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| | number = ML14346A443 | | | number = ML14346A443 |
| | issue date = 02/05/2015 | | | issue date = 02/05/2015 |
| | title = Dresden Nuclear Power Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, Request for Additional Information Relate to License Amendment Request Technical Specification Changes, to Add an NRC Approved Topical Repor | | | title = Request for Additional Information Relate to License Amendment Request Technical Specification Changes, to Add an NRC Approved Topical Report Reference |
| | author name = Mozafari B L | | | author name = Mozafari B |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Kaegi G T | | | addressee name = Kaegi G |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000237, 05000249, 05000254, 05000265 | | | docket = 05000237, 05000249, 05000254, 05000265 |
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| =Text= | | =Text= |
| {{#Wiki_filter:OFFICIAL USE ONLY -PROPRIETARY INFORMATION Mr. Glenn Kaegi UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2015 Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:OFFICIAL USE ONLY - PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2015 Mr. Glenn Kaegi Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2, REQUEST FOR ADDITIONAL INFORMATION RELATE TO LICENSE AMENDMENT REQUEST TECHNICAL SPECIFICATION CHANGES, TO ADD AN NRC APPROVED TOPICAL REPORT REFERENCE (TAC NOS. MF3359 AND MF3362) | | DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2, REQUEST FOR ADDITIONAL INFORMATION RELATE TO LICENSE AMENDMENT REQUEST TECHNICAL SPECIFICATION CHANGES, TO ADD AN NRC APPROVED TOPICAL REPORT REFERENCE (TAC NOS. MF3359 AND MF3362) |
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| ==Dear Mr. Kaegi:== | | ==Dear Mr. Kaegi:== |
| By application to the U.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13354C045), Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRG-approved topical report reference to the list of analytical methods that are used to determine the core operating limits. EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application." We revised our RAI draft based on the telephone call with Exelon on November 25, 2014 (ADAMS Accession No. ML 14344A325). | | |
| During that call it was agreed that you would provide a response by one month from the date of the formal letter. The NRC staff considers that timely responses help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | By application to the U.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13354C045), Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRG-approved topical report reference to the list of analytical methods that are used to determine the core operating limits. EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application." |
| If circumstances result in the need to revise the requested response date, please contact me to discuss any need for clarification OFFICIAL USE ONLY -PROPRIETARY INFORMATION OFFICIAL USE ONLY-PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020. | | We revised our RAI draft based on the telephone call with Exelon on November 25, 2014 (ADAMS Accession No. ML14344A325). During that call it was agreed that you would provide a response by one month from the date of the formal letter. |
| Brenda Mozafari, Senior Project anager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265 | | The NRC staff considers that timely responses help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me to discuss any need for clarification OFFICIAL USE ONLY - PROPRIETARY INFORMATION |
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| | OFFICIAL USE ONLY-PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020. |
| | Brenda Mozafari, Senior Project anager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information (proprietary) | | Request for Additional Information (proprietary) |
| OFFICIAL USE ONLY-PROPRIETARY INFORMATION | | OFFICIAL USE ONLY-PROPRIETARY INFORMATION |
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| OFFICIAL USE ONLY -PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGES TO ADD AN NRC APROVED TOPICAL REPORT REFERENCE EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NO. 50-237, 50-249, 50-254, AND 50-265 By letter to the l.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013, Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRC-approved topical report reference to the list of analytical methods that are used to determine the core operating limits. EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS [boiling-water reactor emergency core coling system] Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application." The NRC staff has reviewed the request submitted by the licensee and determined that the following additional information is needed. RAl-01 In the report (NF-BEX-13-143-P) the licensee states (or implies) that the report is specific to QC [Quad Cities] in several places, such as in the 2nd paragraph on page 12, the 1st sentence of the 2nd paragraph on page 20, the 4th bullet on page 51, etc. However, the LAR requests an amendment to Renewed Facility Operating Licenses for not only the QC units but also the Dresden units as well. Justify this report BEX-13-143-P), a sample application of the LOCA [loss-of-coolant accident]methodology (WCAP-16865-P-A, Revision 1) for QC, can also be applied to the Dresden units. Provide additional information to confirm that the Quad Cities and Dresden Plants are "similar". | | OFFICIAL USE ONLY - PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGES TO ADD AN NRC APROVED TOPICAL REPORT REFERENCE EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NO. 50-237, 50-249, 50-254, AND 50-265 By letter to the l.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013, Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS), |
| Confirm that the application of the methodology applied for Quad Cities will be applied for Dresden "similarly" when applied in the future. RAl-2 [[ ]] RAl-03 The equation given on page 34 implies that the pressure loss (or differential pressures) caused by leakage is the same as the pressure loss due to either LPCS or LPCI. (a) Explain the upstream and downstream locations of the two pressure losses. (b) What is the basis for the assumption that the two pressure losses are the same? OFFICIAL USE ONLY-PROPRIETARY INFORMATION OFFICIAL USE ONLY -PROPRIETARY INFORMATION RAl-04 In Section B.1.1 on page 51 EGC discusses ASD (Adjustable Speed Drive). It is stated, "Reference 3-12 concluded that the predicted coastdown time (PCT) constant for the QC ASD modification of> 5.1 seconds is reasonable for applications to ECCS performance analysis. | | Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRC-approved topical report reference to the list of analytical methods that are used to determine the core operating limits. |
| Reference 3-12 and the current AOR [analysis of record] both use a modeled coastdown time constant of 4.45 seconds which therefore remains conservative to the predicted time constant with the ASD modification." Explain why the coast down time constant of 4.45 seconds is conservative compared to the reasonable time of> 5.1 seconds. RAl-05 [[ ]] RAl-06 [[ ]] RAl-07 [[ ]] RAl-08 [[ ]] OFFICIAL USE ONLY -PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020. | | EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS [boiling-water reactor emergency core coling system] |
| Sincerely, IRA/ Brenda Mozafari, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265 | | Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application." |
| | The NRC staff has reviewed the request submitted by the licensee and determined that the following additional information is needed. |
| | RAl-01 In the report (NF-BEX-13-143-P) the licensee states (or implies) that the report is specific to QC [Quad Cities] in several places, such as in the 2nd paragraph on page 12, the 1st sentence of the 2nd paragraph on page 20, the 4th bullet on page 51, etc. |
| | However, the LAR requests an amendment to Renewed Facility Operating Licenses for not only the QC units but also the Dresden units as well. Justify this report (NF-BEX-13-143-P), a sample application of the LOCA [loss-of-coolant accident]methodology (WCAP-16865-P-A, Revision 1) for QC, can also be applied to the Dresden units. Provide additional information to confirm that the Quad Cities and Dresden Plants are "similar". Confirm that the application of the methodology applied for Quad Cities will be applied for Dresden "similarly" when applied in the future. |
| | RAl-2 (( )) |
| | RAl-03 The equation given on page 34 implies that the pressure loss (or differential pressures) caused by leakage is the same as the pressure loss due to either LPCS or LPCI. |
| | (a) Explain the upstream and downstream locations of the two pressure losses. |
| | (b) What is the basis for the assumption that the two pressure losses are the same? |
| | OFFICIAL USE ONLY- PROPRIETARY INFORMATION |
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| | OFFICIAL USE ONLY - PROPRIETARY INFORMATION RAl-04 In Section B.1.1 on page 51 EGC discusses ASD (Adjustable Speed Drive). It is stated, "Reference 3-12 concluded that the predicted coastdown time (PCT) constant for the QC ASD modification of> 5.1 seconds is reasonable for applications to ECCS performance analysis. Reference 3-12 and the current AOR [analysis of record] both use a modeled coastdown time constant of 4.45 seconds which therefore remains conservative to the predicted time constant with the ASD modification." Explain why the coast down time constant of 4.45 seconds is conservative compared to the reasonable time of> 5.1 seconds. |
| | RAl-05 (( )) |
| | RAl-06 (( )) |
| | RAl-07 (( )) |
| | RAl-08 (( )) |
| | OFFICIAL USE ONLY - PROPRIETARY INFORMATION |
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| | OFFICIAL USE ONLY PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020. |
| | Sincerely, IRA/ |
| | Brenda Mozafari, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information (proprietary) | | Request for Additional Information (proprietary) |
| DISTRIBUTION: | | DISTRIBUTION: |
| NON-PUBLIC LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssStsb Resource RidsNrrSRXB Resource GThomas, SRXB Accession Number: ML 14346A443 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA NAME BMozafari SRohrer Date 02/04/15 02/05/15 DSS/SRXB/BC CJackson* | | NON-PUBLIC LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssStsb Resource RidsNrrSRXB Resource GThomas, SRXB Accession Number: ML14346A443 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DSS/SRXB/BC DORL/LPL3-2/BC DORL/LPL3-2 NAME BMozafari SRohrer CJackson* TTate BMozafari Date 02/04/15 02/05/15 02/04/15 02/5 /15 02/ 5/15 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION}} |
| 02/04/15 OFFICIAL RECORD COPY DORL/LPL3-2/BC TTate 02/5 /15 OFFICIAL USE ONLY PROPRIETARY INFORMATION DORL/LPL3-2 BMozafari 02/ 5/15}} | |
Letter Sequence RAI |
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MONTHYEARRS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. Project stage: Request ML14069A3822014-03-0808 March 2014 NRR E-mail Capture - FW: Acceptance Review - Dresden, Units 2 and 3 and Quad Cities, Units 1 and 2, License Amendment Requests to TS Section 5.6.5. Core Operating Limits Report. (TACs MF3359-3360;MF3361-3362) Project stage: Request ML14128A5662014-07-29029 July 2014 Request for Withholding Proprietary Information from Public Disclosure Project stage: Other ML14324A1392014-11-20020 November 2014 Notice of Closed Meeting with Exelon Nuclear to Discuss Exelon Nuclear'S 12/19/2013, Application for Amendment of the Dresden and Quad Cities Nuclear Power Station'S Technical Specifications to Add Reference to Topical Report WCAP-16865-P-A Project stage: Meeting ML14344A3252015-01-28028 January 2015 Summary of November 25, 2014, Meeting with Exelon Generation Company, LLC Regarding It'S Application to Add a Methodology to Technical Specification 5.6.5 (TAC Nos. MF3359-MF3362) Project stage: Meeting ML15034A2932015-02-0505 February 2015 Request for Additional Information Related to the Request for LAR Regarding COLR Project stage: RAI ML14346A4432015-02-0505 February 2015 Request for Additional Information Relate to License Amendment Request Technical Specification Changes, to Add an NRC Approved Topical Report Reference Project stage: RAI ML15183A3512015-08-0505 August 2015 Issuance of Amendments Concerning Adding Topical References to Technical Specifications (TAC Nos. MF3359, MF3363, MF3361, and MF3362)(RS-13-288) Project stage: Approval ML15294A3172015-11-19019 November 2015 Correction to License Pages (TAC Nos. MF3361 and MF3362)(RS-13-288) Project stage: Other 2014-07-29
