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| | issue date = 06/12/2007 | | | issue date = 06/12/2007 |
| | title = Electronic Transmission, Draft Request for Additional Information Regarding the Reactor Coolant System Pressure - Temperature Safety Limit (TAC No. MD49100) | | | title = Electronic Transmission, Draft Request for Additional Information Regarding the Reactor Coolant System Pressure - Temperature Safety Limit (TAC No. MD49100) |
| | author name = Bamford P J | | | author name = Bamford P |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
| | addressee name = Chernoff H K | | | addressee name = Chernoff H |
| | addressee affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | addressee affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
| | docket = 05000289 | | | docket = 05000289 |
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| =Text= | | =Text= |
| {{#Wiki_filter:June 12, 2007MEMORANDUM TO: Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Peter Bamford, Project Manager /ra/Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | {{#Wiki_filter:June 12, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION,DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910)The attached draft request for additional information (RAI) was transmitted by electronicmail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensee's submittal. The draft RAI is related to AmerGen's submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. | | THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910) |
| | The attached draft request for additional information (RAI) was transmitted by electronic mail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. |
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| Docket No. 50-289 | | Docket No. 50-289 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated June 12, 2007MEMORANDUM TO: Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Peter Bamford, Project Manager /ra/Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | As stated |
| | |
| | June 12, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION,DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910)The attached draft request for additional information (RAI) was transmitted by electronicmail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensee's submittal. The draft RAI is related to AmerGen's submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. | | THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910) |
| | The attached draft request for additional information (RAI) was transmitted by electronic mail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. |
| Docket No. 50-289 | | Docket No. 50-289 |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedDISTRIBUTION | | As stated DISTRIBUTION: |
| :Public BMarcus, NRRRidsNrrPMPBamfordAHowe, NRR GCranston, NRRLPL1-2 R/FRidsNrrPMEMillerSSun, NRRAccession No.: ML071630052 *via e-mail **via memorandumOFFICELPL1-2/PMLPL1-2/PMEICB/BCSRSB/BCNAMEPBamfordEMillerAHowe**GCranston*
| | Public BMarcus, NRR RidsNrrPMPBamford AHowe, NRR GCranston, NRR LPL1-2 R/F RidsNrrPMEMiller SSun, NRR Accession No.: ML071630052 *via e-mail **via memorandum OFFICE LPL1-2/PM LPL1-2/PM EICB/BC SRSB/BC NAME PBamford EMiller AHowe** GCranston* |
| DATE6/12/076/12/0705/21/200705/22/2007OFFICIAL RECORD COPY Enclosure DRAFTREQUEST FOR ADDITIONAL INFORMATIONHTP FUEL RCS PRESSURE-TEMPERATURE SAFETY LIMIT TECHNICAL SPECIFICATION AMENDMENT TAC NO. MD4910DOCKET NO. 50-289By letter dated March 22, 2007 (Agencywide Documents Access and Management SystemAccession No. ML070860968), AmerGen Energy Company, LLC (the licensee) submitted a license amendment request (LAR) regarding Three Mile Island Unit 1 Technical Specifications (TS). The proposed amendment would revise the reactor coolant system pressure-temperature limit to support use of the AREVA NP Mark-B-HTP fuel design. Based on the review of the information provided by the licensee, the staff has the following additional questions. 1.The licensee indicated that the transient core penalty for a specific transient core modelwas calculated based on the largest DNBR difference between the limiting Mark-B-HTP fuel rod in a full core model of the mark-B-HTP fuel and specific transient core model for all of the statepoints, condition I/II DNB transients, and axial power shapes.Discuss the results of the transient core penalty analyses for condition I/II DNBtransients with associated axial power shapes, and demonstrate that (1) the analysis scope in terms of the applicable condition I/II DNB transients and the allowable axialpower shapes is adequate, and (2) the calculated value of the transient core penalty is a bounding value and acceptable for determining the thermal design limit that is used to calculate the reactor core safety limit. 2.Provide the basis for your determination that no setpoint changes to reactor tripfunctions, other than the variable low reactor coolant system pressure trip, are needed to assure that the analyses of record remain bounding, or new analyses meet the applicable acceptance criteria for DBEs. 3.Identify the reactor coolant pressure and reactor outlet temperature at the end pointsand mid point of proposed TS Figure 2.1-1.4.Identify the low reactor coolant pressure and high reactor outlet temperature interceptpoints of proposed TS Figure 2.3-1.5.Demonstrate that, for operation with measured values at the limits of the "AcceptableOperation" region of proposed TS Figure 2.3-1, there would be adequate assurance that the actual operating point will be conservative relative to the indicated Safety Limit line, given measurement errors consistent with the instrument channel uncertainties.6.Identify the normal operating point for the reactor coolant pressure and reactor outlettemperature.7.Identify the low reactor coolant pressure and high reactor outlet temperature interceptpoints for:(a)TS Variable Low Pressure Trip (VLPT) Limiting Safety System Setting (LSSS)Setpoint (b)Adjusted TS VLPT(c)VLPT Nominal Setpoint (NSP)
| | DATE 6/12/07 6/12/07 05/21/2007 05/22/2007 OFFICIAL RECORD COPY |
| (d)VLPT As-Left Tolerance Band (e)VLPT Pre-Defined As-Found Tolerance Band.8.Provide additional details concerning the methodology used to develop the VLPT 10psig additional margin. Confirm that this additional margin has not been used in determining the VLPT Pre-Defined As-Found Tolerance Band.9.Although the licensee has stated that the VLPT setpoint calculation is prepared inaccordance with American National Standards Institute (ANSI) / Instrument Society of America (ISA) Standard 67.04.01-2000, "Setpoints for Nuclear Safety-Related Instrumentation," and Recommended Practice ISA-RP67.04.02-2000, "Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation," the licensee has not directly addressed how the recommendations of Regulatory Guide (RG) 1.105, Revision 3, "Setpoints for Safety-Related Instrumentation," are met. The licensee should address the regulatory positions of RG 1.105, Revision 3 or provide an acceptable alternative.10.The Summary of AMERGEN Commitments includes a commitment to determine thepredefined limits for the VLPT NSP As-Found Tolerance on a programmatic basis. The licensee should clarify this commitment. Aren't the predefined limits for the VLPT NSP As-Found Tolerance Band determined and included in March 22, 2007 submittal? Why would the limits of the VLPT NSP As-Found Tolerance Band need to be recalculated on a programmatic basis? What are the periodicity or events that would trigger a recalculation of the VLPT NSP As-Found Tolerance Band? Would a recalculation of the VLPT NSP As-Found Tolerance Band be the cause for a revision to any of the VLPT related items in RAI 7 (a) - (d) above?}} | | |
| | DRAFT REQUEST FOR ADDITIONAL INFORMATION HTP FUEL RCS PRESSURE-TEMPERATURE SAFETY LIMIT TECHNICAL SPECIFICATION AMENDMENT TAC NO. MD4910 DOCKET NO. 50-289 By letter dated March 22, 2007 (Agencywide Documents Access and Management System Accession No. ML070860968), AmerGen Energy Company, LLC (the licensee) submitted a license amendment request (LAR) regarding Three Mile Island Unit 1 Technical Specifications (TS). The proposed amendment would revise the reactor coolant system pressure-temperature limit to support use of the AREVA NP Mark-B-HTP fuel design. Based on the review of the information provided by the licensee, the staff has the following additional questions. |
| | : 1. The licensee indicated that the transient core penalty for a specific transient core model was calculated based on the largest DNBR difference between the limiting Mark-B-HTP fuel rod in a full core model of the mark-B-HTP fuel and specific transient core model for all of the statepoints, condition I/II DNB transients, and axial power shapes. |
| | Discuss the results of the transient core penalty analyses for condition I/II DNB transients with associated axial power shapes, and demonstrate that (1) the analysis scope in terms of the applicable condition I/II DNB transients and the allowable axial power shapes is adequate, and (2) the calculated value of the transient core penalty is a bounding value and acceptable for determining the thermal design limit that is used to calculate the reactor core safety limit. |
