Letter Sequence Request |
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MONTHYEARML0830903882008-10-29029 October 2008
Request for Relief 2008-TMI-01 to Utilize Code Case N-725
Project stage: Request
ML0907003132009-04-0606 April 2009
(TMI-1), Relief Request 2008-TMI-01, Regarding the Use of American Society of Mechanical Engineers Code Case N-725 During Fabrication of Replacement Steam Generators
Project stage: Other
2008-10-29
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Category:Code Relief or Alternative
MONTHYEARML20099D9552020-04-17017 April 2020
Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations
ML19269C5342019-09-27027 September 2019
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
ML19226A0232019-09-19019 September 2019
Relief from the Requirements of the Asme Code Examination and Testing for Containment Unbonded Post-Tensioning System (EPID-L-2018-LLR-0132)
ML19161A2572019-06-0404 June 2019
BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
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
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
ML16308A0272017-01-10010 January 2017
Relief from the Requirements of the ASME Code
ML15163A2492015-09-15015 September 2015
Relief Request RR-14-01 Concerning Alternative Root Mean Square Depth Sizing Requirements
TMI-14-136, Response to Request for Additional Information - Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (Rms) Depth Sizing Requirements2014-11-19019 November 2014
Response to Request for Additional Information - Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (Rms) Depth Sizing Requirements
ML13232A0512013-08-28028 August 2013
Relief Request VR-01, Proposed Alternative Testing of the Pressurizer Pilot Operated Relief Valve
ML13227A0072013-08-27027 August 2013
End-of-Interval Relief Request RR-12-01, Pressurizer Nozzle-to-Head Weld Examinations
ML13227A0242013-08-15015 August 2013
Relief Requests PR-01, PR-02, and VR-02, Associated with the Fifth Ten-Year Inservice Test Interval
TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval2012-11-0707 November 2012
Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval
ML12121A6372012-05-10010 May 2012
Request to Use Code Case N-789
ML1117304752011-07-20020 July 2011
Fourth Inservice Inspection Interval Relief Requests I4R-02, I 4R-03, I4R-04, I4R-05, and I4R-06
TMI-11-017, Submittal of Relief Request RR-11-01 and RR-11-022011-02-10010 February 2011
Submittal of Relief Request RR-11-01 and RR-11-02
ML1029303472010-10-21021 October 2010
Acceptance of Requested Licensing Action Request for Relief l4R-02, Fourth Inservice Inspection Interval, Alternate Risk Informed Selection and Examination Criteria for Pressure Retaining Welds
ML1026406132010-09-23023 September 2010
Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief l4R-02, Fourth Inservice Inspection Interval, Alternate Risk Informed Selection and Examination Criteria for
ML0830903882008-10-29029 October 2008
Request for Relief 2008-TMI-01 to Utilize Code Case N-725
ML0527906602005-10-0606 October 2005
Response to Request for Additional Information Request for Relief to Utilize Code Case N-638-1, Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique, Section XI Division 1
ML0416705102004-07-21021 July 2004
(TMI-1) Request for Relief from Flaw Removal, Heat Treatment, and Nondestructive Examination Requirements for the Third 10-Year Inservice Inspection (ISI) Interval
ML0416701962004-07-0202 July 2004
(TMI-1) Request for Relief (P5) for the Nuclear Service Closed Cooling Water (Nsccw) Pumps for Third 10-Year Inservice Testing (IST) Interval
ML0334305002003-11-25025 November 2003
Additional Information Concerning a Proposed Alternative Associated with the Use of a Weld Overlay
ML0333709532003-11-20020 November 2003
Additional Information Concerning a Proposed Alternative with the Use of Weld Overlay
ML0335602922003-11-0707 November 2003
Additional Information Concerning a Proposed Alternative Associated with the Use of a Weld Overlay
ML0335602942003-11-0303 November 2003
Proposed Alternative Associated with the Use of a Weld Overlay
ML0323205482003-09-0505 September 2003
Request for Relief from Selected Aspects of ASME Code.
