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| | issue date = 10/17/2011 | | | issue date = 10/17/2011 |
| | title = Acceptance Review Regarding the Proposed License Amendment Request to Eliminate License Condition 2.G | | | title = Acceptance Review Regarding the Proposed License Amendment Request to Eliminate License Condition 2.G |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
| | addressee name = Krich R M | | | addressee name = Krich R |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000390 | | | docket = 05000390 |
| | license number = | | | license number = |
| | contact person = Lamb J G | | | contact person = Lamb J |
| | case reference number = TAC ME7322 | | | case reference number = TAC ME7322 |
| | document type = Letter, Acceptance Review Letter | | | document type = Letter, Acceptance Review Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 17, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 WATTS BAR NUCLEAR PLANT, UNIT 1 -ACCEPTANCE REVIEW REGARDING THE PROPOSED LICENSE AMENDMENT REQUEST TO ELIMINATE LICENSE CONDITION 2.G (TAC NO. ME7322) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 17, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT, UNIT 1 -ACCEPTANCE REVIEW REGARDING THE PROPOSED LICENSE AMENDMENT REQUEST TO ELIMINATE LICENSE CONDITION 2.G (TAC NO. ME7322) |
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| ==Dear Mr. Krich:== | | ==Dear Mr. Krich:== |
| By letter dated October 5,2011 (Agencywide Documents and Access Management System Accession No. ML 11285A049), Tennessee Valley Authority (TVA) submitted a license amendment request for Watts Bar Nuclear Plant, Unit 1. The proposed amendment request would eliminate License Condition 2.G requiring reporting of violations of Section 2.C of the operating license. The proposed change is consistent with the U.S. Nuclear Regulatory Commission (NRC)-approved change notice published in the Federal Register on November 4, 2005 (70 FR 67202), announcing the availability of this improvement through the consolidated line item improvement process. The Federal Register Notice included a model safety evaluation and model no significant hazards consideration (NSHC) determination, relating to the elimination of the license condition involving reporting of violations of other requirements (typically in License Conditions 2.C) in the operating license of some commercial nuclear power plants. TVA affirmed the applicability of the model NSHC determination in its application dated October 5, 2011. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment 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. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. | | |
| Section 50.34 of 10 CFR addresses the content of technical information required. | | By letter dated October 5,2011 (Agencywide Documents and Access Management System Accession No. ML11285A049), Tennessee Valley Authority (TVA) submitted a license amendment request for Watts Bar Nuclear Plant, Unit 1. The proposed amendment request would eliminate License Condition 2.G requiring reporting of violations of Section 2.C of the operating license. |
| This section stipulates that the submittal address the design and operating characteristics, unusual or novel deSign features, and principal safety considerations. | | The proposed change is consistent with the U.S. Nuclear Regulatory Commission (NRC)-approved change notice published in the Federal Register on November 4, 2005 (70 FR 67202), announcing the availability of this improvement through the consolidated line item improvement process. The Federal Register Notice included a model safety evaluation and model no significant hazards consideration (NSHC) determination, relating to the elimination of the license condition involving reporting of violations of other requirements (typically in License Conditions 2.C) in the operating license of some commercial nuclear power plants. TVA affirmed the applicability of the model NSHC determination in its application dated October 5, 2011. |
| R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | | The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment 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. |
| If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), |
| | an amendment to the license must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel deSign features, and principal safety considerations. |
| | |
| | R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the 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. |
| If you have any questions, please contact me at (301) 415-3100. | | If you have any questions, please contact me at (301) 415-3100. |
| G. Lamb, Senior Project Manager p cial Projects Branch . ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | | 11~~?b G. Lamb, Senior Project Manager p cial Projects Branch |
| If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | | . ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv |
| | |
| | R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the 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. |
| If you have any questions, please contact me at (301) 415-3100. | | If you have any questions, please contact me at (301) 415-3100. |
| Docket No. 50-390 cc: Distribution via Listserv NRC Distribution PUBLIC LPWB Reading RidsAcrsAcnw
| | Sincerely, IRA! |
| _MailCTR Resource RidsNrrDraAadb Resource RidsNrrDraApla Resource RidsNrrDorl Resource RidsNrrDorlLp-Wb Resource RidsNrrPMWattsBar1 Resource RidsNrrLABClayton Resource Accession No'.. ML 11280A285 Sincerely, IRA! John G. Lamb, Senior Project Manager Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrDssScvb RidsNrrDeEeeb Resource GBowman. OEDO RHannah. OPA RII RidsNrrDirsltsb Resource OFFICE DORLlLPWB/PM DORLlLPWB/LA DORLlLPWB/BC NAME .JLamb BClayton SCampbell DATE 10/17/11 10/17111 10/17/11 OFFICIAL RECORD COpy}}
