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Category:Letter type:NL
MONTHYEARNL-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 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 NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation 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 NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
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Mark J. Ajluni, P.E. Southern Nuclear Nuclear licensi ng Director Operating Company, Inc. 40 Inverness Center Post Office Box 1295 Birmingham, Alabama 35201 Tel Fax May 27,2011 SOUTHERN'\'
COMPANY Docket 50-348 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Units 1 and NRC Request for Addition Information Risk-Informed lSI Alternative FNP-ISI-ALT-12, Version Ladies and Gentlemen:
By letter dated January 5, 2011, Southern Nuclear Operating Company Inc. (SNC) submitted alternative FNP-ISI-ALT-12, Version 2.0, for U.S. Nuclear Regulatory Commission (NRC) review and approval.
Subsequently, by letter dated April 27, 2011 (ADAMS Accession Number ML11094A008) the NRC submitted a request for additional information (RAI) to enable completion of the review. The responses to the NRC RAls are provided in the Enclosure.
This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
Sincerely, M. J. Ajluni Nuclear Licensing Director MJAJLWWllac
Enclosure:
Farley Nuclear Plant -Units 1 and 2, FNP-ISI-ALT-12, Version 2.0, RAI Responses U. S. Nuclear Regulatory Commission NL-11-0941 Page 2 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. L. M. Stinson, Vice President
-Farley Ms. P. M. Marino, Vice President
-Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatorv Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager -Farley Mr. E. L. Crowe, Senior Resident Inspector
-Farley Mr. P. G. Boyle, NRR Project Manager Joseph M. Farley Nuclear Plant, Units 1 and NRC Request for Addition Information Risk-Informed lSI Alternative FNP-ISI-AL T-12, Version Farley Nuclear Plant -Units 1 and 2, FNP-ISI-ALT-12, Version RAJ By letter dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML110060173), Southern Nuclear Operating Company, Inc. (SNC) submitted Relief Request (RR)
Version 2.0, for U.S. Nuclear Regulatory Commission (NRC) review and approval, which requests the use of alternative inservice inspection selection and examination criteria for Category B-J, C-F-1, and C-F-2 pressure retaining piping welds. To enable completion of the review, the NRC staff requests additional information as follows: 1. NRC RAI In Enclosure 1, Section 2.2 of the RR, under the fourth bullet, the FNP examination program for dissimilar metal butt welds is discussed.
The second paragraph's
'first sentence states, "Even though Code Case N-716 only considers the RPV [reactor pressure vessel] hot leg nozzle Alloy 82/182 weld locations to be susceptible to PWSCC [primary water stress corrosion cracking], SNC has selected all six welds to be ultrasonically examined for PWSCC within the scope of Code Case N-716." The third sentence of this paragraph states, "However, the examination frequency of these eight welds is currently based on the frequencies established by the requirements of Materials Reliability Program (MRP)-139, Revision 1." Clarify this discrepancy in the number of welds considered to be susceptible to PWSCC and examined in accordance with MRP-139. SNC Response The sentence should read, "However, the examination frequency of these six welds is currently based on the frequencies established by the requirements of Materials Reliability Program (MRP)-139, Revision 1." 2. NRC RAI In Enclosure 1, Section 3.1 (5) of the RR, SNC states that, "During the review, it was determined that in order to reduce the flooding scenario frequencies due to the postulated rupture of fire protection piping in the auxiliary building areas (210, 211, 228, and 234 for Unit 1 and 2210, 2211, 2228, and 2234 for Unit 2) that supplementary visual inspection of the associated fire protection piping is required every quarter. With these inspections, no piping segments with a contribution to CDF [core damage frequency]
greater than 1 E-06 (1 E-07 for LERF [large early release frequency])
were identified." This appears to be a deviation from the methodology of Code Case N-716 which would apply high safety significance to the segments with a contribution to CDF greater than 1 E-6 and require additional volumetric examinations.
Please provide justification for this approach.
Discuss how the quarterly visual exams reduce the flooding frequencies.
Were the degradation mechanisms applicable to the fire protection piping evaluated?
Discuss the classification results if the quarterly visual examinations are not performed.
SNC Response The core damage and large early release frequencies for this postulated flooding event are approximately 1 E-6 if quarterly visual examinations are not performed. Therefore, without performing the visual examinations, the piping would be classified as high safety significant.
The visual examination is credited in the internal flooding analysis to adjust the pipe rupture frequency.
The credit is based on the application of revised EPRI methodology (Pipe Rupture Frequencies for Internal Flooding Probabilistic Risk Assessments, EPRI, Palo Alto, CA: 2006. 1021086 Draft Revision 2, May 2010) which results in less than an order of magnitude reduction in the pipe rupture frequency for fire protection piping identified in NRC RAI 2 by incorporating a quarterly visual inspection.
The reduction is based on the 0.9 probability of detection for finding a leak in the piping where there is an easy accessibility of the piping, as discussed below. The Code Case N-716 requirement is for those piping segments that are found to be high safety significant (HSS) per a realistic internal flooding analysis where risk reducing credits, such as visual inspections, are already included in the assessment.
Therefore, it was judged that Code Case N-716 requirements for additional volumetric examinations did not apply to the subject fire protection piping. The following paragraph presents additional information which provides reasonable assurance that applying the EPRI methodology recommended rupture frequency correction was justified for the subject fire protection piping. The subject fire protection piping material is A 106 GR. 8 carbon steel and the nominal wall thickness is Schedule 40 with welded joint construction.
The fire protection system utilizes untreated well water as the primary water source, with a service water backup. The Farley-specific experience is that indoor fire protection lines of similar construction will exhibit detectable leakage well in advance of an overall integrity concern. For carbon steel piping, with untreated well water, the postulated degradation mechanism is wall loss due to pitting (or possibly microbiological induced corrosion).
The subject piping is generally located just overhead in the auxiliary building areas (210, 211,228, and 234 for Unit 1 and 2210, 2211, 2228, and 2234 for Unit 2) and is easily accessible for visual examinations.
Therefore, leakage should be detected well before the piping is degraded to the extent that it would break and create the flooding scenario.
Additionally, and as an added level of assurance, since the January 5, 2011 submittal to the NRC, SNC has been performing additional evaluations of the subject piping. This includes walkdowns of the subject piping to better define the scope and to evaluate the fabrication requirements.
The walkdowns indicated that Farley Unit 1 has approximately 56 welds and Farley Unit 2 has approximately 75 welds in the scope. The piping includes 8" diameter headers, plus 2.5" and 4" diameter branch lines. The piping was fabricated and erected per American National Standards Institute (ANSI) 831.1, Class III requirements.
During construction, the welds were only required to receive a visual examination; therefore, the weld crowns were not prepped and were left in an "as-welded" configuration.
Even though the use of the visual examinations, as described above, reduced the failure frequencies and subsequently lowered the Code Case N-716 classification from high to low safety significance, SNC has determined that the subject welds will be categorized as Category R-A, Item R1.17, HSS welds. Item R1.17 welds are those welds that are subject to localized corrosion and a volumetric examination is required to verify the minimum wall thickness.
During a ten-year inservice inspection interval, six Farley Unit 1 welds and eight Farley Unit 2 welds will be examined to verify that the wall thickness meets minimum wall requirements.
Performance of these thickness measurements, along with the previously discussed visual examinations, will provide reasonable assurance that the structural integrity of the subject fire protection piping is being maintained.