|
|
(7 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML17262A723 | | | number = ML17262A723 |
| | issue date = 09/20/2017 | | | issue date = 09/20/2017 |
| | title = FENOC Fleet - Results of Acceptance Review of the Exemption Request Exemption from the Definition of Physical Barrier in 10 CFR 73.2 for Physical Security Plans (CAC Nos. MG0010, MG0011, MG0012, and MG0013) | | | title = FENOC Fleet - Results of Acceptance Review of the Exemption Request Exemption from the Definition of Physical Barrier in 10 CFR 73.2 for Physical Security Plans |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Belcher S L | | | addressee name = Belcher S |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000334, 05000440, 07200014, 07200069, 07201043 | | | docket = 05000334, 05000440, 07200014, 07200069, 07201043 |
| | license number = DPR-066, NPF-003, NPF-058, NPF-073 | | | license number = DPR-066, NPF-003, NPF-058, NPF-073 |
| | contact person = Vaidya B K, 415-3308 | | | contact person = Vaidya B, 415-3308 |
| | case reference number = CAC MG0010, CAC MG0011, CAC MG0012, CAC MG0013 | | | case reference number = CAC MG0010, CAC MG0011, CAC MG0012, CAC MG0013 |
| | document type = Acceptance Review Letter, Letter | | | document type = Acceptance Review Letter, Letter |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 20, 2017 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 20, 2017 FENOC FLEET-BEAVER VALLEY POWER STATION, UNIT NOS. 1, AND 2; DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1, AND PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -RESULTS OF ACCEPTANCE REVIEW OF THE EXEMPTION REQUEST RE: EXEMPTION FROM THE DEFINITION OF PHYSICAL BARRIER IN 10 CFR 73.2 FOR PHYSICAL SECURITY PLANS (CAC NOS. MG0010, MG0011, MG0012, AND MG0013)
| | FENOC FLEET-BEAVER VALLEY POWER STATION, UNIT NOS. 1, AND 2; DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1, AND PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - RESULTS OF ACCEPTANCE REVIEW OF THE EXEMPTION REQUEST RE: EXEMPTION FROM THE DEFINITION OF PHYSICAL BARRIER IN 10 CFR 73.2 FOR PHYSICAL SECURITY PLANS (CAC NOS. MG0010, MG0011, MG0012, AND MG0013) |
|
| |
|
| ==Dear Mr. Belcher:== | | ==Dear Mr. Belcher:== |
| By letter dated July 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17200D139), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted an exemption request for Renewed Facility Operating Licenses for the Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear PowerStation, Unit No. 1, and Facility Operating License for Perry Nuclear Power Plant, Unit 1. The licensee requested the permanent exemption pursuant to Title 1 O of the Code of Federal Regulations (10 CFR) Section 73.5, "Specific exemptions," from a requirement of 10 CFR 73.2, "Definitions" for "Physical Barrier." The regulation requires, in part, fences topped by three strands or more of barbed wire or similar material on brackets be angled inward or outward between 30 and 45 degrees from the vertical. An exemption is requested since not all protected area physical barrier fencing sections meet this requirement. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC or Commission) staff's acceptance review of the proposed exemption request. The acceptance review was performed to determine if there is proper regulatory basis and 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. Section 73.5 of 10 CFR, "Specific exemptions," states that the Commission may grant exemptions from the requirements of the regulations of this part provided the following specific criteria are met: (1) the exemption is authorized by law, (2) the exemption will not endanger life or property or the common defense and security, and (3) the exemption is otherwise in the public interest. Additionally, the categorical exclusion requirement in 10 CFR 51.22(c)(25), states that to meet the requirements for the categorical exclusion in accordance with 1 O CFR 51.22(c)(25), the exemption must meet the following: (i) no significant hazards consideration determination ; (ii) no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) no significant increase in individual or cumulative public or occupational radiation exposure; (iv) no significant construction impact; (v) no significant increase in the potential for or consequences from radiological accidents; and (vi) the S. Belcher requirements from which the exemption is sought involves safeguards plans or other requirements of an administrative, managerial or organizational nature. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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 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 [[estimated NRC review hours::400 hours]] to complete. The staff expects to complete this review by the requested date of July 31, 2018. 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 staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. 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 at (301) 415-3308. Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-346, 50-412, and 50-440 cc: Distribution via ListServ
| |
|
| |
|
| ML 17262A723 OFFICE DORL/LPL3/PM DORL/LPL3/LA DLR/RERP/BC(*) NAME BVaidya SRohrer BBeasley (WRautzen for) DATE 09/20/17 09/20/17 08/01/17 OFFICE DORL/LPL3/BC DORL/LPL3/PM NAME DWrona (KGreen for) BVaidya DATE 09/20/17 09/20/17}}
| | By letter dated July 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17200D139), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted an exemption request for Renewed Facility Operating Licenses for the Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear PowerStation, Unit No. 1, and Facility Operating License for Perry Nuclear Power Plant, Unit 1. |
| | The licensee requested the permanent exemption pursuant to Title 1O of the Code of Federal Regulations (10 CFR) Section 73.5, "Specific exemptions," from a requirement of 10 CFR 73.2, "Definitions" for "Physical Barrier." The regulation requires, in part, fences topped by three strands or more of barbed wire or similar material on brackets be angled inward or outward between 30 and 45 degrees from the vertical. An exemption is requested since not all protected area physical barrier fencing sections meet this requirement. |
| | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC or Commission) staff's acceptance review of the proposed exemption request. The acceptance review was performed to determine if there is proper regulatory basis and 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. |
| | Section 73.5 of 10 CFR, "Specific exemptions," states that the Commission may grant exemptions from the requirements of the regulations of this part provided the following specific criteria are met: (1) the exemption is authorized by law, (2) the exemption will not endanger life or property or the common defense and security, and (3) the exemption is otherwise in the public interest. Additionally, the categorical exclusion requirement in 10 CFR 51.22(c)(25), |
| | states that to meet the requirements for the categorical exclusion in accordance with 10 CFR 51.22(c)(25), the exemption must meet the following: (i) no significant hazards consideration determination ; (ii) no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) no significant increase in individual or cumulative public or occupational radiation exposure; (iv) no significant construction impact; (v) no significant increase in the potential for or consequences from radiological accidents; and (vi) the |
| | |
| | S. Belcher requirements from which the exemption is sought involves safeguards plans or other requirements of an administrative, managerial or organizational nature. |
| | The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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 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 [[estimated NRC review hours::400 hours]] to complete. The staff expects to complete this review by the requested date of July 31, 2018. 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 staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. 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 at (301) 415-3308. |
| | Sincerely, |
| | ~~ |
| | ~ |
| | Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-346, 50-412, and 50-440 cc: Distribution via ListServ |
| | |
| | ML17262A723 *by e-mail OFFICE DORL/LPL3/PM DORL/LPL3/LA DLR/RERP/BC(*) NSIR/DPCP/RSB/BC(*) |
| | NAME BVaidya SRohrer BBeasley (WRautzen for) ARivera (DGordon for) |
| | DATE 09/20/17 09/20/17 08/01/17 07/28/17 OFFICE DORL/LPL3/BC DORL/LPL3/PM NAME DWrona (KGreen for) BVaidya DATE 09/20/17 09/20/17}} |
Letter Sequence Acceptance Review |
---|
|
Results
Other: ML18130A760, ML18130A820, ML18130A849, ML18130A885, NRC-2018-0187, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment, NRC-2018-0192, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment, NRC-2018-0193, First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2
|
