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MONTHYEARLIC-09-0088, Request for Use of an Alternate Depth Sizing Qualification2009-10-30030 October 2009 Request for Use of an Alternate Depth Sizing Qualification Project stage: Request ML0932402572009-11-20020 November 2009 Email to Licensee, Change to Normal Review Schedule for Request to Use of an Alternate Depth Sizing Qualification Relief Request Project stage: Other ML0932402402009-11-20020 November 2009 Acceptance Review Email, Request for Use of Alternate to Depth Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds Project stage: Acceptance Review LIC-09-0071, Request for Exemption from Physical Security Requirements2009-12-31031 December 2009 Request for Exemption from Physical Security Requirements Project stage: Request ML1001508452010-01-15015 January 2010 RAI, Regarding Use of Alternate Depth Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds Project stage: RAI LIC-10-0004, Response to Request for Additional Information Re Use of Alternate Depth Sizing Qualification2010-02-16016 February 2010 Response to Request for Additional Information Re Use of Alternate Depth Sizing Qualification Project stage: Response to RAI ML1004707252010-02-16016 February 2010 Acceptance Review Email, Request for Exemption from 10 CFR Part 73 Physical Security Requirements Project stage: Acceptance Review ML1003602182010-03-0202 March 2010 Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request Project stage: Other ML1003601772010-03-0202 March 2010 Cover Letter, Environmental Assessment and Finding of No Significant Impact, Related to 10 CFR Part 73 Exemption Request Project stage: Other ML1006304472010-03-23023 March 2010 Exemption from 10 CFR Part 73 Physical Security Requirements Project stage: Approval ML1006304512010-03-23023 March 2010 FRN: General Notice. Fort Calhoun Station, Unit 1 - Exemption from 10 CFR Part 73 Physical Security Requirements Project stage: Approval NRC-2010-0087, FRN: General Notice. Fort Calhoun Station, Unit 1 - Exemption from 10 CFR Part 73 Physical Security Requirements2010-03-23023 March 2010 FRN: General Notice. Fort Calhoun Station, Unit 1 - Exemption from 10 CFR Part 73 Physical Security Requirements Project stage: Approval 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 Project stage: Other LIC-11-0107, Closure to NRC TAC Issues2011-10-26026 October 2011 Closure to NRC TAC Issues Project stage: Other 2010-02-16
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Category:Letter type:LIC
MONTHYEARLIC-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 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 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 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 LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release LIC-18-0027, Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2018-10-0303 October 2018 Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool2018-09-28028 September 2018 License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool LIC-18-0025, Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 20192018-07-19019 July 2018 Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 2019 LIC-18-0023, Fort Calhoun Station, Unit 1 Request for Partial Site Release2018-06-29029 June 2018 Fort Calhoun Station, Unit 1 Request for Partial Site Release LIC-18-0021, Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan)2018-06-0606 June 2018 Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan) LIC-18-0017, Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy2018-04-26026 April 2018 Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy 2023-08-24
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ii;;;;ii Omaha Public Power District Fort Calhoun Station 9610 Power Lane Blair, NE 68008 February 16, 2010 LlC-10-0004 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
References:
- 1. Docket No. 50-285
- 2. Letter from OPPD (R. P. Clemens) to NRC (Document Control Desk), "Request for Use of an Alternate Depth Sizing Qualification,"
dated October 30,2009 (LlC-09-0088) (ML093030358)
- 3. Email from NRC (Lynnea Wilkins) to OPPD (M. L. Edwards),
"Request for Additional Information Regarding Relief Request for Use of an Alternate Depth Sizing Qualification" dated January 15, 2010 (ML100150845)
SUBJECT:
Response to Request for Additional Information Regarding Use of an Alternate Depth Sizing Qualification In Reference 2, pursuant to 10 CFR 50.55a(g)(5)(iii), the Omaha Public Power District (OPPD) requested approval for use of an alternate depth sizing qualification on the Fort Calhoun Station (FCS), Unit No. 1 reactor pressure vessel (RPV) nozzle-to-safe end dissimilar metal (DM) welds from the inside surface. The request was submitted for the fourth 1O-year in-service inspection interval.
