1 Component Design Basis Inspection (CDBI) Graydon Strong 6/17/14.

Slides:



Advertisements
Similar presentations
EMS Checklist (ISO model)
Advertisements

“RULES FOR INSERVICE INSPECTION OF NUCLEAR PLANT COMPONENTS”
Key Reliability Standard Spot Check Frank Vick Compliance Team Lead.
INPO Update CMBG Meeting June 2013
Chapter 7: Key Process Areas for Level 2: Repeatable - Arvind Kabir Yateesh.
Vermont Yankee Presentation to VSNAP 7/17/13 VY/Entergy Fukushima Response Update Bernard Buteau.
RISK INFORMED APPROACHES FOR PLANT LIFE MANAGEMENT: REGULATORY AND INDUSTRY PERSPECTIVES Björn Wahlström.
NRC Perspective of Recent Configuration Management Issues Tom Farnholtz Chief, Engineering Branch 1 Division of Reactor Safety, Region IV June 2014 CMBG.
Cyber Security Plan Implementation Presentation to CMBG Glen Frix, Duke Energy June 20,
NRC PERSPECTIVE ON RELIEF AND SAFETY VALVES Charles G. Hammer Component Performance & Testing Branch Division of Component Integrity Office of Nuclear.
ISTOG MOV TESTING TRANSITION Prepared by: E. Cavey DTE-Fermi 2 Page 1 The GOAL of this effort was to develop implementation guidance for ASME Code Case.
Temporary Configuration Change Mike Hayes Exelon Nuclear.
January 24, SA12-PE-04 Purpose and Scope The purpose of this self assessment is to conduct a multi-discipline team review (deep dive) of the Feedwater.
PowerCare Customer Support Agreement LP Products and Systems 2013 PM.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.7 Commissioning Geoff Vaughan University of Central.
©2012 Doble Engineering Company. All Rights Reserved Transformer Life Extension and Adaptation to New Uses 2013 Power Forum Istanbul October 2013.
Software Engineering Institute Capability Maturity Model (CMM)
Top Tactics for Maximizing GMP Compliance in Blue Mountain RAM Jake Jacanin, Regional Sales Manager September 18, 2013.
Oconee RPS/ESPS Digital Upgrade Presented by: Michael Bailey June 3,
1 ISTOG Position on Pre-conditioning ISTOG Input on Interpretation and Clarification Of NUREG-1482 Sections 3.5 / 3.6.
Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006.
Commissioning of Fire Protection and Life Safety Systems Presented by: Charles Kilfoil Bechtel National Waste Treatment Plant Richland WA.
Organization and Implementation of a National Regulatory Program for the Control of Radiation Sources Staffing and Training.
Quality Assurance Program National Enrichment Facility Warren Dorman September 19, National Energy and Environmental Conference.
Configuration Management Benchmarking Group Conference June 6 – 9, 2004 Kansas City, MO © 2004 CMBG Configuration Management Fundamentals including Margin.
A SUMMARY OF CDBI FINDINGS IN SERVICE TESTING OWNERS GROUP December 2010 Clearwater, Florida.
Fatigue Management Rule Russell Smith Nuclear Energy Institute (NEI)
NRC Leadership Expectations and Practices for Sustaining a High Performing Organization NRC Commissioner William C. Ostendorff FR/SSO/FS Workshop U.S.
1 ISA&D7‏/8‏/ ISA&D7‏/8‏/2013 Systems Development Life Cycle Phases and Activities in the SDLC Variations of the SDLC models.
2007 CMBG Conference David Hembree Institute of Nuclear Power Operations June 20, 2007 Charleston, SC INPO Perspective on Configuration Management.
1 Human Performance in Reactor Safety George E. Apostolakis Massachusetts Institute of Technology Presented at the Quality Colloquium,
School for drafting regulations Nuclear Safety Operation Vienna, 26 November -7 December 2012 Tea Bilic Zabric.
