Letter Sequence Request |
---|
|
|
MONTHYEARML12121A6382012-04-30030 April 2012 Response to Nuclear Regulatory Commission Standard Steam Generator Questions for Oconee Unit 3 Project stage: Request ML12178A2062012-06-28028 June 2012 Summary of Conference Call Regarding the Spring 2012 Steam Generator Tube Inspection Results, Oconee Nuclear Station, Unit 3 Project stage: Other 2012-04-30
[Table View] |
|
---|
Category:- No Document Type Applies
MONTHYEARML22112A0062022-04-20020 April 2022 (Public Version) Oconee SLRA - Final RCI 3.5.2.2.2.6-L ML21323A1152021-11-23023 November 2021 Subsequent License Renewal Environmental Review Requests for Additional and Subsequent Information - Enclosure ML18060A0282018-02-28028 February 2018 Noncurrence Process - Alternative to Codes and Standards ML16055A1882016-01-15015 January 2016 FOIA/PA-2016-0071 - Resp 3 - Interim, Continuing to Process Request. Part 2 of 2 ML16055A1872016-01-15015 January 2016 FOIA/PA-2016-0071 - Resp 3 - Interim, Continuing to Process Request. Part 1 of 2 ML15224A7792015-08-0707 August 2015 FOIA/PA-2015-0393 - Resp 2 - Final, Part 1 of 1 ML15162A0842015-06-11011 June 2015 GTCC Disposals at the Barnwell Low-Level Radioactive Waste Facility from 1998 to Present ML14135A4082014-05-0707 May 2014 FOIA/PA-2013-0213 - Resp 3 - Final, Group Letter D. Part 1 of 1 ML14058A0822014-02-0404 February 2014 Questions and Answers Related to the Oconee External Flooding Issue ML14058A0522014-02-0404 February 2014 Use of FERC Inundation Calculation Parameters ML14058A0502014-02-0404 February 2014 Questions and Answers Related to Oconee Flood Barrier ML14058A0492014-02-0404 February 2014 Site Adequate Protection Backfit Documented Evaluation ML14058A0212014-02-0404 February 2014 Request for Opinion on the Safe Shutdown Facility Added to the License Basis for the Oconee Units in an SER ML14058A0202014-02-0404 February 2014 Nancy Ssf Flooding URI Number 1 ML14058A0192014-02-0404 February 2014 TIA, Answers to Questions in Relation to Licensing Basis for Flooding for the Safe Shutdown Facility at Oconee Station ML14058A0152014-02-0404 February 2014 Site Adequate Protection Backfit Documented Evaluation ML14049A2872013-08-28028 August 2013 Meeting Feedback Form Meeting No. 20140354 ML16070A2882013-04-24024 April 2013 Jocassee and Keowee Dams, Breach Parameter Review, Dated April 24, 2013 (Redacted) ML13240A0162013-03-0606 March 2013 Report, Enclosure Oconee Nuclear Station Flooding Hazard Reevaluation Report ML13052A7852013-02-26026 February 2013 Flood Licensing Basis Evaluation Open Items ML13056A1052013-02-0606 February 2013 Comparison of Approaches for Calculating a Jocassee Dam Failure Frequency ML13052A7802013-02-0606 February 2013 Options for Revising Oconee Flood CAL Due Dates ML13052A7812013-02-0606 February 2013 Timeline - Summary of Events ML13052A7832013-02-0606 February 2013 Draft NRC Information Notice on Dam Failure Frequency in Probabilistic Risk Assessments ML13052A7872013-02-0606 February 2013 Justification for Continued Operation of Oconee Nuclear Station ML13056A1002013-02-0606 February 2013 Resolution of Oconee Flooding Issue ML13052A7862013-02-0606 February 2013 Jocassee Dame Failure Frequency Components ML12121A6382012-04-30030 April 2012 Response to Nuclear Regulatory Commission Standard Steam Generator Questions for Oconee Unit 3 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12003A0632011-12-16016 December 2011 Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 2 of 6 ML12003A0672011-12-16016 December 2011 Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 4 of 6 ML12003A0682011-12-16016 December 2011 Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 5 of 6 ML12003A0692011-12-16016 December 2011 Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 6 of 6 ML1131406132011-11-0101 November 2011 Enclosure 3 - Regulatory Enforcement Conference - Resubmittal of Supplement ML11279A2532011-10-0606 October 2011 NRC Pre-submittal Meeting - Proposed Tornado Mitigation Flowchart Revision 6 Oconee Nuclear Station, Units 1, 2, and 3 ML11279A2522011-10-0606 October 2011 NRC Pre-submittal Meeting- Proposed Turbine Building HELB Mitigation Flow Chart Revision 5 Oconee Nuclear Station, Units 1, 2, and 3 ML1101907492011-01-18018 January 2011 Enclosure 3 - List of Attendees ML1035103792010-12-17017 December 2010 NFPA 805 Transition Pilot Plant FAQ 08-0054, Revision 1 ML1026404582010-09-13013 September 2010 Enclosure 2 - Redacted Version of Request for Additional Information Re the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) ML1035100122010-08-19019 August 2010 NRC Staff Response to NFPA 805 Transition Pilot Plant FAQ 08-0054, Revision 0 (Updated) ML1023705812010-08-19019 August 2010 NFPA 805 Transition Pilot Plant FAQ 08-0054 ML1019301982010-06-0909 June 2010 Onsite Ground/Surface Water Monitoring Questionnaire for Oconee Nuclear Station ML14058A0612010-04-13013 April 2010 Draft Oconee Nuclear Site Adequate Protection Backfit Documented Evaluation ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML1019305442010-02-0808 February 2010 Ground Water Communication Supplemental Information Questions and Answers ML1100606662009-10-0909 October 2009 Photographs of Ssf Asw Leak and Piping Replacement Project Taken Between August 20, 2009 and October 9, 2009, by Oconee Resident Inspectors. Part 2 of 14 ML0927103442009-09-25025 September 2009 Site Visit Observation on 09/25/2009 by Joel Munday for Oconee ML1100404352009-09-15015 September 2009 Plant Issue Tracking Application; Plant Status Daily - Oconee Information for 09/15/2009 ML1100309332009-07-13013 July 2009 Congressional Staff Briefing: Monday July 13, 2009, 3:30 Pm, Room 2108 Rayburn Bldg; Topic: Follow-Up Questions Regarding Chairman'S June 17, 2009 Response Regarding a IP2 Buried Pipe Leak ML0909004332009-04-0606 April 2009 Enclosure 2 - Oconee Nuclear Station Regulatory Audit - Documents Reviewed 2022-04-20
[Table view] |
Text
Response to NRC Standard Steam Generator Questions For Oconee Unit 3 EOC26 April 2012
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
Duke Response:
No leakage has been observed
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
Duke Response:
No secondary side pressure tests were performed.
