|
|---|
Category:Memoranda
MONTHYEARML18331A3702018-12-0303 December 2018
Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding Use of New Probabilistic Risk Assessment Methods
ML18253A0642018-09-0505 September 2018
EPRI - Transmittal of NEl-03-08 Needed Interim Guidance. for PWR CRDM Thermal Sleeve Wear
ML17166A1952017-06-14014 June 2017
NRC Fee Exemption Request for NEI White Paper for Use by Design Certification Applicants to Determine the Scope of Tier 1 and Itacc
ML14142A4362014-06-11011 June 2014
Questions on White Paper Describing Proposed Methodology and Criteria Regarding Small Modular Reactor Emergency Planning Zone
ML14142A4252014-06-11011 June 2014
Feedback Questions on NEI SMR EPZ Methodology White Paper
ML13023A0512013-05-0909 May 2013
Transmittal Memo for Final Safety Evaluation for Technical Report NEI 11-04, Quality Assurance Program Description, Revision 0
ML1122000212011-08-31031 August 2011
8/4/2011- Summary of Meeting with the Nuclear Energy Institute and the Technical Specifications Task Force Regarding Gas Accumulation Issues and TSTF-523
ML1034402692010-12-22022 December 2010
Summary of Public Meeting with Industry'S New Plant Working Group (Npwg) on Combined License Applications
ML0715705202007-06-27027 June 2007
Summary of Meeting with NRC Industry Representatives to Present a Matrix of Potential Modeling Cases for the Phase II Sensitivity, Benchmarking, and Validation Calculations in Their Advanced Finite Element Fracture Mechanics Analyses
ML0713403322007-05-21021 May 2007
Withdrawal of Electric Power Research Institute (EPRI) Topical Report 1002865, Reactivity Initiated Accidents (Ria): Bases for Ria Fuel Rod Failures and Core Coolability Criteria,
ML0711301132007-04-26026 April 2007
Closeout for Review of Materials Reliability Program (Mrp): Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in Pressurized Water Reactors (MRP-169)
ML0710602852007-04-17017 April 2007
Forthcoming Category 2 Public Meeting with Nuclear Energy Institute Regarding Implications of Wolf Creek Dissimilar Metal Weld Inspections
ML0709303092007-04-12012 April 2007
Transmittal of Draft Safety Evaluation for Nuclear Energy Institute (NEI) Topical Report (TR) NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specifications (Rmts) Guidelines
ML0716304282007-04-0303 April 2007
NFPA 805 Transition Pilot Plant FAQ Process: Substantive E-Mails; April 2007
ML0631103902006-11-0707 November 2006
Notice of Meeting with Nuclear Energy Institute (NEI) Implications of Dissimilar Metal Weld Inspection Results at Wolf Creek
ML0901301502006-07-0606 July 2006
Maintenance Rule Guidance, NUMARC 93-01
ML0319001292003-07-0808 July 2003
Review of NRC Draft NUREG Report Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Criteria in the PTS Rule (10CFR50.61, NEI Project Number 689
ML0228206872002-10-23023 October 2002
Emergent Material and Inspection Issues
ML0133902222001-08-24024 August 2001
Standard Format for Operating License Amendment Requests
2018-09-05
[Table view] |
Text
July 8, 2003 Mr. Alexander Marion Director, Engineering Department, Nuclear Generation Division Nuclear Energy Institute 1776 I St NW # 400 Washington, DC 20006
SUBJECT:
REVIEW OF NRC DRAFT NUREG REPORT "TECHNICAL BASIS FOR REVISION OF THE PRESSURIZED THERMAL SHOCK (PTS) SCREENING CRITERIA IN THE PTS RULE (10CFR50.61)," NEI PROJECT NUMBER 689
Dear Mr. Marion:
Thank you for your letter dated June 23, 2003, on this topic, and for the detailed comments you provided on our draft NUREG. Your comments on our report will be very helpful to us as we improve and finalize our findings. Currently, we are performing probabilistic risk assessment and probabilistic fracture mechanics calculations on the fourth and final plant in our study (Calvert Cliffs Unit 1), and are examining the steps needed to generalize these results to all domestic pressurized water reactors. This information, along with your comments and those that we have received from the Office of Nuclear Reactor Regulation (NRR), will provide the basis for a revised suite of reports that should be completed in March 2004. We are convening an external expert panel to conduct a peer review of this revised report. We plan to issue a final report after receiving and addressing comments from this peer review panel.
The assistance of the industry, working under the auspices of the Electric Power Research Institutes Materials Reliability Program, has been invaluable in the conduct and success of the PTS re-evaluation effort. My staff and I look forward to continued interactions with your colleagues in this group.
Should you have any additional questions please feel free to contact me at any time, either by e-mail to ncc1@nrc.gov, or at 301-415-0190. Technical questions should be directed to Mark Kirk of my staff; Mark can be reached at mtk@nrc.gov or 301-415-6015.
Sincerely,
/RA/ Jitendra P. Vora/ for Nilesh C. Chokshi, Chief Materials Engineering Branch Division of Engineering Technology Office of Nuclear Regulatory Research
Distribution:
A. Thadani, M. Mayfield S. Malik S. Newberry M. Cunningham N. Siu H. Woods F. Eltawila J. Rosenthal D. Bessette MEB r/f
'2&80(171$0( * .LUNQLOHVKUHSO\WR1(,376FRPPHQWVZSG 2$5LQ$'$06" <RU1 < $'$06$&&(66,2112 0/ 7(03/$7(125(6
3XEOLFO\$YDLODEOH" <RU1 < '$7(2)5(/($6(7238%/,& 6(16,7, 9("
1
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
- see previous concurrence 2)),&( 5(60(% 5(60(%
1$0( 0.LUN5$ 1
&KRNVKL5$9RUDIRU
'$7(
2)),&,$/5(&25'&23<