| | John G. Lamb, Senior Project Manager Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv NRC Distribution PUBLIC RidsOgcRp Resource LPWB Reading RidsNrrDorlDpr Resource RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrDraAadb Resource RidsNrrDssScvb RidsNrrDraApla Resource RidsNrrDeEeeb Resource RidsNrrDorl Resource GBowman. OEDO RidsNrrDorlLp-Wb Resource RHannah. OPA RII RidsNrrPMWattsBar1 Resource RidsNrrDirsltsb Resource RidsNrrLABClayton Resource Accession No'.. ML11280A285 OFFICE DORLlLPWB/PM DORLlLPWB/LA DORLlLPWB/BC NAME .JLamb BClayton SCampbell DATE 10/17/11 10/17111 10/17/11 OFFICIAL RECORD COpy}} |
Letter Sequence Acceptance Review |
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MONTHYEARML11285A0492011-10-0505 October 2011 Application to Eliminate License Condition 2.G Requiring Reporting of Violations of Section 2.C of Operating License (WBN-TS-11-13) Project stage: Request ML11280A2852011-10-17017 October 2011 Acceptance Review Regarding the Proposed License Amendment Request to Eliminate License Condition 2.G Project stage: Acceptance Review ML11285A2512012-01-0606 January 2012 Issuance of Amendment Regarding the Elimination of License Condition 2.G Project stage: Approval 2011-10-05
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
[Table view] Category:Acceptance Review Letter
MONTHYEARML21095A2482021-04-0101 April 2021 Acceptance Correspondence for Application to Modify TS for Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (EPID L-2021-LLA-0043 (Email) ML18248A0252018-09-0404 September 2018 Acceptance Review for Watts Bar Nuclear Plant, Units 1 and 2 - Adopt TSTF-266-A, Revision 3 ML18060A0542018-03-0101 March 2018 Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1, Fuel Assemblies, and Technical Specifications Related to Fuel Storage ML16340A0482016-11-30030 November 2016 Acceptance for Review - Request for Relief from ASME Section XI Coverage Examinations for Preservice Inspection (WBN-2_PSI-1) ML16340A0402016-11-30030 November 2016 Acceptance for Review - Request to Modify TS 3.7.12 Auxiliary Building Gas Treatment System ML15173A0972015-06-26026 June 2015 Acceptance Review Results for Requested License Amendment to Increase Tpbar Production ML13351A2202014-05-14014 May 2014 E-mail Accepted for Review of Request for an Alternative 13-ISI-01 to Extend the Reactor Vessel Weld ML14056A1142014-04-0707 April 2014 NRC Acceptance of Withdrawal of Request to Update Watts Bar Unit 1 Fire Protection License Condition to Allow Two-Unit Operation ML13260A2022013-09-17017 September 2013 Accepted for Review of Application to Modify Watts Bar Nuclear Plant Unit 1 Tech Spec Regarding AC Sources ML13032A5612013-02-0505 February 2013 Acceptance of Requested License Action Regarding Application to Modify Technical Specification 3.7.10 Control Room Emergency Ventilation System ML1209706852012-04-0606 April 2012 Acceptance Review for Watts Bar Nuclear Plant Unit 1 License Amendment Request ML11280A2852011-10-17017 October 2011 Acceptance Review Regarding the Proposed License Amendment Request to Eliminate License Condition 2.G ML1019000692010-07-15015 July 2010 Acceptance Review Regarding the Proposed Relief Request PV-02, Revision 1 ML1018908192010-07-13013 July 2010 Acceptance Review Regarding the Proposed Relief Request PV-05 ML1017504032010-06-30030 June 2010 Acceptence Review Regarding the Proposed Amendment Request for the Control Rod Assembles ML1006801422010-04-0101 April 2010 Acceptance Review Regarding the Proposed Allowed Outage Time One-Time Extension for the Chiller Upgrade Project (Tac No. ME3429) 2021-04-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 17, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 -ACCEPTANCE REVIEW REGARDING THE PROPOSED LICENSE AMENDMENT REQUEST TO ELIMINATE LICENSE CONDITION 2.G (TAC NO. ME7322)
Dear Mr. Krich:
By letter dated October 5,2011 (Agencywide Documents and Access Management System Accession No. ML11285A049), Tennessee Valley Authority (TVA) submitted a license amendment request for Watts Bar Nuclear Plant, Unit 1. The proposed amendment request would eliminate License Condition 2.G requiring reporting of violations of Section 2.C of the operating license.
The proposed change is consistent with the U.S. Nuclear Regulatory Commission (NRC)-approved change notice published in the Federal Register on November 4, 2005 (70 FR 67202), announcing the availability of this improvement through the consolidated line item improvement process. The Federal Register Notice included a model safety evaluation and model no significant hazards consideration (NSHC) determination, relating to the elimination of the license condition involving reporting of violations of other requirements (typically in License Conditions 2.C) in the operating license of some commercial nuclear power plants. TVA affirmed the applicability of the model NSHC determination in its application dated October 5, 2011.
The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR),
an amendment to the license must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel deSign features, and principal safety considerations.
R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the 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.
If you have any questions, please contact me at (301) 415-3100.
11~~?b G. Lamb, Senior Project Manager p cial Projects Branch
. ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv
R. M. Krich -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the 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.
If you have any questions, please contact me at (301) 415-3100.
Sincerely, IRA!
John G. Lamb, Senior Project Manager Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 cc: Distribution via Listserv NRC Distribution PUBLIC RidsOgcRp Resource LPWB Reading RidsNrrDorlDpr Resource RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrDraAadb Resource RidsNrrDssScvb RidsNrrDraApla Resource RidsNrrDeEeeb Resource RidsNrrDorl Resource GBowman. OEDO RidsNrrDorlLp-Wb Resource RHannah. OPA RII RidsNrrPMWattsBar1 Resource RidsNrrDirsltsb Resource RidsNrrLABClayton Resource Accession No'.. ML11280A285 OFFICE DORLlLPWB/PM DORLlLPWB/LA DORLlLPWB/BC NAME .JLamb BClayton SCampbell DATE 10/17/11 10/17111 10/17/11 OFFICIAL RECORD COpy