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Category:Code Relief or Alternative
MONTHYEARML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval LIC-15-0114, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI2015-11-24024 November 2015 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI LIC-15-0089, Submits Relief Requests Associated with the Fifth Inservice Testing Interval2015-08-27027 August 2015 Submits Relief Requests Associated with the Fifth Inservice Testing Interval ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval LIC-15-0086, Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record2015-07-0202 July 2015 Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record ML15139A0102015-05-26026 May 2015 Summary of 5/17/15 Telephone Call, Verbal Authorization of Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, 4th 10-Year Inservice Inspection Interval LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds2015-05-0909 May 2015 Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML0712300902007-04-27027 April 2007 Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants ML0634504072007-01-0505 January 2007 Request for Relief Use of Later Edition and Addenda of ASME Code for Examination of Cast Austenitic Stainless Steel Piping ML0609701242006-04-0606 April 2006 Relief E-2, 4-th 10-year Pump and Valve Inservice Testing Program ML0519600742005-10-0303 October 2005 Relief Request - Alternative Test Requirements for Containment Repairs ML0514407352005-05-24024 May 2005 5/24/05 Fort Calhoun - Relaxation Request from U.S. NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles ML0501203572005-02-28028 February 2005 Request for Relief from ASME Code Repair Requirements and Using an Alternative for the Pressurizer Nozzle Repair. LIC-04-0008, Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision2004-04-0202 April 2004 Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision ML0326000132003-09-12012 September 2003 Relief Request - Third and Fourth 10-Year Interval Inservice Inspection Program Plan - Request for Relief RR-8 LIC-03-0062, Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components2003-05-0101 May 2003 Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components LIC-02-0142, Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003)2002-12-20020 December 2002 Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003) 2016-04-15
[Table view] Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
[Table view] |
Text
444SOUTH16THSTREETMALL
10 CFR 50.55a(g)(4)(iv)
LIC-15-0114 November 24, 2015
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
Subject:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv), the Omaha Public Power District (OPPD) is requesting NRC approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components." Specifically, OPPD proposes to implement Mandatory Appendix I, I-2600, "Appendix VIII Examination," from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. Implementation of Mandatory Appendix I, I-2600 from the 2007 Edition through 2008 Addenda will permit the use of Appendix VIII Performance Demonstration Initiative (PDI) techniques to be used for components to which Appendix VIII is not applicable. The approval of the 2007 Edition through the 2008 Addenda of the ASME B&PV Code for use was announced in the Federal Register on June 21, 2011 (i.e., 76 FR 36232).
OPPD requests the review and approval of this request by September 9, 2016.
There are no regulatory commitments contained in this letter.
LIC-15-0114 Attachment
Page 1
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
LIC-15-0114 Attachment
Page 2 In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv) and the guidance provided in Reference 1, the Omaha Public Power District (OPPD) requests NRC approval to use specific provisions of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the plant identified in Section 2 of this letter. Currently, ASME Section XI, IWA-2232 (for the edition and addenda identified in Section 2) requires that ultrasonic (UT) examinations be conducted in accordance with Mandatory Appendix I. Current versions of Mandatory Appendix I, I-2000 (for the edition identified in Section 2) required the performance of ultrasonic examinations in accordance with Appendix III, Appendix VIII, or Section V, Article 4, without substitution. In lieu of the current versions (for the edition identified in Section 2) of Mandatory Appendix I, I-2000 (for the edition identified in Section 2), OPPD requests the use of Mandatory Appendix I, I-2600 ("Appendix VIII Examination") from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI. This provision states:
a) For components to which Appendix VIII is not applicable, examination procedures, personnel, and equipment qualified in accordance with Appendix VIII may be applied, provided such components, materials, sizes, and shapes are within the scope of the qualified examination procedure.
(b) Examination coverage shall be in accordance with I-3000.
(c) No other I-1000 or I-2000 requirements apply.
OPPD will implement I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. This new provision permits the use of Appendix VIII Performance Demonstration Initiative (PDI) techniques for components to which Appendix VIII is not mandatory.
The 2007 Edition through the 2008 Addenda of the ASME B&PV Code was approved for use in Federal Register 76 FR 36232, dated Tuesday, June 21, 2011.
Industry experience has demonstrated that use of Appendix VIII techniques for detection and characterization of flaws is equal to or surpasses the requirements of the ASME Code,Section XI, Appendix III or Section V, Article 4.
- 1. ASME Code Component(s) Affected:
This change may be applied to examinations where the alternative conditions of I-2600 are applicable.
- 2. Applicable Code Edition and Addenda:
PLANT INTERVAL EDITION START END Fort Calhoun Station, Unit 1 Fourth 1998 Edition, through 2000Addenda October 31, 2003 June 6, 2017
Fort Calhoun has extended the Fourth ISI Interval to June 6, 2017 as allowed by IWA-2430(d)(1) and IWA-2430(e) as noted in Reference 3.
LIC-15-0114 Attachment
Page 3 3. Proposed Subsequent Code Edition and Addenda (or Portion):
OPPD requests the use of Mandatory Appendix I, I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI for the remainder of the current interval as specified in Section 2.
- 4. Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
"Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met." 10 CFR 50.55a(b)(2) incorporated by reference Section XI, Division 1, of the ASME B&PV Code, 2007 Edition through the 2008 Addenda as approved in Reference 2. There are no limitations or modifications in 10 CFR 50.55a(b)(2) related to Mandatory Appendix I, I-2600 ("Appendix VIII Examination") for the 2007 though 2008 Addenda of Section XI.
