Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARML16319A0572016-12-0101 December 2016
Acceptance of Requested Licensing Action Relief Request for Proposed Alternative to Perform As-Found Set-Pressure Test
Project stage: Acceptance Review
ML17047A6102017-03-0202 March 2017
Relief from the Requirements of the American Society of Mechanical Engineers Code
Project stage: Approval
ML17074A0192017-03-16016 March 2017
Acceptance of Requested Licensing Action Proposed Alternative to ASME Code Reactor Pressure Vessel Head Penetration Examination Frequency Requirements (Request 1-TYP-4-RV-05)
Project stage: Acceptance Review
2017-03-16
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML24226A3652024-05-13013 May 2024
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
ML23249A1842023-09-18018 September 2023
Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06
ML22082A2532022-03-29029 March 2022
Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27
ML22012A2972022-01-21021 January 2022
Proposed Alternative to Use ASME OM Code Case OMN-27
L-20-256, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-28028 September 2020
Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML20223A0142020-08-20020 August 2020
Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19))
ML20206K8652020-08-0707 August 2020
Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19))
ML20145A0002020-06-0303 June 2020
Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19))
ML20100N3222020-04-0909 April 2020
Verbal Relief for Penetration Evaluation and Hot Leg Nozzles - Delivered 4/9/2020 at 10:00 Am
ML20099B2572020-04-0808 April 2020
Verbal Relief Unit 2 CIV
ML20098F3012020-04-0707 April 2020
Verbal Relief for Appendix I Safety Relief Valves
ML20095J2192020-04-0404 April 2020
Email Beaver Valley Power Station, Unit 2 - Verbal Relief for MOVs - Delivered 4/4/2020 at 4:00 Pm
ML20095J0992020-04-0404 April 2020
Email Beaver Valley Power Station, Unit 2 - Verbal Relief for Snubbers - Delivered 4/4/2020 at 4:00 P.M
L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections2020-04-0303 April 2020
10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections
L-20-118, CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing2020-04-0303 April 2020
CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing
L-20-060, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0202 April 2020
CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency
L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020
CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
ML20079F8162020-03-26026 March 2020
Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval
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
L-19-107, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2019-08-27027 August 2019
Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
ML19051A1082019-02-20020 February 2019
Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0)
ML18227A7332018-08-27027 August 2018
Request for Relief from the Requirements of the ASME Code
ML18004A1222018-01-22022 January 2018
FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088)
L-17-317, Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01)2017-11-15015 November 2017
Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01)
L-17-308, 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2)2017-10-25025 October 2017
10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2)
ML17167A0672017-06-26026 June 2017
Requests for Alternatives and Requests for Relief Fourth 10-Year Inservice Test Program Interval (CAC Nos. MF8333-MF8356). Note: Correction Safety Evaluation See ML17255A526
ML17159A4422017-06-26026 June 2017
Requests for Alternatives and Requests for Relief Fifth 10-Year Inservice Testing Program Interval (CAC Nos. MF8332 Through MF8357). Note: Correction Safety Evaluation See ML17255A508
ML17047A6102017-03-0202 March 2017
Relief from the Requirements of the American Society of Mechanical Engineers Code
ML17041A1852017-03-0202 March 2017
Relief from the Requirements of the ASME Code
ML17048A0042017-03-0202 March 2017
Relief from the Requirements of the ASME Code
ML16328A1252017-01-23023 January 2017
Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783)
ML16190A1332016-12-27027 December 2016
Relief from the Requirements of the ASME Code
ML16319A0572016-12-0101 December 2016
Acceptance of Requested Licensing Action Relief Request for Proposed Alternative to Perform As-Found Set-Pressure Test
ML16257A6212016-11-21021 November 2016
Relief Request BV2-PZR-01, Regarding Alternative to Requirements for Components Connected to the Steam Side of the Pressurizer
ML16228A4082016-10-21021 October 2016
Correction to Relief Request 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds
ML16147A3622016-06-17017 June 2016
Relief Request No. 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds
ML14363A4092015-01-28028 January 2015
Relief Request No. 1-TYP-4-RV-04 Regarding the Examination Requirements of Code Case N-729-1
ML1202702982012-02-0707 February 2012
Relief Request VRR3 Regarding Solenoid Operated Valve Remote Position Verification Frequency
ML1131304282011-11-22022 November 2011
Relief Request VRR5 Regarding Turbine Driven Auxiliary Feedwater Valve Test Frequency for the 10-Year Inservice Testing Program Interval
ML1126404122011-09-20020 September 2011
Acceptance Review Results for VC Summer Relief Request (ME6879)
ML1107705512011-04-26026 April 2011
Relief Request VRR2 Regarding the 10-Year Inservice Testing Program Interval
ML1104705572011-02-25025 February 2011
Relief Request Regarding an Alternative Weld Repair Method for Reactor Vessel Head Penetrations J-Groove Welds
ML1006807812010-03-12012 March 2010
Third 10-Year ISI Interval Relief Request (ME2608)
L-08-362, Beaver, Units 1 and 2, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Paragraph IWA-5244 Examination Requirements2008-12-0202 December 2008
Beaver, Units 1 and 2, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Paragraph IWA-5244 Examination Requirements
L-08-207, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement2008-09-24024 September 2008
Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement
L-08-069, Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements (Request Nos. 1-TYP-3-RA-1, 1-TYP-3-RA-2, 1-TYP-3-RA-3)2008-04-0909 April 2008
Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements (Request Nos. 1-TYP-3-RA-1, 1-TYP-3-RA-2, 1-TYP-3-RA-3)
ML0720504882007-09-17017 September 2007
Relief Request No. BV1-PZR-01 Regarding Weld Overlay Repairs on Pressurizer Nozzle Welds
ML0705905552007-04-30030 April 2007
Relief, Relief Request No. BV2-PZR-01 Regarding Weld Overlay Repairs on Pressurizer Nozzle Welds
L-07-056, Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update2007-03-28028 March 2007
Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update
ML0625801202006-10-0202 October 2006
(BVPS-1 and 2), Inservice Inspection (ISI) Program, Alternative Examination of Reactor Coolant Pipe Welds, Request for Relief No. BV3-RV-2
2024-05-13
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 1 , 201 6 Mr. Marty L. Richey Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST FOR PROPOSED ALTERNATIVE TO PERFORM AS-FOUND SET-PRESSURE TEST (CAC NO. MF8531)
Dear Mr. Richey:
By letter dated October 24, 2016 (Agencywide Documents Access and Management System Accession No. ML16298A289), FirstEnergy Nuclear Operating Company submitted a relief request for the Beaver Valley Power Station (BVPS), Unit No. 2. The proposed relief request concerns the performance of an as-found set-pressure test of the residual heat removal system relief valve. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's 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, 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 staff's 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 75 hours3.125 days <br />0.446 weeks <br />0.103 months <br /> to complete. The NRC staff expects to complete this review by October 27, 2017. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant
M. Richey 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 staff's initial review of the application and they could change due to several factors, including requests for additional information and unanticipated additions to scope of 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 the BVPS Project Manager, Michael Marshall, at (301) 415-2871 or Michael.Marshall@nrc.gov.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-334 cc: Distribution via Listserv
ML16319A057 OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/PM DORL/LPL 1-2/LA DORL/LPL 1-2/BC(A) DORL/LPL 1-2/PM NAME MMarshall JPoole LRonewicz SKoenick MMarshall DATE 11/21/2016 11/22/2016 11/16/2016 12/01/2016 12/01/2016