|
|
| (9 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML13282A330 | | | number = ML13282A330 |
| | issue date = 10/18/2013 | | | issue date = 10/18/2013 |
| | title = Sequoyah RAI Set 16 | | | title = RAI Set 16 |
| | author name = Plasse R A | | | author name = Plasse R |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = Shea J W | | | addressee name = Shea J |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000327, 05000328 | | | docket = 05000327, 05000328 |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384 October 18, 2013 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)-SET 16. Dear Mr. Shea: By letter dated January 7, 2013, Tennessee Valley Authority submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information (RAis), outlined in the Enclosure were discussed with Henry Lee, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard.Piasse@nrc.gov. Docket Nos. 50-327 and 50-328 Enclosure: Requests for Additional Information cc: Listserv Sincerely, Richard A Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation October 18, 2013 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)-SET 16. Dear Mr. Shea: By letter dated January 7, 2013, Tennessee Valley Authority submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information (RAis), outlined in the Enclosure were discussed with Henry Lee, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard. Plasse@nrc.gov. Docket Nos. 50-327 and 50-328 Enclosure: Requests for Additional Information cc: Listserv DISTRIBUTION: See next page ADAMS Accession No.: ML 13282A330 Sincerely, IRA/ Richard A. Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation OFFICE LA:RPB1 :DLR PM:RPB1 :DLR BC:RPB1 :DLR PM: RPB1 :DLR NAME Y. Edmonds E Say_oc Y Diaz-Sanabria R Plasse DATE 10/10/2013 10/10/2013 10/10/2013 10/18/2013 OFFICIAL RECORD COPY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION RAI B.1.23-2c (Follow up) Background: In its September 30, 2013, response to RAI 8.1.23-2a, the applicant described justification for why an inspection program is not necessary to manage the wear of the control rod drive mechanism (CRDM) nozzles. As part of the response, the applicant addressed its analysis on the maximum wear depth of CRDM nozzles (i.e., 0.050 inches). In its response, the applicant stated that, when contact occurs between the CRDM nozzle and the thermal sleeve centering pads of the nozzle, only a relatively small wear volume of the three centering pads is distributed over the relatively large areas of the CRDM nozzle inside surfaces. The applicant acknowledged that the specific hardness values of the sleeves, centering pads and CRDM nozzles are not known, and further stated that similar grades of stainless steel and lnconel materials have similar hardness values (i.e., approximately 90 on Rockwell 8 scale). As previously discussed in RAI 8.1.23-2a, the applicant's analysis on the maximum wear depth involves uncertainties in local vibratory motions, residual stresses, and hardness levels of the CRDM nozzles, thermal sleeves, and centering pads. Without an inspection of the wear indications, localized severe wear conditions cannot be excluded. Therefore, the staff finds that an inspection program is necessary to confirm the adequacy of the applicant's analysis. In addition, wear of the CRDM nozzles may interfere with the volumetric examination of the CRDM nozzles which is specified in the applicant's Nickel Alloy Inspection Program. The staff needs to clarify how the applicant's program would resolve the situation that wear of the CRDM nozzles interferes with the volumetric examination of the CRDM nozzles. Request: 1. Identify an inspection program to confirm the adequacy of the applicant's analysis on the maximum wear depth of the CRDM nozzles. As part of the response, describe how applicant's inspection program confirms the adequacy of the applicant's analysis. 2. Clarify whether the applicant's Nickel Alloy Inspection Program accounts for a potential loss of ultrasonic testing signal due to the surface irregularities of the wear areas. 3. In addition, describe how the applicant's Nickel Alloy Inspection Program would resolve the interference caused by wear of the CRDM nozzles with volumetric examination of the CRDM nozzles. As part of the response, clarify how the applicant's program will confirm the absence of cracking in the wear areas that could not be adequately examined by the volumetric examination. ENCLOSURE | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 18, 2013 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384 |