[Table View] |
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Category:Letter
MONTHYEARML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) SVP-24-046, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, Safety Limit MCPR SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24135A0182024-05-13013 May 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment ML24102A2422024-04-10010 April 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments ML24066A1532024-03-0606 March 2024 NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments ML24066A0872024-03-0404 March 2024 NRR E-mail Capture - Dresden 2 and 3 - Request for Additional Information for Alternative Request I5R-22 ML24067A1242024-03-0101 March 2024 Email to Christian Williams: Request for Additional Information Regarding Dresden Relief Request Dated February 23, 2024 ML24053A1192024-02-22022 February 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010 ML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23118A1652023-04-28028 April 2023 NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23065A2832023-03-0707 March 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000254/2023010 and 05000265/2023010 ML23052A0652023-02-21021 February 2023 NRR E-mail Capture - Dresden Units 2 and 3 - Request for Additional Information for Alternative Request RV-23H ML23037A9192023-02-0707 February 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000237/2023011 and 05000249/2023011 ML23013A1502023-01-17017 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002 ML23019A0132023-01-12012 January 2023 NRR E-mail Capture - Final RAI Dresden 2 and 3 - License Amendment Pertaining to GNF3 Fuel Transition ML23004A0262022-12-16016 December 2022 NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070) ML22348A0452022-12-14014 December 2022 NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09 ML22290A0842022-10-13013 October 2022 NRR E-mail Capture - Dresden 2 and 3 - RAI License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22227A1152022-09-27027 September 2022 Request for Withholding Information from Public Disclosure ML22270A1032022-09-27027 September 2022 Notification of NRC Baseline Inspection and Request for Information (05000249/2022004) ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22249A2332022-09-0606 September 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000254/2022011 05000265/2022011 ML22203A0442022-07-21021 July 2022 Request for Additional Information (RAI) ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22199A2422022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Dresden 2 and 3 Proposed Alternative Related to Sblc Nozzle Inspection for the Sixth Inservice Inspection Interval ML22193A0412022-07-11011 July 2022 NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods ML22182A1992022-07-0101 July 2022 NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28 ML22178A1362022-06-28028 June 2022 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Quad Cities Station ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22076A1122022-03-15015 March 2022 Request for Additional Information Related to the Amendment Request to Transition to GNF3 Fuels (EPID L-2021-LLA-0159) (Redacted) ML22059A9902022-03-0101 March 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Implement Prime Methodologies for Evaluating Thermal Overpower and Mechanical Overpower Limits for Non-Global Nuclear Fuels Fuel ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22039A1912022-02-0808 February 2022 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21342A3842021-12-0808 December 2021 NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel ML21294A0032021-10-26026 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding Transition to GNF3 Fuel ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21238A3142021-08-26026 August 2021 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000254/2021004; 05000265/2021004 ML21244A4012021-08-10010 August 2021 (Final) Request for Information (RAI) Dresden, Units 1, 2, 3, and ISFSI Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50 Appendix E ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21097A2602021-04-0808 April 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21096A1752021-04-0606 April 2021 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000237/2021011; 05000249/2021011 ML21063A3202021-03-0202 March 2021 RAIs for Dresden, Units 2 and 3, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (EPID L-2020-LLA-0239) (E-mail) 2024-07-12
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OFFICIAL USE ONLY - PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2015 Mr. Glenn Kaegi Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2, REQUEST FOR ADDITIONAL INFORMATION RELATE TO LICENSE AMENDMENT REQUEST TECHNICAL SPECIFICATION CHANGES, TO ADD AN NRC APPROVED TOPICAL REPORT REFERENCE (TAC NOS. MF3359 AND MF3362)
Dear Mr. Kaegi:
By application to the U.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13354C045), Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRG-approved topical report reference to the list of analytical methods that are used to determine the core operating limits. EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application."
