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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C 20555-0001 September 26, 2018 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority Sequoyah Nuclear Plant 1101 Market Street, LP 4A Chattanooga, TN 37402-2801 0MB Control No. 3150-0231 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C 20555-0001 September 26, 2018 0MB Control No. 3150-0231 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority Sequoyah Nuclear Plant 1101 Market Street, LP 4A Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2-CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" (CAC NOS. MF9418 AND MF9419; EPID L-2016-LRC-0001) | | SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2-CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" (CAC NOS. MF9418 AND MF9419; EPID L-2016-LRC-0001) |
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| ==Dear Mr. Shea:== | | ==Dear Mr. Shea:== |
| On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16097A169), to address the degradation of neutron-absorbing materials (NAMs) in wet storage systems for reactor fuel at power and non-power reactors. | | |
| The generic letter requested that licensees provide information to allow the NRC staff to verify continued compliance through effective monitoring to identify and mitigate any degradation or deformation of NAMs credited for criticality control in spent fuel pools (SFPs). By letter dated December 19, 20*16 (ADAMS Accession No. ML 163548569), Tennessee Valley Authority (the licensee), responded to GL 2016-01 Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah-1 and 2). In the licensee's response to GL 2016-01, the licensee stated that, for Sequoyah-1 and 2, the licensee credits Boral for criticality control and has an established NAM monitoring program. The NRC staff's review determined that the provided response sufficiently addressed the five areas of information described in Appendix A of GL 2016-01 for Boral. In particular, the described monitoring program for the Boral includes the following key features: | | On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAMs) in wet storage systems for reactor fuel at power and non-power reactors. |
| | The generic letter requested that licensees provide information to allow the NRC staff to verify continued compliance through effective monitoring to identify and mitigate any degradation or deformation of NAMs credited for criticality control in spent fuel pools (SFPs). |
| | By letter dated December 19, 20*16 (ADAMS Accession No. ML163548569), Tennessee Valley Authority (the licensee), responded to GL 2016-01 Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah-1 and 2). In the licensee's response to GL 2016-01, the licensee stated that, for Sequoyah-1 and 2, the licensee credits Boral for criticality control and has an established NAM monitoring program. The NRC staff's review determined that the provided response sufficiently addressed the five areas of information described in Appendix A of GL 2016-01 for Boral. In particular, the described monitoring program for the Boral includes the following key features: |
| * Neutron attenuation testing of coupons. | | * Neutron attenuation testing of coupons. |
| * Established processes to ensure that the licensee will take the appropriate corrective actions if any potentially non-conforming material is discovered. | | * Established processes to ensure that the licensee will take the appropriate corrective actions if any potentially non-conforming material is discovered. |
| * A testing frequency not to exceed 10 years. | | * A testing frequency not to exceed 10 years. |
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| J.Shea | | J.Shea |
| * Acceptance criteria to ensure maintenance of the 5-percent subcriticality margin for the SFP. The NRC staff found that the licensee intends to continue monitoring the condition of its NAMs as described in its response. | | * Acceptance criteria to ensure maintenance of the 5-percent subcriticality margin for the SFP. |
| In the licensee's response to GL 2016-01, the licensee also stated that some deformation has been identified as part of their Boral monitoring program. Further, the licensee stated that a criticality evaluation was performed to determine the effect of blisters on the Boral panels for the flux trap SFP cells installed at Watts Bar Nuclear Plant, Units 1 and 2 (WB-1 and 2). The conclusions from that evaluation were determined to bound the Sequoyah SFP configuration; however, no additional information regarding the evaluation was provided. | | The NRC staff found that the licensee intends to continue monitoring the condition of its NAMs as described in its response. |
