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Category:Code Relief or Alternative
MONTHYEARML22307A2462022-11-10010 November 2022 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (EPIDs L-2021-LLR-0035 and L-2021-LLR-0036) RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21134A0062021-08-0303 August 2021 Proposed Alternatives to the Requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (Epids L-2020-LLR-0099 and L-2020-LLR-0100) RS-21-008, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)2021-01-25025 January 2021 Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20245E5062020-09-0909 September 2020 Relief from the Requirements of the ASME Code (COVID-19) ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19136A3862019-06-0505 June 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML19141A0202019-06-0505 June 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML19155A0602019-06-0505 June 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19035A2942019-02-25025 February 2019 Relief from the Requirements of the ASME Code JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds RS-19-015, Relief Request 14-RS-1 to Implement Code Case OMN-132019-01-31031 January 2019 Relief Request 14-RS-1 to Implement Code Case OMN-13 ML18318A3342019-01-17017 January 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML18331A0372019-01-17017 January 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML18347B4192019-01-17017 January 2019 Relief Request I4R-03, Relief from ASME Requirements for the Fourth 10-Year Inservice Inspection Interval Related to Degraded Canopy Seal Welds Associated with Control Rod Drive Mechanism ML18305A3602018-12-0606 December 2018 Relief from the Requirements of the American Society of Mechanical Engineers Code RS-18-125, Proposed Alternative Requirements for the Repair and Examination of Reactor Pressure Vessel Head Penetration Nozzles for the Fourth Lnservice Inspection Interval in Accordance with 10 CFR 50.55a(z)(1)2018-10-11011 October 2018 Proposed Alternative Requirements for the Repair and Examination of Reactor Pressure Vessel Head Penetration Nozzles for the Fourth Lnservice Inspection Interval in Accordance with 10 CFR 50.55a(z)(1) RS-18-123, Request for Alternative Follow-up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)2018-09-24024 September 2018 Request for Alternative Follow-up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML17325B5712018-01-10010 January 2018 Non-Proprietary, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Services (CAC No. MF9854; EPID L-2017-LLR-0042) RS-17-168, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1)2017-12-20020 December 2017 Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1) RS-17-168, Braidwood Station, Unit 2, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1)2017-12-20020 December 2017 Braidwood Station, Unit 2, Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(1) ML17249A2982017-11-13013 November 2017 Relief from the Requirements of the ASME Code (CAC No. MF9597; EPID L-2017-LLR-0021) ML17249A2412017-09-19019 September 2017 Relief from the Requirements of the ASME Code RS-17-083, Inservice Inspection Program Third Interval Relief Requests 13R-12 and 13R-152017-06-29029 June 2017 Inservice Inspection Program Third Interval Relief Requests 13R-12 and 13R-15 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17095A2682017-03-31031 March 2017 Submittal of Request for Relief for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces: Attachment 1, Relief Request ML17054C2552017-03-15015 March 2017 Request for Relief from Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) ML17062A4282017-03-0606 March 2017 Request for Relief from the Requirements of the ASME Code ML17047A0382017-02-24024 February 2017 Request I4R-11 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) ML16327A3182016-12-20020 December 2016 Request I4R-06, Relief from the Requirements of the ASME Code ML16327A3962016-12-20020 December 2016 Request I4R-01, Relief from the Requirements of the ASME Code ML16327A4212016-12-19019 December 2016 Requested Relief from the Requirements of the Asme Code (CAC Nos. MF7641 and MF7642) ML16306A3662016-11-0808 November 2016 Request I4R-08, Relief from the Requirements of the ASME Code ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16162A2112016-06-29029 June 2016 Request for Use of Alternative ML16109A3372016-04-27027 April 2016 Relief from the Requirements of the ASME Code (CAC Nos. MF6715, MF6716, MF6717, and MF6718) ML15173A4362015-06-30030 June 2015 Relief from the Requirements of the ASME Code RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval2015-06-22022 June 2015 Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval 2022-09-20
