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Category:Letter
MONTHYEARL-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 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 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-2024-032, 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 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 ML24065A2892024-02-28028 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 IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) 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) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements 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-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook 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-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 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 ML23275A0522023-10-0202 October 2023 Requalification Program Inspection 2024-08-06
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EDO Principal Correspondence Control FROM: DUE: 07/21/03 EDO CONTROL: G20030384 DOC DT: 06/30/03 FINAL REPLY:
Debbie B. Grinnell C-10 Research and Education Foundation TO:
Chairman Diaz FOR SIGNATURE OF : ** PRI ** CRC NO: 03-0435 Chairman Diaz DESC: ROUTING:
Steam Generator Tube - Seabrook Travers Paperiello Kane Norry Dean Burns/Cyr DATE: 07/09/03 Thadani, RES Miller, RI ASSIGNED TO: CONTACT:
NRR Collins SPECIAL INSTRUCTIONS OR REMARKS:
Ihewf tc& sL~ f7L E- t6SS 5EVt(
OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET Date Printed:Jul 08, 2003 17:06 PAPER NUMBER: LTR-03-0435 LOGGING DATE: 07/08/2003 ACTION OFFICE: EDO AUTHOR: Debbie Grinnell AFFILIATION: MA ADDRESSEE: Nils Diaz
SUBJECT:
Seabrook nuclear power station ACTION: Signature of Chairman DISTRIBUTION: RF, SECY to Ack LETTER DATE: 06/30/2003 ACKNOWLEDGED No SPECIAL HANDLING: Commission Correspondence NOTES: OCM #3233 FILE LOCATION: Adams DATE DUE: 07/23/2003 DATE SIGNED:
EDO -- G20030384
C10 RESEARCH & EDUCATION FOUNDATION, INC.
[io - - l 44 MERRIMAC STREET NEWBURYPORT, MA 01950 "dedicatedto radiofogicalmonitoing,researcVATWIANFitFlsice 1991" 03 JUL -7 AM 9: 50 June 30", 2003 Nils J. Diaz, Chairman U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Dear Chairman; The C-1O Foundation recently became aware of a critical safety issue at the Seabrook nuclear power plant through an April 1, 2003 "NRC Information Notice 2002-21, Supplement : Axial Outside-Diameter Cracking Affecting Thermally Treated Alloy 600 Steam Generator Tubing". Of particular concern to us was the fact that the tube cracking at Seabrook was both "unexpected and unusual" and the means of detecting these tube crackings with current technical specification requirements using the eddy current offset technique is inadequate, as stated in your notice.
In investigating what your agency was doing in response to this critical new finding at Seabrook, we contacted NRC staff to pursue what actions have been taken by the NRC to require "the highest quality standards practical" for steam generator tubing and to assure that the technical specifications required are adequate to assure that steam generator tubes have "an extremely low probability of abnormal leakage" as stated in Title 10 of the Code of Federal Regulations. We were directed by your staff to review the information available in your "Steam Generator Action Plan", which we did.
As we researched the Indian Point 2 steam generator leakage event which caused your agency to develop "action items" and pursued the research documentation, we discovered a letter from J. Hopenfeld "Differing Professional Opinion On Steam Generator Tube Integrity Issues" which clearly stated that excessively degraded tubes was an issue of grave concern to NRC staff and had been for a decade. According to your staff, the issue of allowing plants with these degraded steam generator tubes to stay in service and continue to threaten public safety was a violation of 10 CFR PART 100 and presented an unacceptable safety risk.
We continued to review NRC documentation within the "Steam Generator Action Plan" materials and found a letter from Louise Lund on your staff to James Riley at NEI where she is quoted as saying" the NRC staff is relying on the industry's initiative to maintain tube integrity by considering the NRC staff's comments in the enclosuresl-4. She states that it would be "highly desirable for the industry to address these issues". We then TEL: 978-465-6646 FAX: 978-462-3959 WEBSITE: WWW.C-10.0RG EMAIL: INFO@C-10.ORG
reviewed "Enclosure 4 - Priority Guideline Issues" which states "it would be important that inspection techniques employed during each inspection are capable of detecting active and potential degradation mechanisms which can occur over the lifetime of the steam generators at all locations where such mechanisms may potentially occur". I ask you, Chairman Diaz, when did it become voluntary for the nuclear industry to come into compliance with Federal Code requirements? Who is mandated under the law to assure public health and safety here, the NRC or NEI? Under your leadership the operational mode of your agency, when the industry to the NRC's knowledge, is not in compliance with Federal Codes, is to enforce them through polite suggestion.
It is more than important... it is imperative under the Federal Codes to understand that your agency is in violation of its mandate if it does not issue clear orders to assure that the industry comes into compliance with the Federal Codes. It is your duty to issue a proposed rule to ensure public safety and regulate the integrity of steam generator tubes and do it in a reasonable time frame.
When your staff has identified solutions and technology currently available to better manage tube degradation and the Advisory Committee on Reactor Safeguards has stated in publicly available NRC documents that the NRC does not have a defensible basis for determining that steam generator tube degradation will not experience multiple tube ruptures in an accident, you have a moral imperative but more significantly as an agency a requirement under the Federal Codes to issue an order to correct this critical safety issue in a reasonable timeframe. You have been aware as an agency that the current requirements contained in NRC technical specifications to the industry to assess tube integrity are inadequate and have not definitively acted on it. Had you issued a license amendment years ago and taken appropriate action to assure steam generator tube integrity, the issues would not have crept up and worsened. Had you allowed the NRC staff to keep pace with the colective actions needed to assure tube integrity, you may have been able to head off the likelihood of the accidents that have already occurred and to also head-off the potential increase in the frequency of future steam generator tube accidents.
Public confidence in the ability of the NRC to be an unbiased and effective regulator is significantly damaged by such Commission stall tactics. We are well aware that such tactics gamble with public safety by favoring the financial interests of utilities operating nuclear reactors with defective generator tubes. Growing public concerns demand that those within the Commission who would obfuscate such hazards step down in order to make way for an agency that heeds its public safety mandate.
Seabrook will be refueling in October, what formal NRC request to FPL Seabrook operators has been made to ensure that a full inspection of all stream generators is accomplished in response to the" unanticipated and unusual tube cracking"? Will you" ensure that inspection techniques and personnel used for the detection and sizing of flaws
are appropriate for all existing and potential degradation mechanisms", as stated in "Enclosure 3 'NRC Staff Comments Pertaining to EPRI PWR Steam Generator Examination Guidelines, Revision 6"? Will you request that "array probes be used to inspect for all degradation mechanisms at speeds comparable to a bobbin, as the bobbin is not qualified to detect these degradation types and locations", according to your staff?
Through our research of NRC documents, we are now all aware that Revision 5, which clearly identifies who and what is capable of assessing tube degradation, needs to be implemented with this new finding at Seabrook. Will you request that the following conditions of plant operations be evaluated in-depth and reported "by qualified personnel and inspection techniques: high operating temperature, off-nominal chemistry, high stress, micro-structural variability associated tube fabrication and heat treatment", as proposed by your staff in Enclosure 3?
Chairman Diaz, would you forward to us your agency's request of the Seabrook operator's for a steam generator inspection action plan for this October outage and the written results of your investigation of tube degradation, as well as a response to our questions. Thank you.
S
/ic, /2 Dqbbie B. Crinnell Research Advocate C-1O Research and Education Foundation cc; Sandra Gavutis, Ex. Dir., C-10 Foundation Congressman John F. Tierney Congressman Edward J. Markey