|
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm Resource From:Hall, Randy Sent:Wednesday, August 31, 2016 3:56 PM To:Wasik, Christopher J (Christ opher.Wasik@duke-energy.com) | | {{#Wiki_filter:1 NRR-PMDAPEm Resource From:Hall, Randy Sent: Wednesday, August 31, 2016 3:56 PM To: Wasik, Christopher J (Christ opher.Wasik@duke-energy.com) |
| Cc:Newman, Stephen (Stephen | | Cc:Newman, Stephen (Stephen.Newman@duke-energy.com) |
| .Newman@duke-energy.com) | |
|
| |
|
| ==Subject:== | | ==Subject:== |
Line 43: |
Line 42: |
| Sincerely, | | Sincerely, |
|
| |
|
| 2James R. (Randy) Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov
| | 2 James R. (Randy) Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov |
|
| |
|
| Hearing Identifier: NRR_PMDA Email Number: 3030 Mail Envelope Properties (Randy.Hall@nrc.gov20160831155600) | | Hearing Identifier: NRR_PMDA Email Number: 3030 Mail Envelope Properties (Randy.Hall@nrc.gov20160831155600) |
Letter Sequence Acceptance Review |
---|
|
|
MONTHYEARML16209A2232016-07-21021 July 2016 Amendment Request to Add the Copernic Fuel Performance Code to Technical Specifications 2.1.1.1, Reactor Core Safety Limits, and 5.6.5, Core Operating Limits Report (COLR) Project stage: Other ML16250A0282016-08-31031 August 2016 NRR E-mail Capture - Oconee Nuclear Station, Units 1, 2 and 3 - Acceptance for Review of License Amendment Request to Add Copernic Fuel Performance Code to TS Project stage: Acceptance Review ML17103A5092017-05-11011 May 2017 Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code Project stage: Approval 2016-08-31
[Table View] |
|
---|
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
1 NRR-PMDAPEm Resource From:Hall, Randy Sent: Wednesday, August 31, 2016 3:56 PM To: Wasik, Christopher J (Christ opher.Wasik@duke-energy.com)
Cc:Newman, Stephen (Stephen.Newman@duke-energy.com)
Subject:
Oconee Nuclear Station, Units 1, 2 and 3 - Acceptance for Review of License Amendment Request to Add COPERNIC Fu el Performance Code to TS (CAC Nos.
MF8158, MF8159, and MF8160)August 31, 2016 Mr. Christopher J. Wasik Manager, Regulatory Affairs Oconee Nuclear Station
Duke Energy Carolinas, LLC
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - ACCEPTANCE FOR REVIEW OF LICENSE AMENDMENT REQUEST TO ADD COPERNIC FUEL PERFORMANCE CODE TO TS (CAC NOS. MF8158, MF8159, AND MF8160)
Chris:
By letter dated July 21, 2016 (ADAMS Accession No. ML16209A223
), Duke Energy (the licensee) submitted a license amendment request for the Oconee Nuclear Station (ONS), Units 1, 2, and 3. The proposed amendment would add the COPERNIC Fuel Performance Code to Technical Specifications 2.1.1.1 and 5.6.5.
In accordance with NRC's process as described in LIC-109, "Acceptance Review Procedures," the NRC staff has performed an acceptance review of the amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-4032.
Sincerely,
2 James R. (Randy) Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 3030 Mail Envelope Properties (Randy.Hall@nrc.gov20160831155600)
Subject:
Oconee Nuclear Station, Units 1, 2 and 3 - Acceptance for Review of License Amendment Request to Add COPERNIC Fuel Performance Code to TS (CAC Nos. MF8158, MF8159, and MF8160)
Sent Date: 8/31/2016 3:56:22 PM Received Date: 8/31/2016 3:56:00 PM From: Hall, Randy Created By: Randy.Hall@nrc.gov
Recipients: "Newman, Stephen (Stephen.Newman@duke-energy.com)" <Stephen.Newman@duke-energy.com> Tracking Status: None "Wasik, Christopher J (Christopher.Wasik@duke-energy.com)" <Christopher.Wasik@duke-energy.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 2936 8/31/2016 3:56:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: