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| | issue date = 03/29/2010 | | | issue date = 03/29/2010 |
| | title = License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process | | | title = License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process |
| | author name = Simpson P R | | | author name = Simpson P |
| | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:RS-10-052 March 29, 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NFIC Docket Nos. 50-456 and 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NFIC Docket Nos. 50-454 and STN 50-455 10 CFR 50.90 | | {{#Wiki_filter:10 CFR 50.90 RS-10-052 March 29, 2010 U . S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos . NPF-72 and NPF-77 NFIC Docket Nos. 50-456 and 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos . NPF-37 and NPF-66 NFIC Docket Nos . 50-454 and STN 50-455 Subject : License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process In accordance with 10 CIFIR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), is requesting an amendment to Appendix A, "Technical Specifications" (TS) of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . The proposed amendment would revise Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program," by extending the reactor coolant pump (RCP) motor flywheel inspection interval from the currently approved 10-year inspection interval to an interval not to exceed 20 years . |
| | The changes are consistent with the NFIC-approved Technical Specification Task Force (TSTF) |
| | Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-15666-A evaluation . The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLIIP) . |
| | The proposed changes have been evaluated using the risk-informed processes described in Regulatory Guide (RG) 1 .174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Revision 1, dated November 2002. The evaluation concluded that WCAP-115666A "Extension of Reactor Coolant Pump Motor Flywheel Examination," is applicable to Braidwood and Byron, with the exception of two RCP motor/flywheel combinations that were not included in the WCAP- 1 5666-A evaluation. |
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| ==Subject:==
| | U. S. Nuclear Regulatory Commission March 29, 2010 Page 2 The attached request is subdivided as shown below. |
| License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process In accordance with 10 CIFIR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), is requesting an amendment to Appendix A, "Technical Specifications" (TS) of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron). The proposed amendment would revise Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program," by extending the reactor coolant pump (RCP) motor flywheel inspection interval from the currently approved 10-year inspection interval to an interval not to exceed 20 years. The changes are consistent with the NFIC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-15666-A evaluation. The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLIIP). The proposed changes have been evaluated using the risk-informed processes described in Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Revision 1, dated November 2002. The evaluation concluded that WCAP-115666A "Extension of Reactor Coolant Pump Motor Flywheel Examination," is applicable to Braidwood and Byron, with the exception of two RCP motor/flywheel combinations that were not included in the WCAP- 1 5666-A evaluation.
| | Attachment 1 provides an evaluation of the proposed changes. |
| U. S. Nuclear Regulatory Commission March 29, 2010 Page 2 The attached request is subdivided as shown below. Attachment 1 provides an evaluation of the proposed changes. Attachments 2 and 3 include the marked-up TS pages with the proposed changes indicated for the Braidwood and Byron TSs, respectively - These proposed changes have been reviewed by the Braidwood and Byron Plant Operations Review Committees and approved by the respective Nuclear Safety Review Boards in accordance with the requirements of the EGC Quality Assurance Program. EGC requests approval of the proposed amendment by March 29, 2011. Once approved, the amendment will be implemented within 60 days. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official. This submittal does not contain any regulatory commitments. Should you have any questions concerning this letter, please contact Ms. Lisa Schofield at (630) 65T2815. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of March 2010. Respectfully, Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC Attachments | | Attachments 2 and 3 include the marked-up TS pages with the proposed changes indicated for the Braidwood and Byron TSs, respectively - |
| : 1. Evaluation of Proposed Change 2. Proposed Mark-up of Braidwood Technical Specification 5.5 3. Proposed Mark-up of Byron Technical Specification
