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| {{#Wiki_filter:==SUBJECT:== | | {{#Wiki_filter:W EFFICIAT USE ENLY SECURITY RETATED INFERMATION UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406.1415 September L9, 20LL EA-11-130 Mr. Thomas Vice President Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, New York 13093 SUBJECT: FINAL SIcNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FtNDtNG [NRC TNSPECTTON REPORT NOS. 050002201201M04; 05000410120114041-NINE MILE POINT NUCLEAR STATION |
| FINAL SIcNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FtNDtNG [NRC TNSPECTTON REPORT NOS. 050002201201M04; 05000410120114041-NINE MILE POINT NUCLEAR STATION | |
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| ==Dear Mr. Lynch:== | | ==Dear Mr. Lynch:== |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 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 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 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report 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 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 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 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) 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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 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)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 2024-09-04
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W EFFICIAT USE ENLY SECURITY RETATED INFERMATION UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406.1415 September L9, 20LL EA-11-130 Mr. Thomas Vice President Nine Mile Point Nuclear Station, LLC P. O. Box 63 Lycoming, New York 13093 SUBJECT: FINAL SIcNIFICANCE DETERMINATION FOR A SECURITY-RELATED GREEN FtNDtNG [NRC TNSPECTTON REPORT NOS. 050002201201M04; 05000410120114041-NINE MILE POINT NUCLEAR STATION
Dear Mr. Lynch:
This letter provides you with the final significance determination for a finding preliminarily determined to be of at least low to moderate security significance (greater than Green). The finding was identified during a U.S. Nuclear Regulatory Commission (NRC) security baseline inspection conducted at the Nine Mile Point Nuclear Station (Nine Mile Point) from May 23 - 27, 2011, and was presented at an exit meeting held on May 27 , 2011. The finding was discussed in detail in NRC Inspection Report 0500022012011403 and 0500041012011403, issued on July 6, 2011 (ADAMS Accession No. ML1118702891).
Nine Mile Point took immediate corrective actions to address any security-related vulnerability associated with this finding before the NRC inspectors left the site. The nature of security-related findings is considered sensitive information and is not included in this letter, but is described in the non-public enclosure.
The NRC July 6, 2011,letter also offered Nine Mile Point the opportunity to attend a Regulatory Conference or reply in writing to provide its position on the facts and assumptions the NRC used to arrive at the finding and itJ security significance.
In a letter dated August 5,20112, Nine Mile Point provided additional information regarding the finding and also described Nine Mile Point's assessment of the significance of the finding. On August 4 - 5, 2011, NRC Region I conducted an additional on-site review at Nine Mile Point and re-evaluated the finding to confirm the information provided in Nine Mile Point's August 5,2011 letter.When separated from its Enclosure, this document is DECONTROLLED.
1 Designation in parentheses refers to an Agency-wide Documents Access and Management System (ADAMS) accession number. The inspection report cover letter is publicly-available using the accession number in ADAMS. The report is not publicly-available because it contains security-related information.
'The letter is not publicly-available because it contains security-related information.
oFFIGINt USE ENtY SEGURITY RETATEB INFERMNTION EFFIEIAT USE ENtY SEEURTY RETATED INFERMATION After considering the information developed during the inspection and the additional on-site NRC review, as well as the information provided by Nine Mile Point in its August 5,2011, letter, the NRC has determined that the inspection finding is of very low security significance and should be characterized as Green. The NRC has also determined that the condition is a violation of NRC regulations.
The NRC is treating the issue as a non-cited violation (NCV) in accordance with Section 2.3.2.a of the NRC Enforcement Policy because: 1) the violation was of very low security significan ce; 2) Nine Mile Point restored compliance immediately upon identification of the issue; 3) Nine Mile Point entered the issue into its corrective action program;and, 4) the NRC determined that the violation was neither repetitive nor willful. The basis for the NRC significance determination and discussion of the violation are provided in the attached Enclosure, which also contains Security-Related Information and, therefore, is non-public.
lf you contest this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with copies to the Regional Administrator Region 1; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Nine Mile Point.Additionally, in the letter dated August 5,.2011, Nine Mile Point disputed the cross-cutting aspect that the NRC had assigned to the finding, as described in the inspection report.However, during a follow-up conversation with NRC Region I on August 31, 2011, Nine Mile Point rescinded its dispute. Therefore, the cross-cutting aspect in the area of human performance (decision making, H.1(b)) that was previously assigned to this finding remains unchanged.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room located at NRC Headquarters in Rockville, MD, and from the NRC's document system, the Agency-wide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(dX1), and its disclosure to unauthorized individuals could present a security vulnerability, Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web s ite at http ://www. n rc. o ov/read i no -rm/ad am s. htm l.EFFIENT USE ENtY SECURITY RETATED INFORMATIEN EFFIGNT USE ENtY SECURITY RETATED INFERMNTION lf Security-Related Information is necessary to provide an aoceptable response, if you choose to submit one, please follow the instructions for withholding in 10 CFR 2.390(bX1).
In accordance with 10 CFR 2.390(bxlXii), the NRC is waiving the affidavit requirements for your response.
Sincerely, (\. {)rr'Jl-"ppz James M. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-220; 50-410 License Nos. DPR-63: NPF-69 Enclosure:
As Described (coNTArNS OFFlClAL USE ONLy - SECURTTY RELATED INFORMATION (OUO-SRl))
cc w/encl: w/OUO-SRl:
A. Verno, Manager Nuclear Security R. Frazier, Homeland Security Advisor, NY State Dept. of Homeland Security F. Murray, President and CEO, NY State Energy Research and Development Authority cc w/o encl: Mo OUO-SRI: Distribution via ListServ EFFIENT USE ENLY SECURLTY RETATED INFERMNTIEN