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Category:E-Mail
MONTHYEARGO2-25-021, NRR E-mail Capture - (External Sender) Energy Northwest Columbia Generating Station 2024 Priority Pollutant Discharge Monitoring Annual Report2025-01-15015 January 2025 NRR E-mail Capture - (External_Sender) Energy Northwest Columbia Generating Station 2024 Priority Pollutant Discharge Monitoring Annual Report ML25003A1752024-12-30030 December 2024 Relief Request 73- Proposed Alternative for Pressurizer Lower Shell Temperature Nozzle Life of Repair ML24354A2012024-12-18018 December 2024 PVNGS EP Exercise Inspection March 2025 RFI ML24348A0902024-12-12012 December 2024 NRR E-mail Capture - Columbia Generating Station - Acceptance of Requested Licensing Action - Relief Request for Alternative 5ISI-03 for Fifth Interval ML24348A0892024-12-12012 December 2024 NRR E-mail Capture - Columbia Generating Station - Acceptance of Requested Licensing Action - Relief Request for Alternative 5ISI-04 for Fifth Interval ML24331A1762024-11-21021 November 2024 Acceptance Review of Palo Verde Valve Relief Request (VRR) - 03 ML24326A2002024-11-20020 November 2024 Acceptance Review of Palo Verde Valve Relief Request (VRR) - 02 ML24319A0382024-11-13013 November 2024 February 2025 Emergency Preparedness Program Inspection - Request for Information ML24297A6212024-10-22022 October 2024 Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300 ML24296B1852024-10-16016 October 2024 NRR E-mail Capture - Final - Request for Additional Information - Columbia - Relief Request for Fourth Ten-Year Interval Inservice Testing - EPID: L-2024-LLR-0039 ML24291A1072024-10-16016 October 2024 NRR E-mail Capture - LIC-109 Acceptance Review - Columbia Generating Station - Application to Revise TS to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements - EPID L-2024-LLA-0132 ML24267A2172024-09-23023 September 2024 (E-Mail) Palo Verde Nuclear Generating Station Units 1, 2, and 3 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24257A1012024-09-11011 September 2024 Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components ML24248A2632024-09-0404 September 2024 Acceptance Review of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Relief Request (RR) No. 71: Re?Submittal of RR?30 ML24242A2812024-08-26026 August 2024 RR72 Acceptance 08/27/24 - La Jr ML24221A2382024-08-0606 August 2024 Change in Estimated Review Schedule and Level of Effort for Palo Verde Units 1, 2, and 3 ML24215A3672024-08-0101 August 2024 NRR E-mail Capture - Final Request for Additional Information - Columbia Generating Station - License Amendment Request to Revise Emergency Plan - EPID L-2024-LLA-0011 ML24183A2392024-07-0101 July 2024 NRR E-mail Capture - LIC-109 Acceptance - Columbia Generating Station - Relief Request for the Fourth Ten-Year Interval Inservice Testing - EPID L-2024-LLR-0039 ML24169A0402024-06-14014 June 2024 NRR E-mail Capture - Final Request for Additional Information - Columbia Generating Station (Columbia) - Relief Requests for the Fifth Ten-Year Interval Inservice Testing - EPIDs (L-2024-LLR-007 Through 0013) ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24138A1112024-05-16016 May 2024 Draft 2nd Round Request for Additional Information (Rais) Concerning License Amendment Request (LAR) to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2 ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24120A2612024-05-0101 May 2024 Email Acceptance Review of Requested Licensing Action License Renewal Commitment 23A, Alloy 600 Management Program Plan ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24103A1222024-04-11011 April 2024 – Acceptance of Requested Licensing Action Re_ License Amendment Request to Revise Technical Specifications 3 ML24103A2022024-04-0909 April 2024 EN 57068 - Transco Products Inc Part 21 Initial Notification of Unverified Critical Characteristics of Darmatt KM-1 Flat Board ML24060A1022024-02-28028 February 2024 NRR E-mail Capture - (External_Sender) Energy Northwest Columbia Generating Station 2023 Biological Monitoring Report ML24053A0092024-02-21021 February 2024 NRR E-mail Capture - Columbia Generating Station - LIC-109 Acceptance of Relief Requests for the Fifth Ten-Year Interval Inservice Testing - EPIDs L-2024-LLR-0007 Through 00013 ML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML24008A0022024-01-0505 January 2024 NRR E-mail Capture - Columbia Generating Station - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation - EPID L-2023-LLA-0170 ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23278A0042023-10-0404 October 2023 NRR E-mail Capture - LIC-109 Acceptance Review of LAR for Columbia - Application to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling - EPID L-2023-LLA-0128 ML23275A0092023-09-29029 September 2023 NRR E-mail Capture - LIC-109 Acceptance Review of LAR for Columbia - Application to Revise Tech Specs to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling - EPID: L-2023-LLA-0128 ML23243B0082023-08-31031 August 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23233A0132023-08-18018 August 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23220A0512023-08-0303 August 2023 NRR E-mail Capture - Re Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 22 ML23202A0162023-07-20020 July 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Revise TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23150A2502023-05-26026 May 2023 NRR E-mail Capture - LIC-109 Acceptance Review of LAR for Columbia Generating Station - License Amendment Request to Clean-Up Operating License and Appendix a, Technical Specifications - EPID L-2023-LLA-0062 ML23143A1332023-05-23023 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Revising TS 3.3.11 to Adopt TSTF-266-A, Rev. 