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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, 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, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, 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 L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 ML23151A4372023-05-24024 May 2023 Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database ML23095A0082023-04-0404 April 2023 Attachment 2 - Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-051, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information2022-03-29029 March 2022 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information L-2021-213, Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology2021-11-19019 November 2021 Response to Request for Additional Information Regarding License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology L-2021-207, Response to Request for Additional Information for ISI Relief Request No. 102021-10-25025 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 L-2021-197, Response to Request for Additional Information for ISI Relief Request No. 102021-10-15015 October 2021 Response to Request for Additional Information for ISI Relief Request No. 10 ML21258A3792021-09-14014 September 2021 Response to Request for Additional Information, Relief Requests 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1), Extension of Inspection Interval for Turkey Point Unit 3 and Unit 4 Reactor. L-2020-111, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report2020-06-24024 June 2020 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Report L-2020-081, Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor2020-06-0808 June 2020 Response to Request for Additional Information Regarding License Amendment Request 264, Adopt Emergency Action Level Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor L-2020-083, Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re2020-05-21021 May 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Re L-2020-071, Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2020-04-16016 April 2020 Response to Request for Additional Information Regarding License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2020-064, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information2020-04-0909 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information ML20098F3412020-04-0707 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program - Response to Request for Additional Information L-2019-135, Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-07-22022 July 2019 Response to Request for Additional Information Regarding License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications ML19158A5032019-06-0707 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Turkey Point ESA Section 7 Consultation L-2019-114, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response2019-06-0404 June 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 10, RAI No. B.2.3.28-1b Updated Response L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 82019-03-15015 March 2019 Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8 L-2019-037, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses2019-03-0606 March 2019 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses L-2019-033, Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses2019-03-0101 March 2019 Response to Requests for Additional Information Subsequent License Renewal Application Safety Review Revision 1, Set 8 First Submittal Responses ML19056A1252019-02-25025 February 2019 Turky Point SLRA RAIs 1 2 3 4 5 6 7 8 9 11 - Set 8 Rev 1 Irradiated Concrete-Steel Responses L-2019-012, Response to Follow-on NRC RAI No. B.2.3.9-1 a2019-02-13013 February 2019 Response to Follow-on NRC RAI No. B.2.3.9-1 a L-2019-023, Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals2019-01-31031 January 2019 Response to Request for Additional Information Regarding License Amendment Request 265, Revise NFPA-805 License Condition for Reactor Coolant Pump Seals L-2018-234, Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision2018-12-21021 December 2018 Subsequent License Renewal Application Safety Review Request for Additional Information (RAI) Set 5 Response 4.3.5-2 Revision L-2018-223, Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses2018-12-14014 December 2018 Subsequent License Renewal Application Safety Review - November 15, 2018 Public Meeting Action Item Responses L-2018-222, Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses2018-12-12012 December 2018 Subsequent License Renewal Application Safety Review - November 13, 2018 Public Meeting Discussion Topic Responses L-2018-218, Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review2018-11-28028 November 2018 Supplemental Response to Request for Additional Information (RAI) Set 1, Subsequent License Renewal Application Environmental Review L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review2018-11-28028 November 2018 Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review2018-11-0202 November 2018 Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review L-2018-166, WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings.2018-10-31031 October 2018 WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings. ML18299A1142018-10-24024 October 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 4 Responses L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items ML18296A0242018-10-16016 October 2018 Set 3 Response to Request for Additional Information to Subsequent License Renewal Application Safety Review ML18299A1162018-10-15015 October 2018 Structural Integrity Associates Engineering Report No. 1700109.401P, Revision 7 - Redacted, Evaluation of Environmentally-Assisted Fatigue for Turkey Point Units 3 and 4 for Subsequent License Renewal ML18299A1172018-10-12012 October 2018 Framatome Calculation No. 32-9280712, Rev. 002, Tp CRDM Lower Joint Environmentally Assisted Fatigue Dated October 12, 2018 (Non-Proprietary) L-2018-174, Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines2018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.401, Revision 4, Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines ML18299A1182018-10-12012 October 2018 Structural Integrity Associates Engineering Report No. 0901350.304, Revision 3, Fatigue Crack Growth Evaluation, October 12, 2018 ML18283A3102018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application Environmental Review L-2018-169, Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review2018-10-0505 October 2018 Responses to Requests for Additional Information for Subsequent License Renewal Application No. HC-7-a L-2018-169 Environmental Review L-2018-154, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses2018-09-14014 September 2018 Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 2 Responses 2023-08-07
[Table view] |
Text
NRC FORIs 195 I2 76) I NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL U.S. NUCLEAR REGULATORY ~MISSION DOCKET NVMBE 5O-2 FILE NUMBER
/251 TO:.- 'FROM: DATE OF DOCUMENT Florida Power & Light Company 2/2/77 Mr;"George Lear r
Miami, Florida DATE RECEIVED
~ t r r Mr, Robert E. Uhri 2/7/77 fggCl'TE R 'CINOTORIZED PROP (NPUT FORM NUMBER OF COPIES RECEIVED JQ;0 R I G INA L /KUNG LASS IF I E D Three sighed
,-'. ~ Ht:otv. 37. co ~es'ncl.;recvd.
DESCRIPTION ENCLOSURE
~~ ~
h Ltr..re our 1/25/77 ltr. and their 1/21/77 r ltr. ~ . ~ trans the following: Consists . of supplemental information '
'oncerning ~S earn Geperator Tube Integrity.. ~
ZCKXOVrLEDGED PLANT NAME: (1-P) ,((9-P)
Turkey Point Units t
3 & 4 Dp Npp ggjgpvg SAFETY FOR ACTION/INFORMATION 2 7 77 RJL
" ASSIGNED AD:
gg . ~-Lear C MANA v, Elliott . ~ PROJECT MANAGER L C ASS . Parrish- LIC ASST INTERNAL DISTRIBUTION
,REG FXLE SYSTEMS SAFETY PLANT SYSTEMS S TE SAFE
~g
HEINEMAN SCHROEDER TEDESCO QN'0 OELD GOSSXCK & STAFF --ENGXNEERING IPPOLXTO ..- .
. MIPC ERNST CASE KNIGHT BALLARD HANAUER SI1WEIL OPERATXNG REACTORS SPANGLER HARLESS PAVLXCK STELLO SITE TECH PROJECT MANAGEMENT REACTOR. SAFE OPFRATING EXSENHUT.
CH GA19IILL STEPP BOYD . ROSS P ~ COLLINS 0 HULMAN HOUSTON ROSZTOCZY PFTERSON CHECK BUTLER SITE ANALYSIS MELTZ VOLLMER HELTEMES AT&X BUNCH SKOVIIOLT SALTZMAN- J ~ COLLINS RUTBFRG KREGER
. EXTERNAL DISTRIBUTION CO/ OL NUMBER LPDR'IC:
NAT~ LAB'EG MOKIAYEKM V.IE ULR KSON OR NSIC: LA PDR ASLB: CONSULTANTS:
ACRS CYS WeueNe/ E
FLORIDA POWER & LIGHT COMPANY February 2, 1977 L-77-40 Office of Nuclear Reactor Regulation Attention: Mr. George Lear, Chief 9> Lgo Operating Reactors Branch I3 g(cU~(0 Division of Operating Reactors S0jt U. S. Nuclear .Regulatory Commission <
Washington, D. C. 20555 u,S.iiiIP~~ISSI0ii ~,.
I ~isa CO
Dear Mr. Lear:
'4 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Steam Generator Tube Integrity Su lemental Information Your letter of January 25, 1977 formally requested additional information regarding steam generator tube integrity at Turkey Point. All of the questions in your letter have been answered by our submittals L-76-432, L-76-434, L-77-3,', and,L-77-30.
Subsequent to your January,25 letter, we received two additional f
questions from your'taff. The answers to the two additional questions are attached.
