Letter Sequence Draft RAI |
---|
|
|
MONTHYEARML15072A4472015-03-13013 March 2015 E-mail Re. Accepted for Review of License Amendment Request to Adopt Emergency Action Level Scheme Project stage: Approval ML15272A4262015-09-29029 September 2015 NRR E-mail Capture - Draft RAI on Proposed Amendment Re. EAL Scheme Change Project stage: Draft RAI ML15274A0042015-09-30030 September 2015 NRR E-mail Capture - Summary of the 9/29/15 Conference Call on the Proposed Brunswick EAL Scheme Change Amendment Project stage: Other ML15350A0962015-11-23023 November 2015 Response to Request for Additional Information Re Adoption of Emergency Action Level Scheme Per NEI 99-01, Rev. 6 Project stage: Response to RAI ML15303A3962015-12-0808 December 2015 Safety Evaluation Input on Emergency Action Level Scheme Upgrade for Brunswick Steam Electric Plant Units 1 and 2 (TAC No'S. MF5766 and MF5767 Project stage: Approval 2015-03-13
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML23248A2612023-09-0505 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) 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 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 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 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2023-09-05
[Table view] |
Text
1 NRR-PMDAPEm Resource From: Tam, Peter Sent: Tuesday, September 29, 2015 10:21 AM To: michael.braden@duke-energy.com Cc: Hon, Andrew; Johnson, Don; Helton, Shana
Subject:
Draft RAI on proposed amendment re. EAL scheme change (TAC MF5766, MF5767)
Michael:
By letter dated January 30, 2015, Duke Energy Progress, Inc. (Duke Energy) requested approval for an amendment changing the emergency action level (EAL) scheme for Brunswick Steam Electric Plant (BSEP), Units 1 and 2, to one based upon Revision 6 to Nuclear Energy Institute (NEI) document NEI 99-01, "Development of Emergency Action Levels for Non-Passive Reactors." We are continuing our review of the licensee's application. Meanwhile, we found that additional information, as described in the draft questions below, is needed to complete our review of the application. We propose to discuss each one of these draft questions, including the disposition of each draft question, with your staff in a conference call.
This email will be entered into ADAMS as an official agency record. Your January 30, 2015 application is a publicly available document; thus, we assume that the draft questions below, which are based on the submittal, contains no sensitive unclassified non-safeguards information (SUNSI). However, we will delay release of this email for 7 days. If we do not hear any request from you within 7 days to withhold any part of this email, we will release it for public disclosure.
cxxÜ fA gtÅ Senior Project Manager Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RAI-01 Section 4.3, "Instrumentation Used for EALs," to NEI 99-01, Revision 6, states in part, "Scheme developers should ensure that specific values used as EAL setpoints are within the calibrated range of the referenced instrumentation." Please confirm that all setpoints and indications used in the proposed EAL scheme are within the calibrated range(s) of the stated instrumentation and that the resolution of the instrumentation is appropriate for the setpoint/indication.
RAI-02 Section 2.1, "Background," and Section 4.0, "Ref erences," use ADAMS Accession Number ML110240324 as the document the NRC endorsed when in fact it is M L12326A805, which is part of the endorsement package contained within ML13091A209. Please revise to refer ence either one of these ADAMS numbers as the NRC endorsed EAL scheme development guidance
RAI-03 Section 2.5, "Technical Bases Information," states, "A Plant-specific basis section that provides BNP [BSNP]-relevant information concerning the EAL. This is followed by a Generic basis section that provides a description of the rationale for the EAL as provided in NEI 99-01 Rev. 6." Due to the high probability that EAL decision-makers will be confused between these two sections when the information appears to be inconsistent, please explain the basis for two sections rather than one basis section that is specific to the plant, or revise accordingly.
2 RAI-04 Section 5.0, "Definitions," does not include definitions for the following. Please incorporate these definitions into the document or provide justification for not including definitions consistent with NRC endorsed guidance:
- Notification of Unusual Event,
- Emergency Classification Level,
- Fission Product Barrier Threshold, and
RAI-05 For the following EALs, please explain why the listed NOTEs were included, or revise accordingly.
- RG1.2 - NOTE-3 RAI-06 For EAL RA2.2, please explain why the information in the NEI 99-01 Basis section does not contain all of the actual information from NEI 99-01 as it is germane to this particular EAL, or revise accordingly.
RAI-07 For EAL RS2.1, please explain why the escalation path apparently incorrectly lists EAL AG1 instead of EAL RG1, or revise accordingly.
RAI-08 For EALs CU2.1, SA1.1 and SU1.1, please add a list of the AC power sources to the EAL to ensure consistent and timely recognition of the event, or provide justification for not including this list. [NOTE: It is not necessary to have this list for EALs CA2.1, SG1.1, SG1.2, and SS1.1 as these EALs are concerned with a loss of all AC power sources.]
RAI-09 For EAL CG1.2 and the Fission Barrier Matrix, please confirm that the "Max Normal" and "Max Safe" values can be promptly obtained from within the Control Room, or revise accordingly to support timely event declaration.
RAI-10 For EALs CU4.1, SG1.2 and SS2.1, please explain the impact on timely event declaration, since the BNP Basis states that battery voltage must be read locally.
RAI-11 For EALs CU5.1 and SU7.1, please explain how the Corporate Telephone Communications System can work for in-plant/onsite communications, or revise accordingly.
RAI-12 For EAL HU2.1, please provide additional details on the process used to determine if the seismic activity exceeded the Operating Basis Earthquake (OBE) threshold and availability to support timely event declaration. If the OBE threshold is not recognized, in a timely fashion, from indications in or near the Control Room, then explain why the alternative EAL was not developed in accordance with NEI 99-01 Revision 6, or revise accordingly.
RAI-13 For EAL HU3.2, the proposed basis information includes the statement: "Refer to Updated FSAR section 3.4.2, Protection from Internal Flooding, to identify susceptible internal flooding areas." If the intent of this statement 3is to limit the areas of consideration, then provide a list of areas in the EAL for the staff to review, or otherwise explain the purpose for this statement.
RAI-14 For EAL HU3.4, please explain where the BSNP Basis information related to when the 15-minute clock starts came from.
RAI-15 For EALs HU4.1 and HU4.2, the areas listed in Table H-1 seem to be vague or too all-encompassing. Please explain if the listed areas are all the areas that contain equipment needed for safe operation, safe shutdown and safe cool-down, and if these areas can be fine-tuned to limit consideration for these EALs.
RAI-16 For EAL HU4.2, please explain why all the required information related to Appendix R was not carried over into this EAL, or revise accordingly.
RAI-17 For EALs HU4.2 and HU4.4, please confirm that the Independent Spent Fuel Storage Installation (ISFSI) would be an area applicable to these EALs, or revise accordingly.
RAI-18 For EAL HS6.1, please explain why reactivity control is not required at the Remote Shutdown Panel, or revise accordingly. In addition, please consider incorporating operating mode specificity to the key safety functions listed in the EAL.
RAI-19 For EAL SU4.1, please explain the intent of the 15-minute qualifier, and basis for consideration in this EAL.
RAI-20 For EAL SU4.2, please explain why the timing note is not part of this EAL, or revise accordingly.
RAI-21 For EALs SU6.1, SU6.2, SA6.1 and SS6.1, please explain why the power level (
RAI-22 Category E - Independent Spent Fuel Storage Installation (ISFSI) guidance: The statement:
"Formal offsite planning is not required because the postulated worst-case accident involving an ISFSI has insignificant consequences to the public health and safety," is not applicable to this proposed EAL scheme. Please remove, or provide further justification for inclusion.
In addition, please incorporate guidance related to the fact that EALs HU1 and HA1 are also considered for events that occur at the ISFSI.
RAI-23 Fission Product Barrier Matrix: The cited NEI 99-01 Basis sections for several of the Fission Product Barrier criteria are not from NRC-endorsed NEI 99-01, Revision 6. Please either revise to what has actually been endorsed, or (depending on respond to RAI-03) consider unifying the basis sections into one.
Hearing Identifier: NRR_PMDA Email Number: 2421 Mail Envelope Properties (Peter.Tam@nrc.gov20150929102100)
Subject:
Draft RAI on proposed amendment re. EAL scheme change (TAC MF5766, MF5767) Sent Date: 9/29/2015 10:21:10 AM Received Date: 9/29/2015 10:21:00 AM From: Tam, Peter Created By: Peter.Tam@nrc.gov Recipients: "Hon, Andrew" <Andrew.Hon@nrc.gov> Tracking Status: None "Johnson, Don" <Don.Johnson@nrc.gov> Tracking Status: None "Helton, Shana" <Shana.Helton@nrc.gov> Tracking Status: None "michael.braden@duke-energy.com" <michael.braden@duke-energy.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 8372 9/29/2015 10:21:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: