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Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core2023-05-0404 May 2023 Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 42023-04-13013 April 2023 Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0084, Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 42023-03-29029 March 2023 Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 4 RA-23-0083, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 22023-03-16016 March 2023 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0331, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 12022-11-22022 November 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 1 RA-22-0266, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core2022-09-19019 September 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core RA-22-0201, Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-07-21021 July 2022 Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections RA-22-0220, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-19019 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0218, Emergency Action Level (EAL) Technical Basis Document, Revision 32022-07-14014 July 2022 Emergency Action Level (EAL) Technical Basis Document, Revision 3 RA-22-0205, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-11011 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0149, Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-28028 April 2022 Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-22-0029, Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 20212022-04-27027 April 2022 Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 2021 RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 2024-01-10
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{{#Wiki_filter:Mandy Hare tl_~ DUKE Manager Nuclear Support Services Catawba Nuclear Station
~ ENERGY~
Duke Energy CN03CH I 4800 Concord Rd York, SC 29745 803.701.2218 Mandy.Hare@duke-energy.com Serial: RA-22-0201 July 21, 2022 United States Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Unit No. 2 Docket No. 50-414 / Renewed License No. NPF-52
Subject:
Catawba Unit 2, Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, "Revised Frequencies for Steam Generator Tube Inspections" Ladies and Gentlemen:
By letter dated March 4, 2022 (ADAMS Accession No. ML22010A281) , the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Numbers 311 and 307 to the Renewed Facility Operating Licenses for CNS, Units 1 and 2, respectively. Amendments 311 and 307 revised Technical Specification 5.6.8, "Steam Generator (SG) Tube Inspection Report," based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, "Revised Frequencies for Steam Generator Tube Inspections." Pursuant to TSTF-577, Revision 1, a SG tube inspection report satisfying the revised TS 5.6.8 requirements is being provided to the NRC staff because a 100% inspection during CNS Unit 2, Refuel 24 (i.e., before adopting TSTF-577) is being credited as the beginning point of the new inspection period.
The Enclosure to this letter contains the SG tube inspection report for CNS Unit 2, Refuel 24 in accordance with the revised TS 5.6.8 reporting requirements.
This submittal contains no regulatory commitments. Should you have any questions concerning this letter, or require additional information, please contact Ryan Treadway, Manager - Nuclear Fleet Licensing, at 980-373-5873.
Sincerely, 7>7 1.3. J-{aAJ-,,
Mandy Hare Manager Nuclear Support Services, Catawba Nuclear Station
U.S. Nuclear Regulatory Commission Page 2 RA-22-0201
Enclosure:
Catawba Unit 2, Refuel 24 Steam Generator Tube Inspection Report cc: (w/ Enclosure)
L. Dudes, NRC Regional Administrator, Region II Z. Stone, NRC Project Manager, NRR J.D. Austin, NRC Senior Resident Inspector, Catawba Nuclear Station
U.S. Nuclear Regulatory Commission RA-22-0201 Enclosure Catawba Unit 2, Refuel 24 Steam Generator Tube Inspection Report
Steam Generator Tube Inspection Report Catawba Nuclear Station Unit 2 EOC-24 April 2021 Location: 4800 Concord Road, York South Carolina 29745 NRC Docket No. 50-414 \ License No. NPF-52 National Board No. 173 Commercial Service Date: August 19, 1986 Owner: Duke Energy Corporation 526 South Church St.
Charlotte, N.C. 28201-1006 Revision 0 Prepared By: Dan Mayes Checked By: Marie Turner Approved By: Etienne Fonteneau
TSTF-577 supplement to Catawba Nuclear Station Unit 2 EOC 24 Steam Generator Tube Inspection Report Pursuant to Catawba technical specification 5.6.8 and industry guidance the following information is provided:
Background
Catawba Nuclear Station utilizes a Recirculating Steam Generator (RSG) design for primary to secondary heat transfer. There are four preheat steam generators with reactor coolant flow divided among them. The Catawba Unit 2 RSGs are Model D5, manufactured by Westinghouse and are original to the station. Each steam generator has 4578 tubes constructed of thermally treated Inconel Alloy 600 (I-600) with an outside diameter of 0.750 inches and nominal wall thickness of 0.043 inches. The tubes are hydraulically expanded full depth of the tubesheet, complete from the primary to secondary face, and flush seal welded at the primary face.
On the secondary side, the tubes are supported in the hot leg by seven quatrefoil broached tubes support plates (TSP) and the drilled flow distribution baffle (FDB). The cold leg is supported by five quatrefoil broached tube support plates, five drilled preheater baffles (PB) and the drilled flow distribution baffle arranged vertically along the SG above the tubesheet.
There are two sets of square nested anti-vibration bars per steam generator to support the u-bends. Figure 1 provides a visual representation of the SGs.
The preheater acts to collect most foreign objects.
No deviations have been taken from industry guidelines.
The nominal Thot is ~617 degrees Fahrenheit.
There has been no detectable primary to secondary leakage since the last inspection at EOC-24.
- a. The scope of inspections performed on each SG See report ADAMS accession number ML21214A160.
- b. The nondestructive examination techniques utilized for tubes with increased degradation susceptibility.
All currently known tubes with increased degradation susceptibility have been plugged.
- c. For each degradation mechanism found:
- 1. The nondestructive examination techniques utilized.
See report ADAMS accession number ML21214A160.
- 2. The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported.
See report ADAMS accession number ML21214A160.
- 3. A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment.
See report ADAMS accession number ML21214A160.
The table below shows the comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment to the current as found degradation Degradation EOC-23 Projection (%TW) EOC-24 As found (%TW)
AVB Wear 53.2 36 Broached TSP 49.5 34 Wear Drilled TSP wear 24.2 11 FO wear See below 43 No growth is typically considered for FO wear indications provided that the wear-initiating object is no longer being in the tube vicinity for these indications.
Therefore, there is no comparison to a projected depth needed as performed for other tube wear mechanisms since no OA with growth was performed for EOC-23 for historical foreign object wear indications over the past operating cycle.
No crack like indications were identified during EOC-24
- 4. The number of tubes plugged [or repaired] during the inspection outage.
See report ADAMS accession number ML21214A160.
- d. An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results.
The operational assessment for wear was determined deterministically for the worst-case flaw.
Degradation Maximum depth projected OA Limit Growth rate Projected Wear at next inspection (%TW) (%TW/EFPY) EFPY
(%TW)
AVB 52 63.5 2.051 4.5 Broached TSP 57.1 58.4 3.42 4.5 Drilled 31 59 3.42 4.5 1=95th percentile 2=maximum The maximum measured wear indication from foreign objects returned to service is 33%TW. None of the foreign object wear indications that were left in service were found to have a PLP present that would represent a continued mechanism for wear on the tube. As such, growth on these indications is assumed to be zero over the next inspection interval.
Therefore, by virtue of meeting CM, OA is met for three cycles for foreign object wear.
The operational assessment for stress corrosion mechanisms was determined probabilistically. Below are the results:
Degradation Cycles Number of POB POL 90/50 LR flaws (%) (%) (gpm)
Axial ODSCC at TSP 3 2 3.339 3.246 0.009 Circumferential PWSCC 3 1 N/A 0 0 within tubesheet Axial ODSCC in freespan 3 3 1.069 0.061 0
- e. The number and percentage of tubes plugged [or repaired] to date, and the effective plugging percentage in each SG.
See report ADAMS accession number ML21214A160.
- f. The results of any SG secondary side inspections.
See report ADAMS accession number ML21214A160.
Approximately 8000 pounds of iron is contained in the four steam generators by iron transport at EOC-24.
- g. For Unit 2, the primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign leakage to an individual SG, the entire primary to secondary LEAKAGE should be conservatively assumed to be during the cycle preceding the inspection which is the subject of the report.
See report ADAMS accession number ML21214A160.
- h. For Unit 2, the calculated accident leakage rate from the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident leakage rate from the most limiting accident is less than 3.27 primary to secondary leakage rate, the report shall describe how it was determined: and
It was previously reported (ADAMS accession number ML21214A160) that there was no calculated leakage. Upon start up Catawba unit 2 was power limited. To return the unit to full power the unit will raise Tave and therefore Thot by ~2 degrees F. At the elevated Thot of 619 degrees F, no leakage is calculated for the first two cycles 25 and 26; leakage is only projected for the last cycle 27. The leakage was determined probabilistically using Westinghouses Full Bundle Model software. The leakage for the last cycle was projected to be 0.009 gpm. The new administrative limit was calculated as follows:
= 0.10417 / 3.27 - 0.009 = 0.02286 = 32.9
- i. For Unit 2, the results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.
See report ADAMS accession number ML21214A160.
Figure 1 - Catawba Unit 2 Elevation Map AV 2 AV 3 AV 1 AV 4 Westinghouse Model D5 Tube Information:
Number of tubes: 4578 Flush 08H 09C Tube Material: Alloy 600 TT Nominal Diameter: 0.750 Nominal Wall: 0.040 49 rows and 114 columns Tube Support Information:
07H 10C TSP Type: quatrefoil broached FDB Type: drilled round hole PB type: drilled round hole Material: ferritic SS AVB Information:
06H 11C AVB Type: Square Material: Chrome Plated Inconel 05H 12C 04H 13C 14C 15C 03H 16C 02H 17C 18C 01H 19C TSH TSC TEH TEC}}