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Category:Letter type:ONS
MONTHYEARONS-2018-025, 2017 Annual Radiological Environmental Operating Report (AREOR)2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report (AREOR) ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)2018-04-30030 April 2018 2017 Annual Radioactive Effluent Release Report (ARERR) ONS-2018-032, Ufsar/Selected Licensee Commitment Changes2018-04-17017 April 2018 Ufsar/Selected Licensee Commitment Changes ONS-2018-029, Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 32018-04-0404 April 2018 Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3 ONS-2018-027, Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-0022018-03-28028 March 2018 Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-002 ONS-2018-023, Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency2018-03-20020 March 2018 Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency ONS-2018-017, Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan2018-03-15015 March 2018 Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan ONS-2018-021, ISFSI - Submittal of 2017 Annual Effluent Release Report2018-03-0101 March 2018 ISFSI - Submittal of 2017 Annual Effluent Release Report ONS-2018-020, Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2018-02-26026 February 2018 Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes ONS-2018-015, Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cabl2018-02-19019 February 2018 Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cables i ONS-2018-014, License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-012018-02-12012 February 2018 License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-01 ONS-2018-019, Submittal of Emergency Plan, Section B2018-02-0505 February 2018 Submittal of Emergency Plan, Section B ONS-2018-011, Ufsar/Selected Licensee Commitment Changes2018-01-25025 January 2018 Ufsar/Selected Licensee Commitment Changes ONS-2017-087, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2017-12-0404 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ONS-2017-083, Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 02017-11-21021 November 2017 Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 0 ONS-2017-041, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments2017-11-15015 November 2017 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments ONS-2017-085, Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR)2017-11-15015 November 2017 Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR) ONS-2017-079, Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-11-13013 November 2017 Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-078, Emergency Plan Revision 2017-0042017-11-0909 November 2017 Emergency Plan Revision 2017-004 ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 ONS-2017-067, Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 22017-10-16016 October 2017 Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 2 ONS-2017-069, (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement2017-10-13013 October 2017 (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement ONS-2017-070, Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0022017-10-0505 October 2017 Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-002 ONS-2017-072, Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-10-0303 October 2017 Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-066, Registration for Use of General License Spent Fuel Cask Numbers 147 and 1482017-09-20020 September 2017 Registration for Use of General License Spent Fuel Cask Numbers 147 and 148 ONS-2017-061, Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations2017-08-10010 August 2017 Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations ONS-2017-060, Registration for Use of General License Spent Fuel Cask Numbers 145 and 1462017-08-0303 August 2017 Registration for Use of General License Spent Fuel Cask Numbers 145 and 146 ONS-2017-059, Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary2017-07-31031 July 2017 Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 ONS-2017-047, Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 1442017-06-27027 June 2017 Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 144 ONS-2017-042, Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 22017-06-0101 June 2017 Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 2 ONS-2017-040, Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0032017-05-22022 May 2017 Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-003 ONS-2017-037, 2016 Annual Radiological Environmental Operating Report2017-05-15015 May 2017 2016 Annual Radiological Environmental Operating Report ONS-2017-026, Submittal of Ufsar/Selected Licensee Commitment Change2017-04-11011 April 2017 Submittal of Ufsar/Selected Licensee Commitment Change ONS-2017-024, Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program2017-03-16016 March 2017 Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program ONS-2017-001, Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 0452017-03-0202 March 2017 Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 045 ONS-2017-017, Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-001 ONS-2017-018, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-001 ONS-2017-015, End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2017-02-24024 February 2017 End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 ONS-2017-011, Emergency Plan Revised Evaluation2017-02-0202 February 2017 Emergency Plan Revised Evaluation ONS-2017-009, Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events.2017-02-0101 February 2017 Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events. ONS-2017-004, Submittal of Core Operating Limits Report2017-01-12012 January 2017 Submittal of Core Operating Limits Report ONS-2017-006, Emergency Plan Revision 2016-0032017-01-12012 January 2017 Emergency Plan Revision 2016-003 ONS-2016-097, Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S)2016-11-17017 November 2016 Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S) ONS-2016-098, Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors2016-11-14014 November 2016 Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors ONS-2016-096, Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations2016-11-10010 November 2016 Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations 2018-05-15
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARRA-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023 Reply to a Notice of Violation (NOV) 05000270/2023010-02 RA-21-0019, Reply to a Notice of Violation; EA-2021-0042021-02-19019 February 2021 Reply to a Notice of Violation; EA-2021-004 ONS-2015-015, Revised Reply to a Notice of Violation; EA-14-0912015-02-19019 February 2015 Revised Reply to a Notice of Violation; EA-14-091 ML12080A1482012-02-27027 February 2012 Reply to a Notice of Violation Regarding Inspection Report 05000269-11-008, 05000270-11-008, and 05000287-11-008 ML0708607672007-03-15015 March 2007 Reply to a Notice of Violation ML0636200922006-12-20020 December 2006 Appeal of Final Significance Determination for White Finding and Reply to Notice of Violation; EA-06-199 ML0606004172006-02-15015 February 2006 Integrated Inspection Report 05000269/2005004, 05000270/2005004, 05000287/2005004, Unresolved Items 2005004-10 and 2005004-08 ML0430905122004-10-25025 October 2004 Response to Notice of Violation ML0424304192004-08-19019 August 2004 Duke Energy Corporation, Oconee Nuclear Station, Units 1, 2, and 3, Reply to Notice of Violation - EA 04-018 (Supplemental Information) ML0302401232003-01-10010 January 2003 Response to NRC Preliminary White Finding 2023-08-17
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DUKE Scott L. Batson Vice President Oconee NuclearStation Duke Energy ONO1VP 17800 Rochester Hwy Seneca, SC 29672 o: 864.873.3274 ONS-2015-015 10 CFR 2.201 f 864.873.4208 Scott.Batson@duke-energy.com February 19, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station, Unit 1 Docket No. 50-269 Revised Reply to a Notice of Violation; EA-14-091
References:
- 1. Letter from Victor M. McCree (NRC) to Scott Batson (Duke Energy), Oconee Nuclear Station - Final Significance Determination of White Finding, Notice of Violation and Assessment Follow-up Letter (NRC Inspection Report No.
05000269/2014012),. dated August 12, 2014 (ML14224A629)
- 2. Letter from Scott Batson (Duke Energy) to NRC, Reply to a Notice of Violation; EA-14-091, dated September 11, 2014 In a letter dated August 12, 2014 (Reference 1), the Nuclear Regulatory Commission (NRC) provided Duke Energy with the final significance determination for a White finding and an associated Notice of Violation, EA-14-091. The Nuclear Regulatory Commission (NRC) letter provides final results of the significance determination of the preliminary Greater than Green finding identified in NRC Inspection Report 05000269/2014011, dated June 26, 2014 (ML14177A333). The report identifies a violation of 10 CFR 50, Appendix B, Criterion XVI, Corrective Action which involves Oconee Nuclear Station's (ONS) failure to identify and correct a significant condition adverse to quality involving a crack in a weld located in the Unit I High Pressure Injection system. In response, Duke Energy provided the reply to the Notice of Violation EA-14-091 on September 11, 2014 (Reference 2), in accordance with 10 CFR 2.201, "Notice of Violation."
This letter provides an amended reply to Notice of Violation EA-14-091 that includes revised causal information and corrective actions resulting from completion of the associated root cause analysis. Due to the nature of the changes, Duke Energy has determined that a revision to the September 11, 2014, reply to the Notice of Violation is warranted. The attachment to this letter provides Duke Energy's revised reply to Notice of Violation EA-14-091. This revised reply supersedes the previous reply to the Notice of Violation provided in Reference 2.
www.duke-energy.com
U.S. Nuclear Regulatory Commission February 19, 2015 Page 2 There are no regulatory commitments contained in this submittal. Any questions regarding the content of this report should be directed to Chris Wasik, Oconee Nuclear Station Regulatory Affairs Manager, at 864-873-5789.
Sincerely, Scott L. Batson Site Vice President Oconee Nuclear Station Attachment
U.S. Nuclear Regulatory Commission February 19, 2015 Page 3 cc w/
Attachment:
Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. James R. Hall Senior Project Manager (by electronic mail only)
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2746 Mr. Jeffrey Whited Project Manager (by electronic mail only)
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike Mail Stop 0-8 BlA Rockville, MD 20852-2746 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Ms. Susan E. Jenkins Manager, Infectious and Radioactive Waste Management Division of Waste Management South Carolina Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201
Oconee Nuclear Station Revised Reply to Notice of Violation EA-14-091 Attachment NRC Violation:
10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, states, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and non-conformances are promptly identified and corrected. In the case of significant conditions adverse to quality (SCAQ), the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.
Contrary to the above, prior to November 11, 2013, the licensee failed to establish measures to promptly identify and correct a significant condition adverse to quality involving a circumferential crack in weld 1-RC-201-105 located on the Unit 1 High Pressure Injection (HPI) piping-to-cold leg nozzle safe end interface of the 1B2 reactor coolant pump suction pipe, which resulted in non-isolable pressure boundary leakage while the reactor was in Mode 1. Specifically, in 2004, the licensee implemented procedure, NDE [Non-Destructive Examination] -995, "Ultrasonic Examination of Small Diameter Piping Butt Welds and Base Material for Thermal Fatigue Damage," to perform augmented in-service inspection program ultrasonic examinations which did not provide measures to assure that HPI nozzle component cracking would be identified and corrected. Consequently, in 2012, the licensee performed procedure NDE-995 on weld 1-RC-201-105, and did not identify any reportable indications; even though the > 50%
through wall circumferential crack was present in the weld. The presence of the crack was confirmed after a re-review of a radiographic film obtained during a non-destructive test of the 1B2 thermal sleeve in 2011. On November 11, 2013, the licensee identified the through-wall circumferential crack in weld 1-RC 201-105 after transitioning Unit 1 to Mode 3 to investigate non-isolable pressure boundary leakage.
This violation is associated with a White significance determination process finding.
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Oconee Nuclear Station Revised Reply to Notice of Violation EA-14-091 Oconee Nuclear Station (ONS) Response to the Notice of Violation:
(1) the reason for the violation Duke Energy acknowledges this violation. This violation was attributed to an unisolable reactor coolant system leak on the 1B2 HPI line. On November 8, 2013, the ONS Unit 1 control room received indications of potential reactor coolant system (RCS) leakage in the Unit 1 reactor building. On November 10, 2013, following initial indication of RCS leakage in the vicinity of 1HP-1 52, Operations initiated power reduction to 20% full power. On November 11, 2013, a reactor building entry determined RCS pressure boundary leakage from 1 B2 High Pressure Injection (HPI) nozzle or piping. A shutdown to Mode 5 was initiated in accordance with Tech Spec 3.4.13, Operational Leakage.
The leak was from a circumferential crack in the safe end-to-pipe butt weld (1-RC-201-105) located between the 1B2 HPI injection nozzle and valve 1HP-152. The total circumferential extent of the aggregate crack was about 1.2" on the pipe inside diameter and about 0.1" on the outside surface.
An internal investigation was conducted by Duke Energy to evaluate the cause of both the weld failure and Duke Energy's failure to identify the crack before it became through-wall. Mechanical, high-cycle fatigue caused a through-wall crack in the butt weld between the safe end and HPI pipe. The crack in the HPI safe end-to-pipe butt weld developed when the system vibration exceeded material fatigue endurance limits causing the crack initiation from the weld root. Duke Energy's investigation also determined that ownership and oversight of the augmented examination program was inadequate, as was guidance to the examiners for actions to be taken when full weld volume coverage could not be achieved.
(2) the corrective steps that have been taken and the results achieved, Upon identification of the RCS leak, ONS Unit 1 was shut down for initial investigation and the weld repairs. On November 19, 2013, the leaking weld was replaced.
Post-repair Radiographic Testing was completed November 23, 2013. Additional actions include the following:
- 1. Remaining ONS HPI safe end-to-pipe butt welds for Units 1 and 2 have been re-inspected using diverse techniques, (e.g., PDI-UT-2, which calls for a different UT beam angle to be used than that recommended in previously used procedure NDE-995, Phased Array UT, RT [Radiography Testing], and PT [Penetrant Testing]).
Similar welds on Unit 3 were inspected during Spring 2014 using the revised NDE-995 procedure. No rejectable weld indications requiring repair were identified.
- 2. Other welds inspected using NDE-995, "Ultrasonic Examination of Small Diameter Piping Butt Welds and Base Material for Thermal Fatigue Damage," were reviewed for those that resulted in limited coverage. These welds were inspected using PDI-UT-2 or by reviewing RT data, with no indications identified.
- 3. Welds were re-examined using the enhanced NDE-995 procedure in refueling outages since this event. During the thermal fatigue extent of condition examinations, rejectable indications were detected in the extrados of the 1 B2 Cold Page 2 of 3
Oconee Nuclear Station Revised Reply to Notice of Violation EA-14-091 Leg Drain elbow. The 1 B2 drain line elbow and adjacent butt weld developed cracking due to turbulent penetration thermal transient effects. The elbow was replaced.
- 4. Vibration data was evaluated for the HPI system on all three ONS units. Based on this review, the relatively high vibrations observed for the HPI lines during the Full Flow test appeared to be largest for the "B2" lines on all three units, with the 1 B2 line having the highest reported acceleration values of all 12 HPI Lines. Vibration levels were within acceptable limits, but the frequency of the ISI augmented examination (UT) was increased to every refueling outage (1 R) for Al and B2 HPI safe end-to-pipe butt welds on each unit (six total). These HPI lines have the highest vibration stresses.
- 5. Procedure NDE-995, "Ultrasonic Examination of Small Diameter Piping Butt Welds and Base Material for Thermal Fatigue Damage," was revised to incorporate the root cause lessons learned regarding application of appropriate probes and technology.
The procedure now includes guidance that weld crowns must be reduced to allow UT probes to traverse without loss of signal, specifies higher angle probes for one-sided examinations, and requires pre/post job briefs and brief content.
- 6. NDE procedures were revised to provide prescriptive guidance for maximizing examination coverage when performing augmented examinations, including entry into the corrective action program for evaluation by functional owner when limitations or indications of degradation are detected.
- 7. NDE procedure for Level III oversight of routine NDE examination activities was revised to utilize a "graded approach" relative to the significance of the NDE examination activity and operating experience.
(3) the corrective steps that will be taken, and Duke Energy will separate the Augmented Inspection portion of the ISI program from the ASME Section Xl portion so that the Augmented Inspection portion can function as an independent Engineering Program. This change is being tracked to completion in the corrective action program.
(4) the date when full compliance will be achieved.
Although additional actions as described above are ongoing, full compliance has been achieved. The 1B2 weld was repaired November 19, 2013, and post-repair RT was successfully completed on November 23, 2013. NDE-995 was revised. Comprehensive actions have been taken to prevent recurrence.
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