MONTHYEARL-17-112, Exemption Request for Physical Barrier Requirement2017-07-19019 July 2017 Exemption Request for Physical Barrier Requirement Project stage: Request ML17262A7232017-09-20020 September 2017 FENOC Fleet - Results of Acceptance Review of the Exemption Request Exemption from the Definition of Physical Barrier in 10 CFR 73.2 for Physical Security Plans Project stage: Acceptance Review L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement Project stage: Response to RAI L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 Project stage: Request ML18130A8852018-08-29029 August 2018 FENOC Fleet - Beaver Valley; Davis-Besse; Perry - Environment Assessment and Finding of No Significant Impact Related to Exemption Request for a Physical Barrier Requirement (CAC Nos. MG0010, MG0011, MG0012, and MG0013; EPID L-2018-LLE-0019 Project stage: Other ML18130A8892018-08-29029 August 2018, 4 September 2018 Environmental Assessment and Finding of No Significant Impact Related to Exemption Request for a Physical Barrier Requirement Project stage: Request ML18130A7602018-09-0404 September 2018 First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2 Project stage: Other ML18130A8492018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment Project stage: Other ML18130A8202018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment Project stage: Other NRC-2018-0192, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment2018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment Project stage: Other NRC-2018-0187, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment2018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment Project stage: Other NRC-2018-0193, First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 22018-09-0404 September 2018 First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2 Project stage: Other 2018-03-16
[Table View] |
|
---|
Category:Acceptance Review Letter
MONTHYEARML22304A6882022-11-16016 November 2022 Withdrawal of Requested Licensing Action Amendment Request for Fire Protection Program Changes ML20329A4562020-11-24024 November 2020 Acceptance of License Amendment Request: Beaver Valley RCS and PTLR TS Changes ML20324A0872020-11-19019 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Unit 2 Capsule Pull ML20275A2032020-09-30030 September 2020 Acceptance of Requested Licensing Action, One-Time Acceptance for Review: Beaver Valley of Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML20197C3872020-07-15015 July 2020 Acceptance Review for Beaver Valley - Non-Conservative Heat Flux Factor TS LAR ML20197B4802020-07-15015 July 2020 Acceptance Review for Beaver Valley - Steam Generator Tube Sleeve Inspection and Repair LAR ML20059J6792020-02-27027 February 2020 Acceptance Review for Beaver Valley - TS Change for Permanently Defueled Condition (Epids L-2020-LLA-0025) ML19256B5062019-09-20020 September 2019 Acceptance of Requested Licensing Action ML19249A6742019-09-0505 September 2019 Acceptance Review for Beaver Valley Units 1 and 2 - Impracticality for Inservice Inspection for Certain Welds - 2 Relief Requests (L-2019-LLR-0083 and L-2019-LLR-0082) ML19070A2692019-03-11011 March 2019 Acceptance Review - Beaver Valley Unit 2: Request for Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds ML18094A7992018-04-0303 April 2018 Acceptance Review for Beaver Valley - Relief Request from ASME Section XI Code - 5th ISI Interval ML17291A4582017-10-19019 October 2017 Acceptance for Review of Request for Alternative in Lieu of ASME Section XI Requirements ML17278A5022017-10-10010 October 2017 Acceptance for Review of Application Concerning Revision to Technical Specification 3.3.6.1 (CAC No. MG0150) (L-17-241) ML17264A6252017-09-25025 September 2017 FENOC-Beaver Valley Power Station, Unit Nos. 1 and 2; Davis-Besse Nuclear Power Station, Unit No. 1; and Perry Nuclear Power Plant, Unit No. 1 - Results of Acceptance Review Proposed Alternative for the Use of ASME Code Case N-513-4 ML17262A7232017-09-20020 September 2017 FENOC Fleet - Results of Acceptance Review of the Exemption Request Exemption from the Definition of Physical Barrier in 10 CFR 73.2 for Physical Security Plans ML17187A2162017-07-24024 July 2017 Perry Nuclear Power Plant, Unit 1 - Acceptance for Review of Application Concerning Revision to Technical Specification 3.8.1 Surveillance Requirement (CAC No. MF9855) (L-17-089) ML17184A0122017-07-13013 July 2017 Acceptance for Review of Application Concerning Revisions