As stated in our letter L-77-29 of January 21, 1977, Florida Power & Light Company has submitted considerable information on the subject of steam generator tube integrity as it to Turkey Point Units 3 and 4. Based on the information we.
applies have submitted through today, we request that you grant approval for continued operation of Turkey Point Unit 4 beyond the time limit specified in Amendment 20 to Operating License DPR-41.
Based on our operating history from December 3, 1976 to date, and operational considerations, we woul approval by 5:00 p.m. on February 8,
'o and assuming continued operation at 100% rated power, we will reach the limit on February 9, 1977. Because of load management have your Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment 8t C'P//8 g5 6
'~op, QC786 Dg+
cc: Mr. Norman C. Moseley, Region Robert Lowenstein, Esquire II PEOPLE... SERVING PEOPLE
E ATTACHMENT Turkey Point Units 3 a 4 Steam Generator Tube Integrity Su elemental Information Sup ort Plate Ex ansion a.) We have correlated support plate expansion vith actual months of operati by means of a finite element model which utilizes a pseudo-thermal expansion technique. This technique has been used to simulate plate.
behavior up to full closure and several months beyond. The expansion has been correlated with actual months of operation. In order to do this, relationships between field data, effective months (EM's) and, results of the finite element anlysis must be established. Since the denting phenomenon .extends over the entire plate, there's good correl-atipn between measured denting and expansion of a dented plate.
Although our finite element -model .is not detailed. enough to yield dent ing rates, it does quantify the extent of flow slot closure for a pre-scribed expansion rate. Since the amount of closure over an extended period of EM's is available from field data, a relationship between model closure and EM's can be established. The rate of expansion-is'(
independent of boundary effects, insertion of blocking devices, and tim The procedure for calculating the rate of expansion per EM-is as follow For a plate expansion of . 014 (hot leg)/. 010 (cold leg) in/in applied to the updated plate model (Figure 1)
- the average flow slot. closure is .675 inches.
- The model shown in Figure 1 is for a 51 top support plate. Several comments are necessary regarding applicability of this model to a 44 bottom support plate. With regard to the differences between a 44 and 51 plate all significant parameters are approximately 5% smaller for a 44 than a 51. Thus, the two plates are virtually identical with regard to relative parameters and. 5% different. in overall size. The effect. of this on our results would be insignificant. The bottom plate is suppor differently than the top plate in both units However, the difference can be accounted for by transposing support locations about the diameter perpendicular to the tube lane. This can be accomplished simply by flipping the results of the finite element, number the flow slots in the model as 1-6 analysis. That is, from left to right for if we the to plate, they become 6-1 for the bottom plate.
i I
~ ~
For the actual plate the maximum (most conservative) rate of closure for a bottom support plate flow slot is
.24 inches/EM Thus .675 inches of closure represents 2.8 EM's and the plate expansion equivalent of a single month is
. 014 = ..005 in/in on the hot leg side and 2.8
. 010 2.8 .0036 in/in on the cold. leg side The .hot and cold leg expansions will be denoted as follows:
.005/.0036 in/in Based on field data taken during the last outage, the average opening was 1.5". Using a rate of closure of .24 in/month, the expected open-ing at the end of the current 2 month period is 1.0" This is equivale to a 1.75" average closure. Figure 2 shows the strain intensity plots for, the plate at. an average closure of 1.75", and a pseudo-thermal expa sion of .041/.029 in/in.
The rate of plate expansion occurs on a'ery local level and will not-change after complete closure of the flow slots. Thus, for each addi-tional month of operation beyond closure, an additional plate expansion of
.0050/.0036 in/in should be utilized.
Our results show closure occurring at
.064/.046 in/im expansion.
Thus, based on the expansion rate of
.005/.0036 in/in/month the number of operating months between the current: closure (at two mont subsequent to the December start-up) and. full closure is 4.6 zaonths.
More conservatively, we can consider the worst, slot which had an -openin 7/8" at the last inspection as being representative of all slots. The expected time to full closure for that slot, is
~ .
(. 875 2 (. 24)) l. 24 = l. 6 EM's beyond the end of the current two effective month period.
Figure 3 shows the strain intensity plots for the plate with an expansio of
".08l/.058 in/in or 3.4 EM's after closure.
The two plots indicate that while expansion continues, the continued, operation to closure, then more than 3 EM's beyond that, does not alter the strain intensity patterns. That is, the areas .of excessive hard spots are currently wel3. bounded, and will remain so for more than months a'dditional operation.
NOTE: An "effective month" is defined as operation of the reactor coolant system above 350 F.
Tube Loadin j 1n order to quantify the additional load on the tubes, due to the possible tendency of the plate to buckle after full closure, j.t j.s necessary to determine the load required. to prevent buckling of support plate. He have combined two analyses from Timoshenko's "Theory o Elastic Stability" to arrive at a very conservative load,,
which is still quite small.
Consider the case which generates the highest in-place load before buckling occurs, and ther'efore would require the largest transverse load to prevent buckling. This is the case of a circular plate with clamped edges. From Timoshenko, page 390:
(N ),14. 68 D a2 where E*h3 D
12 (1-v* )
v* = .42@
h = 75'I (Nr)c = 1215 lbs/in-Now let us consider a unit strip with clamped edges of length 2a m2D
~cr (Timoshenko, page 390) 817 lbs.
4 0 ~
For the case of where-a beam on an
~
Ncr = g2 E*
L elastic foundation (Timoshenko, page 94)-
I= 1/12 bh = 1/12 (1) (.75) = .035 in for a 1" strip of plate.
L = "reduced" length of the strip or beam as described on pages 96 and 97 of Timoshenko.
7f 2 E*
Ncr The'ctual length in question is R = 2a = 116" and L/R = .51 is the ratio of the "reduced" or equivalent beam length to the The reduction is due to the effect of the transverse support actual'ength.
on the beam, in our case created by the tubes. Table 2-5 in Timoshenko relates this ratio to the force per unit. length of the beam for a unit deflection 8. The stiffness of the tubes is such that the most conser-vative evaluation of tube loads would not. cause axial deformation of Thus, assuming a 1" deflection in order to calculate the reactive fore'e is conservative. From Table 2-5 for L/R = .51:
4R /16 E* I = 18.5 P
18.5 x 16 x 7.8 x 106 x 035 1164
.45 lbs per linear inch for a 1" strip or
.45 lb/in2 For the whole plate this translates into 4755 lbs.
Xf we add a further conservatism and assume that only 100 tubes take all of the load, the load per tube is 48 lbs/tube.
However, let us go one step further in the direction of: conservatism an use a buckling load of 1215 pounds from the circular plate results, but use the strip model to obtain 4.
1 L2 >2 x;26 x 30 x 106 x 035 1215 L 47 1" L/R = .42 50 18.5 x .45
= 1.22 lbs/in 2
~
and the total load on the tube bundle is 12,850 pounds.
Again, assuming that only 100 tubes interact, the load per tube is 129 lbs/tube This translates into a stress of 129/p ( 43752 38752) or E
1,000 psi
1 Hadst Characteris ties
- l. Hot/Cold Side Expansion Bias
- 2. Improved Perforated Area ~aterial Behavior (Anisotropic)
- 3. Elastic Behavior oir Channels at Support Locations
- 4. scrapper Stiffness Incorporated at Periphery
~
5 60.
'OT LEG 30, l5, COLD LEG I ~
~
, I
-'7'i. 0 X
=GO. 0 ~'a. 0=3K 0 a.O Figure 1. Finite Element l!odel.
CONTOURS REPRESENT % OF i~fAXINEf STRAIN INTENSITY:
1-10%
'2-50%
3-60%
4-70%
5-80%
.041/.029 in/in Expansion Load 0 03 0
Figure 2. In-Plane Strain Intensity At 1.75" Closure.
CONTOURS REPRESENT % OF i&GH~aQP;1 STRAIN INTENSITY:
1-10%
'-50%
3-60%
4-70%
5-80%
.081/.058 in/in Expansion Load G >4 Figure 3. In-Plane Str in Intensity 3 ~~months After. Closure.
~ I