Letter Sequence RAI |
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MONTHYEARULNRC-05521, Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-24024 June 2008
Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Request
ML0818503312008-06-27027 June 2008
Email Response from Scott Maglio to Mohan Thadani, Jack Donahew, Leon Whitney Generic Letter - 2004 - 02
Project stage: Other
ML0818503552008-06-27027 June 2008
Attachment, Summary of Telephone Conference Regarding Request for Extension of Completion of Corrective Actions for NRC Generic Letter 2004-02
Project stage: Request
ML0818406062008-07-0303 July 2008
Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
Project stage: Other
ML0920101192008-12-18018 December 2008
Email Re Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0920101222008-12-18018 December 2008
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0920306202009-07-31031 July 2009
Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station
Project stage: Draft RAI
ML0922205722009-08-27027 August 2009
Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0924607142009-09-28028 September 2009
Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek
Project stage: Draft RAI
ML0928003162009-10-16016 October 2009
Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively
Project stage: RAI
ML0929300152009-10-20020 October 2009
Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML0933801482009-11-20020 November 2009
Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S
Project stage: Request
ULNRC-05668, Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs2009-11-24024 November 2009
Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs
Project stage: Request
ML0933805662009-12-17017 December 2009
Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively
Project stage: RAI
ULNRC-05989, Path Forward for Resolution of GSI-1912013-05-16016 May 2013
Path Forward for Resolution of GSI-191
Project stage: Request
ML13263A1682013-09-23023 September 2013
Request for Additional Information, Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191
Project stage: RAI
ULNRC-06045, Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage2013-10-31031 October 2013
Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage
Project stage: Response to RAI
2009-11-24
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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] |
Text
From: Thadani, Mohan Sent: Thursday, December 18, 2008 3:40 PM To: Internet:; Internet:
Cc: Leon Whitney; Scott, Michael; Harrison, Donnie
Subject:
FW: Callaway GL 2004-02 RAIs Attachments: Callaway RAIs.doc Importance: High Scott/Tom:
By letter dated February 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML080810491), Union Electric Company (the licensee) submitted a supplemental response to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, for Callaway.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensees submittals.
The process involved detailed review by a team of approximately 10 subject matter experts, with a focus on the review areas described in the NRCs Content Guide for Generic Letter 2004-02 Supplemental Responses (ADAMS Accession No. ML073110389). Based on these reviews, the staff has determined that additional information is needed in order to conclude that there is a reasonable assurance that GL 2004-02 has been satisfactorily addressed for Callaway. The attached document describes these requests for additional information (RAIs).
The NRC requests that the licensee respond to these RAIs within 90 days of the date of the formal letter. However, the NRC would like to receive only one response letter for all RAIs with exceptions stated below. If the licensee concludes that more than 90 days are required to respond to the RAIs, the licensee should request additional time, including a basis for why the extension is needed.
If the licensee concludes, based on its review of the RAIs, that additional corrective actions are needed for GL 2004-02, the licensee should request additional time to complete such corrective actions as needed. Criteria for such extension requests are contained in SECY-06-0078 (ADAMS Accession No. ML053620174), and examples of previous requests and approvals can be found on the NRCs sump performance website, located at:
http://www.nrc.gov/reactors/operating/ops-experience/pwr-sump-performance.html.
Any extension request should also include results of contingency planning that will result in near term identification and implementation of any and all modifications needed to fully address GL 2004-02. The NRC strongly suggests that the licensee discuss such plans with the staff before formally transmitting an extension request.
The exception to the above response timeline is RAI 17 in the enclosure. The NRC staff considers in-vessel downstream effects to not be fully addressed at Callaway, as well as at other pressurized water reactors. The licensee's submittal refers to draft WCAP-16793-NP, Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid. At this time, the NRC staff has not issued a final safety evaluation (SE) for WCAP-16793.
The licensee may demonstrate that in-vessel downstream effects issues are resolved for Callaway, by showing that the licensees plant conditions are bounded by the final WCAP-16793 and the corresponding final NRC staff SE, and by addressing the conditions and limitations in the final SE. The licensee may also resolve RAI 17 by demonstrating, without reference to WCAP-16793 or the NRC staff SE, that in-vessel downstream effects have been addressed at Callaway. The specific issues raised in RAI 17 should be addressed regardless of the approach the licensee chooses to take.
The licensee should report how it has addressed the in-vessel downstream effects issue and the associated RAI referenced above within 90 days of issuance of the final NRC staff SE on WCAP-16793. The NRC staff is currently developing a Regulatory Issue Summary to inform licensees of the staffs expectations and plans regarding resolution of this remaining aspect of Generic Safety Issue 191, Assessment of Debris Accumulation on PWR Sump Performance.
Please review the attached RAI, and let me know when you would like to discuss the RAI with the NRC's subject experts for any clarifications needed on the RAI. I will setup a phoncon at mutually convenient time.
Thanks.
Mohan C Thadani Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov
