Letter Sequence RAI |
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EPID:L-2021-LLA-0231, License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23353A0742023-12-19019 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17 ML23348A3462023-12-14014 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML23268A0292023-09-20020 September 2023 SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23249A2092023-09-0606 September 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) ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4822023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen ML23228A1212023-08-16016 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397 ML23227A2182023-08-15015 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f) ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23172A1122023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23054A3322023-02-23023 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record ML23053A1362023-02-13013 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML23012A2102022-07-26026 July 2022 Letter Submitting Monticello Outline Package ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML22101A0712022-04-11011 April 2022 NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency ML22089A1302022-03-30030 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency ML22082A1812022-03-23023 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28 ML22075A2612022-03-16016 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26 ML22067A2032022-03-0808 March 2022 Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted) ML22011A0642022-01-11011 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection ML22005A3612022-01-0505 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22 ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21330A0382021-11-18018 November 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing ML21286A7882021-10-0606 October 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing ML21256A1892021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves ML21256A1862021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing ML21256A1882021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps ML21253A2002021-09-10010 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing ML21252A0132021-08-31031 August 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies ML21130A3022021-05-0707 May 2021 Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System ML21110A7042021-04-20020 April 2021 Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees ML21084A2522021-03-24024 March 2021 NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062) ML21068A2772021-03-0909 March 2021 NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20342A1782020-12-0707 December 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request ML20289A1072020-10-0606 October 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements (EPID L-2020-LLA-0209 ML20191A0252020-07-0101 July 2020 NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F1292020-04-0606 April 2020 E-mail to Licensee for Monticello Lr Phase 4 RFI ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20064C5352020-03-0404 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Revise the Previously Authorized Alternative in RR-008 for the H8 and H9 Welds 2024-01-20
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23268A0252023-09-25025 September 2023 SLRA - Requests for Confirmation of Information - Set 2 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4832023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23219A1082023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23200A3512023-07-19019 July 2023 SLRA - Request for Additional Information - Set 1 ML23059A3522023-03-0101 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000263/2023010 ML23058A1522023-02-27027 February 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002 ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML22206A1662022-07-25025 July 2022 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Monticello Nuclear Generating Plant ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML21322A2362021-11-18018 November 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401 ML21085A8582021-03-26026 March 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010 ML21068A2772021-03-0909 March 2021 NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request ML20191A0252020-07-0101 July 2020 NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations ML20133K0532020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20134H9282020-05-12012 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013 ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F3622020-04-0606 April 2020 Lr Phase 4 Request for Information ML20055F3672020-02-24024 February 2020 Information Request to Support Upcoming Temporary Instruction 2515/193 Inspection at Monticello Nuclear Generating Plant ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19270E8652019-09-27027 September 2019 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Rbaker) ML19080A2182019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Remove Note TS LCO 3.5.1 ML19070A1302019-03-0808 March 2019 Ltr. 03/08/19 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2019003 (DRS-V.Petrella) ML19031A9132019-01-31031 January 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt 10 CFR 50.69 ML18269A3572018-09-26026 September 2018 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt TSTF-425 ML18173A0512018-06-22022 June 2018 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (L-2018-LLE-0001) ML18130A7472018-05-0909 May 2018 NRR E-mail Capture - Request for Information Monticello TSTF-542 License Amendment Request ML18121A2542018-05-0101 May 2018 Enclosurequest for Additional Information (05/01/2018, E-Mail from C. Jacobs/Dsfm to S. Jurek Monticello Exemption: NRC Clarification Questions on RAI#1 Responses) ML18065A5482018-03-0606 March 2018 EnclosuRAI-1 (non-proprietary) (Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15) ML17293A0912017-10-18018 October 2017 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (CAC No. MF9586; EPID L-2017-LLE-00012) ML17235B0012017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Monticello EAL Scheme Change Amendment Request ML17221A3882017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17219A0752017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17086A0602017-03-27027 March 2017 NRR E-mail Capture - Request for Additional Information Monticello Nuclear Generating Plant Integrated Leak Rate Test Interval Extension Request ML16323A2422016-11-18018 November 2016 NRR E-mail Capture - Monticello ILRT Extension Amendment Request for Additional Information ML13336A7072013-12-0404 December 2013 Request for Additional Information Changes to Security Plan Revision 18 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13275A1872013-10-28028 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051 ML13154A4702013-06-0404 June 2013 Rai'S Following Ifib Analysis 2013 Decommissioning Funding Status Report for Prairie Island 1 and 2 and Monticello ML12279A2952012-10-12012 October 2012 Request for Additional Information 10 CFR 50.54(p)(2) Changes to Security Plan ML12221A3362012-08-0808 August 2012 Draft RAI on Revision to Security Plan 2024-01-20
[Table view] |
Text
From: Kuntz, Robert Sent: Friday, June 24, 2022 1:42 PM To: Loeffler, Richard A.