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code ML23241A9092023-09-19019 September 2023 Enclosure 2 - Non-Proprietary - Review of License Renewal Commitment Number 10 Safety Evaluation ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML22305A6992022-12-28028 December 2022 Issuance of Amendment Nos. 231 and 231 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22307A2462022-11-10010 November 2022 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (EPIDs L-2021-LLR-0035 and L-2021-LLR-0036) ML22210A0312022-08-30030 August 2022 Issuance of Amendments Nos. 230, 230, 230, and 230, Respectively, Regarding Adoption of Technical Specifications Task Force Traveler (TSTF) 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22173A1812022-08-11011 August 2022 Issuance of Amendment No. 229 to Remove License Condition ML22173A2142022-08-10010 August 2022 Issuance of Amendments Nos. 228 and 228 Revision of Technical Specifications for the Ultimate Heat Sink ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21076A3712021-08-17017 August 2021 Approval of Certified Fuel Handler Training and Retraining Program ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21134A0062021-08-0303 August 2021 Proposed Alternatives to the Requirements of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (Epids L-2020-LLR-0099 and L-2020-LLR-0100) ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21166A1682021-06-25025 June 2021 ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21054A0082021-03-10010 March 2021 Issuance of Amendment Nos. 220 and 220 One-Time Deferral of Steam Generator Tube Inspections ML21063A0162021-03-0808 March 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Alternative to 10 CFR 50.55a(z)(2) ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20245E4192020-09-24024 September 2020 Issuance of Amendments Nos. 218 and 218 Revision of Technical Specifications for the Ultimate Heat Sink ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20163A0462020-09-18018 September 2020 Issuance of Amendments Nos. 217, 217, 221, and 221, Revise Technical Specification 5.6.6 to Allow Use of Areva Np Topical Report BAW-2308 ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20149K6982020-09-10010 September 2020 Issuance of Amendment Nos. 215, 215, 219, and 219 Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20133K0932020-05-14014 May 2020 Relief from the Requirements of the ASME Code ML20111A0002020-05-0101 May 2020 Issuance of Amendment No. 209, Revision Technical Specification 5.5.9, Steam Generator (SG) Program, for One-Time Revision to Frequency of SG Tube Inspections (Exigent Circumstances) ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels 2023-09-19
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 March 3, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 - RELIEF REQUEST FROM ASME CODE CASE N-729-1 REQUIREMENTS FOR EXAMINATION OF REACTOR VESSEL HEAD PENETRATION WELDS (TAC NOS. ME3510, ME3511, ME3512, and ME3513)
Dear Mr. Pacilio:
By letter to the U.S. Nuclear Regulatory Commission (NRC), dated March 12, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100710764), as supplement by letter dated December 6,2010 (ADAMS Accession No. ML103410394). Exelon Generation Company, LLC (the licensee), submitted a relief request from certain requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(D) for the third 10-year inservice inspection (lSI) interval of Braidwood Station (Braidwood), Units 1 and 2, and Byron Station (Byron), Units Nos. 1 and 2.
The submittal requests authorization of a proposed alternative from the inspection requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, ASME Code Case N-729-1, for the examination of reactor pressure vessel upper head penetrations for the control rod drive mechanism (CRDM).
Specifically, pursuant to 10 CFR 50.55a(a)(3)(ii), the licensee requested to use the alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty.
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, and that the alternative proposed will provide reasonable assurance of structural integrity of the CRDM nozzles. Therefore, the alternative proposed is authorized pursuant to 10 CFR 50.55a(a)(3)(ii), for the third 10-year lSI interval for Braidwood, Units 1 and 2, and Byron, Unit Nos. 1 and 2, or until the respective head for each unit is replaced, whichever comes first.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including a third-party review by the Authorized Nuclear Inservice Inspector. The NRC staff's safety evaluation is enclosed.
M. Pacilio -2 Please contact Mr. Nicholas DiFrancesco at (301) 415-1115 if you have any questions on this action.
Sincerely, Robert D. Carlson, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454 and STN 50-455
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM REQUIREMENTS FOR EXAMINATION OF REACTOR VESSEL HEAD PENETRATION NOZZLES EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION. UNITS 1 AND 2. AND BYRON STATION. UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457. STN 50-454. AND STN 50-455.
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated March 12, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100710764), as supplement by letter dated December 6,2010 (ADAMS Accession No. ML103410394). Exelon Generation Company. LLC (the licensee), submitted a relief request from certain requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(D) for the third 1O-year inservice inspection (lSI) interval of Braidwood Station (Braidwood), Units 1 and 2, and Byron Station (Byron). Unit Nos. 1 and 2.
