Presentation is loading. Please wait.

Presentation is loading. Please wait.

ANSI/ANS-3.11 Determining Meteorological Information at Nuclear Facilities Stanley L. Marsh, CCM, Southern California Edison 8th NUMUG Meeting St. Charles,

Published byBasil Sims Modified over 8 years ago

Similar presentations

Presentation on theme: "ANSI/ANS-3.11 Determining Meteorological Information at Nuclear Facilities Stanley L. Marsh, CCM, Southern California Edison 8th NUMUG Meeting St. Charles,"— Presentation transcript:

1 ANSI/ANS-3.11 Determining Meteorological Information at Nuclear Facilities Stanley L. Marsh, CCM, Southern California Edison 8th NUMUG Meeting St. Charles, IL May 9, 2002

2 ANSI/ANS-3.11  Purpose Report on ANSI/ANS-3.11, a new Standard for Determining Meteorological Information at Nuclear Facilities. Explore nuclear industry position on approaching NRC for their endorsement of ANSI/ANS-3.11. Initiate steps to reaffirm, revise, or modify ANSI/ANS-3.11.

3 ANSI/ANS-3.11 Attributes  Reflects the current operational and regulatory climate by incorporating state-of-the-art data acquisition, processing, and recording technology.  Applicable to all nuclear facilities nationwide, civilian nuclear power industry and Federal government.  Replaces ANSI/ANS-2.5; clarifies existing issues and provides additional guidance without imposing new requirements.  Represents a technically sound, state- of-the-art standard without consideration of regulatory forcing functions.

4 Why Was ANSI/ANS-2.5 Replaced? No longer active per ANS Standards rules Technically outdated Emphasizes siting, not operation of nuclear facilities Does not reflect current in situ meteorological instrumentation standards Does not consider remote sensing technology Does not reflect state-of-the-art data acquisition, processing, and archiving technology Inconsistent with USEPA and ASTM guidance Addresses only civilian nuclear power plants and not all non-reactor nuclear facilities Does not address meteorological program life cycle considerations Does not fully address complex terrain siting and operational issues Inconsistent with NEXRAD, ASOS, EPA, and ASTM guidance

5 ANSI/ANS-3.11 Design Criteria Replace ANSI/ANS-2.5, not just revise it. Applicable to both civilian nuclear power industry and Federal Gov’t nuclear facilities. Applicable to meteorological monitoring supporting siting, licensing, operation, emergency response, decontamination, and decommissioning of nuclear facilities. Reside in ANS-3.0, Operations. Rely on existing, technically sound, meteorological guidance. Develop new guidance only where necessary. Stand alone, technically sound document.

6 ANSI/ANS-3.11 WG PARTICIPANTS AND STRUCTURE WG ELEMENT I: CHAIRMEN OVERSIGHT AND FACILITATION NUMUG Rep:Stan Marsh (SCE) DMCC Rep:Carl Mazzola (SW) WG ELEMENT II: TECHNICAL RESEARCHERS AND WRITERS DEVELOPMENT OF TECHNICAL MATERIALS Mark AbramsVendorPLG Bob BantaFed ResearchERL/ETL Tom BellingerFed PgmIDNS Paul FransioliConsultantSAIC Brad HarveyUtil Pgm MgrDESI Stan MarshUtil Pgm MgrSCE Carl MazzolaConsultantSW Matt ParkerFed PgmWSRC Ken WastrackUtil/Fed PgmTVA

7 ANSI/ANS-3.11 WG PARTICIPANTS WG ELEMENT III: PEER REVIEWERS Rob Addis Fed Pgm MgrWSRC Ron BaskettFed Pgm MgrLLNL Leta BrownRegulator NRC Bruce Carson Util Pgm PP&L Tom CoulterRegulator EPA Jerry Crescenti Fed Pgm MgrINEEL Jim FairobentFed PgmDOE/SO Jim HolianConsultantSAIC John IrwinRegulatorEPA Bob KornasiewiczRegulatorNRC Stanley KrivoRegulatorEPA IV Tom LockhartConsultantMSI Doyle PittmanUtil Fed PgmTVA Darryl RandersonFed Pgm MgrNTS Gene ShelarUtil PgmPG&E Irv SpicklerFed PgmDOE/EM Bob SwansonConsultantCCC Ping WanConsultantBechtel Marvin WeselyFed PgmANL Bob YewdallUtil Pgm MgrPSE&G

8 ANSI/ANS-3.11 REGULATORY IMPLICATIONS NRC RESPONSE (7/94) “…we are not aware of any safety issues which would suggest that a revision of this Regulatory Guide (1.23) is in order.” “…NRC approval is not needed for ANS to revise the subject standard.” “We cannot make a commitment at this time to endorse the revised ANSI/ANS-2.5 (ANSI/ANS-3.11) without a compelling safety argument.” “…the NRC will determine how to support your activity.”

9 ANSI/ANS-3.11 REGULATORY IMPLICATIONS NRC’S CURRENT POSITION ON METEOROLOGY (05/02) SAFETY GUIDE 23 (AKA, R.G. 1.23) IS STILL IN EFFECT. PROPOSED REV. 1, AND 2 nd PROPOSED REV. 1 TO R.G. 1.23 WERE NEVER ADOPTED. AT PRESENT, THERE IS NO EFFORT, ONGOING OR PLANNED WITHIN NRC, FOR AN UPDATE OR REVISION. NRC IS WAITING FOR AN INDUSTRY TRADE GROUP (e.g. NUMUG) TO TAKE THE INITIATIVE TO GET ANSI/ANS-3.11 RECOGNIZED.

10 ANSI/ANS-3.11 WORKING GROUP (WG) FUTURE  UPDATES/REVISIONS TO ANSI/ANS-3.11 THROUGH REAFFIRMATION PROCESS REAFFIRM “AS IS” BY 2/16/05 REVISE (MINOR EDITORIAL REVISIONS) MODIFY (MAJOR REVISIONS)  REACTIVATE THE ANSI/ANS-3.11 WG VOLUNTEERS FOR WG MEMBERS? VOLUNTEERS FOR WG CHAIR?  WG KICKOFF MEETING PLANNED AT AMERICAN METEOROLOGICAL SOCIETY (AMS) ANNUAL MEETING IN LONG BEACH, CA, FEBRUARY 2003  DEVELOPMENT OF OTHER METEOROLOGICAL STANDARDS

11 ANSI/ANS-3.11 NUMUG SURVEY  Should NUMUG initiate discussions with NRC to gain endorsement of ANSI/ANS-3.11? Yes No  Should NUMUG support WG to seek re-affirmation of ANSI/ANS-3.11? Yes No  Would you serve as a member on the ANSI/ANS-3.11 WG? Yes No  Would you Chair the ANSI/ANS-3.11 WG? Yes No  Comments/Ideas _________________________________________________  Name ________________________  Affiliation _______________________ Please tear out this page and leave with NUMUG Steering Committee member at the end of day.

12  HOW DO I PURCHASE A COPY?  WRITE OR CALL, AMERICAN NUCLEAR SOCIETY 555 NORTH KENSINGTON AVENUE LA GRANGE PARK, ILLINOIS 60526 Attn.: ANS STANDARDS MANAGER (708) 352-6611 (708) 352-0499 (FAX) E-mail at NUCLEUS@ans.orgNUCLEUS@ans.org http://www.ans.org ANSI/ANS-3.11

Download ppt "ANSI/ANS-3.11 Determining Meteorological Information at Nuclear Facilities Stanley L. Marsh, CCM, Southern California Edison 8th NUMUG Meeting St. Charles,"

Similar presentations

NRC Consensus Standards Program

NRC Consensus Standards Program
MAIN COMMITTEE OFFICERS DUTIES AND RESPONSIBILITIES.

MAIN COMMITTEE OFFICERS DUTIES AND RESPONSIBILITIES.
Reliability Subcommittee Report Vishal C. Patel Chair – Reliability Subcommittee March 2014.

Reliability Subcommittee Report Vishal C. Patel Chair – Reliability Subcommittee March 2014.
What is NUMUG? 1 Kenneth G. Wastrack Tennessee Valley Authority Presented at the 12 th NUMUG Meeting Charlotte, NC / 25-27 June 2008.

What is NUMUG? 1 Kenneth G. Wastrack Tennessee Valley Authority Presented at the 12 th NUMUG Meeting Charlotte, NC / June 2008.
1 Accredited Standards Committee C63 ® - EMC Subcommittee 5 – Immunity Stephen R Whitesell SC-5 Chair 11/13/2014.

1 Accredited Standards Committee C63 ® - EMC Subcommittee 5 – Immunity Stephen R Whitesell SC-5 Chair 11/13/2014.
CSWEA Plant Maintenance Technologist Certification Program CSWEA Plant Maintenance Technologist Certification Program Gary B. Scott, CPMM Glenbard Wastewater.

CSWEA Plant Maintenance Technologist Certification Program CSWEA Plant Maintenance Technologist Certification Program Gary B. Scott, CPMM Glenbard Wastewater.
1 ANSI/ANS-3.11-2005 American National Standard for Determining Meteorological Information at Nuclear Facilities R. Brad Harvey, CCM Physical Scientist.

1 ANSI/ANS American National Standard for Determining Meteorological Information at Nuclear Facilities R. Brad Harvey, CCM Physical Scientist.
MARSSIM Revision 2 Request for Input Public Meeting February 10, 2011 Kathryn Snead MARSSIM Workgroup Chair.

MARSSIM Revision 2 Request for Input Public Meeting February 10, 2011 Kathryn Snead MARSSIM Workgroup Chair.
NREP 2009 Emergency Preparedness and the New Reactor Licensing Process: An Update on Where We Are Now Dan Barss Division of Preparedness & Response Office.

NREP 2009 Emergency Preparedness and the New Reactor Licensing Process: An Update on Where We Are Now Dan Barss Division of Preparedness & Response Office.
Chesapeake Bay Program Goal Development, Governance, and Alignment Carin Bisland, GIT6 Vice Chair.

Chesapeake Bay Program Goal Development, Governance, and Alignment Carin Bisland, GIT6 Vice Chair.
Licensing of Nuclear Power Plants in Pakistan

Licensing of Nuclear Power Plants in Pakistan
HITSP – enabling healthcare interoperability 1 enabling healthcare interoperability 1 Standards Harmonization HITSP’s efforts to address HIT-related provisions.

HITSP – enabling healthcare interoperability 1 enabling healthcare interoperability 1 Standards Harmonization HITSP’s efforts to address HIT-related provisions.
Departmental Initiative to Enhance Activity-level Work Planning and Control DOE and DOE Contractors Industrial Hygiene Meeting in Conjunction with the.

Departmental Initiative to Enhance Activity-level Work Planning and Control DOE and DOE Contractors Industrial Hygiene Meeting in Conjunction with the.
1 NRC Plans for NESCC Concrete Specifications, Codes & Standards (SCS) Endorsement NESCC Meeting March 28, 2013 Richard Jervey USNRC Office of Regulatory.

1 NRC Plans for NESCC Concrete Specifications, Codes & Standards (SCS) Endorsement NESCC Meeting March 28, 2013 Richard Jervey USNRC Office of Regulatory.
01/14/2001Standards1 Introduction to Standards Paul M. Fransioli, CCM AMS Short Course on Introduction to Measurements and Observation Techniques January.

01/14/2001Standards1 Introduction to Standards Paul M. Fransioli, CCM AMS Short Course on Introduction to Measurements and Observation Techniques January.
FGDC Standards Process Review Survey Results Summary Julie Binder Maitra FGDC Standards Coordinator 703-648-4627 April 13, 2010 Coordination.

FGDC Standards Process Review Survey Results Summary Julie Binder Maitra FGDC Standards Coordinator April 13, 2010 Coordination.
Balanced Scorecard 101 A Brief Overview of the BSC Methodology

Balanced Scorecard 101 A Brief Overview of the BSC Methodology
April 11, 2007 Prepared by the North American Energy Standards Board 1 North American Energy Standards Board Standards Development Process.

April 11, 2007 Prepared by the North American Energy Standards Board 1 North American Energy Standards Board Standards Development Process.
PSAP Service Capability Assessment Tool Session A Joint Effort of APCO and NENA Presented June 10, 2009 for Discussion & Feedback by: Tom Breen, ENP.

PSAP Service Capability Assessment Tool Session A Joint Effort of APCO and NENA Presented June 10, 2009 for Discussion & Feedback by: Tom Breen, ENP.
Safety Analysis Working Group FY2010 EFCOG Semi-Annual Meeting Brad Evans, Chair Pacific Northwest National Laboratory Rob McKeehan, Vice-Chair Oak Ridge.

Safety Analysis Working Group FY2010 EFCOG Semi-Annual Meeting Brad Evans, Chair Pacific Northwest National Laboratory Rob McKeehan, Vice-Chair Oak Ridge.

Similar presentations

Ads by Google