Letter Sequence Acceptance Review |
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MONTHYEARML21091A2592021-04-0101 April 2021
and Beaver Valley Power Station, Proposed Alternative to Use ASME OM Code Case OMN-27
Project stage: Request
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
Project stage: Acceptance Review
ML22012A2972022-01-21021 January 2022
Proposed Alternative to Use ASME OM Code Case OMN-27
Project stage: Other
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)
Project stage: Other
ML22082A2532022-03-29029 March 2022
Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27
Project stage: Approval
2022-01-21
[Table View] |
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Category:E-Mail
MONTHYEARML23348A1222023-12-14014 December 2023
NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems
ML23335A0652023-12-0101 December 2023
NRR E-mail Capture - GGNS - Audit Questions for LARs Associated with TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Init. 4b and 50.69, Risk-Informed Cat. and Treatment of SSCs for Nuclear Pwr Rx (L-2023-LLA-0081/0080)
ML23240A3412023-08-28028 August 2023
NRR E-mail Capture - ANO-2, Grand Gulf, and River Bend - Acceptance Review of LAR Revising TSs to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
ML23191A2802023-07-10010 July 2023
NRR E-mail Capture - Grand Gulf - Acceptance Review for LAR Adopting TSTF-505, Rev. 2, Provide Risk-Informed Completion Times - RITSTF Initiative 4b
ML23191A8662023-07-10010 July 2023
NRR E-mail Capture - Grand Gulf - Acceptance Review of LAR Adopting 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSCs for Nuclear Power Reactors
ML23129A3122023-05-0909 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
ML23116A1462023-04-26026 April 2023
NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)
ML23089A1252023-03-30030 March 2023
NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection
ML23086B9862023-03-27027 March 2023
NRR E-mail Capture - Davis-Besse, Unit No. 1 - Acceptance Review Results for Davis-Besse, Unit No. 1 - Proposed Alternative Request RP-5
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
ML23072A3672023-03-0909 March 2023
NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment
ML23065A0782023-03-0303 March 2023
Final RAIs Regarding the Beaver Valley Emergency LAR (EPID L-2023-LLA-002) - Email
ML23033A0322023-02-0101 February 2023
NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115)
ML23009B6912023-01-0909 January 2023
NRR E-mail Capture - Grand Gulf, Unit 1 and River, Unit 1 - Acceptance of Requested Licensing Action Request to Update ASME Code RR SE with NRC-Approved Revision of BWRVIP Guidelines
ML22353A6122022-12-19019 December 2022
March 2023 Emergency Preparedness Exercise Inspection - Request for Information
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
ML22266A1102022-09-23023 September 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure
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
ML22206A0152022-07-21021 July 2022
NRR E-mail Capture - Entergy (Grand Gulf, River Bend, and Waterford-3) - Acceptance Review of the RR EN-RR-22-001, Case N-752, Risk-informed Cat & Treatment for Repair/Replacement Activities in Class 2 & 3 Systems
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
ML22173A0372022-06-21021 June 2022
NRR E-mail Capture - Entergy (Grand Gulf and River Bend) - Acceptance Review of the License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
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
ML22164A8572022-06-13013 June 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan
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
ML22118A6862022-04-28028 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval
ML22112A1092022-04-22022 April 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
ML22110A1172022-04-19019 April 2022
(GG) 2022 Emergency Preparedness (EP) Program Inspection RFI Sdh 041922
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)
ML22090A1692022-03-30030 March 2022
Re_ Action Tracking Item 2022 SST - 335 - Tom Gurdziel, E-mail Re_ Event Number 55734 at Davis Besse, a Matter of Interpretation
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
ML22075A3692022-03-0303 March 2022
Email Grand Gulf 2022 PI&R Request for Information
ML22055B0382022-02-24024 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Upcoming Steam Generator Tube Inservice Inspection
ML22055A0872022-02-23023 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3
ML22045A4962022-02-14014 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Emergency Plan
ML22040A1832022-02-0707 February 2022
LTR-22-0033 Tom Gurdziel, E-mail Event Number 55734 at Davis Besse, a Matter of Interpretation
ML22034A9472022-02-0303 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Revised Review Estimates for Proposed Alternative to Extend the Steam Generator Weld Inspection Interval
ML22033A0632022-02-0101 February 2022
NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Design Basis for the Shield Building Containment Structure
2023-08-28
[Table view] |
Text
From: Vaidya, Bhalchandra Sent: Wednesday, April 28, 2021 2:18 PM To: Lashley, Phil H (EH Cc: Farnan, Michael; Scarbrough, Thomas; Buford, Angie; Salgado, Nancy; Kuntz, Robert; Purnell, Blake; Tobin, Jennifer; Danna, James; Wolfgang, Bob
Subject:
ENERGY HARBOR FLEET, BEAVER VALLEY UNITS 1 AND 2 AND DAVIS-BESSE UNIT 1- ACCEPTANCE OF RELIEF REQUEST RE: PROPOSED ALTERNATIVE TO USE ASME OM CODE CASE OMN-27
SUBJECT:
ENERGY HARBOR FLEET, BEAVER VALLEY UNITS 1 AND 2 AND DAVIS-BESSE UNIT 1- ACCEPTANCE OF RELIEF REQUEST RE: PROPOSED ALTERNATIVE TO USE ASME OM CODE CASE OMN-27 Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 EPID-L-2021-LLR-0026 By letter dated April 1, 2021 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML21091A259), in accordance with the provisions of 10 CFR 50.55a(z)(1), Energy Harbor Nuclear Corp. hereby requested Nuclear Regulatory Commission (NRC) approval of a proposed alternative to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), Subsection ISTC, "Inservice Testing of Valves in Light-Water Reactor Power Plants," for use at Davis-Besse Nuclear Power Station (DBNPS), and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and BVPS-2, respectively).
Specifically, Energy Harbor Nuclear Corp. requested approval to use ASME OM Code Case OMN-27, "Alternative Requirements for Testing Category A Valves (Non[1]PIV/CIV)," to determine valve test frequency in lieu of the two-year leakage rate test frequency requirement specified in ASME OM Code Section ISTC-3630(a) for Category A valves that are not reactor coolant system pressure isolation valves (PIVs) or containment isolation valves (CIVs).
The purpose of this e-mail 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 amendment 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. If additional information is needed, you will be advised by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 150 man-hours to complete. The NRC staff expects to complete this review in approximately 12 months, which is March 2021. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, 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 NRC 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.
Bhalchandra K. Vaidya US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing LPL3 301-415-3308 Bhalchandra.vaidya@nrc.gov
Hearing Identifier: NRR_DRMA Email Number: 1155 Mail Envelope Properties (SJ0PR09MB64156121DD1A60BA2315D7968D409)
Subject:
ENERGY HARBOR FLEET, BEAVER VALLEY UNITS 1 AND 2 AND DAVIS-BESSE UNIT 1- ACCEPTANCE OF RELIEF REQUEST RE: PROPOSED ALTERNATIVE TO USE ASME OM CODE CASE OMN-27 Sent Date: 4/28/2021 2:17:38 PM Received Date: 4/28/2021 2:17:38 PM From: Vaidya, Bhalchandra Created By: Bhalchandra.Vaidya@nrc.gov Recipients:
"Farnan, Michael" <Michael.Farnan@nrc.gov>
Tracking Status: None "Scarbrough, Thomas" <Thomas.Scarbrough@nrc.gov>
Tracking Status: None "Buford, Angie" <Angela.Buford@nrc.gov>
Tracking Status: None "Salgado, Nancy" <Nancy.Salgado@nrc.gov>
Tracking Status: None "Kuntz, Robert" <Robert.Kuntz@nrc.gov>
Tracking Status: None "Purnell, Blake" <Blake.Purnell@nrc.gov>
Tracking Status: None "Tobin, Jennifer" <Jennifer.Tobin@nrc.gov>
Tracking Status: None "Danna, James" <James.Danna@nrc.gov>
Tracking Status: None "Wolfgang, Bob" <Robert.Wolfgang@nrc.gov>
Tracking Status: None "Lashley, Phil H (EH" <phlashley@energyharbor.com>
Tracking Status: None Post Office: SJ0PR09MB6415.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 4437 4/28/2021 2:17:38 PM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: