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| ---UPP U ----Omaha Public Power District 444 South 1 ftn Stre et M a ll Omaha, NE 68102-2247 LIC-15-0054 April 13, 2015 U.S. Nuclear Reg u latory Comm i ssion Attn: Document Control Desk Washington , DC 20555-0001 Fort Calho u n Station , Unit No. 1 Renew e d Facility Operating L i cense No. DPR-40 NRC Docket No. 50-285 Subjec t: OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internal s (TAC No. MF3412) References | | ---- |
| : 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "Submittal of Reactor Vessel Internal (RVI) Compon e nt Aging Management Program (AMP) for Fort Calhoun Stat i on (FCS), Unit No.1 ," dated September 27 , 2012 (LIC-12-0144) (ML12276A005) 2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortop ass i), " F ort Calhoun Station , Unit No.1 -Request for Additional Inform a tio n R E: Aging Management Program for Reactor Ve s sel Intern a l s (TAC N o. MF3412)," dated March 3 , 2015 (NRC-15-010) (M L 15057A015) | | .-..------- --- |
| This l e tt er is s u bmitted in response to an NRC reque s t for add i t i ona l i nfo r m a t i on (Refere n c e 2) r e garding Omaha Public Power District's (OPPD) propo se d aging manag e ment p r ogram for the Fort Calhoun Station , Unit No. 1 , reactor v esse l int e rnal s (R e ference 1 ). OPPD's re s pons e to the NRC RAI is a ttach e d. Thi s lett e r cont a ins no regulatory commitm e nt s. E mploym e nt w i th E qu a l Opportunity U. S. Nuclear Regulatory Commission LI C-15-0054 Page2 If you should have any questions regarding this submittal or require addit i onal information, please contact Mr. Bill R. Hansher, Principal Regulatory Engineer, at 402-533-6894. | | -- - - |
| Respectfully, LoLJssl Site Vice President and CNO LPC/KGM/mle | | UPPU Omaha Public Power District 444 South 1ftn Street Mall Omaha, NE 68102-2247 LIC-15-0054 April 13, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington , DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 |
| | |
| | ==Subject:== |
| | OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internals (TAC No. MF3412) |
| | |
| | ==References:== |
| | : 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk) , "Submittal of Reactor Vessel Internal (RVI) Component Aging Management Program (AMP) for Fort Calhoun Station (FCS), Unit No.1," dated September 27, 2012 (LIC-12-0144) (ML12276A005) |
| | : 2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi) , "Fort Calhoun Station, Unit No.1 - Request for Additional Information RE: |
| | Aging Management Program for Reactor Vessel Internals (TAC No. |
| | MF3412)," dated March 3, 2015 (NRC-15-010) (ML15057A015) |
| | This letter is submitted in response to an NRC request for additional information (Reference 2) regarding Omaha Public Power District's (OPPD) proposed aging management program for the Fort Calhoun Station, Unit No. 1, reactor vessel internals (Reference 1). |
| | OPPD's response to the NRC RAI is attached. |
| | This letter contains no regulatory commitments. |
| | Employment with Equal Opportunity |
| | |
| | U. S. Nuclear Regulatory Commission LI C-15-0054 Page2 If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher, Principal Regulatory Engineer, at 402-533-6894. |
| | Respectfully, ~ |
| | LoLJssl Site Vice President and CNO LPC/KGM/mle |
|
| |
|
| ==Attachment:== | | ==Attachment:== |
| | OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internals (TAC No. MF3412) c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector |
| | |
| | LIC-15-0054 Attachment Page 1 REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT N0.1 DOCKET NO. 50-285 In a letter dated September 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12276A005), Omaha Public Power District (OPPD, the licensee) submitted an aging management program (AMP) for the reactor vessel internals (RVls) at Fort Calhoun Station, Unit No. 1 (FCS). The Electric Power Research lnstitute's Materials Reliability Program report MRP-227-A, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," December 2008 (ADAMS Accession No. |
| | ML090160205), and its supporting reports were used as technical bases for developing FCS's AMP. The U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation (SE) for MRP-227-A was issued on December 16, 2011 (ADAMS Accession No. ML11308A770), with seven topical report conditions and eight applicant/licensee action items Section 6 2 of the licensee's September 27, 2012, submittal addressed the staff's eight action items. The following request for additional information (RAI) is related to the staff's Action Item 3 addressed in the staff's SE for the MRP-227-A. |
| | RAl-2-1: |
| | Section 6.2.3 of the licensee's September 27, 2012 submittal, included the following plant-specific reports which are related to the NRC staff's Action Item 3. The staff requested that the licensee provide a brief summary of the AMP related to the following RVI components. The summary should include: (a) the aging degradation; (b) the licensee's inspection methods of identifying aging effects; (c) the inspection results; and, (d) the frequency of subsequent inspections of these components during the extended period of operation. |
| | * Plant-specific thermal shield integrity program - WCAP-17471-P, "OPPD Thermal Shield Integrity Program Task 2 Report," November 2011 |
| | * Plant-specific in-core instrumentation (ICI) thimble tube program - DAR-ME-05-15, Revision 00, "Recommendation for Replacement ICI Thimble Measurement," |
| | September 30, 2005 OPPD Response: |
| | Thermal Shield The Thermal Shield is monitored for the aging mechanisms of cumulative fatigue damage, cracking, reduction of fracture toughness, changes in dimension, fatigue, and loss of preload . |
| | Monitoring of neutron noise data is performed every 12 weeks (except during a refueling outage). A follow-up visual inspection (VT-3) to a 1992 repair will be performed in refueling outage (RFO) 28 scheduled for the fall of 2016 to confirm there is no further loss of preload. |
| | Neutron noise data has been monitored since the plant restarted in 2013 and no issues have been identified. The frequency of future visual inspections will be determined after RFO 28. |
|
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|
| OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internals (TAC No. MF3412) c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector LIC-15-0054 Attachment Page 1 REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT N0.1 DOCKET NO. 50-285 In a letter dated September 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12276A005), Omaha Public Power District (OPPD, the licensee) submitted an aging management program (AMP) for the reactor vessel internals (RVls) at Fort Calhoun Station, Unit No. 1 (FCS). The Electric Power Research lnstitute's Materials Reliability Program report MRP-227-A, " Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," December 2008 (ADAMS Accession No. ML090160205), and its supporting reports were used as technical bases for developing FCS's AMP. The U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation (SE) for MRP-227-A was issued on December 16, 2011 (ADAMS Accession No. ML11308A770), with seven topical report conditions and eight applicant/licensee action items Section 6 2 of the licensee's September 27, 2012, submittal addressed the staff's eight action items. The following request for additional information (RAI) is related to the staff's Action Item 3 addressed in the staff's SE for the MRP-227-A.
| | LIC-15-0054 Attachment Page2 In-Core Instrumentation (ICI) Thimble Tubes The ICI thimble tubes are monitored for changes in dimensions, cracking, loss of material. and reduction in fracture toughness. The ICI tubes will be visually inspected (VT-3) in RFO 28, which will be the first time this inspection occurs as it is part of the inspections required by MRP-227-A. The maximum radial peaking factor is also monitored after every RFO to ensure it is within the limits described in the Core Operating Limits Report (COLA). The VT-3 inspection will determine which ICls need to be replaced. ICls are replaced within a 9 year interval (22 are scheduled for replacement in RFO 27 beginning in April 2015, and 6 are scheduled for replacement in RFO 28).}} |
| RAl-2-1: Section 6.2.3 of the licensee's September 27, 2012 submittal, included the following plant-specific reports which are related to the NRC staff's Action Item 3. The staff requested that the licensee provide a brief summary of the AMP related to the following RVI components.
| |
| The summary should include: (a) the aging degradation; (b) the licensee's inspection methods of identifying aging effects; (c) the inspection results; and, (d) the frequency of subsequent inspections of these components during the extended period of operation.
| |
| * Plant-specific thermal shield integrity program -WCAP-17471-P, "OPPD Thermal Shield Integrity Program Task 2 Report," November 2011
| |
| * Plant-specific in-core instrumentation (ICI) thimble tube program -DAR-ME-05-15, Revision 00, "Recommendation for Replacement ICI Thimble Measurement," September 30, 2005 OPPD Response:
| |
| Thermal Shield The Thermal Shield is monitored for the aging mechanisms of cumulative fatigue damage, cracking, reduction of fracture toughness, changes in dimension, fatigue, and loss of preload. Monitoring of neutron noise data is performed every 12 weeks (except during a refueling outage). A follow-up visual inspection (VT-3) to a 1992 repair will be performed in refueling outage (RFO) 28 scheduled for the fall of 2016 to confirm there is no further loss of preload. Neutron noise data has been monitored since the plant restarted in 2013 and no issues have been identified.
| |
| The frequency of future visual inspections will be determined after RFO 28.
