ONR Transport Permissioning Stakeholder Event. 20% NCT Regulation

Similar documents
Review and Assessment of Engineering Factors

UNIVERSITY OF EDINBURGH GENERIC RISK ASSESSMENT - RADIATION RP/RA8 - WORK WITH X-RAY FLUORESCENCE ANALYSERS

Local Rules for Radiography: Ionising Radiation Regulations Working Instructions Staff MUST Follow

Guidance on the Ionising Radiations Regulations 1999 (IRR99)

QUALIFICATION TESTS FOR A TYPE B (U) PACKAGE

Regulatory Review of Safety Assessment for Decommissioning of Facilities Using Radioactive Material

Safety assessments for Aerodromes (Chapter 3 of the PANS-Aerodromes, 1 st ed)

Purpose. Scope. Process flow OPERATING PROCEDURE 07: HAZARD LOG MANAGEMENT

What should a radiation regulator do about NORM?

Safety Analysis: Event Classification

IAEA Regional Workshop Legal and Regulatory Aspects of Decommissioning of Research Reactors June Manila, Philippines

Hazardous Waste Training Plan. Supersedes: 02/15/16 (Rev.02) Preparer: Owner: Approver: EHS Team Member EHS Team Member EHS Manager

MANAGING INDUSTRIAL SITE RADIOGRAPHY WORK

IAEA SAFETY STANDARDS for protecting people and the environment

Planned reference and intervention levels in Finland

Aeronautical studies and Safety Assessment

BEFORE THE ENVIRONMENTAL PROTECTION AUTHORITY. of an Application under Section 38 of the Act for Marine Consents by Trans-Tasman Resources Limited

Safety Assessments Revised Toy Safety Directive 2009/48/EC

MINE SAFETY TARGETED ASSESSMENT PROGRAM. Ground or strata failure NSW metalliferous mines. April

Regional Workshop on the International Basic Safety Standards. Session 1: Dose Limits and Dose Constraints

DISTRIBUTION LIST. Preliminary Safety Report Chapter 19 Internal Hazards UK HPR1000 GDA. GNS Executive. GNS all staff. GNS and BRB all staff CGN EDF

Ionising Radiations Code of Practice & Guidance Contingency Arrangements

Moving Cambridge. City of Cambridge Transportation Master Plan Public Consultation Centre. March 7, :00 8:00 PM.

Yale University Human Research Protection Program

SUPPLIER HEALTH AND SAFETY. Supporting a healthy and safe working environment for our people and customers

Faculty/School: Pharmacy Initial Issue Date: Oct 2016

PIQCS HACCP Minimum Certification Standards

Systems of Accounting for and Control of Nuclear Material

Hazardous Materials Management Guidelines

IAEA SAFETY STANDARDS for protecting people and the environment

University of Cincinnati. Radiation Safety Committee Operations Guidelines Statement of Policy (RSC Guidelines) RSC Guidelines (revision 5)

1.0 PURPOSE 2.0 REFERENCES

ONR GUIDE DECOMMISSIONING. Nuclear Safety Technical Assessment Guide. NS-TAST-GD-026 Revision 4

Transportation Emergency Preparedness Program (TEPP) Model First Responder Procedure for Transportation Accidents Involving Radiological Materials

Release: 1. UEPOPL002A Licence to operate a reciprocating steam engine

(DD/MMM/YYYY): 10/01/2013 IP

SAFETY APPROACHES. The practical elimination approach of accident situations for water-cooled nuclear power reactors

So it s Reliable but is it Safe? - a More Balanced Approach To ATM Safety Assessment

10 December 2010 GUIDANCE FOR WATERTIGHT DOORS ON PASSENGER SHIPS WHICH MAY BE OPENED DURING NAVIGATION

TAMPA ELECTRIC COMPANY ENERGY SUPPLY HAZARDOUS ENERGY CONTROL LOCKOUT PROGRAM

The Safety Case. The safety case

Reviewed: DD Month Management of Closed Radioactive Sources

Evaluation and Demonstration of Safety of Decommissioning of

Nuclear Safety Regulation: Before and after Fukushima*

2016 American Academy of Actuaries. All rights reserved. May not be reproduced without express permission. ADDITIONAL LIABILITY ASSUMPTION OVERVIEW

HAZARDOUS WASTE OPERATIONS AND EMERGENCY RESPONSE

7.0 Compliance certificates

Justification and use of hand-held X-ray equipment

INTERIM ADVICE NOTE 171/12. Risk Based Principal Inspection Intervals

[Type here] MANAGEMENT OF X-RAY GENERATING EQUIPMENT

Guidance on the Legal Obligations for Importers, Retailers and Distributors of Category 1 Fireworks

IGEM/TD/2 Edition 2 with amendments July 2015 Communication 1779 Assessing the risks from high pressure Natural Gas pipelines

Procedure: Pressure equipment safety

HAZARD MANAGEMENT PROCEDURE

Phase B: Parameter Level Design

To comply with the OHS Act, the responsible manager must carry out and document the following:

Safe High Pressure Water Washing (HPWW) Requirement

HAZARD RECOGNITION EVALUATION & CONTROL. Procedure No. HR-405-PR-2 Division Human Resources. Supersedes n/a Board Policy Ref.