| | These proposed changes have been reviewed by the Braidwood and Byron Plant Operations Review Committees and approved by the respective Nuclear Safety Review Boards in accordance with the requirements of the EGC Quality Assurance Program . |
| | EGC requests approval of the proposed amendment by March 29, 2011 . Once approved, the amendment will be implemented within 60 days . |
| | In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," |
| | paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official . |
| | This submittal does not contain any regulatory commitments. Should you have any questions concerning this letter, please contact Ms. Lisa Schofield at (630) 65T2815 . |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of March 2010. |
| | Respectfully, Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC Attachments: |
| | 1 . Evaluation of Proposed Change |
| | : 2. Proposed Mark-up of Braidwood Technical Specification 5.5 |
| | : 3. Proposed Mark-up of Byron Technical Specification 5 .5 |
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| ===5.5 ATTACHMENT===
| | ATTACHMENT 1 Evaluation of Proposed Change 1 .0 INTRODUCTION 2 .0 DESCRIPTION OF PROPOSED AMENDMENT 3 .0 BACKGROUND 4.0 REGULATORY REQUIREMENTS AND GUIDANCE 5 .0 TECHNICAL ANALYSIS 5 .1 Applicability of TSTF-421 and Published NRC Safety Evaluation 5.2 Variation from TSTF-421 and Published NRC Safety Evaluation |
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| 1 Evaluation of Proposed Change
| | ==6.0 REGULATORY ANALYSIS== |
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| ==1.0 INTRODUCTION==
| | 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION 8 .0 ENVIRONMENTAL EVALUATION 9.0 PRECEDENT |
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| ==2.0 DESCRIPTION== | | ==10.0 REFERENCES== |
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| OF PROPOSED AMENDMENT
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| ==3.0 BACKGROUND==
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| ===4.0 REGULATORY===
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| REQUIREMENTS AND GUIDANCE 5.0 TECHNICAL ANALYSIS 5.1 Applicability of TSTF-421 and Published NRC Safety Evaluation
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| ===5.2 Variation===
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| from TSTF-421 and Published NRC Safety Evaluation
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| ===6.0 REGULATORY===
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| ANALYSIS 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION
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| ===8.0 ENVIRONMENTAL===
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| EVALUATION
| | ATTACHMENT 1 Evaluation of Proposed Change 1 .0 INTRODUCTION The proposed amendment would revise Appendix A, "Technical Specifications" (TS) 5 .5-7, "Reactor Coolant Pump Flywheel Inspection Program," of Facility Operating License Nos . |
| | NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . The changes are consistent with the NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-1 5666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-1 5666-A evaluation . The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLI I P) . |
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| ===9.0 PRECEDENT=== | | ==2.0 DESCRIPTION== |
| | OF PROPOSED AMENDMENT Braidwood and Byron TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program," |
| | currently state, in part, the following: |
| | In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place LIT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section X1 . |
| | Consistent with the NFIC-approved TSTF-421 and site-specific equipment, the proposed TS change revises TS 5.5.7 as follows: |
| | For reactor coolant pump motor serial numbers 4S88P961 and 1 S88P9Q in Heu of Regulatory Position c.4.b(l) and cA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI . |
| | For all other reactor coolant pump motors, in lieu of Regulatory Position cA.b(l) and cAb(o, a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years . |
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| ==10.0 REFERENCES==
| | ATTACHMENT 1 Evaluation of Proposed Change |
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| ==1.0 INTRODUCTION== | | ==3.0 BACKGROUND== |
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| ATTACHMENT 1 Evaluation of Proposed Change The proposed amendment would revise Appendix A, "Technical Specifications" (TS) 5.5-7, "Reactor Coolant Pump Flywheel Inspection Program," of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron). The changes are consistent with the NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-1 5666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-1 5666-A evaluation. The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLI I P).