| Therefore, the NRC requested additional information from the licensee regarding evaluation of the criticality impact due to blistering at WB-1 and 2. By letter dated May 31, 2018 (ADAMS Accession No. ML 18158A330), the licensee stated that the observed deformation for WB-1 and 2 is bounded by the criticality studies documented in Electric Power Research Institute (EPRI) document 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," May 2018 (ADAMS Accession No. ML 18226A292). | | In the licensee's response to GL 2016-01, the licensee also stated that some deformation has been identified as part of their Boral monitoring program. Further, the licensee stated that a criticality evaluation was performed to determine the effect of blisters on the Boral panels for the flux trap SFP cells installed at Watts Bar Nuclear Plant, Units 1 and 2 (WB-1 and 2). The conclusions from that evaluation were determined to bound the Sequoyah SFP configuration; however, no additional information regarding the evaluation was provided. Therefore, the NRC requested additional information from the licensee regarding evaluation of the criticality impact due to blistering at WB-1 and 2. By letter dated May 31, 2018 (ADAMS Accession No. ML18158A330), the licensee stated that the observed deformation for WB-1 and 2 is bounded by the criticality studies documented in Electric Power Research Institute (EPRI) document 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," May 2018 (ADAMS Accession No. ML18226A292). |
| EPRI Report 3002013119 documents a series of sensitivity studies performed on representative SFP rack configurations to demonstrate that the amount of observed pitting and blistering would not be expected to have a significant reactivity impact. Preliminary conclusions are obtained based on the estimated reactivity impact from EPRI Report 3002013119 for pitting and blistering dimensions that go well beyond that observed by the licensee's monitoring program. The NRC staff notes that the studies documented in EPRI Report 3002013119 are intended to be generic analyses and were not provided as site-specific analyses. | | EPRI Report 3002013119 documents a series of sensitivity studies performed on representative SFP rack configurations to demonstrate that the amount of observed pitting and blistering would not be expected to have a significant reactivity impact. Preliminary conclusions are obtained based on the estimated reactivity impact from EPRI Report 3002013119 for pitting and blistering dimensions that go well beyond that observed by the licensee's monitoring program. |
| Therefore, the results of the analyses, or any part of those analyses, have currently not been shown as directly applicable to WB-1 and 2 or Sequoyah-1 and 2. In addition, the NRC staff did not review whether the EPRI Reports could be used to justify equipment operability, design basis changes, or licensing changes requested pursuant to Title 10 of the Code of Federal Regulations, Section 50.90, "Application for amendment of license, construction permit, or early site permit." However, the NRC staffs review determined that the EPRI report does provide the information required to satisfy the request in GL 2016-01 for Boral at this time. | | The NRC staff notes that the studies documented in EPRI Report 3002013119 are intended to be generic analyses and were not provided as site-specific analyses. Therefore, the results of the analyses, or any part of those analyses, have currently not been shown as directly applicable to WB-1 and 2 or Sequoyah-1 and 2. In addition, the NRC staff did not review whether the EPRI Reports could be used to justify equipment operability, design basis changes, or licensing changes requested pursuant to Title 10 of the Code of Federal Regulations, Section 50.90, "Application for amendment of license, construction permit, or early site permit." |
| J. Shea For Sequoyah-1 and 2, the NRC staff's review determined that the information provided sufficiently addressed the five areas of information described in Appendix A to GL 2016-01. Based on the review of the information provided, the NRC staff concludes no further information is requested regarding GL 2016-01. Docket Nos. 50-327 and 50-328 cc: Listserv Sincerely, Douglas A. Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation J. Shea | | However, the NRC staffs review determined that the EPRI report does provide the information required to satisfy the request in GL 2016-01 for Boral at this time. |
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| | J. Shea For Sequoyah-1 and 2, the NRC staff's review determined that the information provided sufficiently addressed the five areas of information described in Appendix A to GL 2016-01. |
| | Based on the review of the information provided, the NRC staff concludes no further information is requested regarding GL 2016-01. |
| | Sincerely, Douglas A. Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 cc: Listserv |
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| ==SUBJECT:==
| | ML18249A383 *via email OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL2-2/PM NRR/DORL/LAiT NRR/DORL/LSPB/LA NAME SWall AHon PTalukdar JBurkhardt DATE 9/25/18 9/25/18 9/11/18 9/17/18 OFFICE NRR/DMLR/MCCB/BC* NRR/DIRS/IRGB/BC* N RR/DSS/SN PB/BC* NRR/DORL/LSPB/BC NAME SBloom BPham Rlukes DBroaddus DATE 9/25/18 9/25/18 9/19/18 9/26/18}} |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" (CAC NOS. MF9418 AND MF9419; EPID L-2016-LRC-0001)
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| DATED SEPTEMBER 26, 2018 DISTRIBUTION:
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| PUBLIC PM File Copy RidsACRS_MailCTR Resource RidsNrrDirslrgb Resource RidsNrrDmlrMccb Resource RidsNrrDorlLp12-2 Resource RidsNrrDorlLspb Resource RidsNrrDssSnpb Resource RidsNrrLAJBurkhardt Resource RidsNrrLABClayton Resource RidsNrrPMSequoyah Resource RidsRgn2MailCenter Resource BBenney, NRR SKrepel, NRR SWall, NRR ADAMS Accession No.: ML 18249A383 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL2-2/PM N RR/DORL/LAiT NAME SWall AHon PTalukdar DATE 9/25/18 9/25/18 9/11/18 OFFICE NRR/DMLR/MCCB/BC*
