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MONTHYEARML12159A3772012-06-0808 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident Project stage: RAI 2012-06-08
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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 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 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review 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 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-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations 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 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 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-2024-037, 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 ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) 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 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
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 8, 2012 Mr. Paul Freeman Site Vice President clo Michael O'Keefe Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SEABROOK STATION, UNIT NO.1 -REVIEW OF 60-DAY RESPONSE TO REQUEST FOR INFORMATION REGARDING RECOMMENDATION 9.3, OF THE NEAR-TERM TASK FORCE RELATED TO THE FUKUSHIMA DAIICHI NUCLEAR POWER PLANT ACCIDENT (TAC NO. ME8752)
Dear Mr. Freeman:
By letter dated March 12,2012, the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) which included the Near Term Task Force (NTIF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. By letter dated May 10, 2012, and supplemented with a letter dated June 6,2012, Seabrook Station submitted its 60-day response proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. As discussed in the enclosed NRC staff evaluation, the licensee's alternative approach outlined in its 60-day response letter is consistent with the guidance of industry document Nuclear Energy Institute (NEI) 12-01, "Guidance for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities,,,1 and the direction of the Commission.
In addition, the NRC staff concludes that the licensee provided an adequate basis for its proposed alternative to responding to the 50.54(f) Request for Information regarding communications and staffing for NTIF Recommendation 9.3. 1 NRC staff determined NEI 12-01 to be an acceptable approach in letter dated 05-15-2012 (ADAMS Accession No. ML 12131A043).
P. Freeman -2 If you have any questions, please contact me at 301-415-3100 or via e-mail at John. Lamb@nrc.gov.
G. Lamb, Senior Project Manager t Licensing Branch 1-2 Di sion of Operating Reactor Licensing o ice of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Staff Evaluation cc w/encl: Distribution via Listserv NUCLEAR REGULATORY COMMISSION STAFF EVALUATION INFORMATION REQUEST MADE UNDER 10 CFR 50.54(f) REGARDING NEAR-TERM TASK FORCE RECOMMENDATION
9.3 NEXTERA
ENERGY SEABROOK, LLC. SEABROOK STATION, UNIT 1 DOCKET NUMBER 50-443 By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12073A348), the U.S. Nuclear Regulatory Commission (NRC or Commission) issued a Request for Information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.54(f) which included the Near-Term Task Force (NTIF) Recommendation 9.3 for Emergency Preparedness (EP). Specifically, licensees were requested to assess their means to power communications equipment onsite and offsite during a prolonged Station Blackout (SBO) event and to perform a staffing study to determine the staff required to fill all necessary positions in response to a multi-unit event. If a licensee could not meet the requested 90-day response, then that licensee was required to provide a response within 60 days of the issuance of the letter describing an alternative course of action and estimated completion date. By letter dated May 3, 2012 (ADAMS Accession No. ML 12125A41 0), the Nuclear Energy Institute (NEt) submitted NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities," Revision 0, May 2012. The NRC staff reviewed NEI 12-01 and found it to be an acceptable method for licensees to use when responding to the NRC's 10 CFR 50.54(f) Request for Information regarding communications and staffing for EP. This staff evaluation is focused specifically on the licensee's response to the 10 CFR 50.54(f) letters and not on the associated Orders. By letter dated May 10, 2012, and supplemented with a letter dated June 6, 2012, NextEra Energy Seabrook, LLC submitted its 60-day response to the 10 CFR 50.54(f) Request for Information proposing an alternative course of action based upon the higher priority to complete the implementation of the revised EP Rule. The NRC staff reviewed the licensee's proposed alternative against the guidance contained in NEI 12-01. In addition, the NRC staff also considered the direction given by the Commission in the Staff Requirements Memorandum (SRM) to SECY 12-0025, "Proposed Orders and Requests for Information in Response to Lessons Learned from Japan's March 11,2011, Great Tohoku Earthquake and Tsunami," dated March 9,2012 (ADAMS Accession No. ML120690347).
This SRM stated, in part, that Completing implementation activities associated with the rule we have already promulgated has greater safety significance and also involves the coordinated actions of our partners in State and local governments.
Substantial public credibility benefits accrue from continuing these activities as a priority.
Enclosure
-2 The NRC staff considers the existing EP framework and regulations provide reasonable assurance of adequate protection of public health and safety in the event of a radiological emergency.
The revised EP rule that was promulgated on November 23, 2011, initiated a number of activities that will enhance EP programs, including conducting a staffing analysis and enhancing public notification systems. The implementation of the EP rule was given priority by the Commission and the NTTF recommendations should not displace ongoing work that has greater safety benefit, higher priority, or is necessary for continued safe operation of nuclear power plants. The NTTF Report concluded that continued operation and continued licensing activities do not pose an imminent risk to the public health and safety and are not inimical to the common defense and security.
The phased approach to responding to the 10 CFR 50.54(f) letters, combined with the definition of new response requirements associated with Fukushima NTTF Recommendation 4.2, as subsequently modified by the NRC staff and issued as NRC Order EA-12-049 (ADAMS Accession No. ML 12054A736), will ensure that enhancements will be made to staffing and communications by licensees.
It should be noted that the 10 CFR 50.54(f) letter and implementation of the Order includes completion of actions related to response assignments, staffing changes, issuance of new or revised procedures or guidelines, and training.
Activities are ongoing by both the NRC and industry to initiate interim actions as a result of lessons learned from the events which will be provided in the 90-day response such as:
- Methods to access the site
- Interim actions taken to date Given the above and that the licensee's approach was found to be consistent with the guidance of NE112-01 and the direction of the Commission, the NRC staff concludes that the licensee has provided an adequate basis for its proposed alternative responding to the 10 CFR 50.54{f) letters regarding communications and staffing for Recommendation 9.3.
P. Freeman -If you have any questions, please contact me at 301-415-3100 or via e-mail at John. Larnb@nrc.gov.
Docket No. 50-443 Staff cc w/encl: Distribution via RidsAcrsAcnw
_MailCTR RidsNrrDorlLpl1-2 RidsNrrLAABaxter RidsNrrPMSeabrook RidsNsirDpr RidsOgcRp RidsRgn 1 MailCenter CMurray, JShea, JKratchman, ADAMS Accession No. ML 12159A377 Sincerely, IRN John G. Lamb, Senior Project Manager Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- concurrence via email OFFICE NAME I NRR/DORLlLPL 1-2/PM iJLamb NRRlDORLlLPL 1-2/LA i ABaxter (SRohrer for) NSIR/DPR/DDEPE/NRLB/BC KWilliams*
I DATE 06/812012 06/07/2012 06/07/2012 OFFICE NAME j NRR/JLD/PMB/BC I RPascarelli NRR/DORLlLPL 1-2/BC MKhanna NRRIDORULPL 1-2/PM JLamb (JHughey for) I DATE 106/07/2012 06/8/2012 06/8/2012 OFFICIAL RECORD