Maintenance and general care of secondary standard and field instruments

Global Certifying Authority for Scrum and Agile Professionals

Assessing Combinations of Hazards in a Probabilistic Safety Analysis

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS

Hazard Identification

Exposure estimations before and after the new EFSA-Guidance ECPA s perspective based on examples

Unit 5: Prioritize and Manage Hazards and Risks STUDENT GUIDE

The Safety Case. Structure of Safety Cases Safety Argument Notation

Policy for Evaluation of Certification Maintenance Requirements

Subject: Structural Certification Criteria Date: 10/11/18 Policy No: PS-AIR for Antennas, Radomes, and Other External Modifications

Risks Associated with Caissons on Ageing Offshore Facilities

Further guidance from BSI Technical Committee PH/5 - Personal Fall Protection on eyebolts for rope access

Safety Standards Acknowledgement and Consent (SSAC) CAP 1395

Best Practice RBI Technology Process by SVT-PP SIMTECH

TITLE 11. DEPARTMENT OF JUSTICE NOTICE OF PROPOSED RULEMAKING

USER MANUAL. MACMAG magnetic separator MHK MHF

Application of the Commission s Recommendations for the Protection of People in Emergency Exposure Situations. Table of contents

Severe Accident Management Programmes for Nuclear Power Plants

Understanding safety life cycles

HEALTH AND SAFETY EXECUTIVE HM NUCLEAR INSTALLATIONS INSPECTORATE

PERSONAL PROTECTIVE EQUIPMENT PROGRAM INTERNAL AND EXTERNAL PAGE: 1 DEPARTMENT: ALL OF: 5

ANNUAL REVIEW OF INDUSTRY EXPERIENCE - FINAL REPORT AS OF DECEMBER 31, 2016 COMMERCIAL VEHICLES ALBERTA AUTO INSURANCE RATE BOARD 29 SEPTEMBER 2017

Radon Chamber Accreditation Policy. 1.0 Introduction

RP COP006- Working with Unsealed Radioactive material

Project & Task Work Health and Safety Risk Management Procedure

DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS

MANUFACTURING TECHNICAL INSTRUCTIONS - SAFETY FALL HAZARD CONTROL REQUIREMENTS SERIES & NO. SMI - 157

Age Concern Hounslow Manual Handling Risk Assessment PART ONE PRELIMINARY RISK ASSESSMENT

Traceable calibration of automatic weighing instruments in dynamic operation

Nuclear and radiation safety: Guidance for emergency response

International Standard for Athlete Evaluation. September 2016

International Association of Drilling Contractors North Sea Chapter HPHT Guidance on MODU Safety Case Content

OBJECTIVE 6: FIELD RADIOLOGICAL MONITORING - AMBIENT RADIATION MONITORING

The above item, as tested, is considered to comply with the above specifications. PAGE 1 OF 6

CONTRACTOR WHS HAZARD STANDARD HAZARDOUS CHEMICALS EXTERNAL USE ONLY

EN ISO/IEC Technical Requirements

User Information Sheet 015

Arc flash versus arc resistant; different concerns

TEMPLE UNIVERSITY ENVIRONMENTAL HEALTH AND RADIATION SAFETY

Work Health and Safety Risk Management Procedures

RISK ASSESSMENT GUIDE

Revisions to the National Standard 1 Guidelines:

Transcription:

ONR Transport Permissioning Stakeholder Event 20% NCT Regulation

Introduction The NCT 20% regulation & guidance quick overview Issues & ONR view on how they can be resolved Future changes to improve the regulation

The Regulation e.g. 624. A package to be qualified as Type IP-2shall be designed to meet the requirements for Type IP-1 as specified in para. 623 and, in addition,if it were subjected to the tests specified in paras 722 and 723, it would prevent: (b) More than a 20% increase in the maximum radiation level at any external surface of the package.

The Regulation -scope CA approved, self-approved IP-II*, IP-III, Type A, Type B, Type C New designs, mods, renewals, validations etc. Damage/movement to packaging, furniture or source(s). Other effects e.g. neutron multiplication (as a consequence) * Only free drop & stacking tests apply to IP-2 [722 & 723]

History Regs RCT NCT ACT Notes 1961 1967 2mSv/h @ contact - - Different for Cat I, II, III Testing brought in (doesn t 2mSv/h @ 10mSv/h @ differentiate between contact - 1m NCT/ACT) 1973 1985 2mSv/h @ contact 2mSv/h @ contact No Increase following NCT <20% increase following NCT 10mSv/h @ 1m 10mSv/h @ 1m Requirement for intermediate NCT testing No increase following NCT too restrictive so <20% introduced

What the guidance (SSG-26) says 624.4. For packages exhibiting little external deformation and negligible internal movement of the radioactive contents or shielding, a careful visual examination may provide sufficient assurance that the surface radiation level is essentially unchanged. 624.5. If it is considered that the maximum surface radiation level has increased, monitoring tests should be performed to confirm this.

