Letter Sequence Draft Approval |
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MONTHYEARML0631203352006-11-14014 November 2006
Acceptance for Review of Electric Power Research Institute Motor-operated Valve Performance Prediction Methodology Software
Project stage: Acceptance Review
ML0710703702007-04-23023 April 2007
Request for Additional Information (RAI) Regarding Topical Report (TR) -103237, Electric Power Research Institute Motor-Operated Valve Performance Prediction Methodology Software
Project stage: RAI
ML0811301332008-06-0303 June 2008
Request for Additional Information Nuclear Energy Institute (NEI) Topical Report (TR) - 103237, EPRI (EPRI Power Research Institute) MOV (Motor-operated Valve) Performance Prediction Program - Topical Report
Project stage: RAI
ML0834300642009-01-14014 January 2009
to Draft Safety Evaluation for Nuclear Energy Institute Addenda 3,4,5,6 & 7 to Electric Power Research Institute Topical Report 103237, EPRI Mov (Motor-Operated Valve) Performance Prediction Program, Rev. 2
Project stage: Draft Approval
ML0904006212009-02-24024 February 2009
to Final Safety Evaluation for Nuclear Energy Institute (NEI) Addenda 3, 4, 5, 6, and 7 to Electric Power Research Institute (EPRI) Topical Report (TR) 103237, EPRI Mov (Motor-Operated Valve) Performance Prediction Program, Rev. 2.
Project stage: Approval
ML0904006102009-02-24024 February 2009
to Final Safety Evaluation for Nuclear Energy Institute (NEI) Addenda 3, 4, 5, 6, and 7 to Electric Power Research Institute (EPRI) Topical Report (TR) 103237, EPRI Mov (Motor-Operated Valve) Performance Prediction Program, Revision 2.
Project stage: Approval
2008-06-03
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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
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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
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NRC NEI Fee Waiver Request Changes to NEI 10-04 and NEI 13-10, Dated November 10, 2021
ML21306A3652021-10-29029 October 2021
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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
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2024-01-22
[Table view] |
Text
January 14, 2009 Mr. James H. Riley, Director Engineering Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708
SUBJECT:
SUPPLEMENT 4 TO DRAFT SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE (NEI) ADDENDA 3, 4, 5, 6, AND 7 TO ELECTRIC POWER RESEARCH INSTITUTE (EPRI) TOPICAL REPORT (TR) 103237, EPRI MOV
[MOTOR-OPERATED VALVE] PERFORMANCE PREDICTION PROGRAM, REVISION 2 (TAC NO. MD3236)
Dear Mr. Riley:
In February 1994, the NEI submitted for U.S. Nuclear Regulatory Commission (NRC) review EPRI TR-103237, Revision 0. In November 1995, NEI submitted for NRC review the EPRI Topical Report TR-103237, Revision 1. On March 15, 1996, the NRC staff issued a safety evaluation (SE) documenting the staff's acceptance of the EPRI MOV Performance Prediction Methodology (PPM) described in the subject TR, with certain conditions and limitations. The SE addressed the EPRI computer model for globe and butterfly valves and various gate valves, and EPRI hand-calculation models for Anchor/Darling double disk gate valves and Westinghouse Electric Company flexible wedge gate valves. On February 20, 1997, the NRC staff issued Supplement 1 to the SE dated March 15, 1996. This supplemental SE discussed two additional gate valve (WKM parallel expanding and Aloyco split wedge) hand-calculation methods and highlighted other aspects of the TR.
On September 8, 1999, the NEI submitted for NRC review Addendum 1, PPM Version 2.0, and Addendum 2, Thrust Uncertainty Method, to EPRI TR-103237, Revision 2. Version 2.0 of the EPRI MOV PPM described in Addendum 1 to the TR resolves several previous modeling errors and incorporates other improvements to the modeling software. In Addendum 2 to TR-103237, Revision 2, the EPRI describes the development of its Thrust Uncertainty Method that takes into account conservatism in the EPRI MOV PPM to predict a more realistic thrust requirement for closing gate valves. On April 20, 2001, the NRC staff issued Supplement 2 to the SE dated March 15, 1996, concluding that the changes made to the PPM in Addendum 1 to TR-103237, Revision 2, improve the ability of the EPRI model to predict the applicable thrust or torque required to operate gate, globe, and butterfly valves.
On January 5 and December 6, 2001, and June 10, 2002, the NEI submitted for NRC review revisions to Addendum 2 to EPRI TR-103237, Revision 2. These revisions involved the establishment of additional criteria for application of the Thrust Uncertainty Method for gate valves under cold water applications within the scope of the Thrust Uncertainty Method.
J. Riley On September 30, 2002, the NRC staff issued Supplement 3 to the SE dated March 15, 1996, concluding that the Thrust Uncertainty Method developed by EPRI is acceptable for the prediction of minimum allowable thrust at control switch trip (or flow isolation) for applicable gate valves under cold water applications within the scope of the Thrust Uncertainty Method subject to the applicable limitations and conditions specified in the Thrust Uncertainty Method.
On June 8, 2004, the NEI submitted Addendum 5, PPM Version 3.1 Software Changes, Addendum 6, PPM Version 3.2 Software Changes, and recent PPM error and information notices to TR-103237, Revision 2, for NRC review. Addendum 5 provided PPM Software Version 3.1; updated the PPM to a Window-based application; automated certain manual calculations; adjusted the software to allow more ready use for air-operated valve (AOV) and hydraulic-operated valve (HOV) applications; and incorporated software and documentation improvements. Addendum 6 provided PPM Software Version 3.2; corrected potential non-conservative effects from upstream disturbances; and prevented incorrect use of best estimate butterfly valve torque predictions.
On January 6, 2006, the NEI submitted Addendum 3, An Improved and Validated Method for Predicting Gate Valve Unwedging Thrust Requirements, Addendum 4, Use of Static Closure Data for Determining Stem Stem-Nut Coefficients of Friction at Unwedging, and Addendum 7, PPM Version 3.3 Software Changes, to Topical Report TR-103237, Revision 2, for NRC review. Addenda 3, 4, and 7 document changes made to the EPRI PPM computer code between Versions 3.2 and 3.3, and also provide improved methods for evaluating gate valve undwedging thrust requirements.
On April 23, 2007, and June 3, 2008, the NRC staff requested that the NEI to submit additional information to support its request. The NEI submitted the requested information in letters dated September 27, 2007, and August 7, 2008.
Enclosed for NEI review and comment is a copy of the NRC staff's draft SE for the TR, Supplement 4 to Safety Evaluation Dated March 15, 1996: Addenda 3, 4, 5, 6, and 7 to EPRI TR-103237, Revision 2.
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we have determined that the enclosed draft SE does not contain proprietary information. However, we will delay placing the draft SE in the public document room for a period of 10 working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects.
If you believe that any information in the enclosure is proprietary, please identify such information line-by-line and define the basis pursuant to the criteria of 10 CFR 2.390. After 10 working days, the draft SE will be made publicly available, and an additional 10 working days are provided to you to comment on any factual errors or clarity concerns contained in the draft SE. The final SE will be issued after making any necessary changes and will be made publicly available. The NRC staff's disposition of your comments on the draft SE will be discussed in the final SE.
J. Riley To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the draft SE showing proposed changes and provide a summary table of the proposed changes.
If you have any questions, please contact Tanya Mensah at 301-415-3610.
Sincerely,
/RA/
Stacey L. Rosenberg, Chief Special Projects Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Project No. 689
Enclosure:
Supplement 4 to Draft SE cc w/encl: See next page
ML083440409 (Package); ML083430064 (Letter);
ML083430071 (Draft SE) *No major changes to SE input. NRR-043 OFFICE PSPB/PM PSPB/LA DCI/CPTB* PSPB/BC NAME TMensah DBaxley JMcHale SRosenberg DATE 01/05/09 12/30/09 10/30/08 01/14/09