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| | number = ML13115A232 | | | number = ML13115A232 |
| | issue date = 04/24/2013 | | | issue date = 04/24/2013 |
| | title = 2013/04/24 NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information | | | title = NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information |
| | author name = Purnell B A | | | author name = Purnell B |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Nicely K | | | addressee name = Nicely K |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Purnell, BlakeSent:Wednesday, April 24, 2013 3:14 PMTo:Ken.Nicely@exeloncorp.comCc:Mozafari, Brenda; Bowen, Jeremy; Mitchel.Mathews@exeloncorp.comSubject:Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional InformationOFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EXELON GENERATION COMPANY, LLC RELIEF REQUEST NOS. I5R-01, I5R-02, and I5R-06 DOCKET NUMBERS 50-254 and 50-265 TAC Nos. ME9668, ME9669, ME9670, ME9671, ME9676, and ME9677 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and management System (ADAMS) Accession No. ML12275A070), as supplemented by letter dated November 28, 2012 (ADAMS Accession No. ML12333A262), Exelon Generation Company, LLC (the licensee) submitted several proposed relief requests for the Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS). The NRC staff determined that the following additional information is necessary to complete the review of relief requests I5R-01, I5R-02, and I5R-06. To support the schedule for approval the response to this request is expected by May 24, 2013. | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Purnell, Blake Sent: Wednesday, April 24, 2013 3:14 PM To: Ken.Nicely@exeloncorp.com Cc: Mozafari, Brenda; Bowen, Jeremy; Mitchel.Mathews@exeloncorp.com |
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| Based on the staff's review of relief request I5R-01: | | ==Subject:== |
| 1. Discuss in the relief request why the proposed alternative provides reasonable assurance of structural integrity or leak tightness of the subject components. 2. Discuss in the relief request how the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. 3. Provide a technical basis as to why the ultrasonic testing is not required. Based on the staff's review of relief request I5R-02: | | Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R Request for Additional Information OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EXELON GENERATION COMPANY, LLC RELIEF REQUEST NOS. I5R-01, I5R-02, and I5R-06 DOCKET NUMBERS 50-254 and 50-265 TAC Nos. ME9668, ME9669, ME9670, ME9671, ME9676, and ME9677 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and management System (ADAMS) Accession No. ML12275A070), as supplemented by letter dated November 28, 2012 (ADAMS Accession No. ML12333A262), Exelon Generation Company, LLC (the licensee) submitted several proposed relief requests for the Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS). The NRC staff determined that the following additional information is necessary to complete the review of relief requests I5R-01, I5R-02, and I5R-06. To support the schedule for approval the response to this request is expected by May 24, 2013. |
| 1. Do the augmented inspection programs for intergranular stress corrosion cracking Category B-G (Generic Letter 88-01), service water integrity (Generic Letter 89-13), flow accelerated corrosion (Generic Letter 89-08), and high-energy line break (NRC Branch Technical Position MEB 3-1), as described in the initial QCNPS risk-informed ISI submittal dated November 30, 2000 (ADAMS Accession No. ML003776493), remain unaffected by the risk-informed ISI program developed for the fifth interval? 2. Are the inspection locations in the QCNPS risk-informed ISI programs that have been developed for the fifth 10-year interval the same locations as those in the fourth interval risk-informed ISI programs approved in the NRC staff's January 28, 2004, safety evaluation? If not, please summarize the changes to the program and what caused those changes. | | Based on the staffs review of relief request I5R-01: |
| 3. If there are changes in the inspection locations for the QCNPS fifth 10-year interval risk-informed ISI programs please provide information for the fifth interval program regarding: examinations, system, components, degradation mechanisms, class, etc. The information expected should be similar to what 2is in Tables 2, 3, 4, 5 and 6 of the original submittal of the risk-informed ISI program for the QCNPS third 10-year inservice inspection interval dated November 30, 2000. Based on the staff's review of relief request I5R-06: 1. Confirm whether NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets. 2. Section 4.1 item 5 of the BWRVIP-100-A report, "Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds," states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 report, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines." Identify whether the core shroud welds and base materials will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) during the current ISI interval. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the NRC staff requests that the licensee address the following issue: The inspection frequency and strategy that are specified in Section 3 of the BWRVIP-76 report require further evaluation taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report. 3. Dresden and Quad Cities (D/QC) Safety Evaluation Report, "NUREG-1796, Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2," license renewal application (LRA) commitment #9 in Appendix A of NUREG-1796 states that the licensee should implement the staff approved aging management program for the steam dryers at the D/QC units. In July 2009, the BWRVIP issued a staff approved topical report BWRVIP-139-A, "BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines." The NRC staff requests that the licensee confirm that it will comply with the guidelines addressed in the BWRVIP-139-A report as per LRA commitment #9 in NUREG-1796. | | : 1. Discuss in the relief request why the proposed alternative provides reasonable assurance of structural integrity or leak tightness of the subject components. |
| : 4. Consistent with the LRA commitment #9, with respect to the aging management program related to the top guide, the licensee should confirm that it will comply with the inspection guidelines addressed in the BWRVIP-26-A and BWRVIP-183 reports. A copy of this email will be placed into ADAMS and made publicly available. | | : 2. Discuss in the relief request how the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| Sincerely, | | : 3. Provide a technical basis as to why the ultrasonic testing is not required. |
| | Based on the staffs review of relief request I5R-02: |
| | : 1. Do the augmented inspection programs for intergranular stress corrosion cracking Category B-G (Generic Letter 88-01), service water integrity (Generic Letter 89-13), flow accelerated corrosion (Generic Letter 89-08), and high-energy line break (NRC Branch Technical Position MEB 3-1), as described in the initial QCNPS risk-informed ISI submittal dated November 30, 2000 (ADAMS Accession No. ML003776493), remain unaffected by the risk-informed ISI program developed for the fifth interval? |
| | : 2. Are the inspection locations in the QCNPS risk-informed ISI programs that have been developed for the fifth 10-year interval the same locations as those in the fourth interval risk-informed ISI programs approved in the NRC staff's January 28, 2004, safety evaluation? If not, please summarize the changes to the program and what caused those changes. |
| | : 3. If there are changes in the inspection locations for the QCNPS fifth 10-year interval risk-informed ISI programs please provide information for the fifth interval program regarding: examinations, system, components, degradation mechanisms, class, etc. The information expected should be similar to what 1 |
| | |
| | is in Tables 2, 3, 4, 5 and 6 of the original submittal of the risk-informed ISI program for the QCNPS third 10-year inservice inspection interval dated November 30, 2000. |
| | Based on the staffs review of relief request I5R-06: |
| | : 1. Confirm whether NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets. |
| | : 2. Section 4.1 item 5 of the BWRVIP-100-A report, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds, states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 report, BWR Core Shroud Inspection and Flaw Evaluation Guidelines. Identify whether the core shroud welds and base materials will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) during the current ISI interval. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the NRC staff requests that the licensee address the following issue: |
| | The inspection frequency and strategy that are specified in Section 3 of the BWRVIP-76 report require further evaluation taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report. |
| | : 3. Dresden and Quad Cities (D/QC) Safety Evaluation Report, NUREG-1796, Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2, license renewal application (LRA) commitment #9 in Appendix A of NUREG-1796 states that the licensee should implement the staff approved aging management program for the steam dryers at the D/QC units. In July 2009, the BWRVIP issued a staff approved topical report BWRVIP-139-A, BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines. The NRC staff requests that the licensee confirm that it will comply with the guidelines addressed in the BWRVIP-139-A report as per LRA commitment #9 in NUREG-1796. |
| | : 4. Consistent with the LRA commitment #9, with respect to the aging management program related to the top guide, the licensee should confirm that it will comply with the inspection guidelines addressed in the BWRVIP-26-A and BWRVIP-183 reports. |
| | A copy of this email will be placed into ADAMS and made publicly available. |
| | Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-1380 2 |
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| Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-1380 Hearing Identifier: NRR_PMDA Email Number: 675 Mail Envelope Properties (Blake.Purnell@nrc.gov20130424151400)
| | Hearing Identifier: NRR_PMDA Email Number: 675 Mail Envelope Properties (Blake.Purnell@nrc.gov20130424151400) |
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| ==Subject:== | | ==Subject:== |
| Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information Sent Date: 4/24/2013 3:14:22 PM Received Date: 4/24/2013 3:14:00 PM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients: "Mozafari, Brenda" <Brenda.Mozafari@nrc.gov> Tracking Status: None "Bowen, Jeremy" <Jeremy.Bowen@nrc.gov> Tracking Status: None "Mitchel.Mathews@exeloncorp.com" <Mitchel.Mathews@exeloncorp.com> Tracking Status: None "Ken.Nicely@exeloncorp.com" <Ken.Nicely@exeloncorp.com> Tracking Status: None | | Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R Request for Additional Information Sent Date: 4/24/2013 3:14:22 PM Received Date: 4/24/2013 3:14:00 PM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients: |
| | | "Mozafari, Brenda" <Brenda.Mozafari@nrc.gov> |
| Post Office: Files Size Date & Time MESSAGE 5627 4/24/2013 3:14:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | Tracking Status: None "Bowen, Jeremy" <Jeremy.Bowen@nrc.gov> |
| }} | | Tracking Status: None "Mitchel.Mathews@exeloncorp.com" <Mitchel.Mathews@exeloncorp.com> |
| | Tracking Status: None "Ken.Nicely@exeloncorp.com" <Ken.Nicely@exeloncorp.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 5627 4/24/2013 3:14:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
Letter Sequence RAI |
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MONTHYEARML1100404192011-02-15015 February 2011
Summary of Telephone Conference Call Held on December 6, 2010, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operating, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application (Tac No. MC9669)
Project stage: Other
ML1108206892011-04-19019 April 2011
February 24, 2011, Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application
Project stage: Other
RS-12-151, Fifth Interval Lnservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012
Fifth Interval Lnservice Inspection Program Plan and Relief Requests
Project stage: Request
RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012
Fifth Interval Inservice Inspection Program Plan and Relief Requests
Project stage: Request
RS-12-202, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-19019 November 2012
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01
Project stage: Supplement
ML12331A2772012-11-28028 November 2012
Supplemental Information Needed for Acceptance of RLA, I5R-02
Project stage: Acceptance Review
RS-12-203, Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-28028 November 2012
Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01
Project stage: Supplement
RS-12-205, Supplement to Fifth Inservice Inspection Interval Relief Request I5R-022012-11-28028 November 2012
Supplement to Fifth Inservice Inspection Interval Relief Request I5R-02
Project stage: Supplement
ML12348A8302012-12-13013 December 2012
NRR E-mail Capture - Acceptance Review of Dresden, Units 2 and 3, Relief Request I5R-02
Project stage: Acceptance Review
ML12348A8312012-12-13013 December 2012
NRR E-mail Capture - Acceptance Review of Quad Cities, Units 1 and 2, Relief Request I5R-02
Project stage: Acceptance Review
ML12348A4272012-12-21021 December 2012
Request for Additional Information Related to the Request for Alternative I5R-03
Project stage: RAI
RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013
Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03
Project stage: Supplement
RS-13-040, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-042013-01-24024 January 2013
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04
Project stage: Supplement
ML13099A2802013-04-0909 April 2013
NRR E-mail Capture - Finalized Dresden RAI I5R-01 I5R-02 and I5R-07
Project stage: RAI
ML13110A0072013-04-19019 April 2013
NRR E-mail Capture - RAI for Dresden Units 2 and 3 Exelon Generation Company, LLC Relief Request Nos. I5R-01, I5R-02, and I5R-07 Docket Numbers 50-237 and 50-249 TAC Nos. ME9682-83, ME9684-85, and ME9692-93
Project stage: RAI
ML13115A2322013-04-24024 April 2013
NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information
Project stage: RAI
ML13123A0852013-05-0202 May 2013
NRR E-mail Capture - Dresden Relief Request No. I5R-02 - Request for Additional Information
Project stage: RAI
ML13123A0862013-05-0202 May 2013
NRR E-mail Capture - Quad Cities Relief Request No. I5R-02 - Request for Additional Information
Project stage: RAI
RS-13-147, Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-062013-05-30030 May 2013
Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-06
Project stage: Request
RS-13-107, Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-072013-06-0303 June 2013
Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-07
Project stage: Supplement
ML13258A0032013-09-30030 September 2013
Safety Evaluation for the Fifth 10-Year Interval Inservice Inspection Relief Request for Exelon Generation Boiling Water Reactor (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc.)
Project stage: Approval
ML13260A5852013-09-30030 September 2013
Cover Letter -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10-Year Interval Inservice Inspection Program (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc
Project stage: Approval
ML13267A0972013-09-30030 September 2013
Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Inspection Program
Project stage: Approval
2013-01-10
[Table View] |
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Category:E-Mail
MONTHYEARML24254A2082024-09-10010 September 2024
NRR E-mail Capture - Quad Cities, Unit Nos. 1 and 2 - Alternative to RV-08, Rev 1, SRV Testing Interval - Acceptance of Requested Licensing Action Re Relief Request Associated with Safety Relief Valve Testing Interval
ML24250A1062024-09-0606 September 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030)
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
ML24197A0482024-07-12012 July 2024
Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection
ML24135A0182024-05-13013 May 2024
NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment
ML24131A0612024-05-10010 May 2024
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030)
ML24086A5182024-04-30030 April 2024
E-mail to Christian Williams Decision on the Exemption Request for Quad Cities
ML24086A4782024-04-24024 April 2024
Email to Christian Williams Availability of Environmental Assessment for the Quad Cities Exemption
ML24114A1702024-04-15015 April 2024
Request for State Review of the Quad Cities HI-STORM Exemption Request Environmental Assessment
ML24102A2422024-04-10010 April 2024
NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments
ML24089A0102024-03-29029 March 2024
NRR E-mail Capture - Quad Cities Unit Nos. 1 and 2 - Alternative to Core Spray Pump Testing - Acceptance of Requested Licensing Action Relief Request Associated with the Sixth Inservice Testing Interval
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
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
ML23268A0022023-09-22022 September 2023
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0
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
ML23262A7432023-09-19019 September 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 Acceptance of Relief Request I5R-26
ML23186A1412023-07-0505 July 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-505
ML23186A1482023-07-0505 July 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt 10 CFR 50.69
ML23163A2292023-06-12012 June 2023
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1
ML23118A1652023-04-28028 April 2023
NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11
ML23083B9572023-03-24024 March 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-564
ML23055A0392023-02-24024 February 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Amendment to Adopt TSTF-416
ML23052A0772023-02-21021 February 2023
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance Timely Renewal Exemption Request
ML22357A0392022-12-23023 December 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of I6R-10 Related to Repair of Penetration N-11B
ML22354A2622022-12-20020 December 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI
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
ML22301A0902022-10-28028 October 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-301, Revision 2
ML22290A0662022-10-17017 October 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-04 Related to HPCI Drain Pot Solenoid Valve Testing
ML23079A0272022-10-0505 October 2022
Licensee Outline Submittal Email (Quad Cities, 2023)
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
ML22224A0222022-08-12012 August 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative I6R-09 Related to Use of Certain 2013 Edition ASME Code Requirements
ML22200A0782022-07-19019 July 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits
ML22206A0352022-07-13013 July 2022
NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection
ML22193A0412022-07-11011 July 2022
NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods
ML22187A1832022-07-0606 July 2022
NRR E-mail Capture - Completion of Activities Related to EPID L-2022-LLD-003, Quad Cities Potential NOED
ML22182A1992022-07-0101 July 2022
NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28
ML22164A8582022-06-13013 June 2022
NRR E-mail Capture - RAI Alternative RV-09, MSSVs
ML22164A8562022-06-13013 June 2022
NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves
ML22164A7852022-06-13013 June 2022
NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis
ML22101A0932022-04-11011 April 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Relief I6R-01 Related to SLC Nozzle Inner Radius Inspection
ML22077A4122022-03-18018 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-06 Related to MSSV Setpoint Testing
ML22076A0322022-03-17017 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-03 Related to PIV Leak Test Frequency
ML22075A0752022-03-16016 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-07 Related to MSIV Stroke Testing
ML22068A1512022-03-0909 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-10 Related to Code Case OMN-28, MOV Testing
ML22068A0552022-03-0909 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-09 Related to MSSV Testing
ML22068A0062022-03-0909 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-11 Related to OMN-28, Valve Position Verification
ML22067A2172022-03-0808 March 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative Related to MSRV Testing
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
2024-09-06
[Table view] |
Text
NRR-PMDAPEm Resource From: Purnell, Blake Sent: Wednesday, April 24, 2013 3:14 PM To: Ken.Nicely@exeloncorp.com Cc: Mozafari, Brenda; Bowen, Jeremy; Mitchel.Mathews@exeloncorp.com
Subject:
Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R Request for Additional Information OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 EXELON GENERATION COMPANY, LLC RELIEF REQUEST NOS. I5R-01, I5R-02, and I5R-06 DOCKET NUMBERS 50-254 and 50-265 TAC Nos. ME9668, ME9669, ME9670, ME9671, ME9676, and ME9677 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and management System (ADAMS) Accession No. ML12275A070), as supplemented by letter dated November 28, 2012 (ADAMS Accession No. ML12333A262), Exelon Generation Company, LLC (the licensee) submitted several proposed relief requests for the Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS). The NRC staff determined that the following additional information is necessary to complete the review of relief requests I5R-01, I5R-02, and I5R-06. To support the schedule for approval the response to this request is expected by May 24, 2013.
Based on the staffs review of relief request I5R-01:
- 1. Discuss in the relief request why the proposed alternative provides reasonable assurance of structural integrity or leak tightness of the subject components.
- 2. Discuss in the relief request how the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
- 3. Provide a technical basis as to why the ultrasonic testing is not required.
Based on the staffs review of relief request I5R-02:
- 1. Do the augmented inspection programs for intergranular stress corrosion cracking Category B-G (Generic Letter 88-01), service water integrity (Generic Letter 89-13), flow accelerated corrosion (Generic Letter 89-08), and high-energy line break (NRC Branch Technical Position MEB 3-1), as described in the initial QCNPS risk-informed ISI submittal dated November 30, 2000 (ADAMS Accession No. ML003776493), remain unaffected by the risk-informed ISI program developed for the fifth interval?
- 2. Are the inspection locations in the QCNPS risk-informed ISI programs that have been developed for the fifth 10-year interval the same locations as those in the fourth interval risk-informed ISI programs approved in the NRC staff's January 28, 2004, safety evaluation? If not, please summarize the changes to the program and what caused those changes.
- 3. If there are changes in the inspection locations for the QCNPS fifth 10-year interval risk-informed ISI programs please provide information for the fifth interval program regarding: examinations, system, components, degradation mechanisms, class, etc. The information expected should be similar to what 1
is in Tables 2, 3, 4, 5 and 6 of the original submittal of the risk-informed ISI program for the QCNPS third 10-year inservice inspection interval dated November 30, 2000.
Based on the staffs review of relief request I5R-06:
- 1. Confirm whether NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets.
- 2. Section 4.1 item 5 of the BWRVIP-100-A report, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds, states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 report, BWR Core Shroud Inspection and Flaw Evaluation Guidelines. Identify whether the core shroud welds and base materials will be exposed to a neutron fluence value greater than 1 X 1021 n/cm2 (E > 1 MeV) during the current ISI interval. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the NRC staff requests that the licensee address the following issue:
The inspection frequency and strategy that are specified in Section 3 of the BWRVIP-76 report require further evaluation taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report.
- 3. Dresden and Quad Cities (D/QC) Safety Evaluation Report, NUREG-1796, Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2, license renewal application (LRA) commitment #9 in Appendix A of NUREG-1796 states that the licensee should implement the staff approved aging management program for the steam dryers at the D/QC units. In July 2009, the BWRVIP issued a staff approved topical report BWRVIP-139-A, BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines. The NRC staff requests that the licensee confirm that it will comply with the guidelines addressed in the BWRVIP-139-A report as per LRA commitment #9 in NUREG-1796.
- 4. Consistent with the LRA commitment #9, with respect to the aging management program related to the top guide, the licensee should confirm that it will comply with the inspection guidelines addressed in the BWRVIP-26-A and BWRVIP-183 reports.
A copy of this email will be placed into ADAMS and made publicly available.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-1380 2
Hearing Identifier: NRR_PMDA Email Number: 675 Mail Envelope Properties (Blake.Purnell@nrc.gov20130424151400)
Subject:
Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R Request for Additional Information Sent Date: 4/24/2013 3:14:22 PM Received Date: 4/24/2013 3:14:00 PM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:
"Mozafari, Brenda" <Brenda.Mozafari@nrc.gov>
Tracking Status: None "Bowen, Jeremy" <Jeremy.Bowen@nrc.gov>
Tracking Status: None "Mitchel.Mathews@exeloncorp.com" <Mitchel.Mathews@exeloncorp.com>
Tracking Status: None "Ken.Nicely@exeloncorp.com" <Ken.Nicely@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 5627 4/24/2013 3:14:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
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