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| | issue date = 09/13/2016 | | | issue date = 09/13/2016 |
| | title = NRC Material Control and Accounting Program Inspection Report 05000266/2016406; 05000301/2016406 | | | title = NRC Material Control and Accounting Program Inspection Report 05000266/2016406; 05000301/2016406 |
| | author name = Cameron J L | | | author name = Cameron J |
| | author affiliation = NRC/RGN-IV/DRS | | | author affiliation = NRC/RGN-IV/DRS |
| | addressee name = Coffey R | | | addressee name = Coffey R |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 September 13, 2016 | | {{#Wiki_filter:UNITED STATES ptember 13, 2016 |
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| Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
| | ==SUBJECT:== |
| | | POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT 05000266/2016406; 05000301/2016406 |
| SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2-NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT 05000266/2016406; 05000301/2016406 | |
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| ==Dear Mr. Coffey:== | | ==Dear Mr. Coffey:== |
| On September 1, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the Security Cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results which were discussed on September 1, 2016, with Mr. J. Helfenberger and other members of your staff. The inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license. | | On September 1, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the Security Cornerstone of the NRC's Reactor Oversight Process. |
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| The inspector reviewed selected procedures and records, observed material storage conditions, and interviewed personnel. Based on the results of this inspection, no findings of more than minor significance were identified. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://nrv.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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| However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) 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 PARS component of NRC's
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| Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from public disclosure under 10 CFR 2.390" in accordance with
| | The enclosed inspection report documents the inspection results which were discussed on September 1, 2016, with Mr. J. Helfenberger and other members of your staff. |
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| 10 CFR 2.390(d)(1)(ii), the NRC is waiving the affidavit requirements for your response.
| | The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| Sincerely,/RA/ Jamnes L. Cameron, Chief Branch 4 Division of Reactor Projects
| | The inspector reviewed selected procedures and records, observed material storage conditions, and interviewed personnel. Based on the results of this inspection, no findings of more than minor significance were identified. |
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| Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://nrv.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Non-public | | However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) 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 PARS component of NRCs Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
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| ===Enclosure:===
| | Sincerely, |
| IR 05000266/2016406; 05000301/2016406 cc: B. Kopetsky, Security Manager B. Woyak, Licensing Manager M. Nazar, Executive VP, Nuclear Division and Chief Nuclear Officer cc w/o encl: Distribution via LISTSERV OFFICAL USE ONLY | | /RA/ |
| | Jamnes L. Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27 Non-public Enclosure: |
| | IR 05000266/2016406; 05000301/2016406 cc: B. Kopetsky, Security Manager B. Woyak, Licensing Manager M. Nazar, Executive VP, Nuclear Division and Chief Nuclear Officer cc w/o encl: Distribution via LISTSERV |
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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024
Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010
IR 05000266/20230042024-02-0101 February 2024
Integrated Inspection Report 05000266/2023004 and 05000301/2023004
ML24030A0352024-01-30030 January 2024
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024
Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements
L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
ML24005A3242024-01-24024 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23352A2752024-01-23023 January 2024
Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program
L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023
Quality Assurance Topical Report (FPL-1) Revision 30 Update
L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023
Subsequent License Renewal Application - Third Annual Update
L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023
Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023
Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule
IR 05000266/20234022023-11-14014 November 2023
Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402
ML23279A0672023-11-0909 November 2023
Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval
IR 05000266/20230032023-10-16016 October 2023
Integrated Inspection Report 05000266/2023003 and 05000301/2023003
ML23346A1322023-10-0606 October 2023
Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published
L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023
License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML23243A9102023-09-0606 September 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
IR 05000266/20235012023-08-29029 August 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501
ML23208A2262023-08-28028 August 2023
Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter
ML23208A0952023-08-28028 August 2023
Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach
IR 05000266/20230052023-08-24024 August 2023
Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005)
ML23160A0642023-08-21021 August 2023
Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System
L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023
Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update
ML23221A0522023-08-0909 August 2023
Confirmation of Initial License Examination, March 2024
L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
ML23201A0872023-08-0303 August 2023
Audit Plan in Support of Review of License Amendment
L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023
Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections
IR 05000266/20230022023-07-18018 July 2023
Integrated Inspection Report 05000266/2023002 and 05000301/2023002
IR 05000266/20234012023-07-13013 July 2023
Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401
L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023
Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023
10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval
ML23171B1062023-06-21021 June 2023
Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2
ML23163A2422023-06-13013 June 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023
Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023
Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response
ML23103A1332023-06-0101 June 2023
Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023
NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal
ML23118A1762023-05-0404 May 2023
Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191
IR 05000266/20230012023-05-0101 May 2023
Integrated Inspection Report 05000266/2023001 and 05000301/2023001
ML23114A1222023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023
2022 Annual Monitoring Report
L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
2024-02-05
[Table view] |
Text
UNITED STATES ptember 13, 2016
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT 05000266/2016406; 05000301/2016406
Dear Mr. Coffey:
On September 1, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the Security Cornerstone of the NRC's Reactor Oversight Process.
The enclosed inspection report documents the inspection results which were discussed on September 1, 2016, with Mr. J. Helfenberger and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed material storage conditions, and interviewed personnel. Based on the results of this inspection, no findings of more than minor significance were identified.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://nrv.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) 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 PARS component of NRCs Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Jamnes L. Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27 Non-public Enclosure:
IR 05000266/2016406; 05000301/2016406 cc: B. Kopetsky, Security Manager B. Woyak, Licensing Manager M. Nazar, Executive VP, Nuclear Division and Chief Nuclear Officer cc w/o encl: Distribution via LISTSERV