| | : 2. Provide the basis for your determination that no setpoint changes to reactor trip functions, other than the variable low reactor coolant system pressure trip, are needed to assure that the analyses of record remain bounding, or new analyses meet the applicable acceptance criteria for DBEs. |
| | : 3. Identify the reactor coolant pressure and reactor outlet temperature at the end points and mid point of proposed TS Figure 2.1-1. |
| | : 4. Identify the low reactor coolant pressure and high reactor outlet temperature intercept points of proposed TS Figure 2.3-1. |
| | : 5. Demonstrate that, for operation with measured values at the limits of the Acceptable Operation region of proposed TS Figure 2.3-1, there would be adequate assurance that the actual operating point will be conservative relative to the indicated Safety Limit line, given measurement errors consistent with the instrument channel uncertainties. |
| | : 6. Identify the normal operating point for the reactor coolant pressure and reactor outlet temperature. |
| | : 7. Identify the low reactor coolant pressure and high reactor outlet temperature intercept points for: |
| | (a) TS Variable Low Pressure Trip (VLPT) Limiting Safety System Setting (LSSS) |
| | Setpoint Enclosure |
| | |
| | (b) Adjusted TS VLPT (c) VLPT Nominal Setpoint (NSP) |
| | (d) VLPT As-Left Tolerance Band (e) VLPT Pre-Defined As-Found Tolerance Band. |
| | : 8. Provide additional details concerning the methodology used to develop the VLPT 10 psig additional margin. Confirm that this additional margin has not been used in determining the VLPT Pre-Defined As-Found Tolerance Band. |
| | : 9. Although the licensee has stated that the VLPT setpoint calculation is prepared in accordance with American National Standards Institute (ANSI) / Instrument Society of America (ISA) Standard 67.04.01-2000, Setpoints for Nuclear Safety-Related Instrumentation, and Recommended Practice ISA-RP67.04.02-2000, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation, the licensee has not directly addressed how the recommendations of Regulatory Guide (RG) 1.105, Revision 3, Setpoints for Safety-Related Instrumentation, are met. The licensee should address the regulatory positions of RG 1.105, Revision 3 or provide an acceptable alternative. |
| | : 10. The Summary of AMERGEN Commitments includes a commitment to determine the predefined limits for the VLPT NSP As-Found Tolerance on a programmatic basis. The licensee should clarify this commitment. Arent the predefined limits for the VLPT NSP As-Found Tolerance Band determined and included in March 22, 2007 submittal? Why would the limits of the VLPT NSP As-Found Tolerance Band need to be recalculated on a programmatic basis? What are the periodicity or events that would trigger a recalculation of the VLPT NSP As-Found Tolerance Band? Would a recalculation of the VLPT NSP As-Found Tolerance Band be the cause for a revision to any of the VLPT related items in RAI 7 (a) - (d) above?}} |
Letter Sequence Draft RAI |
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MONTHYEARML0708609682007-03-22022 March 2007 Technical Specification Change Request No. 335, Incorporating Revised Limit or the Variable Low Reactor Coolant System Pressure-Temperature Core Protection Safety Limit Project stage: Other ML0709601652007-04-10010 April 2007 Notice of Meeting with Amergen Energy Company, LLC to Discuss the Content of the Three Mile Island, Unit 1 License Amendment Request (LAR) Re High Thermal Performance Fuel Type Change Project stage: Meeting ML0709306012007-04-18018 April 2007 Areva Np Inc., Request for Withholding Information from Public Disclosure for Three Mile Island Nuclear Station, Unit 1 Project stage: Withholding Request Acceptance ML0714404222007-05-24024 May 2007 Facsimile Transmission, Draft Request for Additional Information Regarding the Reactor Coolant System Pressure-Temperature Safety Limit Project stage: Draft RAI ML0716300522007-06-12012 June 2007 Electronic Transmission, Draft Request for Additional Information Regarding the Reactor Coolant System Pressure - Temperature Safety Limit (TAC No. MD49100) Project stage: Draft RAI ML0717001772007-07-11011 July 2007 Request for Additional Information Regarding the High Thermal Performance (Htp) Fuel Reactor Coolant System Pressure-Temperature Safety Limit Technical Specification Amendment Project stage: RAI ML0721205662007-07-25025 July 2007 Response to Request for Additional Information - Technical Specification Change Request No. 335: Reactor Coolant System Pressure-Temperature Safety Limit Project stage: Response to RAI ML0728804182007-10-15015 October 2007 Tech Spec Pages for Amendment 262 Regarding Reactor Coolant System Pressure-Temperature Limit Project stage: Other ML0726800132007-10-15015 October 2007 Issuance of Amendment 262 Regarding Reactor Coolant System Pressure-Temperature Limit Project stage: Approval 2007-04-18
[Table View] |
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Category:Memoranda
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Al ML21218A0082021-08-10010 August 2021 NSIR Review of the Three Mile Island Physical Security Plan Revision 24 for the Verification of ASM 20-103 Incorporation ML21166A1182021-06-15015 June 2021 Technical Assistance Request - Review of Physical Security Plan for the Three Mile Island Unit 1 Power Station Independent Spent Fuel Storage Installation ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML19044A3842019-02-0606 February 2019 Notification of the Facility Director Change for the Nuclear Regulatory Commission Regulated Independent Spent Fuel Storage Installations (CLNl90659) ML18093B1022018-04-0303 April 2018 Notice of Public Meeting with Exelon Generation Company, LLC, to Discuss the NRCs Assessment of Safety Performance at Three Mile Island Nuclear Station, Unit 1 for 2017, as Described in the Annual Assessment Letter Dated February 28, 2018 ML17271A0532017-09-29029 September 2017 2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16252A2732016-08-26026 August 2016 Notification of the Facility Director Change Update for the NRC Independent Spent Fuel Storage Installations (EM-NRC-16-020) ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15230A5332015-08-18018 August 2015 Draft Request for Additional Information ML15175A3002015-08-0606 August 2015 Final Response to Task Interface Agreement 2015-01, Assessment of Three Mile Island Nuclear Station'S Use of a Non-Seismic Qualified Cleanup Path for the Borated Water Storage Tank ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML14133A0592014-07-0101 July 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, Federal Energy Regulatory Commission, Exelon Generation Co, LLC, and PPL Susquehanna, LLC, to Discuss Dam Failure Analysis.. ML14112A2392014-04-22022 April 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Peach Bottom Atomic Power Station Units 2 and 3, Susquehanna Steam Electric Station Units 1 and 2, and Three Mile Island Nuclear Station Unit 1 ML14106A3742014-03-31031 March 2014 Notification of Facility Director Change for the Nuclear Regulatory Commission Regulated Fort St Vrain, Three Mile Island and Idaho Spent Fuel Facility Independent Spent Fuel Storage Installations (EM-FMDP-14-018) ML13269A1792013-09-25025 September 2013 Draft Request for Additional Information ML13262A1632013-09-23023 September 2013 Meeting Report - Three Mile Island, Unit 2, Post-Shutdown Decommissioning Activities Report Public Meeting ML13253A2252013-09-10010 September 2013 Draft Request for Additional Information ML13249A2072013-09-0505 September 2013 Draft Request for Additional Information ML13221A4462013-08-12012 August 2013 Meeting Notice: to Discuss the Three Mile Island, Unit 2, Post-Shutdown Decommissioning Activities Report Submittal and Obtain Public Comments ML13190A1992013-08-0606 August 2013 FRN - Memo to Cindy Bladey Transmitting Federal Register Notice on Receipt of Three Mile Island - Unit 2 Post-Shutdown Decommissioning Activities Report ML13193A1452013-07-12012 July 2013 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values (TAC Nos. MF0425 & MF0426) ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML13177A3902013-06-26026 June 2013 Electronic Transmission, Draft Request for Additional Information Regarding Overall Integrated Plan in Response to Order Number EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13136A2032013-05-20020 May 2013 Meeting Notice with Exelon Generation Company, LLC, to Discuss Once Through Steam Generator Tube-to-Tube Wear at Three Mile Island, Unit 1 ML13066A1262013-03-0707 March 2013 Electronic Transmission, Draft Request for Additional Information Regarding Fifth Inservice Test Interval Relief Request PR-01 Nuclear Services Closed Cooling Water Flow Measurement ML13050A6362013-02-20020 February 2013 Draft RAI Memo ML13044A6652013-02-13013 February 2013 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval ML13044A3122013-02-13013 February 2013 Electronic Transmission, Draft Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML12310A2022012-11-0606 November 2012 Electronic Transmission, Draft Request for Additional Information Regarding 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12306A4542012-11-0101 November 2012 Electronic Transmission, Draft Request for Additional Information Regarding 2011 Steam Generator Tube Inspection Report ML1208701692012-03-28028 March 2012 Electronic Transmission, Draft Request