Design Bases From 1957 to 2003 June 18, 2007 Chuck Casto Region II NRC.

Slides:



Advertisements
Similar presentations
1 Introduction to Safety Management April Objective The objective of this presentation is to highlight some of the basic elements of Safety Management.
Advertisements

Westinghouse Owners Group Risk-Informed Repair and Replacement – Implementation of 10 CFR Twelfth International Conference on Nuclear Engineering.
Department of Energy Quality Assurance Updates Frank Russo Deputy Assistant Secretary Office of Corporate Performance Assessment Energy & Environmental.
Meteorology Combined License NRC Review Process Meteorology Joseph Hoch Physical Scientist U.S. Nuclear Regulatory Commission June , 2008 Nuclear.
“Regulatory Risk-Informed Activities and Supporting PRA Technical Acceptability” Presented to Nuclear Energy Standards Coordination Collaborative (NESCC)
© November, 2001 LeBlond and Associates, LLC Training Program Overview Produced by LeBlond & Associates, LLC Thanks for taking the time to view this presentation.
NRC Perspective of Recent Configuration Management Issues Tom Farnholtz Chief, Engineering Branch 1 Division of Reactor Safety, Region IV June 2014 CMBG.
© April, 2005 LeBlond and Associates, LLC Overview of a Training Program Produced by LeBlond & Associates, LLC Thanks for taking the time to view this.
Cyber Security Plan Implementation Presentation to CMBG Glen Frix, Duke Energy June 20,
Lindy Hughes Fleet Fire Protection Program Engineer Southern Nuclear Operating Company June 4, 2013 Fire Protection.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.7 Commissioning Geoff Vaughan University of Central.
Protection Against Occupational Exposure
OH&S Management System
MENTAL HEALTH (AMENDMENT) ACT 2003 Given Royal Assent on 21 October Except for Part 2, the Act came into operation the day after it was given Royal.
ANSI-NIST Nuclear Energy Standards Coordination Collaborative Larry Burkhart, Chief, AP1000 Projects Branch (LB4) Division of New Reactor Licensing NRC’s.
Regulatory Approach to the Lifetime Management of the Nuclear Power Plants in Korea June 30, 2004 Choi, Kyung Woo Korea Institute of Nuclear Safety International.
Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006.
Organization and Implementation of a National Regulatory Program for the Control of Radiation Sources Staffing and Training.
A Proposed Risk Management Regulatory Framework Commissioner George Apostolakis Presented at the Organization of Agreement States 2012 Annual Meeting Milwaukee,
Quality Assurance Program National Enrichment Facility Warren Dorman September 19, National Energy and Environmental Conference.
Guidelines for the Development and Maintenance of RTF- Approved Measure Savings Estimates December 7, 2010 Regional Technical Forum Presented by: Michael.
Configuration Management Benchmarking Group Conference June 6 – 9, 2004 Kansas City, MO © 2004 CMBG Configuration Management Fundamentals including Margin.
NHUG - Boston - 08/04/20101 Considerations for Operability of Chillers and Chilled Water Systems NHUG Summer Meeting August 4, 2010 Tim Mitchell Component.
1 Public Hearing to Consider Proposed Amendments to the Emission Inventory Criteria and Guidelines Regulation for the AB 2588 Air Toxics “Hot Spots” Program.
IAEA International Atomic Energy Agency LICENSING OF RADIOACTIVE WASTE MANAGEMENT FACILITIES Luc Baekelandt Safety of radioactive.
1 Human Performance in Reactor Safety George E. Apostolakis Massachusetts Institute of Technology Presented at the Quality Colloquium,
ACADs (08-006) Covered Keywords CFR policy, CFR violation, CFR enforcement Description Supporting Material
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
EIA-legislation and practice in Norway history history latest amendments of regulations latest amendments of regulations integrated planning/EIA processes.
1 Control Room Habitability Program James A. Carlson, Omaha Public Power District, Author Deep Ghosh, Southern Nuclear Operating Greg Holbrooks, PE, Duke.
ANSI-NIST Nuclear Energy Standards Coordination Collaborative David Matthews, Director, Division of New Reactor Licensing Larry Burkhart, Chief, AP1000.
1 NEI Process Discussion. 2 Topics for Discussion Relationship to NFPA 805 Relationship to Regulatory Guide Technical Process currently in NEI
NRC Region I Lessons Learned Steve Barr Senior Emergency Preparedness Inspector Region I US Nuclear Regulatory Commission 2010 NRC Region I Joint Exercise.
1 RIC 2009 NFPA 805 Regulatory Infrastructure Development Steven A. Laur, PE Sr. Tech Adv. Risk-Informed Initiatives NRC Office of Nuclear Reactor Regulation.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
Configuration Management Fundamentals including Margin Management Bill Kline FirstEnergy Nuclear Operating Company (FENOC) June 2, 2008 Shell Beach, CA.
International Atomic Energy Agency Roles and responsibilities for development of disposal facilities Phil Metcalf Workshop on Strategy and Methodologies.
IAEA International Atomic Energy Agency Methodology and Responsibilities for Periodic Safety Review for Research Reactors William Kennedy Research Reactor.
International Security Management Standards. BS ISO/IEC 17799:2005 BS ISO/IEC 27001:2005 First edition – ISO/IEC 17799:2000 Second edition ISO/IEC 17799:2005.
NRC Environmental Reviews for Uranium Recovery Applicants and Licensees James Park (301)
ISO Registration Common Areas of Nonconformances.
Milestones for Nuclear Power Infrastructure Development Establishment of A Regulatory Framework Gustavo Caruso, Section Head, Regulatory Activities Section.
1 Public Meeting with ASME to Discuss Pump Inservice Testing Issues NRC Headquarters OWFN Room 1F22 June 4, 2007.
ISTOG – NRC Update Winter Meeting 2010 – Clearwater, FL Tony McMurtray Chief, Component Performance & Testing Branch Office of Nuclear Reactor Regulation.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification.
CMBG Conference 2013 Atlanta GA June 3, 2013 ANSI/NIRMA Standard CM Year History.
2-6 November 2015 Lisbon, Portugal Regional Meeting on Applications of the Code of Conduct on Safety of RR's 1 Some aspects of the Code of Conduct on the.
Organizations of all types and sizes face a range of risks that can affect the achievement of their objectives. Organization's activities Strategic initiatives.
Configuration Management in NRC’s Reactor Inspection Program Tony Gody, Region II/DRS.
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
OH&S Management System
Instructor: Lloyd Hancock
CM-101 Configuration Management Fundamentals
The ORR/RA and the Authorization Basis May 2005 Revision
Delivering Risk Informed Engineering Programs (50.69) The OG Plan
Regulation (EU) No 2015/1136 on CSM Design Targets (CSM-DT)
Joe Bellini, Exelon Drew Miller Exelon April 6, 2012
Industry Guidance on Part 21 Evaluation and Reporting
Flooding Walkdown Guidance
Mitigation of Beyond Design Basis Events (MBDBE) Rule Implementation
OH&S Management System
IAEA Safety Guidance on Licensing and Oversight Activities
NRC Cyber Security Regulatory Overview
Changes to Exempt Categories
Current Configuration Management Inspection Issues
Temporary Alterations in Support of Maintenance and Temporary Modifications Beth Kernes Krause - Cooper Station February 24, 2019 Cleveland 2005.
TRTR Briefing September 2013
RESOLUTION OF GENERIC SAFETY ISSUE 191
Vendor Technical Information
License Amendments Patrick Boyle Nuclear Engineer
Presentation transcript:

Design Bases From 1957 to 2003 June 18, 2007 Chuck Casto Region II NRC

HISTORY OF DESIGN BASES Atomic Energy Act of 1954 –(1957 Thru 1962) Section 182 Technical Specifications are part of license Implemented in 10CFR50.34 & Hazards Summary Report –Safety Analysis Report

HISTORY OF DESIGN BASES (cont’d) Two approaches for Tech Specs –Vallecitos –Include entire Hazard Summary Report –Yankee Atomic – TS culled from Hazard Summary Report Section 189 – Mandatory hearing for issuance of license or license amendment

HISTORY OF DESIGN BASES (cont’d) Results were unworkable –Diminishing return – Mandatory Hearing –Need recognized for discriminating significant and insignificant changes The Vallecitos Decision (1960) –Concept of Unreviewed Safety Question (10CFR50.59) –No significant hazards consideration (10CFR50.92)

HISTORY OF DESIGN BASES (cont’d) Regulations to manage changes –10CFR50.59 –10CFR50.91 –10CFR50.92

Early History of “ Clarifies” the extent which the licensee may make changes, conduct tests & experiments not specifically provided in the license Changes: –1. Explicit license authority –2. Credible probability by possibility –3. Licensee can conduct test & experiments in HAR approved by NRC April 8, 1961 (AEC) NRC issues proposed Rule June 9, issued

Early History of Changed reference to Safety Analysis Report from HAR (HSR) Tech Specs could serve purpose with less content. The PSAR & SAR explicitly specified and Bases for TS were required Final Rule change brought in –1. Consideration of “malfunctions” –2. Inclusions of the “margin of safety” as defined in the bases for any TS 1966 August 16, 1986 Proposed Rule change December 17, 1988 Rule Revised

Public Impact of 50.59

Historical Definitions and Assumptions No undue risk to health safety No unreviewed safety questions remain Licensee’s have freedom to control the plant Drew a line across which the licensee could not step without NRC approval Permitted the license to determine if line crossed

Historical Definitions and Assumptions (cont’d) Consequences equal dose 50.2 defines design basis as..”That information which identifies the specific functions to be performed by a SSC of a facility, and the specific values or ranges of values chosen for controlling parameters as reference bounds for design.”

Historical Definitions and Assumptions (cont’d) Experiment – an operation carried out under controlled conditions in order to discover an unknown effect. Test – the procedure of submitting a statement to such conditions or operations as will lead to its proof or disproof to its acceptance or rejection.

Historical Definitions and Assumptions (cont’d) Malfunction – Failure, breakdown, or inaccurate operation. In 50.59, the term malfunction is more component or equipment oriented, e.g., single failure. Margin of safety – the difference between the acceptable limit and the design failure point.

