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| | number = ML17115A062 | | | number = ML17115A062 |
| | issue date = 04/25/2017 | | | issue date = 04/25/2017 |
| | title = 2017/04/25 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 | | | title = NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 |
| | author name = Klos J J | | | author name = Klos J |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Elwood T B | | | addressee name = Elwood T |
| | addressee affiliation = AmerenUE | | | addressee affiliation = AmerenUE |
| | docket = 05000483 | | | docket = 05000483 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm Resource From:Klos, John Sent:Tuesday, April 25, 2017 8:10 AM To:'Telwood@ameren.com' Cc:Klos, John | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Klos, John Sent: Tuesday, April 25, 2017 8:10 AM To: 'Telwood@ameren.com' Cc: Klos, John |
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| ==Subject:== | | ==Subject:== |
| Requests for Additional Information -- | | Requests for Additional Information -- CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, CORE OPERATING LIMITS REPORT CAC MF8463 Follow Up Flag: Follow up Flag Status: Flagged |
| CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, "CORE OPER ATING LIMITS REPORT" CAC MF8463 Follow Up Flag:Follow up Flag Status: | |
| Flagged | |
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| ==Dear Mr. Elwood,== | | ==Dear Mr. Elwood,== |
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| By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaway's Technical Specification (TS) 5.6.5, "Core Operating Limits Report (COLR)", to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A). | | By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS) |
| | Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaways Technical Specification (TS) 5.6.5, Core Operating Limits Report (COLR), to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A). |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the requests for additional information (RAIs) below are needed to complete the technical review and make a regulatory finding regarding this LAR. |
| | You have stated that a clarification call for these RAIs are not needed, via voice mail. These RAIs are being issued formally with a response due 30 days from today on May 25, 2017. |
| | REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST CALLAWAY UNIT 1 DOCKET NO. 50-483 (CAC MF8463) |
| | By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS) |
| | Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaways Technical Specification 5.6.5, Core Operating Limits Report (COLR), to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A), respectively. |
| | The requests for additional information (RAIs) listed below are needed to support NRC staffs continued technical review of the proposed LAR. |
| | Regulatory Basis for RAIs: |
| | Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical Specifications," includes the method of controlling reactor physics parameters to assure conformance by specifying specific value(s) determined to be within specified acceptance criteria (usually the limits of the safety analyses) using an approved calculation methodology. |
| | RAIS: |
| | 1 |
| | : 1. NRC Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications, allows licensees to control certain reactor physics parameters on a cycle-by-cycle basis by moving them to a separate report, provided they specify the calculation methodology. The discussion in the GL references terms indicating that approval of licensee control of these parameters is contingent on selection of a single, specific methodology (e.g., the specified methodology and an NRC-approved methodology, etc.). |
| | The proposed amendment would preserve both the current PHOENIX-P/ANC nuclear design methodology and the new PARAGON-NEXUS/ANC nuclear design methodology in the licensees TS. By leaving both the current and proposed methodologies in the TS, the proposed amendment leaves open the possibility that either methodology could be used to calculate the core operating limits addressed in the COLR, effectively creating a new, ambiguous methodology. The NRC staff has therefore been unable to determine that the proposed amendment is consistent with GL 88-16 guidance. Please propose a revision to TS 5.6.5 that provides for a single, unambiguous method to determine how the core operating limits discussed in the submittal will be calculated. |
| | : 2. (Clarification) Addendum 1-A to WCAP-16045-P-A brings about a change to the way boron letdown curves are calculated and input into the overall nuclear design method. Because of this, in previous reviews of PARAGON-NEXUS/ANC applications, the NRC staff found it necessary to verify that no changes were made to the analysis methods for post-loss of coolant accident (LOCA) subcriticality and boric acid precipitation behavior. Please verify that no changes are made to these analysis methods as part of this LAR. |
| | Thank you, John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, O8E7 NRC/NRR/DORL/LPL4, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax) |
| | John.Klos@NRC.gov 2 |
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| The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the requests for additional information (RAIs) below are needed to complete the technical review and make a regulatory finding regarding this LAR.
| | Hearing Identifier: NRR_PMDA Email Number: 3467 Mail Envelope Properties (2cc83d6509654dabaeb2550c0e7a8a4f) |
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| You have stated that a clarification call for these RAIs are not needed, via voice mail. These RAIs are being issued formally with a response due 30 days from today on May 25, 2017.
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| REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST CALLAWAY UNIT 1 DOCKET NO. 50-483 (CAC MF8463)
| |
| | |
| By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaway's Technical Specification 5.6.5, "Core Operating Limits Report (COLR)", to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A), respectively.
| |
| The requests for additional information (RAIs) listed below are needed to support NRC staff's continued technical review of the proposed LAR.
| |
| | |
| Regulatory Basis for RAIs: Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical Specifications," includes the method of controlling reactor physics parameters to assure conformance by specifying specific value(s) determined to be within specified acceptance criteria (usually the limits of the safety analyses) using an approved calculation methodology.
| |
| | |
| RAIS:
| |
| : 21. NRC Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," allows licensees to control certain reactor physics parameters on a cycle-by-cycle basis by moving them to a separate report, provided they specify the calculation methodology. The discussion in the GL references terms indicating that approval of licensee control of these parameters is contingent on selection of a single, specific methodology (e.g., "the specified methodology" and "an NRC-approved methodology," etc.).
| |
| The proposed amendment would preserve both the current PHOENIX-P/ANC nuclear design methodology and the new PARAGON-NEXUS/ANC nuclear design methodology in the licensee's TS. By leaving both the current and proposed methodologies in the TS, the proposed amendment leaves open the possibility that either methodology could be used to calculate the core operating limits addressed in the COLR, effectively creating a new, ambiguous methodology. The NRC staff has therefore been unable to determine that the proposed amendment is consistent with GL 88-16 guidance. Please propose a revision to TS 5.6.5 that provides for a single, unambiguous method to determine how the core operating limits discussed in the submittal will be calculated.
| |
| : 2. (Clarification) Addendum 1-A to WCAP-16045-P-A brings about a change to the way boron letdown curves are calculated and input into the overall nuclear design method. Because of this, in previous reviews of PARAGON-NEXUS/ANC applications, the NRC staff found it necessary to verify that no changes were made to the analysis methods for post-loss of coolant accident (LOCA) subcriticality and boric acid precipitation behavior. Please verify that no changes are made to these analysis methods as part of this LAR.
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| Thank you,
| |
| | |
| John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Re actor Licensing, O8E7 NRC/NRR/DORL/LPL4, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax)
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| John.Klos@NRC.gov
| |
| | |
| Hearing Identifier: NRR_PMDA Email Number: 3467 Mail Envelope Properties (2cc83d6509654dabaeb2550c0e7a8a4f) | |
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| ==Subject:== | | ==Subject:== |
| Requests for Additional Information -- CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, "CORE OPERATING LIMITS REPORT" CAC MF8463 Sent Date: 4/25/2017 8:10:08 AM Received Date: 4/25/2017 8:10:12 AM From: Klos, John Created By: John.Klos@nrc.gov Recipients: "Klos, John" <John.Klos@nrc.gov> Tracking Status: None | | Requests for Additional Information -- CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, CORE OPERATING LIMITS REPORT CAC MF8463 Sent Date: 4/25/2017 8:10:08 AM Received Date: 4/25/2017 8:10:12 AM From: Klos, John Created By: John.Klos@nrc.gov Recipients: |
| "'Telwood@ameren.com'" <Telwood@ameren.com> Tracking Status: None | | "Klos, John" <John.Klos@nrc.gov> |
| | | Tracking Status: None |
| Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 4346 4/25/2017 8:10:12 AM | | "'Telwood@ameren.com'" <Telwood@ameren.com> |
| | | Tracking Status: None Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 4346 4/25/2017 8:10:12 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: Follow up}} | | Recipients Received: Follow up}} |
Letter Sequence RAI |
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MONTHYEARML16320A0702016-11-15015 November 2016 NRR E-mail Capture - Callaway, Unit 1, Acceptance of Requested Licensing Action CAC No. MF8463 Change in Technical Specification 5.6.5, Core Reload Methodology Project stage: Acceptance Review ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 Project stage: RAI ML17138A2132017-05-18018 May 2017 Response to Request for Additional Information Concerning Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011) Project stage: Response to RAI ML17236A0822017-09-15015 September 2017 Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr), Project stage: Approval 2017-04-25
[Table View] |
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Category:E-Mail
MONTHYEARML23362A0572023-12-28028 December 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - SUNSI Review of the Final Safety Analysis Report (FSAR) Revision OL-26 ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23121A0112023-04-28028 April 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Revise TS to Adopt TSTF-501-A Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control - EPID L-2023-LLA-0046 ML23114A2302023-04-24024 April 2023 NRR E-mail Capture - Regulatory Audit Question - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23107A1812023-04-17017 April 2023 NRR E-mail Capture - Regulatory Audit Questions - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23037A0022023-02-0303 February 2023 NRR E-mail Capture - Callaway - LAR to Adopt AST - EPID L-2021-LLA-0177 - Revised Schedule for Completion of the Project ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - ML22346A0132022-12-0909 December 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of LAR to Revise TS 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies - EPID L-2022-LLA-0165 ML22322A0062022-11-17017 November 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) Callaway - LAR for Proposed Changes to TS and Exemption Request Use of Framatome Gaia Fuel - L-2022-LLA-0150 & L-2022-LLE-0030 ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22280A1322022-10-0707 October 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway - License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-0 ML22278A0122022-10-0404 October 2022 NRR E-mail Capture - Draft - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-013 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22251A0122022-09-0707 