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MONTHYEARML0922504672009-08-0707 August 2009 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 08-ON-002 Request for Additional Information Response Project stage: Request ML0934106362009-12-0202 December 2009 Request for Additional Information Response Request for Relief No. 08-ON-002 Project stage: Request ML1013800672010-05-13013 May 2010 Fourth Ten Year Inservice Interval Request for Relief No. 08-ON-002 Request for Resumption of Review Project stage: Request ML1023200102010-08-20020 August 2010 Relief Request 08-ON-002 for Limited Weld Examinations Project stage: Other 2009-08-07
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MONTHYEARIR 05000269/20243012024-09-23023 September 2024 NRC Operator License Examination Report 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency ML24220A1092024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 2024-09-23
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Duke DAVE BAXTER Vice President Oconee Nuclear Station Duke Energy ONQI VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 864-873-4208 fax dabaxter@dukeenergy.
com December 2, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 3 Docket No: 50-287 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 08-ON-002 Request for Additional Information Response By letter dated December 29, '2008 (ML090050027), Duke Energy Carolinas, LLC (Duke) submitted Request for Relief No. 08-ON-002 seeking relief, pursuant to 10 CFR 50.55a(g)(5)(iii), from the requirement to examine 100% of the volume specified by the ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition with 2000 Addenda (as modified by Code Case N-460).The relief would allow Duke Energy to take credit for two (2) limited ultrasonic examinations on welds associated with various systems and components described in the request.On July 15, 2009, Duke received a request for additional information (RAI) and submitted a response dated August 7, 2009 (ML092250467).
Subsequently, via additional e-mails dated August 25, 2009, September 23, 2009, and September 29, 2009, and a teleconference on September 10, 2009, Duke received additional questions, some new and some clarifying the original questions.
The following enclosure contains the reviewer's questions, and Duke's responses to each.If there are any questions or further information is needed you may contact Randy Todd at (864) 873-3418.www. duke-energy.
comr U. S. Nuclear Regulatory Commission December 2, 2009 Page 2 Sincerely, Dave Ba er, Site Vice President Enclosure xc w/att: Luis Reyes Region II Administrator U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SWW, Suite 23T85 Atlanta, GA 30303 John Stang Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 xc (w/o attch): Andrew Sabisch Senior NRC Resident Inspector Oconee Nuclear Station Susan Jenkins, Section Manager Division of Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.Columbia, SC 29201 Request for Additional Information Relief Request 08-ON-002 Limited Weld Examination Coverage Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 3 Docket No. 50-287 By letter dated December 29, 2008, Duke Energy Carolinas, LLC (the licensee)submitted relief request 08-ON-002 for Nuclear Regulatory Commission review and approval.
On July 15, 2009 Duke received a request for additional information (RAI)and submitted a response dated August 7, 2009. Subsequently, via additional e-mails dated August 25, 2009, September 23, 2009, and September 29, 2009, and a teleconference on September 10, 2009, Duke received additional questions, some new and some clarifying the original questions.
The following enclosure contains the reviewer's questions, and Duke's responses to each.For the weld 3HP-365-9C:
- 1. Please clarify the discrepancies in regard to the shear wave examinations in the circumferential directions, between the text in your response to question No. 2 of the supplement dated August 7, 2009, and the contents of the Table on page 11 of Attachment A, including the contents of page 5 of Attachment A of the letter dated December 29, 2008. It is not clear why the Table on page 11 of Attachment A indicates scanning in only one circumferential direction for shear wave examinations, but then claims 100% volume coverage.Response: The table listing "Clockwise pipe side" and "Counter clockwise tee side" is a typo.The entries should read "Clockwise pipe and tee side" and "Counter clockwise pipe and tee side".2. Please clarify the discrepancies in regard to the content of the Table on page 11 of Attachment A, for 600 <i.e. 60 degree> shear wave examinations in the axial direction from the tee side and the pipe side, specifically the contents of "Weld Length Scanned," and "Percent of Volume Covered." Inconsistencies in the contents of the Table on page 11 of Attachment A are as follow: a) For the pipe side, it is not clear how 14.1-inches is recorded for "Weld Length Scanned" while you state in page 8 of Attachment A that only 10.1-inches plus 50% (i.e.2.0-inches) of the obstructed weld length is scanned. Also, by the same token, how 71.6+14.2 is recorded for "Percent of Volume Covered" while the recorded value for"Weld Length Scanned" is 14.1-inches.
Response: From the pipe side, the total weld length of 14.1" was scanned. Of this, 10.1" of the scan obtained 100% coverage.
The 10.1" represents 71.6% of the total weld length of 14.1" (10.1"/14.1" x 100 = 71.6%).Scanning of the remaining 4.0" obtained 50% coverage.
The 4.0" represents 28.4% of the total weld length of 14.1" (4.0"/14.1" x 100 = 28.4%). The 50%coverage in this weld length resulted in 14.2% coverage (28.4% x 50% = 14.2%).Therefore the total percent of coverage from the pipe side obtained was 85.8%(71.6% + 14.2%) from the pipe side.b) For the tee side scan, it is not clear how 100% is recorded for the "Percent of Volume Covered" while the recorded value for "Weld Length Scanned" is 10.1-inches.
Response: The 10.1" weld length scanned from the tee side obtained 100% coverage.The 100% coverage listed only applies to the scanned weld length of 10.1".The remaining 4.0" received no scan due to the tee configuration.
Therefore the 100% coverage obtained in the 10.1" of weld length results in a total coverage of 71.6% coverage (10.1 "114.1 " x 100= 76.1%) from the tee side.For the Weld 3LP-1 34-103: 3. Clarification of contents of Table titled "Limitation Summary for Weld 3LP-1 34-103 (C05.011.004)," on page-1 0/11 of Attachment-A, specifically the contents of columns titled '"Weld Length Scanned (in.)," "Percent of Volume Covered," and "Percent of Coverage Claimed," for the 60-degree shear and the 45-degree shear. Clarification on the computation of the "Aggregate" percentage.
Response: The component inspected is a 10.75 OD reducer welded to a valve. The total circumference of this weld is 33.77" as shown under "Weld Length Scanned (in.)" for one 60-degree axial scan (S2) and two 45-degree circumferential scans, clockwise and counterclockwise.
There was no axial scan performed from the valve side (S1)."However, the 0% coverage obtained is factored into the total aggregate coverage.
Therefore the aggregate coverage was calculated as follows: (S1) 0% + (S2) 50% + (CW) 50% + (CCW) 50% = 150%150%/4 = 37.5% Total aggregate coverage.
The table is correct.
Reaardina the Dates of Exams Reported: 4. RR 08-ON-002 reported on page 4 a date of May of 2006 for a VT-2 exam. The date reported on page 5 of Attachment A for UT Pipe Weld Exam was Feb 2006. Why was there 4-months difference?
Didn't Oconee perform both examinations during the 2006 outage? Had 2006-Outage taken for 4-months?Response: VT2 examinations (pressure tests) are conducted on a different frequency and (frequently) under different operating conditions from the NDE (UT, RT, etc.)exams. Therefore they are treated as separate activities and are scheduled/performed at different times. In accordance with Subsubarticle IWA 6230 of Section XI, an Inservice Inspection Report is submitted following each refueling outage and provides information on inspections and repair/replacement activities completed since the prior outage. In a similar manner, while RR 08-ON-002 nominally addressed inspections performed during the Unit 3 End of Cycle 22 (3EOC22) refueling outage, as noted on page 1 of 7, it actually addressed inspections performed during the time interval addressed by the 3EOC22 Inservice Inspection Report (submitted August 31, 2006, see ML062480197).
In the specific cases of the exams referenced in the question, the UT was performed in February, 2006, and the VT-2 exam in May, 2006. The actual dates for 3EOC22 were April 29, 2006 through June 2, 2006.