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| NRR/DIRS/IRGB/BC* | |
| N RR/DSS/SN PB/BC* NAME SBloom BPham Rlukes DATE 9/25/18 9/25/18 9/19/18 OFFICIAL RECORD COPY *via email NRR/DORL/LSPB/LA JBurkhardt 9/17/18 NRR/DORL/LSPB/BC DBroaddus 9/26/18}} | |
Letter Sequence Other |
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CAC:MF9418, (Open) CAC:MF9419, (Open) EPID:L-2016-LRC-0001, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station (Open) |
|
MONTHYEARRS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017
Response to Request for Additional Information Regarding Generic Letter 2016-01
Project stage: Response to RAI
ML17297A8472017-10-27027 October 2017
Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001)
Project stage: Other
ML17285B1962017-10-27027 October 2017
Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
Project stage: RAI
ML17304A0102017-11-0101 November 2017
Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001)
Project stage: RAI
ML17303B1582017-11-0707 November 2017
FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information
Project stage: Other
ML17307A3302017-11-20020 November 2017
Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools(Cac Nos. MF9920, MF9452, MF9437, MF9919, and MF9432; EPID L-2016-LRC-0001)
Project stage: Other
ML18025A7992018-01-25025 January 2018
Response to Request for Additional Information Regarding Generic Letter 2016-01
Project stage: Response to RAI
NL-18-0085, Response to NRC RAIs Regarding Generic Letter 2016-012018-02-0505 February 2018
Response to NRC RAIs Regarding Generic Letter 2016-01
Project stage: Request
ML18030B2382018-04-13013 April 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
Project stage: Other
L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018
Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
Project stage: Request
PLA-7704, Response to Generic Letter 2016-01, Request for Supplemental Information2018-05-24024 May 2018
Response to Generic Letter 2016-01, Request for Supplemental Information
Project stage: Request
AEP-NRC-2018-01, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-25025 May 2018
Response to Request for Additional Information Regarding Generic Letter 2016-01
Project stage: Response to RAI
L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018
Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
Project stage: Request
ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018
Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information
Project stage: Request
RS-18-067, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-29029 May 2018
Response to Request for Additional Information Regarding Generic Letter 2016-01
Project stage: Response to RAI
RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018
Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
Project stage: Request
CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018
Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station
Project stage: Request
ULNRC-06440, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information2018-05-31031 May 2018
Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information
Project stage: Request
CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-31031 May 2018
Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
Project stage: Supplement
ML18031A9952018-08-27027 August 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9423; EPID L-2016-LRC-0001)
Project stage: Other
ML18030B1782018-08-27027 August 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9441; EPID L-2016-LRC-0001)
Project stage: Other
ML18030B3612018-08-30030 August 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9427; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3832018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9418 and MF9419; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A0802018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9431 and MF9430; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A4072018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC MF9920, MF9452, MF9451, MF9425, MF9406-MF9408; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A0492018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9449 and MF9450; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A0612018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9428 and MF9429; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A0752018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9410 and MF9411; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A0912018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9421 and MF9422; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A1622018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9424; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A1782018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9438; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A1802018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9456 and MF9457; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A2312018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9448; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A2422018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9415 and MF9416; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3342018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9435 and MF9436; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3652018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9437; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3802018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9412 and MF9413; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3862018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9433 and MF9434; EPID L-2016-LRC-0001)
Project stage: Other
ML18249A3922018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC MF9444, MF9445, MF9443, MF9440, MF9409; EPID L-2016-LRC-0001)
Project stage: Other
ML18253A0992018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC No. MF9414; EPID L-2016-LRC-0001)
Project stage: Other
ML18253A1302018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9920 and MF9432; EPID L-2016-LRC-0001)
Project stage: Other
ML18269A3512018-09-26026 September 2018
Closeout of Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
Project stage: Other
2018-04-13
[Table View] |
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Category:Letter
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24282B0412024-10-15015 October 2024
Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2
ML24260A1682024-10-0404 October 2024
Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5
ML24284A1072024-09-26026 September 2024
Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2
05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024
Reactor Trip Due to an Electrical Trouble Turbine Trip
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24267A0402024-09-19019 September 2024
Cycle 27 Core Operating Limits Report Revision 0
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24185A1742024-09-18018 September 2024
Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation
ML24253A0152024-09-0808 September 2024
Emergency Plan Implementing Procedure Revisions
ML24247A2212024-08-29029 August 2024
Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021
ML24247A1802024-08-28028 August 2024
Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea
IR 05000327/20240052024-08-26026 August 2024
Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024
Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),
IR 05000327/20240022024-07-31031 July 2024
Integrated Inspection Report 05000327/2024002 and 05000328/2024002
ML24211A0542024-07-29029 July 2024
Operator License Examination Report
ML24211A0572024-07-29029 July 2024
Submittal of Emergency Plan Implementing Procedure Revision
ML24211A0412024-07-26026 July 2024
Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
ML24191A4652024-07-0909 July 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24177A0282024-06-25025 June 2024
Emergency Plan Implementing Procedure Revisions
ML24176A0222024-06-24024 June 2024
Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24145A0852024-05-30030 May 2024
1B-B Diesel Generator Failure - Final Significance Determination Letter
ML24145A1052024-05-29029 May 2024
301 Exam Approval Letter
ML24134A1762024-05-13013 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24128A0352024-05-0707 May 2024
Providing Supplemental Information to Apparent Violation
ML24120A0582024-04-26026 April 2024
10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2
ML24116A2612024-04-25025 April 2024
Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N
ML24114A0482024-04-23023 April 2024
Annual Radioactive Effluent Release Report for 2023 Monitoring Period
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
ML24144A2322024-04-20020 April 2024
Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9
ML24144A2362024-04-20020 April 2024
Discharge Monitoring Report (Dmr), March 2024
ML24102A1212024-04-18018 April 2024
Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections
ML24089A0882024-04-18018 April 2024
– Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
IR 05000327/20240012024-04-17017 April 2024
Integrated Inspection Report 05000327/2024001 and 05000328/2024001
CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024
Hydrologic Engineering Center River Analysis System Project Milestone Status Update
ML24109A0272024-04-16016 April 2024
Cycle 27 Core Operating Limits Report Revision 0
CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024
Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)
ML24106A0502024-04-12012 April 2024
Discharge Monitoring Report (Dmr), February 2024
ML24100A0162024-04-11011 April 2024
Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant)
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
ML24088A0332024-03-28028 March 2024
Request for Regulatory Conference (Tennessee Valley Authority)
CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024
Annual Insurance Status Report
2024-09-08
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C 20555-0001 September 26, 2018 0MB Control No. 3150-0231 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority Sequoyah Nuclear Plant 1101 Market Street, LP 4A Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2-CLOSEOUT OF GENERIC LETTER 2016-01, "MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS" (CAC NOS. MF9418 AND MF9419; EPID L-2016-LRC-0001)
Dear Mr. Shea:
On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, "Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials (NAMs) in wet storage systems for reactor fuel at power and non-power reactors.
