Letter Sequence Other |
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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
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Category:E-Mail
MONTHYEARML23349A0272023-12-15015 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
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
ML22113A0082022-04-20020 April 2022
Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Additional Information 3.1.2-1
ML22088A0452022-03-28028 March 2022
Radiation Safety Baseline Inspection Initial Information Request Inspection Report 2022002
ML22081A0052022-03-21021 March 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3
ML22080A0792022-03-16016 March 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 4 (2nd Round Rais)
ML22075A2032022-03-11011 March 2022
Email from Duke to NRC - Follow-Up Items from March 7, 2022 Public Meeting
ML22074A0022022-03-11011 March 2022
Email from Duke to NRC - Follow-up Item from March 7, 2022 Public Meeting - SSW Tendon AMP
ML22069A0022022-03-0808 March 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Confirmation of Information - Set 4
ML22063A4502022-03-0404 March 2022
Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump
ML22063A1152022-02-23023 February 2022
Email from Duke to NRC - Follow Up Item from February 17, 2022 Public Meeting
ML22038A1572022-02-0707 February 2022
NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2
ML22035A1892022-01-31031 January 2022
Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Request for Public Meeting
ML22018A0272022-01-18018 January 2022
2022 All RFI Responses - Exercise and Program Inspections - Revl
ML22019A1032022-01-18018 January 2022
Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3
ML22012A0432022-01-11011 January 2022
SLRA - Requests for Additional Information - Set 2
2023-09-26
[Table view] |
Text
From: Shingleton, Boyd To: Guzman, Richard Cc: Wasik, Christopher J
Subject:
ONS 54 EFPY PT Curve LAR - additonal information.
Date: Monday, December 16, 2013 9:18:36 AM Attachments: Response for NRC on Unirrad USE Values-ONS RPV Lower Regions.pdf
- Rich, Information requested by the NRC staff attached.
Boyd Shingleton ONS Regulatory Affairs 864-873-4716 From: Guzman, Richard [1]
Sent: Wednesday, December 11, 2013 8:28 AM To: Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Boyd, Just to clarify my previous messagethe specific information that the staff is requesting is the initial USE and the 54 EFPY USE for the RPV lower head materials having fluences greater than 1017 n/cm 2.
- Thanks, Rich From: Shingleton, Boyd [2]
Sent: Wednesday, December 11, 2013 7:50 AM To: Guzman, Richard
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals OK Boyd Shingleton ONS Regulatory Affairs 864-873-4716 From: Guzman, Richard [3]
Sent: Wednesday, December 11, 2013 7:43 AM To: Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Boyd, A call is not necessary. You can provide me the initial USE value based on material reports for the RPV lower head materials having fluences greater than 1017 n/cm 2 - via
email is fine. Please confirm the value is non-proprietary and I can then add the associated email response to ADAMS as an official agency record; the reviewer can then reference it in the staffs SE.
- Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030 From: Shingleton, Boyd [4]
Sent: Tuesday, December 10, 2013 3:50 PM To: Guzman, Richard
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Rich, Talked to AREVA. The USE at 54 EFPY will be above 50 ft-lbs. They did not use Options 1 and 2 (described below), they used the material report. Lets set up a call with the reviewer and confirm we are not missing the point. Also, need to determine whether the response will need to be docketed.
Boyd Shingleton ONS Regulatory Affairs 864-873-4716 From: Guzman, Richard [5]
Sent: Thursday, December 05, 2013 4:33 PM To: Newman, Stephen; Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- This is an EXTERNAL email. Exercise caution. DO NOT open attachments or click links from unknown senders or unexpected email. ***
- 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/cm 2 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 [6]
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
NRC email information request received by Duke Energy:
Further clarification Boyd Shingleton ONS Regulatory Affairs 8648734716 From: Guzman, Richard [7]
Sent: Wednesday, December 11, 2013 8:28 AM To: Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Boyd, Just to clarify my previous messagethe specific information that the staff is requesting is the initial USE and the 54 EFPY USE for the RPV lower head materials having fluences greater than 1017 n/cm2.
- Thanks, Rich From: Shingleton, Boyd [8]
Sent: Wednesday, December 11, 2013 7:50 AM To: Guzman, Richard
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals OK Boyd Shingleton ONS Regulatory Affairs 8648734716 From: Guzman, Richard [9]
Sent: Wednesday, December 11, 2013 7:43 AM To: Shingleton, Boyd
Subject:
RE: Oconee Nuclear Station _ NRC Commitment and RAI Submittals
- Boyd, A call is not necessary. You can provide me the initial USE value based on material reports for the RPV lower head materials having fluences greater than 1017 n/cm2 - via email is fine. Please confirm the value is non-proprietary and I can then add the associated email response to ADAMS as an official agency record; the reviewer can then reference it in the staffs SE.
- Thanks, Rich Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030
Response
In response to the NRC email above sent to Duke Energy, the following Tables with the unirradiated CvUSE values and the 54 EFPY CvUSE per Regulatory Guide 1.99 Revision 2 for the Oconee Nuclear Stations (ONS) RPV lower region materials having fluences greater than 1017 n/cm2 are provided. The information is considered non-proprietary.
ONS-1 Non-Traditional Beltline RPV Material CvUSE Values Unirradiated Method for CvUSE at CvUSE Determining 54 EFPY Non-Traditional Beltline RPV Materials (ft-lbs) CvUSE (ft-lbs)
Dutchman Forging 58.5 Measured (65% 53.5 Long. CVN data)*
Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 53.8 ONS-2 Non-Traditional Beltline RPV Material CvUSE Values Unirradiated Method for CvUSE at CvUSE Determining 54 EFPY Non-Traditional Beltline RPV Materials (ft-lbs) CvUSE (ft-lbs)
Dutchman Forging 67.3 Measured (65% 61.5 Long. CVN data)*
Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 52.3 ONS-3 Non-Traditional Beltline RPV Material CvUSE Values Unirradiated Method for CvUSE at CvUSE Determining 54 EFPY Non-Traditional Beltline RPV Materials (ft-lbs) CvUSE (ft-lbs)
Dutchman Forging 59.2 Measured (65% 51.3 Long. CVN data)*
Lower Shell to Dutchman Forging Circ. Weld 64 Generic** 55.6
- Data taken from actual RPV material test report where limited CVN test data were performed at a single test temperature to confirm that at least 30 ft-lbs was obtained for the material. CVN test data does not represent the impact energy upper-shelf (i.e., >95% shear), a mean value taken at a reduced percent shear fracture is a conservative estimate of the CvUSE in that the impact energy will increase as the percent shear fracture increases.
- Charpy impact test data not available; conservative generic value for that class of material is used. The class of material is determined for base metals by the material specification and for weld metal by the type of welding flux (i.e., Linde 80 or others).
