ML13247A452: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(11 intermediate revisions by the same user not shown) | |||
Line 2: | Line 2: | ||
| number = ML13247A452 | | number = ML13247A452 | ||
| issue date = 09/04/2013 | | issue date = 09/04/2013 | ||
| title = | | title = NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology | ||
| author name = Beltz T | | author name = Beltz T | ||
| author affiliation = NRC/NRR/DORL/LPLIII-1 | | author affiliation = NRC/NRR/DORL/LPLIII-1 | ||
| addressee name = Adams G | | addressee name = Adams G | ||
Line 14: | Line 14: | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:MF2479 | | project = TAC:MF2479 | ||
| stage = Acceptance Review | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter: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 - Acceptance Review re: License Amendment Request to Transition to AREVA ATRIUM 10XM Fuel & AREVA Safety Analysis Methodology (TAC No. MF2479) | |||
==Dear Mr. Adams:== | |||
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: | 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 staffs 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-3119P, Mechanical Design Report for Monticello ATRIUM 10XM Fuel Assemblies | ||
* ANP-3092P, Monticello Thermal-Hydraulic Design Report for ATRIUM 10XM Fuel Assemblies | * ANP-3092P, Monticello Thermal-Hydraulic Design Report for ATRIUM 10XM Fuel Assemblies | ||
Line 31: | Line 37: | ||
* ANP-3139P, Nuclear Fuel Design Report Monticello Cycle 28 ATRIUM 10XM Fuel | * 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) | * 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: | * 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-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-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) | * ANP-3212P, Monticello LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel (EPU/MELLLA) 1 | ||
Finally, the NRC staff notes that the remaining enclosure to the LAR, ANP-2637, Boiling Water Reactor Licensing Methodology Compendium, serves as a general reviewers 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 concluded 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 safety 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 has reviewed your application and concluded 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 safety 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 additional information no later than November 6, 2013. Should you have any questions regarding this review, please contact me at (301) 415-3049. | The NRC staff anticipates to issue any requests for additional information no later than November 6, 2013. | ||
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD | 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 2 | |||
Hearing Identifier: NRR_PMDA Email Number: 826 Mail Envelope Properties (Terry.Beltz@nrc.gov20130904070600) | |||
==Subject:== | ==Subject:== | ||
Monticello Nuclear Generating Plant - Acceptance Review re: License Amendment Request to Transition to AREVA ATRIUM 10XM Fuel & AREVA Safety Analysis Methodology (TAC No. MF2479) | Monticello Nuclear Generating Plant - Acceptance Review re: License Amendment Request to Transition to AREVA ATRIUM 10XM Fuel & AREVA Safety Analysis Methodology (TAC No. MF2479) | ||
Sent Date: | 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: | ||
Tracking Status: None | "gene.eckholt@xenuclear.com" <gene.eckholt@xenuclear.com> | ||
Tracking Status: None | 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:}} |
Latest revision as of 11:48, 5 December 2019
ML13247A452 | |
Person / Time | |
---|---|
Site: | Monticello ![]() |
Issue date: | 09/04/2013 |
From: | Beltz T Plant Licensing Branch III |
To: | George Adams Northern States Power Co |
References | |
TAC MF2479 | |
Download: ML13247A452 (3) | |
Text
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 - Acceptance 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 staffs 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) 1
Finally, the NRC staff notes that the remaining enclosure to the LAR, ANP-2637, Boiling Water Reactor Licensing Methodology Compendium, serves as a general reviewers 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 concluded 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 safety 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 additional 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 2
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 Transition 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: