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Category:Letter type:NL
MONTHYEARNL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers 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 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-23-0713, 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-23-0716, 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-23-0704, 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 2024-07-03
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Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN . \
COMPANY August 18, 2008 Energy to Serve Your World'"
Docket Nos.: 50-364 NL-08-1233 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 2 Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18 Ladies and Gentlemen:
In letter dated November 1,2007, Southern Nuclear Company (SNC) submitted information summarizing the results of the 2007 steam generator (SG) tube inspections performed at Joseph M. Farley Nudear Plant Unit 2 during refueling outage 18.
On July 1, 2008, a NRC Request for Additional Information (RAI) was received regarding information needed for the staff to complete review. The SHC response to the requested information is provided in the Endosure.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJAlJLS/phr
U. S. Nuclear Regulatory Commission NL-08-1233 Page 2
Enclosure:
Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. H. Jones, Vice President - Engineering RTYPE: CFA04.054; LC# 14816 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. A. Jervey, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 2 Enclosure Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18
Enclosure Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18 NRC Question 1
- 1. Regarding the scope of your inspection, please clarify the following:
a) Please discuss the nature of the tubes that "could not be examined full length."
b) It was indicated that 1 dent or ding in SG C had a bobbin voltage greater than or equal to 5 volts. Discuss whether the size of this indication has changed with time (or any other dent or ding indication). If so, please discuss the nature/reason for the change. Please refer to your letter dated December 17, 2004 (ADAMS Accession No. ML043570226).
c) Please discuss how many tubes have non-quantifiable signals and the nature of these indications. In addition, discuss the nature of the "history based indications." Are these indications manufacturing related (since no service induced indications have been reported)?
d) Please discuss the scope and results of any secondary side inspections. If any foreign objects were found during these inspections, discuss how they were detected (bobbin, rotating probe, visual) and whether they were removed from the steam generator. If the objects were not removed, please discuss whether an analysis was performed to ensure tube integrity would not be compromised for the period of time between planned inspections.
SNC Response to NRC Question 1 1.a) Low Row Tubes (Rows 1 and 2) can not be examined full length with the "Bobbin Probe" due to the tight radius of the U-Bends. Inspection of these locations were performed using a "+ Point" probe.
1.b) The size of the referenced SG C indication, has not changed with time. A review of SNC letter dated December 17, 2004 revealed that all Dent and Dings (DNGs) discovered in SG C were inadvertently discussed as less than 5 volts, but actually the referenced SG C indication was greater than 5 volts. Therefore, the 2R18 inspection plan included the 2R15 DNG in SG C which was greater than 5 volts. The 2R18 inspection results determined that the referenced SG C signal was from the U-Bend transition and was not aDNG.
1.c) There were two non-quantifiable signals (NQS) reported from the 2R15 inspection results. These signals are deemed to be manufacturing indications from the single step pilgering process.
The term "history based indications" was used in the section for those inspections that are to be performed by the Bobbin probe. The "history Page 1 of 3
Enclosure Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18 based indications" inspected were the 2R15 dents and dings and the non quantifiable signals listed in this section.
1.d) Inspections I Results Secondary side inspections in all three SGs included:
- Foreign Object Search and Retrieval (FOSAR) -Inspection to search for and remove foreign objects from the tube bundle, annulus and tube lane. For inspection results - see "Foreign Objects Discovered in SGs" below.
- 100% Top of Tubesheet (TIS) In-Bundle - A column-by-column visual examination of the TIS region to search and remove foreign objects.
For inspection results - see "Foreign Objects Discovered in SGs" below.
- Shell Wrapper Annulus Transport System (SWATS) - Annulus inspection performed from the wrapper looking inward toward the tube region. Inspection results were acceptable.
- Wrapper Drop - Inspection to verify access to the tubelane without interference. Inspection results were acceptable.
- Upper Internals - Visual inspection performed in each SG's steam drum of the feedring assembly, support brackets and welds, primary separators, steam outlet nozzle flow limiter, and sludge collector. For inspection results - see "Foreign Objects Discovered in SGs" below.
Additional secondary side inspections performed for SG A:
- Tube Support Plate Ligament Erosion-Corrosion and Cracking: Upper Bundle In-Bundle (USIB) to provide surveillance information on support plate ligaments, quatrefoil blockage, and appearance of upper tube support plates. The 7th tube support plate was also visually inspected from an upper handhole. Inspection results were acceptable.
Foreign Objects Discovered in SGs A number of small objects were observed at the top of the tubesheet within the tube bundle, for example - fragments of spiral wound gaskets, machining remnants, wire bristles, weld slag, pieces of tube scale, and sludge rocks. Approximately 272 objects were found in all three SGs (TIS - 87, Sludge Lance Filter -124, Feedrings - 61), approximately 238 objects were removed. After the extensive retrieval effort, approximately 34 objects remain in the SGs, due to the objects being locked in hard sludge. These objects are being tracked in the plants Page 2 of 3
Enclosure Response to Request for Additional Information Regarding the Steam Generator Tube Inservice Inspection Report for Refueling Outage 18 corrective action program. Wear assessments were performed on the objects remaining in the SG. The SG tube inspection results and analysis of the potential for the remaining foreign objects to cause tube degradation, gives assurance that tube integrity will be maintained until the next scheduled eddy current inspection during 2R21.
NRC Question 2 For each refueling outage and SG tube inspection outage since replacement of your SGs, please provide the cumulative effective full power months (EFPM) that the SGs have operated.
SNC Response to NRC Question 2
- 2R15 - First lSI after replacement (approximately 16.2 EFPM)
- 2R18 - Second ISI- (approximately 67.0 EFPM since replacement)
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