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| | number = ML17194A973 | | | number = ML17194A973 |
| | issue date = 07/13/2017 | | | issue date = 07/13/2017 |
| | title = 2017/07/13 NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) | | | title = NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) |
| | author name = Kim J | | | author name = Kim J |
| | author affiliation = NRC/NRR/DORL/LSPB | | | author affiliation = NRC/NRR/DORL/LSPB |
| | addressee name = Matzke E P | | | addressee name = Matzke E |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
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| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
| | page count = 3 | | | page count = 3 |
| | | project = |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Kim, JamesSent:Thursday, July 13, 2017 12:32 PMTo:MATZKE, ERICK PCc:BLOME, BRADLEY H | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Kim, James Sent: Thursday, July 13, 2017 12:32 PM To: MATZKE, ERICK P Cc: BLOME, BRADLEY H |
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| ==Subject:== | | ==Subject:== |
| Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)Final Request for Additional Information On June 28, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent Fort Calhoun Station (FCS) the draft Request for Additional Information (RAI). This RAI relates to the amendment to revise Updated Safety Analysis Report (USAR) to change the structural design methodology for the Auxiliary Building at FCS. | | Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) |
| On July 13, 2017, a teleconference between FCS and NRC staff was held to discuss the information requested by the NRC staff was understood and any additional clarifications on the RAI were required. Based on the teleconference, FCS determined that the information requested by the NRC staff was clearly understood and any other additional clarifications on the RAI was not necessary. FCS agreed to provide a response to this final RAI shown below by September 29, 2017. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRC's Agencywide Documents Access and Management System. | | Final Request for Additional Information On June 28, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent Fort Calhoun Station (FCS) the draft Request for Additional Information (RAI). This RAI relates to the amendment to revise Updated Safety Analysis Report (USAR) to change the structural design methodology for the Auxiliary Building at FCS. |
| | | On July 13, 2017, a teleconference between FCS and NRC staff was held to discuss the information requested by the NRC staff was understood and any additional clarifications on the RAI were required. Based on the teleconference, FCS determined that the information requested by the NRC staff was clearly understood and any other additional clarifications on the RAI was not necessary. FCS agreed to provide a response to this final RAI shown below by September 29, 2017. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System. |
| REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING LICENSE AMENDMENT REQUEST 16-04 REVISING CURRENT LICENSING BASIS TO USE ACI ULTIMATE STRENGTH REQUIREMENTS FORT CALHOUN STATION, UNIT 1 DOCKET NO.: 50-285 | | REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | REGARDING LICENSE AMENDMENT REQUEST 16-04 REVISING CURRENT LICENSING BASIS TO USE ACI ULTIMATE STRENGTH REQUIREMENTS FORT CALHOUN STATION, UNIT 1 DOCKET NO.: 50-285 |
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| ==Reference:== | | ==Reference:== |
| : 1. Letter from Shane M. Marik, Omaha Public Power District, to NRC Document Control Desk, "License Amendment Request (LAR) 16-04; Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements" dated October 25, 2016 (ML16299A275) Structural Engineering Branch (ESEB) - RAI 1 | | : 1. Letter from Shane M. Marik, Omaha Public Power District, to NRC Document Control Desk, License Amendment Request (LAR) 16-04; Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements dated October 25, 2016 (ML16299A275) |
| | Structural Engineering Branch (ESEB) - RAI 1 |
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| ==Background:== | | ==Background:== |
| Table 1 in Section 2.1.1 of the LAR (Reference 1) notes that ACI 318-63 is the current licensing basis (CLB) design code of record for Fort Calhoun Station (FCS). The CLB requires the use of working stress design (WSD) method for normal service conditions, and ultimate strength design (USD) method for no loss-of-function and special load cases. The LAR proposes to revise the CLB to use the USD method from ACI 318-63 for normal service load conditions for future design and evaluation of the Auxiliary Building. Section 4.2 of the LAR notes that several operating nuclear power plants constructed in the era that FCS was built use the ACI 318-63 USD method for normal operating/service load combinations.
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| Class 1 concrete structures, including earlier-vintage plants that have adapted ACI 318-63 or ACI 318-71 as the licensing basis code-of-record, have typically been licensed to load combinations (normal operating/service condition and extreme (no loss of function and special cases) condition) with load factors associated with design loads in the combination based on the NRC staff position documented in NUREG-0800 Standard Review Plan (SRP) 3.8.4 and Regulatory Guide (RG) 1.142 (which currently endorses ACI 349-97 with 2conditions). The factor assigned to each load in a load combination is influenced by the degree of accuracy to which the load effect can be calculated, the variation expected in the load during the life of the structure, the probability of simultaneous occurrence, and assumptions and approximations in the structural analysis calculations. Issue: The second and third load combinations (associated with footnote (2) in LAR Table 5) use the existing USAR USD equations for the no loss-of-function condition (extreme condition) and modify the equation by replacing the differential pressure component with the live load, and the differential temperature component with the soil load. The LAR notes that the resulting equation is "similar" to ACI 318-71 equation 9-2 (the load factors are not the same as equation 9-2). It is unclear to the staff why it is appropriate to modify in this fashion the loads in existing USD equations for extreme load conditions to develop load factors for the proposed USD service load combinations. It is also unclear why it is appropriate to selectively choose numerically inconsistent load factors from later editions of ACI 318 without reconciling the other related code provisions, and/or existing NRC staff positions in the SRP and RG 1.142.
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| The LAR notes that other operating nuclear plants use the ACI 318-63 USD method for normal operating/service load conditions; however, the LAR does not cite specific precedent where the NRC has previously approved the load factors for USD service load combinations proposed in Table 5 of the LAR. The NRC staff is not aware of past precedent that used the proposed load factors. Request: Provide technical justification for the proposed load factors associated with USD service load combinations in the second and third equations (associated with footnote 2) in LAR Table 5 (i.e., justify acceptability of substituting service loads into an equation associated with unusual or extreme load conditions).
| | Table 1 in Section 2.1.1 of the LAR (Reference 1) notes that ACI 318-63 is the current licensing basis (CLB) design code of record for Fort Calhoun Station (FCS). The CLB requires the use of working stress design (WSD) method for normal service conditions, and ultimate strength design (USD) method for no loss-of-function and special load cases. The LAR proposes to revise the CLB to use the USD method from ACI 318-63 for normal service load conditions for future design and evaluation of the Auxiliary Building. Section 4.2 of the LAR notes that several operating nuclear power plants constructed in the era that FCS was built use the ACI 318-63 USD method for normal operating/service load combinations. |
| | Class 1 concrete structures, including earlier-vintage plants that have adapted ACI 318-63 or ACI 318-71 as the licensing basis code-of-record, have typically been licensed to load combinations (normal operating/service condition and extreme (no loss of function and special cases) condition) with load factors associated with design loads in the combination based on the NRC staff position documented in NUREG-0800 Standard Review Plan (SRP) 3.8.4 and Regulatory Guide (RG) 1.142 (which currently endorses ACI 349-97 with 1 |
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| | conditions). The factor assigned to each load in a load combination is influenced by the degree of accuracy to which the load effect can be calculated, the variation expected in the load during the life of the structure, the probability of simultaneous occurrence, and assumptions and approximations in the structural analysis calculations. |
| | Issue: |
| | The second and third load combinations (associated with footnote (2) in LAR Table 5) use the existing USAR USD equations for the no loss-of-function condition (extreme condition) and modify the equation by replacing the differential pressure component with the live load, and the differential temperature component with the soil load. The LAR notes that the resulting equation is similar to ACI 318-71 equation 9-2 (the load factors are not the same as equation 9-2). It is unclear to the staff why it is appropriate to modify in this fashion the loads in existing USD equations for extreme load conditions to develop load factors for the proposed USD service load combinations. It is also unclear why it is appropriate to selectively choose numerically inconsistent load factors from later editions of ACI 318 without reconciling the other related code provisions, and/or existing NRC staff positions in the SRP and RG 1.142. |
| | The LAR notes that other operating nuclear plants use the ACI 318-63 USD method for normal operating/service load conditions; however, the LAR does not cite specific precedent where the NRC has previously approved the load factors for USD service load combinations proposed in Table 5 of the LAR. The NRC staff is not aware of past precedent that used the proposed load factors. |
| | Request: |
| | Provide technical justification for the proposed load factors associated with USD service load combinations in the second and third equations (associated with footnote 2) in LAR Table 5 (i.e., justify acceptability of substituting service loads into an equation associated with unusual or extreme load conditions). |
| If the response discusses ACI 318-71 equation 9-2 clearly explain why it is appropriate to selectively use load factors from three different codes in the proposed USAR (ACI 318-63, ACI 318-71, and ACI 349-97) without reconciliation with other related code provisions or an existing staff position. | | If the response discusses ACI 318-71 equation 9-2 clearly explain why it is appropriate to selectively use load factors from three different codes in the proposed USAR (ACI 318-63, ACI 318-71, and ACI 349-97) without reconciliation with other related code provisions or an existing staff position. |
| If the response basis relies on precedent based on operating nuclear power plants that used ACI 318-63 USD service load combinations, provide details identifying previous case history and explain how the proposed load factors for the second and third USD service load combinations in FCS's LAR is consistent with that of the precedent plant. | | If the response basis relies on precedent based on operating nuclear power plants that used ACI 318-63 USD service load combinations, provide details identifying previous case history and explain how the proposed load factors for the second and third USD service load combinations in FCSs LAR is consistent with that of the precedent plant. |
| Regards, | | : Regards, Jim Kim Project Manager - Fort Calhoun Station NRR/DORL/LSPB 301-415-4125 2 |
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| Jim Kim Project Manager - Fort Calhoun Station NRR/DORL/LSPB 301-415-4125 Hearing Identifier: NRR_PMDA Email Number: 3603 Mail Envelope Properties (James.Kim@nrc.gov20170713123100)
| | Hearing Identifier: NRR_PMDA Email Number: 3603 Mail Envelope Properties (James.Kim@nrc.gov20170713123100) |
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| ==Subject:== | | ==Subject:== |
| Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) Sent Date: 7/13/2017 12:31:48 PM Received Date: 7/13/2017 12:31:00 PM From: Kim, James Created By: James.Kim@nrc.gov Recipients: "BLOME, BRADLEY H" <bblome@oppd.com> | | Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) |
| Tracking Status: None "MATZKE, ERICK P" <ematzke@oppd.com> | | Sent Date: 7/13/2017 12:31:48 PM Received Date: 7/13/2017 12:31:00 PM From: Kim, James Created By: James.Kim@nrc.gov Recipients: |
| Tracking Status: None Post Office: Files Size Date & Time MESSAGE 5530 7/13/2017 12:31:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | | "BLOME, BRADLEY H" <bblome@oppd.com> |
| | Tracking Status: None "MATZKE, ERICK P" <ematzke@oppd.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 5530 7/13/2017 12:31:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
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Category:E-Mail
MONTHYEARML24025A1792024-01-23023 January 2024 State Consultation Response e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment (License No. DPR-40, Docket No. 50-285) ML24024A2242024-01-22022 January 2024 State Consultation e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment- (License No. DPR-40, Docket No. 50-285) ML23311A0862023-11-0505 November 2023 Letter to M Morales Re Ft Calhoun License Termination Section 7 Determination for Ipac 2022-0029456 ML23038A1882023-01-31031 January 2023 Request for Additional Time to Respond to Request for Additional Information on License Amendment Request for Approval of License Termination Plan (License No. DPR-40, Docket No. 50-285) ML22222A1192022-08-0808 August 2022 Email Section 106 NHPA- Ft Calhoun Station License Termination Plan ML21069A2482021-03-10010 March 2021 Umax, 07200054, 05000361, 05000362, FSAR Revision 4 for San Onofre ISFSI ML21335A3352021-01-25025 January 2021 January 25, 2021 e-mail from J. Parrott, NRC to C. Cameron, OPPD Use of Resrad Model to Represent Well Water Concentrations in a Basement Substructure (License No. DPR-40, Docket No. 50-285) ML20204B0782020-07-22022 July 2020 Donna Gilmore Email Holtec Umax Materials (07200054, 05000361, 05000362) ML20113F0622020-04-22022 April 2020 E-mail Results of Acceptance Review of OPPD Request for Exemption from 10 CFR 20, App G, Section Iii.E (License No. DPR-40, Docket No. 50-285) ML20100J2272020-03-26026 March 2020 E-mail Notification to the State of Nebraska on the Issuance of the License Amendment for Revised Security Plans to Reflect an ISFSI-only Configuration (License No. DPR-40, Docket Nos. 50-285 and 72-54) ML20100L7232020-03-15015 March 2020 Email: Town of Desoto National Register of Historic Places Eligibility ML19353C3612019-12-11011 December 2019 E-mail to State of Nebraska Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status (License DPR-40, Docket Nos. 50-285 and 72-054) ML19309F1112019-10-11011 October 2019 ISFSI-Only Tech Specs 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 ML19175A0212019-06-19019 June 2019 Acceptance Review - License Amendment Request to Revise Security and Safeguards Requirements to Reflect ISFSI-Only Configuration ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML19126A2802019-05-0101 May 2019 Acceptance Review - License Amendment Request for ISFSI-Only EP and EAL Scheme ML18100A2712018-04-0909 April 2018 04-09-18 OPPD E-Mail (FCS Permanently Defueled Emergency Plan Implementation) ML17236A3462017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567) 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) 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) ML17191B0212017-07-10010 July 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Modification of LC 3.C to Delete Commission-approved CSP ML17184A0042017-06-30030 June 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits ML17142A0202017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 to TQ-DC-FC-101 ML17144A0132017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun PSDAR - Findings and Concerns ML17139C5082017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 for LIC-17-0043 ML17139C8342017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Partial Exemption from Record Retention Requirements ML17139B6782017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 50.54(w)(1), On-Site Property Damage Insurance ML17139B6762017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 140.11(a)(4), Off-Site Liability Insurance ML17136A1692017-05-16016 May 2017 NRR E-mail Capture - (External_Sender) OPPD FCS Decommissioning Financial Reports ML17115A4722017-04-25025 April 2017 NRR E-mail Capture - (External_Sender) Corrected Page 18 to TQ-DC-FC-201 ML17114A3112017-04-24024 April 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review TS Changes to Align for Decommissioning 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 ML17052A0272017-02-15015 February 2017 NRR E-mail Capture - Fort Calhoun Station, Unit No. 1 - Acceptance of Requested Amendment Revise Permanently Defueled Emergency Plan and EAL Scheme ML17033A9692017-02-0202 February 2017 NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment ML16350A0392016-12-15015 December 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8858) Fort Calhoun, Unit 1 - License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program ML16351A0432016-12-15015 December 2016 NRR E-mail Capture - (External_Sender) Fort Calhoun Station Offsite Response Organizations ML16334A3002016-11-29029 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8525) Fort Calhoun, Unit 1 - License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements ML16333A0992016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8452), Fort Calhoun, Unit 1 - Request for Exemption from Specific Provisions in 10 CFR 73.55 ML16333A2312016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8843)Fort Calhoun, Unit 1, Request for Rescission of Interim Compensatory Measure B.1.a from EA-02-026, Order for Interim Safeguards and Security Compensatory Measures. ML16286A0812016-10-12012 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station, Unit 1, License Amendment Request 16-03, Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning ML16278A0292016-10-0303 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station Radiological Emergency Response Plan (RERP) for Decommissioning ML16257A0262016-09-12012 September 2016 NRR E-mail Capture - (External_Sender) OPPD Slides for 9/13/16 Pre-Application Meeting on Class 1 Structures ML16207A0182016-07-22022 July 2016 NRR E-mail Capture - Acceptance Review ML16137A0092016-05-16016 May 2016 NRR E-mail Capture - Acceptance Review CAC No. MF7574 ML16131A7312016-05-10010 May 2016 NRR E-mail Capture - (External_Sender) Question Rvi Inspection Results 2024-01-23
[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 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 ML16174A1502016-06-27027 June 2016 Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML16146A1782016-05-27027 May 2016 Request for Additional Information, Round 2, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16106A0232016-04-29029 April 2016 Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 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 ML16048A1542016-02-23023 February 2016 Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011 ML16048A0242016-02-23023 February 2016 Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML15343A1082015-12-15015 December 2015 Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15323A0362015-11-24024 November 2015 Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval ML15194A2722015-07-14014 July 2015 Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15057A0152015-03-0303 March 2015 Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review ML15043A0612015-02-25025 February 2015 Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III 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 ML14259A3652014-09-24024 September 2014 Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML14195A0862014-07-16016 July 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML13317A5832013-11-25025 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13282A5362013-10-0909 October 2013 Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) ML13290A0022013-10-0909 October 2013 Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks ML13270A2872013-09-27027 September 2013 Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML13261A2122013-09-18018 September 2013 Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7) ML13233A2482013-08-26026 August 2013 Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7) ML13235A1682013-08-23023 August 2013 Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13234A4352013-08-22022 August 2013 Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source ML13226A1222013-08-14014 August 2013 Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML13212A0092013-07-30030 July 2013 Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source ML13205A1252013-07-24024 July 2013 Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13205A0182013-07-23023 July 2013 Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13144A4822013-05-23023 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13100A1752013-04-10010 April 2013 Request for Additional Information 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 ML13086A4732013-03-27027 March 2013 Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13120A0842013-03-22022 March 2013 Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660) ML13053A2262013-02-22022 February 2013 Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. ML13016A4322013-01-16016 January 2013 E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) 2023-06-06
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NRR-PMDAPEm Resource From: Kim, James Sent: Thursday, July 13, 2017 12:32 PM To: MATZKE, ERICK P Cc: BLOME, BRADLEY H
Subject:
Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
Final Request for Additional Information On June 28, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent Fort Calhoun Station (FCS) the draft Request for Additional Information (RAI). This RAI relates to the amendment to revise Updated Safety Analysis Report (USAR) to change the structural design methodology for the Auxiliary Building at FCS.
On July 13, 2017, a teleconference between FCS and NRC staff was held to discuss the information requested by the NRC staff was understood and any additional clarifications on the RAI were required. Based on the teleconference, FCS determined that the information requested by the NRC staff was clearly understood and any other additional clarifications on the RAI was not necessary. FCS agreed to provide a response to this final RAI shown below by September 29, 2017. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System.
REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING LICENSE AMENDMENT REQUEST 16-04 REVISING CURRENT LICENSING BASIS TO USE ACI ULTIMATE STRENGTH REQUIREMENTS FORT CALHOUN STATION, UNIT 1 DOCKET NO.: 50-285
Reference:
- 1. Letter from Shane M. Marik, Omaha Public Power District, to NRC Document Control Desk, License Amendment Request (LAR) 16-04; Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements dated October 25, 2016 (ML16299A275)
Structural Engineering Branch (ESEB) - RAI 1
Background:
Table 1 in Section 2.1.1 of the LAR (Reference 1) notes that ACI 318-63 is the current licensing basis (CLB) design code of record for Fort Calhoun Station (FCS). The CLB requires the use of working stress design (WSD) method for normal service conditions, and ultimate strength design (USD) method for no loss-of-function and special load cases. The LAR proposes to revise the CLB to use the USD method from ACI 318-63 for normal service load conditions for future design and evaluation of the Auxiliary Building. Section 4.2 of the LAR notes that several operating nuclear power plants constructed in the era that FCS was built use the ACI 318-63 USD method for normal operating/service load combinations.
Class 1 concrete structures, including earlier-vintage plants that have adapted ACI 318-63 or ACI 318-71 as the licensing basis code-of-record, have typically been licensed to load combinations (normal operating/service condition and extreme (no loss of function and special cases) condition) with load factors associated with design loads in the combination based on the NRC staff position documented in NUREG-0800 Standard Review Plan (SRP) 3.8.4 and Regulatory Guide (RG) 1.142 (which currently endorses ACI 349-97 with 1
conditions). The factor assigned to each load in a load combination is influenced by the degree of accuracy to which the load effect can be calculated, the variation expected in the load during the life of the structure, the probability of simultaneous occurrence, and assumptions and approximations in the structural analysis calculations.
Issue:
The second and third load combinations (associated with footnote (2) in LAR Table 5) use the existing USAR USD equations for the no loss-of-function condition (extreme condition) and modify the equation by replacing the differential pressure component with the live load, and the differential temperature component with the soil load. The LAR notes that the resulting equation is similar to ACI 318-71 equation 9-2 (the load factors are not the same as equation 9-2). It is unclear to the staff why it is appropriate to modify in this fashion the loads in existing USD equations for extreme load conditions to develop load factors for the proposed USD service load combinations. It is also unclear why it is appropriate to selectively choose numerically inconsistent load factors from later editions of ACI 318 without reconciling the other related code provisions, and/or existing NRC staff positions in the SRP and RG 1.142.
The LAR notes that other operating nuclear plants use the ACI 318-63 USD method for normal operating/service load conditions; however, the LAR does not cite specific precedent where the NRC has previously approved the load factors for USD service load combinations proposed in Table 5 of the LAR. The NRC staff is not aware of past precedent that used the proposed load factors.
Request:
Provide technical justification for the proposed load factors associated with USD service load combinations in the second and third equations (associated with footnote 2) in LAR Table 5 (i.e., justify acceptability of substituting service loads into an equation associated with unusual or extreme load conditions).
If the response discusses ACI 318-71 equation 9-2 clearly explain why it is appropriate to selectively use load factors from three different codes in the proposed USAR (ACI 318-63, ACI 318-71, and ACI 349-97) without reconciliation with other related code provisions or an existing staff position.
If the response basis relies on precedent based on operating nuclear power plants that used ACI 318-63 USD service load combinations, provide details identifying previous case history and explain how the proposed load factors for the second and third USD service load combinations in FCSs LAR is consistent with that of the precedent plant.
- Regards, Jim Kim Project Manager - Fort Calhoun Station NRR/DORL/LSPB 301-415-4125 2
Hearing Identifier: NRR_PMDA Email Number: 3603 Mail Envelope Properties (James.Kim@nrc.gov20170713123100)
Subject:
Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
Sent Date: 7/13/2017 12:31:48 PM Received Date: 7/13/2017 12:31:00 PM From: Kim, James Created By: James.Kim@nrc.gov Recipients:
"BLOME, BRADLEY H" <bblome@oppd.com>
Tracking Status: None "MATZKE, ERICK P" <ematzke@oppd.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 5530 7/13/2017 12:31:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
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