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MONTHYEARML11130A1502011-05-0606 May 2011 Revision to Nine Mile Point Units 1 and 2 Emergency Action Levels in Accordance with NEI 99-01, Methodology for Development of Emergency Action Levels, Revision 5 Project stage: Request 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 Project stage: Acceptance Review ML1132004002011-11-17017 November 2011 Request for Additional Information Revision to EAL in Accordance with NEI 99-01, Revision 5 Project stage: RAI ML12045A3962012-01-13013 January 2012 EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 2 of 2 Project stage: Other ML12045A3942012-01-13013 January 2012 EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 1 of 2 Project stage: Other ML12045A3932012-01-13013 January 2012 EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 2 of 2 Project stage: Other ML12045A3922012-01-13013 January 2012 EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 1 of 2 Project stage: Other ML12045A3912012-01-13013 January 2012 EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 2 of 2 Project stage: Other ML12045A3902012-01-13013 January 2012 EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 1 of 2 Project stage: Other ML12045A3892012-01-13013 January 2012 EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 1 of 2 Project stage: Other ML12045A3872012-01-13013 January 2012 EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 2 of 2 Project stage: Other ML12045A2552012-01-13013 January 2012 Updated Revision to Nine Mile Point, Units 1 & 2 - Emergency Action Levels, Attachments 4 and 5 Project stage: Other ML12045A2422012-01-13013 January 2012 Response to NRC Request for Additional Information Regarding the Proposed Change to the Emergency Action Level Scheme, Attachment 1 Project stage: Response to RAI ML12045A2412012-01-13013 January 2012 Revision to Emergency Action Levels in Accordance with NEI 99-01, Methodology for Development of Emergency Action Levels, Revision 5 - Response to NRC Request for Additional Information Project stage: Response to RAI ML1209900032012-04-27027 April 2012 Emergency Action Level Scheme Change to Nuclear Energy Institute Standard 99-01, Revision 5 Project stage: Other 2011-06-07
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Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
[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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 17, 2011 Mr. Ken Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2 -RE: REVISION TO EMERGENCY ACTION LEVELS IN ACCORDANCE WITH NUCLEAR ENERGY INSTITUTE (NEI) 99-01, METHODOLOGY FOR DEVELOPMENT OF EMERGENCY ACTION LEVELS, REVISION 5 (TAC NOS. ME6221 AND ME6222)
Dear Mr. Langdon:
By letter dated May 6, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) requested approval to implement revised emergency action levels (EALs) at Nine Mile Point, Unit No. 1 (NMP1) and Nine Mile Point, Unit No.2 (NMP2). The EAL scheme used at both NMP1 and NMP2 would change from NUMARC/NESP-007, "Methodology for Development of Emergency Action Levels," Revision 2, to the scheme delineated in NEI 99-01, "Methodology for Development of Emergency Action Levels," Revision 5. The Nuclear Regulatory Commission staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on November 9, 2011, and it was agreed that your response would be provided by January 13, 2012. Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosure:
As stated cc w/enci: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2 EMERGENCY ACTION LEVEL SCHEME CHANGE TO NEI 99-01, REVISION 5 DOCKET NOS. 50-220 AND 50-410 By letter dated May 6,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11130A 150), Nine Mile Point Nuclear Station, LLC (NMPNS) requested prior approval of a revised emergency action level (EAL) scheme for Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2). The Nuclear Regulatory Commission (NRC) staff is reviewing the request letter and has determined that additional information as requested below will be needed to support its review. NMPNS's letter stated that the current NMP1 and NMP2 EAL schemes are based on generic development guidance from NUMARC/NESP-007, "Methodology for Development of Emergency Action Levels," Revision 2, dated January 1992 (ADAMS Accession No. ML041120174).
Since 1992, numerous enhancements and clarification efforts have been made to the generic EAL development guidance resulting in the most latest document, Nuclear Energy Institute (NEI) 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," (ADAMS Accession No. ML080450149), which was found to be acceptable for use as generic EAL development guidance by the NRC staff by letter dated February 22,2008 (ADAMS Accession No. ML080430535).
The proposed EAL schemes were developed using the generic development guidance from NEI 99-01, Revision 5 with numerous differences and deviations based upon design criteria applicable to the site as well as licensee preferences for terminology, format, and other licensee desired modifications to the generic EAL scheme provided in NEI 99-01, Revision 5. Definitions:
Please provide site-specific definitions for the following: Containment Closure, and Vital Area. Additionally, NMP2 definition of "Hostile Action" contains the wording "take FIREs" vice the wording "take HOSTAGEs" endorsed in NEI 99-01 (Revision 5). Please provide further justification for difference or revise consistent with endorsed guidance. RA2.2 (NMP2): NMP1 EAL RA2.2 has procedural guidance listed to determine that the fuel is uncovered.
For NMP2, please clarify methods of determining that the fuel is uncovered (e.g., video cameras) and revise the EAL accordingly.
Enclosure
-2 RU2.1 (NMP2): Please clarify whether the following radiation monitors are applicable to this EAL and revise accordingly: 2HVR*RE 14A, and 2HVR*RE14B. RU2.2: Please clarify whether installed plant radiation monitors have the range to declare this EAl. HA 1.1: Please clarify the following: Timeliness for confirmation by the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) seismic instrumentation; and Whether corroboration by the Nation Earthquake Information Center (NEIC) is used for declaration of this EAl. The plant-specific basis has information related to corroboration by the NEIC; however, this information was removed from the EAL and described as a deviation from the endorsed guidance. HA1.2 and HU1.2 (NMP1): NMP2 basis provides that winds can be measured up to 100 miles-per-hour (mph). Please clarify whether NMP1 instrumentation can measure winds of 90 mph as listed in the EAl. HA 1.5 and HU1.5: Please clarify how and where the site-specific water level is read. HU2.1: The standard EAL scheme required by 10 CFR 50.47(b)(4), and endorsed by the NRC (NEI 99-01, Revision 5), has the timing expectation well defined. Please explain the deviation from endorsed guidance or revise accordingly. HA3.1: Please confirm that the areas as listed in Table H-1 are required to be entered for safe operation or safe shutdown/cooldown per endorsed guidance.
If access to the area is unnecessary to operate the said equipment, then the table does not need the area listed. Additionally, the EAL wording is not in accordance with the endorsed guidance.
Please revise accordingly or justify how this EAL, as written, meets the intent of the guidance. HS5.1: The endorsed guidance (NEI 99-01, Revision 5) does not have a timing note associated with this EAl. Please justify why Note 4 is applicable to this EAL or revise accordingly. CA 1.1 (NMP2): Please clarify whether or not a typo exists for the electrical bus designation and revise accordingly. CU6.1 and SU6.1: Please explain how the "UHF radios" are acceptable for contacting the NRC in the required timeframe or revise table accordingly.
Additionally, please clarify whether the Control Room satellite phones, identified to meet this EAL criteria, are described in the NMPNS Emergency Plan.
SU1.1 (NMP2): Please justify why this EAL is missing the 15-minute timing information per endorsed guidance or revise accordingly. SA3.1: Please clarify the processes in place to prevent additional information related to reactor scram setpoints from being changed under another process (e.g., plant modifications, etc.) that may cause this technical bases document to be inadvertently made inaccurate. SU7.2 (NMP2): Please justify the difference between unit thresholds listed (NMP1: minutes I NMP2: > 15minutes) based on endorsed guidance or revise accordingly.
November 17,2011 Mr. Ken Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2 -RE: REVISION TO EMERGENCY ACTION LEVELS IN ACCORDANCE WITH NUCLEAR ENERGY INSTITUTE (NEI) 99-01, METHODOLOGY FOR DEVELOPMENT OF EMERGENCY ACTION LEVELS, REVISION 5 (TAC NOS. ME6221 AND ME6222)
Dear Mr. Langdon:
By letter dated May 6, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) requested approval to implement revised emergency action levels (EALs) at Nine Mile Point, Unit No.1 (NMP1) and Nine Mile Point, Unit No.2 (NMP2). The EAL scheme used at both NMP1 and NMP2 would change from NUMARC/NESP-007, "Methodology for Development of Emergency Action Levels," Revision 2, to the scheme delineated in NEI 99-01, "Methodology for Development of Emergency Action Levels," Revision
- 5. The Nuclear Regulatory Commission staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on November 9,2011, and it was agreed that your response would be provided by January 13, 2012. Sincerely, lraJ Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLI-1 R/F MNorris, NSIR RidsNrrPMNineMilePoint RidsNrrLASLittle RidsOGCRp RidsRgn1MailCenter RidsN rrAcrsAcnw&mMailCenter RidsNrrDorlLpl1-1 JAnderson, NSIR LPL1-1/PM RGuzman 11/16/11 e-mail. No substantial chan es made. LPL 1-1/LA NSIRlDPRlORLOB*
LPL1-1/BC S Little JAnderson NSalgado 11/16/11 10/27/11 11/17/11 OFFICIAL RECORD COPY