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| | issue date = 07/16/2014 | | | issue date = 07/16/2014 |
| | title = Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application Set 28 (TAC Nos. ME4936 and ME4937) | | | title = Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application Set 28 (TAC Nos. ME4936 and ME4937) |
| | author name = Daily J W | | | author name = Daily J |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = Koehl D L | | | addressee name = Koehl D |
| | addressee affiliation = South Texas Project Nuclear Operating Co | | | addressee affiliation = South Texas Project Nuclear Operating Co |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
| | license number = | | | license number = |
| | contact person = Daily J W, 415-3873 | | | contact person = Daily J, 415-3873 |
| | case reference number = TAC ME4936, TAC ME4937 | | | case reference number = TAC ME4936, TAC ME4937 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 5 | | | page count = 5 |
| | project = TAC:ME4936, TAC:ME4937 | | | project = TAC:ME4936, TAC:ME4937 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2014 Mr. Dennis L. Koehl President and Chief Nuclear Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937) Dear Mr. Koehl: By letter dated October 25, 2010, STP Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew operating licenses NPF-76 and NPF-80 for South Texas Project, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC 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. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2014 Mr. Dennis L. Koehl President and Chief Nuclear Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483 |
| | |
| | ==SUBJECT:== |
| | REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937) |
| | |
| | ==Dear Mr. Koehl:== |
| | |
| | By letter dated October 25, 2010, STP Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew operating licenses NPF-76 and NPF-80 for South Texas Project, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC 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. |
| This request for additional information has been presented to Mr. Arden Aldridge of your staff, and we request your response within 90 days of the date of this letter. If portions of your response need more time, please advise the staff of the date that information will be provided. | | This request for additional information has been presented to Mr. Arden Aldridge of your staff, and we request your response within 90 days of the date of this letter. If portions of your response need more time, please advise the staff of the date that information will be provided. |
| If you have any questions, please contact me by telephone at 301-415-3873 or by e-mail at john.daily@nrc.gov. Sincerely, /RA/ John W. Daily, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 | | If you have any questions, please contact me by telephone at 301-415-3873 or by e-mail at john.daily@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | John W. Daily, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: Listserv July 16, 2014 Mr. Dennis L. Koehl President and Chief Nuclear Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937) Dear Mr. Koehl: By letter dated October 25, 2010, STP Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew operating licenses NPF-76 and NPF-80 for South Texas Project, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC 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.
| |
| This request for additional information has been presented to Mr. Arden Aldridge of your staff, and we request your response within 90 days of the date of this letter. If portions of your response need more time, please advise the staff of the date that information will be provided. If you have any questions, please contact me by telephone at 301-415-3873 or by e-mail at john.daily@nrc.gov. Sincerely, /RA/ John W. Daily, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
| |
|
| |
|
| ==Enclosure:==
| | As stated cc w/encl: Listserv |
| As stated cc w/encl: Listserv DISTRIBUTION: See next page ADAMS Accession No. ML14183B719 *concurrence via email OFFICE PM: DLR/RPB1 LA: DLR/RPB1 BC: DLR/RPB1 PM: DLR/RPB1 NAME JDaily YEdmonds YDiaz JDaily DATE 7/14/14 79/14 7/16/14 7/16/14 OFFICIAL RECORD COPY ENCLOSURE SOUTH TEXAS PROJECT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION - SET 28 (TAC NOS. ME4936 AND ME4937) RAI B2.1.35-1 - Aging Management of Reactor Vessel Internals and MRP-227A Background: The license renewal application (LRA) for South Texas Project (STP), Units 1 and 2, proposed aging management for the reactor vessel internal (RVI) components based on a regulatory commitment in the LRA's Updated Final Safety Analysis Report (UFSAR) Supplement. The commitment stated that the applicant will develop an aging management program (AMP) and inspection plan based on augmented inspection activities for the components developed by the EPRI Materials Reliability Project (MRP), and that the inspection plan will be submitted for NRC review and approval at least two (2) years prior to entering into the period of extended operation for STP, Units 1 and 2. The NRC's recommended AMP for Pressured Water Reactor (PWR) RVIs in Revision 2 of NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is given in Section XI.M16A, "PWR Vessel Internals," which was issued in December 2010. On January 9, 2012, subsequent to the issuance of Revision 2 of the GALL Report, the EPRI MRP issued Technical Report No. 1022863, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," which included the NRC safety evaluation (SE) on the report's methodology dated December 16, 2011. On June 3, 2013, the staff revised AMP XI.M16A and the aging management review (AMR) items in the GALL Report for PWR RVI components to be consistent with the contents of the MRP-227-A report and issued them in License Renewal Interim Staff Guidance Document No. LR-ISG-2011-04, "Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors." On July 21, 2011, the NRC issued Regulatory Information Summary (RIS) 2011-07, "License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management," which provided updated NRC procedures for LRA reviews of PWR RVI AMPs. This RIS identifies Category C plants as those plants that have an LRA currently under review, and states that these applicants will be expected to revise their commitment for aging management of PWR vessel internals such that the information identified in the SE for MRP-227 would be submitted to the NRC for review and approval not later than two years after issuance of the renewed license or not later than two years before the plant enters the period of extended operation, whichever comes first. STP, Units 1 and 2, are Category C plants in accordance with the RIS. Issue: The categorization of STP, Units 1 and 2, and other plants in Category C of RIS 2011-07 was based on an expectation that the LRA would be reviewed and approved on a normal review schedule of 22 months, and that it would be an unreasonable burden to expect the applicant to address all aspects of the NRC's SE for MRP-227 within the LRA review. However, the applicant requested that the NRC place the LRA review on hold for the year 2013 to allow the applicant to address plant-specific technical issues. The staff noted that, as of the date of this RAI, the review of these technical issues is still on-going. Since the resolution of these issues is | | |
| - 2 - not imminent and completion of the staff's review of the LRA is on-going, the staff has concluded that the applicant should provide an LRA update or amendment that includes updated AMP and AMR items for the RVI components, including responses to the applicable Applicant/License Actions Items identified in the staff's SE for MRP-227.
| | ML14183B719 *concurrence via email OFFICE PM: DLR/RPB1 LA: DLR/RPB1 BC: DLR/RPB1 PM: DLR/RPB1 NAME JDaily YEdmonds YDiaz JDaily DATE 7/14/14 79/14 7/16/14 7/16/14 |
| In addition to the issues identified above, the staff has noted that recent operating experience at one 4-loop PWR (in 2010) reported cracking and failures of some nickel alloy (Alloy X-750) clevis insert bolts in the clevis assemblies attached to the lower internal portion of its reactor vessel (see EPRI Technical Report No. 1022863, "Materials Reliability Program: Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines (MRP-227-A)," Appendix A). The staff further noted that some inspection routines (such as an ASME Section XI visual VT-3 inspection on a 10-year frequency) of the clevis insert assemblies may not be adequate to ensure the integrity of clevis insert assemblies during design basis events if multiple bolt failures occur prior to detection, and then the design basis event were to occur. Request: The staff requests that STPNOC provide the following: | | |
| : 1. MRP-227-A Applicant/Licensee Action Items (A/LAIs): Provide either an LRA amendment or update that includes an updated AMP, updated AMR items, and any applicable inspection plan(s) for the PWR RVI components at STP, Units 1 and 2, that are based on the guidance in LR-ISG-2011-04, including responses to applicable A/LAIs identified in the staff's SE for MRP-227, dated December 16, 2011. 2. Reactor vessel clevis assemblies: Please address the clevis insert bolt operating experience issue cited above in reference to STP: a) Describe the configuration of clevis insert assemblies at STP, including number of bolts in the assemblies. Specify the materials of fabrication, including any applicable heat treatments, that were used for the design of the clevis insert bolts at STP. b) Discuss and justify whether the operating experience associated with cracking of the clevis insert bolts is applicable to the clevis insert assembly designs at STP. c) Describe the inspections that have been performed of the clevis insert bolts, including the type of inspection (e.g., VT-3). Discuss the visual inspection coverage that was achieved during these inspections. Clarify the ASME examination category that applies to inspections of the clevis insert bolts (and identify the applicable inspection method and frequency) and whether any past examinations have resulted in the detection of any indications of cracking or failures of the clevis insert bolts that are included in the clevis insert assembly designs. If so, provide the details of the inspection results and clarify the corrective actions that were taken at the facility to justify the structural integrity of the clevis insert assemblies and the intended safety function of the plant's core support structure and its components during plant operations. d) Based on your responses to Parts (a) through (c) of this request, clarify whether the 10-year lSI basis (or the current approach used for STP) for the clevis insert bolts is sufficient to manage cracking and wear of the bolts during the period of extended operation. Justify your response to this request. | | SOUTH TEXAS PROJECT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION - SET 28 (TAC NOS. ME4936 AND ME4937) |
| Letter to D. L. Koehl from John W. Daily dated July 16, 2014 SUBJECT: REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937) DISTRIBUTION: E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsOgcMailCenter ---------------------------------- JDaily TTran WHolston JWise DMcIntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV | | RAI B2.1.35 Aging Management of Reactor Vessel Internals and MRP-227A |
| | |
| | ==Background:== |
| | |
| | The license renewal application (LRA) for South Texas Project (STP), Units 1 and 2, proposed aging management for the reactor vessel internal (RVI) components based on a regulatory commitment in the LRAs Updated Final Safety Analysis Report (UFSAR) Supplement. The commitment stated that the applicant will develop an aging management program (AMP) and inspection plan based on augmented inspection activities for the components developed by the EPRI Materials Reliability Project (MRP), and that the inspection plan will be submitted for NRC review and approval at least two (2) years prior to entering into the period of extended operation for STP, Units 1 and 2. |
| | The NRCs recommended AMP for Pressured Water Reactor (PWR) RVIs in Revision 2 of NUREG-1801, Generic Aging Lessons Learned (GALL) Report, is given in Section XI.M16A, PWR Vessel Internals, which was issued in December 2010. On January 9, 2012, subsequent to the issuance of Revision 2 of the GALL Report, the EPRI MRP issued Technical Report No. |
| | 1022863, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A), which included the NRC safety evaluation (SE) on the reports methodology dated December 16, 2011. On June 3, 2013, the staff revised AMP XI.M16A and the aging management review (AMR) items in the GALL Report for PWR RVI components to be consistent with the contents of the MRP-227-A report and issued them in License Renewal Interim Staff Guidance Document No. LR-ISG-2011-04, Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors. |
| | On July 21, 2011, the NRC issued Regulatory Information Summary (RIS) 2011-07, License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management, which provided updated NRC procedures for LRA reviews of PWR RVI AMPs. This RIS identifies Category C plants as those plants that have an LRA currently under review, and states that these applicants will be expected to revise their commitment for aging management of PWR vessel internals such that the information identified in the SE for MRP-227 would be submitted to the NRC for review and approval not later than two years after issuance of the renewed license or not later than two years before the plant enters the period of extended operation, whichever comes first. STP, Units 1 and 2, are Category C plants in accordance with the RIS. |
| | Issue: |
| | The categorization of STP, Units 1 and 2, and other plants in Category C of RIS 2011-07 was based on an expectation that the LRA would be reviewed and approved on a normal review schedule of 22 months, and that it would be an unreasonable burden to expect the applicant to address all aspects of the NRCs SE for MRP-227 within the LRA review. However, the applicant requested that the NRC place the LRA review on hold for the year 2013 to allow the applicant to address plant-specific technical issues. The staff noted that, as of the date of this RAI, the review of these technical issues is still on-going. Since the resolution of these issues is ENCLOSURE |
| | |
| | not imminent and completion of the staffs review of the LRA is on-going, the staff has concluded that the applicant should provide an LRA update or amendment that includes updated AMP and AMR items for the RVI components, including responses to the applicable Applicant/License Actions Items identified in the staffs SE for MRP-227. |
| | In addition to the issues identified above, the staff has noted that recent operating experience at one 4-loop PWR (in 2010) reported cracking and failures of some nickel alloy (Alloy X-750) clevis insert bolts in the clevis assemblies attached to the lower internal portion of its reactor vessel (see EPRI Technical Report No. 1022863, Materials Reliability Program: Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines (MRP-227-A), Appendix A). The staff further noted that some inspection routines (such as an ASME Section XI visual VT-3 inspection on a 10-year frequency) of the clevis insert assemblies may not be adequate to ensure the integrity of clevis insert assemblies during design basis events if multiple bolt failures occur prior to detection, and then the design basis event were to occur. |
| | Request: |
| | The staff requests that STPNOC provide the following: |
| | : 1. MRP-227-A Applicant/Licensee Action Items (A/LAIs): Provide either an LRA amendment or update that includes an updated AMP, updated AMR items, and any applicable inspection plan(s) for the PWR RVI components at STP, Units 1 and 2, that are based on the guidance in LR-ISG-2011-04, including responses to applicable A/LAIs identified in the staffs SE for MRP-227, dated December 16, 2011. |
| | : 2. Reactor vessel clevis assemblies: Please address the clevis insert bolt operating experience issue cited above in reference to STP: |
| | a) Describe the configuration of clevis insert assemblies at STP, including number of bolts in the assemblies. Specify the materials of fabrication, including any applicable heat treatments, that were used for the design of the clevis insert bolts at STP. |
| | b) Discuss and justify whether the operating experience associated with cracking of the clevis insert bolts is applicable to the clevis insert assembly designs at STP. |
| | c) Describe the inspections that have been performed of the clevis insert bolts, including the type of inspection (e.g., VT-3). Discuss the visual inspection coverage that was achieved during these inspections. Clarify the ASME examination category that applies to inspections of the clevis insert bolts (and identify the applicable inspection method and frequency) and whether any past examinations have resulted in the detection of any indications of cracking or failures of the clevis insert bolts that are included in the clevis insert assembly designs. If so, provide the details of the inspection results and clarify the corrective actions that were taken at the facility to justify the structural integrity of the clevis insert assemblies and the intended safety function of the plant's core support structure and its components during plant operations. |
| | d) Based on your responses to Parts (a) through (c) of this request, clarify whether the 10-year lSI basis (or the current approach used for STP) for the clevis insert bolts is sufficient to manage cracking and wear of the bolts during the period of extended operation. Justify your response to this request. |
| | |
| | Letter to D. L. Koehl from John W. Daily dated July 16, 2014 |
|
| |
|
| }} | | ==SUBJECT:== |
| | REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937) |
| | DISTRIBUTION: |
| | E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsOgcMailCenter |
| | ---------------------------------- |
| | JDaily TTran WHolston JWise DMcIntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV}} |
Letter Sequence RAI |
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|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML110620203, ML11140A163, ML11224A265, ML11230A003, ML11318A121, ML11318A122, ML11318A123, ML11318A124, ML11318A125, ML11318A126, ML11318A127, ML11318A128, ML11318A129, ML11318A130, ML11318A131, ML11318A132, ML11318A133, ML11318A135, ML11318A136, ML11318A138, ML11318A139, ML11318A140, ML11318A141, ML11318A142, ML11318A143, ML11318A144, ML11318A145, ML11318A146, ML11318A147, ML11318A148, ML11318A149, ML11318A150, ML11318A151, ML11318A152, ML11318A153, ML11318A154, ML11318A155, ML11318A156, ML11318A157, ML11318A158, ML11318A159, ML11318A160, ML11318A161, ML11318A162, ML11318A163, ML11318A164, ML11318A165, ML11318A166, ML11318A167, ML11318A168... further results
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MONTHYEARML1106202032011-03-17017 March 2011 License Renewal Application Online Reference Portal Project stage: Other ML1108907642011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application-Electrical Branch Scoping Project stage: RAI ML1108205792011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application -Section 2.4 Structural (TAC Nos. ME4936, ME4937) Project stage: RAI ML1108309782011-04-14014 April 2011 Request for Additional Information for the Review of the South Texas Project, License Renewal Application, Fire Protection and Component Integrity (TAC Nos. ME4536 ME4637 Project stage: RAI NOC-AE-11002670, Response to Request for Additional Information for License Renewal Application2011-05-0505 May 2011 Response to Request for Additional Information for License Renewal Application Project stage: Response to RAI NOC-AE-11002672, Response to Request for Additional Information for Licence Renewal Application2011-05-12012 May 2011 Response to Request for Additional Information for Licence Renewal Application Project stage: Response to RAI ML11137A0922011-05-24024 May 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application Future Consideration of Operating Experience Project stage: RAI ML11140A1632011-06-0606 June 2011 Plan for the Aging Management Program Regulatory Audit Regarding the South Texas Project, Units 1 and 2 License Renewal Application Review (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002681, Amendment 2 to the License Renewal Application2011-06-16016 June 2011 Amendment 2 to the License Renewal Application Project stage: Other NOC-AE-11002683, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-06-23023 June 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML11154A0132011-07-0606 July 2011 Summary of Telephone Conference Call Held on May 23, 2011, Between the NRC and STPNOC, Concerning Requests for Additional Information Pertaining to the South Texas Project, LRA-Future Consideration of Operating Experience Project stage: RAI ML11166A2392011-07-12012 July 2011 Letter Request for Additional Information for South Texas Project Electric Generating Station, Units 1 and 2 License Renewal Application - Scoping and Screening Balance of Plant (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11201A0552011-07-28028 July 2011 Requests for Additional Information for the Review of the South Texas Project, License Renewal Application - Scoping and Screening Audit (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002702, Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application2011-08-0909 August 2011 Response to Request for Additional Information for the Review of the South Texas Project License Renewal Application Project stage: Response to RAI ML11214A0882011-08-15015 August 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Plant Systems (TAC ME4936 and ME4937) Project stage: RAI ML11214A0052011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Structures/Electrical (TAC ME4936 and ME4937) Project stage: RAI ML11214A0272011-08-15015 August 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Programs Audit, Reactor Systems (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002716, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-18018 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML1123000162011-08-18018 August 2011 License Renewal - Errata in AMP RAI Package Project stage: RAI NOC-AE-11002714, Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937)2011-08-23023 August 2011 Response to Request for Additional Information for the South Texas Project License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI ML11230A0032011-09-0606 September 2011 Scoping and Screening Audit Report Regarding the South Texas Project, Units 1 and 2 (TAC Nos. ME4936 and ME4937) Project stage: Other NOC-AE-11002730, Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Request for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002731, Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937)2011-09-15015 September 2011 Response to Requests for Additional Information for License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Response to RAI ML1124402012011-09-21021 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 2 (TAC Nos. ME4936, ME4937) Project stage: RAI ML11250A0432011-09-22022 September 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 1 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11224A2652011-09-22022 September 2011 Aging Management Programs Audit Report Regarding the South Texas Project, Units 1 and 2, Station License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Other ML11258A1612011-09-22022 September 2011 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application - Aging Management Review, Set 3 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11272A1652011-10-0404 October 2011 Summary of Telephone Conference Call Held on September 28, 2011, Between the NRC and STP Nuclear Operating Company, Concerning Request for Additional Information Pertaining to the South Texas Project, LRA (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002732, Response to Requests for Additional Information for the License Renewal Application2011-10-10010 October 2011 Response to Requests for Additional Information for the License Renewal Application Project stage: Response to RAI ML11273A0172011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 5 (TAC Nos. ME4936 and ME4937) Project stage: RAI ML11273A0082011-10-11011 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Review, Set 4 (TAC Nos. ME4936 and ME4937) Project stage: RAI NOC-AE-11002737, Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937)2011-10-18018 October 2011 Supplement to License Renewal Application (TAC Nos. ME4936 and ME4937) Project stage: Supplement ML11277A0472011-10-18018 October 2011 Requests for Additional Information for the Review of the South Texas Project, Units 1 and 2, License Renewal Application - Aging Management Program, Set 6 Project stage: RAI ML11305A0762011-10-25025 October 2011 Response to Requests for Additional Information for License Renewal Application (TAC ME4936 and ME4937) Project stage: Response to RAI NOC-AE-11002756, Contact Information Change, License Renewal Application (TAC ME4936 and ME4937)2011-10-26026 October 2011 Contact Information Change, License Renewal Application (TAC ME4936 and ME4937) Project stage: Other ML11318A1792011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1802011-11-0303 November 2011 Drawing No. LR-STP-WS-6R329F05048#1, Rev. 1, Piping and Instrumentation Diagram Solid Waste Processing System Project stage: Other ML11318A1762011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F05024#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1652011-11-0303 November 2011 Drawing No. LR-STP-PS9Z329Z00047#1, Rev. 1, Piping and Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1642011-11-0303 November 2011 Drawing No. LR-STP-PS-5Z329Z00045#2, Rev. 1, Piping & Instrumentation Diagram Primary Sampling System. Project stage: Other ML11318A1782011-11-0303 November 2011 Drawing No. LR-STP-WL-7R309F90021#1, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System Project stage: Other ML11318A1682011-11-0303 November 2011 Drawing No. LR-STP-RC-5R149F05004#2, Rev. 1, Piping and Instrumentation Diagram Acs Pressurizer Relief Tank. Project stage: Other ML11318A1722011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05022#2, Rev. 1, Piping and Instrumentation Diagram Liquid Waste Processing System. Project stage: Other ML11318A1702011-11-0303 November 2011 Drawing No. LR-STP-RM-5R279F05033#2, Rev. 1, Piping & Instrumentation Reactor Makeup Water System. Project stage: Other ML11318A1602011-11-0303 November 2011 Drawing No. LR-STP-IA-8Q119F05050#2, Rev. 1, Piping & Instrumentation Diagram Mechanical Aux. Building Instrument Air. Project stage: Other NOC-AE-11002749, Drawing No. LR-STP-SB-7S209F200032, Rev. 0, Piping and Instrumentation Diagram Steam Generator Blowdown System2011-11-0303 November 2011 Drawing No. LR-STP-SB-7S209F20003#2, Rev. 0, Piping and Instrumentation Diagram Steam Generator Blowdown System Project stage: Other ML11318A1742011-11-0303 November 2011 Drawing No. LR-STP-WL-5R309F05027#2, Rev. 1, Piping & Instrumentation Diagram Auxiliary Steam and Condensate Return System (Lwps) Project stage: Other ML11318A1462011-11-0303 November 2011 Drawing LR-STP-ED-5Q069F05030 #2, Rev. 17, Piping & Instrumentation Diagram Radioactive Vent & Drain System Sump Pumps. Project stage: Other ML11318A1552011-11-0303 November 2011 Drawing No. LR-STP-FP-7Q272F00046, Rev. 1, Piping and Instrumentation Diagram Fire Protection Loop. Project stage: Other ML11318A1482011-11-0303 November 2011 Drawing No. LR-STP-ED-5Q069F90011#2, Revision 1, Piping & Instrumentation Diagram Radioactive Vent and Drain System Fuel Handling Building Gravity Drains. Project stage: Other 2011-06-16
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Category:Letter
MONTHYEARML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20243012024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 NOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24184C0832024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24183A1742024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump ML24179A3412024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24171A0112024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 NOC-AE-240040, Annual Dose Report for 20232024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A3172024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 ML24092A1902024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) ML24017A2972024-02-15015 February 2024 Project Manager Assignment NOC-AE-240040, Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation2024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24039A1112024-02-0808 February 2024 Operator Licensing Examination Schedule Revision 2 ML24039A1602024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan 2024-09-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24052A0112024-02-16016 February 2024 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications (L-2023-LLE-0046) ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information ML23334A0062023-11-29029 November 2023 NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements ML23319A4442023-11-15015 November 2023 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements ML23278A1532023-10-0505 October 2023 NRR E-mail Capture - South Texas Project Request for Additional Information - Request for Indirect Transfer of Licenses and Conforming Amendments (L-2023-LLM-0004) ML23264A0972023-09-21021 September 2023 NRR E-mail Capture - South Texas Project - Request for Additional Information - License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047) ML23255A2862023-09-12012 September 2023 NRR E-mail Capture - South Texas Project Draft Request for Additional Information License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047) ML23145A1872023-05-24024 May 2023 July 2023 Emergency Preparedness Program Inspection - Request for Information ML22255A1542022-09-13013 September 2022 Operating Company Information Request for the Cyber Security Baseline Inspection 05000498/2022401 and 05000499/2022401 ML22206A0142022-07-20020 July 2022 NRR E-mail Capture - South Texas Project - Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22194A0502022-07-0707 July 2022 NRR E-mail Capture - South Texas Project - Updated Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22194A0492022-06-0808 June 2022 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request ML22123A3272022-05-0303 May 2022 STP EP Exercise Inspection July 2022 RFI ML22084A0762022-04-0404 April 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000498/2022012 and 05000499/2022012) and Request for Information ML21286A5732021-10-18018 October 2021 Notification of NRC Design Bases Assurance Inspection (Programs) (05000498/2022011 and 05000499/2022011) and Request for Information ML21166A2392021-06-16016 June 2021 Notification of Inspection (NRC Inspection Report 05000498/2021003 and 05000499/2021003) and Request for Information ML21160A1522021-06-0909 June 2021 Request for Information NRC Inspection 2021-003 Public Radiation Safety ML21133A2372021-05-0505 May 2021 Request for Additional Information: STP EP Exercise Inspection - July 2021 ML21039A8902021-02-0808 February 2021 NRR E-mail Capture - South Texas Project - Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing ML21029A3312021-01-29029 January 2021 NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing ML20280A5452020-08-17017 August 2020 STP 2020 PIR Request for Information ML20111A0052020-04-17017 April 2020 NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME OM Code 2012 Edition - Relief Request PRR-01 ML20070N0222020-03-10010 March 2020 NRC Selection for Onsite Review ML20057G4612020-02-26026 February 2020 05000498/499 Request for Information - Occupational Radiation Safety Inspection ML20045E2172020-02-13013 February 2020 Licensed Operator Positive Fitness-For-Duty Test ML20036F5862020-02-0404 February 2020 Request for Additional Information - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L-2019-LLR-0096)Redacted ML19165A1032019-06-14014 June 2019 NRR E-mail Capture - Draft RAI for STP TS 3.8.1.1 Sbdg SR Change ML19081A1512019-03-21021 March 2019 NRR E-mail Capture - Draft Round 2 RAI - Sbdg Voltage and Frequency LAR (L-2018-LLA-0078) ML18283B9522018-10-10010 October 2018 NRR E-mail Capture - Final RAI - South Texas Standby DG TS Change (L-2018-LLA-0078) ML18263A1432018-09-12012 September 2018 NRR E-mail Capture - Final RAI for South Texas Project RR-ENG-E-16 (L-2018-LLR-0097) ML18197A4172018-07-17017 July 2018 Notification of NRC Triennial Heat Sink Performance Inspection (05000498/2018003 and 05000499/2018003) and Request for Information ML18003B4222018-01-0303 January 2018 NRR E-mail Capture - Final Request for Additional Information Amendment Request to Modify the Emergency Response Organization for South Texas Project ML17229B4672017-08-16016 August 2017 Notification of NRC Inspection 05000499/2017008 and Request for Information ML17132A0712017-05-15015 May 2017 Information Request the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000498/2017407; 05000499/2017407 ML17103A6272017-04-13013 April 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000498/2017007 and 05000499/2017007) and Request for Information ML16351A1502016-12-16016 December 2016 Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409) ML16302A4532016-12-12012 December 2016 Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409) ML16343A0422016-12-0808 December 2016 Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application (CAC NOS. ME4936, ME4937) ML16340A1022016-12-0505 December 2016 Requests for Additional Information for the Review of the South Texas Project License Renewal Application (CAC Nos. ME4936 and ME4937) ML16246A0952016-09-15015 September 2016 Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16214A2912016-08-26026 August 2016 Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16187A0522016-07-0707 July 2016 Request for Additional Information Regarding License Renewal Application ML16141B0812016-05-31031 May 2016 Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information ML16125A2902016-05-26026 May 2016 Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) ML16127A4522016-05-12012 May 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16104A3522016-04-22022 April 2016 Requests for Additional Information Set 35 for the Review of the South Texas Project License Renewal Application (Tac Nos. ME4936, ME4937) ML16082A5072016-04-11011 April 2016 Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) ML16082A4842016-03-22022 March 2016 NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Risk Review for GSI-191 ML16081A0042016-03-18018 March 2016 NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Thermal-hydraulic Review for GSI-191 2024-07-25
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2014 Mr. Dennis L. Koehl President and Chief Nuclear Officer STP Nuclear Operating Company P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937)
Dear Mr. Koehl:
By letter dated October 25, 2010, STP Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew operating licenses NPF-76 and NPF-80 for South Texas Project, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC) staff. The NRC 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.
This request for additional information has been presented to Mr. Arden Aldridge of your staff, and we request your response within 90 days of the date of this letter. If portions of your response need more time, please advise the staff of the date that information will be provided.
If you have any questions, please contact me by telephone at 301-415-3873 or by e-mail at john.daily@nrc.gov.
Sincerely,
/RA/
John W. Daily, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
As stated cc w/encl: Listserv
ML14183B719 *concurrence via email OFFICE PM: DLR/RPB1 LA: DLR/RPB1 BC: DLR/RPB1 PM: DLR/RPB1 NAME JDaily YEdmonds YDiaz JDaily DATE 7/14/14 79/14 7/16/14 7/16/14
SOUTH TEXAS PROJECT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION - SET 28 (TAC NOS. ME4936 AND ME4937)
RAI B2.1.35 Aging Management of Reactor Vessel Internals and MRP-227A
Background:
The license renewal application (LRA) for South Texas Project (STP), Units 1 and 2, proposed aging management for the reactor vessel internal (RVI) components based on a regulatory commitment in the LRAs Updated Final Safety Analysis Report (UFSAR) Supplement. The commitment stated that the applicant will develop an aging management program (AMP) and inspection plan based on augmented inspection activities for the components developed by the EPRI Materials Reliability Project (MRP), and that the inspection plan will be submitted for NRC review and approval at least two (2) years prior to entering into the period of extended operation for STP, Units 1 and 2.
The NRCs recommended AMP for Pressured Water Reactor (PWR) RVIs in Revision 2 of NUREG-1801, Generic Aging Lessons Learned (GALL) Report, is given in Section XI.M16A, PWR Vessel Internals, which was issued in December 2010. On January 9, 2012, subsequent to the issuance of Revision 2 of the GALL Report, the EPRI MRP issued Technical Report No.
1022863, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A), which included the NRC safety evaluation (SE) on the reports methodology dated December 16, 2011. On June 3, 2013, the staff revised AMP XI.M16A and the aging management review (AMR) items in the GALL Report for PWR RVI components to be consistent with the contents of the MRP-227-A report and issued them in License Renewal Interim Staff Guidance Document No. LR-ISG-2011-04, Updated Aging Management Criteria for Reactor Vessel Internal Components of Pressurized Water Reactors.
On July 21, 2011, the NRC issued Regulatory Information Summary (RIS) 2011-07, License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management, which provided updated NRC procedures for LRA reviews of PWR RVI AMPs. This RIS identifies Category C plants as those plants that have an LRA currently under review, and states that these applicants will be expected to revise their commitment for aging management of PWR vessel internals such that the information identified in the SE for MRP-227 would be submitted to the NRC for review and approval not later than two years after issuance of the renewed license or not later than two years before the plant enters the period of extended operation, whichever comes first. STP, Units 1 and 2, are Category C plants in accordance with the RIS.
Issue:
The categorization of STP, Units 1 and 2, and other plants in Category C of RIS 2011-07 was based on an expectation that the LRA would be reviewed and approved on a normal review schedule of 22 months, and that it would be an unreasonable burden to expect the applicant to address all aspects of the NRCs SE for MRP-227 within the LRA review. However, the applicant requested that the NRC place the LRA review on hold for the year 2013 to allow the applicant to address plant-specific technical issues. The staff noted that, as of the date of this RAI, the review of these technical issues is still on-going. Since the resolution of these issues is ENCLOSURE
not imminent and completion of the staffs review of the LRA is on-going, the staff has concluded that the applicant should provide an LRA update or amendment that includes updated AMP and AMR items for the RVI components, including responses to the applicable Applicant/License Actions Items identified in the staffs SE for MRP-227.
In addition to the issues identified above, the staff has noted that recent operating experience at one 4-loop PWR (in 2010) reported cracking and failures of some nickel alloy (Alloy X-750) clevis insert bolts in the clevis assemblies attached to the lower internal portion of its reactor vessel (see EPRI Technical Report No. 1022863, Materials Reliability Program: Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines (MRP-227-A), Appendix A). The staff further noted that some inspection routines (such as an ASME Section XI visual VT-3 inspection on a 10-year frequency) of the clevis insert assemblies may not be adequate to ensure the integrity of clevis insert assemblies during design basis events if multiple bolt failures occur prior to detection, and then the design basis event were to occur.
Request:
The staff requests that STPNOC provide the following:
- 1. MRP-227-A Applicant/Licensee Action Items (A/LAIs): Provide either an LRA amendment or update that includes an updated AMP, updated AMR items, and any applicable inspection plan(s) for the PWR RVI components at STP, Units 1 and 2, that are based on the guidance in LR-ISG-2011-04, including responses to applicable A/LAIs identified in the staffs SE for MRP-227, dated December 16, 2011.
- 2. Reactor vessel clevis assemblies: Please address the clevis insert bolt operating experience issue cited above in reference to STP:
a) Describe the configuration of clevis insert assemblies at STP, including number of bolts in the assemblies. Specify the materials of fabrication, including any applicable heat treatments, that were used for the design of the clevis insert bolts at STP.
b) Discuss and justify whether the operating experience associated with cracking of the clevis insert bolts is applicable to the clevis insert assembly designs at STP.
c) Describe the inspections that have been performed of the clevis insert bolts, including the type of inspection (e.g., VT-3). Discuss the visual inspection coverage that was achieved during these inspections. Clarify the ASME examination category that applies to inspections of the clevis insert bolts (and identify the applicable inspection method and frequency) and whether any past examinations have resulted in the detection of any indications of cracking or failures of the clevis insert bolts that are included in the clevis insert assembly designs. If so, provide the details of the inspection results and clarify the corrective actions that were taken at the facility to justify the structural integrity of the clevis insert assemblies and the intended safety function of the plant's core support structure and its components during plant operations.
d) Based on your responses to Parts (a) through (c) of this request, clarify whether the 10-year lSI basis (or the current approach used for STP) for the clevis insert bolts is sufficient to manage cracking and wear of the bolts during the period of extended operation. Justify your response to this request.
Letter to D. L. Koehl from John W. Daily dated July 16, 2014
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 28 (TAC NOS. ME4936 AND ME4937)
DISTRIBUTION:
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JDaily TTran WHolston JWise DMcIntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV