|
|---|
Category:Letter
MONTHYEARML24023A0392024-01-22022 January 2024
NEI Comments on the Information Collection Renewal for Domestic Licensing of Special Nuclear Material, Docket Id NRC-2023-0118
ML23355A1972023-12-14014 December 2023
NEI, Comments on NRC Draft Resolution of SFAQ 2022-02, SAE Program Requirements
ML23219A1672023-10-25025 October 2023
Response Letter to Fee Exemption Request for Pre-Submittal Activities, Review, and Endorsement of NEI 20-07
ML23270B9002023-09-27027 September 2023
NEI Letter Request for an Extension of Comment Period on Proposed Revision to Standard Review Plan Section 15.0, Introduction - Transient and Accident Analyses, Docket Id NRC 2023 0079
ML23268A0102023-09-22022 September 2023
NEI, Fee Exemption Request for Endorsement, Review and Meeting to Discuss Draft Nuclear Energy Institute Technical Report NEI 23-01, Operator Cold License Training Plan for Advanced Nuclear Reactors
ML23241A8612023-08-25025 August 2023
Consolidated Industry Comments to NRC Regulatory Issue Summary 2023-02, Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels
ML23236A4992023-08-24024 August 2023
Industry Feedback on Region II Fuel Cycle Facility Construction Oversight Workshop Held August 15, 2023, and Suggested Topics for Additional Public Meetings in Fall 2023
ML23256A1622023-08-0101 August 2023
Incoming NEI Letter Dated August 1, 2023 Regarding Increase in Fees 2023-2025
ML23206A0292023-07-24024 July 2023
Incoming Fee Exemption Request for Pre-Submittal Activities, Review, and Endorsement of NEI 20-07
ML23143A1232023-06-22022 June 2023
NRC Fee Waiver Request for Draft NEI 23-01
ML23200A1662023-05-30030 May 2023
NEI Proposed Metrics for a Performance-Based Emergency Preparedness Program
ML23116A0732023-05-25025 May 2023
Letter to Hillary Lane in Response to a Request for a Fee Exemption for NEI 23-03
ML23135A7332023-05-0909 May 2023
NEI Comments on NRC Safety Culture Program Effectiveness Review
ML23110A6752023-04-18018 April 2023
04-18-23_NRC_Fee Waiver for NEI 23-03
ML23110A6782023-04-18018 April 2023
Request for Review and Endorsement of NEI 23-03, Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications at Non-Power Production or Utilization Facilities
ML23110A6762023-04-18018 April 2023
04-18-23_NRC_NEI 23-03 Review + Endorse
ML23107A2302023-03-31031 March 2023
NEI Letter, to Andrea Veil, NRC, Regarding Industry Recommendations for a 10 CFR 50.46a/c Combined Rulemaking
ML23138A1662023-03-24024 March 2023
Transmittal of NEI 22-05 Revision a, Technology Inclusive Risk Informed Change Evaluation (Tirice) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07
ML23083B4622023-03-24024 March 2023
Transmittal of NEI 22-05 Revision a, Technology Inclusive Risk Informed Change Evaluation (Tirice) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07
ML23060A3272023-03-0101 March 2023
NEI, Wireless Cyber Security Guidance
ML23060A2142023-03-0101 March 2023
NEI, Request for NRC Endorsement of NEI White Paper, Enabling a Remote Response by Members of an Emergency Response Organization, Revision 0
ML23023A2752023-01-23023 January 2023
Request for Extension of Comment Period from the Nuclear Energy Institute on PRM-50-124 - Licensing Safety Analysis for Loss-of-Coolant Accidents
ML22348A1122023-01-17017 January 2023
Letter to Richard Mogavero Response to Fee Exemption NEI 08-09 Revision 7
ML22353A6082023-01-11011 January 2023
U.S. Nuclear Regulatory Commission Report of the Regulatory Audit of the NEI-Proposed Aging Management Program Revision to Selective Leaching Program (XI.M33)
ML22349A1012022-12-12012 December 2022
LTR-22-0343 Ellen Ginsberg, Sr. Vice President, General Counsel and Secretary, Nuclear Energy Institute, Expresses Concerns Related to Issuance of Regulatory Issue Summary 2022-02; Operational Leakage
ML22336A0372022-11-16016 November 2022
Fee Exemption Request for NEI 08-09 Revision 7 - Changes to NEI 08-09 Cyber Security Plan for Nuclear Power Reactors
ML22321A3152022-11-16016 November 2022
NEI Letter with Comments on Significance Determination Process Timeliness Review
ML22298A2262022-10-25025 October 2022
Endorsement of NEI 15-09, Cyber Security Event Notifications, Revision 1, Dated October 2022
ML22298A2302022-10-17017 October 2022
Submittal of NEI 22-03, Draft Revision 0, Nuclear Generation Quality Assurance Program Description
ML22207B6512022-07-26026 July 2022
NEI, Full Fee Exemption Request for Industry Guidance Proposal - Weather Related Administrative Controls During Transient Outdoor Dry Cask Operations
ML22195A1662022-07-14014 July 2022
NEI, Draft G of NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors, Revision 7
ML22195A0202022-07-13013 July 2022
07-13-22 NRC Fee Exemption Request for NEI 21-05 Review
ML22195A0672022-07-13013 July 2022
Fee Exemption Request for Review and Meeting to Discuss Draft Nuclear Energy Institute Technical Report NEI 21-05, Reporting Guidance for Licensees with Risk-Informed Licensing Bases
ML22159A2772022-06-28028 June 2022
Response Letter to Richard Mogavero for Fee Exemption for the Nuclear Regulatory Commission Review Ad Endorsement of NEI 15-09, Revision 1
ML22153A2782022-06-0202 June 2022
Nie, Fee Exemption Request for Endorsement of NEI 15-09, Cyber Security Event Notifications, Revision 1, Dated May 2022
ML22154A2962022-06-0202 June 2022
LTR from R. Mogavero to M. Sampson Dated Jun 2 2022 Endorsement of NEI 15-09 Cyber Security Event Notifications Rev 1 Dated May 2022
ML22152A2712022-06-0101 June 2022
Digital Instrumentation and Control Common Cause Failure Policy Considerations, Revision 1
ML22143A9362022-05-20020 May 2022
May 13, 2022, Public Meeting on Draft Regulatory Issue Summary Operational Leakage, 87 Fed. Reg. 2361 (Jan. 14, 2022) (Docket Id NRC-2021-0173)
ML22110A1752022-05-0303 May 2022
NRC Response to the Nuclear Energy Institute April 1, 2022, Letter, Regarding the Nrc'S CUI Implementation Plan
ML22109A2082022-04-0808 April 2022
April 8, 2022, NEI White Paper on Digital Instrumentation and Control Common Cause Policy Considerations Version 2.0
ML22110A1782022-04-0101 April 2022
April 1, 2022, Letter from NEI Regarding Nrc'S Controlled Unclassified Information Program Implementation
ML22048A5812022-02-16016 February 2022
NEI 22-02: Guidelines for Weather-Related Administrative Controls for Short Duration Outdoor Dry Cask Storage Operations
ML22019A2922022-01-12012 January 2022
NEI, Submittal of Proposed Revisions to Aging Management Programs XI.M33, Selective Leaching and XI.E3, Inaccessible Power Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements
ML21343A2922021-12-0808 December 2021
NEI, Transmittal of NEI 21-07 Revision 0-B, Technology Inclusive Guidance for Non-Light Water Reactor Safety Analysis Report: for Applicants Utilizing NEI 18-04 Methodology
ML21337A3802021-12-0303 December 2021
NEI Technical Report NEI 17-06 - Guidance on Using Iec 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, Revision 1
ML21319A3522021-11-10010 November 2021
NRC NEI Fee Waiver Request Changes to NEI 10-04 and NEI 13-10, Dated November 10, 2021
ML21306A3652021-10-29029 October 2021
NEI Letter from D. Young to NRC S. Atack to Cease Work on Draft D of NEI 20-05, Methodological Approach and Considerations for a Technical Analysis to Demonstrate Compliance with the Eligibility Criteria of 10 CFR 73.55(a)(7)
ML21342A1682021-10-29029 October 2021
Letter from W. Gross to S. Atack, Endorsement of Nuclear Energy Institute 10-04, Identifying Systems and Assets Subject to the Cyber Security Rule, Revision 3, Dated October 29, 2021
ML21342A2032021-10-29029 October 2021
Letter from W. Gross to S. Atack, Endorsement of Nuclear Energy Institute 13-10, Cyber Security Control Assessments, Revision 7, Dated October 29, 2021
ML22081A2002021-10-29029 October 2021
NEI Backfitting Concerns with NRCs Developing Position on Protection of Dry Storage Systems from Natural Phenomena During Short Term Operations
2024-01-22
[Table view] |
Text
December 6, 2011 Mr. Alex Marion Executive Director for Engineering Nuclear Energy Institute 1776 I Street NW, Suite 400 Washington, DC 20006-3708
SUBJECT:
REQUEST FOR ASSISTANCE IN IDENTIFYING A LICENSEE VOLUNTEER FOR THE FULL-SCOPE SITE LEVEL 3 PROBABILISTIC RISK ASSESSMENT STUDY
Dear Mr. Marion:
In a September 21, 2011 staff requirements memorandum (SRM) (Ref. 1), the Commission directed the staff to initiate a project to develop a full-scope site Level 3 probabilistic risk assessment (PRA). The principal objectives of this project include (1) developing a Level 3 PRA that reflects technical advances since the last NRC-sponsored Level 3 PRAs were completed over 20 years ago, and addresses scope considerations that were not previously considered, and (2) extracting new insights to enhance regulatory decision-making and to help focus limited agency resources on issues most directly related to the agencys mission to protect public health and safety. The scope of this Level 3 PRA study includes all site radiological sources,1 all internal and external initiating event hazards, and all modes of plant operation. In general, the Level 3 PRA study will be based on current state of practice methods, tools, and data, but the desire for realism will be balanced against resource and schedule limitations. The staff also plans to build this PRA model from an existing plant Standardized Plant Analysis Risk (SPAR) model in order to improve project efficiency and the staffs ability to maintain and update the model in the future.
As discussed in a public meeting on November 10, 2011 (Ref. 2), the NRC requests the Nuclear Energy Institutes assistance in identifying licensees willing to volunteer a nuclear power plant site for this study. Enclosure 1 to this letter includes a list of high, medium, and low site selection criteria. Since one of the objectives of the Level 3 PRA study is to gain insight into multi-unit risk, it is necessary to select a site that contains multiple reactors. Also, performance of this study will require significant support from the volunteer licensee. Therefore, it is imperative that the volunteer licensee be highly committed to supporting the study by making available both staff resources and information needed to complete the project. Enclosure 2 provides a preliminary list of estimated impacts on the volunteer licensee.
We recognize that it is unlikely that any specific site will meet all of the medium and low priority criteria listed in Enclosure 1. However, the more of these criteria that are met by the volunteer site, the more likely the study can be completed within schedule and budget without affecting its scope or quality. This is particularly true for the availability of information on electrical cable locations and seismic fragilities, since developing this information would require significant NRC 1
Including all reactor cores, spent fuel pools, and dry storage casks on site, but excluding fresh nuclear fuel, radiological waste, and minor radiological sources (e.g., calibration devices).
A. Marion staff resources. Also, to enhance the types and applicability of insights obtained by the study, it is preferable to select a site that is not isolated (in terms of nearby population) and that is more typical in terms of its reactor design (i.e., involves a reactor design that is representative of more than one nuclear plant site).
We anticipate that a volunteer licensee for the project could obtain several benefits from participating in this study. In addition to developing a PRA that more fully considers public health consequences, the staff will also address other potential risk contributors, including multi-unit risk, spent fuel pools, and external hazards. This more comprehensive risk assessment approach would be expected to provide a more robust basis for risk-informed licensing actions and support innovative applications of PRA in the regulatory process. However, it is noted that while the Level 3 PRA study will be technically adequate for its intended use, it will not necessarily meet any particular capability category (as defined in the ASME/ANS PRA standard
[Ref. 3]) for every aspect of the study. As such, the resulting Level 3 PRA study will not necessarily be suitable for licensing applications without additional effort on the part of the licensee. We will be available to further discuss potential benefits with the selected volunteer licensee.
In order to meet the project schedule as directed by the Commission, we request that the volunteer sites be identified no later than January 13, 2012. The staff will make the final selection by January 31, 2012. Your assistance in this matter is greatly appreciated.
Sincerely,
/RA/
Timothy J. McGinty, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation References
- 1. SRM-SECY-11-0089, Staff RequirementsSECY-11-0089Options for Proceeding with Future Level 3 Probabilistic Risk Assessment (PRA) Activities, dated September 21, 2011, Agencywide Documents Access and Management System (ADAMS) Accession No. ML112640419.
- 2. Gilbertson, Anders, U.S. Nuclear Regulatory Commission, memorandum to Kevin Coyne, U.S. Nuclear Regulatory Commission, November 23, 2011, ADAMS Accession No. ML113200061.
- 3. ASME/ANS RA-Sa-2009, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, Addendum A to RA-S-2008, ASME, New York, NY, American Nuclear Society, La Grange Park, Illinois, February 2009.
Enclosures:
As stated cc: T. McGinty, NRR W. Dean, RI V. McCree, RII C. Pederson, RIII E. Collins, RIV
ML113200061.
- 6. ASME/ANS RA-Sa-2009, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, Addendum A to RA-S-2008, ASME, New York, NY, American Nuclear Society, La Grange Park, Illinois, February 2009.
Enclosures:
As stated cc: T. McGinty, NRR W. Dean, RI V. McCree, RII C. Pederson, RIII E. Collins, RIV DISTRIBUTION:
See next page ADAMS Accession No.: ML113330813 OFFICE RES/DRA/PRAB RES/DRA/PRAB RES/DRA NRR/DORL NRR/DPR NAME A. Kuritzky K. Coyne R. Correia L. Lund T. McGinty DATE 11/29/11 11/30/11 12/1/11 12/2/11 12/6/11 Letter to Alex Marion from Timothy J. McGinty dated December 6, 2011
SUBJECT:
REQUEST FOR ASSISTANCE IN IDENTIFYING A LICENSEE VOLUNTEER FOR THE FULL-SCOPE SITE LEVEL 3 PROBABILISTIC RISK ASSESSMENT STUDY DISTRIBUTION:
RCorreia, RES DCoe, RES KCoyne, RES AKuritzky, RES AGilbertson, RES MStutzke, RES LKillian, RES GDeMoss, RES CAder, NRO LLund, NRR AHowe, NRR SStuchell, NRR JGiitter, NRR RBradley, NEI ELyman, UCS SLewis, EPRI