| |
| LIC-15-0054 Attachment Page2 In-Core Instrumentat i on (ICI) Thimble Tubes The ICI thimble tubes are monitored for changes in dimensions, cracking, loss of material. | |
| and reduction in fracture toughness. | |
| The ICI tubes will be visually inspected (VT-3) in RFO 28 , which will be the first time this inspection occurs as it is part of the inspections required by MRP-227-A. The maximum radial peaking factor is also monitored after every RFO to ensure it is within the limits described in the Core Operating Limits Report (COLA). The VT-3 inspection will determine which ICls need to be replaced. ICls are replaced within a 9 year interval (22 are scheduled for replacement in RFO 27 beginning in April 2015, and 6 are scheduled for replacement in RFO 28).}} | |
Letter Sequence Response to RAI |
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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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UPPU Omaha Public Power District 444 South 1ftn Street Mall Omaha, NE 68102-2247 LIC-15-0054 April 13, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington , DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
Subject:
OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internals (TAC No. MF3412)
References:
- 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk) , "Submittal of Reactor Vessel Internal (RVI) Component Aging Management Program (AMP) for Fort Calhoun Station (FCS), Unit No.1," dated September 27, 2012 (LIC-12-0144) (ML12276A005)
- 2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi) , "Fort Calhoun Station, Unit No.1 - Request for Additional Information RE:
Aging Management Program for Reactor Vessel Internals (TAC No.
MF3412)," dated March 3, 2015 (NRC-15-010) (ML15057A015)
This letter is submitted in response to an NRC request for additional information (Reference 2) regarding Omaha Public Power District's (OPPD) proposed aging management program for the Fort Calhoun Station, Unit No. 1, reactor vessel internals (Reference 1).
OPPD's response to the NRC RAI is attached.
This letter contains no regulatory commitments.
Employment with Equal Opportunity
U. S. Nuclear Regulatory Commission LI C-15-0054 Page2 If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher, Principal Regulatory Engineer, at 402-533-6894.
Respectfully, ~
LoLJssl Site Vice President and CNO LPC/KGM/mle
Attachment:
OPPD Response to NRC Request for Additional Information Regarding Aging Management Program For Reactor Vessel Internals (TAC No. MF3412) c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector
LIC-15-0054 Attachment Page 1 REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT N0.1 DOCKET NO. 50-285 In a letter dated September 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12276A005), Omaha Public Power District (OPPD, the licensee) submitted an aging management program (AMP) for the reactor vessel internals (RVls) at Fort Calhoun Station, Unit No. 1 (FCS). The Electric Power Research lnstitute's Materials Reliability Program report MRP-227-A, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," December 2008 (ADAMS Accession No.
ML090160205), and its supporting reports were used as technical bases for developing FCS's AMP. The U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation (SE) for MRP-227-A was issued on December 16, 2011 (ADAMS Accession No. ML11308A770), with seven topical report conditions and eight applicant/licensee action items Section 6 2 of the licensee's September 27, 2012, submittal addressed the staff's eight action items. The following request for additional information (RAI) is related to the staff's Action Item 3 addressed in the staff's SE for the MRP-227-A.
RAl-2-1:
Section 6.2.3 of the licensee's September 27, 2012 submittal, included the following plant-specific reports which are related to the NRC staff's Action Item 3. The staff requested that the licensee provide a brief summary of the AMP related to the following RVI components. The summary should include: (a) the aging degradation; (b) the licensee's inspection methods of identifying aging effects; (c) the inspection results; and, (d) the frequency of subsequent inspections of these components during the extended period of operation.
- Plant-specific thermal shield integrity program - WCAP-17471-P, "OPPD Thermal Shield Integrity Program Task 2 Report," November 2011
- Plant-specific in-core instrumentation (ICI) thimble tube program - DAR-ME-05-15, Revision 00, "Recommendation for Replacement ICI Thimble Measurement,"
September 30, 2005 OPPD Response:
Thermal Shield The Thermal Shield is monitored for the aging mechanisms of cumulative fatigue damage, cracking, reduction of fracture toughness, changes in dimension, fatigue, and loss of preload .
Monitoring of neutron noise data is performed every 12 weeks (except during a refueling outage). A follow-up visual inspection (VT-3) to a 1992 repair will be performed in refueling outage (RFO) 28 scheduled for the fall of 2016 to confirm there is no further loss of preload.
Neutron noise data has been monitored since the plant restarted in 2013 and no issues have been identified. The frequency of future visual inspections will be determined after RFO 28.
LIC-15-0054 Attachment Page2 In-Core Instrumentation (ICI) Thimble Tubes The ICI thimble tubes are monitored for changes in dimensions, cracking, loss of material. and reduction in fracture toughness. The ICI tubes will be visually inspected (VT-3) in RFO 28, which will be the first time this inspection occurs as it is part of the inspections required by MRP-227-A. The maximum radial peaking factor is also monitored after every RFO to ensure it is within the limits described in the Core Operating Limits Report (COLA). The VT-3 inspection will determine which ICls need to be replaced. ICls are replaced within a 9 year interval (22 are scheduled for replacement in RFO 27 beginning in April 2015, and 6 are scheduled for replacement in RFO 28).