Letter Sequence RAI |
---|
TAC:ME8135, Control Room Habitability (Approved, Closed) TAC:ME8136, Control Room Habitability (Approved, Closed) |
|
MONTHYEARML12076A0622012-03-0606 March 2012 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report (Colr) and Revision to Technical Specification 2.1.1.2 Project stage: Request ML12107A0662012-04-12012 April 2012 NRR E-mail Capture - Acceptance Review for TACs ME8135/6, Addition of Analytical Methodology TR to TS 5.6.5 and Revision to TS 2.1.1.2 Project stage: Acceptance Review ML12223A1962012-08-0909 August 2012 NRR E-mail Capture - Brunswick Units 1 and 2- RAIs Regarding TSs 2.1.1.2 and 5.6.5 and Revising a License Condition (ME8135 and ME8136) Project stage: RAI ML12251A1422012-08-29029 August 2012 Response to Request for Additional Information Re License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report, & Rev. to Tech Spec 2.1.1.2.. Project stage: Response to RAI BSEP 12-0104, Response to Request for Additional Information Regarding License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report (Colr), and Rev. To..2012-09-21021 September 2012 Response to Request for Additional Information Regarding License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report (Colr), and Rev. To.. Project stage: Response to RAI ML12348A0152012-11-29029 November 2012 Response to Request for Additional Information Re License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report, and Revision to Technical. Project stage: Response to RAI ML12300A3812012-12-0505 December 2012 Request for Withholding Information from Public Disclosure (TAC TAC ME8135 and ME8136) Project stage: Withholding Request Acceptance ML12305A2082012-12-20020 December 2012 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML12305A1982012-12-20020 December 2012 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML13031A0102013-01-22022 January 2013 Supplement to License Amendment Request for Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report (Colr), and Revision to Tech Spec 2.1.1.2 Minimum Critical Power.. Project stage: Supplement ML13023A2242013-02-0404 February 2013 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML13039A2102013-02-11011 February 2013 Letter - Draft SE for Amendments Regarding Addition of Analytical Methodology Topic Reports to TS 5.6.5 and Revision to Minimum Critical Power Ratio Safety Limit Project stage: Draft Approval ML13037A5512013-03-0101 March 2013 Issuance of Amendments Regarding Addition of Analytical Methodology TR to TS 5.6.5 and Revision to TS 2.1.1.2 Project stage: Approval 2012-08-29
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML23248A2612023-09-0505 September 2023 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise the 10 CFR 50.69 Categorization Process ML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) 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) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23006A0642023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML23006A1892023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 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) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21357A0472021-12-23023 December 2021 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Adoption of TSTF-580 ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21200A1582021-07-16016 July 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ML21168A0042021-06-17017 June 2021 Notification of Inspection and Request for Information ML21137A1622021-04-26026 April 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-505 Risk-Informed Completion Time (L-2021-LLA-0060) ML21082A0162021-03-22022 March 2021 Accepted for Review - Brunswick License Amendment Request to Change Tech Spec Limit for Standby Liquid Control System Boron Solution Storage Tank Volume L-2021-LLA-0022 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information Request ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20294A0642020-10-20020 October 2020 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-582 RPV Water Inventory Control Enhancements(L-2020-LLA-0218) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML21033A8562020-08-0505 August 2020 NRR E-mail Capture - Accepted for Review - Brunswick Relief Request for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements EPID-L-2020-LLR-0091 ML20121A1262020-04-29029 April 2020 Radiation Safety Baseline Inspection Information Request ML20111A1212020-04-20020 April 2020 NRR E-mail Capture - Accepted for Review - Brunswick Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior - EPID: L-2020-LLR-0048 ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19252A4572019-09-0808 September 2019 (FEMA Email 09-08-19) Tentative Notification of Brunswick Preliminary Capability Assessment Results ML19252A4092019-09-0606 September 2019 (E-mail to FEMA 09-06-19) FEMA Notification for Planned Restart of Brunswick Units 1 and 2 ML19219A2132019-08-0707 August 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Amendment Requests to Relocate the TSs Staff Qualification Requirements to the Duke Energy Corporation QAPD ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19162A3912019-06-11011 June 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Relief Request (19-GO-001) Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19162A3902019-06-11011 June 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Fourth 10-Year Inservice Inspection Interval ISI-12 ML19092A1152019-04-0101 April 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirements for Safety Relief Valves (L-2019-LLA-0043) ML19092A1142019-04-0101 April 2019 NRR E-mail Capture - Brunswick Plant, Unit 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify TS 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (L-2019-LLA-0031) ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2024-09-04
[Table view] |
Text
1NRR-PMDAPEm ResourceFrom:Saba, FaridehSent:Thursday, August 09, 2012 5:31 PMTo:Murray, William R. (Bill)Subject:Brunswick Units 1 and 2- RAIs Regarding TSs 2.1.1.2 and 5.6.5 and revising a license condition (ME8135 and ME8136)Attachments:ME8135-6-BSEP RAIs _SNPB.docxImportance:High By letter dated March 6, 2012 (Agencywide Documents Access and Management System Accession No. ML12076A062), Progress Energy (the licensee) submitted a license amendment request to (1) revise Technical Specification (TS) 5.6.5 to replace AREVA Topical Report (TR) ANF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors" with AREVA TR ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," (2) revise TS 2.1.1, "Reactor Core SLs [Safety Limits]" by updating the SL minimum critical power ratios (SLMCPR) per TR ANP-10307PA, and (3) revise the license condition in Appendix B, "Additional Conditions," of the operating licenses regarding an alternate method for evaluating SLMCPR values. In the course of the review, the NRC staff determined that additional information was necessary in order to complete its review. The first set of the NRC's staff's request for additional information (RAIs) were emailed to Mr. Turkal on July 30, 2012. During a conference call on 08/09/12, these RAIs were discussed with the licensee to have a better understanding of the NRC staff's questions. Questions 1, 2 and 4 from first set of RAIs remains the same. However, Question 4 is revised as follows: Provide information to demonstrate that the channel bow database is specifically applicable to Brunswick predicted core operating conditions. (Enclosure 1, Page 5, Last Paragraph). To review your responses to these RAIs, please provide your responses by August 30, 2012, as it was requested in the July 30th email.
