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| {{#Wiki_filter:August 8, 2006Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:August 8, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FORADDITIONAL INFORMATION REGARDING SNUBBER EXAMINATION AND TESTING (TAC NOS. MC9657 AND MC9658) | | SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SNUBBER EXAMINATION AND TESTING (TAC NOS. MC9657 AND MC9658) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| By letter dated January 25, 2006, Tennessee Valley Authority (the licensee) requested relieffrom the American Society of Mechanical Engineers Section XI Code requirements for snubber examination and testing. The proposed request for relief is a continuation of the previously approved relief request from the Sequoyah Nuclear Plant (SQN), Units 1 and 2 second 10-year inspection interval and was submitted for applicability during SQN's third 10-year inspectioninterval that began on June 1, 2006.In order for the staff to complete its review of this application, we request that the licenseeprovide responses to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you intend to respond to this RAI within 30 days of receipt of this letter.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 | | By letter dated January 25, 2006, Tennessee Valley Authority (the licensee) requested relief from the American Society of Mechanical Engineers Section XI Code requirements for snubber examination and testing. The proposed request for relief is a continuation of the previously approved relief request from the Sequoyah Nuclear Plant (SQN), Units 1 and 2 second 10-year inspection interval and was submitted for applicability during SQNs third 10-year inspection interval that began on June 1, 2006. |
| | In order for the staff to complete its review of this application, we request that the licensee provide responses to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you intend to respond to this RAI within 30 days of receipt of this letter. |
| | 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:== |
| As stated cc w/encl: See next page | | As stated cc w/encl: See next page |
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| ML062180078NRR-088OFFICELPL2-2/PMLPL2-2/LA(A) CPTB/BCLPL2-2/BCNAMEDPickettRSolaCHammer for TLiuLRaghavan for MMarshallDATE 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 Mr. Karl W. SingerSEQUOYAH NUCLEAR PLANTTennessee Valley Authority 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 REQUEST FOR ADDITIONAL INFORMATIONSEQUOYAH NUCLEAR PLANT UNITS 1 AND 2SNUBBER RELIEF REQUESTSNUBBERS INSPECTION AND TESTING FOR THIRD 10-YEAR INTERVALTAC NOS. MC9657 AND MC96581.The licensee requested relief from the requirements of IWF-5200(a) and (b), and IWF-5300(a) and (b) (Page E1-2). IWF-1220 states that "the inservice inspection requirements for snubbers shall be in accordance with the requirements of IWF-5000."
| | ML062180078 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA (A) CPTB/BC LPL2-2/BC NAME DPickett RSola CHammer for TLiu LRaghavan for MMarshall DATE 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc: |
| Article IWF-5000 also contains requirements for snubber preservice and inservice examinations, and tests for snubbers integral and nonintegral attachments under IWF-5200(c) and IWF-5300(c). Please explain, whether and how the requirements of IWF-5200(c) and IWF-5300(c) will be met. 2.The licensee requested relief from IWF-5400, Repair/ Replacement Activities (Page E1-2). IWF-5400 states that "Repair/replacement activities performed on snubbers shall be in accordance with IWA-4000. Snubbers installed, corrected or modified by repair/replacement activities shall be examined and tested in accordance with the applicable requirements of IWF-5200 prior to return to service." Please explain, whether and how IWF-5200(c) requirements of IWF-5200 will be met.
| | 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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| 3.IWF-5200(a) and (b), and IWF-5300(a) and (b) states that "preservice and inserviceexamination and testings shall be performed in accordance with ASME/ANSI OM, Part 4." Under Basis for Relief (Page E1-3), the licensee states that "Sequoyah Nuclear Plant (SQN) Technical Requirement Manual (TRM) adopts the provisions provided in NRC Generic Letter (GL) 90-09." GL 90-09, only provides guidance for Snubber Visual Examination Intervals and Corrective Actions. GL-90-09 does not replace any other requirements of OM Part 4. Therefore please explain the following:3a.OM-4, Section 2.1 requires preservice examination of snubbers. Please explain,how these preservice requirements are met in the proposed alternative SQN TRM.3b.OM-4, Section 3.1 requires preservice operability testing of snubbers. Pleaseexplain, how these preservice operability testing requirements are met in theproposed alternative SQN TRM.4.On page E1-4, last paragraph, the licensee states that "Performance of each test orinspection is documented and retained with the site procedure as a summary report with the data similar to the requirements prescribed in the ASME Section XI Code. The licensee is to provide actual subsection and/or paragraph of ASME Section XI, which is intended to meet for this requirement of documentation.Enclosure 5.Please explain, how the requirements of OM-4, Section 3.2.4 "Inservice OperabilityFailure Evaluation" are met in the proposed alternative as specified in the SQN TRM.}} | | REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 SNUBBER RELIEF REQUEST SNUBBERS INSPECTION AND TESTING FOR THIRD 10-YEAR INTERVAL TAC NOS. MC9657 AND MC9658 |
| | : 1. The licensee requested relief from the requirements of IWF-5200(a) and (b), and IWF-5300(a) and (b) (Page E1-2). IWF-1220 states that the inservice inspection requirements for snubbers shall be in accordance with the requirements of IWF-5000. |
| | Article IWF-5000 also contains requirements for snubber preservice and inservice examinations, and tests for snubbers integral and nonintegral attachments under IWF-5200(c) and IWF-5300(c). Please explain, whether and how the requirements of IWF-5200(c) and IWF-5300(c) will be met. |
| | : 2. The licensee requested relief from IWF-5400, Repair/ Replacement Activities (Page E1-2). IWF-5400 states that Repair/replacement activities performed on snubbers shall be in accordance with IWA-4000. Snubbers installed, corrected or modified by repair/replacement activities shall be examined and tested in accordance with the applicable requirements of IWF-5200 prior to return to service. Please explain, whether and how IWF-5200(c) requirements of IWF-5200 will be met. |
| | : 3. IWF-5200(a) and (b), and IWF-5300(a) and (b) states that preservice and inservice examination and testings shall be performed in accordance with ASME/ANSI OM, Part |
| | : 4. Under Basis for Relief (Page E1-3), the licensee states that Sequoyah Nuclear Plant (SQN) Technical Requirement Manual (TRM) adopts the provisions provided in NRC Generic Letter (GL) 90-09. GL 90-09, only provides guidance for Snubber Visual Examination Intervals and Corrective Actions. GL-90-09 does not replace any other requirements of OM Part 4. Therefore please explain the following: |
| | 3a. OM-4, Section 2.1 requires preservice examination of snubbers. Please explain, how these preservice requirements are met in the proposed alternative SQN TRM. |
| | 3b. OM-4, Section 3.1 requires preservice operability testing of snubbers. Please explain, how these preservice operability testing requirements are met in the proposed alternative SQN TRM. |
| | : 4. On page E1-4, last paragraph, the licensee states that Performance of each test or inspection is documented and retained with the site procedure as a summary report with the data similar to the requirements prescribed in the ASME Section XI Code. The licensee is to provide actual subsection and/or paragraph of ASME Section XI, which is intended to meet for this requirement of documentation. |
| | Enclosure |
| | : 5. Please explain, how the requirements of OM-4, Section 3.2.4 Inservice Operability Failure Evaluation are met in the proposed alternative as specified in the SQN TRM.}} |
Letter Sequence RAI |
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MONTHYEARML0621800782006-08-0808 August 2006
RAI Re Snubber Examination and Testing
Project stage: RAI
ML0631802062006-12-21021 December 2006
Safety Evaluation of Relief Request for the Third 10-year Inservice Inspection Interval and Test Program for Snubbers
Project stage: Approval
2006-12-21
[Table View] |
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Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024
NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023
ML23319A2452024-01-29029 January 2024
Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions
ML24018A0142024-01-17017 January 2024
Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913
ML24011A3182024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), October 2023
ML24011A3172024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), September 2023
ML24011A3202024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), December 2023
ML24011A3162024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), August 2023
ML24011A3192024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), November 2023
IR 05000327/20234422024-01-11011 January 2024
95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter
ML24010A2132024-01-10010 January 2024
CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers
ML24018A0952024-01-0404 January 2024
Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0
ML24004A0332024-01-0303 January 2024
Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter
ML24004A0402024-01-0303 January 2024
Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation
CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023
Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
ML23346A1222023-12-12012 December 2023
Annual Non-Radiological Environmental Operating Report - 2023
IR 05000327/20234202023-11-28028 November 2023
Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML23324A4362023-11-0909 November 2023
Exam Corporate Notification Letter Aka 210-day Letter
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
IR 05000327/20230032023-11-0303 November 2023
Integrated Inspection Report 05000327/2023003 and 05000328/2023003
ML23306A1592023-11-0202 November 2023
Enforcement Action EA-22-129 Inspection Readiness Notification
ML23292A0792023-10-19019 October 2023
Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency
IR 05000327/20230112023-10-16016 October 2023
Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011
ML23285A0882023-10-12012 October 2023
Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31
ML23284A4252023-10-11011 October 2023
10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report
ML23283A2792023-10-10010 October 2023
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual
ML23279A0612023-10-0505 October 2023
Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23277A0462023-10-0404 October 2023
Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML23275A0272023-09-29029 September 2023
Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023
ML23271A1662023-09-28028 September 2023
Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2)
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023
Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
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IR 05000327/20234032023-09-14014 September 2023
Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter)
ML23257A0062023-09-14014 September 2023
Enforcement Action EA-22-129 Inspection Postponement Request
ML23254A2192023-09-11011 September 2023
Emergency Plan Implementing Procedure Revisions
ML23254A0652023-09-0707 September 2023
Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2)
CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023
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IR 05000327/20230052023-08-29029 August 2023
Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005
ML23233A0122023-08-17017 August 2023
Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement
ML23233A0142023-08-15015 August 2023
Discharge Monitoring Report (Dmr), July 2023
ML23215A1212023-08-0303 August 2023
301 Exam Administrative Items (2B) Normal Release
ML23215A1572023-08-0303 August 2023
Enforcement Action EA-22-129 Inspection Readiness Notification
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Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
2024-01-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23307A0832023-11-0808 November 2023
Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023
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
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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)
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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
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ML22151A0092022-05-26026 May 2022
NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02
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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
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Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04
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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
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NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update
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Request for Additional Information Regarding Hydrologic UFSAR Update
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20200123 - Sequoyah Radiation Safety Inspection Document Request Letter
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Emergency Preparedness Program Inspection Request for Information
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RP Inspection Document Request 2019-03
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NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04)
ML18283B0592018-10-10010 October 2018
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04 RP Inspection Document Request
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NRR E-mail Capture - Additional Information Needs Identified - 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)
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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
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ML17112A0402017-04-20020 April 2017
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Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007)
ML15194A3882015-07-13013 July 2015
Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec
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E-mail Re. Request for Additional Information RR RP-07
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ML15050A0962015-02-19019 February 2015
E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec
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E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink
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Requalification Program Inspection - Sequoyah Nuclear Plant
ML14254A2042014-09-22022 September 2014
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application - Set 22 (TAC Nos. MF0481 and MF0482)
ML14220A2132014-08-0808 August 2014
E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805
2023-02-27
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August 8, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING SNUBBER EXAMINATION AND TESTING (TAC NOS. MC9657 AND MC9658)
Dear Mr. Singer:
By letter dated January 25, 2006, Tennessee Valley Authority (the licensee) requested relief from the American Society of Mechanical EngineersSection XI Code requirements for snubber examination and testing. The proposed request for relief is a continuation of the previously approved relief request from the Sequoyah Nuclear Plant (SQN), Units 1 and 2 second 10-year inspection interval and was submitted for applicability during SQNs third 10-year inspection interval that began on June 1, 2006.
In order for the staff to complete its review of this application, we request that the licensee provide responses to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you intend to respond to this RAI within 30 days of receipt of this letter.
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:
As stated cc w/encl: See next page
ML062180078 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA (A) CPTB/BC LPL2-2/BC NAME DPickett RSola CHammer for TLiu LRaghavan for MMarshall DATE 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 08 / 08 / 06 Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority 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 SNUBBER RELIEF REQUEST SNUBBERS INSPECTION AND TESTING FOR THIRD 10-YEAR INTERVAL TAC NOS. MC9657 AND MC9658
- 1. The licensee requested relief from the requirements of IWF-5200(a) and (b), and IWF-5300(a) and (b) (Page E1-2). IWF-1220 states that the inservice inspection requirements for snubbers shall be in accordance with the requirements of IWF-5000.
Article IWF-5000 also contains requirements for snubber preservice and inservice examinations, and tests for snubbers integral and nonintegral attachments under IWF-5200(c) and IWF-5300(c). Please explain, whether and how the requirements of IWF-5200(c) and IWF-5300(c) will be met.
- 2. The licensee requested relief from IWF-5400, Repair/ Replacement Activities (Page E1-2). IWF-5400 states that Repair/replacement activities performed on snubbers shall be in accordance with IWA-4000. Snubbers installed, corrected or modified by repair/replacement activities shall be examined and tested in accordance with the applicable requirements of IWF-5200 prior to return to service. Please explain, whether and how IWF-5200(c) requirements of IWF-5200 will be met.
- 3. IWF-5200(a) and (b), and IWF-5300(a) and (b) states that preservice and inservice examination and testings shall be performed in accordance with ASME/ANSI OM, Part
- 4. Under Basis for Relief (Page E1-3), the licensee states that Sequoyah Nuclear Plant (SQN) Technical Requirement Manual (TRM) adopts the provisions provided in NRC Generic Letter (GL) 90-09. GL 90-09, only provides guidance for Snubber Visual Examination Intervals and Corrective Actions. GL-90-09 does not replace any other requirements of OM Part 4. Therefore please explain the following:
3a. OM-4, Section 2.1 requires preservice examination of snubbers. Please explain, how these preservice requirements are met in the proposed alternative SQN TRM.
3b. OM-4, Section 3.1 requires preservice operability testing of snubbers. Please explain, how these preservice operability testing requirements are met in the proposed alternative SQN TRM.
- 4. On page E1-4, last paragraph, the licensee states that Performance of each test or inspection is documented and retained with the site procedure as a summary report with the data similar to the requirements prescribed in the ASME Section XI Code. The licensee is to provide actual subsection and/or paragraph of ASME Section XI, which is intended to meet for this requirement of documentation.
Enclosure
- 5. Please explain, how the requirements of OM-4, Section 3.2.4 Inservice Operability Failure Evaluation are met in the proposed alternative as specified in the SQN TRM.