The submittal requests authorization of a proposed alternative from the inspection requirement of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. ASME Code Case N-729-1. for the examination of reactor pressure vessel upper head penetrations for the control rod drive mechanism (CRDM). SpeCifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(ii). the licensee requested to use an alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty.
2.0 REGULATORY EVALUATION
The ASME Boiler and Pressure Vessel Code,Section XI, states that lSI of Class 1. 2 and 3 components shall be performed in accordance with the requirements of Section XI, "Rules for In service Inspection of Nuclear Power Plant Components." of the ASME Code and applicable editions and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission. Pursuant to 10 CFR 50.55a(g)(4), throughout the service-life of a pressurized water reactor (PWR). components which are classified as ASME Code Class 1.
2 and 3 must meet the requirements, except design and access provisions and pre-service examination requirements. set forth in the ASME Code,Section XI, to the extent practical within the limitations of design, geometry and materials of construction of the components.
Further regulations under 10 CFR 50.55a(g)(4)(i) require that lSI of components and system pressure tests conducted during the first 10-year lSI interval and subsequent intervals shall comply with the requirements in the latest edition and addenda of the ASME Code,Section XI,
-2 incorporated by reference in paragraph (b) of 10 CFR 50.55a on the date 12 months prior to the start of the 120-month 151 interval subject to the limitations and modifications listed herein. The Section XI, ASME Code of Record for the third 10-year 151 interval at Braidwood and Byron is the 2001 Edition through the 2003 Addenda. For Braidwood, the third 10-year 151 interval end dates are July 28,2018 for Unit 1 and October 16,2018 for Unit 2. For Byron, the current third 10-year 151 interval end date is July 15, 2016 for both Unit Nos. 1 and 2.
In 10 CFR 50.55a(g)(6)(ii), it states that the Commission may require the licensee to follow an augmented 151 program for systems and components for which the Commission deems that added assurance of structural reliability is necessary. 10 CFR 50.55a(g)(6)(ii)(D) requires augmented 151 of reactor pressure vessel (RPV) head penetration nozzles of PWRs in accordance with ASME Code Case N-729-1, "Alternative Examination Requirements for PWR Reactor Pressure Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial Penetration WeldsSection XI, Division 1", subject to the conditions specified in paragraphs (2) through (6) of 10 CFR 50.55a(g)(6)(ii)(D).
Pursuant to 10 CFR 50.55a(a)(3), proposed alternatives to the requirements of 10 CFR 50.55a(g) may be used when authorized by the Commission if: (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
3.0 TECHNICAL EVALUATION
3.1 Affected Systems and Components The CRDM penetrations nozzles designated as Item No. 84.20, "UNS N06600 nozzles and LlNS N06082 or UNS W86182 partial-penetration welds in head," in Table 1 of Code Case N-729-1, for Braidwood and Byron are as follows; Braidwood, Unit 1 Penetration nozzle Nos. 1,2,4,9,14-17,22,25,26,28-37,42,49, 54, 63, 65, 66, 71, 72, 77 and 78; Braidwood, Unit 2 Penetration nozzle Nos. 1, 4, 5, 8, 32, 34, 35, 40, 46, 66-68, 70, 71, 73,74 and 76-78; Byron, Unit No.1 Penetration nozzle Nos. 1-4,6-8, 15, 17,30-35,37,62,66,68,69, 74 and 75; Byron, Unit No.2 Penetration nozzle Nos. 1-9, 14-17,30-37,39,42,44,45,51-53,55,56, 58, 63, 68, 69 and 71.
-3 3.2 Proposed Alternative The licensee proposes to perform ultrasonic examination of each RPV head CRDM penetration nozzle (Le., nozzle base material) for a distance equal to "a" above the J-groove weld on the uphill slope, as defined by Figure 2 of ASME Code Case N-729-1, and to the minimum required inspection distances below the J-groove weld on the downhill slope as identified in Table 1 through 4, in this safety evaluation for Braidwood and Byron, respectfully. For all other penetrations, the required examination coverage dimension "a" reflected in Figure 2 of ASME Code Case N-729-1, will be met or exceeded.
Table 1: Braidwood 1 CRDM Nozzle Minimum Required Inspection Coverage I. Penetration No.
~~~:Ut~el~~:~; ~~~~~~: i pen~tration Minimum Inspection Coverage Below the J-Groove Weld Toe on the Downhill Side (in) o. on the Downhill Side (in) 1 1.28 33 1.48 I
2 1.36 34 1.28
! 4 1.48 35 1.28 9 1.44 36 1.20 14 1.40 37 i 1.08 15 1.28 42 0.92 16 1.28 49 0.76 17 1.36 54 0.92 22 1.40 63 0.92 25 1.48 65 0.92 26 1.48 66 0.92 28 1.40 71 0.88 29 1.16 72 0.92 30 1.24 77 0.92 31 1.48 78 ~. 0.84 32 I 1.36 I
-4 Table 2: Braidwood 2 CRDM Nozzle Minimum Required Inspection Coverage Minimum Inspection Minimum Inspection Penetration Coverage Below the J- Penetration Coverage Below the J-No. Groove Weld Toe on the No. Groove Weld Toe on the Downhill Side (in) Downhill Side (in) 1 1.40 67 0.68 4 1.44 68 0.92 L 5 1.48 70 0.64 8 1.44 71 0.56 32 1.28 73 0.84 I 34 1.32 74 0.80 I 35 1.28 76 0.92 40 0.96 77 0.96 46 0.88 78 0.68 66 0.92 Table 3: Byron 1 CRDM Nozzle Minimum Required Inspection Coverage Minimum Inspection Minimum Inspection Penetration Coverage Below the J- Penetration Coverage Below the J-No. Groove Weld Toe on the No. Groove Weld Toe on the Downhill Side (in) Downhill Side (in) 1 1.36 32 1.44 2 1.48 33 1.44 I 3 1.32 34 1.36 4 1.40 I 35 1.40 6 1.40 37 1.48 7 1.40 62 0.84 8 1.48 66 0.96 15 1.40 68 0.50 17 1.48 69 0.68 L 30 1.36 74 0.72 31 1.36 75 0.56
- 5 Table 4: Byron 2 CRDM Nozzle Minimum Required Inspection Coverage Minimum Inspection Minimum Inspection Penetration Coverage Below the J- Penetration Coverage Below the J-No. Groove Weld Toe on the No. Groove Weld Toe on the Downhill Side (in) Downhill Side (in) 1 1.16 35 1.28 2 1.40 36 1.16 3 1.28 37 1.48 4 1.28 39 0.80 5 1.20 42 0.88 6 1.16 44 0.84 7 1.12 45 0.80 8 1.16 51 0.96 9 1.20 52 0.88 14 1.16 53 0.88 15 1.16 55 0.92 16 1.44 56 0.64 17 1.24 58 0.84 30 1.12 63 0.76 31 1.20 68 0.84 32 1.08 69 0.80 33 0.92 71 0.96 34 0.88 3.3 Licensee's Basis for Request The bottom end of all of the Braidwood and Byron RPV head CRDM penetrations are externally (outside diameter or "00") threaded, internally (inside diameter or "lO") tapered, and have an ultrasonic corner shadow zone produced by the thread relief, precluding ultrasonic or eddy current data acquisition in a zone extending up approximately 1.18 inches from the bottom of each nozzle. For the majority of the penetrations, these geometric limitations reduce the inspectable distance from the bottom of the J-groove weld fillet to the top of the thread.
Therefore, the licensee requests relief for some CRDM penetrations that cannot meet the required inspection coverage dimension "a" shown in Figure 2 of ASME Code Case N-729-1.
During the previous refueling outages for each unit at Braidwood and Byron, the licensee obtained examination coverage data on all 78 CRDM penetrations in the RPV head. This information was used to support the licensee's previous NRC Order EA-03-09 relaxation requests regarding examination coverage below the J-groove weld which was approved by the NRC in letters dated February 7,2008 (ADAMS Accession No. ML080230600) for Byron, Unit No.2, and September 11, 2006 (ADAMS Accession No. ML062430598) for Byron, Unit No.1 and Braidwood, Unit 2, and September 26, 2007 (ADAMS Accession No. ML072430457) for Braidwood, Unit 1. However, these relaxation authorizations were rescinded with the issuance
-6 of 10 CFR 50.55a(g)(6)(ii)(0), on September 10, 2008 (73 FR 52724), which required implementation of ASME Code Case N-729-1, as conditioned, by December 31, 2008.