| -2-RAI 4.3.1-Sa (Follow up) Background: In its September 30, 2013, response to RAI 4.3.1-8, the applicant stated that the pressurizer surge nozzle-to-safe end welds for the units were originally included in the cumulative usage factor (CUF) analyses for the pressurizer surge nozzles; however, the applicant stated that the design of the welds has been modified to include a full structural weld overlay (SWOL). The applicant also stated that, as identified in LRA Section 4.3.1.3, the current design basis of the pressurizer surge nozzles and their nozzle-to-safe end weld relies on a flaw evaluation that is used to establish the inservice inspection (lSI) frequency for the components. Issue: The response to RAI 4.3.1-8 may be inconsistent with LRA Section 4.3.1.3 Specifically, LRA Section 4.3.1.3, identifies that the flaw evaluation for the nickel alloy pressurizer surge to-safe end weld was performed to assess postulated cracking that could be initiated and grown by a stress corrosion cracking (SCC) mechanism, and not by a metal fatigue mechanism. As a result, the response to RAI 4.3.1-8 will only provide a valid basis for concluding that the welds would not need to be evaluated for environmentally-assisted fatigue if it is demonstrated that the flaw evaluation of the pressurizer surge nozzle-to-safe end welds also included an evaluation of crack initiation and growth that is induced by a thermally-induced metal fatigue mechanism. Thus, it is not evident whether flaw growth by a thermally-induced metal fatigue mechanism was included as part of the basis for establishing the inspection frequency that is used to schedule the inspections of the pressurizer spray nozzle-to-safe end weld under the applicant's lSI Program or Nickel Alloy Inspection Program. Request: Identify whether the flaw evaluation that was performed on the SWOL-modified pressurizer surge nozzle designs included an assessment of cracking that would be induced and grown by a thermally-induced metal fatigue mechanism (i.e., in addition to an assessment of cracking that is initiated and grown by SCC). 1. If it is determined that the flaw evaluation did include an assessment of both sec and fatigue, identify the inspection frequency that is currently applicable to the lSI inspections under the applicant's lSI Program or Nickel Alloy Inspection Program. In addition, identify which of the cracking mechanisms was determined to be limiting for establishment of the inspection frequency. 2. If it is determined that the flaw growth analysis does not include an assessment of cracking that could be initiated and grown by fatigue, identify design basis CUF values that are applicable to the pressurizer surge nozzle-to-safe end weld locations for Units 1 and 2 and justify why the CUF values for these Nickel alloy nozzle-to-safe end weld would not need to be adjusted for environmentally-assisted fatigue, as performed in accordance with the recommended guidance for performing environmentally-assisted fatigue analyses for Nickel alloy components in SRP-LR Section 4.3. Justify your responses to this request.
| | |
| Letter to J. Shea from R. Plasse dated October 18, 2013 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE EQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)-SET 16. DISTRIBUTION: HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsNrrDirRerb Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource beth.mizuno@nrc.gov brian. harris@nrc.gov john. pelchat@nrc. gov gena. woodruff@nrc.gov siva.lingam@nrc.gov wesley.deschaine@nrc.gov galen.smith@nrc.gov scott. shaeffer@n rc. g ov jeffrey. hamman@nrc.gov craig.kontz@nrc.gov caudle.julian@nrc.gov generette.lloyd@epa.gov gmadkins@tva.gov clwilson@tva.gov hleeO@tva.gov dllundy@tva.gov
