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| | number = ML14353A051 | | | number = ML14353A051 |
| | issue date = 12/22/2014 | | | issue date = 12/22/2014 |
| | title = Fort Calhoun, Unit 1, Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm [Alternate Seismic Criteria and Methodologies] Developed Floor Respon | | | title = Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra |
| | author name = Lyon C F | | | author name = Lyon C |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Cortopassi L P | | | addressee name = Cortopassi L |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
| | license number = DPR-040 | | | license number = DPR-040 |
| | contact person = Lyon C F | | | contact person = Lyon C |
| | case reference number = TAC MF4016 | | | case reference number = TAC MF4016 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 22, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 22, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO USE DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES (TAC NO. MF4016) | | FORT CALHOUN STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO USE ASCM-DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES (TAC NO. MF4016) |
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| ==Dear Mr. Cortopassi:== | | ==Dear Mr. Cortopassi:== |
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| By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14118A435), Omaha Public Power District submitted a license amendment request to permit the use at Fort Calhoun Station, Unit No. 1 of alternate seismic criteria and methodologies (ASCM)-developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures. | | By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14118A435), Omaha Public Power District submitted a license amendment request to permit the use at Fort Calhoun Station, Unit No. 1 of alternate seismic criteria and methodologies (ASCM)-developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures. |
| The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on December 18, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov. | | The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on December 18, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov. |
| Docket No. 50-285 | | Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO USE ASCM-DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285 By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14118A435), Omaha Public Power District (OPPD, the licensee) submitted a license amendment request (LAR) to permit the use at Fort Calhoun Station, Unit No. 1 (FCS) of alternate seismic criteria and methodologies (ASCM) developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures. | | Request for Additional Information cc w/encl: Distribution via Listserv |
| The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the LAR and determined that the additional information below is required in order to complete its formal review. 1. Section 2.0 of the LAR states, in part, that Reference 3.6 as identified in USAR [updated safety analysis report], Appendix F is engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," Revision 0, which has since been updated and is now Revision 1 . a) Please describe the content of engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," and clarify its association with the information provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993. b) Please discuss whether the updates to EA-FC-94-003 affect any technical information that was provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993. 2. Regarding the proposed revision to the USAR, Section 5.11.3 and Appendix F, Section 2.1.4, included in Attachment 1 to the LAR: Enclosure b. Figures F-1 and F-2 shown in Appendix F of the FCS USAR are design basis ground response spectra for FCS. The two proposed alternatives, to determine
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| * seismic loading, one using ground response spectra and the other using ASCM floor response spectra are not consistent.
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| In addition, the existing wording of the USAR, Section 5.11.3 refers to Appendix F where FCS seismic criteria are outlined.
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| The proposed revision to Section 5.11.3 of the FCS USAR appears to be redundant.
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| Please provide a discussion relative to the proposed revision of the FCS USAR, Section 5.11.3 and reconcile the apparent inconsistency between the two proposed alternatives.
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| : c. The proposed revision to Appendix F, Section 2.1.4 of the FCS USAR states that: An alternative method of determining the seismic loads for a Class 1 structure and structural elements attached to structures is available using the ASCM floor response spectra provided in Reference 3.6. The maximum "g" value from the curve for the building floor at which the structure is anchored is to be used. The second sentence "The maximum 'g' value from the curve for the building floor at which the structure is anchored is to be used." is not consistent with the seismic analysis methods for piping and heating, ventilation, and air conditioning systems described in the NRC's staff safety evaluation dated April 16, 1993. Please provide further discussion and reconcile this apparent inconsistency.
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| : 3. The OPPD July 31, 1992, letter to the NRC included FCS, Unit 1 in-structure response spectra (ISRS) for the Auxiliary building, Containment building, and containment internal structures.
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| Specifically, the ASCM ISRS in the vertical direction depicts a pronounced second peak at the frequency range of approximately 12 Hertz to 18 Hertz. The design basis vertical floor response spectra for the Reactor and Auxiliary buildings are shown in Figures F-22 through F-27 of Appendix F of the FCS USAR. There are several indications in Appendix F of the FCS USAR that for equipment, piping, and electrical raceways, the spacing of restraints and support system was controlled to maintain the lowest vertical and horizontal natural frequencies of the component equal to or greater than 18 Hertz and 6 Hertz, respectively.
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| Thus, limiting the acceleration used for the analysis to approximately zero period acceleration of the floor response spectra. OPPD has indicated that the ASCM ISRS represent an updated and a more refined version of the FCS original design basis spectra. Please provide information to reconcile the effects of the ASCM ISRS on the existing Class I systems and components, located in Class I structures.
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| December 22, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008
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| ==SUBJECT:==
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO USE ASCM-DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285 By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14118A435), Omaha Public Power District (OPPD, the licensee) submitted a license amendment request (LAR) to permit the use at Fort Calhoun Station, Unit No. 1 (FCS) of alternate seismic criteria and methodologies (ASCM) developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures. |
| FORT CALHOUN STATION, UNIT NO.1-REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO USE DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES (TAC NO. MF4016)
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the LAR and determined that the additional information below is required in order to complete its formal review. |
| | | : 1. Section 2.0 of the LAR states, in part, that Reference 3.6 as identified in USAR [updated safety analysis report], |
| ==Dear Mr. Cortopassi:==
| | Appendix F is engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," Revision 0, which has since been updated and is now Revision 1. |
| | | a) Please describe the content of engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," and clarify its association with the information provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993. |
| By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14118A435), Omaha Public Power District submitted a license amendment request to permit the use at Fort Calhoun Station, Unit No. 1 of alternate seismic criteria and methodologies (ASCM)-developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures. | | b) Please discuss whether the updates to EA-FC-94-003 affect any technical information that was provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993. |
| The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on December 18, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov. | | : 2. Regarding the proposed revision to the USAR, Section 5.11.3 and Appendix F, Section 2.1.4, included in Attachment 1 to the LAR: |
| Docket No. 50-285
| | Enclosure |
| | | : b. Figures F-1 and F-2 shown in Appendix F of the FCS USAR are design basis ground response spectra for FCS. The two proposed alternatives, to determine |
| ==Enclosure:==
| | * seismic loading, one using ground response spectra and the other using ASCM floor response spectra are not consistent. In addition, the existing wording of the USAR, Section 5.11.3 refers to Appendix F where FCS seismic criteria are outlined. The proposed revision to Section 5.11.3 of the FCS USAR appears to be redundant. |
| | Please provide a discussion relative to the proposed revision of the FCS USAR, Section 5.11.3 and reconcile the apparent inconsistency between the two proposed alternatives. |
| | : c. The proposed revision to Appendix F, Section 2.1.4 of the FCS USAR states that: |
| | An alternative method of determining the seismic loads for a Class 1 structure and structural elements attached to structures is available using the ASCM floor response spectra provided in Reference 3.6. The maximum "g" value from the curve for the building floor at which the structure is anchored is to be used. |
| | The second sentence "The maximum 'g' value from the curve for the building floor at which the structure is anchored is to be used." is not consistent with the seismic analysis methods for piping and heating, ventilation, and air conditioning systems described in the NRC's staff safety evaluation dated April 16, 1993. |
| | Please provide further discussion and reconcile this apparent inconsistency. |
| | : 3. The OPPD July 31, 1992, letter to the NRC included FCS, Unit 1 in-structure response spectra (ISRS) for the Auxiliary building, Containment building, and containment internal structures. Specifically, the ASCM ISRS in the vertical direction depicts a pronounced second peak at the frequency range of approximately 12 Hertz to 18 Hertz. |
| | The design basis vertical floor response spectra for the Reactor and Auxiliary buildings are shown in Figures F-22 through F-27 of Appendix F of the FCS USAR. There are several indications in Appendix F of the FCS USAR that for equipment, piping, and electrical raceways, the spacing of restraints and support system was controlled to maintain the lowest vertical and horizontal natural frequencies of the component equal to or greater than 18 Hertz and 6 Hertz, respectively. Thus, limiting the acceleration used for the analysis to approximately zero period acceleration of the floor response spectra. |
| | OPPD has indicated that the ASCM ISRS represent an updated and a more refined version of the FCS original design basis spectra. Please provide information to reconcile the effects of the ASCM ISRS on the existing Class I systems and components, located in Class I structures. |
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| Sincerely, IRA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
| | *.. ML14353A051 *memo dated OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1/LA NRR/DE/EMCB/BC(A)* NRR/DORL/LPL4-1/BC(A) NRR/DORLILPL4-1/PM NAME FLyon JBurkhardt YLi EOesterle FLyon DATE 12/22/14 12/19/14 12/16/14 12/22/14 12/22/14}} |
| PUBLIC LPL4-1 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEmcb Resource RidsNrrDoriLpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMFortCalhoun Resource RidsRgn4MaiiCenter Resource FFarzam, NRR/DE/EMCB ADAMS Accession No* ML 14353A051
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| .. *memo dated OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1/LA NRR/DE/EMCB/BC(A)* | |
| NRR/DORL/LPL4-1/BC(A) | |
| NRR/DORLILPL4-1/PM NAME FLyon JBurkhardt YLi EOesterle FLyon DATE 12/22/14 12/19/14 12/16/14 12/22/14 12/22/14 OFFICIAL RECORD COPY}} | |
Letter Sequence RAI |
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MONTHYEARLIC-14-0036, License Amendment Request (LAR) 14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra2014-04-25025 April 2014
License Amendment Request (LAR) 14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra
Project stage: Request
ML15050A1892014-12-18018 December 2014
NRR E-mail Capture - Draft RAI
Project stage: Draft Other
ML14353A0512014-12-22022 December 2014
Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra
Project stage: RAI
LIC-15-0020, Response to NRC Request for Additional Information License Amendment Request to Use ASCM-Developed Floor Response Spectra in the Design and Evaluation of Seismic Class I Structures2015-02-13013 February 2015
Response to NRC Request for Additional Information License Amendment Request to Use ASCM-Developed Floor Response Spectra in the Design and Evaluation of Seismic Class I Structures
Project stage: Response to RAI
ML15062A5312015-03-0303 March 2015
NRR E-mail Capture - Response to NRC RAI on Ascm
Project stage: Response to RAI
LIC-15-0046, Withdrawal of License Amendment Request - License Amendment Request (LAR)14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra.2015-04-0101 April 2015
Withdrawal of License Amendment Request - License Amendment Request (LAR)14-05; Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra.
Project stage: Withdrawal
ML15092A1842015-04-0606 April 2015
FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra
Project stage: Withdrawal
ML15092A1822015-04-0606 April 2015
Letter, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra
Project stage: Withdrawal
NRC-2014-0159, FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra2015-04-0606 April 2015
FRN, Withdrawal of License Amendment Request to Revise Updated Safety Analysis Report, to Permit Use of Design and Evaluation of Seismic Class I Structures Using Ascm Developed Floor Response Spectra
Project stage: Withdrawal
2015-02-13
[Table View] |
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Category:Letter
MONTHYEARML24019A1672024-01-31031 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
IR 05000285/20230012023-02-24024 February 2023
NRC Inspection Report 05000285/2023001
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
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
ML22138A1262022-08-0303 August 2022
Letter to Roger Trudell, Chairman, Santee Sioux Nation, Nebraska, 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
ML22138A1242022-08-0303 August 2022
Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, 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
ML22138A1212022-08-0303 August 2022
Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, 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
ML22138A1232022-08-0303 August 2022
Letter to Mr. Leander Merrick, Chairperson, Omaha Tribe of 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
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
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
ML22159A2152022-06-28028 June 2022
Letter Forwarding FRN on Public Meeting and Request for Comment on License Termination Plan
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
IR 05000285/20220032022-06-15015 June 2022
NRC Inspection Report 05000285/2022003
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
IR 05000285/20220022022-04-28028 April 2022
NRC Inspection Report 050-00285/2022-002
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
2024-01-31
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23151A0042023-06-0606 June 2023
Second Set RAIs Rev 4
ML22357A0672022-12-30030 December 2022
Enclosure RAI Re Approval of License Termination Plan
ML22119A2472022-05-0303 May 2022
Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review
ML20111A2162020-05-20020 May 2020
Revised PSDAR Request for Additional Information - RAI
ML19241A1812019-08-21021 August 2019
Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status
ML18067A1432018-03-0808 March 2018
Enclosurequest for Additional Information (Letter to M. J. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI)
ML17236A3442017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)
ML17236A3462017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567)
ML17234A4692017-08-22022 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831)
ML17194A9732017-07-13013 July 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
ML17112A0362017-04-20020 April 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR
ML17090A3942017-03-31031 March 2017
NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437)
ML17082A0022017-03-22022 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption
ML17081A0192017-03-21021 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption
ML17067A3862017-03-15015 March 2017
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17033A9692017-02-0202 February 2017
NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment
ML16263A0492016-09-20020 September 2016
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2023-06-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 22, 2014 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Omaha, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO USE ASCM-DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES (TAC NO. MF4016)
Dear Mr. Cortopassi:
By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14118A435), Omaha Public Power District submitted a license amendment request to permit the use at Fort Calhoun Station, Unit No. 1 of alternate seismic criteria and methodologies (ASCM)-developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that additional information is required in order to complete its formal review. The enclosed questions were provided to B. Hansher of your staff on December 18, 2014. Please provide a response to the enclosed questions within 30 days of the date of this letter. If you have any questions, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO USE ASCM-DEVELOPED FLOOR RESPONSE SPECTRA IN THE DESIGN AND EVALUATION OF SEISMIC CLASS I STRUCTURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285 By letter dated April 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14118A435), Omaha Public Power District (OPPD, the licensee) submitted a license amendment request (LAR) to permit the use at Fort Calhoun Station, Unit No. 1 (FCS) of alternate seismic criteria and methodologies (ASCM) developed seismic floor response spectra in the design and evaluation of seismic Class I structures and structural elements attached to structures.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the LAR and determined that the additional information below is required in order to complete its formal review.
- 1. Section 2.0 of the LAR states, in part, that Reference 3.6 as identified in USAR [updated safety analysis report],
Appendix F is engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," Revision 0, which has since been updated and is now Revision 1.
a) Please describe the content of engineering analysis EA-FC-94-003, "Alternate Seismic Criteria and Methodologies," and clarify its association with the information provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993.
b) Please discuss whether the updates to EA-FC-94-003 affect any technical information that was provided to the NRC staff at the time of review of FCS ASCM and preparation of the NRC's safety evaluation dated April 16, 1993.
- 2. Regarding the proposed revision to the USAR, Section 5.11.3 and Appendix F, Section 2.1.4, included in Attachment 1 to the LAR:
Enclosure
- b. Figures F-1 and F-2 shown in Appendix F of the FCS USAR are design basis ground response spectra for FCS. The two proposed alternatives, to determine
- seismic loading, one using ground response spectra and the other using ASCM floor response spectra are not consistent. In addition, the existing wording of the USAR, Section 5.11.3 refers to Appendix F where FCS seismic criteria are outlined. The proposed revision to Section 5.11.3 of the FCS USAR appears to be redundant.
Please provide a discussion relative to the proposed revision of the FCS USAR, Section 5.11.3 and reconcile the apparent inconsistency between the two proposed alternatives.
- c. The proposed revision to Appendix F, Section 2.1.4 of the FCS USAR states that:
An alternative method of determining the seismic loads for a Class 1 structure and structural elements attached to structures is available using the ASCM floor response spectra provided in Reference 3.6. The maximum "g" value from the curve for the building floor at which the structure is anchored is to be used.
The second sentence "The maximum 'g' value from the curve for the building floor at which the structure is anchored is to be used." is not consistent with the seismic analysis methods for piping and heating, ventilation, and air conditioning systems described in the NRC's staff safety evaluation dated April 16, 1993.
Please provide further discussion and reconcile this apparent inconsistency.
- 3. The OPPD July 31, 1992, letter to the NRC included FCS, Unit 1 in-structure response spectra (ISRS) for the Auxiliary building, Containment building, and containment internal structures. Specifically, the ASCM ISRS in the vertical direction depicts a pronounced second peak at the frequency range of approximately 12 Hertz to 18 Hertz.
The design basis vertical floor response spectra for the Reactor and Auxiliary buildings are shown in Figures F-22 through F-27 of Appendix F of the FCS USAR. There are several indications in Appendix F of the FCS USAR that for equipment, piping, and electrical raceways, the spacing of restraints and support system was controlled to maintain the lowest vertical and horizontal natural frequencies of the component equal to or greater than 18 Hertz and 6 Hertz, respectively. Thus, limiting the acceleration used for the analysis to approximately zero period acceleration of the floor response spectra.
OPPD has indicated that the ASCM ISRS represent an updated and a more refined version of the FCS original design basis spectra. Please provide information to reconcile the effects of the ASCM ISRS on the existing Class I systems and components, located in Class I structures.
- .. ML14353A051 *memo dated OFFICE NRRIDORULPL4-1/PM NRR/DORLILPL4-1/LA NRR/DE/EMCB/BC(A)* NRR/DORL/LPL4-1/BC(A) NRR/DORLILPL4-1/PM NAME FLyon JBurkhardt YLi EOesterle FLyon DATE 12/22/14 12/19/14 12/16/14 12/22/14 12/22/14
