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| | number = ML060260259 | | | number = ML060260259 |
| | issue date = 03/02/2006 | | | issue date = 03/02/2006 |
| | title = RAI, Nominal Trip Setpoints (TAC MC4408, TAC MC4409) | | | title = RAI, Nominal Trip Setpoints |
| | author name = Pickett D | | | author name = Pickett D |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
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| =Text= | | =Text= |
| {{#Wiki_filter:March 2, 2006Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 | | {{#Wiki_filter:March 2, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FORADDITIONAL INFORMATION REGARDING NOMINAL TRIP SETPOINTS (TAC NOS. MC4408 AND MC4409) (TVA-SQN-TS-02-01) | | SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING NOMINAL TRIP SETPOINTS (TAC NOS. MC4408 AND MC4409) (TVA-SQN-TS-02-01) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| The U. S. Nuclear Regulatory Commission (NRC) staff is continuing its review of yourapplication dated August 18, 2004, Technical Specification Change No. 02-01, Revision 1, Nominal Trip Setpoints for Reactor Protection System and Engineered Safety Features Instrumentation. In a letter dated May 19, 2005 (ADAMS Accession Number: ML0512604640), the NRC staffrequested additional information from Tennessee Valley Authority (TVA) as part of the interim approach adopted by the NRC to review license amendments related to setpoint methodology.As a result of the NRC's updated approach to this issue, the request for additionalinformation (RAI) originally contained in our letter dated May 19, 2005, is hereby withdrawn and replaced by the RAI enclosed in this letter. Our letter dated May 19, 2005, also asked for the following three items: | | The U. S. Nuclear Regulatory Commission (NRC) staff is continuing its review of your application dated August 18, 2004, Technical Specification Change No. 02-01, Revision 1, Nominal Trip Setpoints for Reactor Protection System and Engineered Safety Features Instrumentation. |
| 1.An explicit regulatory commitment to adopt the final Technical Specification Task Forcetechnical specification change to come into conformance with the existing understanding of the requirements of 10 CFR 50.36.2.An explicit regulatory commitment to assess the operability of tested instrumentationbased on the previous as-left instrument setting and accounting for the uncertainties associated with the test or calibration.3.A revision to the technical specifications for the limiting safety system settings beingchanged by the license amendment request to incorporate a footnote that states:The as-left instrument setting shall be returned to a setting within thetolerance band of the trip setpoint established to protect the safety limit.These three items are likewise withdrawn and do not need to be addressed by TVA. Based upon discussions with your staff, we understand that you plan to respond to theenclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364.Sincerely,/RA/ Douglas V. Pickett, Senior Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-327 and 50-328 | | In a letter dated May 19, 2005 (ADAMS Accession Number: ML0512604640), the NRC staff requested additional information from Tennessee Valley Authority (TVA) as part of the interim approach adopted by the NRC to review license amendments related to setpoint methodology. |
| | As a result of the NRCs updated approach to this issue, the request for additional information (RAI) originally contained in our letter dated May 19, 2005, is hereby withdrawn and replaced by the RAI enclosed in this letter. |
| | Our letter dated May 19, 2005, also asked for the following three items: |
| | : 1. An explicit regulatory commitment to adopt the final Technical Specification Task Force technical specification change to come into conformance with the existing understanding of the requirements of 10 CFR 50.36. |
| | : 2. An explicit regulatory commitment to assess the operability of tested instrumentation based on the previous as-left instrument setting and accounting for the uncertainties associated with the test or calibration. |
| | : 3. A revision to the technical specifications for the limiting safety system settings being changed by the license amendment request to incorporate a footnote that states: |
| | The as-left instrument setting shall be returned to a setting within the tolerance band of the trip setpoint established to protect the safety limit. |
| | These three items are likewise withdrawn and do not need to be addressed by TVA. |
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| | Based upon discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364. |
| | Sincerely, |
| | /RA/ |
| | Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/enclosure: See next page | | Request for Additional Information cc w/enclosure: See next page |
