|
|
| Line 2: |
Line 2: |
| | number = ML13247A452 | | | number = ML13247A452 |
| | issue date = 09/04/2013 | | | issue date = 09/04/2013 |
| | title = Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology | | | title = Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology |
| | author name = Beltz T A | | | author name = Beltz T A |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARL-MT-14-022, the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp2002-10-10010 October 2002
the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp
Project stage: Other
ML13247A4522013-09-0404 September 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology
Project stage: Acceptance Review
ML13353A3662013-12-18018 December 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Request for Additional Information NRC Staff Review of Areva Fuel Transition License Amendment Request
Project stage: Approval
L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014
Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information
Project stage: Response to RAI
ML14035A2982014-01-31031 January 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Response to RAI
ML14077A3022014-03-12012 March 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Request
ML14090A0052014-03-27027 March 2014
NRR E-mail Capture - Monticello Nuclear Generating Plant - NRC Staff Request for Additional Information (Follow-up Question) Areva Fuel Transition License Amendment Request
Project stage: RAI
L-MT-14-033, Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period2014-04-29029 April 2014
Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period
Project stage: Supplement
L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014
ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.
Project stage: Other
ML14132A1942014-05-0909 May 2014
Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information
Project stage: Response to RAI
L-MT-14-042, Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request2014-05-0909 May 2014
Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request
Project stage: Request
ML14155A1672014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on January 23, 2014, by Mr. Alan B. Meginnis of Areva Np, Inc.
Project stage: Withholding Request Acceptance
ML14155A1692014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 22, 2014, by Mr. Alan B. Meginnis of Areva Inc.
Project stage: Withholding Request Acceptance
ML14155A1772014-07-0808 July 2014
Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 28, 2014, by Mr. Philip A. Opsal of Areva Inc.
Project stage: Withholding Request Acceptance
ML15154A4772015-06-0505 June 2015
Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted)
Project stage: Approval
ML15072A1412015-06-0505 June 2015
Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods
Project stage: Approval
L-MT-15-091, Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462015-12-22022 December 2015
Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
Project stage: Request
L-MT-16-027, Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462016-05-24024 May 2016
Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
Project stage: Other
2014-03-27
[Table View] |
|
|---|
Category:E-Mail
MONTHYEARML24022A0212024-01-20020 January 2024
NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f)
ML23353A0742023-12-19019 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17
ML23348A3462023-12-14014 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML23268A0292023-09-20020 September 2023
SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23249A2092023-09-0606 September 2023
NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX)
ML23248A3462023-09-0505 September 2023
NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports
ML23237A4822023-08-25025 August 2023
SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen
ML23228A1212023-08-16016 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397
ML23227A2182023-08-15015 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f)
ML23219A1072023-08-0707 August 2023
SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23200A3502023-07-19019 July 2023
SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23172A1122023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23054A3322023-02-23023 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record
ML23053A1362023-02-13013 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program
ML23017A2222023-01-13013 January 2023
Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email)
ML23004A1982023-01-0404 January 2023
NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing
ML23012A2102022-07-26026 July 2022
Letter Submitting Monticello Outline Package
ML22181A1962022-06-24024 June 2022
NRR E-mail Capture - Draft RAI Monticello Alternative VR-08
ML22175A1602022-06-24024 June 2022
NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection
ML22131A2652022-05-11011 May 2022
NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island
ML22123A2822022-05-0303 May 2022
NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency
ML22101A0712022-04-11011 April 2022
NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
ML22089A1302022-03-30030 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency
ML22082A1812022-03-23023 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28
ML22075A2612022-03-16016 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26
ML22067A2032022-03-0808 March 2022
Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted)
ML22011A0642022-01-11011 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection
ML22005A3612022-01-0505 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22
ML21347A0082021-12-10010 December 2021
NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility
ML21330A0382021-11-18018 November 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing
ML21286A7882021-10-0606 October 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing
ML21256A1892021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves
ML21256A1862021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing
ML21256A1882021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps
ML21253A2002021-09-10010 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing
ML21252A0132021-08-31031 August 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies
ML21130A3022021-05-0707 May 2021
Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
ML21110A7042021-04-20020 April 2021
Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees
ML21084A2522021-03-24024 March 2021
NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062)
ML21068A2772021-03-0909 March 2021
NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20342A1782020-12-0707 December 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR
ML20302A1972020-10-26026 October 2020
NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request
ML20289A1072020-10-0606 October 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements (EPID L-2020-LLA-0209
ML20191A0252020-07-0101 July 2020
NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations
ML20120A0272020-04-28028 April 2020
NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan
ML20099F1292020-04-0606 April 2020
E-mail to Licensee for Monticello Lr Phase 4 RFI
ML20077L4632020-03-17017 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529
ML20064C5352020-03-0404 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Revise the Previously Authorized Alternative in RR-008 for the H8 and H9 Welds
