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| Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. | | Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. |
| The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence. | | The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence. |
| Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 150 hours to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager. | | Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately [[estimated NRC review hours::150 hours]] to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager. |
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| These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications. | | These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications. |
Latest revision as of 13:30, 5 March 2020
Letter Sequence Acceptance Review |
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EPID:L-2019-LLR-0013, Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0) (Approved, Closed) |
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MONTHYEARML19051A1082019-02-20020 February 2019 Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0) Project stage: Request ML19051A1092019-02-20020 February 2019 LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds Project stage: Request ML19070A2692019-03-11011 March 2019 Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds Project stage: Acceptance Review ML19070A2422019-03-11011 March 2019 Acceptance Review Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds Project stage: Acceptance Review ML19070A2992019-03-14014 March 2019 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Unit 2 Project stage: Withholding Request Acceptance ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements Project stage: Approval 2019-02-20
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Category:E-Mail
MONTHYEARML23129A3122023-05-0909 May 2023 NRR E-mail Capture - Beaver Valley Unit 2 - Verbal Authorization of Alternative Request, 2-TYP-4-RV-06 ML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML23089A1252023-03-30030 March 2023 NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection ML23079A1202023-03-20020 March 2023 NRR E-mail Capture - Acceptance Review for Beaver Valley 1 & 2 Exemption from Specific Provisions in 10 CFR 50 Appendix H ML23065A0782023-03-0303 March 2023 Final RAIs Regarding the Beaver Valley Emergency LAR (EPID L-2023-LLA-002) - Email ML22321A2392022-11-17017 November 2022 NRR E-mail Capture - (External_Sender) Beaver Valley Power Station, Units 1&2 - Clarification on LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22273A1132022-09-30030 September 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action to Add Full Spectrum LOCA Methodology to COLR ML22277A5122022-09-19019 September 2022 NRR E-mail Capture - (External_Sender) Eh Response to Corrected SE Associated with Beaver Valley Amendments 315 and 205 Changes to the EPP ML22238A2812022-08-25025 August 2022 Request for Additional Information for Beaver Valley Unit 2 - 2R22 Steam Generator 180 Day Report ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22173A0402022-06-21021 June 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22147A0392022-05-27027 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley, Units 1 & 2 Amendment - Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Separation Instrumentation ML22129A0122022-05-0606 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Unit 2 Amendment - Correct TS 3.1.7 Change Made by TSTF-547 ML22123A0232022-05-0202 May 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action for Beaver Valley Power Station, Units 1 and 2 - Adoption of TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22153A5212022-04-15015 April 2022 Email Error in Energy Harbor Submittal and Associated SE for Beaver Valley 1 & 2 - Containment Isolation Valve Relief Request ML22101A0122022-04-0808 April 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML22087A1302022-03-28028 March 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Adopt TSTF-577 ML22080A2512022-03-18018 March 2022 NRR E-mail Capture - (External_Sender) ASME OM Code Case OMN-27, Alternative Requirements for Testing Category a Valves (Non- Piv/Civ) ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML21344A0392021-12-0909 December 2021 NRR E-mail Capture - Beaver Valley TSTF-577-A Acceptance Review ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21286A7892021-10-0707 October 2021 NRR E-mail Capture - Beaver Valley Acceptance Review for LAR Regarding TS 3.1.7.2 to Correct a Logic Error (L-2021-LLA-0160) ML21266A2222021-09-23023 September 2021 NRR E-mail Capture - Beaver Valley Loss of Power Diesel Generator Start and Bus Separation Instrument ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21225A0362021-08-12012 August 2021 NRR E-mail Capture - Beaver Valley Unit Nos. 1 and 2 - Acceptance Review Determination Emergency Plan Amendment Request ML21197A0242021-07-15015 July 2021 NRR E-mail Capture - Beaver Valley No. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Emergency Plan Amendment Request ML21137A0082021-05-14014 May 2021 Acceptance of License Amendment Request: Beaver Valley COLR TS LAR ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21032A2582021-02-0101 February 2021 Acceptance of License Amendment Request: Beaver Valley Steam Generator Inspection Deferral ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21014A1142021-01-12012 January 2021 Correction Letter Notification from Licensee ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20329A4562020-11-24024 November 2020 Acceptance of License Amendment Request: Beaver Valley RCS and PTLR TS Changes ML20325A2312020-11-20020 November 2020 Request for Additional Information - Beaver Valley Request for Exemption - Part 73 Force-on-Force Exemption ML20324A0872020-11-19019 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Unit 2 Capsule Pull ML20323A0452020-11-17017 November 2020 2.206 Petition ML20310A1632020-11-0404 November 2020 Acceptance of Requested Licensing Action: Beaver Valley One-time Exemption App. B Sect. VI.C.3.(I)(1) Force on Force (COVID-19) ML20307A5762020-11-0202 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Adv Non-Conservative TS LAR ML20297A3222020-10-22022 October 2020 Final Request for Additional Information - Steam Generator Tube Sleeve LAR ML20283A7722020-10-0909 October 2020 Submittal of Pennsylvania Letter Requesting Exemption from Biennial Exercise Requirements for Pennsylvania Nuclear Power Plants in Calendar Year 2020 2023-05-09
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Text
From: Parker, Carleen To: "phlashley@firstenergycorp.com" Cc: Collins, Jay; Danna, James; Cumblidge, Stephen
Subject:
Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (L-2019-LLR-0013)
Date: Monday, March 11, 2019 8:43:00 AM
- Phil, By letter dated February 20, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19051A108), FirstEnergy Nuclear Operating Company (FENOC) submitted a request for an alternative examination frequency for cold leg reactor vessel inlet nozzle to safe-end welds at Beaver Valley Power Station, Unit No. 2.
Specifically, FENOC is proposing an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-770-2 inspection frequency requirements to volumetrically examine the reactor vessel cold leg nozzle to safe-end welds every second inspection period, not to exceed 7 years.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed alternative in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 150 hours6.25 days <br />0.893 weeks <br />0.205 months <br /> to complete. The NRC staff expects to complete this review by your requested date of February 28, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates will be communicated, during the routine interactions with the assigned project manager.
These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
If you have any questions, please contact me.
Carleen Carleen Parker Project Manager -
Beaver Valley and FitzPatrick Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov