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MONTHYEARRS-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 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 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 2013-01-24
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Category:Letter type:RS
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to 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, and TSTF-5912024-10-21021 October 2024 Supplement to 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, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 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 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 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-080, 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-003, 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram 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 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-101, 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-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 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-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists 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 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 for V 2024-07-31
[Table view] |
Text
1 RS-12-202 10 10 CFR 50.55a November 19, 2012 November U. S. Nuclear Nuclear Regulatory Regulatory Commission Commission ATTN: Document Control Control Desk Washington,D.C.
Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Dresden Units 2 and 3 Station, Units Renewed Facility FacilityOperating License Nos. DPR Operating License DPR 19 and DPR-25 NRC Docket NRC Docket Nos.
Nos. 50-237 50-237 and 50-249
Subject:
Supplement to the Dresden Nuclear NuclearPowerPowerStation StationFifth FifthInservice InserviceInspection Inspection Interval Relief Request Interval Request 15R-01 15R-01
Reference:
from D.
Letter from D. M.
M. Gullott Gullott(Exelon (Exelon Generation Generation Company, Company, LLC LLC (EGC))
(EGC>> to to U.
U. S.
S.
NRC, "Dresden NuclearNuclear Power Power Station, Station,UnitsUnits22andand3,3,Fifth FifthInterval Inservice Intervallnservice Inspection Program Inspection Program Plan Plan and and Relief Relief Requests,"
Requests," dateddated September 28, 2012 28,2012 In the In the referenced letter, letter, EGC EGC submitted relief relief requests associated associatedwith withthe thefifth fifth inservice inservice inspection (ISI) interval for Dresden Nuclear Power Station (lSI) interval for Dresden Nuclear Power Station (DNPS), Units 2 (DNPS), Units 2 and 3. Upon Uponfurther further review of review of Relief Relief Request Request 15R-01, 15R-01, itit became became apparent that that 10 10 CFR CFR 50.55a 50.55a (a)(3)(ii)
(a)(3)(ii) is the appropriate relief appropriate reliefcriterion criterionforforthis thisrequest.
request.Therefore, Therefore,EGC EGCrequests requests toto supersede supersede the theversion version of 15R-01 15R-01 in in the referenced letterletter with with the version version in in the the attachment attachmenttotothisthisletter letterininitsitsentirety.
entirety.
EGC EGC continues to request approval approval of of this this relief relief request request by by September September 28, 2013, 2013, to to support support examination of components components during during the DNPS, DNPS, UnitUnit 22 Fall Fall 2013 2013refueling refueling outage outagewhichwhichfallsfalls within within the fifth 10-year ISI interval.
fifth 10-year lSI interval.
There There are are nonoregulatory regulatorycommitments commitmentscontained containedwithin within this this letter.
letter.
Should you have have any anyquestions questionsconcerning concerningthis thisletter, letter,please pleasecontact contactMr.Mr.Mitchel MitchelA. A.Mathews Mathewsatat (630) 657-2819.
Patrick R.R. Simpson Simpson Manager Manager - Licensing Licensing Exelon Generation Company, LLC LLC
Attachment:
Attachment:
10 CFR CFR 50.55a 50.55aRequest RequestNumber Number15R-01, 15R-01,Revision Revision 11
ATTACHMENT 10 CFR CFR 50.55a SO.SSaRequest RequestNumber Number15R -01, Revision ISR-01, Revision 11 Proposed Alternative Alternative In In Accordance Accordance with with 1010 CFR CFR 50.55a(a)(3)(ii)
SO.SSa(a)(3}(ii}
--Hardship
--Hardship or or Unusual Unusual Difficulty Difficulty without without Compensating Compensating Increase Increase in in Level of Quality and Safety-- Safety--
- 1. ASME ASME Code Code Component(s)
Component(s)Affected: Affected:
Class:
Code Class: 11
Reference:
IWB-2500, IWB-2500, Table Table IWB-2500-1 IWB-2500-1 Category:
Examination Category: B-D Item Number: B3.100 83.100
Description:
Inspection of Standby Standby Liquid Liquid Control Control Nozzle Nozzle Inner InnerRadius Radius Component Number:
Component Number: Unit 2: N12-1 N12-1 Unit 3: N12-1 N12-1 Number:
Drawing Number: Unit 2:
2: ISI-128, ISI-128, Sheet Sheet 33 Unit 3: ISI-125, Sheet 3: ISI-125, Sheet 33 Applicable
- 2. Code Edition Applicable Code and EditionAddenda:
and Addenda:
Dresden Nuclear The Dresden NuclearPowerPowerStation Station(DNPS),
(DNPS), UnitsUnits 22andand33Inservice InserviceInspection Inspection Program is based basedon onthe theAmerican AmericanSociety SocietyofofMechanical MechanicalEngineers Engineers(ASME) (ASME) BoilerBoiler and Pressure Vessel Pressure Vessel(B&PV)(B&PV) Code, Code, Section Section XI, XI, 2007 Edition Edition through the 2008 Addenda.
- 3. Applicable Applicable Code Code Requirement:
IWB-2500 IWB-2500states states that that components components shall shall be examined and tested tested as asspecified specified in in Table IWB-2500-1.
Table IWB-2500-1.
Table IWB-2500-1 IWB-2500-1 requires aa volumetricvolumetric examination to be be performed performed on on the theinner innerradius radius section of all all reactor reactor pressure vessel nozzles pressure vessel nozzleseach eachinspection inspectioninterval.
interval.
Reason 4. forReason Request: for Request:
Pursuant Pursuant to 10 10 CFR CFR 50.55a(a)(3)(ii),
50.55a(a)(3)(ii), reliefrelief isis requested requested on the the basis basisthat thatconformance conformancewith with the Code requirements requirements impose imposehardship hardshipwithout without aa compensating compensatingincrease increaseininthethelevel levelofof quality andand safety.
StandbyLiquid The Standby Liquid Control Control (SBLC)
(SBLC) nozzle, as as shown shownininFigure Figure15R-01.1, 15R-01.1, isis designed designedwith with an integral integral socket socket to to which which the the boron boron injection injection piping is fillet filletwelded.
welded. The SBLC nozzle is located near near the the bottom bottom of of the the vessel vesselin in an anarea areawhich whichisisinaccessible inaccessiblefor forultrasonic ultrasonic examinations from from thethe inside inside ofof the the vessel. Therefore, ultrasonic vessel. Therefore, ultrasonic examinations would need to be performed performed from from the outside diameterdiameter of of the vessel.
vessel. As Asshown shownininFigure Figure15R-01.1, 15R-01.1, thethe ultrasonic scan would need ultrasonic need to to travel travel through the full full thickness thickness of of the the vessel into a complex cladding/socket configuration.
configuration. These Thesegeometric geometricand andmaterial materialreflectors reflectorsinherent inherentin in the the design prevent prevent aa meaningful meaningful examination examination from from being performed on the inner inner radius of of the SBLC nozzle.
In In addition, addition,the the inner inner radius radius socket attaches attachesto topiping piping which which injects injects boron boron atat locations locations farfar removed from from thethe nozzle. Therefore, Therefore, the theSBLC SBLC nozzle nozzle inner inner radius radius isis not not subjected subjectedto to turbulent mixing mixingconditions conditionsthat thatareare aa concern concern at other nozzles.
Page 1 of 3
ATTACHMENT 50.55a Request 10 CFR SO.SSa Request Number Number15R-01, ISR-01, Revision Revision 11 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
Proposed SO.SSa(a}(3}(ii}
--Hardship or Unusual Difficulty without Compensating Increase in in Level Level of Quality and Safety--
Compliance with with the the applicable applicable Code Code requirements would require an ultrasonic ultrasonic examination examination to be performed performed on on the the outside outside diameter diameter of ofthe thereactor reactorpressure pressure vessel. Geometric and vessel. Geometric material material reflectors reflectors would would prevent prevent a meaningful examination, resulting resulting in inaccurate inaccurate data.
data.
Based on this, this, the Code requirements impose hardship without without aa compensating increase increase in in the level of quality quality and and safety inin accordance accordance with with 10 10 CFR CFR 50.55a(a)(3)(ii).
50.55a(a)(3)(ii).
ProposedS.
5.Alternate Proposedand Basis Alternate for for and Basis Use:Use:
As an alternate examination, Exelon Generation Company, LLC LLC will willperform perform aa VT-2 visual examination examination of of the the subject subject nozzles DNPS, Units nozzles at DNPS, Units 22 and and 33each eachrefueling refuelingoutage outageinin conjunction conjunctionwith withthe theClass Class 11 System System Leakage Test. Test.
- 6. Duration of Proposed Alternative:
Alternative:
Relief is requested requested forfor the Fifth Fifth Ten-Year Ten-Year Inspection Interval Intervalfor forDresden Dresden Nuclear Nuclear Power Station Units Units 2 and 3.
7.
Precedents:
- 7. Precedents:
DNPS, Units Units 22 and and 33fourth fourth inspection inspection interval interval Relief Relief Request Request14R14R-01 was authorized
-01 was authorized in in an NRC NRC safety evaluation evaluation (SE)
(SE) dated September 4, 2003. The Thefifth fifth inspection interval interval relief (Le., 15R-01, relief request (i.e., 15R-01, Revision 1) 1) utilizes utilizes aasimilar similar approach approach thatthat was waspreviously previously approved.
Quad Cities Cities Nuclear Nuclear Power Power Station, Station, Units Units 11and and22fourth fourth inspection inspectioninterval intervalRelief Relief 14R-01 was Request 14R-01 was authorized authorized in in an an NRC NRC SE SE dated January 28, dated January 28, 2004.
2004.
Page 22 of of33
ATTACHMENT ATTACHMENT 10 CFR CFR 50.55a 50.55a Request RequestNumber Number15R-01, 15R-01,Revision Revision11 Proposed Alternative In In Accordance Accordance withwith 1010 CFR CFR 50.55a(a)(3)(ii) 50.55a(a}(3}(ii}
--Hardship or or Unusual Unusual Difficulty Difficulty without without Compensating Compensating Increase in Level ofof Quality Quality andand Safety--
Safety--
Vessel Vessel (Mn-Mo)
(Mn-MO)\
- 1. D. Cladding I.D.
Safe-End (Stainless Steel)
Steel) Nozzle (Stainless Pipe (Mn-Mo)
(Stainless Steel) 1 15/16" 1/8" Min 3/4" R Min 6 3/8" FIGURE 15R-01.1: Two (2) Inch FIGURE 15R-01.1: Inch Standby Standby Liquid Liquid Control Control Nozzle Nozzle Page 3 of3of 3