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| | ML060260259 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA BC:CSGB LPL2-2/BC NAME DPickett RSola AHowe MMarshall DATE 2 / 13 / 06 2 / 13 / 06 2 / 14 / 06 3 / 02 / 06 Mr. Karl W. Singer Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT cc: |
| | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place ATTN: Mr. James D. Smith 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 Tennessee Valley Authority P.O. Box 2000 Mr. Robert J. Beecken, Vice President Soddy Daisy, TN 37384-2000 Nuclear Support Tennessee Valley Authority Mr. David A. Kulisek, Plant Manager 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Site Vice President Senior Resident Inspector Sequoyah Nuclear Plant Sequoyah Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 2600 Igou Ferry Road Soddy Daisy, TN 37384-2000 Soddy Daisy, TN 37379 General Counsel Mr. Lawrence E. Nanney, Director Tennessee Valley Authority Division of Radiological Health ET 11A Dept. of Environment & Conservation 400 West Summit Hill Drive Third Floor, L and C Annex Knoxville, TN 37902 401 Church Street Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing County Mayor Tennessee Valley Authority Hamilton County Courthouse 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854 |
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| | REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS CHANGES FOR NOMINAL TRIP SETPOINTS FOR REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURES INSTRUMENTATION DOCKET NOS. 50-327 AND 50-328 |
| | : 1. Setpoint Calculation Methodology: Provide documentation (including sample calculations) of the methodology used for establishing the limiting nominal setpoint and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing as described below. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint. |
| | : 2. Safety Limit (SL)-Related Determination: Provide a statement as to whether or not the setpoint is a limiting safety system setting for a variable on which a SL has been placed as discussed in Title 10 of the Code of Frederal Regulations (10 CFR) Part 50.36(c)(ii)(A). Such setpoints are described as SL-Related in the discussions that follow. For each setpoint that you determined not to be SL-Related, explain the basis for this determination. |
| | : 3. For setpoints that are determined to be SL-Related: The NRC letter to the Nuclear Energy Institute (NEI) Setpoint Methods Task Force (SMTF) dated September 7, 2005 (ADAMS Accession Number: ML052500004), describes Setpoint-Related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part A of the Enclosure to the letter provides limiting condition for operation (LCO) notes to be added to the TS, and Part B includes a check list of the information to be provided in the TS Bases related to the proposed TS changes. |
| | : a. Describe whether and how you plan to implement the SRTS suggested in the September 7, 2005, letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below. |
| | : b. As-Found Setpoint Evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the ENCLOSURE |
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| ML060260259 NRR-088OFFICELPL2-2/PMLPL2-2/LABC:CSGBLPL2-2/BCNAMEDPickettRSolaAHoweMMarshallDATE 2 / 13 / 06 2 / 13 / 06 2 / 14 / 06 3 / 02 / 06 Mr. Karl W. SingerTennessee Valley Authority SEQUOYAH NUCLEAR PLANT cc: Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Robert J. Beecken, Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Randy DouetSite Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000General CounselTennessee Valley Authority ET 11A 400 West Summit Hill DriveKnoxville, TN 37902Mr. John C. Fornicola, ManagerNuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. Paul L. Pace, ManagerLicensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Mr. David A. Kulisek, Plant ManagerSequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Senior Resident InspectorSequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379Mr. Lawrence E. Nanney, DirectorDivision of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532County MayorHamilton County Courthouse Chattanooga, TN 37402-2801Ms. Ann P. Harris341 Swing Loop Road Rockwood, Tennessee 37854 ENCLOSUREREQUEST FOR ADDITIONAL INFORMATIONSEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2TECHNICAL SPECIFICATIONS CHANGES FOR NOMINAL TRIP SETPOINTS FOR REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURESINSTRUMENTATIONDOCKET NOS. 50-327 AND 50-3281.Setpoint Calculation Methodology: Provide documentation (including samplecalculations) of the methodology used for establishing the limiting nominal setpoint andthe limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing as described below. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint.2.Safety Limit (SL)-Related Determination: Provide a statement as to whether or not thesetpoint is a limiting safety system setting for a variable on which a SL has been placedas discussed in Title 10 of the Code of Frederal Regulations (10 CFR) Part50.36(c)(ii)(A). Such setpoints are described as "SL-Related" in the discussions that follow. For each setpoint that you determined not to be SL-Related, explain the basisfor this determination.3.For setpoints that are determined to be SL-Related: The NRC letter to the NuclearEnergy Institute (NEI) Setpoint Methods Task Force (SMTF) dated September 7, 2005(ADAMS Accession Number: ML052500004), describes Setpoint-Related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part "A" of the Enclosure to the letter provides limiting condition for operation (LCO) notes to be added to the TS, and Part "B" includes a check list of the information to be provided in the TS Bases related to the proposed TS changes.a.Describe whether and how you plan to implement the SRTS suggested in theSeptember 7, 2005, letter. If you do not plan to adopt the suggested SRTS, thenexplain how you will ensure compliance with 10 CFR 50.36 by addressing items3b and 3c, below.b.As-Found Setpoint Evaluation: Describe how surveillance test results andassociated TS limits are used to establish operability of the safety system. Showthat this evaluation is consistent with the assumptions and results of the setpointcalculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be "inoperable" or "operable but degraded." If the criteria for determining operability of the instrument being tested are located in adocument other than the TS (e.g. plant test procedure), explain how the requirements of 10 CFR 50.36 are met.c.As-Left Setpoint Control: Describe the controls employed to ensure that theinstrument setpoint is, upon completion of surveillance testing, consistent withthe assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met.4.For setpoints that are not determined to be SL-related setpoints in response toQuestion 2: Describe the measures to be taken to ensure that the associatedinstrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the As-Left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. If the controls are located in a document other than the TS (e.g., plant test procedure),describe how it is ensured that the controls will be implemented to satisfy operabilityrequirements.}}
| | criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g. plant test procedure), explain how the requirements of 10 CFR 50.36 are met. |
| | : c. As-Left Setpoint Control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met. |
| | : 4. For setpoints that are not determined to be SL-related setpoints in response to Question 2: Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the As-Left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. If the controls are located in a document other than the TS (e.g., plant test procedure), |
| | describe how it is ensured that the controls will be implemented to satisfy operability requirements.}} |
Letter Sequence RAI |
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MONTHYEARML0501803662005-01-19019 January 2005 RAI Revise Trip Setpoint Column of RPS (TACs MC4408, MC4409) Project stage: RAI ML0512604642005-05-19019 May 2005 RAI, Normal Trip Setpoints Using Revised Method 3 (Tac No. MC4408, MC4409) (TVA-SQN-TS-02-01) Project stage: RAI ML0520706042005-07-26026 July 2005 Notice of Meeting with Tennessee Valley Authority (TVA) BFN Units 1, 2, and 3, and Sequoyah Units 1 and 2 on Resolution of Instrument Setpoint Concerns Project stage: Meeting ML0602602592006-03-0202 March 2006 RAI, Nominal Trip Setpoints Project stage: RAI ML0619903032006-07-11011 July 2006 Technical Specifications Change 02-01, Revision 2 - Nominal Trip Setpoints for Reactor Protection System and Engineered Safety Features Instrumentation and Response to Request for Additional Information Project stage: Response to RAI 2005-07-26
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Category:Letter
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Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24046A2362024-02-15015 February 2024 Discharge Monitoring Report (Dmr), January 2024 ML24046A2072024-02-15015 February 2024 Emergency Plan Implementing Procedure Revisions. Includes EPIP-6, Revision 59 and EPIP-7, Revision 38 ML24046A2372024-02-15015 February 2024 Annual Water Withdrawal Report 2023 ML24046A0252024-02-14014 February 2024 Final Report of a Deviation or Failure to Comply Lube Oil Scavenging and Fuel Oil Engine Driven Pump 2024-08-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - 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D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. 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Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink 2024-05-31
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March 2, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION REGARDING NOMINAL TRIP SETPOINTS (TAC NOS. MC4408 AND MC4409) (TVA-SQN-TS-02-01)
Dear Mr. Singer:
The U. S. Nuclear Regulatory Commission (NRC) staff is continuing its review of your application dated August 18, 2004, Technical Specification Change No. 02-01, Revision 1, Nominal Trip Setpoints for Reactor Protection System and Engineered Safety Features Instrumentation.
In a letter dated May 19, 2005 (ADAMS Accession Number: ML0512604640), the NRC staff requested additional information from Tennessee Valley Authority (TVA) as part of the interim approach adopted by the NRC to review license amendments related to setpoint methodology.
As a result of the NRCs updated approach to this issue, the request for additional information (RAI) originally contained in our letter dated May 19, 2005, is hereby withdrawn and replaced by the RAI enclosed in this letter.
Our letter dated May 19, 2005, also asked for the following three items:
- 1. An explicit regulatory commitment to adopt the final Technical Specification Task Force technical specification change to come into conformance with the existing understanding of the requirements of 10 CFR 50.36.
- 2. An explicit regulatory commitment to assess the operability of tested instrumentation based on the previous as-left instrument setting and accounting for the uncertainties associated with the test or calibration.
- 3. A revision to the technical specifications for the limiting safety system settings being changed by the license amendment request to incorporate a footnote that states:
The as-left instrument setting shall be returned to a setting within the tolerance band of the trip setpoint established to protect the safety limit.
These three items are likewise withdrawn and do not need to be addressed by TVA.
Based upon discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML060260259 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA BC:CSGB LPL2-2/BC NAME DPickett RSola AHowe MMarshall DATE 2 / 13 / 06 2 / 13 / 06 2 / 14 / 06 3 / 02 / 06 Mr. Karl W. Singer Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place ATTN: Mr. James D. Smith 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 Tennessee Valley Authority P.O. Box 2000 Mr. Robert J. Beecken, Vice President Soddy Daisy, TN 37384-2000 Nuclear Support Tennessee Valley Authority Mr. David A. Kulisek, Plant Manager 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Site Vice President Senior Resident Inspector Sequoyah Nuclear Plant Sequoyah Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 2600 Igou Ferry Road Soddy Daisy, TN 37384-2000 Soddy Daisy, TN 37379 General Counsel Mr. Lawrence E. Nanney, Director Tennessee Valley Authority Division of Radiological Health ET 11A Dept. of Environment & Conservation 400 West Summit Hill Drive Third Floor, L and C Annex Knoxville, TN 37902 401 Church Street Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing County Mayor Tennessee Valley Authority Hamilton County Courthouse 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854
REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS CHANGES FOR NOMINAL TRIP SETPOINTS FOR REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURES INSTRUMENTATION DOCKET NOS. 50-327 AND 50-328
- 1. Setpoint Calculation Methodology: Provide documentation (including sample calculations) of the methodology used for establishing the limiting nominal setpoint and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing as described below. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint.
- 2. Safety Limit (SL)-Related Determination: Provide a statement as to whether or not the setpoint is a limiting safety system setting for a variable on which a SL has been placed as discussed in Title 10 of the Code of Frederal Regulations (10 CFR) Part 50.36(c)(ii)(A). Such setpoints are described as SL-Related in the discussions that follow. For each setpoint that you determined not to be SL-Related, explain the basis for this determination.
- 3. For setpoints that are determined to be SL-Related: The NRC letter to the Nuclear Energy Institute (NEI) Setpoint Methods Task Force (SMTF) dated September 7, 2005 (ADAMS Accession Number: ML052500004), describes Setpoint-Related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part A of the Enclosure to the letter provides limiting condition for operation (LCO) notes to be added to the TS, and Part B includes a check list of the information to be provided in the TS Bases related to the proposed TS changes.
- a. Describe whether and how you plan to implement the SRTS suggested in the September 7, 2005, letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below.
- b. As-Found Setpoint Evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the ENCLOSURE
criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g. plant test procedure), explain how the requirements of 10 CFR 50.36 are met.
- c. As-Left Setpoint Control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
- 4. For setpoints that are not determined to be SL-related setpoints in response to Question 2: Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the As-Left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. If the controls are located in a document other than the TS (e.g., plant test procedure),
describe how it is ensured that the controls will be implemented to satisfy operability requirements.