The generic letter requested that licensees provide information to allow the NRC staff to verify continued compliance through effective monitoring to identify and mitigate any degradation or deformation of NAMs credited for criticality control in spent fuel pools (SFPs).
By letter dated December 19, 20*16 (ADAMS Accession No. ML163548569), Tennessee Valley Authority (the licensee), responded to GL 2016-01 Sequoyah Nuclear Plant, Units 1 and 2 (Sequoyah-1 and 2). In the licensee's response to GL 2016-01, the licensee stated that, for Sequoyah-1 and 2, the licensee credits Boral for criticality control and has an established NAM monitoring program. The NRC staff's review determined that the provided response sufficiently addressed the five areas of information described in Appendix A of GL 2016-01 for Boral. In particular, the described monitoring program for the Boral includes the following key features:
- Neutron attenuation testing of coupons.
- Established processes to ensure that the licensee will take the appropriate corrective actions if any potentially non-conforming material is discovered.
- A testing frequency not to exceed 10 years.
J.Shea
- Acceptance criteria to ensure maintenance of the 5-percent subcriticality margin for the SFP.
The NRC staff found that the licensee intends to continue monitoring the condition of its NAMs as described in its response.
In the licensee's response to GL 2016-01, the licensee also stated that some deformation has been identified as part of their Boral monitoring program. Further, the licensee stated that a criticality evaluation was performed to determine the effect of blisters on the Boral panels for the flux trap SFP cells installed at Watts Bar Nuclear Plant, Units 1 and 2 (WB-1 and 2). The conclusions from that evaluation were determined to bound the Sequoyah SFP configuration; however, no additional information regarding the evaluation was provided. Therefore, the NRC requested additional information from the licensee regarding evaluation of the criticality impact due to blistering at WB-1 and 2. By letter dated May 31, 2018 (ADAMS Accession No. ML18158A330), the licensee stated that the observed deformation for WB-1 and 2 is bounded by the criticality studies documented in Electric Power Research Institute (EPRI) document 3002013119, "Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity," May 2018 (ADAMS Accession No. ML18226A292).
EPRI Report 3002013119 documents a series of sensitivity studies performed on representative SFP rack configurations to demonstrate that the amount of observed pitting and blistering would not be expected to have a significant reactivity impact. Preliminary conclusions are obtained based on the estimated reactivity impact from EPRI Report 3002013119 for pitting and blistering dimensions that go well beyond that observed by the licensee's monitoring program.
The NRC staff notes that the studies documented in EPRI Report 3002013119 are intended to be generic analyses and were not provided as site-specific analyses. Therefore, the results of the analyses, or any part of those analyses, have currently not been shown as directly applicable to WB-1 and 2 or Sequoyah-1 and 2. In addition, the NRC staff did not review whether the EPRI Reports could be used to justify equipment operability, design basis changes, or licensing changes requested pursuant to Title 10 of the Code of Federal Regulations, Section 50.90, "Application for amendment of license, construction permit, or early site permit."
However, the NRC staffs review determined that the EPRI report does provide the information required to satisfy the request in GL 2016-01 for Boral at this time.
J. Shea For Sequoyah-1 and 2, the NRC staff's review determined that the information provided sufficiently addressed the five areas of information described in Appendix A to GL 2016-01.
Based on the review of the information provided, the NRC staff concludes no further information is requested regarding GL 2016-01.
Sincerely, Douglas A. Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 cc: Listserv
ML18249A383 *via email OFFICE NRR/DORL/LSPB/PM NRR/DORL/LPL2-2/PM NRR/DORL/LAiT NRR/DORL/LSPB/LA NAME SWall AHon PTalukdar JBurkhardt DATE 9/25/18 9/25/18 9/11/18 9/17/18 OFFICE NRR/DMLR/MCCB/BC* NRR/DIRS/IRGB/BC* N RR/DSS/SN PB/BC* NRR/DORL/LSPB/BC NAME SBloom BPham Rlukes DBroaddus DATE 9/25/18 9/25/18 9/19/18 9/26/18