2020-04-17
[Table view]
Category:Letter
MONTHYEARRS-24-097, Notice of Intent to Pursue Subsequent License Renewal for Three Mile Island Nuclear Station, Unit 12024-10-23023 October 2024
Notice of Intent to Pursue Subsequent License Renewal for Three Mile Island Nuclear Station, Unit 1
ML24256A0422024-10-0404 October 2024
Updated Post-Shutdown Decommissioning Activities Report, Rev. 6
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24242A3032024-09-0909 September 2024
Letter - Three Mile Island Station, Unit 2, Issuance of Amendment No. 68, Historic and Cultural Resources
IR 05000320/20240012024-08-28028 August 2024
TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report Nos. 05000320/2024001 and 05000320/2024002
ML24240A2222024-08-27027 August 2024
Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 6
ML24220A2742024-08-15015 August 2024
Request for Additional Information Clarification Call Regarding Three Mile Island Station, Unit 2, Amended Post-Shutdown Decommissioning Activities Report, Rev. 6
ML24135A3292024-08-0909 August 2024
Amendment No 68, Historic and Cultural Resources Cover Letter
IR 07200077/20240012024-06-18018 June 2024
Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 07200077/2024001
ML24157A3672024-06-13013 June 2024
Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter
ML24135A1972024-06-13013 June 2024
– Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0091 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24120A3242024-05-24024 May 2024
TMI-2 Email to Fws
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
ML24121A2472024-04-29029 April 2024
And Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report
ML24120A2552024-04-29029 April 2024
Annual Radiological Environmental Operating Report
ML24113A0212024-04-18018 April 2024
(TMI-2), Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24092A0012024-03-28028 March 2024
(TMI-2), Decommissioning Trust Fund Annual Report
ML24065A0042024-03-28028 March 2024
Submittal of 2023 Aircraft Movement Data Annual Report
ML24088A0122024-03-28028 March 2024
Notification of Amended Post-Shutdown Decommissioning Activities Report (PSDAR) in Accordance with 10 CFR 50.82(a)(7), Revision 6
ML24085A2152024-03-25025 March 2024
(TMI-2) - Annual Notification of Property Insurance Coverage
RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024
Report on Status of Decommissioning Funding.
ML24052A0602024-03-20020 March 2024
– Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0061 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24074A3922024-03-14014 March 2024
Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5
ML24075A0062024-03-14014 March 2024
List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project
ML24073A2312024-03-13013 March 2024
And Three Mile Island Nuclear Station, Unit 2 - Management Change
ML24044A0092024-02-12012 February 2024
License Amendment Request – Three Mile Island, Unit 2, Historic and Cultural Resources Review, Response to Request for Additional Information
IR 05000320/20230042024-02-0707 February 2024
TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023004
ML24038A0222024-02-0505 February 2024
Achp Letter on Section 106 Programmatic Agreement Participation
IR 05000289/20230062024-01-29029 January 2024
Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006
ML23342A1242024-01-0909 January 2024
Independent Spent Fuel Storage Installation Security Inspection Plan
ML23325A1092024-01-0505 January 2024
Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material
ML23354A2062023-12-20020 December 2023
(TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23354A2112023-12-20020 December 2023
Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5
IR 05000320/20230032023-11-28028 November 2023
TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003
ML23243A9082023-08-29029 August 2023
SHPO Letter to TMI-2 Regarding Section 106 Activities
IR 05000320/20230022023-08-17017 August 2023
TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002
ML23216A1782023-08-14014 August 2023
Consultation Letter to Steve Letavic for TMI-2
IR 05000289/20230052023-08-14014 August 2023
Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005
ML23216A1772023-08-14014 August 2023
Consultation Letter to Rebecca Countess for TMI-2
ML23216A1732023-08-14014 August 2023
Consultation Letter to Christine Turner for TMI-2
ML23216A1742023-08-14014 August 2023
Consultation Letter to David Morrison for TMI-2
ML23216A1752023-08-14014 August 2023
Consultation Letter to Joanna Cain for TMI-2
ML23221A1402023-08-0808 August 2023
(TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5
ML23213A2342023-08-0101 August 2023
Submittal of Defueled Safety Analysis Report and Decommissioning Quality Assurance Plan
ML23200A1882023-07-31031 July 2023
TMI-2 Correction Letter Amendment 67
ML23209A7632023-07-28028 July 2023
Letter from PA SHPO to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning
ML23192A8272023-07-10010 July 2023
TMI-2 Solutions, LLC - Response to SHPO Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project
ML23167A4642023-07-0505 July 2023
Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance
2024-09-09
[Table view] |
Text
AmerGen Energy Company, LLC www.exeloncorp.com AmerGe . An Exelon Company 20o Exelon Way Kennett Square, PA 19348 10 CFR 50.55a 5928-08-20210 October 29, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Three Mile Island, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Request for Relief 2008-TMI-01 to Utilize Code Case N-725 In accordance with the provisions of 10CFR50.55a(a)(3)(i), attached for your review is a proposed alternative to utilize the American Society of Mechanical Engineers (ASME) Code Case N-725, "Design Stress Values for UNS N06690 With a Minimum Specified Yield Strength of 35 ksi (240 MPa), Classes 2 and 3 Components,Section III, Division 1." Specifically, this alternative allows the use of Unified Number System (UNS) N06690 materials that have a minimum yield strength of 35 ksi and that otherwise conform to ASME Material Specification SB-1 67 (hot or cold worked, annealed) and SB-564 (annealed) in the TMI, Unit 1 replacement steam generator Main Feedwater (MFW) and Emergency Feedwater (EFW) riser assemblies.
