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| | issue date = 01/25/2013 | | | issue date = 01/25/2013 |
| | title = Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval | | | title = Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval |
| | author name = Gullott D M | | | author name = Gullott D |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:oon RS-13-04510 CFR 50.55a January 25, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 | | {{#Wiki_filter:1 oon RS-13-045 10 CFR 50.55a January 25, 2013 u.s. |
| | U.S. Nuclear Nuclear Regulatory Regulatory Commission Commission ATTN: |
| | A TIN: Document ControlControl Desk Washington,DC Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. Nos. DPR-29 DPR-29 and and DPR-30 DPR-30 NRC Docket Nos. 50-254 and 50-265 50-265 |
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| ==Subject:== | | ==Subject:== |
| Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval | | Additional Information Additional Information Regarding Regarding Relief Relief Request Request RV-06 RV-06 Associated Associatedwith with the theFifth Fifth Inservice Testing Interval Interval |
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| ==Reference:== | | ==Reference:== |
| Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.
| | from D. M. Gullott Letter from Gullott (Exelon Generation Company, Company, LLC) to U. U.S.S. NRC, "Submittal of "Submittal of Relief Relief Requests Associated with the Fifth Inservice Testing Interval," dated Interval," dated February February 15, 15, 2012 In the In the referenced letter, letter, Exelon Exelon Generation Generation Company, Company,LLC LLC (EGC) |
| S.NRC,"Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 In the referenced letter, Exelon Generation Company, LLC (EGC) requested NRC approval of relief requests associated with the fifth 10-year inservice testing (IST) program interval for Quad Cities Nuclear Power Station (QCNPS). EGC's submittal included relief request RV-06, which is related to main steam safety valve testing. In an email dated January 16, 2013, the NRC requested additional information that is needed to complete the review of relief request RV-06. | | (EGC) requested requestedNRC NRCapproval approvalofof relief requests relief requests associated associatedwith withthe thefifth fifth 10-year 10-yearinservice inservice testing testing(IST) |
| In response to this request, EGC is providing the attached information. | | (1ST) program programinterval interval for for Quad Quad Cities Nuclear Power Station (QCNPS). |
| There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803. | | Cities (QCNPS). EGC's EGC'ssubmittal submittal included included relief relief request requestRV-06, RV-06, which which isis related to related to main main steam steam safety valve valve testing. |
| Respectfully, David M. Gullott Manager - Licensing | | testing. In In an email dated January January 16,16, 2013, 2013, thethe NRC NRC requested requested additional additional information needed to information that is needed to complete complete thethereview review ofof relief relief request request RV-06. |
| | RV-06. |
| | In response In response toto this this request, request, EGC EGCisisproviding providing the the attached attachedinformation. |
| | information. |
| | There are no no regulatory regulatory commitments contained in this letter. letter. Should Should youyou have have any anyquestions questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803. 657-2803. |
| | Respectfully, |
| | ~0~ |
| | David M. Gullott Manager -- Licensing Licensing |
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| ==Attachment:== | | ==Attachment:== |
| Response to Request for Additional Information cc:NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station 1 RS-13-045 January 25, 2013 u.s. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 10 CFR 50.55a
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| ==Subject:== | | ==Attachment:== |
| Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval
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| ==Reference:== | | ===Response=== |
| | ResponsetotoRequest Request forforAdditional AdditionalInformation Information cc: NRC Regional Administrator, Administrator, Region III III NRC Senior Resident Inspector, Inspector, Quad Quad Cities Cities Nuclear Nuclear Power Power Station Station |
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| Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 In the referenced letter, Exelon Generation Company, LLC (EGC) requested NRC approval of relief requests associated with the fifth 10-year inservice testing (1ST) program interval for Quad Cities Nuclear Power Station (QCNPS). EGC's submittal included relief request RV-06, which is related to main steam safety valve testing. In an email dated January 16, 2013, the NRC requested additional information that is needed to complete the review of relief request RV-06. In response to this request, EGC is providing the attached information.
| | ATTACHMENT Response to Request for for Additional Additional Information Information NRC Request Request RV-06 states, Request RV-06 states, inin Section Section 5, 5, "If "If more than one safety safety valve valve fails, the sample sample expansion expansion criteria of Appendix Appendix I,I, 1350(c) will willbebe implemented." Section1-1350 implemented." Section 1-1350 of of Mandatory Mandatory Appendix Appendix II isis for Class 2 and for and 33 pressure pressurerelief relief valves. |
| There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.
| | valves. Section Section1-1320 1-1320isisfor for Class Class11pressure pressurerelief reliefvalves. |
| Respectfully, David M. Gullott Manager -Licensing
| | valves. |
| | | : Also, Also, Request RV-05RV-05 isis requesting requesting thethe use use ofof Code Code Case Case OMN-17. |
| ==Attachment:==
| | OMN-17. PleasePlease discuss discusswhether, whether, ifif RV-05 RV-05 is is approved, Code Code Case CaseOMN-17, OMN-17,primarily primarily Paragraph Paragraph(1)(c)(2), |
| | (1)(c)(2), would would also alsoapply applyto to Request RV-06. |
| | Request RV-06. |
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| Response to Request for Additional Information cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station ATTACHMENT Response to Request for Additional Information NRC Request Request RV-06 states, in Section 5, "If more than one safety valve fails, the sample expansion criteria of Appendix I, 1350(c) will be implemented." Section 1-1350 of Mandatory Appendix I is for Class 2 and 3 pressure relief valves. Section 1-1320 is for Class 1 pressure relief valves. | | ===Response=== |
| Also, Request RV-05 is requesting the use of Code Case OMN-17. Please discuss whether, if RV-05 is approved, Code Case OMN-17, primarily Paragraph (1)(c)(2), would also apply to Request RV-06.
| | The original original Relief Relief Request Request RV-06 transmitted in in Reference 11 contained contained an anincorrect incorrectcode code reference (i.e., |
| Response The original Relief Request RV-06 transmitted in Reference 1 contained an incorrect code reference (i.e., 1-1350 should have been 1-1320, which refers to Class 1 relief valves). This error was corrected in a revised relief request that was submitted to the NRC in Reference 2.
| | (Le., 1-1350 1-1350 should should have been been 1-1320, 1-1320, which which refers to Class 11 relief relief valves). This This error error was corrected corrected in in aa revised revised relief relief request request thatthat was wassubmitted submittedto to the theNRC NRC in in Reference Reference2. 2. |
| Relief Request RV-05 requests relief from test frequency requirements for Class 1 pressure relief valves, based on the guidance of ASME Code Case OMN-1 7. Upon approval of RV-05, Exelon Generation Company, LLC would also apply Code Case OMN-17, Paragraph (1)(c)(2), to Request RV-06. It is noted that that the requirements of Code Case OMN-17, Paragraph (1)(c)(2), and ASME OM Code, Appendix I, I-1320(c)(2) are functionally equivalent. | | Relief Relief Request RV-05 requests relief Request RV-05 relief from from test test frequency frequency requirements for for Class pressure Class 1 pressure relief relief valves, valves, based on on the the guidance guidanceof ofASME ASME CodeCode Case CaseOMN-1 OMN-17. Upon approval |
| References 1.Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 2.Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval," dated September 13, 2012 Page 1 ATTACHMENT Response to Request for Additional Information NRC Request Request RV-06 states, in Section 5, "If more than one safety valve fails, the sample expansion criteria of Appendix I, 1350(c) will be implemented." Section 1-1350 of Mandatory Appendix I is for Class 2 and 3 pressure relief valves. Section 1-1320 is for Class 1 pressure relief valves. Also, Request RV-05 is requesting the use of Code Case OMN-17. Please discuss whether, if RV-05 is approved, Code Case OMN-17, primarily Paragraph (1)(c)(2), would also apply to Request RV-06. Response The original Relief Request RV-06 transmitted in Reference 1 contained an incorrect code reference (Le., 1-1350 should have been 1-1320, which refers to Class 1 relief valves). This error was corrected in a revised relief request that was submitted to the NRC in Reference
| | : 7. Upon approvalof of RV-05, RV-05, Exelon Exelon Generation Company, LLC LLC would would alsoalso apply apply Code Code Case OMN-17, Paragraph Case OMN-17, Paragraph(1)(c)(2), |
| : 2. Relief Request RV-05 requests relief from test frequency requirements for Class 1 pressure relief valves, based on the guidance of ASME Code Case OMN-17. Upon approval of RV-05, Exelon Generation Company, LLC would also apply Code Case OMN-17, Paragraph (1)(c)(2), to Request RV-06. It is noted that that the requirements of Code Case OMN-17, Paragraph (1)(c)(2), and ASME OM Code, Appendix I, 1-1320(c)(2) are functionally equivalent.
| | (1)(c)(2), |
| | to Request Request RV-06. |
| | RV-06. ItIt isis noted noted that that that that the the requirements requirements of of Code Code Case CaseOMN-17, OMN-17, Paragraph Paragraph (1)(c)(2), |
| | (1)(c)(2), and ASME OM Code, Appendix Appendix I,I, I-1320(c)(2) 1-1320(c)(2) are arefunctionally functionally equivalent. |
| | equivalent. |
| References | | References |
| : 1. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated February 15, 2012 2. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval," dated September 13,2012 Page 1}} | | : 1. Letter Letter from from D. D. M. |
| | M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) to U.S. NRC, NRC, "Submittal "Submittal of Requests Associated Relief Requests Associatedwith withthe theFifth FifthInservice InserviceTesting TestingInterval," |
| | Interval," dated dated February February 15, 15, 2012 Letter from |
| | : 2. Letter from D.D. M. |
| | M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) LLC) to U.S. NRC, "Response to Request for Request for Additional InformationRegarding Additional Information RegardingRelief ReliefRequests Requests Associated Associated with with the Fifth Fifth Inservice Testing Interval," dated September Interval," dated September 13,2012 13, 2012 Page Page 11}} |
Letter Sequence Request |
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MONTHYEARRS-12-026, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval2012-02-15015 February 2012
Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval
Project stage: Request
ML12240A0562012-09-12012 September 2012
Request for Additional Information Related to Relief Request RV-01, RV-03, RV-05, and RV-06
Project stage: RAI
RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval2012-09-13013 September 2012
Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval
Project stage: Response to RAI
RS-12-179, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval2012-10-0808 October 2012
Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval
Project stage: Response to RAI
ML12325B1122012-12-0303 December 2012
Request for Additional Information Related to Relief Request, RV-04, from ASME OM Code ISTC-5150, Solenoid-Operated Valves Associated with the Fifth Inservice Testing
Project stage: RAI
RS-12-210, Additional Information Regarding Relief Request RV-04 Associated with the Fifth Inservice Testing Interval2012-12-0707 December 2012
Additional Information Regarding Relief Request RV-04 Associated with the Fifth Inservice Testing Interval
Project stage: Request
ML13018A1882013-01-16016 January 2013
NRR E-mail Capture - Quad Cities RAI for Relief Request RV-06, (TAC Nos. ME7992 & ME7993)
Project stage: RAI
RS-13-045, Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval2013-01-25025 January 2013
Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval
Project stage: Request
ML13042A3482013-02-14014 February 2013
IST Relief Request ME7981-88 and ME7990-95
Project stage: Other
2012-09-12
[Table View] |
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Category:Letter type:RS
MONTHYEARRS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024
Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023
Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023
Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days
RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023
Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023
Sixth Ten-Year Interval Inservice Testing Program
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023
Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023
10 CFR 50.46 Annual Report
RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023
Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell
RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023
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RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023
Application to Adopt TSTF-564, Safety Limit MCPR
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023
Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location
RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023
Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
RS-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023
Request for Exemption from 10 CFR 2.109(b)
RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023
Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves
RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022
Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022
Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval
RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022
Response to Request for Additional Information License Amendments Related to Fuel Storage
RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022
Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval
RS-22-108, Response to 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 Storage2022-10-0505 October 2022
Response to 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
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022
Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times
RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022
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RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022
Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel
RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022
Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval
RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022
Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28
RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022
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RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022
Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies
RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022
Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves
RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022
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RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022
Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022
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RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022
CFR50.46 Annual Report
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022
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RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022
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RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022
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RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022
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RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022
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RS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022
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RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
2024-01-03
[Table view] |
Text
1 oon RS-13-045 10 CFR 50.55a January 25, 2013 u.s.
U.S. Nuclear Nuclear Regulatory Regulatory Commission Commission ATTN:
A TIN: Document ControlControl Desk Washington,DC Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. Nos. DPR-29 DPR-29 and and DPR-30 DPR-30 NRC Docket Nos. 50-254 and 50-265 50-265
Subject:
Additional Information Additional Information Regarding Regarding Relief Relief Request Request RV-06 RV-06 Associated Associatedwith with the theFifth Fifth Inservice Testing Interval Interval
Reference:
from D. M. Gullott Letter from Gullott (Exelon Generation Company, Company, LLC) to U. U.S.S. NRC, "Submittal of "Submittal of Relief Relief Requests Associated with the Fifth Inservice Testing Interval," dated Interval," dated February February 15, 15, 2012 In the In the referenced letter, letter, Exelon Exelon Generation Generation Company, Company,LLC LLC (EGC)
(EGC) requested requestedNRC NRCapproval approvalofof relief requests relief requests associated associatedwith withthe thefifth fifth 10-year 10-yearinservice inservice testing testing(IST)
(1ST) program programinterval interval for for Quad Quad Cities Nuclear Power Station (QCNPS).
Cities (QCNPS). EGC's EGC'ssubmittal submittal included included relief relief request requestRV-06, RV-06, which which isis related to related to main main steam steam safety valve valve testing.
testing. In In an email dated January January 16,16, 2013, 2013, thethe NRC NRC requested requested additional additional information needed to information that is needed to complete complete thethereview review ofof relief relief request request RV-06.
RV-06.
In response In response toto this this request, request, EGC EGCisisproviding providing the the attached attachedinformation.
information.
There are no no regulatory regulatory commitments contained in this letter. letter. Should Should youyou have have any anyquestions questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803. 657-2803.
Respectfully,
~0~
David M. Gullott Manager -- Licensing Licensing
Attachment:
Attachment:
Response
ResponsetotoRequest Request forforAdditional AdditionalInformation Information cc: NRC Regional Administrator, Administrator, Region III III NRC Senior Resident Inspector, Inspector, Quad Quad Cities Cities Nuclear Nuclear Power Power Station Station
ATTACHMENT Response to Request for for Additional Additional Information Information NRC Request Request RV-06 states, Request RV-06 states, inin Section Section 5, 5, "If "If more than one safety safety valve valve fails, the sample sample expansion expansion criteria of Appendix Appendix I,I, 1350(c) will willbebe implemented." Section1-1350 implemented." Section 1-1350 of of Mandatory Mandatory Appendix Appendix II isis for Class 2 and for and 33 pressure pressurerelief relief valves.
valves. Section Section1-1320 1-1320isisfor for Class Class11pressure pressurerelief reliefvalves.
valves.
- Also, Also, Request RV-05RV-05 isis requesting requesting thethe use use ofof Code Code Case Case OMN-17.
OMN-17. PleasePlease discuss discusswhether, whether, ifif RV-05 RV-05 is is approved, Code Code Case CaseOMN-17, OMN-17,primarily primarily Paragraph Paragraph(1)(c)(2),
(1)(c)(2), would would also alsoapply applyto to Request RV-06.
Request RV-06.
Response
The original original Relief Relief Request Request RV-06 transmitted in in Reference 11 contained contained an anincorrect incorrectcode code reference (i.e.,
(Le., 1-1350 1-1350 should should have been been 1-1320, 1-1320, which which refers to Class 11 relief relief valves). This This error error was corrected corrected in in aa revised revised relief relief request request thatthat was wassubmitted submittedto to the theNRC NRC in in Reference Reference2. 2.
Relief Relief Request RV-05 requests relief Request RV-05 relief from from test test frequency frequency requirements for for Class pressure Class 1 pressure relief relief valves, valves, based on on the the guidance guidanceof ofASME ASME CodeCode Case CaseOMN-1 OMN-17. Upon approval
- 7. Upon approvalof of RV-05, RV-05, Exelon Exelon Generation Company, LLC LLC would would alsoalso apply apply Code Code Case OMN-17, Paragraph Case OMN-17, Paragraph(1)(c)(2),
(1)(c)(2),
to Request Request RV-06.
RV-06. ItIt isis noted noted that that that that the the requirements requirements of of Code Code Case CaseOMN-17, OMN-17, Paragraph Paragraph (1)(c)(2),
(1)(c)(2), and ASME OM Code, Appendix Appendix I,I, I-1320(c)(2) 1-1320(c)(2) are arefunctionally functionally equivalent.
equivalent.
References
- 1. Letter Letter from from D. D. M.
M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) to U.S. NRC, NRC, "Submittal "Submittal of Requests Associated Relief Requests Associatedwith withthe theFifth FifthInservice InserviceTesting TestingInterval,"
Interval," dated dated February February 15, 15, 2012 Letter from
- 2. Letter from D.D. M.
M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) LLC) to U.S. NRC, "Response to Request for Request for Additional InformationRegarding Additional Information RegardingRelief ReliefRequests Requests Associated Associated with with the Fifth Fifth Inservice Testing Interval," dated September Interval," dated September 13,2012 13, 2012 Page Page 11
