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| | issue date = 02/21/2012 | | | issue date = 02/21/2012 |
| | title = Email, Courtesy Notification of 50.54(f) Letter Regarding Thermal Conductivity Degradation (TAC No. M99899) | | | title = Email, Courtesy Notification of 50.54(f) Letter Regarding Thermal Conductivity Degradation (TAC No. M99899) |
| | author name = Singal B K | | | author name = Singal B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Hope T | | | addressee name = Hope T |
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| 10 CFR 50.54(f) Letters to Plants Using Westinghouse Realistic Emergency Core Cooling System (ECCS) Methods (ASTRUM or CQD) | | 10 CFR 50.54(f) Letters to Plants Using Westinghouse Realistic Emergency Core Cooling System (ECCS) Methods (ASTRUM or CQD) |
| On Thursday, February 16, 2012, the Nuclear Regulatory Commission (NRC) staff issued Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.54(f) letters to plants that use Westinghouse realistic emergency core cooling system (ECCS) methods (ASTRUM or CQD) and have a peak cladding temperature (PCT) greater than 2000 degrees F. The letters required that the plants listed below provide information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation (TCD), on peak cladding temperature in the Westinghouse Electric Company-furnished realistic ECCS evaluation models, to enable the NRC staff to determine whether the affected plant licenses should be modified, suspended, or revoked. A list of plants that received the 10 CFR 50.54(f) letters and ADAMS Accession number is below: | | On Thursday, February 16, 2012, the Nuclear Regulatory Commission (NRC) staff issued Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.54(f) letters to plants that use Westinghouse realistic emergency core cooling system (ECCS) methods (ASTRUM or CQD) and have a peak cladding temperature (PCT) greater than 2000 degrees F. The letters required that the plants listed below provide information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation (TCD), on peak cladding temperature in the Westinghouse Electric Company-furnished realistic ECCS evaluation models, to enable the NRC staff to determine whether the affected plant licenses should be modified, suspended, or revoked. A list of plants that received the 10 CFR 50.54(f) letters and ADAMS Accession number is below: |
| Beaver Valley, Units 1 and 2 - ADAMS Accession No. ML120400672 DC Cook, Units 1 and 2 - ADAMS Accession No. ML12041A384 Kewaunee - ADAMS Accession No. ML120410195 Byron, Unit 2 / Braidwood, Unit 2 - ADAMS Accession No. ML120410134 Catawba, Units 1 and 2 - ADAMS Accession No. ML12044A018 McGuire, Units 1 and 2 - ADAMS Accession No. ML12044 A019 You are receiving this information for awareness since Comanche Peak Nuclear Power Plants, Units 1 and 2 use the Westinghouse realistic ECCS methods (ASTRUM or CQD) but have a PCT less than 2000 degrees F. Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation, provides additional technical details on this issue. | | Beaver Valley, Units 1 and 2 - ADAMS Accession No. ML120400672 DC Cook, Units 1 and 2 - ADAMS Accession No. ML12041A384 Kewaunee - ADAMS Accession No. ML120410195 Byron, Unit 2 / Braidwood, Unit 2 - ADAMS Accession No. ML120410134 Catawba, Units 1 and 2 - ADAMS Accession No. ML12044A018 McGuire, Units 1 and 2 - ADAMS Accession No. ML12044A019 You are receiving this information for awareness since Comanche Peak Nuclear Power Plants, Units 1 and 2 use the Westinghouse realistic ECCS methods (ASTRUM or CQD) but have a PCT less than 2000 degrees F. Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation, provides additional technical details on this issue. |
| Balwant K. Singal Senior Project Manager (Comanche Peak, STP, and Palo Verde) | | Balwant K. Singal Senior Project Manager (Comanche Peak, STP, and Palo Verde) |
| Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222}} | | Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222}} |
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Category:E-Mail
MONTHYEARML24025A0172024-01-22022 January 2024
NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment
ML24019A0742024-01-19019 January 2024
NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator
ML24008A2492023-12-18018 December 2023
Texas Shpo Response for Comanche Peak Deis Review and Comment
ML23311A2202023-11-20020 November 2023
NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2023
ML23255A2882023-09-12012 September 2023
NRR E-mail Capture - Comanche Peak - Acceptance of Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
ML23256A1492023-09-11011 September 2023
Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4
ML23226A0072023-08-11011 August 2023
NRR E-mail Capture - Comanche Peak 1 and 2 Audit Plan - License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML23188A0442023-07-0707 July 2023
Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3
ML23181A0722023-06-29029 June 2023
NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML23181A0202023-06-29029 June 2023
Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2
ML23172A0152023-06-20020 June 2023
NRR E-mail Capture - Re Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81
ML23167A0222023-06-14014 June 2023
Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1
ML23145A2332023-05-25025 May 2023
Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 2
ML23143A1382023-05-23023 May 2023
Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 1
ML23139A0802023-05-18018 May 2023
NRR E-mail Capture - Comanche Peak Draft Supplemental Information Request - License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81
ML23138A1522023-05-18018 May 2023
Lr Docs - (External_Sender) Comanche Peak Nuclear Power Plants
ML23135A9132023-05-15015 May 2023
NRR E-mail Capture - Comanche Peak - Draft Supplemental Information Request - License Amendment Request to 10 CFR 50.69
ML23131A2932023-05-11011 May 2023
Lr Docs - License Renewal for Comanche Peak Nuclear Power Plant, Units 1 and 2
ML23128A1612023-05-0808 May 2023
NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing
ML23110A7122023-04-20020 April 2023
NRR E-mail Capture - Comanche Peak - Verbal Authorization of Proposed Alternative RV-1 (L-2023-LLR-0019)
ML23103A4682023-04-11011 April 2023
NRR E-mail Capture - Comanche Peak Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model
ML23086B9852023-03-27027 March 2023
NRR E-mail Capture - Comanche Peak Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model
ML23061A1612023-03-0202 March 2023
E-mail from David Griggs Regarding Submission to NRC Electronic Information Exchange on 03/01/2023 for Citizens for Fair Utility Regulation in Comanche Peak Proceeding
ML23032A3842023-02-0101 February 2023
LRA On-Site Audit Needs List
ML23214A0192023-01-30030 January 2023
(External_Sender) Request to Broaden Extended Deadline to the General Public (with Attachments) - C3
ML23214A0202023-01-29029 January 2023
(External_Sender) Requesting a Deadline Extension on NRC-2002-0183, Comanche Peak License Renewal - C2
ML23214A0182023-01-26026 January 2023
(External Sender) NRC-2022-0183-0003 (with Attachment) - C6
ML23214A0162023-01-24024 January 2023
(External Sender) EPA Scoping Comment Letter for the Comanche Peak Nuclear Power Plant License Renewal (with Attachment) - C8
ML23214A0142023-01-23023 January 2023
(External Sender) Docket NRC-2022-0183 Comanche Peak Nuclear Power Plant Renewal (with Attachment) - C1
ML23214A0172023-01-17017 January 2023
(External Sender) NRC License Extension? No!
