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| #REDIRECT [[LIC-06-0077, Corrections to Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs]] | | {{Adams |
| | | number = ML062330084 |
| | | issue date = 08/18/2006 |
| | | title = Corrections to Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs |
| | | author name = Faulhaber H J |
| | | author affiliation = Omaha Public Power District |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000285 |
| | | license number = DPR-040 |
| | | contact person = |
| | | case reference number = LIC-06-0077, NRC-05-0120, TAC MC4653 |
| | | document type = Letter |
| | | page count = 2 |
| | | project = TAC:MC4653 |
| | | stage = Other |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 August 18,2006 LIC-06-0077 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 |
| | |
| | ==References:== |
| | : 1. Docket No. 50-285 |
| | : 2. Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated October 11, 2004, "Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs" (LIC-04-0093) |
| | : 3. Letter from NRC (D. S. Collins) to OPPD (R. |
| | T. Ridenoure) dated October 3, 2005, "Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs" (TAC No. |
| | MC4653) (NRC-05-0120) |
| | |
| | ==SUBJECT:== |
| | Corrections to Fort Calhoun Station Unit No. |
| | 1 Relief Request: Alternative Test Requirements for Containment Repairs (TAC No. |
| | MC4653) In Reference 2, the Omaha Public Power District (OPPD) requested approval for alternative testing to demonstrate the leak-tight integrity of a required repair resulting from cutting an access opening through the post tensioned containment concrete and metallic liner. The access opening is necessary for the replacement of the steam generators, pressurizer and reactor vessel head during the Fall 2006 outage. |
| | In Reference 3, the Nuclear Regulatory Commission (NRC) approved the relief request. The purpose of this letter is to correct two administrative errors in Reference |
| | : 2. First, Reference 2 incorrectly stated that the applicable code edition and addenda is American Society of Mechanical Engineers (ASME) Section XI 1998 edition with 2000 Addenda. The correct reference is ASME Section XI 1992 edition with the 1992 Addenda, which is the applicable code of record. Second, due to a typographical error, Reference 2 cited IWL-5500, which does not exist. The correct reference is IWL-5000. The above code edition is consistent with the Federal Register (FR) dated August 8, 1996 (61 FR 41303), where the NRC amended its regulations to incorporate by reference the 1992 edition with 1992 addenda of Subsections IWE and IWL of Section XI of the ASME Boiler and Pressure Vessel Code. Subsections IWE and IWL provide the Employment with Equal Opportunity U.S. Nuclear Regulatory Commission LIC-06-0077 Page 2 requirements for inservice inspection (ISI) of Class CC (Concrete Containment) and Class MC (metallic containment) of light-water cooled power plants. |
| | In conclusion, this submittal documents the applicable code requirements, as discussed in the Safety Evaluation Report (Reference 3) approving the relief request. No commitments are made to the NRC in this letter. If you have any questions or require additional information, please contact Mr. Thomas C. Matthews at (402) 533-6938. |
| | Sincerely, Division Manager Nuclear Engineering Division}} |
|
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Category:Letter
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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 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request 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 - 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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 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1262022-08-0303 August 2022 Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1282022-08-0303 August 2022 Letter to Victoria Kitcheyan, Chairwoman, Winnebago Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1292022-08-0303 August 2022 Letter to Tiauna Carnes, Chairperson, Sac and Fox Nation of Missouri in Kansas, 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 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1272022-08-0303 August 2022 Letter to Vern Jefferson, Chairman, Sac and Fox Tribe of the Mississippi in Iowa, Re., Ft Calhoun LTP Section 106 ML22138A1232022-08-0303 August 2022 Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, 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 2024-07-08
[Table view] |
Text
Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 August 18,2006 LIC-06-0077 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
References:
- 1. Docket No. 50-285
- 2. Letter from OPPD (R. T. Ridenoure) to NRC (Document Control Desk) dated October 11, 2004, "Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs" (LIC-04-0093)
- 3. Letter from NRC (D. S. Collins) to OPPD (R.
T. Ridenoure) dated October 3, 2005, "Fort Calhoun Station Unit No. 1 Relief Request: Alternative Test Requirements for Containment Repairs" (TAC No.
MC4653) (NRC-05-0120)
SUBJECT:
Corrections to Fort Calhoun Station Unit No.
1 Relief Request: Alternative Test Requirements for Containment Repairs (TAC No.
MC4653) In Reference 2, the Omaha Public Power District (OPPD) requested approval for alternative testing to demonstrate the leak-tight integrity of a required repair resulting from cutting an access opening through the post tensioned containment concrete and metallic liner. The access opening is necessary for the replacement of the steam generators, pressurizer and reactor vessel head during the Fall 2006 outage.
In Reference 3, the Nuclear Regulatory Commission (NRC) approved the relief request. The purpose of this letter is to correct two administrative errors in Reference
- 2. First, Reference 2 incorrectly stated that the applicable code edition and addenda is American Society of Mechanical Engineers (ASME)Section XI 1998 edition with 2000 Addenda. The correct reference is ASME Section XI 1992 edition with the 1992 Addenda, which is the applicable code of record. Second, due to a typographical error, Reference 2 cited IWL-5500, which does not exist. The correct reference is IWL-5000. The above code edition is consistent with the Federal Register (FR) dated August 8, 1996 (61 FR 41303), where the NRC amended its regulations to incorporate by reference the 1992 edition with 1992 addenda of Subsections IWE and IWL of Section XI of the ASME Boiler and Pressure Vessel Code. Subsections IWE and IWL provide the Employment with Equal Opportunity U.S. Nuclear Regulatory Commission LIC-06-0077 Page 2 requirements for inservice inspection (ISI) of Class CC (Concrete Containment) and Class MC (metallic containment) of light-water cooled power plants.
In conclusion, this submittal documents the applicable code requirements, as discussed in the Safety Evaluation Report (Reference 3) approving the relief request. No commitments are made to the NRC in this letter. If you have any questions or require additional information, please contact Mr. Thomas C. Matthews at (402) 533-6938.
Sincerely, Division Manager Nuclear Engineering Division