ML13050A019: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Beltz, Terry Sent: Friday, February 15, 2013 8:07 AM To: 'Adams, Glenn D.' | ||
Cc: 'Eckholt, Gene F.'; Hunt, Christopher; Yoder, Matthew; Wong, Emma | |||
==Subject:== | ==Subject:== | ||
Monticello Nuclear Generating Plant - | Monticello Nuclear Generating Plant - Reques t for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) | ||
Attachments: | |||
Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No. | |||
ME9893).docx | |||
==Dear Mr. Adams:== | ==Dear Mr. Adams:== | ||
By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs. | By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs. | ||
The U.S. Nuclear Regulatory Commission (NRC) staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The ESGB staff has determined that additional information is required to complete its review. The draft request for additional information (RAI) is attached. | |||
The U.S. Nuclear Regulatory Commission (NRC) staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The ESGB staff has determined that additional information is required to complete its review. The draft request for additional information (RAI) is attached. | |||
You may accept this draft RAI as a formal Request for Additional Information and respond to the questions by March 28, 2013. Alternatively, you may request to discuss the contents of this RAI with the NRC staff in a conference call, including any change to the proposed response date. | You may accept this draft RAI as a formal Request for Additional Information and respond to the questions by March 28, 2013. Alternatively, you may request to discuss the contents of this RAI with the NRC staff in a conference call, including any change to the proposed response date. | ||
Please let me know if you have any questions or concerns. Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov Hearing Identifier: NRR_PMDA | Please let me know if you have any questions or concerns. | ||
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov | |||
Hearing Identifier: NRR_PMDA Email Number: 612 Mail Envelope Properties (87B1F1BDFE5A554CA9D C5EAA75EB6D0DC63D87391B) | |||
==Subject:== | ==Subject:== | ||
Monticello Nuclear Generating Plant - Request for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) Sent Date: 2/15/2013 8:07:08 AM Received Date: 2/15/2013 8:07:00 AM | Monticello Nuclear Generating Plant - Request for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) Sent Date: 2/15/2013 8:07:08 AM Received Date: 2/15/2013 8:07:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "'Eckholt, Gene F.'" <Eugene.Eckholt@xenuclear.com> Tracking Status: None "Hunt, Christopher" <Christopher.Hunt@nrc.gov> Tracking Status: None "Yoder, Matthew" <Matthew.Yoder@nrc.gov> | ||
Tracking Status: None "Wong, Emma" <Emma.Wong@nrc.gov> Tracking Status: None | Tracking Status: None "Wong, Emma" <Emma.Wong@nrc.gov> Tracking Status: None | ||
"'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com> Tracking Status: None Post Office: HQCLSTR01.nrc.gov | "'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com> Tracking Status: None | ||
REQUEST FOR ADDITIONAL INFORMATION REGARDING MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST SUPPORTING SPENT FUEL STORAGE CHANGES SPENT FUEL POOL NEUTRON ABSORBING MATERIAL NORTHERN STATES POWER COMPANY - MINNESOTA | |||
: 1. When was the last time a neutron attenuation test was performed (in-situ or coupon) for the Boral in the MNGP spent fuel pool? | Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1441 2/15/2013 8:07:00 AM Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No. ME9893).docx 23140 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | ||
2. When is the next planned neutron attenuation test at MNGP? | REQUEST FOR ADDITIONAL INFORMATION REGARDING MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST SUPPORTING SPENT FUEL STORAGE CHANGES SPENT FUEL POOL NEUTRON ABSORBING MATERIAL NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant (MNGP) Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs. The U.S. Nuclear Regulatory Commission staff in the Steam Generator Tube Integrity and Chemical Engineering Branch of the Office of Nuclear Reactor Regulation has determined that additional information is required to complete its review. The NRC staff requests the following information: | ||
3. Your application states that Boral integrity is managed using the Water Chemistry Aging Management Program and One-time Inspection Program as described in NUREG-1865. While the use of Industry and historical plant operating experience is useful for informing a neutron absorbing material aging management program, it is not an adequate replacement for physical testing. Additionally, your Water Chemistry Aging Management Program does not include neutron attenuation testing. The concern is how MNGP will continue to monitor and mitigate any degradation or deformation of your Boral so that it will not reduce the neutron attenuation capability of the material in the future. | : 1. When was the last time a neutron attenuation test was performed (in-situ or coupon) for the Boral in the MNGP spent fuel pool? | ||
: a. Discuss whether you plan on performing in-situ neutron attenuation testing on the Boral panels installed in the spent fuel pool? If so, provide the frequency, acceptance criteria, and proposed corrective actions should the acceptance criteria not be met after a given test. b. Alternatively, if in-situ testing will not be performed, describe the method you will use to detect any degradation, deformation, or reduction in neutron attenuation capability of your Boral, and what actions will be taken to monitor and mitigate future degradation, deformation, or reduction in neutron attenuation capability. | : 2. When is the next planned neutron attenuation test at MNGP? | ||
}} | : 3. Your application states that Boral integrity is managed using the Water Chemistry Aging Management Program and One-time Inspection Program as described in NUREG-1865. While the use of Industry and historical plant operating experience is useful for informing a neutron absorbing material aging management program, it is not an adequate replacement for physical testing. Additionally, your Water Chemistry Aging Management Program does not include neutron attenuation testing. The concern is how MNGP will continue to monitor and mitigate any degradation or deformation of your Boral so that it will not reduce the neutron attenuation capability of the material in the future. | ||
: a. Discuss whether you plan on performing in-situ neutron attenuation testing on the Boral panels installed in the spent fuel pool? If so, provide the frequency, acceptance criteria, and proposed corrective actions should the acceptance criteria not be met after a given test. b. Alternatively, if in-situ testing will not be performed, describe the method you will use to detect any degradation, deformation, or reduction in neutron attenuation capability of your Boral, and what actions will be taken to monitor and mitigate future degradation, deformation, or reduction in neutron attenuation capability.}} | |||
Revision as of 00:52, 19 July 2018
| ML13050A019 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/15/2013 |
| From: | Beltz T A Plant Licensing Branch III |
| To: | Adams G D Northern States Power Co |
| References | |
| TAC ME9893 | |
| Download: ML13050A019 (4) | |
Text
1 NRR-PMDAPEm Resource From: Beltz, Terry Sent: Friday, February 15, 2013 8:07 AM To: 'Adams, Glenn D.'
Cc: 'Eckholt, Gene F.'; Hunt, Christopher; Yoder, Matthew; Wong, Emma
Subject:
Monticello Nuclear Generating Plant - Reques t for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893)
Attachments:
Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No.
ME9893).docx
Dear Mr. Adams:
By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The ESGB staff has determined that additional information is required to complete its review. The draft request for additional information (RAI) is attached.
You may accept this draft RAI as a formal Request for Additional Information and respond to the questions by March 28, 2013. Alternatively, you may request to discuss the contents of this RAI with the NRC staff in a conference call, including any change to the proposed response date.
Please let me know if you have any questions or concerns.
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 612 Mail Envelope Properties (87B1F1BDFE5A554CA9D C5EAA75EB6D0DC63D87391B)
Subject:
Monticello Nuclear Generating Plant - Request for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) Sent Date: 2/15/2013 8:07:08 AM Received Date: 2/15/2013 8:07:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "'Eckholt, Gene F.'" <Eugene.Eckholt@xenuclear.com> Tracking Status: None "Hunt, Christopher" <Christopher.Hunt@nrc.gov> Tracking Status: None "Yoder, Matthew" <Matthew.Yoder@nrc.gov>
Tracking Status: None "Wong, Emma" <Emma.Wong@nrc.gov> Tracking Status: None
"'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com> Tracking Status: None
Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1441 2/15/2013 8:07:00 AM Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No. ME9893).docx 23140 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REGARDING MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST SUPPORTING SPENT FUEL STORAGE CHANGES SPENT FUEL POOL NEUTRON ABSORBING MATERIAL NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant (MNGP) Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs. The U.S. Nuclear Regulatory Commission staff in the Steam Generator Tube Integrity and Chemical Engineering Branch of the Office of Nuclear Reactor Regulation has determined that additional information is required to complete its review. The NRC staff requests the following information:
- 1. When was the last time a neutron attenuation test was performed (in-situ or coupon) for the Boral in the MNGP spent fuel pool?
- 2. When is the next planned neutron attenuation test at MNGP?
- 3. Your application states that Boral integrity is managed using the Water Chemistry Aging Management Program and One-time Inspection Program as described in NUREG-1865. While the use of Industry and historical plant operating experience is useful for informing a neutron absorbing material aging management program, it is not an adequate replacement for physical testing. Additionally, your Water Chemistry Aging Management Program does not include neutron attenuation testing. The concern is how MNGP will continue to monitor and mitigate any degradation or deformation of your Boral so that it will not reduce the neutron attenuation capability of the material in the future.
- a. Discuss whether you plan on performing in-situ neutron attenuation testing on the Boral panels installed in the spent fuel pool? If so, provide the frequency, acceptance criteria, and proposed corrective actions should the acceptance criteria not be met after a given test. b. Alternatively, if in-situ testing will not be performed, describe the method you will use to detect any degradation, deformation, or reduction in neutron attenuation capability of your Boral, and what actions will be taken to monitor and mitigate future degradation, deformation, or reduction in neutron attenuation capability.