ML23214A0132023-01-17017 January 2023
(External Sender) Docket Id NRC-2022-0183, Request for Extension of License for Comanche Peak, Comment for Environmental Scoping - C9
ML23214A0122023-01-13013 January 2023
(External Sender) Correction to Comment Submitted 01-13-23 - C11
ML22362A0992022-12-28028 December 2022
NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Apply Westinghouse Fsloca Evaluation Model
ML22362A0972022-12-28028 December 2022
NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications,
ML22325A2742022-11-21021 November 2022
NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps
ML22318A3102022-11-10010 November 2022
NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps
ML22237A2842022-08-25025 August 2022
CPNPP 2022 EP Program Inspection RFI Hjs 08252022
ML22230B1092022-08-17017 August 2022
NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing
ML22229A0792022-08-17017 August 2022
NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps
ML22220A1942022-08-0808 August 2022
NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing
ML22133A0472022-05-13013 May 2022
July 2022 Emergency Preparedness Exercise Inspection - Request for Information
ML22083A0262022-03-23023 March 2022
NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2
ML22031A2122022-01-31031 January 2022
NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative to Extend the Snubber Inservice Program Third Interval
ML21300A1342021-10-27027 October 2021
NRR E-mail Capture - Comanche Peak Units 1 and 2 - License Amendment Request to Adopt TSTF-505 - Audit Plan Update and Audit Questions (L-2021-LLA-0085)
ML21286A7912021-10-13013 October 2021
NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1
ML21272A2002021-09-29029 September 2021
NRR E-mail Capture - Comanche Peak Unit 2 - Upcoming Steam Generator Tube Inservice Inspection (L-2021-NFO-0013)
ML21270A1632021-09-27027 September 2021
NRR E-mail Capture - Comanche Peak - Acceptance of Quality Assurance Program Change Request Regarding Internal Audit Frequency
ML21253A2242021-09-0909 September 2021
Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021
ML21252A0062021-08-26026 August 2021
NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
2024-01-22
[Table view] |
Text
From: Singal, Balwant Sent: Tuesday, February 21, 2012 8:22 AM To: 'Hope, Timothy' Cc: Paige, Jason
Subject:
10 CFR 50.54(f) Letters to Plants Using Westinghouse Realistic Emergency Core Cooling System (ECCS) Methods (ASTRUM or CQD)
On Thursday, February 16, 2012, the Nuclear Regulatory Commission (NRC) staff issued Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.54(f) letters to plants that use Westinghouse realistic emergency core cooling system (ECCS) methods (ASTRUM or CQD) and have a peak cladding temperature (PCT) greater than 2000 degrees F. The letters required that the plants listed below provide information regarding the effect of a potentially significant error, as defined in 10 CFR 50.46(a)(3)(i), associated with thermal conductivity degradation (TCD), on peak cladding temperature in the Westinghouse Electric Company-furnished realistic ECCS evaluation models, to enable the NRC staff to determine whether the affected plant licenses should be modified, suspended, or revoked. A list of plants that received the 10 CFR 50.54(f) letters and ADAMS Accession number is below:
Beaver Valley, Units 1 and 2 - ADAMS Accession No. ML120400672 DC Cook, Units 1 and 2 - ADAMS Accession No. ML12041A384 Kewaunee - ADAMS Accession No. ML120410195 Byron, Unit 2 / Braidwood, Unit 2 - ADAMS Accession No. ML120410134 Catawba, Units 1 and 2 - ADAMS Accession No. ML12044A018 McGuire, Units 1 and 2 - ADAMS Accession No. ML12044A019 You are receiving this information for awareness since Comanche Peak Nuclear Power Plants, Units 1 and 2 use the Westinghouse realistic ECCS methods (ASTRUM or CQD) but have a PCT less than 2000 degrees F. Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting From Nuclear Fuel Thermal Conductivity Degradation, provides additional technical details on this issue.
Balwant K. Singal Senior Project Manager (Comanche Peak, STP, and Palo Verde)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222