to the Technical Specifications (CAC No. MF9818) (L-17-042) ML17192A4942017-07-12012 July 2017 Acceptance for Review of Application Concerning Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement ML17184A1862017-07-0505 July 2017 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1 ML17153A2072017-06-0505 June 2017 Acceptance for Review of Application Concerning Revisions to the Environmental Protection Plan 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) ML16295A2462016-12-29029 December 2016 Letter to M. Richey, FENOC Notice of Consideration of Approval of Transfer of Facility Operating License and Conforming Amendment, Opportunity for a Hearing, and Order ML16347A1322016-12-15015 December 2016 Acceptance of Requested Licensing Action Relief Request for Proposed Alternative Examination of Reactor Vessel Head Penetration J-Groove Weld Repairs ML16335A3042016-12-0202 December 2016 Acceptance for Review of Application to Revise Technical Specifications Related to Adoption of Technical Specifications Task Force Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. ML16334A4532016-12-0202 December 2016 Acceptance for Review of Application Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) ML16172A2322016-06-20020 June 2016 FENOC- Bv 1 & 2, DBNPS, PNPS - Acceptance of Requested Licensing Action - Request an Alternative to the ASME Code Case OMN-20, CAC Nos. MF7780, MF7781, MF7782, MF7783 ML16074A1232016-03-15015 March 2016 Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16060A0952016-03-0202 March 2016 Acceptance of License Amendment Request to Revise Technical Specifications Requirements for the Radioactive Effluent Controls Program (CAC No. MF7351)(L-16-030) ML16056A2532016-02-26026 February 2016 Acceptance of License Amendment Request to Change the Emergency Plan by Revising the Emergency Action Level Scheme ML15036A4022015-03-0303 March 2015 DAVIS-BESSE Nuclear Power Station, Unit No. 1 - Acceptance Review Concerning Type C Test Intervals (TAC No. MF5433) (L-14-407) ML15036A4512015-02-13013 February 2015 Acceptance Review Concerning Revision of Containment Spray Nozzle Surveillance Frequency (TAC No. MF5483)(L-14-405) ML15040A7182015-02-13013 February 2015 Acceptance Review Concerning Cyber Security Implementation Plan Milestone 8 Completion Date (TAC No. MF5557) (L-14-421) ML14323A5752014-12-0303 December 2014 Unit No.1 - Acceptance Review Concerning Change to Definition of Shutdown Margin (TAC No. MF4791)(L-14-137) ML14323A6312014-12-0303 December 2014 Acceptance Review Concerning Revision to Safety Limit Minimum Critical Power Ratio (TAC No. MF5007)(L-14-325) ML14310A8532014-11-0606 November 2014 E-mail from J. Whited to P. Lashley Beaver Valley Power Station Unit 1 Acceptance of Requested Licensing Action Relief Request 1TYP-4-RV-04 ML14240A5882014-08-28028 August 2014 E-mail from J.Whited to P.Lashley Acceptance Review of FENOC Relief Request BV3-N-789 for Beaver Valley Power Station Units 1 and 2 ML14224A2212014-08-14014 August 2014 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation (Tac MF4213) ML14213A4182014-08-0505 August 2014 Acceptance Review Concerning Change to Pressure-Temperature Curves (TAC No. MF4351)(L-14-150) ML14142A0832014-05-22022 May 2014 E-mail from J. Whited to T. Lentz Acceptance of BVPS LAR to Extend Containment Leakage Test Frequency ML14120A4592014-05-13013 May 2014 Acceptance Review Concerning Notice of Impracticality Concerning Vessel Skirt (TAC MF3666)(L-14-105) ML14108A4082014-04-22022 April 2014 Acceptance of Requested Licensing Action License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Generating Plants ML13326A7512013-11-22022 November 2013 Acceptance of Requested Licensing Action Adoption of TSTF-425 ML1210904752012-04-18018 April 2012 Acceptance Review of Proposed BVPS Emergency Preparedness Plan Using Nuclear Energy Institute 99-01, Revision 5 ML1202304412012-01-23023 January 2012 Acceptance Review Email, Relief Request for Alternative Examination Requirements for Reactor Vessel Sage-End Welds ML1135402602011-12-19019 December 2011 Acceptance Review Results BVPS-1 and 2 Relief Request VRR1 (ME7684 and ME7685) ML1132900482011-11-25025 November 2011 Acceptance Review Results for Perry Nuclear Power Plant Relief Request IR-049, Revision 1 ML1127800542011-10-0303 October 2011 Acceptance Review Results for Fenco License Amendment Request Changes to LLC ML1126404122011-09-20020 September 2011 Acceptance Review Results for VC Summer Relief Request (ME6879) ML1117515752011-06-23023 June 2011 Acceptance Review Results for Davis-Besse License Amendment Changes to Technical Specifications 5.5.8 ML1108804692011-03-29029 March 2011 Acceptance Review Results Regarding Relief Request VRR3, VRR4, and VRR5 (ME5749, ME5750, ME5752, ME5781, and ME5782) 2022-11-16
[Table view] Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23261B0192023-09-25025 September 2023 Aging Management Audit Plan Regarding the License Renewal Application Review ML23261C3642023-09-25025 September 2023 License Renewal Application Online Reference Portal ML23256A3592023-09-22022 September 2023 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Energy Harbor Nuclear Corp. Application for License Renewal IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report 2024-02-02
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 20, 2017
SUBJECT:
FENOC FLEET-BEAVER VALLEY POWER STATION, UNIT NOS. 1, AND 2; DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1, AND PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - RESULTS OF ACCEPTANCE REVIEW OF THE EXEMPTION REQUEST RE: EXEMPTION FROM THE DEFINITION OF PHYSICAL BARRIER IN 10 CFR 73.2 FOR PHYSICAL SECURITY PLANS (CAC NOS. MG0010, MG0011, MG0012, AND MG0013)
Dear Mr. Belcher:
By letter dated July 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17200D139), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted an exemption request for Renewed Facility Operating Licenses for the Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear PowerStation, Unit No. 1, and Facility Operating License for Perry Nuclear Power Plant, Unit 1.
The licensee requested the permanent exemption pursuant to Title 1O of the Code of Federal Regulations (10 CFR) Section 73.5, "Specific exemptions," from a requirement of 10 CFR 73.2, "Definitions" for "Physical Barrier." The regulation requires, in part, fences topped by three strands or more of barbed wire or similar material on brackets be angled inward or outward between 30 and 45 degrees from the vertical. An exemption is requested since not all protected area physical barrier fencing sections meet this requirement.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC or Commission) staff's acceptance review of the proposed exemption request. The acceptance review was performed to determine if there is proper regulatory basis and 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.
Section 73.5 of 10 CFR, "Specific exemptions," states that the Commission may grant exemptions from the requirements of the regulations of this part provided the following specific criteria are met: (1) the exemption is authorized by law, (2) the exemption will not endanger life or property or the common defense and security, and (3) the exemption is otherwise in the public interest. Additionally, the categorical exclusion requirement in 10 CFR 51.22(c)(25),
states that to meet the requirements for the categorical exclusion in accordance with 10 CFR 51.22(c)(25), the exemption must meet the following: (i) no significant hazards consideration determination ; (ii) no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) no significant increase in individual or cumulative public or occupational radiation exposure; (iv) no significant construction impact; (v) no significant increase in the potential for or consequences from radiological accidents; and (vi) the
S. Belcher requirements from which the exemption is sought involves safeguards plans or other requirements of an administrative, managerial or organizational nature.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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 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 400 hours16.667 days <br />2.381 weeks <br />0.548 months <br /> to complete. The staff expects to complete this review by the requested date of July 31, 2018. 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 staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. 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 at (301) 415-3308.
Sincerely,
~~
~
Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-346, 50-412, and 50-440 cc: Distribution via ListServ
ML17262A723 *by e-mail OFFICE DORL/LPL3/PM DORL/LPL3/LA DLR/RERP/BC(*) NSIR/DPCP/RSB/BC(*)
NAME BVaidya SRohrer BBeasley (WRautzen for) ARivera (DGordon for)
DATE 09/20/17 09/20/17 08/01/17 07/28/17 OFFICE DORL/LPL3/BC DORL/LPL3/PM NAME DWrona (KGreen for) BVaidya DATE 09/20/17 09/20/17