We revised our RAI draft based on the telephone call with Exelon on November 25, 2014 (ADAMS Accession No. ML14344A325). During that call it was agreed that you would provide a response by one month from the date of the formal letter.
The NRC staff considers that timely responses help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me to discuss any need for clarification OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY-PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020.
Brenda Mozafari, Senior Project anager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information (proprietary)
OFFICIAL USE ONLY-PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGES TO ADD AN NRC APROVED TOPICAL REPORT REFERENCE EXELON GENERATION COMPANY, LLC DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NO. 50-237, 50-249, 50-254, AND 50-265 By letter to the l.S. Nuclear Regulatory Commission (NRC) dated December 19, 2013, Exelon Generation Company, LLC (EGC), the licensee for the Dresden Nuclear Power Station (DNPS),
Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, submitted a license amendment request (LAR) for review and approval of a revision to the DNPS and QCNPS Technical Specifications (TS) Section 5.6.5 to add an NRC-approved topical report reference to the list of analytical methods that are used to determine the core operating limits.
EGC states that the proposed change adds a reference to Westinghouse topical report WCAP-16865-P-A, "Westinghouse BWR ECCS [boiling-water reactor emergency core coling system]
Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application."
The NRC staff has reviewed the request submitted by the licensee and determined that the following additional information is needed.
RAl-01 In the report (NF-BEX-13-143-P) the licensee states (or implies) that the report is specific to QC [Quad Cities] in several places, such as in the 2nd paragraph on page 12, the 1st sentence of the 2nd paragraph on page 20, the 4th bullet on page 51, etc.
However, the LAR requests an amendment to Renewed Facility Operating Licenses for not only the QC units but also the Dresden units as well. Justify this report (NF-BEX-13-143-P), a sample application of the LOCA [loss-of-coolant accident]methodology (WCAP-16865-P-A, Revision 1) for QC, can also be applied to the Dresden units. Provide additional information to confirm that the Quad Cities and Dresden Plants are "similar". Confirm that the application of the methodology applied for Quad Cities will be applied for Dresden "similarly" when applied in the future.
RAl-2 (( ))
RAl-03 The equation given on page 34 implies that the pressure loss (or differential pressures) caused by leakage is the same as the pressure loss due to either LPCS or LPCI.
(a) Explain the upstream and downstream locations of the two pressure losses.
(b) What is the basis for the assumption that the two pressure losses are the same?
OFFICIAL USE ONLY- PROPRIETARY INFORMATION
OFFICIAL USE ONLY - PROPRIETARY INFORMATION RAl-04 In Section B.1.1 on page 51 EGC discusses ASD (Adjustable Speed Drive). It is stated, "Reference 3-12 concluded that the predicted coastdown time (PCT) constant for the QC ASD modification of> 5.1 seconds is reasonable for applications to ECCS performance analysis. Reference 3-12 and the current AOR [analysis of record] both use a modeled coastdown time constant of 4.45 seconds which therefore remains conservative to the predicted time constant with the ASD modification." Explain why the coast down time constant of 4.45 seconds is conservative compared to the reasonable time of> 5.1 seconds.
RAl-05 (( ))
RAl-06 (( ))
RAl-07 (( ))
RAl-08 (( ))
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION G. Kaegi If you have any questions related to the RAI or cannot meet the one month response date, please call me at 301-415-2020.
Sincerely, IRA/
Brenda Mozafari, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information (proprietary)
DISTRIBUTION:
NON-PUBLIC LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDssStsb Resource RidsNrrSRXB Resource GThomas, SRXB Accession Number: ML14346A443 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DSS/SRXB/BC DORL/LPL3-2/BC DORL/LPL3-2 NAME BMozafari SRohrer CJackson* TTate BMozafari Date 02/04/15 02/05/15 02/04/15 02/5 /15 02/ 5/15 OFFICIAL RECORD COPY OFFICIAL USE ONLY PROPRIETARY INFORMATION