| | The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 375901 TSTF4421, WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC safety evaluation (SE) dated May 5, 2003 . |
| | 4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), |
| | TSTF-421, WCAP-1 5666-A and the related NRC SE dated May 5, 2003. |
| | 5 .0 TECHNICAL ANALYSIS 5.1 Applicability Of TST4421 and Published NRC Safety Evaluation Exelon Generation Company, LLC (EGC) has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP for the Braidwood and Byron reactor coolant pump (RCP) flywheels specified in WCAP- 1 5666-A, Table 2-2, Category 3 . This verification of applicability included a review of the NRC's model SE, as well as the information provided to support TSTF-421 (including WCAP-15666-A and the related SE dated May 5, 2003) . EGC has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC are applicable to Braidwood and Byron, and justify the incorporation of the proposed changes to the respective TS for the Braidwood and Byron RCP flywheels specified in WCAP- 1 5666-A. |
| | Variation from TSTF-421 and Published NRC Safety Evaluation The proposed change maintains the existing examination requirements for two alternate RCP flywheels that were not included in the WCAP-1 5666-A evaluation (i .e ., as specified in Table 2-2, Category 3 of WCAP-15666-A). These two alternate RCP flywheels, as integral elements of RCP motors, were originally designed and built for the Marble Hill Nuclear Generating Station (Marble Hill), the construction of which was cancelled in the early 1980s. |
| | EGC procured two original Marble Hill RCP motor/flywheel combinations, and subsequently installed one RCP motor/flywheel combination in Byron Unit 1 during the spring 2005 Unit 1 refueling outage (i.e., serial number 1S88P961). The second is currently stored as a spare RCP motor/flywheel combination at Braidwood (i.e ., serial number -AS88P961 I While these two RCP motor/flywheel combinations can be utilized at either Braidwood or Byron, the Marble Hill flywheels are not interchangeable with the Braidwood and Byron RCP flywheels that are specified in WCAP- 1 5666-A. |
| | Since neither the installed Marble Hill RCP motor/flywheel nor the spare were included in the 2001 WCAP-1 5666-A evaluation, the conclusion of the WCAP (i.e., justification for an extended RCP flywheel examination interval) is not applicable for these two RCP flywheels. |
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| ==2.0 DESCRIPTION==
| | ATTACHMENT 1 Evaluation of Proposed Change Therefore, the proposed TS provides separate examination requirements for the Marble Hill RCP flywheels and the WCAP-evaluated RCP flywheels. |
| | EGC has concluded that the proposed RCP flywheel examination requirements (i.e ., |
| | differentiated requirements for the WCAP-evaluated RCP flywheels and the alternate Marble with Hill RCP flywheels) are consistent the intent of TSTF-421, Revision 0, and with the NRC's model safety evaluation dated June 24, 2003, in that the relaxed theexamination interval is only applicable to the RCP flywheels that were evaluated as pal of WCAP. |
| | 6 .0 REGULATORY ANALYSIS A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666-A, and the associated SE. |
| | 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION EGC has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the proposed determination presented in the notice is applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(x) . |
| | 8.0 ENVIRONMENTAL EVALUATION EGC has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the findings presented in that evaluation are applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the evaluation is hereby incorporated by reference for this application . |
| | 9 .0 PRECEDENT This application is being made in accordance with the CLIIP, with the exception of a site-specific variation . This variation ensures that the proposed TS are consistent with the intent of TSTF-421, Revision 0, the NRC's model safety evaluation dated June 24, 2003, and the existing equipment at Braidwood and Byron . |
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| OF PROPOSED AMENDMENT Braidwood and Byron TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program," currently state, in part, the following: In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place LIT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section X1. Consistent with the NFIC-approved TSTF-421 and site-specific equipment, the proposed TS change revises TS 5.5.7 as follows: For reactor coolant pump motor serial numbers 4S88P961 and 1 S88P9Q in Heu of Regulatory Position c.4.b(l) and cA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI. For all other reactor coolant pump motors, in lieu of Regulatory Position cA.b(l) and cAb(o, a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years.
| | ==10.0 REFERENCES== |
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| ==3.0 BACKGROUND==
| | 1 . Federal Register Notice : Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422) |
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| ATTACHMENT 1 Evaluation of Proposed Change The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 375901 TSTF 4 421, WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC safety evaluation (SE) dated May 5, 2003. 4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-1 5666-A and the related NRC SE dated May 5, 2003. 5.0 TECHNICAL ANALYSIS 5.1 Applicability Of TST4421 and Published NRC Safety Evaluation Exelon Generation Company, LLC (EGC) has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP for the Braidwood and Byron reactor coolant pump (RCP) flywheels specified in WCAP- 1 5666-A, Table 2-2, Category 3. This verification of applicability included a review of the NRC's model SE, as well as the information provided to support TSTF-421 (including WCAP-15666-A and the related SE dated May 5, 2003). EGC has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC are applicable to Braidwood and Byron, and justify the incorporation of the proposed changes to the respective TS for the Braidwood and Byron RCP flywheels specified in WCAP- 1 5666-A. Variation from TSTF-421 and Published NRC Safety Evaluation The proposed change maintains the existing examination requirements for two alternate RCP flywheels that were not included in the WCAP-1 5666-A evaluation (i.e., as specified in Table 2-2, Category 3 of WCAP-15666-A). These two alternate RCP flywheels, as integral elements of RCP motors, were originally designed and built for the Marble Hill Nuclear Generating Station (Marble Hill), the construction of which was cancelled in the early 1980s. EGC procured two original Marble Hill RCP motor/flywheel combinations, and subsequently installed one RCP motor/flywheel combination in Byron Unit 1 during the spring 2005 Unit 1 refueling outage (i.e., serial number 1S88P961). The second is currently stored as a spare RCP motor/flywheel combination at Braidwood (i.e., serial number -AS88P961 I While these two RCP motor/flywheel combinations can be utilized at either Braidwood or Byron, the Marble Hill flywheels are not interchangeable with the Braidwood and Byron RCP flywheels that are specified in WCAP- 1 5666-A. Page 3 of 5 Since neither the installed Marble Hill RCP motor/flywheel nor the spare were included in the 2001 WCAP-1 5666-A evaluation, the conclusion of the WCAP (i.e., justification for an extended RCP flywheel examination interval) is not applicable for these two RCP flywheels.
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| Therefore, the proposed TS provides separate examination requirements for the Marble Hill RCP flywheels and the WCAP-evaluated RCP flywheels. EGC has concluded that the proposed RCP flywheel examination requirements (i.e., differentiated requirements for the WCAP-evaluated RCP flywheels and the alternate Marble Hill RCP flywheels) are consistent with the intent of TSTF-421, Revision 0, and with the NRC's model safety evaluation dated June 24, 2003, in that the relaxed examination interval is only applicable to the RCP flywheels that were evaluated as pal of the WCAP. 6.0 REGULATORY ANALYSIS A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666-A, and the associated SE. 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION EGC has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the proposed determination presented in the notice is applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(x). 8.0 ENVIRONMENTAL EVALUATION EGC has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the findings presented in that evaluation are applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the evaluation is hereby incorporated by reference for this application. 9.0 PRECEDENT This application is being made in accordance with the CLIIP, with the exception of a site-specific variation. This variation ensures that the proposed TS are consistent with the intent of TSTF-421, Revision 0, the NRC's model safety evaluation dated June 24, 2003, and the existing equipment at Braidwood and Byron.
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| ==10.0 REFERENCES==
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| ATTACHMENT 1 Evaluation of Proposed Change 1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422) | | ATTACHMENT I Evaluation of Proposed Change |
| ATTACHMENT I Evaluation of Proposed Change 2. Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published June 24, 2003 (68 FR 37590) 3. Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)," Revision 0, November 2001 4. Westinghouse WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," Revision 1, October 2003 5. Letter from H. Berkow (NRC) to R. Bryan (WOG), "Safety Evaluation of Topical Report WCAP-15666, 'Extension of Reactor Coolant Pump Motor Flywheel Examination,' (TAC NO. MB2819)," May 5, 2003 ATTACHMENT 2 Proposed Mark-up of Braidwood Technical specification 5.5 Technical.Specification Pale 5.5-5
| | : 2. Federal Register Notice : Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published June 24, 2003 (68 FR 37590) 3 . Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)," Revision 0, November 2001 |
| | : 4. Westinghouse WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," Revision 1, October 2003 |
| | : 5. Letter from H . Berkow (NRC) to R. Bryan (WOG), "Safety Evaluation of Topical Report WCAP-15666, 'Extension of Reactor Coolant Pump Motor Flywheel Examination,' |
| | (TAC NO . MB2819)," May 5, 2003 |
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| ===5.5 Programs===
| | ATTACHMENT 2 Proposed Mark-up of Braidwood Technical specification 5.5 Technical .Specification Pale 5 .5-5 |
| and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, duly 1990. BRAIDWOOD - UNITS 1 & 2 The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies. 5.5.7 Reactor Coolant Pump Flywheel Inspection Program Programs and Manuals 5.5 This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975. 4++ lieu of Regulatory Position c.401) and c.402), a qualified An-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI. For all other reactor coolant pump motors, in lieu of Regulatory Position c.4.41) and c.40(2), a qualified in-place OT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years. 5.5 - 5 Amendment 4-58 ATTACHMENT 3 Proposed Mark-up of Byron Technical specification
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| ===5.5 Technical===
| | Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, duly 1990 . |
| | The provisions of SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies . |
| | 5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 . |
| | 4++ lieu of Regulatory Position c .401) and c .402), a qualified An-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI . |
| | For all other reactor coolant pump motors, in lieu of Regulatory Position c .4 .41) and c .40(2), a qualified in-place OT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years . |
| | BRAIDWOOD - UNITS 1 & 2 5 .5 - 5 Amendment 4-58 |
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| Specification Page 5.5-5 | | ATTACHMENT 3 Proposed Mark-up of Byron Technical specification 5 .5 Technical Specification Page 5 .5-5 |
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| ===5.5 Programs===
| | Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containmen don Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, July 1990 . |
| and Manuals 5.5.6 Pre-Stressed Concrete Containmen For reactor coolant pump motor serial numbers 4S88P961 and IS88P961, in BYRON - UNITS 1 & 2 don Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990. The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies. 5.5.7 Reactor Coolant Pump Flywheel Inspection Program Programs and Manuals 5.5 This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975. lieu of Regulatory Position c.4.b(l) and c.402), a qualified -place UT examination over the volume from the inner bore of the heel to the circle of one-half the outer radius or a surface examination AT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI. all other reactor coolant pump motors, in lieu of Regulatory Position c.4.41) and c .4.b{2>, a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years. 5.5 - 5 Amendment 4-64}} | | The provisions of SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies . |
| | 5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 . |
| | lieu of Regulatory Position c .4 .b(l) and c .402), a qualified |
| | -place UT examination over the volume from the inner bore of the heel to the circle of one-half the outer radius or a surface examination AT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI . |
| | For reactor all other reactor coolant pump motors, in lieu of coolant pump motor Regulatory Position c .4 .41) and c .4 .b{2>, a qualified serial numbers in-place UT examination over the volume from the inner 4S88P961 and bore of the flywheel to the circle of one-half the IS88P961, in outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years . |
| | BYRON - UNITS 1 & 2 5 .5 - 5 Amendment 4-64}} |
Letter Sequence Request |
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TAC:ME3640, Revision to RCP Flywheel Inspection Program - WCAP-15666 (Approved, Closed) |
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, 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-23-117, 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-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 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-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink 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-23-045, 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-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators 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-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator 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-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly 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-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control 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-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 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 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 RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC 2024-01-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-057, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2021-05-27027 May 2021 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-130, License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition2020-11-0202 November 2020 License Amendment Request - Proposed Changes to Byron Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 of 5 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5 ML20303A3262020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 3 of 5 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 52020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5 RS-20-114, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition RS-20-089, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2020-07-15015 July 2020 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating RS-20-058, Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-16016 April 2020 Supplement to License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-20-002, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-02-0606 February 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions RS-19-078, License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies.2019-09-24024 September 2019 License Amendment Request to Revise Technical Specifications 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies. RS-19-082, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS)2019-09-11011 September 2019 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink (UHS) RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) RS-19-081, Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-08-0909 August 2019 Supplement to Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-19-008, Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2019-01-31031 January 2019 Application for Technical Specifications Change to Add LCO 3.0.9 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RS-18-149, Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.22018-12-21021 December 2018 Supplemental Information Related to License Amendment Request for a One-Time Extension to Technical Specification 3.8. 1, AC Sources-Operating, Required Action A.2 RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-129, Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies2018-10-19019 October 2018 Supplement to License Amendment Request to Utilize Tvel TVS-K Lead Test Assemblies RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 RS-18-035, License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference2018-04-0202 April 2018 License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference RS-18-027, License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies2018-03-0808 March 2018 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies 2023-09-29
[Table view] Category:Technical Specifications
MONTHYEARML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position 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 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML21008A4052020-12-17017 December 2020 Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20086M2882020-04-0202 April 2020 Correction of Amendments Nos. for Amendments Revising Instrument Testing and Calibration Definitions RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-20020 December 2019 Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML19190A0812019-08-28028 August 2019 Issuance of Amendments Regarding Limiting Condition of Operation for Inoperability of Snubbers RS-19-018, Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times2019-02-14014 February 2019 Supplement to Application to Revise Technical Specifications to Adopt Risk Informed Completion Times RS-18-102, License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.22018-08-10010 August 2018 License Amendment Request for a One-Time Extension to Technical Specification 3.8.1, AC Sources-Operating, Required Action A.2 ML18067A1812018-06-0404 June 2018 Correction to Technical Specification Amendment Identification Format ML16180A2512016-08-0101 August 2016 Issuance of Amendments Regarding Use of Optimized Zirlo as Fuel Cladding Material ML16133A4382016-07-26026 July 2016 Issuance of Amendments Ultimate Heat Sink Temperature Increase RS-16-034, License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding2016-02-23023 February 2016 License Amendment Request and 10 CFR 50.12 Exemption Request for the Use of Optimized Zirlo Fuel Rod Cladding ML15336A7312016-01-27027 January 2016 TS 50456-Bwd-AppsABC ML15307A7762015-12-21021 December 2015 Braidwood - Issuance of Amendments Regarding Installation of New Low Degraded Voltage Relays and Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses (CAC Nos. MF4051 - MF4054) ML15341A3162015-12-14014 December 2015 Correction of Technical Specifications Related to Amendment 145 ML15286A2762015-11-19019 November 2015 Technical Specifications ML15232A4412015-10-28028 October 2015 Issuance of Amendments to Utilize WCAP-16143-P, Revision 1 Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2, Dated October 2014 ML15268A4862015-10-0606 October 2015 Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446) ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-337, Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement2014-12-18018 December 2014 Units 1 & 2 - License Amendment Request for Diesel Generator Load Rejection Surveillance Requirement ML14239A4272014-12-0707 December 2014 Issuance of Amendments to Clarify Technical Specification 3.3.1, Reactor Trip System Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation RS-14-285, License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs)2014-11-24024 November 2014 License Amendment Request to Revise Technical Specifications 3.7.9, Ultimate Heat Sink(Uhs) ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements ML13311B4812014-07-21021 July 2014 Issuance of Amendments to Revise Technical Specifications Section 3.5.3 ML14069A3372014-04-0202 April 2014 Final Response to Task Interface Agreement 2012-13, Braidwood Station Technical Specification 3.6.3 Compliance with One or More Main Steam Isolation Valves Inoperable ML13326A1072014-03-13013 March 2014 Issuance of Amendments to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program ML13281A0002014-02-0707 February 2014 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate RS-13-240, License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2013-10-10010 October 2013 License Amendment Request to Administratively Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program. RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-009, License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel2012-05-0101 May 2012 License Amendment Request - Diesel Generator Steady State Maximum Frequency and Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria RS-11-136, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.12011-09-0202 September 2011 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications (TS) 3.3.1 ML1117900312011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 2A, Markup of Proposed Operating License and Technical Specifications Pages 2023-07-20
[Table view] |
Text
10 CFR 50.90 RS-10-052 March 29, 2010 U . S. Nuclear Regulatory Commission Attn : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos . NPF-72 and NPF-77 NFIC Docket Nos. 50-456 and 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos . NPF-37 and NPF-66 NFIC Docket Nos . 50-454 and STN 50-455 Subject : License Amendment Request for an Extension of the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process In accordance with 10 CIFIR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), is requesting an amendment to Appendix A, "Technical Specifications" (TS) of Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . The proposed amendment would revise Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program," by extending the reactor coolant pump (RCP) motor flywheel inspection interval from the currently approved 10-year inspection interval to an interval not to exceed 20 years .
The changes are consistent with the NFIC-approved Technical Specification Task Force (TSTF)
Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-15666-A evaluation . The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLIIP) .
The proposed changes have been evaluated using the risk-informed processes described in Regulatory Guide (RG) 1 .174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Revision 1, dated November 2002. The evaluation concluded that WCAP-115666A "Extension of Reactor Coolant Pump Motor Flywheel Examination," is applicable to Braidwood and Byron, with the exception of two RCP motor/flywheel combinations that were not included in the WCAP- 1 5666-A evaluation.
U. S. Nuclear Regulatory Commission March 29, 2010 Page 2 The attached request is subdivided as shown below.
Attachment 1 provides an evaluation of the proposed changes.
Attachments 2 and 3 include the marked-up TS pages with the proposed changes indicated for the Braidwood and Byron TSs, respectively -
These proposed changes have been reviewed by the Braidwood and Byron Plant Operations Review Committees and approved by the respective Nuclear Safety Review Boards in accordance with the requirements of the EGC Quality Assurance Program .
EGC requests approval of the proposed amendment by March 29, 2011 . Once approved, the amendment will be implemented within 60 days .
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official .
This submittal does not contain any regulatory commitments. Should you have any questions concerning this letter, please contact Ms. Lisa Schofield at (630) 65T2815 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of March 2010.
Respectfully, Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC Attachments:
1 . Evaluation of Proposed Change
- 2. Proposed Mark-up of Braidwood Technical Specification 5.5
- 3. Proposed Mark-up of Byron Technical Specification 5 .5
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 INTRODUCTION 2 .0 DESCRIPTION OF PROPOSED AMENDMENT 3 .0 BACKGROUND 4.0 REGULATORY REQUIREMENTS AND GUIDANCE 5 .0 TECHNICAL ANALYSIS 5 .1 Applicability of TSTF-421 and Published NRC Safety Evaluation 5.2 Variation from TSTF-421 and Published NRC Safety Evaluation
6.0 REGULATORY ANALYSIS
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION 8 .0 ENVIRONMENTAL EVALUATION 9.0 PRECEDENT
10.0 REFERENCES
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 INTRODUCTION The proposed amendment would revise Appendix A, "Technical Specifications" (TS) 5 .5-7, "Reactor Coolant Pump Flywheel Inspection Program," of Facility Operating License Nos .
NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, (Braidwood) and NPF-37 and NPF-66 for Byron Station, Units 1 and 2 (Byron) . The changes are consistent with the NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-1 5666-A)," with the exception of two RCP motor/flywheel combinations that were not included in the WCAP-1 5666-A evaluation . The availability of this TS improvement was announced in the Federal Register on October 22, 2003 (68 FR 60422) as part of the consolidated line item improvement process (CLI I P) .
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Braidwood and Byron TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program,"
currently state, in part, the following:
In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place LIT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section X1 .
Consistent with the NFIC-approved TSTF-421 and site-specific equipment, the proposed TS change revises TS 5.5.7 as follows:
For reactor coolant pump motor serial numbers 4S88P961 and 1 S88P9Q in Heu of Regulatory Position c.4.b(l) and cA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
For all other reactor coolant pump motors, in lieu of Regulatory Position cA.b(l) and cAb(o, a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years .
ATTACHMENT 1 Evaluation of Proposed Change
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 375901 TSTF4421, WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC safety evaluation (SE) dated May 5, 2003 .
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590),
TSTF-421, WCAP-1 5666-A and the related NRC SE dated May 5, 2003.
5 .0 TECHNICAL ANALYSIS 5.1 Applicability Of TST4421 and Published NRC Safety Evaluation Exelon Generation Company, LLC (EGC) has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP for the Braidwood and Byron reactor coolant pump (RCP) flywheels specified in WCAP- 1 5666-A, Table 2-2, Category 3 . This verification of applicability included a review of the NRC's model SE, as well as the information provided to support TSTF-421 (including WCAP-15666-A and the related SE dated May 5, 2003) . EGC has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC are applicable to Braidwood and Byron, and justify the incorporation of the proposed changes to the respective TS for the Braidwood and Byron RCP flywheels specified in WCAP- 1 5666-A.
Variation from TSTF-421 and Published NRC Safety Evaluation The proposed change maintains the existing examination requirements for two alternate RCP flywheels that were not included in the WCAP-1 5666-A evaluation (i .e ., as specified in Table 2-2, Category 3 of WCAP-15666-A). These two alternate RCP flywheels, as integral elements of RCP motors, were originally designed and built for the Marble Hill Nuclear Generating Station (Marble Hill), the construction of which was cancelled in the early 1980s.
