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| Section 50.34 of 10 CFR addresses the content of technical information required. | | 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. | | 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 1 O 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: | | In its letter dated May 19, 2017, Exelon requested that the proposed amendments be processed on an exigent basis pursuant to 1 O 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 ... " | | : 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] | | * B. Hanson 3. " ... [Commission] |
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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
MONTHYEARIR 05000220/20244022024-11-20020 November 2024 Material Control and Accounting Program Inspection Report 05000220/2024402 and 05000410/2024402 (Cover Letter Only) IR 05000410/20240032024-11-0808 November 2024 Integrated Inspection Report 05000220/1014003 and 05000410/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, 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 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater 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 2024-09-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 May 23, 2017
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. ML 17139C739), 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 1 O 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 1 O 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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 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.
Docket No. 50-333 cc: Distribution via Listserv Sincerely, James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation B. Hanson
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT TO REVISE EMERGENCY ACTION LEVEL (CAC NO. MF9722) DATED MAY 23, 2017 DISTRIBUTION:
Public LPL 1 R/F RidsACRS_MailCTR Resource RidsNrrDorl Resource RidsNrrDorlLpl1 Resource RidsNrrLALRonewicz Resource RidsNrrPMFitzPatrick Resource RidsRgn1 MailCenter Resource ADAMS Accession No.: ML 17143A264 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NAME BVenkataraman LRonewicz DATE 05/23/2017 05/23/2017 NRR/DORL/LPL 1/BC JDanna 05/23/2017 OFFICIAL RECORD COPY NRR/DORL/LPL 1 PM BVenkataraman 05/23/2017