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| | issue date = 01/14/2009 | | | issue date = 01/14/2009 |
| | title = 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 | | | title = 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 |
| | author name = Rosenberg S L | | | author name = Rosenberg S |
| | author affiliation = NRC/NRR/DPR/PSPB | | | author affiliation = NRC/NRR/DPR/PSPB |
| | addressee name = Riley J H | | | addressee name = Riley J |
| | addressee affiliation = Nuclear Energy Institute (NEI) | | | addressee affiliation = Nuclear Energy Institute (NEI) |
| | docket = PROJ0689 | | | docket = PROJ0689 |
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| ==SUBJECT:== | | ==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 | | 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) | | [MOTOR-OPERATED VALVE] PERFORMANCE PREDICTION PROGRAM, REVISION 2" (TAC NO. MD3236) |
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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
MONTHYEARML24204A2162024-07-22022 July 2024 Withdrawal of Fee Exemption Request for Endorsement of NEI White Paper, “Selection of a Seismic Scenario for an EPZ Boundary Determination” ML24204A2082024-07-22022 July 2024 07-22-24_NRC_NEI Withdrawal of Fee Exemption Request for Wp Selection of Seismic Scenario for EPZ Determination ML24187A0552024-07-0303 July 2024 Fee Exemption Request for NEI White Paper Selection of Seismic Scenario for EPZ Determination ML24173A2712024-06-14014 June 2024 NEI - Proposed Changes to Inspection Procedure (IP) 71130.10, Cybersecurity ML24165A0862024-06-13013 June 2024 NEI White Paper - Proposed Control Room Dose Acceptance Criteria Supporting RG 1.183 R2 ML24165A0852024-06-13013 June 2024 NEI White Paper - Impact of Higher Source Term Fractions on EQ Doses ML24165A0872024-06-12012 June 2024 NEI White Papers Supporting NRC Workshop Discussions Regarding Nuclear Regulatory Commissions (NRC) Potential Changes to Regulatory Guide 1.183 ML24152A3242024-05-31031 May 2024 NEI Concept Paper: Regulation of Rapid High-Volume Deployable Reactors in Remote Locations ML24159A7312024-05-23023 May 2024 05-23-24 Nuclear Energy Institute Letter to the U.S. Nuclear Regulatory Commission Re Industry Comments on Buildings as Items Relied on for Safety ML24135A1982024-04-23023 April 2024 SFAQ No 2022-02, SAE Program Requirements - NEI Withdrawal Letter ML24078A2212024-03-15015 March 2024 3-15-24 NEI Letter Aveil from Juhle on Pur ML24061A0572024-02-29029 February 2024 Endorsement of NEI 08-09, Revision 7, Changes to NEI 08-09 Cyber Security Plan for Nuclear Power Reactors ML24023A0392024-01-22022 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 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 ML23110A6752023-04-18018 April 2023 04-18-23_NRC_Fee Waiver for NEI 23-03 ML24120A2702023-04-0404 April 2023 Melody Rodridguez NEI Comment on Controlled Unclassified Information ML23107A2302023-03-31031 March 2023 NEI Letter, to Andrea Veil, NRC, Regarding Industry Recommendations for a 10 CFR 50.46a/c Combined Rulemaking 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 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 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 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 ML22153A2782022-06-0202 June 2022 Nie, Fee Exemption Request for Endorsement of NEI 15-09, Cyber Security Event Notifications, Revision 1, Dated May 2022 ML22152A2712022-06-0101 June 2022 Digital Instrumentation and Control Common Cause Failure Policy Considerations, Revision 1 2024-07-03
[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 pr edict 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