EGC procured two original Marble Hill RCP motor/flywheel combinations, and subsequently installed one RCP motor/flywheel combination in Byron Unit 1 during the spring 2005 Unit 1 refueling outage (i.e., serial number 1S88P961). The second is currently stored as a spare RCP motor/flywheel combination at Braidwood (i.e ., serial number -AS88P961 I While these two RCP motor/flywheel combinations can be utilized at either Braidwood or Byron, the Marble Hill flywheels are not interchangeable with the Braidwood and Byron RCP flywheels that are specified in WCAP- 1 5666-A.
Since neither the installed Marble Hill RCP motor/flywheel nor the spare were included in the 2001 WCAP-1 5666-A evaluation, the conclusion of the WCAP (i.e., justification for an extended RCP flywheel examination interval) is not applicable for these two RCP flywheels.
Page 3 of 5
ATTACHMENT 1 Evaluation of Proposed Change Therefore, the proposed TS provides separate examination requirements for the Marble Hill RCP flywheels and the WCAP-evaluated RCP flywheels.
EGC has concluded that the proposed RCP flywheel examination requirements (i.e .,
differentiated requirements for the WCAP-evaluated RCP flywheels and the alternate Marble with Hill RCP flywheels) are consistent the intent of TSTF-421, Revision 0, and with the NRC's model safety evaluation dated June 24, 2003, in that the relaxed theexamination interval is only applicable to the RCP flywheels that were evaluated as pal of WCAP.
6 .0 REGULATORY ANALYSIS A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666-A, and the associated SE.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION EGC has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the proposed determination presented in the notice is applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(x) .
8.0 ENVIRONMENTAL EVALUATION EGC has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. EGC has concluded that the findings presented in that evaluation are applicable to the WCAP-evaluated RCP flywheels at Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, and the evaluation is hereby incorporated by reference for this application .
9 .0 PRECEDENT This application is being made in accordance with the CLIIP, with the exception of a site-specific variation . This variation ensures that the proposed TS are consistent with the intent of TSTF-421, Revision 0, the NRC's model safety evaluation dated June 24, 2003, and the existing equipment at Braidwood and Byron .
10.0 REFERENCES
1 . Federal Register Notice : Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422)
ATTACHMENT I Evaluation of Proposed Change
- 2. Federal Register Notice : Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published June 24, 2003 (68 FR 37590) 3 . Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)," Revision 0, November 2001
- 4. Westinghouse WCAP-15666-A, "Extension of Reactor Coolant Pump Motor Flywheel Examination," Revision 1, October 2003
- 5. Letter from H . Berkow (NRC) to R. Bryan (WOG), "Safety Evaluation of Topical Report WCAP-15666, 'Extension of Reactor Coolant Pump Motor Flywheel Examination,'
(TAC NO . MB2819)," May 5, 2003
ATTACHMENT 2 Proposed Mark-up of Braidwood Technical specification 5.5 Technical .Specification Pale 5 .5-5
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, duly 1990 .
The provisions of SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 .
4++ lieu of Regulatory Position c .401) and c .402), a qualified An-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
For all other reactor coolant pump motors, in lieu of Regulatory Position c .4 .41) and c .40(2), a qualified in-place OT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years .
BRAIDWOOD - UNITS 1 & 2 5 .5 - 5 Amendment 4-58
ATTACHMENT 3 Proposed Mark-up of Byron Technical specification 5 .5 Technical Specification Page 5 .5-5
Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .6 Pre-Stressed Concrete Containmen don Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity . The program shall include baseline measurements prior to initial operations . The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50 .55a, except where an alternative, exemption, or relief has been authorized by the NRC . Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1 .35 .1, July 1990 .
The provisions of SR 3 .0 .3 are applicable to the Tendon Surveillance Program inspection frequencies .
5 .5 .7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c .4 .b of Regulatory Guide 1 .14, Revision 1, August 1975 .
lieu of Regulatory Position c .4 .b(l) and c .402), a qualified
-place UT examination over the volume from the inner bore of the heel to the circle of one-half the outer radius or a surface examination AT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI .
For reactor all other reactor coolant pump motors, in lieu of coolant pump motor Regulatory Position c .4 .41) and c .4 .b{2>, a qualified serial numbers in-place UT examination over the volume from the inner 4S88P961 and bore of the flywheel to the circle of one-half the IS88P961, in outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years .
BYRON - UNITS 1 & 2 5 .5 - 5 Amendment 4-64