In Reference 3, the NRC requested that OPPD provide additional information in order to complete its review. In addition, the NRC requested that OPPD revise the Section titled, Proposed Alternative and Basis for Use to clarify that relief is requested due to impracticality pursuant to 10 CFR 50.55a(g)(6)(i) rather than as an alternative that provides acceptable levels of quality and safety.
Accordingly, Attachment 1 provides the requested information. Attachment 2 provides the revised relief request. As requested, the Section titled "Proposed Alternative and Basis for Use" was revised to clarify that relief pursuant to 10 CFR 50.55a(g)(6)(i) is requested due to impracticality. The relief request was also revised to note that the RPV nozzles were successfully inspected during the 2009 Refueling Outage (when initially submitted, the RPV nozzle inspection was yet to be performed). No flaws were found.
Employment with Equal Opportunity 4171
U. S. Nuclear Regulatory Commission LIC-10-0004 Page 2 Please note that Section numbering was removed from the relief request to correct a numbering discrepancy. Revision bars in the right margin denote the location of revised information.
If you have any questions regarding this submittal, please contact Mr. Bill Hansher at (402) 533-6894.
rey A. Reinhart Site Vice President JAR/BL/mle Attachments:
- 1. Response to NRC Request for Additional Information
- 2. Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii) c: E. E. Collins, NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector
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UC~10-0004 Page 1 OPPD Response to NRC Request for Additional Information
LlC-10-0004 Page 2 REQUEST FOR ADDITIONAL INFORMATION Please provide the following information:
- 1. The beginning and end dates for the Fourth Inservice Inspection interval.
- 2. The component materials for each weld.
- 3. The Code item numbers for each weld.
Answers:
- 1. Beginning of Fourth Inservice Inspection Interval: 10/31/2003 End of Fourth Inservice Inspection Interval: 09/25/2013
- 2. Each of the subject nozzle to safe end dissimilar metal welds are Alloy 82/182.
- 3. The welds listed in Table 1 are all Category B-F, Item Number 5.10.
LIC-1 0-0004 Page 1 RELIEF REQUEST IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
ALTERNATIVE TO THE DEPTH SIZING QUALIFICATION REQUIREMENT OF ASME SECTION XI, SUPPLEMENT 10 FOR PIPING EXAMINATIONS PERFORMED FROM THE INSIDE SURFACE FOR FORT CALHOUN STATION, UNIT NO.1
LI C-1 0-0004 Attachment 2 Page 2 ASME Code Components Affected Code class: 1 System: RC Examination Categories: B-F, Inservice Inspection Program TABLE 1 WELD NUMBERS BY lSI DESIGNATION Nozzle-to-Safe End Weld Item Location Weld Type 1 N1A Outlet Nozzle (0°) MRC-1/01 Shop 2 N2A Inlet Nozzle (60°) MRC-1/18 Shop 3 N2B Inlet Nozzle (120°) MRC-1/30 Shop 4 N1B Outlet Nozzle (180°) MRC-2101 Shop 5 N2C Inlet Nozzle (240°) MRC-2/18 Shop 6 N2D Inlet Nozzle (300°) MRC-2/30 Shop
Applicable Code Edition and Addenda
Fort Calhoun Station (FCS) is currently in the fourth 10-year Inservice Inspection (lSI) interval ending in 2013. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) of record for the current 10-year lSI interval isSection XI, 1998 Edition, including Addenda through 2000 (Reference 1).
Applicable Code Requirement
The examination of Class 1 piping welds are required to be performed using procedures, personnel and equipment qualified to the criteria of the applicable ASME Code,Section XI, Appendix VIII, Supplements. The applicable supplement to this relief is 10, "QUALIFICATION REQUIREMENTS FOR DISSIMILAR METAL PIPING WELDS."
Paragraph 3.2, "Sizing Acceptance Criteria," Subparagraph (b) of Supplement 10, states that the "examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS [root mean square] error of the flaw depth measurements, as compared to the true flaw depths, is less than or equal to O.125-inch (3.2mm)."
LI C-1 0-0004 Attachment 2 Page 3 Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division 1," provides alternative requirements to Appendix VIII, Supplement 10. Paragraph 3.3(c) of Code Case N-695 states, "Examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS error of the flaw depth measurements, as compared to the true flaw depths, do not exceed 0.125-in. (3 mm)." Code Case N-695 is unconditionally approved for use through Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 15.
Impracticality of Compliance OPPD successfully completed volumetric examinations of the FCS reactor pressure vessel (RPV) nozzle-to-safe end dissimilar metal (DM) welds from the inside surface for a Materials Reliability Program (MRP-139) inspection during the Fall 2009 refueling outage that began November 1, 2009. No flaws were found. These examinations are scheduled to be performed again for a 1O-year reactor vessel inservice inspection at the end of the current interval. OPPD will implement the NRC approved alternative requirements of Code Case N-695 for the qualification of procedures and personnel for examinations performed during these inspections.
This relief is submitted due to the impracticality of meeting the required 0.125- inch RMS value required by Code Case N-695. Code Case N-695 requires that qualified procedures and personnel shall demonstrate a flaw depth sizing error less than or equal to 0.125-inch RMS.
The nuclear power industry has attempted to qualify personnel and procedures for depth sizing examinations performed from the inside surface of dissimilar metal welds (Supplement 10, Code Case N-695) since November 2002. To date, no personnel or procedure has achieved less than or equal to the ASME Code required 0.125-inch RMS error (Reference 2).
The inability of examination procedures to achieve the required RMS value is primarily due to a combination of factors such as surface condition, scan access, base materials and the dendritic structure in the welds themselves. The combination of these factors has proven too difficult for procedures and personnel to achieve an RMS value that meet current Code requirements or Code Case N-695.
Burden Caused by Compliance The most recent attempt at achieving 0.125-inch RMS was in early 2008. This attempt, as well as previous attempts, did not achieve the required RMS values for personnel or procedures.
The qualification attempts have been substantia/. The attempts have involved multiple vendors, ultrasonic instruments, personnel and flaw depth sizing methodologies, all of which have been incapable of achieving the 0.125-inch RMS value.
The process of qualification for this type of flaw sizing is well established. The cost and effort involved to perform a successful demonstration is quantifiable when a capable technique is available. However, when a capable technique is not available, the costs and effort required for a successful demonstration cannot be easily quantified.
LI C-1 0-0004 Page 4 Proposed Alternative And Basis for Use Fort Calhoun proposes using an alternative depth-sizing RMS error value greater than the 0.125-inch RMS error value stated in Code Case N-695 for the examination of welds listed in Table 1 of this relief request. Pursuant to 10 CFR 50.55a(g)(6)(i), relief is requested to use an alternative depth-sizing RMS error value due to the impracticality of achieving the value stated in Code Case N-695.
As an alternative to the required RMS error stated in Code Case N-695 for procedure and personnel depth sizing, Fort Calhoun will add the difference between the required RMS value of 0.125-inch and the actual RMS value achieved by our inspection vendor to the flaw depth as determined during flaw sizing. The inspection vendor chosen has achieved an RMS of 0.189" for Supplement 10 welds.
Applying the difference between the required RMS error and the achieved RMS error to the actual flaw size, will ensure a conservative flaw bounding approach and provide an acceptable level of quality and safety.
Duration of Proposed Alternative The alternative requirements of this request will be applied for the duration of the Fourth 10-year lSI interval.
Precedents Similar relief requests have been granted to the following plants:
- 1. Seabrook Station, "Seabrook Station Unit No.1 Relief Request For Use Of An Alternate Flaw Sizing Methodology for the Second Inservice Inspection Interval (TAC No. M09785)," dated May 19,2009 (ML090850504)
- 2. Exelon Generating Company, LLC, "Braidwood Station, Units 1 and 2 - Relief Request (12R-49) Regarding Inservice Inspection Program Alternative Method (TAC Nos. MD5996 and M05997)," dated November 8, 2007 (ML072760048)
- 3. Southern Nuclear Operating Company Inc., "Joseph M. Farley Nuclear Plant Unit 1, and VogUe Electric Generating Plant, Units 1 and 2 - Evaluation of Relief Request ISI-GEN-ALT-06-02," (TAC Nos. MD 2482, MD2483 and MD2484), dated September 29, 2006 (ML062770359)
References
- 1. ASME Code,Section XI, 1998 Edition, including Addenda through 2000
- 2. Letter from EPRI (C. Latiolais) to OPPD (B. Lisowyj), "Summary of WESDYNE International, LLC Supplements 2 & 10.0epth Sizing Results Obtained from the Inside Surface," dated October 27, 2009