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Category:Letter
MONTHYEARML24009A1152024-01-29029 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 IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) 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 IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 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-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval 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) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update 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 IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection 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 ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
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- REGoe UNITED STATES
+f NUCLEAR REGULATORY COMMISSION
? a WASHINGTON DC. 205550001 e
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%*o CHAIRMAN September 16,2021 Ms.Natalie H.Treat Executive Director C-10 ResearchandEducation Foundation 11Chestnut Street Amesbury, MA 01913
Dear Ms.Treat:
OnbehalfoftheU.S.Nuclear Regulatory Commission (NRC), Iamresponding to your dated letter August 9,2021, inwhich yourequested responses toseveral questions and concerns alkali-silica about reaction atSeabrook Station, Unit No. 1 (Seabrook). Responses tothe specific questionsinyourletter areenclosed.
your Iappreciate letter andcontinued interestintheNRC's oversight atSeabrook. If youhave additional questions orneedmoreinformation, please contact Justin Poole, Project Manager, ofNuclear Office Reactor Regulation, at301-415-2048 orJustin.Poole@nrc.gov.
Sincerely, s .
( . s ,
Christopher T.Hanson
Enclosure:
Asstated
U.S.Nuclear Regulatory Commission Responses toQuestions intheAugust 9,2021, Letter Question 1 Because so much isunknown about therate ofASR[alkali-silica reaction) expansion,why doesn't NRCrequire theuseoferror bars inmodeling its progression?This isonearea where independent experts could beofassistance toquantify themargin oferror.Wedon't knowwhere we areonthecurve. That iscause forconcern by C-10 andDr. Saouma; itshould beofequal concern to NextEra andtheNRC. Indeed, determination ofthe out-of-plane expansion relies ontheavailabilityof concrete cores saved during construction, andthe empirical curve torelatedegradation ofelastic modulus with expansion. Thuswe have tworelated questions:
a)Howmanyconstruction cores have been saved over thepast 40years? We would like toknowunder which protocol were they collected (how many cores percast cubicyard), under which conditions (temperature andrelative humidity) have they been stored,andhowmanyhave been savedfrom theconcrete cast inthe containment buildingfrom thebase tofive feet aboveground-themost criticalsegment ofthebuilding? A picture ofthose cores would goa long wayin assuaging ourconcerns.
b)Howconfident areyouinusing thecalibration curve? Can youquantify its 90%confidence levelinterms oftheassociated uncertainties (calibration curve, empirical relationshipbetween compressive strength andelastic modulus, representativeness oftheclosest core toanarbitrary location of sudden ASR expansion)? Ultimately,howtall would youexpect the error barsto be?
There isnoNRCrequirement tosave theinitial construction cylinders ("cores")beyond testing theoriginal conducted during construction. Thelicensee collected wetconcrete samples actual during construction pours ofeach structure, andstandard cylinders werecast and tested inaccordance withapplicableAmerican Society for Testing andMaterials standards atspecified times(e.g.,
7 days, 28days), asrequired bytheconstruction codes ofrecord (American ConcreteInstitute 318-71, "Building CodeRequirements for Reinforced Concrete," forother category1 structures, andthe1973 Edition of American Society of Mechanical Engineers Boiler andPressure Vessel CodeSection III, Division 2,for containment). TheNRCdoesnotmaintain constructionrecords; thelicensee maintains these records onsite for future reference anduse, asnecessary. Whenextensometers areinstalled inreinforced concrete structures atSeabrook, coresremoved from theplace where theextensometer will belocated aretested; anythrough expansion thickness todate isthen determined using themethodology approved bytheNRCin LicenseAmendment No.159(Agencywide Documents Access andManagement System (ADAMS) Accession No.ML18204A291).
Asdetailed intheNRCsafety evaluation for that license amendment, theNRCstaff foundthatthelicensee's useofthecalibration curve provided reasonable assurance of adequateprotection ofthepublic health andsafety. While neither thelicensee northeNRC staff placed a quantified confidence level, orerror bars, onthecalibration curve (i.e.,
the correlation"),
"modulus-expansion a conservative modulus reduction factor was appliedtothe curve calibration toaccount for uncertainty. Additionally, aspart ofLicense Amendment No.
Enclosure
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159, theNRCimposed a license condition that the curve becorroborated with actualfield measurements andobservations asadditional plant-specific data become available. The adequacy ofthecalibration curve, along with theuseoferror bars, wasconsidered bythe Atomic Safety andLicensing Board, andtheBoard found that thelicensee's approach tothe corroboration study (without the useoferror bars) provided reasonable assurance ofadequate protection (Atomic Safety and Licensing Board I nitial Decision LBP-20-9 (slip op.at 167-70)
(ADAMS Accession No. ML20254A339); Atomic Safety andLicensing Board Memorandum and Order, LBP-20-12(slip. op.at10) (ADAMS Accession No.ML20322A417)).
Question 2:
HowcantheNRCincrease transparency about whatinspectors seeattheplant, in particular, with regard toASR?
IfNRCinspections donotidentify findings ofmore-than-minor significance, theagency's practice isgenerally todocument theinspection ina brief, straightforward manner, usually consisting ofa sentence ortwodescribingthe subject oftheinspection. WhenNRCinspections identify performance issues thatinvolve findings orviolations ofmore-than-minor significance, theinspectors document agency activities and conclusions in greater detail, following a systematic process. Inspectors also document observations andminor violations inaccordance with theNRC's Enforcement Manual andapplicableinspection manual chapters. For example, the mostrecent Seabrook inspection report (ADAMS Accession No. ML21222A126) provided several such observations anda description ofNextEra'sASR monitoring-related activities, as well asobservations anddocumentation ofa minor violationrelated toseveral other inspections conducted during thequarter. AstheNRCstaff conducts its ongoing inspections atSeabrook, agency inspectors willcontinue todocument their inspection results consistent with agency policy insufficient detail sothat stakeholders canadequately followNRC inspection activities andregulatory conclusions. Inspection reports will continue tobepublicly available inthe NRC's ADAMSat . Members of the publiccanalso sign uptoreceive notice ofplant-specific public documents asthey becomeavailable at Question 3:
Under whatcircumstances might theagency revisit Seabrook's concrete aging management program?
TheNRChasa number ofprocesses toalert theagency tonewinformation thatmay triggerfurther consideration ofa licensee's aging management program (AMP). Forexample, information gathered through inspections ofthelicensee's activities, reviews ofplant operating experience, ortheresults ofresearch activities could prompt a review ofanAMP.Additionally, theNRC's regulation at10CFR2.206 permits anyperson topetition theNRCtomodify, suspend, orrevoke a license, orfor anyother action asmaybeproper.
With respect toSeabrook specifically, Seabrook's ASRAMPinthe current license includes requirements for thelicensee tomonitor plant-specific andindustrywide operating experience, including applicable ongoing industry studies andresearch, update theprogram as necessary. These provisions arediscussed intheNRCstaff's safety evaluation reportfor Seabrook license renewal (ADAMS Accession No.ML18362A370). TheNRCstaff continues to monitor Seabrook's implementation ofits ASRprograms andrelated license conditions through inspections under theReactor Oversight Process. Ifinspection results indicate thatthelicensee
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is not properly implementing its programs ormeeting license then conditions, theNRCcantake actions toincrease inspections andoversight. Thestaff documented theresults oftheNRC's mostrecent inspection that included anASRsample inSeabrook Station, UnitNo.1,Integrated Inspection Report No.05000443/2021002, dated August 11,2021(ADAMS Accession No.ML21222A126).
Question 4:
After whatyou've learned intheSeabrook case, would yousupport thedevelopmentof NRCregulations governing concrete testing, andmorescrutiny ofother material-aging issues?
TheNRCcontinues tobelieve thatcompliance with theexisting in10CFR regulations Part 50,"Domestic licensingofproduction andutilization and10CFRPart facilities," 54,aswell asinspection andrelated activities under theNRC'sReactor Process Oversight provide reasonable assurance that concrete degradation duetoASR,orother material-aging issues, will bemanaged such affected that safety-related structures atnuclear powerplants willremain capable ofperforming their intended functions. Existing NRCregulations licensees require to monitor theperformance andcondition ofsafety-related structures andtoaddress conditions adverse toquality (includingsignificant degradation) ina manner sufficient toprovide reasonable assurance that intended functions will be maintained. NRCregulationsareintended toprovide generic rulesorrequirements.