for Additional Information Regarding Fourth Interval Inservice Testing Relief Request PR-05 ML1208602902012-03-26026 March 2012 Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements ML1134801002011-12-19019 December 2011 Notice of Forthcoming Meeting with Exelon Generation Company, LLC, and Entergy Operations, Inc., to Discuss Steam Generator Inspection Results at Three Mile Island, Unit 1, and Arkansas Nuclear One, Unit 1 ML1133605762011-12-0505 December 2011 Electronic Transmission, Draft Request for Additional Information Regarding Proposed License Amendment Revising Technical Specifications to Incorporate Administrative Changes ML1119900962011-07-20020 July 2011 Electronic Transmission, Draft Request for Additional Information Regarding Third Inservice Inspection Interval Relief Requests RR-11-01 and RR11-02 ML1113802512011-06-0303 June 2011 Memo to Cindy Bladey Federal Register Notice Providing Notice of Issuance of Director'S Decision Under 10 CFR 2.206 ML1111804942011-04-28028 April 2011 Electronic Transmission, Draft Request for Additional Information Regarding Fourth Interval Inservice Inspection Relief Request I4R-04 ML1107305692011-03-14014 March 2011 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request RR-10-01, Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval ML1106200272011-03-0303 March 2011 Electronic Transmission, Draft Request for Additional Information Proposed Technical Specification Changes Regarding Number of Required Operable Main Steam Safety Valves ML1105509182011-02-25025 February 2011 Notice of Meeting with Exelon Generation Company, LLC, to Discuss Three Mile Island, Unit 1, Main Steam Safety Valve License Amendment Request ML1105403472011-02-23023 February 2011 Electronic Transmission, Draft Request for Additional Information, Proposed Technical Specification Changes Regarding Relocation of Equipment Load List from Technical Specifications to a Licensee Controlled Document ML1103416642011-02-0404 February 2011 Electronic Transmission, Draft Request for Additional Information, Proposed Technical Specification Changes Regarding Number of Required Operable Main Steam Safety Valves ML1103402022011-02-0303 February 2011 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request RR-10-02, Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds ML1034405552010-12-10010 December 2010 Electronic Transmission, Draft Request for Additional Information Regarding Relief Request 14R-02 2023-04-10
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24157A3672024-06-13013 June 2024 Updated Post-Shutdown Decommissioning Activities Report Request for Additional Information Transmittal Letter ML24011A2352024-01-11011 January 2024 Eco Request for Additional Information for 2023 License Amendment Request 1-11-24 ML23187A0202023-06-29029 June 2023 TMI Unit 2 RAI Related to the Amended Post-Shutdown Decommissioning Activities Report ML23187A0332023-06-29029 June 2023 TMI Unit 2, PSDAR Rev. 5 RAIs ML23082A3432023-03-31031 March 2023 Enclosure - RAI - Three Mile Island, Unit 2 - Acceptance Review and Request for Additional Information for the Historic and Cultural Resources License Amendment Request - EPID: 2023-LLA-0026 ML22357A0142022-12-22022 December 2022 NRC Request for Additional Information Related to the TMI-2 Pdms Transition License Amendment Request ML22210A0882022-07-29029 July 2022 Enclosure - Three Mile Island, Unit No. 2 - Request for Additional Information for Requested Licensing Action Regarding Decommissioning Technical Specifications ML22143A8902022-05-23023 May 2022 Request for Additional information- TMI-1 ISFSI Only Physical Security License Amendment Request ML22125A0122022-04-28028 April 2022 Clarification RAI Partial Response Email from C Smith to a Snyder ML22110A0202022-04-19019 April 2022 Unit 1 Request for Additional Information ML22038A9362022-02-0707 February 2022 TMI2 Accident Analyses Questions ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML20164A0902020-06-10010 June 2020 Request for Additional Information Related to TMI-1 License Amendment Request to Delete Permanently Defueled Technical Specification 3/4.1.4 (L-2019-LLA-0250) ML19319B2082019-11-15015 November 2019 NRR E-mail Capture - Request for Additional Information Related to TMI-1 Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E (L-2019-LLA-0216) ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML18220A7832018-08-0707 August 2018 NRR E-mail Capture - Request for Additional Information Related to TMI Fall 2017 Steam Generator Tube Inspection Report ML18212A2712018-07-31031 July 2018 NRR E-mail Capture - Request for Additional Information Related to Amendment Regarding Decommissioning ERO Staffing Changes ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML16356A4802016-12-21021 December 2016 NRR E-mail Capture - RAIs on TMI License Amendment Request for Approval of Changes to the Three Mile Island Nuclear Station Emergency Plan Related to Staffing ML16337A0072016-12-0101 December 2016 NRR E-mail Capture - Draft RAIs Three Mile Island Nuclear Station, Units 1 and 2, License Amendment Request for Approval of Changes to the Three Mile Island Nuclear Station Emergency Plan Related to Staffing ML16287A4042016-10-11011 October 2016 Notification of Conduct of a Triennial Fire Protection Baseline Inspection ML15230A5332015-08-18018 August 2015 Draft Request for Additional Information ML15020A7372015-03-0808 March 2015 Request for Additional Information Regarding Related to December 22, 2014, Report Submitted Pursuant to 10 CFR 50.46 ML14307A1172014-11-14014 November 2014 Request for Additional Information Regarding Relief Request RR-14-01 Concerning Alternative Root Mean Square Depth Sizing Requirements ML14240A4122014-09-0404 September 2014 Request for Additional Information Regarding License Amendment Request to Eliminate Certain Technical Specification Reporting Requirements (Tac MF0628) ML14134A3222014-05-22022 May 2014 Request for Additional Information Regarding Review of Three Mile Island Nuclear Station Unit 1 Cycle 20 Core Operating Limits Report ML14134A1722014-05-14014 May 2014 Draft RAIs in Support of NRC Staff Review of TMI Cycle 20 COLR ML14052A2592014-02-27027 February 2014 Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specification Reporting Requirements ML14030A5832014-01-29029 January 2014 Draft Request for Additional Information Proposed Revision to Technical Specifications Reporting Requirements Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1 ML13266A2852013-10-21021 October 2013 Request for Additional Information on Three Mile Island Nuclear Station Unit 2 - post-shutdown Decommissioning Activities Report ML13276A6492013-10-0303 October 2013 Notification of Conduct of a Triennial Fire Protection Baseline Inspection ML13269A1792013-09-25025 September 2013 Draft Request for Additional Information ML13253A2252013-09-10010 September 2013 Draft Request for Additional Information ML13249A2072013-09-0505 September 2013 Draft Request for Additional Information ML13193A1752013-07-22022 July 2013 Request for Additional Information Regarding Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values ML13196A3382013-07-15015 July 2013 2013 Decommissioning Fund Report RAI ML13193A1452013-07-12012 July 2013 Electronic Transmission, Draft Request for Additional Information Regarding Proposed Revision to Pressure and Temperature Limit Curves and Exemption Request for Initial Reference Temperature Values (TAC Nos. 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June 12, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910)
The attached draft request for additional information (RAI) was transmitted by electronic mail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289
Enclosure:
As stated
June 12, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE SAFETY LIMIT (TAC NO. MD4910)
The attached draft request for additional information (RAI) was transmitted by electronic mail on June 7, 2007, to Mr. David Distel, at AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated March 22, 2007, regarding the proposed Three Mile Island, Unit 1 variable reactor coolant system low pressure trip setpoint change in the facility Technical Specifications (TSs) due to the introduction of AREVA High Thermal Performance (HTP) fuel. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289
Enclosure:
As stated DISTRIBUTION:
Public BMarcus, NRR RidsNrrPMPBamford AHowe, NRR GCranston, NRR LPL1-2 R/F RidsNrrPMEMiller SSun, NRR Accession No.: ML071630052 *via e-mail **via memorandum OFFICE LPL1-2/PM LPL1-2/PM EICB/BC SRSB/BC NAME PBamford EMiller AHowe** GCranston*
DATE 6/12/07 6/12/07 05/21/2007 05/22/2007 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION HTP FUEL RCS PRESSURE-TEMPERATURE SAFETY LIMIT TECHNICAL SPECIFICATION AMENDMENT TAC NO. MD4910 DOCKET NO. 50-289 By letter dated March 22, 2007 (Agencywide Documents Access and Management System Accession No. ML070860968), AmerGen Energy Company, LLC (the licensee) submitted a license amendment request (LAR) regarding Three Mile Island Unit 1 Technical Specifications (TS). The proposed amendment would revise the reactor coolant system pressure-temperature limit to support use of the AREVA NP Mark-B-HTP fuel design. Based on the review of the information provided by the licensee, the staff has the following additional questions.
- 1. The licensee indicated that the transient core penalty for a specific transient core model was calculated based on the largest DNBR difference between the limiting Mark-B-HTP fuel rod in a full core model of the mark-B-HTP fuel and specific transient core model for all of the statepoints, condition I/II DNB transients, and axial power shapes.
Discuss the results of the transient core penalty analyses for condition I/II DNB transients with associated axial power shapes, and demonstrate that (1) the analysis scope in terms of the applicable condition I/II DNB transients and the allowable axial power shapes is adequate, and (2) the calculated value of the transient core penalty is a bounding value and acceptable for determining the thermal design limit that is used to calculate the reactor core safety limit.
- 2. Provide the basis for your determination that no setpoint changes to reactor trip functions, other than the variable low reactor coolant system pressure trip, are needed to assure that the analyses of record remain bounding, or new analyses meet the applicable acceptance criteria for DBEs.
- 3. Identify the reactor coolant pressure and reactor outlet temperature at the end points and mid point of proposed TS Figure 2.1-1.
- 4. Identify the low reactor coolant pressure and high reactor outlet temperature intercept points of proposed TS Figure 2.3-1.
- 5. Demonstrate that, for operation with measured values at the limits of the Acceptable Operation region of proposed TS Figure 2.3-1, there would be adequate assurance that the actual operating point will be conservative relative to the indicated Safety Limit line, given measurement errors consistent with the instrument channel uncertainties.
- 6. Identify the normal operating point for the reactor coolant pressure and reactor outlet temperature.
- 7. Identify the low reactor coolant pressure and high reactor outlet temperature intercept points for:
(a) TS Variable Low Pressure Trip (VLPT) Limiting Safety System Setting (LSSS)
Setpoint Enclosure
(b) Adjusted TS VLPT (c) VLPT Nominal Setpoint (NSP)
(d) VLPT As-Left Tolerance Band (e) VLPT Pre-Defined As-Found Tolerance Band.
- 8. Provide additional details concerning the methodology used to develop the VLPT 10 psig additional margin. Confirm that this additional margin has not been used in determining the VLPT Pre-Defined As-Found Tolerance Band.
- 9. Although the licensee has stated that the VLPT setpoint calculation is prepared in accordance with American National Standards Institute (ANSI) / Instrument Society of America (ISA) Standard 67.04.01-2000, Setpoints for Nuclear Safety-Related Instrumentation, and Recommended Practice ISA-RP67.04.02-2000, Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation, the licensee has not directly addressed how the recommendations of Regulatory Guide (RG) 1.105, Revision 3, Setpoints for Safety-Related Instrumentation, are met. The licensee should address the regulatory positions of RG 1.105, Revision 3 or provide an acceptable alternative.
- 10. The Summary of AMERGEN Commitments includes a commitment to determine the predefined limits for the VLPT NSP As-Found Tolerance on a programmatic basis. The licensee should clarify this commitment. Arent the predefined limits for the VLPT NSP As-Found Tolerance Band determined and included in March 22, 2007 submittal? Why would the limits of the VLPT NSP As-Found Tolerance Band need to be recalculated on a programmatic basis? What are the periodicity or events that would trigger a recalculation of the VLPT NSP As-Found Tolerance Band? Would a recalculation of the VLPT NSP As-Found Tolerance Band be the cause for a revision to any of the VLPT related items in RAI 7 (a) - (d) above?