September 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections - EPID L-2022-LLA-0110 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22216A0072022-07-0808 July 2022 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Draft Acceptance Review (Unacceptable for Review with Opportunity to Supplement) for Framatome Fuel Transition LAR and Exemption - EPIDs L-2022-LLA-0083 and L-2022-LLE-0019) ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0102022-06-0303 June 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood Ultimate Heat Sink Temporary Temperature Increase to 102.8 Degrees Fahrenheit ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22089A0222022-03-29029 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LAR to Adopt TSTF-505 and TSTF-439 - Follow Up Clarifications for the Audit Questions - EPID L-2021-LLA-0197 ML22087A4022022-03-28028 March 2022 NRR E-mail Capture - Callaway - Draft RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to Generic Letter 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22070A1362022-03-10010 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals - EPID L-2022-LLA-0024 ML22047A2312022-02-11011 February 2022 Email Between NRC NSIR and FEMA Regarding Callaway Sirens 021122 ML22003A0852022-01-0303 January 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules - EPID L-2021-LLA-0225 ML21334A5172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21335A0172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21308A0692021-11-0404 November 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Unit 1 - License Amendment Request - Adoption of Alternate Source Term and Revision of TSs - ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21125A0452021-05-0404 May 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Plant, Unit 1 - License Amendment Request - Final Resolution to Address Concerns of GSI-191 - EPID L-2021-LLA-0059 ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 ML20296A6332020-10-22022 October 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020 Lle 0140 (Covid 19)) - Revised Completion Schedule ML20205L4252020-07-22022 July 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Acceptance of Requested Licensing Action Request for One-Time License Amendment to Defer Upcoming Steam Generator Inspection (EPID L-2020-LLA-0142)(COVID-19) ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20153A7902020-05-29029 May 2020 Emai: RFI for Callaway EP Program Inspection ML20133K6742020-05-11011 May 2020 05000483, Request for Information 2020-002 ML20099G2422020-04-0808 April 2020 NRR E-mail Capture - Acceptance Callaway Containment Tendon COVID-19 Relief Request ML20097C8362020-04-0606 April 2020 NRR E-mail Capture - Accepted: Callaway TS Change 5.3.1 LAR EPID: L-2020-LLA-0046 2023-07-27
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21319A0062021-11-30030 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21159A2352021-06-17017 June 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000483/2021003) and Request for Information ML21130A5882021-05-11011 May 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions to Adopt a Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004 02 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20280A5442020-03-25025 March 2020 Cwy 2020 PIR Request for Information ML20064B6582020-02-27027 February 2020 Second, Third, and Fourth Request for Information for Callaway Dba Teams Inspection 2020011 ML19317E6332019-11-13013 November 2019 Request for Supporting Information for the Callaway SPRA Audit Review ML19107A5152019-04-11011 April 2019 Cwy 2019410 RFI Cyber Security Gap ML19078A2932019-03-18018 March 2019 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2019010) and Request for Information ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information ML19009A3442019-01-0909 January 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Plant Class 1E LAR, L-2018-LLA-0062 ML18355A4882018-12-20020 December 2018 NRR E-mail Capture - Formal Release of RAI Ref: Callaway Plant EAL Changes, L-2018-LLA-0239 ML18331A2052018-11-27027 November 2018 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Relief Request EPID L-2018-LLR-0051 ML18025B4672018-01-24024 January 2018 NRR E-mail Capture - Request for Extension of Due Date for RAI Response ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection ML17142A1352017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000483/2017007) and Initial Request for Information ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 ML17038A2292017-02-0707 February 2017 NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474 ML16111B3222016-04-20020 April 2016 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000483/2016007) and Request for Information ML15316A1532015-11-12012 November 2015 Request for Additional Information Email, Relief Request 13R-11 (Pressurizer Welds) from Code Case N-460 Requirements, Third 10-Year Inservice Inspection Interval ML15096A0942015-04-0606 April 2015 Notification of Inspection (NRC Inspection Report 05000483/2015003) and Request for Information ML14353A1172014-12-22022 December 2014 Request for Additional Information, Round 3, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14294A7752014-10-28028 October 2014 Request for Additional Information, Round 2, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14203A0632014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Rv ISI Frequency from 10 to 20 Years, Third 10-Year ISI Interval ML14178A8232014-07-0101 July 2014 Request for Additional Information, License Amendment Request to Revise Final Safety Analysis Report- Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ULNRC-06117, Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses2014-04-24024 April 2014 Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses ML14114A1102014-04-24024 April 2014 License Revewal Application, Request for Additional Information (RAI) Set 31 Responses 2023-07-19
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NRR-PMDAPEm Resource From: Klos, John Sent: Tuesday, April 25, 2017 8:10 AM To: 'Telwood@ameren.com' Cc: Klos, John
Subject:
Requests for Additional Information -- CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, CORE OPERATING LIMITS REPORT CAC MF8463 Follow Up Flag: Follow up Flag Status: Flagged
Dear Mr. Elwood,
By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaways Technical Specification (TS) 5.6.5, Core Operating Limits Report (COLR), to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the requests for additional information (RAIs) below are needed to complete the technical review and make a regulatory finding regarding this LAR.
