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| The NRC staff has determined that the criteria for processing the proposed amendment on exigent basis has not been satisfied. Specifically, the first criterion listed above has not been satisfied. Entering an unusual event for the site due to higher than normal lake levels would not have a tangible and deleterious effect on radiological safety, general safety of the public, plant personnel safety, or plant operation that warrant quick action that would shorten the normal prior public comment period of 30 days. | | The NRC staff has determined that the criteria for processing the proposed amendment on exigent basis has not been satisfied. Specifically, the first criterion listed above has not been satisfied. Entering an unusual event for the site due to higher than normal lake levels would not have a tangible and deleterious effect on radiological safety, general safety of the public, plant personnel safety, or plant operation that warrant quick action that would shorten the normal prior public comment period of 30 days. |
| 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 amendments 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. | | 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 amendments 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 40 hours to complete. The NRC staff expects to complete this review by the end of June 2017 (i.e., approximately 1 month). 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. | | Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately [[estimated NRC review hours::40 hours]] to complete. The NRC staff expects to complete this review by the end of June 2017 (i.e., approximately 1 month). 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. |
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| B. Hanson 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. | | B. Hanson 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. |
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Category:Acceptance Review Letter
MONTHYEARML24008A2622024-01-0808 January 2024 Acceptance Review Determination for Relief Request I5R-12, Concerning Installation of a FSWOL on RPV Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld ML23019A3092023-01-19019 January 2023 Acceptance Review Determination License Amendment Request to Adopt 10 CFR 50.69 Categorization Process ML23019A3032023-01-19019 January 2023 Acceptance Review Determination License Amendment Requets to Adopt TSTF-505 ML22252A1522022-09-0909 September 2022 Acceptance Review Determination Partial Adoption of TSTF-568 to Revise TS 3.3.1 for Primary Containment Oxygen Concentration ML22207A0122022-07-26026 July 2022 Acceptance Review Determination Revision to Alternative Source Term Analysis for Containment Leakage ML22173A0802022-06-22022 June 2022 E-mail Dated 6/22/2022, Acceptance of Requested License Amendment Request to Revise Surveillance Requirements to Reduce Number of Fast Starts of EDGs ML22075A0362022-03-16016 March 2022 Acceptance Review Determination - Relief Request CS-PR-02 Associated with Pump Periodic Verification Test of Core Spray System Pumps, E-mail Dated 3/16/2022 ML21278A6872021-10-0505 October 2021 Acceptance Review Determination - Relief Request GV-RR-10 ML21077A1772021-04-0808 April 2021 Withdrawal of Requested Exemption from Certain Requirement in 10 CFR 50.55a (Epids L-2021-LLE-0014, 0015, & 0016) ML21033A9432021-02-0202 February 2021 Correction to Acceptance of Requested License Amendment to Adopt Technical Specification Task Force Traveler 582 ML20294A4242020-10-20020 October 2020 Acceptance of Requested Licensing Action Relief Requests CTNSP-PR-01 and CS-PR-01 (EPIDs L-2020-LLR-0136 and L-2020-LLR-0137) ML20262H0322020-09-18018 September 2020 Acceptance Email of Requested Licensing Actions Concerning Surveillance Frequency for Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20262G9372020-09-17017 September 2020 Acceptance of Requested Licensing Action End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML19339E8542019-12-0505 December 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Adoption of Risk-Informed Completion Times ML19301C3162019-10-28028 October 2019 Acceptance of Requested Licensing Action Relief Request 2ISI - 014 ML18206A7172018-07-25025 July 2018 Acceptance of Requested Licensing Action Revision to Technical Specification for Primary Containment Oxygen Concentration ML18190A1402018-07-0909 July 2018 Acceptance of Requested Licensing Action Relief Requests I5R-05 and I4R-05 Threads in Flange ML18190A0922018-07-0606 July 2018 Acceptance of Requested Licensing Action Relief Requests I5R-06 and I4R-06 - Use of Encoded Phased Array ML18192B8582018-07-0606 July 2018 L-2018-LLR-0085 - Acceptance Email for RR BWRVIP Requirements 2018-07-06 ML18186A5352018-07-0505 July 2018 Acceptance of Requested Licensing Action Relief Requests I5R-04 and I4R-04 - N-513-4 ML18107A0252018-04-16016 April 2018 Acceptance of License Amendment Request Relocation of Surveillance Requirement Frequencies to Inservice Testing Program ML18071A1582018-03-12012 March 2018 Acceptance of License Amendment Request Concerning Proposed Changes to Remove Boraflex Credit ML17340A9542017-12-0505 December 2017 Acceptance of License Amendment Request Concerning Changes to Safety Limit Minimum Critical Power Ratios for Cycle 17 ML17192A1752017-07-11011 July 2017 Plants, Units 1 and 2; Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station, Units 1 and 2; R. E. Ginna - Acceptance of License Amendment Request to Revise Emergency Action Level Schemes ML17167A2192017-06-21021 June 2017 Acceptance of Requested Licensing Action Amendment to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 ML17143A0412017-05-23023 May 2017 Acceptance of Requested Licensing Action Amendments to Revise Emergency Action Level ML17143A2642017-05-23023 May 2017 Acceptance of Requested Licensing Action Amendment to Revise Emergency Action Level ML17117A3622017-05-0202 May 2017 Acceptance of Requested Licensing Action Amendment to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-283A, Revision 3 ML17083A3652017-03-31031 March 2017 Acceptance of Requested Licensing Action Relief Request to Utilize Code Case N-702 ML17058A4342017-03-0202 March 2017 Acceptance of Requested Licensing Action Reduce Steam Dome Pressure in Reactor Core Safety Limits ML17019A0532017-01-31031 January 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Reduce Steam Dome Pressure in Reactor Core Safety Limits ML17017A1092017-01-24024 January 2017 Acceptance of Requested Licensing Action Partial Length Fuel Rod Burnup ML13022A3252013-01-22022 January 2013 MF0345 - Acceptance of Requested Licensing Action License Amendment Request- Relocation of PT Limit Curves to PTLR ML12222A0292012-08-0909 August 2012 Correction to Acceptance Letter - Nine Mile Point Nuclear Station, Unit No. 1 - License Amendment Request Pursuant to 10CFR 50.90: Adoption of NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generat ML1213004912012-05-0909 May 2012 ME8534, E-mail to Licensee for Acceptance of Relief Request RR-PTRR-02 ML1115905522011-06-0707 June 2011 E-mail from R.Guzman to J.Dosa - Acceptance Review Determination for Request to Revise Emergency Action Levels in Accordance with NEI-99-01 ML1109502922011-04-0505 April 2011 Acceptance Review Determination Relief Request for Repair of CRD Housing Penetrations ML1036103342011-01-0505 January 2011 Acceptance Review Determination of License Amendment Request Revisions to Average Power Range Monitor Instrumentation Operability Requirements TS 3.6.2 ML1012601662010-05-0606 May 2010 E-mail from R. Guzman to J. Dosa Acceptance Review Revised Questions for License Amendment Requesting 14 Day Completion Time Extension for Inoperable EDG ML1011803792010-04-28028 April 2010 Unit No.2 - E-mail from R. Guzman to J. Dosa Acceptance Review for LAR - Inoperable DG 14-Day Completion Time Extension ML1011209872010-04-22022 April 2010 E-mail from R. Guzman to J. Dosa Acceptance Review Determination for LAR to Modify Technical Specifications for Inoperable Snubbers and Add LCO 3.0.8 ML0918906662009-07-0808 July 2009 E-mail from R. Guzman to J. Dosa Acceptance Review Results of NMP2 Extended Power Uprate Application ML0905703152009-02-26026 February 2009 Acceptance Review Constellation and Edf Development - Application for Approval of License Transfers and Conforming License Amendment Request-Calvert Cliffs Nuclear Power Plant 1 and 2, Nine Mile Point Nuclear Station 1 and 2, and R.E. Ginna 2024-01-08
[Table view] Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 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 NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 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 NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 23, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT TO REVISE EMERGENCY ACTION LEVEL (CAC NO. MF9722)
Dear Mr. Hanson:
By letter dated May 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17139C739), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for the James A. FitzPatrick Nuclear Power Plant. The proposed amendment would revise emergency action level HU1 .5 by replacing the maximum lake water level with the phrase, "A hazardous event that results in onsite conditions sufficient to prohibit the plant staff from accessing the site via personal vehicles."
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC or the Commission) staff's acceptance review of this amendment 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.
Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
In its letter dated May 19, 2017, Exelon requested that the proposed amendments be processed on an exigent basis pursuant to 10 CFR 50.91 (a)(6) and be approved by June 2, 2017. In order for a license amendment to be processed on an exigent basis, the following criteria from 10 CFR 50.91 (a)(6) need to be satisfied:
- 1. " ... exigent circumstance exist, in that a licensee and the Commission must act quickly ... "
- 2. " ... time does not permit the Commission to publish a Federal Register notice allowing 30 days for prior public comment ... "
- B. Hanson 3. " ... [Commission] determines that the amendment involves no significant hazards consideration ... "
- 4. " ... [Commission] use its normal public notice and comment procedures
... if it determines that the licensee has failed to use its best efforts to make a timely application ... "
Exelon's bases for exigent circumstances include:
- Unexpected conditions in the Lake Ontario and Ottawa River drainage basins and a change in lake level management strategy in 2016 have resulted in Lake Ontario water level being managed at values higher than historic norms.
- The lake level will continue to increase such that Lake Ontario level may exceed the unusual event threshold by June 12, 2017, based on forecasted.
- The site may unnecessarily enter an unusual event for a prolonged period of time which would compound existing public stress and concern caused by the local environmental conditions.
The NRC staff has determined that the criteria for processing the proposed amendment on exigent basis has not been satisfied. Specifically, the first criterion listed above has not been satisfied. Entering an unusual event for the site due to higher than normal lake levels would not have a tangible and deleterious effect on radiological safety, general safety of the public, plant personnel safety, or plant operation that warrant quick action that would shorten the normal prior public comment period of 30 days.
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 amendments 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 40 hours1.667 days <br />0.238 weeks <br />0.0548 months <br /> to complete. The NRC staff expects to complete this review by the end of June 2017 (i.e., approximately 1 month). 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.
B. Hanson 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 the James A. FitzPatrick Nuclear Power Plant Project Manager, Booma Venkataraman, at (301) 415-2934 or Booma.Venkataraman@nrc.gov.
Sincerely,
~-~\ ~,
1~~L~
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333 cc: Distribution via Listserv
ML17143A264 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1 PM NAME BVenkataraman LRonewicz JDanna BVenkataraman DATE 05/23/2017 05/23/2017 05/23/2017 05/23/2017