Letter Sequence Acceptance Review |
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CAC:MF9836, (Approved, Closed) CAC:MF9837, (Approved, Closed) CAC:MF9838, (Approved, Closed) CAC:MF9839, (Approved, Closed) CAC:MF9840, (Approved, Closed) |
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MONTHYEARML17192A1752017-07-11011 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 Project stage: Acceptance Review ML17194B0822017-07-18018 July 2017 Independent Spent Fuel Storage Installation; Nine Mile Point, Units 1 and 2; and R. E. Ginna - Regulatory Audit for License Amendment Request to Revise Emergency Action Level Schemes (CAC Nos. MF9836-MF9840) Project stage: Other ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding Project stage: RAI ML18120A3202018-05-0707 May 2018 Independent Spent Fuel Storage Installation; Nine Mile Point 1 and 2; and R. E. Ginna Regulatory Audit Summary for License Amendment Request to Revise Emergency Action Level Schemes (CAC Nos. MF9836, MF9840; EPID L-2017-LLA-02) Project stage: Other NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. Project stage: Response to RAI ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes Project stage: Approval 2017-07-18
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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 ML23019A3032023-01-19019 January 2023 Acceptance Review Determination License Amendment Requets to Adopt TSTF-505 ML23019A3092023-01-19019 January 2023 Acceptance Review Determination License Amendment Request to Adopt 10 CFR 50.69 Categorization Process ML22269A4522022-09-22022 September 2022 R. E. Ginna Nuclear Power Plant - Acceptance Review: to Revise Technical Specifications (TS) TS 5.6.5, Core Operating Limits Report (COLR) 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 ML21281A1402022-01-14014 January 2022 Acceptance for Review of Proposed Alternative ISI-05-018 for Examinations of Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles ML21293A1332021-10-19019 October 2021 R. E. Ginna Nuclear Power Plant - Acceptance of Request for Exemption from the Biennial Emergency Preparedness Exercise Requirements in 10 CFR 50, Appendix E, Section IV.F.2.C ML21278A6872021-10-0505 October 2021 Acceptance Review Determination - Relief Request GV-RR-10 ML21152A1232021-06-0101 June 2021 Acceptance for Review of Proposed Alternative ISI-05-016 Involving Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (EPID L-2021-LLR-0037) (Email) 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 ML20335A5692020-11-30030 November 2020 R. E. Ginna Nuclear Power Plant - Acceptance Review: Alternative to ASME Code, Section XI ML20325A1002020-11-20020 November 2020 Acceptance Review: Force-on-Force Temporary Exemption Request 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) ML20294A4942020-10-20020 October 2020 R. E. Ginna Nuclear Power Plant - Acceptance Review: to Revise Technical Specifications for Steam Generator Tube Inspection Frequency ML20276A1032020-10-0202 October 2020 R. E. Ginna Nuclear Power Plant - Acceptance Review - Exemptions from 10 CFR 2.109(b), Effect of Timely Renewal Application 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 ML20106F2482020-04-15015 April 2020 Acceptance Review: R. E. Ginna Nuclear Power Plant to Implement WCAP, TSTF-411, and TSTF-418 ML20015A4992020-01-15015 January 2020 Acceptance of Requested Licensing Action Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances 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 ML19084A2872019-03-25025 March 2019 R. E. Ginna Nuclear Power Plant - Acceptance Review: Changes to Emergency Plan Staffing (EPID-L-2019-LLA-0053) ML19078A1262019-03-19019 March 2019 R. E. Ginna Nuclear Power Station - Acceptance Review: TS 5.5.15, Containment Leakage Testing Program, to Extend the Integrated Leakage Rate Testing Program Test Interval from 10 Years to 15 Years ML18304A1392018-10-30030 October 2018 Acceptance of Requested Licensing Action Risk-Informed Approach to Closure for Generic Safety Issue-191 (EPID L-2018-LLA-0222 and EPID L-2018-LLE-0013) ML18271A1372018-09-28028 September 2018 Acceptance of Requested Licensing Action Re Amendment to Relocate Emergency Operations Facility and Joint Information Center ML18249A0312018-09-0404 September 2018 R. E. Ginna Nuclear Power Plant - Acceptance Review: Relief Request ISI-18 to Extend the Reactor Pressure Vessel Inservice Inspection 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 ML18192B8582018-07-0606 July 2018 L-2018-LLR-0085 - Acceptance Email for RR BWRVIP Requirements 2018-07-06 ML18190A0922018-07-0606 July 2018 Acceptance of Requested Licensing Action Relief Requests I5R-06 and I4R-06 - Use of Encoded Phased Array ML18186A5352018-07-0505 July 2018 Acceptance of Requested Licensing Action Relief Requests I5R-04 and I4R-04 - N-513-4 ML18197A2262018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - Acceptance Review: License Amendment Request to Adopt - TSTF-547, Rev 1 Clarification of Rod Position Requirements ML18124A3162018-05-0404 May 2018 Acceptance of Requested Licensing Action Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 ML17340A9762017-12-0606 December 2017 R. E. Ginna Nuclear Power Plant - Acceptance Review to Revise Technical Specifications for Selected Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Channels to Incorporate Bypass Test Capability ML17340A9542017-12-0505 December 2017 Acceptance of License Amendment Request Concerning Changes to Safety Limit Minimum Critical Power Ratios for Cycle 17 ML17331A0082017-11-22022 November 2017 R. E. Ginna Nuclear Power Plant - E-mail Regarding Acceptance Review for Revise TSs Surveillance Requirement SR 3.8.4.3, DC Sources to Allow for a Modified Performance Discharge Test 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 2024-01-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1AND2; CALVERT CLIFFS INDEPENDENT SPENT FUEL STORAGE INSTALLATION; NINE MILE POINT NUCLEAR STATION, UNITS 1AND2; ANDRE. GINNA NUCLEAR POWER PLANT -ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY ACTION LEVEL SCHEMES (CAC NOS. MF9836-MF9840)
Dear Mr. Hanson:
By application dated May 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17164A149), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; and R. E. Ginna Nuclear Power Plant.
The amendments would revise the emergency plans by changing the emergency action level schemes for these facilities. The proposed changes are based on the Nuclear Energy lnstitute's (NEl's) guidance in NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors," which was endorsed by the U.S. Nuclear Regulatory Commission (NRG) by letter dated March 28, 2013 (ADAMS Accession No. ML12346A463).
Exelon's application also included a request to amend the materials license for the Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI). There is not a separate emergency plan for the ISFSI, as it is included in the emergency plan for the Calvert Cliffs Nuclear Power Plant.
The NRC staff's review of changes to the Calvert Cliffs Nuclear Power Plant emergency plan will include a review of changes related to the ISFSI. An amendment to the materials license for the Calvert Cliffs ISFSI is not required.
The purpose of this letter is to provide the results of the NRC 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.
B. Hanson Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license 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.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRG staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRG staff has estimated that the review of this licensing request will take approximately 700 hours29.167 days <br />4.167 weeks <br />0.959 months <br /> to complete. The NRC staff expects to complete this review by 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 NRG 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) 415-1380.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317, 50-318, 72-8, 50-220, 50-410, 72-1036, 50-244, and 72-67 cc: Distribution via Listserv
, ML17192A175 *via email OFFICE LPL3/PM LPL3/LA NMSS/DSFM/SFLB/BC LPL3/BC LPL3/PM NAME BPurnell SRohrer JMcKirgan~ DWrona BPurnell DATE 07/11117 07/11/17 07111/17 07/11/17 07/11117