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| | number = ML18110A141 | | | number = ML18110A141 |
| | issue date = 01/17/1978 | | | issue date = 01/17/1978 |
| | title = Saint Lucie Unit 1 and Turkey Point Units 3 and 4 - Letter Informing the NRC That a Review of a Letter from FP&L Dated December 14, 1977 Has Been Completed and Advising That Further Classification Is Needed | | | title = Letter Informing the NRC That a Review of a Letter from FP&L Dated December 14, 1977 Has Been Completed and Advising That Further Classification Is Needed |
| | author name = Oakes L C | | | author name = Oakes L |
| | author affiliation = Oak Ridge National Lab (ORNL) | | | author affiliation = Oak Ridge National Lab (ORNL) |
| | addressee name = Stello V | | | addressee name = Stello V |
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| {{#Wiki_filter:DISTRIBUTION AFZER.XSSUAHCE g 78I PERQXHG LICENSE VA NVCLSAR RSQVLATORY COMMI$$ON OOCKST NUM 88 R S-0 2 3'3 NRC OISTRISUTION PoR PART 60 OOCIt'ET MATERIAL PILS NUM88R i TQ." I Mr.V.Stello I FROM: Oak Ridge National Lab Oak Ridge, Tennessee L, CD Oakes OATS OP OOCVMSNT 1/17/78 OATS RCCSIVSO 1/24/78'~TTI R!~QINAI+COPY QNOTORI?EO | | {{#Wiki_filter:DISTRIBUTION AFZER. XSSUAHCE PERQXHG LICENSE VA NVCLSAR RSQVLATORY COMMI$$ ON OOCKST NUM88 R g 78I S-0 2 3'3 PILS NUM88R NRC OISTRISUTION PoR PART 60 OOCIt'ET MATERIAL i TQ." FROM: OATS OP OOCVMSNT I Oak Ridge National Lab 1/17/78 Mr. V. Stello Oak Ridge, Tennessee OATS RCCSIVSO I |
| ~tJ NC@ASSI PI 8O PROP INPVT PORM NVM88R OP COPI8$AKCSIVEO/y/5wPC3 8$CRIPTION I I I Review of 1tri from Robert Uhrig (FPL)to George Lear (USNRC)dtd.12/14/77'(1-P)(2-P)RJL 1/24/78 PLY"NAME: Turkey Point 3&4'St Lucie 1 SAPPY BRANCH CHIEF 7 FOR ACTION/INFORMATION INTERNAL 0 Rl BUTION I II!I~L.L-O TERNAL OISTRIBUTION | | L, CD Oakes 1/24/78 |
| [~DR: r/~REFT~s ZXC.HSING aI.1 CYS S=IT Cii="GORE CONTROL NUMBER 5+./75O2p025 1 t NE.I,~NF N)Yg'I OAK RIDGE NATIONAL LABORATORY | | '~TTI R QNOTORI?EO PROP INPVT PORM NVM88R OP COPI8$ AKCSIVEO |
| '"'PP OPERATED BY UNION CARBIDE CORPORATION NUCLEAR DIVISION POST OFFICE BOX X OAK RIDGE, TEHHESSEE 37830 January 17, 1978 Mr.V.Stello, Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S.Nuclear'Regulatory Commission Washington, DC 20555
| | ~QINAI ~tJ NC @ASSI PI 8O |
| | +COPY / y/5wPC3 8$ CRIPTION I |
| | I Review of 1tri from Robert Uhrig (FPL) to George Lear (USNRC) dtd. 12/14/77 ' |
| | I (1-P) (2-P) |
| | RJL 1/24/78 PLY"NAME: Turkey Point 3 & 4 |
| | ' St Lucie 1 SAPPY FOR ACTION/INFORMATION BRANCH CHIEF 7 INTERNAL0 Rl BUTION I II HSING |
| | ! I ~ L.L-O s |
| | [ ~DR: |
| | ZXC. |
| | r / ~ REFT~ |
| | TERNAL OISTRIBUTION CONTROL NUMBER 5+./ |
| | aI. 1 CYS S=IT Cii="GORE 75O2p025 1 |
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| ==Dear Mr.Stello:== | | t NE.I, |
| Review of Letter from Robert Uhrig (FPL)to Geor e Lear USNRC Dated December 14 1977 We have reviewed a letter (with enclosure) from Mr.Robert Uhrig, Florida Power and Light, to Mr.George Lear, USNRC, dated December 14, 1977, Docket Nos.50250, 50251, and 50335.This letter was in response to a Request for Information. | | ~NF N)Yg'I |
| It is our opinion that further clarification is needed as detailed in the attached commentary. | | '"'PP OAK RIDGE NATIONAL LABORATORY OPERATED BY UNION CARBIDE CORPORATION NUCLEAR DIVISION POST OFFICE BOX X OAK RIDGE, TEHHESSEE 37830 January 17, 1978 Mr. V. Stello, Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear 'Regulatory Commission Washington, DC 20555 |
| | |
| | ==Dear Mr. Stello:== |
| | |
| | Review of Letter from Robert Uhrig (FPL) to Geor e Lear USNRC Dated December 14 1977 We have reviewed a letter (with enclosure) from Mr. Robert Uhrig, Florida Power and Light, to Mr. George Lear, USNRC, dated December 14, 1977, Docket Nos. 50250, 50251, and 50335. This letter was in response to a Request for Information. |
| | It is our opinion that further clarification is needed as detailed in the attached commentary. |
| Sincerely,'. | | Sincerely,'. |
| C.Oakes Attachment cc: R.Brodsky, DOE W.R.Butler, NRC F.H.Clark S.J.Ditto H.N.Hill T.A.Ippolito, NRC G.D.McDonald, NRC ,F...R.Mynatt T.W.Reddoch.F.Rosa, NRC D.B.Trauger~~O240-Si | | C. Oakes Attachment cc: R. Brodsky, DOE W. R. Butler, NRC F. H. Clark S. J. Ditto H. N. Hill T. A. Ippolito, NRC G. D. McDonald, NRC |
| ~4V] | | ,F...R. Mynatt T. W. Reddoch |
| COMMENTARY ON LETTER 12/14/77, UHRIG.(FPL)TO LEAR (USNRC)*uestion 1 The response to 1.3 gives limitations on the line based on long-term operation. | | .F. Rosa, NRC D. B. Trauger |
| It does not phrase an operational dictum like"The line may be operated at above x amperes but not exceeding y amperes for a time not to exceed z minutes," where z is a number small enough to provide operational guidance.We presume there is no such operational guideline. | | ~~O240-Si |
| Line sag is computed for two different temperatures, but no indication is given as to what the temperature of the line was when it relayed open.Can we presume that there is no recorded data on the line current over this 16-minute period (10:08-10:24) from which a temperature profile could be determined? | | |
| It was made very clear at the November 18 meeting that all conclusions should be supported by the data on which they were based.It was also made clear that because relays are more apt to respond to transient peak stress conditions than to interval average conditions, an estimate of average interval conditions serves little purpose.The power estimates given in 1.6 fail on both these counts.Therefore, we request the 16-minute (10:08-10:24)record of each variable that was used in making this power calculation and a sample of how the calculation was made.Also a reference is made in this response to past history of division of the load (between the two Ft.Myers-Ranch lines).If there are records of such a division of trans-mission on these lines at approximately 500-600 MW total power, please furnish them.In a dynamic situation such as'he system was then experi-encing would the relative loading of the two lines be e~ected to oscillate so that an average relative loading would not reflect peak conditions on one?Also, in the response to 1.6, oscillogram records from Ringling are included;oscillogram,records from Broward.,and Midway are cited but not included.Please, therefore, furnish copies of the Broward and Midway oscillogram records.Oscillogram records at locations remote from a fault cannot be interpreted without some knowledge of the intervening circuitry, particularly transformer coupling.Therefore, please furnish the indicated inteWening circuitry description for Ringling, Broward, and Midway.uestion 2 The response"We have concluded that the Turkey Point trip could not, by itself, have caused the line to relay" is not supported. | | ~ 4V] |
| Furnish any supporting analysis with full description. | | COMMENTARY ON LETTER 12/14/77, UHRIG .(FPL) TO LEAR (USNRC)* |
| *Attachment to letter from L.C.Oakes to V.Stello,"Review of Letter from.Robert Uhrig (FPL)to George Lear (USNRC)dated December 14, 1977," dated January 17, 1978. | | uestion 1 The response to 1.3 gives limitations on the line based on long-term operation. It does not phrase an operational dictum like "The line may be operated at above x amperes but not exceeding y amperes for a time not to exceed z minutes," where z is a number small enough to provide operational guidance. We presume there is no such operational guideline. |
| uestion 3 The response to Question 3 appears to suggest that the calculation involving the loss of Turkey Point 4 in the FCG study is to be considered to bound the events which occurred around 10:08 on 5/16/77.If this sug-gestion is intended, furnish a detailed description of this calculation showing relevant detail which causes it to be regarded as bounding.uestion 6 The response to Question 6 is unclear in some respects.It is our understanding that Southern Co.and Florida Power and Light have not yet entered an agreement for a 500 kV Georgia-Florida tie.Is that correct?It is our understanding that the 800 MW interchange capability from Georgia to Florida which was, according to referenced FPL reports, to be ready in 1976 is not yet available. | | Line sag is computed for two different temperatures, but no indication is given as to what the temperature of the line was when it relayed open. Can we presume that there is no recorded data on the line current over this 16-minute period (10:08-10:24) from which a temperature profile could be determined? |
| Is that corrects uestion 7 The reply to Question 7.3 does not contain the discussion requested and is not.satisfactory.}} | | It was made very clear at the November 18 meeting that all conclusions should be supported by the data on which they were based. It was also made clear that because relays are more apt to respond to transient peak stress conditions than to interval average conditions, an estimate of average interval conditions serves little purpose. The power estimates given in 1.6 fail on both these counts. Therefore, we request the 16-minute (10:08-10:24) record of each variable that was used in making this power calculation and a sample of how the calculation was made. Also a reference is made in this response to past history of division of the load (between the two Ft. Myers-Ranch lines). If there are records of such a division of trans-mission on these lines at approximately 500-600 MW total power, please furnish them. In a dynamic situation such as'he system was then experi-encing would the relative loading of the two lines be e~ected to oscillate so that an average relative loading would not reflect peak conditions on one? |
| | Also, in the response to 1.6, oscillogram records from Ringling are included; oscillogram,records from Broward.,and Midway are cited but not included. Please, therefore, furnish copies of the Broward and Midway oscillogram records. Oscillogram records at locations remote from a fault cannot be interpreted without some knowledge of the intervening circuitry, particularly transformer coupling. Therefore, please furnish the indicated inteWening circuitry description for Ringling, Broward, and Midway. |
| | uestion 2 The response "We have concluded that the Turkey Point trip could not, by itself, have caused the line to relay" is not supported. Furnish any supporting analysis with full description. |
| | *Attachment to letter from L. C. Oakes to V. Stello, "Review of Letter from. Robert Uhrig (FPL) to George Lear (USNRC) dated December 14, 1977," |
| | dated January 17, 1978. |
| | |
| | uestion 3 The response to Question 3 appears to suggest that the calculation involving the loss of Turkey Point 4 in the FCG study is to be considered to bound the events which occurred around 10:08 on 5/16/77. If this sug-gestion is intended, furnish a detailed description of this calculation showing relevant detail which causes it to be regarded as bounding. |
| | uestion 6 The response to Question 6 is unclear in some respects. It is our understanding that Southern Co. and Florida Power and Light have not yet entered an agreement for a 500 kV Georgia-Florida tie. Is that correct? |
| | It is our understanding that the 800 MW interchange capability from Georgia to Florida which was, according to referenced FPL reports, to be ready in 1976 is not yet available. Is that corrects uestion 7 The reply to Question 7.3 does not contain the discussion requested and is not. satisfactory.}} |
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Category:Letter
MONTHYEARML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter 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 IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 IR 05000250/20243012024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses 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 ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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 ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake 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-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project 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 IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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 L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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 L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23095A0082023-04-0404 April 2023 Attachment 2 - Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 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 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response 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-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response 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-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response 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-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response 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-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response 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-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. 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DISTRIBUTION AFZER. XSSUAHCE PERQXHG LICENSE VA NVCLSAR RSQVLATORY COMMI$$ ON OOCKST NUM88 R g 78I S-0 2 3'3 PILS NUM88R NRC OISTRISUTION PoR PART 60 OOCIt'ET MATERIAL i TQ." FROM: OATS OP OOCVMSNT I Oak Ridge National Lab 1/17/78 Mr. V. Stello Oak Ridge, Tennessee OATS RCCSIVSO I
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'"'PP OAK RIDGE NATIONAL LABORATORY OPERATED BY UNION CARBIDE CORPORATION NUCLEAR DIVISION POST OFFICE BOX X OAK RIDGE, TEHHESSEE 37830 January 17, 1978 Mr. V. Stello, Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear 'Regulatory Commission Washington, DC 20555
Dear Mr. Stello:
Review of Letter from Robert Uhrig (FPL) to Geor e Lear USNRC Dated December 14 1977 We have reviewed a letter (with enclosure) from Mr. Robert Uhrig, Florida Power and Light, to Mr. George Lear, USNRC, dated December 14, 1977, Docket Nos. 50250, 50251, and 50335. This letter was in response to a Request for Information.
It is our opinion that further clarification is needed as detailed in the attached commentary.
Sincerely,'.
C. Oakes Attachment cc: R. Brodsky, DOE W. R. Butler, NRC F. H. Clark S. J. Ditto H. N. Hill T. A. Ippolito, NRC G. D. McDonald, NRC
,F...R. Mynatt T. W. Reddoch
.F. Rosa, NRC D. B. Trauger
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COMMENTARY ON LETTER 12/14/77, UHRIG .(FPL) TO LEAR (USNRC)*
uestion 1 The response to 1.3 gives limitations on the line based on long-term operation. It does not phrase an operational dictum like "The line may be operated at above x amperes but not exceeding y amperes for a time not to exceed z minutes," where z is a number small enough to provide operational guidance. We presume there is no such operational guideline.
Line sag is computed for two different temperatures, but no indication is given as to what the temperature of the line was when it relayed open. Can we presume that there is no recorded data on the line current over this 16-minute period (10:08-10:24) from which a temperature profile could be determined?
It was made very clear at the November 18 meeting that all conclusions should be supported by the data on which they were based. It was also made clear that because relays are more apt to respond to transient peak stress conditions than to interval average conditions, an estimate of average interval conditions serves little purpose. The power estimates given in 1.6 fail on both these counts. Therefore, we request the 16-minute (10:08-10:24) record of each variable that was used in making this power calculation and a sample of how the calculation was made. Also a reference is made in this response to past history of division of the load (between the two Ft. Myers-Ranch lines). If there are records of such a division of trans-mission on these lines at approximately 500-600 MW total power, please furnish them. In a dynamic situation such as'he system was then experi-encing would the relative loading of the two lines be e~ected to oscillate so that an average relative loading would not reflect peak conditions on one?
Also, in the response to 1.6, oscillogram records from Ringling are included; oscillogram,records from Broward.,and Midway are cited but not included. Please, therefore, furnish copies of the Broward and Midway oscillogram records. Oscillogram records at locations remote from a fault cannot be interpreted without some knowledge of the intervening circuitry, particularly transformer coupling. Therefore, please furnish the indicated inteWening circuitry description for Ringling, Broward, and Midway.
uestion 2 The response "We have concluded that the Turkey Point trip could not, by itself, have caused the line to relay" is not supported. Furnish any supporting analysis with full description.
- Attachment to letter from L. C. Oakes to V. Stello, "Review of Letter from. Robert Uhrig (FPL) to George Lear (USNRC) dated December 14, 1977,"
dated January 17, 1978.
uestion 3 The response to Question 3 appears to suggest that the calculation involving the loss of Turkey Point 4 in the FCG study is to be considered to bound the events which occurred around 10:08 on 5/16/77. If this sug-gestion is intended, furnish a detailed description of this calculation showing relevant detail which causes it to be regarded as bounding.
uestion 6 The response to Question 6 is unclear in some respects. It is our understanding that Southern Co. and Florida Power and Light have not yet entered an agreement for a 500 kV Georgia-Florida tie. Is that correct?
It is our understanding that the 800 MW interchange capability from Georgia to Florida which was, according to referenced FPL reports, to be ready in 1976 is not yet available. Is that corrects uestion 7 The reply to Question 7.3 does not contain the discussion requested and is not. satisfactory.