The licensee supported the proposed alternative with a stress analysis and deterministic fracture mechanics analysis. The plant-specific stress analysis demonstrated that the hoop and axial stresses remain below 20 kips per square inch (ksi) over the entire region outside the alternative examination zone defined by the licensee's proposed alternative. The stress analysis was provided for NRC staff review. The licensee also provided a plant-specific fracture mechanics analysis that demonstrated that a potential axial crack in the unexamined zone will not grow to the toe of the J-groove weld within six effective full power years (EFPYs). The licensee noted that the volumetric re-inspection frequency for each unit would be less than six EFPYs. Hence, the licensee's analysis noted, for all cases, each unit's head would be re-inspected prior to a postulated crack, in the uninspected region of the nozzle, growing to the toe of a penetration nozzle's associated J-groove weld and the reactor coolant system (RCS) pressure boundary.
By letter dated December 6, 2010, the licensee also noted that performance of dye penetrant testing may be possible in lieu of eddy current or ultrasonic testing to cover the area of missed inspection coverage. However, compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The presence of thermal sleeves in the vast majority of the CROM penetrations prohibits dye penetrant testing of the tapered 10 surface of the tube. Dye penetrant testing of threaded surfaces, like the tube 00, is difficult due to physical restraints and the need to properly clean the surface to provide accurate test results. As a result, performing dye penetrant testing on the bottom nozzle area would require thermal sleeve removal, extensive manpower, and would result in significant radiation exposure to licensee personnel. The radiation exposure is estimated to be in excess of 100 person-rem, without a compensating increase in the level of quality or safety.
3.4 NRC Staff's Evaluation The NRC staff's review of this request was based on 10 CFR 50.55a(a)(3)(ii) which states that:
Compliance with the speCified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The specifiC regulatory requirements for which relief is requested are defined in 10 CFR 50.55a(g)(6)(ii)(0)(3), which states in part:
Instead of the specified 'examination method' requirements for volumetric and surface examinations in Note 6 of Table 1 of Code Case N-729-1, the licensee shall perform volumetric and/or surface examination of essentially 100 percent of the required volume or equivalent surfaces of the nozzle tube, as identified by Figure 2 of ASME Code Case N-729-1.
-7 The extent of the examination of the nozzle tube in question is determined by the incidence angle, e, and the distance "a" below the J-groove weld, as defined in Figure 2 of ASME Code Case N-729-1, "a = 1.5 in. (38mm) for incidence angle, e, S 30 deg and for all nozzles ~ 4.5 in.
(115 mm) 00 or 1 in. (25 mm) for incidence angle, e, ~ 30 deg; or to the end of the tube, whichever is less." The licensee has identified 106 CRDM penetration nozzles, in Tables 1 through 4 above, for which this inspection coverage is not physically obtainable with ultrasonic inspection.
The licensee has shown a physical and radiological hardship which would be incurred in order to be within compliance with the specified requirements. The NRC staff finds that a physical hardship exists due to the inability of ultrasonic or eddy current inspection to effectively scan the bottom end of each CRDM penetration as each nozzle is threaded on the 00 and internally tapered. While dye penetrant inspection would be a viable option for the licensee, the inspection would require manual application in a high radiation area. Furthermore, additional setup work would require additional accumulation of dose for each nozzle. Therefore, the NRC staff finds that the radiological dose required to perform the additional inspection would be a significant radiological hardship for the limited additional inspection coverage.
The NRC staff then compared the regulatory requirements to the proposed alternative to ensure that given this hardship, compliance with the regulations did not provide a compensating increase in the level of quality and safety. The NRC staff reviewed the licensee's basis for the proposed alternative through a review of the licensee's stress and fracture mechanics analysis.
The NRC staffs review of the stress analysis was based on the degradation phenomenon of concern being primary water stress corrosion cracking (PWSCC). PWSCC typically initiates in the areas of the highest tensile stress in susceptible materials, such as alloy 600 materials, and propagates in response to time, environment (Le., temperature) and stress intensity. The NRC staff reviewed the licensee's stress analysis and conclusions by comparison of the licensee's supporting data for various nozzle angles (Figures 2 through 6 of the March 12, 2010, letter), the conservative analysis performed to support Materials Reliability Program Report, MRP-95R 1, "Generic Evaluation of Examination Coverage Requirements for Reactor Pressure Vessel Head Penetration Nozzles, Revision 1," dated September 2004 (ADAMS Accession No. ML043200602), and Pacific Northwest National Laboratory Report 17763, "Final Report Inspection Limit Confirmation for Upper Head Penetration Nozzle Cracking," dated August of 2008. The results of the NRC staffs review support the licensee's stress analysis and the NRC staff finds the areas of missed inspection coverage are in a reduced stress area, less than 20 ksi.
The licensee's fracture mechanics analysis showed that a conservative through-wall axial flaw located in the uninspected region of the nozzle would not grow to the toe of the J-groove weld, in this case the edge of the RCS pressure boundary, in less than six EFPYs. The NRC staff's assessment of the licensee's fracture mechanics analysis conclusions is based on data analysiS of the supporting Figures 7 through 12 of the crack growth predictions for various nozzle angles, as provided in the licensee's March 12, 2010, letter. In addition, the NRC staff performed an independent crack growth calculation, and the results of which support the licensee's analysis.
- 8 However, the NRC staff notes that the licensee's calculated allowed operational time period of six EFPYs as defined in Figure 12 and Section 5.1 of the March 12, 2010, letter, may not bound the current regulation's allowed time interval between inspections, which is 8 calendar years or 2.25 re-inspection years, whichever is less, in accordance with Item No. B4.20 of Table 1 of ASME Code Case N-729-1 and NRC regulation 10 CFR 50.55a(g)(6)(ii)(D)(2). The licensee, by letter dated December 6, 2010, in response to a request for additional information by the NRC, stated that none of the Braidwood or Byron units would exceed four 18-month cycles of operation between inspections. Due to the operational conditions, four 18-month cycles is less than six EFPYs. Therefore, given the licensee's technical basis, the NRC staff finds the maximum time between volumetric re-inspection in accordance with the requirements of Item No. B4.20 of Table 1 of ASME Code Case N-729-1 for Braidwood, Units 1 and 2 and Byron, Unit No.1 is 8 calendar years, 2.25 re-inspection years or 6 EFPYs, whichever is less. Due to the identification of PWSCC in one penetration nozzle at Byron, Unit No.2, the re-inspection frequency of Byron, Unit No.2 will remain in accordance with a letter dated January 28,2010, from the NRC to the licensee (ADAMS Accession No. ML100210231). Given the above, the NRC staff finds sufficient technical basis, such that the re-inspection frequencies above will provide reasonable assurance of structural integrity of each nozzle, due to the area of missed inspection coverage, as defined in Tables 1 through 4 above.
The safety issues that are addressed by 10 CFR 55a(g)(6)(ii)(D) are degradation (corrosion) of the low-alloy steel RPV upper head, RCS pressure boundary integrity, and ejection of the RPV upper head penetration nozzle due to circumferential cracking of the nozzle above the J-groove weld. The licensee's proposed alternative inspection provides reasonable assurance that these safety issues are addressed at Braidwood and Byron. The licensee has noted that while surface examination could be performed to increase the inspection coverage for the nozzle, these additional inspections would be of limited value and require extensive work in very high radiation fields. The NRC staff finds that performing these additional surface examinations would result in hardship through significant radiation exposure without a compensating increase in the level of quality or safety.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the proposed alternative provides reasonable assurance of structural integrity of the subject components. Based on the information provided in the licensee's submittals and given the maximum time between volumetric reinspection in accordance with the requirements of Item No. B4.20 of Table 1 of ASME Code Case N-729-1 for Braidwood Units 1 and 2 and Byron Unit No.1 is 8 calendar years, 2.25 reinspection years or 6 EFPYs, whichever is less, the NRC staff has determined that the licensee's proposed alternative demonstrates that compliance with the specified requirements of 10 CFR 50.55a(g)(6)(ii)(D) would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the use of the proposed alternative to define an alternate examination zone below the J-groove weld is authorized for Braidwood Units 1 and 2, and Byron Unit Nos. 1 and 2, for the third 10-year lSI interval, or until the respective head for each unit is replaced, whichever occurs first.
- 9 All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Jay Collins, NRR Date of issuance: March 3, 2011
M. Pacilio - 2 Please contact Mr. Nicholas DiFrancesco at (301) 415-1115 if you have any questions on this action.
Sincerely, IRA!
Robert D. Carlson, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454 and STN 50-455
Enclosure:
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