2024-01-20
[Table view] |
Text
1 NRR-PMDAPEm Resource From: Beltz, Terry Sent: Wednesday, September 04, 2013 7:06 AM To: Adams, Glenn D.
Cc: gene.eckholt@xenuclear.com; Fields, John S
.; Panicker, Mathew; Parks, Benjamin; Duvigneaud, Dylanne; Sallman, Ahsan; Carlson, Robert
Subject:
Monticello Nuclear Generating Plant - Acc eptance Review re: License Amendment Request to Transition to AREVA ATRIUM 10XM Fuel
& AREVA Safety Analysis Methodology (TAC No. MF2479)
Dear Mr. Adams:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 15, 2013 (Agencywide Documents Access and Management System Accession No. ML13200A185), Northern States Power Company -
Minnesota (NSPM), doing business as Xcel Energy, requested an amendment to the Renewed Facility
Operating License No. DPR-22, for the Monticello Nuclear Generating Plant (MNGP). The proposed license amendment request (LAR) involves a fuel transition from Global Nuclear Fuels (GNF) GE14 fuel design to AREVA ATRIUM 10XM fuel design for use at MGNP. The LAR also proposes to 1) revise MGNP technical specification (TS) 5.6.3 by adding the AREVA analysis methodologies to the list of approved methods to be used in determining the core operating limits in the Core Operating Limits Report; 2) incorporate a minor change to MNGP TS 4.2.1 to specify ATRIUM 10XM fuel assembly water channel; and, 3) change TS 2.1.1, "Reactor Core Safety Limits," such that the steam dome pressure to be as low as 600 psia/586 psig. The values of the steam dome pressure and the Minimum Critical Power Ratio (MCPR) used in the proposed TS 2.1.1 are supported by the AREVA methodology and confirms the validity of the ACE CPR correlation for the new and co-resident fuel designs.
The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff in the Nuclear Performance and Code Review Branch of the Division of Safety Systems (DSS) performed the review of the following attachments to the LAR:
- ANP-3119P, Mechanical Design Report for Monticello ATRIUM 10XM Fuel Assemblies
- ANP-3092P, Monticello Thermal-Hydraulic Design Report for ATRIUM 10XM Fuel Assemblies
- ANP-3138P, Monticello Improved K-factor model for ACE/ATRIUM 10XM Critical Power Correlation
- ANP-3215P, Monticello Fuel Transition Cycle 28Fuel Cycle Design (EPU/MELLLA)
- ANP-3221P, Fuel Rod Thermal-Mechanical Design for Monticello ATRIUM 10XM Fuel Assemblies
- ANP-3139P, Nuclear Fuel Design Report Monticello Cycle 28 ATRIUM 10XM Fuel
- ANP-3224P, Applicability of AREVA NP BWR Methods to Monticello (Portions of this report)
- Sections of ANP-3213P, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (EPU/MELLLA)
In addition, the NRC staff in the Reactor Systems Branch of DSS reviewed the following attachments:
- ANP-3213P, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (EPU/MELLLA)
- ANP-3211P, Monticello LOCA Break Spectrum Analysis for ATRIUM 10XM Fuel (EPU/MELLLA)
- ANP-3212P, Monticello LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel (EPU/MELLLA)
2Finally, the NRC staff notes that the remaining enclosure to the LAR, ANP-2637, Boiling Water Reactor Licensing Methodology Compendium, serves as a general reviewer's aid pertaining to the AREVA BWR safety analysis methods.
The NRC staff has been currently reviewing three license amendments requests from Xcel Energy for MNGP: (1) an extended power uprate (EPU) with Maximum Extended Load Line Limit Analysis (MELLLA); (2) MELLLA Plus, and (3) reduction in steam dome pressure to as low as 700 psia. NSPM has indicated that implementation of this proposed amendment for transitioning to ATRIUM 10XM would preclude the use of MELLLA+ extended power-flow operating domain. The proposed LAR for reduction in dome pressure to 600 psia will need to be reconciled with the LAR that proposed reduction of steam dome pressure to 700 psia that is currently under NRC review during the course of review of the latest submittal.
The NRC staff has reviewed your application and concl uded that the information in the July 15, 2013, application provides technical information in sufficient detail to enable the staff to complete a detailed technical review and make an independent assessment regarding the acceptability of the LAR in terms of regulatory requirements and protection of public health and safe ty and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.
The NRC staff anticipates to issue any requests for additi onal information no later than November 6, 2013.
Should you have any questions regarding this review, please contact me at (301) 415-3049.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mail Stop: O-8D15 Phone: (301) 415-3049 Terry.Beltz@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 826 Mail Envelope Properties (Terry.Beltz@nrc.gov20130904070600)
Subject:
Monticello Nuclear Generating Plant - Acceptance Review re: License Amendment Request to Transitio n to AREVA ATRIUM 10XM Fuel & AREVA Safety Analysis Methodology (TAC No. MF2479)
Sent Date: 9/4/2013 7:06:03 AM Received Date: 9/4/2013 7:06:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov
Recipients: "gene.eckholt@xenuclear.com" <gene.eckholt@xenuclear.com> Tracking Status: None "Fields, John S." <John.Fields@xenuclear.com> Tracking Status: None "Panicker, Mathew" <Mathew.Panicker@nrc.gov> Tracking Status: None "Parks, Benjamin" <Benjamin.Parks@nrc.gov>
Tracking Status: None "Duvigneaud, Dylanne" <Dylanne.Duvigneaud@nrc.gov> Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov> Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Adams, Glenn D." <Glenn.Adams@xenuclear.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 4958 9/4/2013 7:06:00 AM
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
