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| | issue date = 12/05/2013 | | | issue date = 12/05/2013 |
| | title = 12/5/13 E-mail from R.Guzman to B.Shingleton - Follow-up RAI to Pressure Temperature Curve LAR Supplement 3, Oconee Nuclear Station Units 1, 2, and 3 (TAC Nos. MF0763/64/65) | | | title = 12/5/13 E-mail from R.Guzman to B.Shingleton - Follow-up RAI to Pressure Temperature Curve LAR Supplement 3, Oconee Nuclear Station Units 1, 2, and 3 (TAC Nos. MF0763/64/65) |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Newman S C, Shingleton B | | | addressee name = Newman S, Shingleton B |
| | addressee affiliation = Duke Energy Carolinas, LLC | | | addressee affiliation = Duke Energy Carolinas, LLC |
| | docket = 05000269, 05000270, 05000287 | | | docket = 05000269, 05000270, 05000287 |
| | license number = | | | license number = |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = TAC MF0763, TAC MF0764, TAC MF0765 | | | case reference number = TAC MF0763, TAC MF0764, TAC MF0765 |
| | document type = E-Mail | | | document type = E-Mail |
| | page count = 2 | | | page count = 2 |
| | | project = TAC:MF0763, TAC:MF0764, TAC:MF0765 |
| | | stage = RAI |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:From: Guzman, Richard Sent: Thursday, December 05, 2013 4:33 PM To: 'Newman, Stephen'; Shingleton, Boyd |
| | |
| | ==Subject:== |
| | RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals |
| | : Boyd, As we discussed, based on his preliminary review of the 11/29/13 supplemental response, the technical reviewer has determined that the information regarding the upper-shelf energy evaluation for the RPV lower head is not complete. Below is a description of the follow-on information request. We can support a teleconference to discuss in more detail if needed. |
| | The November 29, 2013, upper-shelf energy (USE) evaluation for the RPV lower head materials having fluences greater than 1017 n/cm2 is incomplete. The licensee states that only USE decreases. Without referencing the initial USE values for the RPV lower head materials, it is not known whether or not the USE at 54 EFPY (considering USE decreases) will be above 50 ft-lbs. |
| | The technical reviewer notes that there are two options to consider if the initial USE values associated with the lower head materials cannot be located: (1) using generic initial USE values applicable to Oconee RPV lower heads, or (2) using the equivalent margins analysis of ASME Code, Section XI, Appendix K, supplemented by RG 1.161, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 ft-lb. We can also discuss these approaches, if applicable, during the teleconference call. |
| | : Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030 From: Newman, Stephen [mailto:Stephen.Newman@duke-energy.com] |
| | Sent: Friday, November 29, 2013 5:05 AM To: Guzman, Richard Cc: Wasik, Christopher J; Shingleton, Boyd; Severance, Sandra N |
| | |
| | ==Subject:== |
| | Oconee Nuclear Station _ NRC Commitment and RAI Submittals |
| | : Richard, Please find attached two submittals associated with a reactor vessels internals inspection program LAR commitment and a PT Limit Curve LAR RAI. Both letters are dated 11/29/13. Please let me know that you received them intact. |
| | Best Regards, |
| | |
| | Stephen C. Newman Sr. Engineer, Regulatory Affairs Oconee Nuclear Station (864) 873-4388}} |
Letter Sequence RAI |
|---|
|
|
MONTHYEARML13058A0592013-02-22022 February 2013
Licesne Amendment Request to Update Pressure-Temperature Limit Curves No. 2012-10
Project stage: Other
ML13165A1472013-06-21021 June 2013
Request for Additional Information Regarding Amendment Application Related to Reactor Coolant System Pressure and Temperature Limit Curves
Project stage: RAI
ML13259A1202013-09-10010 September 2013
Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 1
Project stage: Supplement
ONS-2013-016, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 22013-10-25025 October 2013
Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 2
Project stage: Supplement
ML13322B2762013-11-14014 November 2013
11/14/13 e-mail from B.Shingleton to R.Guzman PT Curves LAR Supplement 2 - ONS Unit 3 Lower Nozzle Belt Forging Reported in ANP-3127, Revision 2
Project stage: Supplement
ML13305A1222013-11-25025 November 2013
Enclosure 3 - Areva Document No. 32-9212003-000, Lst Considering RCS Piping and RVCH Limit for B&W Plant Designs, September 2012
Project stage: Request
ONS-2013-023, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 32013-11-29029 November 2013
Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 3
Project stage: Supplement
ML13342A0022013-12-0505 December 2013
12/5/13 E-mail from R.Guzman to B.Shingleton - Follow-up RAI to Pressure Temperature Curve LAR Supplement 3, Oconee Nuclear Station Units 1, 2, and 3 (TAC Nos. MF0763/64/65)
Project stage: RAI
ML13350A0982013-12-16016 December 2013
E-mail from B.Shingleton to R.Guzman Clarification of Upper Shelf Energy Values for ONS Pressure-Temperature Curve 54 EFPY LAR
Project stage: Other
ML14028A4822014-01-31031 January 2014
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML14041A0932014-02-27027 February 2014
Issuance of Amendments Regarding Revised Pressure-Temperature Limits
Project stage: Approval
2013-12-05
[Table View] |
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Category:E-Mail
MONTHYEARML24257A0212024-09-11011 September 2024
Document Request for Oconee Nuclear Station - Radiation Protection Inspection - Inspection Report 2024-04
ML24234A2972024-08-21021 August 2024
August 21, 2024 - Oconee Nuclear Station, Units 1, 2, and 3 - Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.7.7
ML24211A0872024-07-27027 July 2024
EN 57079 Paragon Energy Solutions Final - No Active Links
ML24197A2292024-07-15015 July 2024
Email from Mark Yoo (NRC) to Steve Snider (Duke) - Oconee SLRA - RAI - 2024 Annual Update
ML24190A0462024-07-0505 July 2024
Notification of Inspection and Request for Information
ML24179A1292024-06-24024 June 2024
Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1
ML24143A1322024-05-22022 May 2024
May 22, 2024, Verbal Authorization for Duke Energy Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI (RA-24-0152) (EPID L- 2024-LLR-0034)
ML24127A0892024-05-0202 May 2024
57079-EN57079-1 - Redline Strikethrough e-mail Re Part 21 Interim Notification of Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker
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
ML24086A3772024-03-26026 March 2024
Request for Additional Information License Amendment Request to Revise Technical Specification 5.5.2
ML24036A1442024-02-27027 February 2024
NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Oconee Nuclear Station, Units 1, 2, and 3, Proposed Subsequent License Renewal in Oconee County, South Carolina (Consultation Code: 2023-0054989)
ML24054A0492024-02-21021 February 2024
Notification of Oconee Nuclear Station FEI Inspection and Information Request-Email
ML23349A0272023-12-15015 December 2023
– Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 5.5.2
ML23284A3322023-10-11011 October 2023
Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060)
ML23270B8362023-09-26026 September 2023
Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards
ML23267A0032023-09-21021 September 2023
RP Inspection Document Request
ML23269A0412023-08-22022 August 2023
Code Case N-752 Audit; August 22, 2023, E-mail Providing Additional Information Regarding Design and Quality Program Requirements
ML23172A0132023-06-20020 June 2023
Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies
ML23153A1892023-06-0202 June 2023
Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies
ML23151A3482023-05-30030 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23144A0862023-05-24024 May 2023
Acceptance of Requested Licensing Action Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853
ML23142A2732023-05-22022 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23125A1452023-05-0505 May 2023
Change in Estimated Review Schedule and Level of Effort for Proposed Alternative to Use Code Case N-752
ML23124A1212023-05-0404 May 2023
Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23095A0052023-04-0404 April 2023
002 Radiation Safety Baseline Inspection Information Request
ML23086C0362023-03-27027 March 2023
Request for Additional Information Steam Generator Tube Inspection Report (03R31)
ML23073A2282023-03-13013 March 2023
Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review
ML23058A0562023-02-27027 February 2023
Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation
ML23048A1512023-02-16016 February 2023
Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003)
ML23038A1832023-02-0707 February 2023
Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752
ML23031A1552023-01-17017 January 2023
1/17/2023 Email from John Moses, Deputy Director, Division of Rulemaking, Environmental, and Financial Support, to Diane Curran, Counsel to Beyond Nuclear and the Sierra Club, Request for Extension of Scoping Comment Period for Oconee EIS
ML22294A0812022-10-21021 October 2022
Nrc/Duke Steam Generator Inspection Call for November 8, 2022
NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022
EN 55999 Valcor Coil Shell Assemblies Final Notification (004)
ML22251A2902022-09-0808 September 2022
Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9
ML22235A6552022-08-23023 August 2022
Acceptance of Requested Licensing Action Proposed Alternative to Use ASME Code Case N-752
NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022
EN 55999 - Valcor Engineering Corporation (009)
ML22234A1262022-07-0808 July 2022
Email from NRC to Duke - Feedback on Trp 76 RAI Responses - July 8, 2022
ML22234A1272022-06-14014 June 2022
Email from NRC to Duke - Feedback on Trp 76 RAI Responses - June 14, 2022
ML22154A2142022-06-0101 June 2022
Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - 2nd Round RAI B2.1.7-4b
ML22157A0012022-06-0101 June 2022
Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a
ML22124A2052022-05-0404 May 2022
Summary of May 4, 2022, Clarification Call with Duke Energy Carolinas, LLC, Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System
ML22124A1612022-05-0303 May 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a
ML22122A0192022-04-28028 April 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a
ML22122A1322022-04-27027 April 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round Requests for Additional Information (FE 3.5.2.2.2.6 - Irradiation Structural)
ML22115A1412022-04-25025 April 2022
NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information
ML22130A0112022-04-25025 April 2022
Email: Oconee SLRA - RAI 4.6.1-1a - NRC Staff Comments
ML22112A1892022-04-22022 April 2022
Acceptance Review for Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9
ML22113A0082022-04-20020 April 2022
Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Additional Information 3.1.2-1
ML22112A0072022-04-20020 April 2022
Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L
ML22088A0452022-03-28028 March 2022
Radiation Safety Baseline Inspection Initial Information Request Inspection Report 2022002
2024-09-11
[Table view] |
Text
From: Guzman, Richard Sent: Thursday, December 05, 2013 4:33 PM To: 'Newman, Stephen'; Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Boyd, As we discussed, based on his preliminary review of the 11/29/13 supplemental response, the technical reviewer has determined that the information regarding the upper-shelf energy evaluation for the RPV lower head is not complete. Below is a description of the follow-on information request. We can support a teleconference to discuss in more detail if needed.
The November 29, 2013, upper-shelf energy (USE) evaluation for the RPV lower head materials having fluences greater than 1017 n/cm2 is incomplete. The licensee states that only USE decreases. Without referencing the initial USE values for the RPV lower head materials, it is not known whether or not the USE at 54 EFPY (considering USE decreases) will be above 50 ft-lbs.
The technical reviewer notes that there are two options to consider if the initial USE values associated with the lower head materials cannot be located: (1) using generic initial USE values applicable to Oconee RPV lower heads, or (2) using the equivalent margins analysis of ASME Code,Section XI, Appendix K, supplemented by RG 1.161, Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 ft-lb. We can also discuss these approaches, if applicable, during the teleconference call.
- Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030 From: Newman, Stephen [1]
Sent: Friday, November 29, 2013 5:05 AM To: Guzman, Richard Cc: Wasik, Christopher J; Shingleton, Boyd; Severance, Sandra N
Subject:
Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Richard, Please find attached two submittals associated with a reactor vessels internals inspection program LAR commitment and a PT Limit Curve LAR RAI. Both letters are dated 11/29/13. Please let me know that you received them intact.
Best Regards,
Stephen C. Newman Sr. Engineer, Regulatory Affairs Oconee Nuclear Station (864) 873-4388
