|
|
(11 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML12165A107 | | | number = ML12165A107 |
| | issue date = 06/14/2012 | | | issue date = 06/14/2012 |
| | title = Joseph M. Farley Nuclear Plant, Units 1 and 2, Vogtle Electric Generating Plant, Units 1 and 2 - Request for Additional Information (TAC Nos. ME7846, ME7847, ME7839, and ME7840) | | | title = Request for Additional Information |
| | author name = Martin R E | | | author name = Martin R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Ajluni M J | | | addressee name = Ajluni M |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364, 05000424, 05000425 | | | docket = 05000348, 05000364, 05000424, 05000425 |
| | license number = | | | license number = |
| | contact person = Martin R E | | | contact person = Martin R |
| | case reference number = TAC ME7839, TAC ME7840, TAC ME7846, TAC ME7847 | | | case reference number = TAC ME7839, TAC ME7840, TAC ME7846, TAC ME7847 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 3 | | | page count = 3 |
| | project = TAC:ME7839, TAC:ME7840, TAC:ME7846, TAC:ME7847 | | | project = TAC:ME7839, TAC:ME7840, TAC:ME7846, TAC:ME7847 |
| | | stage = RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:..."..1\ REGU{ UNITED STATES .:;,V" "I... 01' NUCLEAR REGULATORY /ll ... WASHINGTON, D.C. 20555-0001 << 0 'in 1 June 14,2012't/. ***1<'" Mr. M. J. Nuclear Licensing Southern Nuclear Operating Company, 40 Inverness Center Post Office Box 1295, Bin -Birmingham, AL JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) Dear Mr. Ajluni: By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. Please provide the additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP) VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP) SOUTHERN NUCLEAR OPERATING COMPANY (SNC) The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows: TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide [RG] 1.14, Revision 1, August 1975. In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals. Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years. However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5). Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above. Enclosure June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) Dear Mr. Ajluni: By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML 120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. Please provide the additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107 | | {{#Wiki_filter:.:;,V" |
| * By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy | | ..."..1\ REG U{ |
| }} | | "I r UNITED STATES |
| | ... 01' NUCLEAR REGULATORY COMMISSION |
| | /ll |
| | -'<' WASHINGTON, D.C. 20555-0001 |
| | << 0 |
| | 'in 1 June 14,2012 |
| | ~ ~ |
| | 't/. ~ |
| | ~., ~o |
| | ***1<'" |
| | Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) |
| | |
| | ==Dear Mr. Ajluni:== |
| | |
| | By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. |
| | Please provide the additional information within thirty (30) days of the date of this letter. |
| | Sincerely, |
| | (/2~/J1~ |
| | Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP) |
| | VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP) |
| | SOUTHERN NUCLEAR OPERATING COMPANY (SNC) |
| | The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. |
| | The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows: |
| | TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide |
| | [RG] 1.14, Revision 1, August 1975. |
| | In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals. |
| | Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years. |
| | However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5). |
| | Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above. |
| | Enclosure |
| | |
| | June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. |
| | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) |
| | |
| | ==Dear Mr. Ajluni:== |
| | |
| | By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. |
| | Please provide the additional information within thirty (30) days of the date of this letter. |
| | Sincerely, IRA! |
| | Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107 |
| | * By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC ~Pl2-1/PM NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
---|
TAC:ME7839, Revision to RCP Flywheel Inspection Program - WCAP-15666 (Approved, Closed) TAC:ME7840, Revision to RCP Flywheel Inspection Program - WCAP-15666 (Approved, Closed) TAC:ME7846, Revision to RCP Flywheel Inspection Program - WCAP-15666 (Approved, Closed) TAC:ME7847, Revision to RCP Flywheel Inspection Program - WCAP-15666 (Approved, Closed) |
|
|
|
---|
Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24010A0712024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting) ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML24029A0592024-01-30030 January 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants ML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C ML23347A2092024-01-17017 January 2024 Voluntary Requests for Data, Information, And/Or Observation ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public ML23335A1222023-12-19019 December 2023 Safety Evaluation Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (EPID L-2023-LRQ-0002) - Letter ML23353A1702023-12-19019 December 2023 LAR-22-002, TS 3.8.3 Inverters Operating Completion Time Extension Letter NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report ML23339A1812023-12-0707 December 2023 Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23338A2182023-12-0606 December 2023 Project Manager Reassignment NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23289A1632023-11-28028 November 2023 Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 ML23312A3502023-11-14014 November 2023 Integrated Inspection Report 05200026/2023003 NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23306A3552023-11-0808 November 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 052000/262023008 ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) IR 05000424/20234022023-11-0606 November 2023 Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 ML23291A1512023-10-18018 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 0520026/2024401 ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARIR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23342A0802023-12-0808 December 2023 NRR E-mail Capture - Request for Additional Information (RAI) - Vogtle, Unit 1 - Review of SG Tube Inspection Report for Refueling Outage 24 (L-2023-LRO-0067) ML23279A2082023-10-0505 October 2023 Issuance of Formal RAIs - Vogtle, Units 1 and 2 - Proposed LAR and Proposed Alternative Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23248A3482023-09-0505 September 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 6 - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23188A1512023-08-0909 August 2023 Round 2 RAIs for LAR 22-002 TS 3.8.3 Inverters-Operating, Completion Time Extension ML23200A0112023-07-18018 July 2023 Document Request for Vogtle Unit 3 RP Inspection ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23193A7832023-07-12012 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23065A0612023-03-0303 March 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 14 - Vogtle - AST, TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML23006A0882023-01-0606 January 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - Accident Source Term (Ast), TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22348A0332022-12-13013 December 2022 NRR E-mail Capture - for Your Action - RAI - Vogtle, Unit 2 - Steam Generator Tube Inspection Report (L-2022-LRO-0120) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22192A1042022-08-0101 August 2022 Acceptance of Requested Licensing Action Amendment Request Application to Allow Use of Lead Test Assemblies for Accident Tolerant Fuel with Request for Additional Information ML22157A0902022-06-0606 June 2022 NRR E-mail Capture - RAIs - Vogtle, Unit 1 - Refueling Outage (RFO) 1R23 Steam Generator (SG) Tube Inspection Report ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22026A3942022-01-26026 January 2022 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21350A1032021-12-16016 December 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3762021-11-15015 November 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21033B1072021-02-0202 February 2021 NRR E-mail Capture - RAI - Vogtle Unit 1 - SG Report (L-2020-LRO-0059) ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20338A1512020-12-0303 December 2020 NRR E-mail Capture - RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20325A0432020-11-20020 November 2020 NRR E-mail Capture - for Your Review - Draft RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20297A3052020-10-22022 October 2020 NRR E-mail Capture - RAIs for Vogtle Relief Request - EPRI Report (L-2020-LLR-0109) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate 2024-01-26
[Table view] |
Text
.:;,V"
..."..1\ REG U{
"I r UNITED STATES
... 01' NUCLEAR REGULATORY COMMISSION
/ll
-'<' WASHINGTON, D.C. 20555-0001
<< 0
'in 1 June 14,2012
~ ~
't/. ~
~., ~o
Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840)
Dear Mr. Ajluni:
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely,
(/2~/J1~
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP)
VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP)
SOUTHERN NUCLEAR OPERATING COMPANY (SNC)
The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure.
The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows:
TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide
[RG] 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years.
However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5).
Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above.
Enclosure
June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840)
Dear Mr. Ajluni:
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107
- By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC ~Pl2-1/PM NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy