|
|
Line 24: |
Line 24: |
|
| |
|
| ==Dear Mr. Freeman:== | | ==Dear Mr. Freeman:== |
| On November 4, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Seabrook Station, Unit 1. The inspection covered one or more of the key attributes of the security cornerstone of the NRC | | On November 4, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Seabrook Station, Unit 1. 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 December 12, 2011, with Mr. James Tucker, and other members of your staff. |
| =s Reactor Oversight Process. The enclosed inspection report documents the inspection results which were discussed on December 12, 2011, with Mr. James Tucker, and other members of your staff. | |
|
| |
|
| The inspection examined activities conducted under your license as they relate to security and compliance with the Commission | | 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. |
| =s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. | |
|
| |
|
| One NRC identified finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) was identified during this inspection. The deficiency was promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the area. | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| | |
| | One NRC identified finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) was identified during this inspection. |
| | |
| | The deficiency was promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the area. |
|
| |
|
| The finding was determined to involve a violation of NRC requirements. | | The finding was determined to involve a violation of NRC requirements. |
Line 38: |
Line 40: |
| Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Director, Office of Nuclear Security and Incident Response; the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Seabrook Station. One Cross-Cutting aspect was assigned to a finding in the area of Human Performance, because the licensee did not use conservative assumptions in its decision making [H.1(b)]. If you disagree with a Cross-Cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Director, Office of Nuclear Security and Incident Response; and to the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response. | | Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Director, Office of Nuclear Security and Incident Response; the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Seabrook Station. One Cross-Cutting aspect was assigned to a finding in the area of Human Performance, because the licensee did not use conservative assumptions in its decision making [H.1(b)]. If you disagree with a Cross-Cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Director, Office of Nuclear Security and Incident Response; and to the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response. |
|
| |
|
| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Managem ent System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's |
| | "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| | |
| | However, the material enclosed herewith contains safeguards information as defined by 10 CFR 73.21 and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. 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 website at http://www.nrc.gov/reading-rm/adams.html. If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. |
|
| |
|
| However, the material enclosed herewith contains safeguards information as defined by 10 CFR 73.21 and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Pub lic Document Room or from the NRC's document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html. If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, if security-related information is necessary to provide an acceptable response, please mark your entire response security-related information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
| | Otherwise, if security-related information is necessary to provide an acceptable response, please mark your entire response security-related information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
|
| |
|
| Sincerely, | | Sincerely, |
| /RA/ | | /RA/ |
| Robert C. Johnson, Chief | | Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket No. 50-443 License No. NPF-86 Nonpublic Enclosure: Inspection Report 05000443/2011202 w/Attachment: Supplemental Information cc w/ encl: J. Tucker, NextEra Energy Seabrook, LLC A. Silakoski, Florida Power and Light Company cc w/o encl: M. Nazar, Florida Power and Light Company M. OKeefe, NextEra Energy Seabrook, LLC |
| | |
| Security Performance Evaluation Branch | |
| | |
| Division of Security Operations Office of Nuclear Security and Incident Response | |
| | |
| Docket No. 50-443 License No. NPF-86 | |
| | |
| Nonpublic Enclosure: Inspection Report 05000443/2011202 w/Attachment: Supplemental Information | |
| | |
| cc w/ encl: J. Tucker, NextEra Energy Seabrook, LLC A. Silakoski, Florida Power and Light Company cc w/o encl: M. Nazar, Florida Power and Light Company M. O'Keefe, NextEra Energy Seabrook, LLC | |
| }} | | }} |
|
---|
Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024 Integrated Inspection Report 05000443/2024003 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24303A0352024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000443/20244022024-10-17017 October 2024 Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only) L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024 Core Operating Limits Report for Reload Cycle 24 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes ML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, 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 Applications2024-03-13013 March 2024 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 ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) 2024-09-25
[Table view] |
Text
ary 26, 2012
SUBJECT:
SEABROOK STATION, UNIT 1 - NRC SECURITY BASELINE INSPECTION REPORT 05000443/2011202
Dear Mr. Freeman:
On November 4, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Seabrook Station, Unit 1. 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 December 12, 2011, with Mr. James Tucker, 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.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
One NRC identified finding of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) was identified during this inspection.
The deficiency was promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspectors left the area.
The finding was determined to involve a violation of NRC requirements.
If you contest any non-cited violation in the enclosed report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Director, Office of Nuclear Security and Incident Response; the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response; and the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Seabrook Station. One Cross-Cutting aspect was assigned to a finding in the area of Human Performance, because the licensee did not use conservative assumptions in its decision making H.1(b). If you disagree with a Cross-Cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Director, Office of Nuclear Security and Incident Response; and to the Branch Chief, Security Performance Evaluation Branch, Office of Nuclear Security and Incident Response.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's
"Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains safeguards information as defined by 10 CFR 73.21 and its disclosure to unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954, as amended. 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 website at http://www.nrc.gov/reading-rm/adams.html. If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Otherwise, if security-related information is necessary to provide an acceptable response, please mark your entire response security-related information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Robert C. Johnson, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket No. 50-443 License No. NPF-86 Nonpublic Enclosure: Inspection Report 05000443/2011202 w/Attachment: Supplemental Information cc w/ encl: J. Tucker, NextEra Energy Seabrook, LLC A. Silakoski, Florida Power and Light Company cc w/o encl: M. Nazar, Florida Power and Light Company M. OKeefe, NextEra Energy Seabrook, LLC