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls ML23130A0132023-05-10010 May 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Authorized Use of Mururoa Supplied Air Suits (Models V4F1 and MTH2) Pursuant to 10 CFR 20.1703 and 10 CFR 20.1705 ML23124A2412023-05-0404 May 2023 NRR E-mail Capture - LIC-109 Acceptance Review of LAR for Columbia - Application to Revise TS to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position - EPID L-2023-LLA-0063 ML23124A0062023-05-0303 May 2023 NRR E-mail Capture - LIC-109 Acceptance Review of LAR for Columbia Generating Station - Application to Revise Tech Specs to Adopt TSTF-541, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling - EPID L-2023-LLA-0063 ML23065A0422023-02-23023 February 2023 NRR E-mail Capture - (External_Sender) Energy Northwest Columbia Generating Station 2022 Biological Monitoring Report ML23017A0932023-01-17017 January 2023 NRR E-mail Capture - Palo Verde - Acceptance of License Amendment Request Regarding Adoption of TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable (L-2022-LLA-0181) ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22343A1802022-12-0808 December 2022 February 2023 Emergency Preparedness Program Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 – Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing 2025-01-15
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Text
From:
Parks, Benjamin To:
Dixon-Herrity, Jennifer Cc:
Lukes, Robert; Smith, Ashley; Chawla, Mahesh; Tsao, John; DSS_AA Distribution
Subject:
log id 1977 Concurrence on SE input for Columbia PLTR LAR Date:
Friday, June 17, 2022 4:23:15 PM Attachments:
image001.png
- Jennifer,
By letter dated October 13, 2021, (Agencywide Documents and Access Management System (ADAMS) Accession No. ML21299A182), Energy Northwest (the licensee) requested to revise Technical Specification (TS) 3.4.11, Reactor Coolant System Pressure and Temperature (P/T) Limits, at the Columbia Generating Station (CGS). The proposed amendment request will replace the existing P/T curves in TS 3.4.11 with updated/revised P/T curves that are projected to the end of the period of extended operation. In addition, the licensee provided the revised P/T curves to satisfy the license renewal commitment Number 54 in Table A-1 of Appendix A to NUREG-2123 "Safety Evaluation Report Related to the License Renewal of Columbia Generating Station," which the Nuclear Regulatory Commission (NRC) published in May 2012 (ADAMS Accession Nos. ML12139A300 and ML12139A302).
The Nuclear Methods and Fuel Analysis Branch staff reviewed the reactor vessel neutron fluence estimates supporting the proposed change and determined that it is acceptable.
The safety evaluation input provides the basis for the Nuclear Methods and Fuel Analysis Branch staff determination, and appears below. I have reviewed the safety evaluation and found that it contains sound regulatory and technical bases. The Nuclear Methods and Fuel Analysis Branch staff provided me concurrence on the safety evaluation and this e-mail constitutes my concurrence on the safety evaluation.
In accordance with U.S. Nuclear Regulatory Commission policy, the Nuclear Methods and Fuel Analysis Branch staff did not identify any sensitive information contained in the below.
- Thanks, Ben Parks, Acting Branch Chief
3.2 Licensees Neutron Fluence Calculations
The proposed P-T limits are based on the application of the GE Hitachi Licensing Topical Report, NEDC-33178P-A (Reference 1), a generic methodology that has been approved for use by the NRC staff for generating P-T limits based on the plant-specific adjusted reference temperatures (ARTs). Implementation of the GE Hitachi Licensing Topical
Report, NEDC-33178P-A is documented in the proposed Columbia PTLR, which was included as Enclosures 5 (NEDO-33929, non-proprietary) and 7 (NEC-33929, proprietary) of the licensees October 13, 2021, submittal. Updated fluence values are provided in Section 3.2 of NEDO-33929, and Section 3.0 of Enclosure 1 to the licensees submittal states that the fluence projections were performed using the methods described in NEDC-32983P-A, which has also been approved for use by the NRC staff (Reference 2).
In March 2001, the NRC staff issued RG 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, which provides methods for determining RPV fluence (ML010890301). Fluence calculations are acceptable if they are performed with NRC-approved methods or with methods which are otherwise shown to conform with the guidance in RG 1.190, consistent with the General Design Criteria (GDCs) in Title 10, Energy, of the U.S. Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criteria for the Design of Nuclear Power Plants, specifically, GDCs 14, 30 and 31.
4.1 Neutron Fluence Evaluation
As noted above, the licensee submitted updated fluence calculations for Columbia in its LAR. The licensee updated the fluence calculations using an NRC-approved methodology documented in the GE Hitachi Licensing Topical Report, NEDC-32983P-A (Reference 2).
The NRC staff safety evaluation for NEDC-32983P-A indicates that the method is approved for use for boiling water reactors, such as Columbia, based on its adherence to RG 1.190.
The licensee appropriately projected fluence values supporting the proposed P-T limits to 54 EFPY.
Based on its review, the NRC staff concludes that the information provided assures that the proposed P-T limits are based on acceptable fluence inputs because the fluence calculational methodology has been approved for use by the NRC staff for facilities like Columbia, and it adheres to the guidance in RG 1.190. Therefore, the NRC staff finds that the fluence estimates described in Enclosures 5 and 7 of the LAR are acceptable for use with respect to the proposed P-T limits based on the predicted 54 EFPY exposure period.
References
- 1. GEH Nuclear Energy, NEDC-33178P-A, Revision 1, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves", dated June 2009 (ADAMS Accession No. ML092370487)
- 2. GE-Hitachi Nuclear Energy Topical Report NEDC-32983P-A, Revision 2, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations, dated January 2006 (ADAMS Accession No. ML072480121)
Docket No.: 50-397
Contact:
Ashley Smith, NRR/DSS/SFNB 301-415-3201