| | ==SUBJECT:== |
| }} | | REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 16. |
| | |
| | ==Dear Mr. Shea:== |
| | |
| | By letter dated January 7, 2013, Tennessee Valley Authority submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. |
| | These requests for additional information (RAis), outlined in the Enclosure were discussed with Henry Lee, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard.Piasse@nrc.gov. |
| | Sincerely, |
| | ,f/~ |
| | Richard A Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 |
| | |
| | ==Enclosure:== |
| | |
| | Requests for Additional Information cc: Listserv |
| | |
| | ML13282A330 OFFICE LA:RPB1 :DLR PM:RPB1 :DLR BC:RPB1 :DLR PM: RPB1 :DLR NAME Y. Edmonds E Say_oc Y Diaz-Sanabria R Plasse DATE 10/10/2013 10/10/2013 10/10/2013 10/18/2013 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION RAI B.1.23-2c (Follow up) |
| | |
| | ==Background:== |
| | |
| | In its September 30, 2013, response to RAI 8.1.23-2a, the applicant described justification for why an inspection program is not necessary to manage the wear of the control rod drive mechanism (CRDM) nozzles. As part of the response, the applicant addressed its analysis on the maximum wear depth of CRDM nozzles (i.e., 0.050 inches). |
| | In its response, the applicant stated that, when contact occurs between the CRDM nozzle and the thermal sleeve centering pads of the nozzle, only a relatively small wear volume of the three centering pads is distributed over the relatively large areas of the CRDM nozzle inside surfaces. |
| | The applicant acknowledged that the specific hardness values of the sleeves, centering pads and CRDM nozzles are not known, and further stated that similar grades of stainless steel and lnconel materials have similar hardness values (i.e., approximately 90 on Rockwell 8 scale). |
| | As previously discussed in RAI 8.1.23-2a, the applicant's analysis on the maximum wear depth involves uncertainties in local vibratory motions, residual stresses, and hardness levels of the CRDM nozzles, thermal sleeves, and centering pads. Without an inspection of the wear indications, localized severe wear conditions cannot be excluded. Therefore, the staff finds that an inspection program is necessary to confirm the adequacy of the applicant's analysis. |
| | In addition, wear of the CRDM nozzles may interfere with the volumetric examination of the CRDM nozzles which is specified in the applicant's Nickel Alloy Inspection Program. The staff needs to clarify how the applicant's program would resolve the situation that wear of the CRDM nozzles interferes with the volumetric examination of the CRDM nozzles. |
| | Request: |
| | : 1. Identify an inspection program to confirm the adequacy of the applicant's analysis on the maximum wear depth of the CRDM nozzles. As part of the response, describe how applicant's inspection program confirms the adequacy of the applicant's analysis. |
| | : 2. Clarify whether the applicant's Nickel Alloy Inspection Program accounts for a potential loss of ultrasonic testing signal due to the surface irregularities of the wear areas. |
| | : 3. In addition, describe how the applicant's Nickel Alloy Inspection Program would resolve the interference caused by wear of the CRDM nozzles with volumetric examination of the CRDM nozzles. As part of the response, clarify how the applicant's program will confirm the absence of cracking in the wear areas that could not be adequately examined by the volumetric examination. |
| | ENCLOSURE |
| | |
| | RAI 4.3.1-Sa (Follow up) |
| | |
| | ==Background:== |
| | |
| | In its September 30, 2013, response to RAI 4.3.1-8, the applicant stated that the pressurizer surge nozzle-to-safe end welds for the units were originally included in the cumulative usage factor (CUF) analyses for the pressurizer surge nozzles; however, the applicant stated that the design of the welds has been modified to include a full structural weld overlay (SWOL). The applicant also stated that, as identified in LRA Section 4.3.1.3, the current design basis of the pressurizer surge nozzles and their nozzle-to-safe end weld relies on a flaw evaluation that is used to establish the inservice inspection (lSI) frequency for the components. |
| | Issue: |
| | The response to RAI 4.3.1-8 may be inconsistent with LRA Section 4.3.1.3 Specifically, LRA Section 4.3.1.3, identifies that the flaw evaluation for the nickel alloy pressurizer surge nozzle-to-safe end weld was performed to assess postulated cracking that could be initiated and grown by a stress corrosion cracking (SCC) mechanism, and not by a metal fatigue mechanism. As a result, the response to RAI 4.3.1-8 will only provide a valid basis for concluding that the welds would not need to be evaluated for environmentally-assisted fatigue if it is demonstrated that the flaw evaluation of the pressurizer surge nozzle-to-safe end welds also included an evaluation of crack initiation and growth that is induced by a thermally-induced metal fatigue mechanism. |
| | Thus, it is not evident whether flaw growth by a thermally-induced metal fatigue mechanism was included as part of the basis for establishing the inspection frequency that is used to schedule the inspections of the pressurizer spray nozzle-to-safe end weld under the applicant's lSI Program or Nickel Alloy Inspection Program. |
| | Request: |
| | Identify whether the flaw evaluation that was performed on the SWOL-modified pressurizer surge nozzle designs included an assessment of cracking that would be induced and grown by a thermally-induced metal fatigue mechanism (i.e., in addition to an assessment of cracking that is initiated and grown by SCC). |
| | : 1. If it is determined that the flaw evaluation did include an assessment of both sec and fatigue, identify the inspection frequency that is currently applicable to the lSI inspections under the applicant's lSI Program or Nickel Alloy Inspection Program. In addition, identify which of the cracking mechanisms was determined to be limiting for establishment of the inspection frequency. |
| | : 2. If it is determined that the flaw growth analysis does not include an assessment of cracking that could be initiated and grown by fatigue, identify design basis CUF values that are applicable to the pressurizer surge nozzle-to-safe end weld locations for Units 1 and 2 and justify why the CUF values for these Nickel alloy nozzle-to-safe end weld would not need to be adjusted for environmentally-assisted fatigue, as performed in accordance with the recommended guidance for performing environmentally-assisted fatigue analyses for Nickel alloy components in SRP-LR Section 4.3. Justify your responses to this request. |
| | |
| | Letter to J. Shea from R. Plasse dated October 18, 2013 |
| | |
| | ==SUBJECT:== |
| | REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE EQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 16. |
| | DISTRIBUTION: |
| | HARD COPY: |
| | DLR RF E-MAIL: |
| | PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsNrrDirRerb Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource beth.mizuno@nrc.gov brian. harris@nrc.gov john. pelchat@nrc. gov gena. woodruff@nrc.gov siva.lingam@nrc.gov wesley.deschaine@nrc.gov galen.smith@nrc.gov scott. shaeffer@n rc. g ov jeffrey. hamman@nrc.gov craig.kontz@nrc.gov caudle.julian@nrc.gov generette.lloyd@epa.gov gmadkins@tva.gov clwilson@tva.gov hleeO@tva.gov dllundy@tva.gov}} |
Letter Sequence RAI |
|---|
|
Results
Other: CNL-15-095, Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule for License Renewal, CNL-15-164, Second Annual Update, License Renewal Application, CNL-15-178, License Renewal Application - Clarifications (TAC Nos. MF0481 and MF0482), ML13032A251, ML13057A873, ML13067A201, ML13141A320, ML15236A067
|
MONTHYEARML13024A0042013-01-0707 January 2013
Transmittal of License Renewal Application
Project stage: Request
ML13032A2512013-01-10010 January 2013
Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment
Project stage: Other
ML13057A8732013-03-0808 March 2013
Plan for the Scoping and Screening Regulatory Audit Regarding the Sequoyah Nuclear Plant, Unit 1 and 2, LRA Review
Project stage: Other
ML13067A2012013-03-11011 March 2013
Plan for the Aging Management Program Regulatory Audit Regarding the Sequoyah Nuclear Plant, Units 1 and 2 License Renewal Application Review (TAC Nos. MF0481 and MF0482)
Project stage: Other
ML13109A5152013-04-26026 April 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482)
Project stage: RAI
ML13122A3402013-05-0808 May 2013
RAI for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482)
Project stage: RAI
ML13119A0972013-05-21021 May 2013
Summary of Telephone Conference Call Held on April 22, 2013 Between the U.S. Nuclear Regulatory Commission and Tva,Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, License Renewal Application
Project stage: RAI
ML13142A3322013-05-21021 May 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482)
Project stage: RAI
ML13128A5192013-05-31031 May 2013
Request for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application
Project stage: RAI
ML13134A2012013-06-0505 June 2013
RAI for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, LRA
Project stage: RAI
ML13163A4422013-06-0707 June 2013
Response to NRC Request for Additional Information Regarding the Scoping and Screening Methodology Review of the License Renewal Application, Set 3
Project stage: Response to RAI
ML13144A7122013-06-11011 June 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (Tac Nos. MF0481 and MF0482)- Set 6
Project stage: RAI
ML13134A3712013-06-13013 June 2013
5/9/2013 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, License Ren
Project stage: RAI
ML13141A3202013-06-13013 June 2013
Letter Aging Management Programs Audit Report Regarding the Sequoyah Nuclear Plant, Units 1 and 2
Project stage: Other
ML13150A4122013-06-24024 June 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) - Set 8
Project stage: RAI
ML13178A2832013-06-25025 June 2013
Response to NRC Request for Additional Information Regarding the Reactor Vessel Internals Review of the License Renewal Application, Set 1
Project stage: Response to RAI
ML13158A0162013-06-25025 June 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) Set 9
Project stage: RAI
ML13190A2762013-07-0101 July 2013
Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Set 4
Project stage: Response to RAI
ML13192A3302013-07-0303 July 2013
Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 5 (TAC Nos. MF0481 and MF0482)
Project stage: Response to RAI
ML13204A3992013-07-11011 July 2013
Response to NRC Request for Additional Information Re Reactor Vessel Internals Review of the License Renewal Application, Set 6
Project stage: Response to RAI
ML13213A0262013-07-25025 July 2013
Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 4/Buried Piping, Set 8, and Set 9 (TAC MF0481 and MF0482)
Project stage: Response to RAI
ML13213A0272013-07-29029 July 2013
Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Set 7 (TAC Nos. MF0481 and MF0482)
Project stage: Response to RAI
ML13213A0142013-07-30030 July 2013
Revised Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Sets 1 and 3 (TAC MF0481 and MF0482)
Project stage: Response to RAI
ML13171A0362013-08-0101 August 2013
Summary of Telephone Conference Call Held on June 13, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA
Project stage: RAI
ML13204A2572013-08-0202 August 2013
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) - Set 10
Project stage: RAI
ML13225A3872013-08-0909 August 2013
Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 1, 6, 7, and Revised Responses for 1.4-2, 1.4-3 and 1.4-4 (TAC Nos. MF0481 and MF0482)
Project stage: Response to RAI
ML13224A1262013-08-22022 August 2013
RAI for Review of Sequoyah, Units 1 & 2 License Renewal Application - Set 11
Project stage: RAI
ML13238A2442013-08-30030 August 2013
RAI Set 12
Project stage: RAI
ML13252A0362013-09-0303 September 2013
Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Set 10 (30-day), B.1.9-1, B.1.4-4 Revised RAI Responses and Revision to LRA Page 2.4-44 (TAC Nos. MF0481 and MF0482)
Project stage: Response to RAI
ML13226A3712013-09-10010 September 2013