Margin Management. PAGE 2 Margin Management Plant Shutdowns 1.Late 1990’s – numerous “surprise” long-term plant shutdowns 2.Shutdowns resulted when a.
Georgia Institute of Technology CS 4320 Fall 2003.
2007 CMBG Conference Bill Kline FirstEnergy Nuclear Operating Company (FENOC) June 19, 2006 Charleston, SC Latent Issues and Lessons Learned Discussion.
Programme Performance Criteria. Regulatory Authority Objectives To identify criteria against which the status of each element of the regulatory programme.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
The Reactor Oversight Process: Development and Results Tom Houghton Nuclear Energy Institute September 20, 2005.
Configuration Management of Post-Fukushima Regulations CMBG June 2013 David Gambrell Director, Severe Accident Management Southern Nuclear.
1 CDBI Inspection Insights for 2008 Kelly Clayton Senior Reactor Inspector Engineering Branch 1 Region IV.
NRC Region I Lessons Learned Steve Barr Senior Emergency Preparedness Inspector Region I US Nuclear Regulatory Commission 2010 NRC Region I Joint Exercise.
C O N T R A C T O R I N F O R M A T I O N E X C H A N G E Reister CE Presentation 1/98 1 Program Elements and Related Activities Rich Reister U.S. Department.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
International Recovery Forum 2014 ~ The Role of Private Sector in Disaster Recovery ~ 21 January 2014 Kobe, Japan Dr Janet L. Asherson THE LINK BETWEEN.
IAEA International Atomic Energy Agency INTRODUCTION Module 2.
IAEA International Atomic Energy Agency AGEING MANAGEMENT ASSESSMENT Module 9 Session 9 Resource document: AMAT Guidelines, Reference document for Ageing.
1 Safety factors for periodic safety review for research reactors Group A: SF1 – SF4.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Probabilistic Risk Assessment Program Workshop Information.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Overview of Risk Informed Inspection Workshop Information IAEA Workshop City,
IAEA International Atomic Energy Agency Development of the Basis Document for Periodic Safety Review for Research Reactors William Kennedy Research Reactor.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Maintenance Rule Program Workshop Information IAEA Workshop.
Organization and Implementation of a National Regulatory Program for the Control of Radiation Sources Program Performance Criteria.
By Annick Carnino (former Director of IAEA Division of Nuclear Installations Safety) PIME, February , 2012.
Pilot Component Design Basis Inspection (CDBI) and Equipment Qualification (EQ) Program Inspection Feedback CONFIGURATION MANAGEMENT BENCHMARKING GROUP.
International Atomic Energy Agency Implementation of a Risk-Informed Approach into the Legislative and Regulatory Framework SNRCU Annual Topical Meeting.
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
Current Plant Performance
NRC’s Component Design Bases Inspections
DCPP Performance Based on NRC Performance Indicators
Flooding Walkdown Guidance
Mitigation of Beyond Design Basis Events (MBDBE) Rule Implementation
NRC CM Pilot Inspections Methodology and Results
NRC Cyber Security Regulatory Overview
Results of Design Reviews
Margin Management Configuration Management Benchmarking Group
TRTR Briefing September 2013
Vendor Technical Information
Final Design Authorization
Aerodrome Certification Workshop
Management of Change GROUP HSE RULE (CR-GR-HSE-302)
Presentation transcript:

1 Component Design Basis Inspection (CDBI) Graydon Strong 6/17/14

2 CDBI Bases This inspection of component design bases verifies that plant components are maintained within their design basis. Additionally, this inspection provides monitoring of the capability of the selected components and operator actions to perform their design bases functions. As plants age, modifications may alter or disable important design features making the design bases difficult to determine or obsolete. The plant risk assessment model assumes the capability of safety systems and components to perform their intended safety function successfully. This inspectable area verifies aspects of the Initiating Events, Mitigating Systems and Barrier Integrity cornerstones for which there are no indicators to measure performance.

3 CDBI Objective To gain reasonable assurance that risk significant structures, systems, and components (SSCs) can adequately perform their design basis function. This includes reasonable assurance that the risk significant component can fulfill their design basis function during or after licensee’s activities (e.g., maintenance, surveillance) which can affect component’s availability, reliability and capability. Additionally, this includes that reasonable assurance that risk significant issues resulting from the generic communications have been adequately addressed.

4 CDBI Scope Review risk significant samples in Components and Operating Experience Component Selection – Risk-Significant Systems – Risk-Significant/Low Margin – Event Scenario-Based (Accident sequences) OE actions resolved? – Procedures updated? Mods implemented?

5 NRC Resources 408 hours effort (+/- 15%) Team leader Two or three regional inspectors – Operations/Maintenance – Engineering Two contractor design specialists – Mechanical – Electrical/I&C

6 CDBI Implications Every issue is a challenge to Configuration Management and Design Basis Operability may be in question Resources to recover from inspection

7 Industry Violations (non minor) Since Violations (mostly Green NCV’s) 81 Electrical 80 Mechanical 3 Civil

8 CDBI Violation Components 16 Relays 14 Valves 12 Pumps 11 Circuit Breakers 10 Batteries 6 Motors 5 Thermal Overloads 3 MOVs

9 CDBI Violation Systems 22 Emergency Diesel Generators 5 DC (10 more for batteries) 4 Standby Service Water 4 DG Fuel Oil 3 Spray Ponds

10 CDBI Violation Subjects 26 Degraded Voltage 9 HVAC 6 NPSH (Net Positive Suction Head) 6 SBO (Station Blackout) 5 PM (Preventative Maintenance) 5 Harmonics

11 CDBI Violation Subjects 4 Time Critical Operator Actions 4 HELB (High Energy Line Break) 3 Flooding 3 Tornado 3 Uncertainties 3 Leakage

12 CDBI Violation Processes 32 Procedures 21 Testing 19 Calculations 9 Design Basis 6 Operability

13 Columbia Inspection Trends 5 Calculation 3 Procedure 3 PM frequency change justifications Design Basis Knowledge

14 Columbia Inspection Trends Design Basis Knowledge Calculations PM’s

Legacy Doc Change Only 50.59s vulnerable Sample of 80 legacy 50.59s reviewed by Industry Expert 9 were deemed either required or may require prior NRC approval (based on limited info) Expanded sample for Industry Expert deemed not necessary

16 Calculations CDBI had 3 calculation related specific issues CDBI issue with locating some calculations – Short term: Internal audit performed – Long term: Scan calculations Vulnerability for the future with outstanding CMR’s and certain calculations – Prioritized plan for CMR incorporation – DC calculations being revised Presented calculation plan to NRC Resident – 4 year plan to upgrade calculations

17 PM’s PM extensions without proper justifications New design data base document that requires detailed references and justifications for PM changes Vendor input, Regulatory position, and OE sections Training for System Engineers 5 PM related procedures enhanced

18 Design Basis Knowledge Engineering staff needs review on design basis concepts January 2014 ESP training performed on “Design Basis Refresher” Periodic design basis refresher training

19 Major Modifications Lack of Analysis to show coordination between Non-1E and 1E loads off 1E inverters Design modifications to move Non-1E loads off 1E inverters Division 2 – Design for next outage installation issued Division 1 – Design for following outage installation in progress

20 Inverter Power Panel 8A-A

21 CDBI Preparation CDBI Self Assessment with internal multi discipline team and outside guests Review of Violations from other plants Get vulnerabilities into corrective action process and take action

22 CDBI Support Dedicated technically capable staff to communicate and follow issues to completion Ensure accuracy and timeliness If in house technical support is lacking in an area, consider outside expert Violations addressed immediately in the Corrective Action process

23 Questions?