Shipping and Receiving Control of Strategic Special Nuclear Material 13

Revisions 5. 10 - Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of Pressure Sensitive Special Nuclear Material and Tamper. Indicating Device Seals for Protection of Special Nuclear Material 5. 15 - Tamper-Indicating Seals for the Protection and Control of Special Nuclear Material Final version of this guide will be published in July 2010 14

Update Process • Contractor develops technical basis for revision • NRC staff develop draft RG • Each draft RG will be available for public comment for 60 days • NRC will incorporate public comments and publish final RG 15

Questions? 16