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| | number = ML16007A385 | | | number = ML16007A385 |
| | issue date = 01/15/2016 | | | issue date = 01/15/2016 |
| | title = Fort Calhoun Station, Unit No. 1 - Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements (CAC No. MF6676) | | | title = Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements |
| | 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 = CAC MF6676 | | | case reference number = CAC MF6676 |
| | document type = Acceptance Review Letter | | | document type = Acceptance Review Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 15, 2016 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC 4 Blair, NE 68008 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 15, 2016 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 Blair, NE 68008 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISE CURRENT LICENSING BASIS TO USE AMERICAN CONCRETE INSTITUTE ULTIMATE STRENGTH REQUIREMENTS (CAC NO. MF6676) | | FORT CALHOUN STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISE CURRENT LICENSING BASIS TO USE AMERICAN CONCRETE INSTITUTE ULTIMATE STRENGTH REQUIREMENTS (CAC NO. MF6676) |
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| ==Dear Mr. Cortopassi:== | | ==Dear Mr. Cortopassi:== |
| By letter dated August 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15243A167), as supplemented by letter dated December 23, 2015 (ADAMS Accession No. ML 15363A042), the Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit No. 1 (FCS). The proposed amendment would revise the FCS Updated Safety Analysis Report (USAR) to change the structural design methodology to use American Concrete Institute ultimate strength requirements for Class I structures at FCS with several exceptions. The exceptions are the containment shell, the spent fuel pool, and the foundation mat under the containment and auxiliary buildings, as well as the foundation mat under the intake structure. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50. 90 of Title 10 of the Code of Federal Regulations ( 10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application, as supplemented, and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an L. Cortopassi adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. 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 cc: Distribution via Listserv Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation L. Cortopassi staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. 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 cc: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 Reading RidsACRS_MailCTR Resource RidsNrrDeEmcb Resource RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMFortCalhoun Resource RidsRgn4MailCenter Resource Yli, NRR/DE/EMCB FFarzam, NRR/DE/EMCB RPettis, NRR/DE/EMCB Sincerely, IRA/ Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ADAMS Accession No. ML16007A385 *face-to-face with Flyon OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EMCB/BC(A) NAME FL yon JBurkhardt Yli* DATE 1/12/16 1/12/16 1/12/16 OFFICE NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME RPascarelli FL yon DATE 1/14/16 1/15/16 OFFICIAL RECORD COPY | | |
| }} | | By letter dated August 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15243A167), as supplemented by letter dated December 23, 2015 (ADAMS Accession No. ML15363A042), the Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit No. 1 (FCS). The proposed amendment would revise the FCS Updated Safety Analysis Report (USAR) to change the structural design methodology to use American Concrete Institute ultimate strength requirements for Class I structures at FCS with several exceptions. The exceptions are the containment shell, the spent fuel pool, and the foundation mat under the containment and auxiliary buildings, as well as the foundation mat under the intake structure. |
| | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| | Consistent with Section 50. 90 of Title 10 of the Code of Federal Regulations ( 10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. |
| | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
| | The NRC staff has reviewed your application, as supplemented, and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an |
| | |
| | L. Cortopassi adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. |
| | 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 cc: Distribution via Listserv |
| | |
| | ML16007A385 *face-to-face with Flyon OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EMCB/BC(A) |
| | NAME FLyon JBurkhardt Yli* |
| | DATE 1/12/16 1/12/16 1/12/16 OFFICE NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME RPascarelli FL yon DATE 1/14/16 1/15/16}} |
Letter Sequence Acceptance Review |
|---|
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MONTHYEARLIC-15-0077, License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements2015-08-31031 August 2015
License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
Project stage: Request
ML15344A3492015-12-0404 December 2015
NRR E-mail Capture - Non-Acceptance with Opportunity to Supplement
Project stage: Acceptance Review
ML15341A2242015-12-15015 December 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: Acceptance Review
LIC-15-0142, Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements2015-12-23023 December 2015
Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
Project stage: Supplement
ML16007A3852016-01-15015 January 2016
Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: Acceptance Review
ML16104A2872016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: RAI
ML16165A0282016-06-0909 June 2016
Response to NRC Request for Additional Information Revise Current Licensing Basis to Use American Concrete Institute Ultimate Strength Requirements
Project stage: Response to RAI
LIC-16-0051, Withdrawal of License Amendment Requests (LAR) 15-03, Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements2016-07-27027 July 2016
Withdrawal of License Amendment Requests (LAR) 15-03, Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements
Project stage: Withdrawal
ML16209A3692016-08-0202 August 2016
Letter, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: Withdrawal
ML16209A3702016-08-0202 August 2016
FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: Withdrawal
NRC-2016-0040, FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements2016-08-0202 August 2016
FRN, Withdrawal of Requested Licensing Action, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
Project stage: Withdrawal
2016-01-15
[Table View] |
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Category:Acceptance Review Letter
MONTHYEARML22038A6752022-02-10010 February 2022
Acceptance of Omaha Public Power District'S License Amendment Request to Add a License Condition to Include License Termination Plan Requirements
ML21350A0262021-12-16016 December 2021
Acceptance Review of License Amend Req. to Add License Condition to Include License Termination Plan Requirements, Req. for Supplemental Info
ML17041A2382017-02-15015 February 2017
Acceptance Review Letter, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E to Allow Plant to Reduce Emergency Planning Requirements Consistent with Permanently Defueled Condition
ML16007A3852016-01-15015 January 2016
Acceptance of Requested Licensing Action Following Supplement, Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML15341A2242015-12-15015 December 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML14178B3942014-06-27027 June 2014
NRC Acceptance Review of Fort Calhoun License Amendment Request 14-03
ML13267A1772013-09-24024 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
ML13255A0072013-09-11011 September 2013
Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13249A3182013-09-0606 September 2013
Acceptance Review Email, License Amendment Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML12325A5782012-11-19019 November 2012
Acceptance Review Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup from Current Extended Outage
ML1215800432012-06-0505 June 2012
Acceptance Review Email, Amendment Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML1210706522012-04-16016 April 2012
Acceptance Review Email, Relocate Technical Specification Limiting Condition for Operation 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report
ML1208303282012-03-23023 March 2012
Email License Amendment Request to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
ML1203802312012-02-0707 February 2012
Acceptance Review Email, License Amendment Request to Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6)
ML1136300832011-12-29029 December 2011
Acceptance Review Email, License Amendment Request to Adopt National Fire Protection Standard NFPA -805 Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generation Plants,
ML1124501302011-09-0202 September 2011
Unit No.1 - Acceptance Review Email, Exemption Request from the Requirements of Appendix E, Sections IV.F.2.b and C of Section 50, Title 10 of the Code of Federal Regulations
ML1109605292011-04-0606 April 2011
Acceptance Review Email, License Amendment Request, Establish Ultimate Heat Sink LCOs in Technical Specification (TS) 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests.
ML1034001892010-12-14014 December 2010
Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
ML1026500132010-09-21021 September 2010
Acceptance Review E-mail, Relief Request RR-12, from Requirements of ASME Code Case N-722 Visual Examination of Reactor Vessel Hot-Leg Nozzle to Safe End Dissimilar Metal Welds for 4th 10-Year Inservice Inspection Interval (ME4541)
ML1023006762010-08-18018 August 2010
Acceptance Review Email, License Amendment Request to Revise License Condition and Approve Cyber Security Plan
ML1022406482010-08-12012 August 2010
Acceptance Review E-mail, LAR Regarding Revision to (1) TS LCO 2.15, Table 2-5, Item 1, (2) TS 3.1, Table 3-3, Items 1, 2, and 4 Control Element Assembly Position Indication and (3) TS LCO 2.10.2(7)c
ML1004707252010-02-16016 February 2010
Acceptance Review Email, Request for Exemption from 10 CFR Part 73 Physical Security Requirements
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
ML0918308972009-07-0202 July 2009
Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source, Deletion of Diesel Generator SR 3.7(1)e
ML0905802252009-02-27027 February 2009
Acceptance Review Email, License Amendment Request to Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
ML0905407952009-02-23023 February 2009
Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Add Operability and Testing Requirements for Steam .Generator Blowdown Isolation on a Reactor Trip
ML0833301062008-11-26026 November 2008
Acceptance Review Email, License Amendment Request to Revise TS 3.6(3), Containment Recirculating Air Cooling and Filtering System and License Conditions Replacement of Cacf System
2022-02-10
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 15, 2016 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 Blair, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISE CURRENT LICENSING BASIS TO USE AMERICAN CONCRETE INSTITUTE ULTIMATE STRENGTH REQUIREMENTS (CAC NO. MF6676)
Dear Mr. Cortopassi:
By letter dated August 31, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15243A167), as supplemented by letter dated December 23, 2015 (ADAMS Accession No. ML15363A042), the Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit No. 1 (FCS). The proposed amendment would revise the FCS Updated Safety Analysis Report (USAR) to change the structural design methodology to use American Concrete Institute ultimate strength requirements for Class I structures at FCS with several exceptions. The exceptions are the containment shell, the spent fuel pool, and the foundation mat under the containment and auxiliary buildings, as well as the foundation mat under the intake structure.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50. 90 of Title 10 of the Code of Federal Regulations ( 10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application, as supplemented, and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an
L. Cortopassi adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
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 cc: Distribution via Listserv
ML16007A385 *face-to-face with Flyon OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DE/EMCB/BC(A)
NAME FLyon JBurkhardt Yli*
DATE 1/12/16 1/12/16 1/12/16 OFFICE NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME RPascarelli FL yon DATE 1/14/16 1/15/16