Historical Definitions and Assumptions (cont’d) Unreviewed safety question – If the probability of occurrence or consequences of an accident or malfunction or equipment important to safety previously evaluated in the SAR may be increased; or If a possibility for an accident of malfunction of a different type than any evaluated previously in the SAR may be created; or

Historical Definitions and Assumptions (cont’d) USQ (cont’d) If the margin of safety as defined in the basis for any TS is reduced. –Seven questions were used to determine if a change was a USQ –USQ did not mean unsafe

Regulatory Significance of the FSAR Tech Specs are incorporated into the license (50.36) –Commission approval to change (50.90/91) Descriptive information –Controlled under Descriptive information not controlled under –Subject to 50.9

History of Design Basis Configuration Davis Besse incident NUMARC NUREG 1327 Assessment of DBR 1990 FSAR update Rule GL Commission Policy Statement 1992 Regulatory Review Group

History of Design Basis Configuration (cont’d) 1993/1995 National Performance Review August 1995 plant events July 1996 Commission Policy on Voluntary Industry Initiatives Risk Informed Regulation Special Treatment

Design Bases Interpretation Appendix B of NEI proves guidance for interpreting 10 CFR 50.2 design bases Commission endorsement through RG CFR 50.2 design bases includes: –Design bases functions –Design bases values

Design Bases Functions SSC functions required by, or otherwise necessary to comply with, regulations, license conditions, tech specs or orders; or SSC functions credited in licensee safety analyses to meet NRC requirements

Design Bases Values Design bases values: –Values or ranges of values of controlling parameters established as reference bounds for design to meet design bases functional requirements Established by NRC requirement Derived from or confirmed by safety analyses Chosen by licensees from an applicable code, standard, guidance document

Why are these definitions important? Common understanding of 10 CFR 50.2 “design bases” supports: –UFSAR updates –10 CFR implementation –Proper characterization of design discrepancies

Simplified Relationship

10 CFR Establishes criteria for making changes to the licensing/design bases Guideline for implementation NEI Endorsement of NEI through RG 1.187

10 CFR Objectives of guidelines: –Update existing guidance and provide guidance on new provisions –Provide guidance on when to apply processes other than 10CFR50.59 –Promote more consistent, effective implementation

10 CFR Final Rule changes: –Eliminated “zero standard” –Established “minimal” standard –Enhanced screening process –Replaced problematic “margin of safety” –Clarified role of overlapping requirements –Affirmed purpose as a “regulatory threshold” No more “unreviewed safety questions”

10 CFR Key changes in implementation: –Broad scope of “design functions” as used in “change” definition –Only adverse changes “screen in” Determination based on effects on design functions Change is not adverse if effects are within the bounds of existing safety analysis

10 CFR –Always consider adverse and screen in: Any change to barrier design basis limits Fundamental changes in how required functions are performed (e.g., manual vs. automatic action) –Other clarifications: Applicability of MR(a)(4) to installation and post- mod testing of plant changes Minimal increase in malfunction in likelihood Use of alternative methodologies

10 CFR –Control of maintenance procedures –Definition of “design functions” –Consideration of human factors –Analog-digital upgrades

UFSAR Updates 10CFR50.71e RG 1.181, Sept 1999, endorses NEI UFSAR updates must reflect: –New Commission Requirements –Effects on USFAR info of: Changes made to facility and procedures Evaluations in support of changes Requested analysis of new safety issues

UFSAR Updates

Commitment Management RIS endorses NEI 99-04, Guideline for Managing NRC Commitment changes

Licensing Basis Today!!! Hierarchical approach to licensing basis –Obligations – legally binding requirements imposed by rule, reg, order and licenses. –Mandated documents – documents for which the NRC has established required content, e.g, UFSAR, security, EP, QA plans. –Regulatory Commitments – explicit statements agreed to and submitted on the docket.

Configuration Control Insights Great job! <5% of NRC findings CC all green Big hitters: –Human Performance (~20%) –Failure to follow procedures (~20%) –Decision making (~20%) –Outside design basis (~15%) –Less than adequate procedures (~10%) –Tagging (~8%)

Design Control Insights ~13% of NRC findings related to DC –Design control (~30%) –Awareness of criteria (~22%) –Calculation error (~15%) –Configuration control (~15%) –Corrective action (~6%) –Other (Op Evals, FSAR, OE, vendor, materials) ~(12%)

Human Performance in Industry January 2005 – Present Reference NRC Human Factors Information System Human Performance Cause Codes in LER’s & Inspection Reports –“Work Practices” –Problem identification & resolution –Procedures

Human Performance in Engineering January 2005 – Present Reference NRC Human Factors Information System Human Performance Cause Codes in LER’s & Inspection Reports –Work Practices 20% Design work –Skill –Non-conservative decisions –Implementation of action less than adequate –PI&R 18% Problem Identification Problem Resolution Problem Evaluation

Human Performance in Engineering January 2005 – Present Reference NRC Human Factors Information System Human Performance Cause Codes in LER’s & Inspection Reports –Procedures 16% Design Content of procedures Maintenance/surveillance

Questions????