In addition, the I-3000 Examination Coverage requirements listed in the ASME 2007 Edition with the 2008 Addenda will be utilized in conjunction with the components examined in accordance with I-2600.
- 5. Duration of Proposed Request:
This provision will be used for the remainder of the interval as specified in Section 2.
- 6.
References:
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section Xl," dated July 28, 2004
- 2. Federal Register 76 FR 36232, dated Tuesday, June 21, 2011
- 3. Letter from OPPD (Louis P. Cortopassi) to NRC (Document Control Desk) "Revised Fourth Ten-Year Interval Inservice Inspection (ISI) Interval," dated November 3, 2014 (ML14308A658) (LIC-14-0099)
444SOUTH16THSTREETMALL
10 CFR 50.55a(g)(4)(iv)
LIC-15-0114 November 24, 2015
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
Subject:
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv), the Omaha Public Power District (OPPD) is requesting NRC approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components." Specifically, OPPD proposes to implement Mandatory Appendix I, I-2600, "Appendix VIII Examination," from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. Implementation of Mandatory Appendix I, I-2600 from the 2007 Edition through 2008 Addenda will permit the use of Appendix VIII Performance Demonstration Initiative (PDI) techniques to be used for components to which Appendix VIII is not applicable. The approval of the 2007 Edition through the 2008 Addenda of the ASME B&PV Code for use was announced in the Federal Register on June 21, 2011 (i.e., 76 FR 36232).
OPPD requests the review and approval of this request by September 9, 2016.
There are no regulatory commitments contained in this letter.
LIC-15-0114 Attachment
Page 1
Request to Use a Portion of a Later Edition of the ASME B&PV Code,Section XI
LIC-15-0114 Attachment
Page 2 In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv) and the guidance provided in Reference 1, the Omaha Public Power District (OPPD) requests NRC approval to use specific provisions of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the plant identified in Section 2 of this letter. Currently, ASME Section XI, IWA-2232 (for the edition and addenda identified in Section 2) requires that ultrasonic (UT) examinations be conducted in accordance with Mandatory Appendix I. Current versions of Mandatory Appendix I, I-2000 (for the edition identified in Section 2) required the performance of ultrasonic examinations in accordance with Appendix III, Appendix VIII, or Section V, Article 4, without substitution. In lieu of the current versions (for the edition identified in Section 2) of Mandatory Appendix I, I-2000 (for the edition identified in Section 2), OPPD requests the use of Mandatory Appendix I, I-2600 ("Appendix VIII Examination") from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI. This provision states:
a) For components to which Appendix VIII is not applicable, examination procedures, personnel, and equipment qualified in accordance with Appendix VIII may be applied, provided such components, materials, sizes, and shapes are within the scope of the qualified examination procedure.
(b) Examination coverage shall be in accordance with I-3000.
(c) No other I-1000 or I-2000 requirements apply.
OPPD will implement I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code. This new provision permits the use of Appendix VIII Performance Demonstration Initiative (PDI) techniques for components to which Appendix VIII is not mandatory.
The 2007 Edition through the 2008 Addenda of the ASME B&PV Code was approved for use in Federal Register 76 FR 36232, dated Tuesday, June 21, 2011.
Industry experience has demonstrated that use of Appendix VIII techniques for detection and characterization of flaws is equal to or surpasses the requirements of the ASME Code,Section XI, Appendix III or Section V, Article 4.
- 1. ASME Code Component(s) Affected:
This change may be applied to examinations where the alternative conditions of I-2600 are applicable.
- 2. Applicable Code Edition and Addenda:
PLANT INTERVAL EDITION START END Fort Calhoun Station, Unit 1 Fourth 1998 Edition, through 2000Addenda October 31, 2003 June 6, 2017
Fort Calhoun has extended the Fourth ISI Interval to June 6, 2017 as allowed by IWA-2430(d)(1) and IWA-2430(e) as noted in Reference 3.
LIC-15-0114 Attachment
Page 3 3. Proposed Subsequent Code Edition and Addenda (or Portion):
OPPD requests the use of Mandatory Appendix I, I-2600 from the 2007 Edition through the 2008 Addenda of the ASME B&PV Code,Section XI for the remainder of the current interval as specified in Section 2.
- 4. Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
"Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met." 10 CFR 50.55a(b)(2) incorporated by reference Section XI, Division 1, of the ASME B&PV Code, 2007 Edition through the 2008 Addenda as approved in Reference 2. There are no limitations or modifications in 10 CFR 50.55a(b)(2) related to Mandatory Appendix I, I-2600 ("Appendix VIII Examination") for the 2007 though 2008 Addenda of Section XI.
In addition, the I-3000 Examination Coverage requirements listed in the ASME 2007 Edition with the 2008 Addenda will be utilized in conjunction with the components examined in accordance with I-2600.
- 5. Duration of Proposed Request:
This provision will be used for the remainder of the interval as specified in Section 2.
- 6.
References:
- 1. NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section Xl," dated July 28, 2004
- 2. Federal Register 76 FR 36232, dated Tuesday, June 21, 2011
- 3. Letter from OPPD (Louis P. Cortopassi) to NRC (Document Control Desk) "Revised Fourth Ten-Year Interval Inservice Inspection (ISI) Interval," dated November 3, 2014 (ML14308A658) (LIC-14-0099)