You have stated that a clarification call for these RAIs are not needed, via voice mail. These RAIs are being issued formally with a response due 30 days from today on May 25, 2017.
REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST CALLAWAY UNIT 1 DOCKET NO. 50-483 (CAC MF8463)
By letter dated October 11, 2016, (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16286A553), Union Electric Company (UE, the licensee), dba Ameren Missouri submitted a License Amendment Request (LAR) to amend the Callaways Technical Specification 5.6.5, Core Operating Limits Report (COLR), to include references to the PARAGON and NEXUS Nuclear Data Methodology, (WCAP-16045-P-A and its Addendum 1-A), and New Pin Power Recovery Methodology (WCAP-10965-P-A, Addendum 2-A), respectively.
The requests for additional information (RAIs) listed below are needed to support NRC staffs continued technical review of the proposed LAR.
Regulatory Basis for RAIs:
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical Specifications," includes the method of controlling reactor physics parameters to assure conformance by specifying specific value(s) determined to be within specified acceptance criteria (usually the limits of the safety analyses) using an approved calculation methodology.
RAIS:
1
- 1. NRC Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications, allows licensees to control certain reactor physics parameters on a cycle-by-cycle basis by moving them to a separate report, provided they specify the calculation methodology. The discussion in the GL references terms indicating that approval of licensee control of these parameters is contingent on selection of a single, specific methodology (e.g., the specified methodology and an NRC-approved methodology, etc.).
The proposed amendment would preserve both the current PHOENIX-P/ANC nuclear design methodology and the new PARAGON-NEXUS/ANC nuclear design methodology in the licensees TS. By leaving both the current and proposed methodologies in the TS, the proposed amendment leaves open the possibility that either methodology could be used to calculate the core operating limits addressed in the COLR, effectively creating a new, ambiguous methodology. The NRC staff has therefore been unable to determine that the proposed amendment is consistent with GL 88-16 guidance. Please propose a revision to TS 5.6.5 that provides for a single, unambiguous method to determine how the core operating limits discussed in the submittal will be calculated.
- 2. (Clarification) Addendum 1-A to WCAP-16045-P-A brings about a change to the way boron letdown curves are calculated and input into the overall nuclear design method. Because of this, in previous reviews of PARAGON-NEXUS/ANC applications, the NRC staff found it necessary to verify that no changes were made to the analysis methods for post-loss of coolant accident (LOCA) subcriticality and boric acid precipitation behavior. Please verify that no changes are made to these analysis methods as part of this LAR.
Thank you, John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, O8E7 NRC/NRR/DORL/LPL4, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax)
John.Klos@NRC.gov 2
Hearing Identifier: NRR_PMDA Email Number: 3467 Mail Envelope Properties (2cc83d6509654dabaeb2550c0e7a8a4f)
Subject:
Requests for Additional Information -- CALLAWAY PLANT, UNIT 1, TECHNICAL SPECIFICATION 5.6.5, CORE OPERATING LIMITS REPORT CAC MF8463 Sent Date: 4/25/2017 8:10:08 AM Received Date: 4/25/2017 8:10:12 AM From: Klos, John Created By: John.Klos@nrc.gov Recipients:
"Klos, John" <John.Klos@nrc.gov>
Tracking Status: None
"'Telwood@ameren.com'" <Telwood@ameren.com>
Tracking Status: None Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 4346 4/25/2017 8:10:12 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: Follow up