- 3. Discuss any exceptions taken to the industry guidelines.
Duke Response:
An exception has been taken to the examination guidelines to use single pass analysis versus dual pass analysis.
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
Duke Response The scope of the inspection is as follows:
- 1. 100 % bobbin full length
- 2. Special Interest with array probe
- a. All bobbin indications 35% TW
- b. All bobbin indications at the 7th TSP down to the LTE 20% TW
- c. All indications regardless of size at the drilled holes at the 14th TSP
- d. All ADI, DSI, DWI, NQI, PLP and HIS codes other than wear
- 3. Five tubes deep around the periphery with the array first TSP to LTS
- 4. Plus Point on ADIs
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed ENCLOSURE
circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
Duke Response:
Tube to Tube Wear SG 3A SG 3B Indication 58(86) 32(43)
Location 7th to 8th span 58 32 Length Max (inches) 9.0 8.3 Length Min (inches) 1.0 3.2 Length Avg (inches) 5 6.1 Max Depth (%TW) 20 17 Average Depth 11 11 Number of Wear Indications 50% TW 0 0 Number of Wear Indications 40% TW < 50% TW 0 0 Number of Wear Indications 30% TW < 40% TW 0 0 Number of Wear Indications 20% TW < 30% TW 12(1) 1 Number of Wear Indications 10% TW < 20% TW 46(85) 31(43)
Average Growth Rate per EFPY 0.3 -0.9 95th Percentile Growth Rate per EFPY 2.3 0 Maximum Growth Rate per EFPY 4.3 2.9 The indications are generally located in the center of the bundle.
( ) = Array data Tube support plate wear SG 3A SG 3B Number of Tubes Inspected with Bobbin 15621 15648
% of Tubes Inspected with Bobbin 100% 100%
Number of Wear Indications 14824 6821 Number of Tubes with Wear Indications 8248 4724
% of Tubes Inspected with Wear Indications 53% 30%
Average Wear Depth 8% 8%
Maximum Wear Depth 39% 46%
Number of Wear Indications 50% TW 0 0 Number of Wear Indications 40% TW < 50% TW 0 2 Number of Wear Indications 30% TW < 40% TW 49 24 Number of Wear Indications 20% TW < 30% TW 398 163 EFPY 1.39 1.39 Average Growth Rate per EFPY 0.3% 0.8%
95th Percentile Growth Rate per EFPY 2.9% 3.6%
Maximum Growth Rate per EFPY 12.9% 21.6%
- 6. Describe repair/plugging plans.
Duke Response:
There are no tubes requiring plugging in A ROTSG. Two tubes are to be plugged and stabilized in B ROTSG for wear at tube support plate locations 40% TW.
- 7. Describe in-situ pressure tests and tube pull plans and results (as applicable and if available).
Duke Response:
No in-situ pressure tests were performed and no tube pulls are planned
- 8. Discuss the following regarding loose parts:
- 1. what inspections are performed to detect loose parts
- 2. a description of any loose parts detected and their location within the SG (including
- 3. the source or nature of the loose part, if known)
- 4. if the loose parts were removed from the SG
- 5. indications of tube damage associated with the loose parts Duke Response:
Two loose parts were detected visually. Bounding with the array was performed. PLPs were identified at the top of tubesheet. No degradation was detected. They are located interior to the bundle in a low flow area.
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc).
Duke Response:
The scope of the secondary side inspection is as follow (contingent up on getting to the locations):
- 1. Top of tubesheet - Annulus, five tubes deep and interior of the bundle (selected rows only), bottom and top of orifice plate in both ROTSGs
- 2. General tube conditions (deposit loading, deposit characteristics and blockage) and Structural assessment of the various features at the 9th TSP, 10th TSP, and 11th TSP and in A ROTSG.
Small amounts of sludge coupled with corrosion product flakes were noted at the TTS in A ROTSG. Two foreign objects were found, one being on the 11th support plate and a second on the top of tube sheet, but well within the bundle in A ROTSG. No other issues have been noted. B ROTSG lower tubesheet inspection is pending.
- 10. Discuss any unexpected or unusual results.
Duke Response:
There were no unexpected or unusual results.
- 11. Provide the schedule for steam generator-related activities during the remainder of the current outage.
Duke Response:
- 1) Complete secondary side visual inspections
- 2) Perform retrieval of foreign objects
- 3) Perform tube plugging and stabilization