The TMI, Unit 1 replacement steam generator manufacturer has chosen these materials for fabrication of the MFW and EFW riser assemblies due to their resistance to Flow Accelerated Corrosion (FAC). The TMI, Unit 1 replacement steam generator manufacturer is currently manufacturing the replacement steam generators and its associated appurtenances in accordance with ASME Section III, 2001 Edition with the 2003 Addenda. This relief request is applicable to the 2001 Edition through 2003 Addenda of ASME Section III, Division 1, Subsection NC, Class 2 Components in the TMI, Unit 1 replacement steam generators.
We request your approval by July 1, 2009, in order to support the N-stamping of the vessel prior to shipment.
There are no commitments contained in this letter.
Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Dq7
Submittal of Relief Request to Utilize Code Case N-725 October 29, 2008 Page 2 Respectfully, Pamela B. Cowan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC
Attachment:
Request for Relief RR-2008-TMI-01 to Utilize Code Case N-725 cc: S. J. Collins, USNRC, Regional Administrator, Region I D. M. Kern, USNRC, Senior Resident Inspector, TMI P. J. Bamford, USNRC, Project Manager File No. 08051
Attachment Request for Relief RR-2008-TMI-01 to Utilize Code Case N-725
Request for Relief RR-2008-TMI-01 to Utilize Code Case N-725 (Page 1 of 4) 1.0 ASME CODE COMPONENTS AFFECTED:
Code Class: 2
Reference:
ASME Code Section III, Division 1, Subsection NC, Class 2 Components
Description:
TMI, Unit 1 Replacement Steam Generators - Main Feedwater (MFW) and Emergency Feedwater (EFW)
Riser Assemblies Component Number: RC-H-1A and RC-H-1B 2.0 APPLICABLE CODE EDITION AND ADDENDA:
2001 Edition through 2003 Addenda of the ASME Code Section III, Division 1, Subsection NC, Class 2 components used for manufacture of the replacement steam generators' Main Feedwater (MFW) and Emergency Feedwater (EFW) riser assemblies (see Figures 1 and 2).
3.0 APPLICABLE CODE REQUIREMENT:
The MFW and EFW riser assemblies and integrally attached material on the headers meet the requirements for Class 2 piping of the ASME Code Section III, 2001 Edition through 2003 Addenda, Division 1, Subsection NC.
4.0 REASON FOR REQUEST:
Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested to implement Code Case N-725, "Design Stress Values for UNS N06690 With a Minimum Specified Yield Strength of 35 ksi (240 MPa), Classes 2 and 3 Components,Section III, Division 1,," as it relates to the TMI, Unit 1 replacement steam generator MFW and EFW riser assemblies. The allowable stress values for the chosen materials (UNS N06690, SB-167, and SB-564) were not provided in the ASME Code Section III, 2001 Edition through 2003 Addenda, Division 1, Subsection NC, for Class 2 components. Therefore, application of Code Case N-725 is necessary. These chosen materials are highly resistant to Flow Accelerated Corrosion (FAC) damage and are highly corrosion resistant.
5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE Specifically, this alternative allows the use of ASME Code Case N-725 in the TMI, Unit 1 replacement steam generator MFW and EFW riser assemblies. The use of SB-1 67 material in Class 1 applications has already been approved by the NRC in Regulatory Guide 1.84 by unconditional approval of Code Case N-698. Code Case N-725 provides stress values for Class 2 and 3 components that are similar to Code Case N-698.
Request for Relief RR-2008-TMI-01 to Utilize Code Case N-725 (Page 2 of 4) 6.0 DURATION OF PROPOSED ALTERNATIVE This proposed alternative is applicable to the TMI, Unit 1 replacement steam generator MFW and EFW riser assemblies and is applicable for the lifetime of the component.
7.0 PRECEDENTS None
Request for Relief RR-2008-TMI-01 to Utilize Code Case N-725 (Page 3 of 4)
RISER:PIPE SB-I 67 ALLOY 690 FIGURE 1 Main Feedwater Header
Request for Relief RR-2008-TMI-01 to Utilize Code.Case N-725 (Page 4 of 4)
FIGURE 2 Emergency Feedwater Header