Summary of Telephone Conference Call Held on August 1, 2013, Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1
Project stage: RAI
ML13267A1592013-09-20020 September 2013
Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Set 11 (30-day), and Revised RAI Responses for B.1.14-1a, 2.5.
Project stage: Response to RAI
ML13247A4272013-09-23023 September 2013
Summary of Telephone Conference Call Held on August 19, 2013, Between the NRC and Tennessee Valley Authority, Concerning RAI Pertaining to the Sequoyah Nuclear Plant, Units 1 and 2, LRA
Project stage: RAI
ML13263A3382013-09-26026 September 2013
RAI Set 14
Project stage: RAI
ML13268A4922013-09-27027 September 2013
RAI Set 15
Project stage: RAI
ML13276A0182013-09-30030 September 2013
Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Sets 10 (B.1.23-2a), 11 (4.1-8a), and 12 (30-day)
Project stage: Response to RAI
CNL-13-103, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Sets 8 (B.1.33-1), 10 (3.0.3-1 Request 1), 12 (B.1.23-2b), 13 (30-day), 14 (B.0.4-1a)2013-10-17017 October 2013
Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Sets 8 (B.1.33-1), 10 (3.0.3-1 Request 1), 12 (B.1.23-2b), 13 (30-day), 14 (B.0.4-1a)
Project stage: Response to RAI
ML13282A3302013-10-18018 October 2013
RAI Set 16
Project stage: RAI
CNL-13-104, Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Sets 11 (B.1.40-4a, B.1.25.1a), 13 (B.1.41-4a),14 (3.5.1-57, 3.5.1-87)2013-10-21021 October 2013
Response to NRC Request for Additional Information Regarding the Review of License Renewal Application, Sets 11 (B.1.40-4a, B.1.25.1a), 13 (B.1.41-4a),14 (3.5.1-57, 3.5.1-87)
Project stage: Response to RAI
CNL-13-105, Response to NRC Request for Additional Information Regarding Review of the License Renewal Application, Sets 10 (3.0.3-1, Requests 3, 4, 6), 12 (B.1.6-1b, B.1.6-2b), 16 (4.3.1-8a)2013-11-0404 November 2013
Response to NRC Request for Additional Information Regarding Review of the License Renewal Application, Sets 10 (3.0.3-1, Requests 3, 4, 6), 12 (B.1.6-1b, B.1.6-2b), 16 (4.3.1-8a)
Project stage: Response to RAI
CNL-13-106, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 13 (B.1.34-5a), 15 (4.2-1a), 16 (B.1.23-2c), 17 (B.1.23-2d), LRA Sections A.1.34 and B2013-11-15015 November 2013
Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units I and 2, License Renewal Application, Sets 13 (B.1.34-5a), 15 (4.2-1a), 16 (B.1.23-2c), 17 (B.1.23-2d), LRA Sections A.1.34 and B.1
Project stage: Response to RAI
ML13323A0972013-12-0606 December 2013
RAI Set 18
Project stage: RAI
CNL-13-130, Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, B.1.41-4b, 3.0.3-1 (Requests La, 3a, 4a, 6a), B.1.23-2e, 3.4.2.1.1-2a, Tables (3.4.1, 3.4.2-3-5, 3.3.1..2013-12-16016 December 2013
Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, B.1.41-4b, 3.0.3-1 (Requests La, 3a, 4a, 6a), B.1.23-2e, 3.4.2.1.1-2a, Tables (3.4.1, 3.4.2-3-5, 3.3.1..
Project stage: Response to RAI
ML13353A5382013-12-23023 December 2013
RAI Set 19
Project stage: RAI
ML13338A3332014-01-0808 January 2014
Summary of Telephone Conference Call Held on August 22, 2013, Between the U.S. Nuclear Regulatory Commission and Tennessee Valley Authority, Concerning Requests for Additional Information Pertaining to the Sequoyah Nuclear Plant, Units 1 an
Project stage: RAI
CNL-14-021, Response to Request for Clarification to NRC Request for Additional Information Re Review of License Renewal Application, LRA B.1.31, B.1.25.1b, B.1.34-8a, B.1.34-9A, LRA Annual Update (TAC MF0481 & MF0482)2014-03-0303 March 2014
Response to Request for Clarification to NRC Request for Additional Information Re Review of License Renewal Application, LRA B.1.31, B.1.25.1b, B.1.34-8a, B.1.34-9A, LRA Annual Update (TAC MF0481 & MF0482)
Project stage: Supplement
ML14059A3472014-03-0404 March 2014
Schedule Revision for the Review of the Sequoyah Nuclear Plant License Renewal Application (TAC Nos. MF0481 and MF0482)
Project stage: Approval
ML14063A5422014-03-0404 March 2014
TVA Response to Request for Clarification to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, LRA B.1.31, B.1.25.1 B, B.1.34-Sa, B.1.34-9a, LRA Annual ...
Project stage: Supplement
ML14064A4732014-03-12012 March 2014
Request for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, LRA - Set 20
Project stage: RAI
ML14094A2942014-04-11011 April 2014
Project Manager Change for the Safety Review of the Sequoyah Nuclear Plant, Units 1 & 2, License Renewal Application (TAC Nos. MF0481 & MF0482)
Project stage: Approval
CNL-14-052, TVA Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application: RAIs B.1.13-4 and 3.0.3-1-3c, Commitment 9.G, and 2013 LRA Annual Update (TAC Nos. MF042014-04-22022 April 2014
TVA Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application: RAIs B.1.13-4 and 3.0.3-1-3c, Commitment 9.G, and 2013 LRA Annual Update (TAC Nos. MF0481
Project stage: Response to RAI
2013-07-01
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024
December 2024 Requalification Inspection Notification Letter
IR 05000327/20250102024-10-29029 October 2024
Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010
ML24298A1172024-10-24024 October 2024
Cycle 26, 180-Day Steam Generator Tube Inspection Report
CNL-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
05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024
Reactor Trip Due to a Turbine Trip
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
ML24211A0572024-07-29029 July 2024
Submittal of Emergency Plan Implementing Procedure Revision
ML24211A0542024-07-29029 July 2024
Operator License Examination Report
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
ML24144A2362024-04-20020 April 2024
Discharge Monitoring Report (Dmr), March 2024
ML24144A2322024-04-20020 April 2024
Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9
ML24089A0882024-04-18018 April 2024
– Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
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
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
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
IR 05000327/20240012024-04-17017 April 2024
Integrated Inspection Report 05000327/2024001 and 05000328/2024001
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
2024-09-08
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24309A0552024-11-0101 November 2024
NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5
ML24152A1542024-05-31031 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
ML23307A0832023-11-0808 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
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 TVAs 12/19/2022 Response of the Staffs 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
ML22151A0092022-05-26026 May 2022
NRR E-mail Capture - 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 Plants LAR to Adopt TSTF-505
ML22144A1002022-05-12012 May 2022
NRR E-mail Capture - Request for Additional Information Related to TVAs 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 - 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
NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04)
ML18283A6232018-09-25025 September 2018
04 RP Inspection Document Request
ML18233A1942018-08-21021 August 2018
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)
ML18138A1102018-05-17017 May 2018
Enclosurequest for Additional Information (Letter to E. 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. MF9054 - MF9060)
ML17112A0402017-04-20020 April 2017
NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING
ML17004A0612017-01-0404 January 2017
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
ML15175A2912015-06-24024 June 2015
E-mail Re. Request for Additional Information RR RP-07
ML15159B1642015-06-22022 June 2015
Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482)
ML15050A0962015-02-19019 February 2015
E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec
2024-05-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 18, 2013 Mr. Joe W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority P.O. Box 2000 Soddy-Daisy, TN 37384
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 16.
Dear Mr. Shea:
By letter dated January 7, 2013, Tennessee Valley Authority submitted an application pursuant to Title 10 of the Code of Federal Regulations (CFR) Part 54, to renew the operating license DPR-77 and DPR-79 for Sequoyah Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information (RAis), outlined in the Enclosure were discussed with Henry Lee, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at Richard.Piasse@nrc.gov.
Sincerely,
,f/~
Richard A Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Requests for Additional Information cc: Listserv
ML13282A330 OFFICE LA:RPB1 :DLR PM:RPB1 :DLR BC:RPB1 :DLR PM: RPB1 :DLR NAME Y. Edmonds E Say_oc Y Diaz-Sanabria R Plasse DATE 10/10/2013 10/10/2013 10/10/2013 10/18/2013 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION RAI B.1.23-2c (Follow up)
Background:
In its September 30, 2013, response to RAI 8.1.23-2a, the applicant described justification for why an inspection program is not necessary to manage the wear of the control rod drive mechanism (CRDM) nozzles. As part of the response, the applicant addressed its analysis on the maximum wear depth of CRDM nozzles (i.e., 0.050 inches).
In its response, the applicant stated that, when contact occurs between the CRDM nozzle and the thermal sleeve centering pads of the nozzle, only a relatively small wear volume of the three centering pads is distributed over the relatively large areas of the CRDM nozzle inside surfaces.
The applicant acknowledged that the specific hardness values of the sleeves, centering pads and CRDM nozzles are not known, and further stated that similar grades of stainless steel and lnconel materials have similar hardness values (i.e., approximately 90 on Rockwell 8 scale).
As previously discussed in RAI 8.1.23-2a, the applicant's analysis on the maximum wear depth involves uncertainties in local vibratory motions, residual stresses, and hardness levels of the CRDM nozzles, thermal sleeves, and centering pads. Without an inspection of the wear indications, localized severe wear conditions cannot be excluded. Therefore, the staff finds that an inspection program is necessary to confirm the adequacy of the applicant's analysis.
In addition, wear of the CRDM nozzles may interfere with the volumetric examination of the CRDM nozzles which is specified in the applicant's Nickel Alloy Inspection Program. The staff needs to clarify how the applicant's program would resolve the situation that wear of the CRDM nozzles interferes with the volumetric examination of the CRDM nozzles.
Request:
- 1. Identify an inspection program to confirm the adequacy of the applicant's analysis on the maximum wear depth of the CRDM nozzles. As part of the response, describe how applicant's inspection program confirms the adequacy of the applicant's analysis.
- 2. Clarify whether the applicant's Nickel Alloy Inspection Program accounts for a potential loss of ultrasonic testing signal due to the surface irregularities of the wear areas.
- 3. In addition, describe how the applicant's Nickel Alloy Inspection Program would resolve the interference caused by wear of the CRDM nozzles with volumetric examination of the CRDM nozzles. As part of the response, clarify how the applicant's program will confirm the absence of cracking in the wear areas that could not be adequately examined by the volumetric examination.
ENCLOSURE
RAI 4.3.1-Sa (Follow up)
Background:
In its September 30, 2013, response to RAI 4.3.1-8, the applicant stated that the pressurizer surge nozzle-to-safe end welds for the units were originally included in the cumulative usage factor (CUF) analyses for the pressurizer surge nozzles; however, the applicant stated that the design of the welds has been modified to include a full structural weld overlay (SWOL). The applicant also stated that, as identified in LRA Section 4.3.1.3, the current design basis of the pressurizer surge nozzles and their nozzle-to-safe end weld relies on a flaw evaluation that is used to establish the inservice inspection (lSI) frequency for the components.
Issue:
The response to RAI 4.3.1-8 may be inconsistent with LRA Section 4.3.1.3 Specifically, LRA Section 4.3.1.3, identifies that the flaw evaluation for the nickel alloy pressurizer surge nozzle-to-safe end weld was performed to assess postulated cracking that could be initiated and grown by a stress corrosion cracking (SCC) mechanism, and not by a metal fatigue mechanism. As a result, the response to RAI 4.3.1-8 will only provide a valid basis for concluding that the welds would not need to be evaluated for environmentally-assisted fatigue if it is demonstrated that the flaw evaluation of the pressurizer surge nozzle-to-safe end welds also included an evaluation of crack initiation and growth that is induced by a thermally-induced metal fatigue mechanism.
Thus, it is not evident whether flaw growth by a thermally-induced metal fatigue mechanism was included as part of the basis for establishing the inspection frequency that is used to schedule the inspections of the pressurizer spray nozzle-to-safe end weld under the applicant's lSI Program or Nickel Alloy Inspection Program.
Request:
Identify whether the flaw evaluation that was performed on the SWOL-modified pressurizer surge nozzle designs included an assessment of cracking that would be induced and grown by a thermally-induced metal fatigue mechanism (i.e., in addition to an assessment of cracking that is initiated and grown by SCC).
- 1. If it is determined that the flaw evaluation did include an assessment of both sec and fatigue, identify the inspection frequency that is currently applicable to the lSI inspections under the applicant's lSI Program or Nickel Alloy Inspection Program. In addition, identify which of the cracking mechanisms was determined to be limiting for establishment of the inspection frequency.
- 2. If it is determined that the flaw growth analysis does not include an assessment of cracking that could be initiated and grown by fatigue, identify design basis CUF values that are applicable to the pressurizer surge nozzle-to-safe end weld locations for Units 1 and 2 and justify why the CUF values for these Nickel alloy nozzle-to-safe end weld would not need to be adjusted for environmentally-assisted fatigue, as performed in accordance with the recommended guidance for performing environmentally-assisted fatigue analyses for Nickel alloy components in SRP-LR Section 4.3. Justify your responses to this request.
Letter to J. Shea from R. Plasse dated October 18, 2013
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE EQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MF0481 AND MF0482)- SET 16.
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDir Resource RidsNrrDirRpb1 Resource RidsNrrDirRpb2 Resource RidsNrrDirRerb Resource RidsNrrDirRarb Resource RidsNrrDirRasb Resource beth.mizuno@nrc.gov brian. harris@nrc.gov john. pelchat@nrc. gov gena. woodruff@nrc.gov siva.lingam@nrc.gov wesley.deschaine@nrc.gov galen.smith@nrc.gov scott. shaeffer@n rc. g ov jeffrey. hamman@nrc.gov craig.kontz@nrc.gov caudle.julian@nrc.gov generette.lloyd@epa.gov gmadkins@tva.gov clwilson@tva.gov hleeO@tva.gov dllundy@tva.gov