Guidance cont. 624.6. The method of evaluation of the increase in maximum surface radiation level varies from one design to another. This could lead to discrepancies in evaluating a package s capability to satisfy the requirements of para. 624(b). One way of overcoming this problem may be to define the maximum surface area of the package over which the surface radiation level is assessed. Thus, for example, individual measurements may be taken over areas not greater than 10% of the total surface area of the package. The package surface may be marked to define the subdivisions to be considered and tests conducted by means of a test source suitable for the package (i.e. Co-60 or Na-24 for general package use or specific nuclides for a certain package design). It may be necessary to consider the effect of increased localized radiation levels when evaluating surface dose rate increases.

Guidance cont. 624.7. The increase in maximum radiation level should be evaluated on the basis of the measurements taken both before and after the tests specified in para. 624, and the resulting data should be compared to determine whether the package satisfies the requirement or not. The pre-and post-test maximum radiation levels may be at different positions on the package.

Guidance cont. 624.8. The maximum radiation level should be determined taking into account potential amplifying phenomena, such as internal movement of contents, or, in the case of packages containing liquids, segregation and precipitation of the radionuclides.

Ways to demonstrate compliance: ONR expectations inspectiontogether with reasoned argument (if it is evident that there is little change/movement to package and sources) pre/post-drop measurementsfollowing inspection of a dummy source and replacement of a real source, taking into account measurement uncertainty, and realistically it may be difficult to replace the source if there has been movement to the furniture FEA calculation drop test data from another package and robust justification for why it is applicable any combinationof the above, or method acceptable to the CA

Issues with demonstration Little knowledge of what sources will be transported in the package at the design stage Some characterisation of contents is always necessary Not acceptable to not know the size of the hazard Could cause containment issues e.g. if internal furniture and sources are not characterised, sharps or friction could puncture containment, and radiolysis or hydrolysis could occur may need optioneering process to determine: a) bounding case(s)and b) solution or solutions for ensuring and demonstrating that there won t be movement or damage of/to sources The outcome of the optioneeringprocess needs to be documented with calculations/reasoned argument If the content changes later, may need to update safety case, or consider modifications to the package/using a different package

Issues with demonstration This regulation could drive perverse arrangements e.g. by putting source at edge of the package Para 301: Doses to persons shall be below the relevant dose limits. Protection and safety shall be optimizedin order that the magnitude of individual doses, the number of persons exposed and the likelihood of incurring exposure shall be kept as low as reasonably achievable, economic and social factors being taken into account, within the restriction that the doses to individuals are subject to dose constraints. And IRR (1999) is applicable All the law applies all the time when it says it does

Issues with demonstration It s difficult to show that the source definitely won t move Need to consider the impact of Normal Conditions Tests. The most significant is likely to be the 0.3/0.6 /0.9/1.2 drop (depending on gross mass) for source damage or movement The internals need to give a reasonable confidence that the sources can t move or rattle around

Issues with demonstration The package is monitored before and after shipment and there is never any increase observed. There has been safe practice for 20+ years. Not proof of compliance with NCT conditions However historical operational data can be provided as evidence and form part of safety case to build picture of package performance. Bottom line:we (ONR) need evidence to demonstrate to the public that any package meets all the requirements of regulations, and that there is no potential for increased dosesto workers or the public due to minor mishaps

Issues with demonstration If this regulation has been in place for so long, why haven t we (ONR) looked at compliance in detail before now? With the change in IAEA regulation in 2012 (into effect 2015), meaning that routine conditions need to be demonstrated in design, increased resource was brought in to look at shielding and package dose rates identified some inconsistent practices...but we think that resolution is not insurmountable

Issues with demonstration We are not able to disregard any of the regulations however. if a comprehensive case is submitted and there is a shortfall in compliance, alternative options can be explored (special arrangement or CDG Reg 12 Authorisation). BUT. all potential solutions and combinations of solutions must be fully considered with evidence, calculation and /or reasoned argument OPTIONEERING PHASE the reasons for discounting potential solutions must be due to safety, security or other strategic factors. Difficult to accept arguments based on cost as they are already built into the Regulations in this case, the compliance gap must be quantified and alternative measures identified to ensure at least the same level of safety that would be provided by complying with all the regulations. NOT A SIMPLE ROUTE

Current and Future Proposed Changes to Regulations Minimum threshold 10 μsv/h (US proposal, agreed by TRANNSC) Potential to increase this in this revision round if bullet proof justification is given e.g. dose estimates for worst case scenarios and assumptions what are those scenarios? Further future improvement desired by other MS but would need to retain intentof regulation. The public won t accept loosening of the regulations. Implementation of IAEA regsinto GB law 7ish yrsbut ONR can be cognisant of any agreed changes that haven t yet been implemented Regulation change needs collaboration been thought about a lot but no agreed solution so far.

thoughts? further issues and suggestions under current regulation? proposals for future changes to regulation? how can we work together on this?