The NRC second set of RAIs are attached to this email. Please let me know if you have any questions or comments regarding these RAIs by 08/16/12. Also, I would like to discuss with you a due date for providing responses to these RAIs. Thanks,
Farideh Farideh E. Saba, P.E.
Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV Hearing Identifier: NRR_PMDA Email Number: 439 Mail Envelope Properties (Farideh.Saba@nrc.gov20120809173000)
Subject:
Brunswick Units 1 and 2- RAIs Regarding TSs 2.1.1.2 and 5.6.5 and revising a license condition (ME8135 and ME8136) Sent Date: 8/9/2012 5:30:52 PM Received Date: 8/9/2012 5:30:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients: "Murray, William R. (Bill)" <Bill.Murray2@pgnmail.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 2032 8/9/2012 5:30:00 PM ME8135-6-BSEP RAIs _SNPB.docx 23234
Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received:
Enclosure
REQUEST FOR ADDITIONAL INFORMATION BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 ADDITION OF ANALYTIC METHODOLOGY TOPICAL REPORT DOCKET NOS. 50-325 AND 50-324 (TAC NUMBERS ME8135 AND ME8136) Second Set of RAIs 1. Page 6 of the Enclosure 1 states that "The method described in AREVA Operability Assessment CR 2011-2274, Revision 1 to assess SLMCPR values determined using the ANF-524(P)(A) methodology may not always remain appropriate to assess SLMCPR values determined using the ANP-10307PA methodology." Describe briefly the reasons why ANF-524(P)(A) is inappropriate to assess the SLMCPR values determined using ANP-1037PA. 2. Appendices A and B of ANP-10249PA provide details of the development of ACE/ATRIUM-10 correlation and the K-Factor examples, respectively. Provide a summary of the changes in the modified K-factor methodology that was implemented in response to deficiencies found in the axial averaging process. The Staff would like to have the licensee's response similar to what is presented in the Appendices A and B, i.e., changes in analytical treatment.
3. Section 3.0, "Revised Correlation" of ANP-3086(P) indicates that the assumption that the K-factor (k(z)) appearing in equation 3.1 could be replaced by a single axially averaged K-factor value. This assumption was stated to be found inappropriate because of the two reasons, i.e., (1) it allows downstream conditions above the location of dryout to non-physically influence the critical power and (2) it provides equal weighting to all axial locations. Both these assumptions were found to be capable of influencing the predicted results in a non-conservative manner. Describe how the non-conservatism is removed in the modified methodology, by providing a typical analytical treatment and a calculation. 4. ANP-3086(P) indicates that only 80% of the CHF database was used to develop the critical power correlation, according to EMF-2022(P) which is not available to the NRC staff. What criteria, if any, are used for this selection of database? With the remaining 20% of the database unused, is there a loss of accuracy or increase in statistical error/uncertainty in the correlation? 5. Section 3.3 of ANP-3086(P) states that additive constants can be considered as flow/enthalpy redistribution characteristic for given bundle and spacer design. The questions below are with reference to Figure 3-5 of ANP-3036(P): (a) What are the physical significances of positive and negative additive constants? (b) Figure 3-5 lists rod position, ACE/ATRIUM 10XM additive constants and ATRIUM 10XM SLMCPR Operability Assessment Correlation additive constants. The operability assessment correlation additive constants are derived using the improved K-factor
Enclosure
methodology for rods observed to dryout, for rods not observed to dryout and for part length rods. The staff could not find any trend in the change of additive constants from the ATRIUM 10 XM to the new additive constants for the BSEP operability assessment. If there is a trend, please explain. If there is no trend, explain why not. 6. On several locations in ANP-10307PA, it is mentioned that the ACE critical power correlation uses more detailed power distribution than required for previous correlations. Explain what is meant by "detailed power distribution" and how this new detailed power distribution is used to revise the SLMCPR methodology. 7. Apart from using 3D core nodal power distribution (core nodal power) obtained from MICROBURN-B2 code system, what other improvements are implemented through the "expanded coupling with MICROBURN-B2" in the SLMCPR methodology. 8. (a) Should indications of "abnormal channel bow" be experienced by Brunswick nuclear plant Units, describe how the channel bow model will be applied for the SLMCPR methodology as prescribed in ANP-10307P. (b) For a "mixed core" such as BSEP units, what programs could be in place to minimize or prevent abnormal channel bow.
9. The NRC staff is currently reviewing two supplements to AREVA's topical reports for critical power correlations; They are (1) ANP-10249PA, Revision 1, Supplement 1P, Revision 0, "Improved K-factor Model for ACE/ATRIUM-10 Critical Power Correlation," and (2) ANP-10298PA, Revision 0, Supplement 1P Revision 0, "Improved K-factor Model for ACE/ATRIUM 10XM Critical Power Correlation." These supplements to the TRs describe the improved K-factor methodology similar to what is described in ANP-3086P. What is the licensee's plan and schedule to incorporate these supplements into its list of analytical methods for determining core operating limits, if these supplements are approved by the NRC?