Cc: Scott, Sara
Subject:
RAI RE: Monticello Fuel Oil Storage Tank Inspection (EPID L-2021-LLA-0231 Mr. Loeffler, By request dated December 13, 2021 (Agencywide Documents Access and Management System Accession No. ML21348A718), Northern States Power Company (NSPM), a Minnesota corporation, doing business as Xcel Energy (Xcel), submitted a license amendment request to allow the common fuel oil storage tank to be out of service for up to 14 days at Monticello Nuclear Generating Plant.
The following requests for additional information (RAI) is needed for the Nuclear Regulatory Commission (NRC) staff to complete its review. Subsequent to a clarification discussion held on June 24, 2022 you requested a 45 day response to the following RAI. The staff has determined that a 45 day response is acceptable and therefore expects a response by August 8, 2022.
Robert Kuntz Senior Project Manager NRC/NRR/DORL/LPL3 REQUEST FOR ADDITIONAL INFORMATION XCEL ENERGY MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT RELATED TO THE INSPECTION OF THE FUEL OIL STORAGE TANK DOCKET NO. 50-263 RENEWED FACILITY OPERATING LICENSE NO. DPR-22
RAI 1
Regulatory Basis:
10 CFR 73.55(f)(1) states that The licensee shall document and maintain the process used to develop and identify target sets, to include the site-specific analyses and methodologies used to determine and group the target set equipment or elements.
10 CFR 73.55(e)(9), Vital areas, states that:
(i) Vital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans.
(ii) The licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking devices that allow rapid egress during an emergency and satisfy the vital area entry control requirements of this section.
(iii) Unoccupied vital areas must be locked and alarmed.
(iv) More than one vital area may be located within a single protected area.
Issue:
On page 9 of 22 of the license amendment request dated December 13, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21348A718), the first paragraph mentions that the hoses from the double-walled temporary fuel oil storage tanks referred to as FRAC penetrating the protected area (PA) fencing will have security compensatory measures implemented as determined by the Security Plan. The first paragraph also mentions that the FRAC system will be located outside the PA and the fuel transfer system will be located inside the PA.
Request:
What effect, if any, will the removal of the fuel oil storage tank and the installation of temporary equipment have on (1) target sets, (2) vital areas and equipment, and (3) implementation of the sites protective strategy?
RAI 2
Regulatory Basis:
10 CFR 73.55(b)(9) states that The licensee shall establish, maintain, and implement an insider mitigation program and shall describe the program in the Physical Security Plan.
(i) The insider mitigation program must monitor the initial and continuing trustworthiness and reliability of individuals granted or retaining unescorted access authorization to a protected or vital area, and implement defense-in-depth methodologies to minimize the potential for an insider to adversely affect, either directly or indirectly, the licensees capability to prevent significant core damage and spent fuel sabotage.
(ii) The insider mitigation program must contain elements from:
(A) The access authorization program described in § 73.56; (B) The fitness-for-duty program described in part 26 of this chapter; (C) The cyber security program described in § 73.54; and (D) The physical protection program described in this section.
10 CFR 73.55 (e)(7)(i)(B) states that Monitored with intrusion detection equipment designed to satisfy the requirements of § 73.55(i) and be capable of detecting both attempted and actual penetration of the protected area perimeter barrier before completed penetration of the protected area perimeter barrier.
10 CFR 73.55(g), Access controls, states that (1) Consistent with the function of each barrier or barrier system, the licensee shall control personnel, vehicle, and material access, as applicable, at each access control point in accordance with the physical protection program design requirements of 10 CFR 73.55(b).
10 CFR 73.55(h), Search programs, states, in part, that the licensee is required to develop and implement a search program to detect, deter, and prevent the introduction of firearms, explosives, incendiary devices, or other items which could be used to commit radiological sabotage.
10 CFR 73.55(i) Land vehicles, states that:
Licensees shall: (A) Design, construct, install, and maintain a vehicle barrier system, to include passive and active barriers, at a stand- off distance adequate to protect personnel, equipment, and systems necessary to prevent significant core damage and spent fuel sabotage against the effects of the design basis threat of radiological sabotage land vehicle bomb assault.
10 CFR 73.55(o), Compensatory measures, states that (1) The licensee shall identify criteria and measures to compensate for degraded or inoperable equipment, systems, and components to meet the requirements of this section.
(2) Compensatory measures must provide a level of protection that is equivalent to the protection that was provided by the degraded or inoperable, equipment, system, or components.
Appendix C to Part 73,Section II.B.3.c (v), requires licensees to develop, implement, and maintain a written protective strategy to be documented in procedures that describes in detail the physical protection measures, security systems and deployment of the armed response team relative to site specific conditions, to include but not be limited to, facility layout, and the location of target set equipment and elements. The protective strategy should support the general goals, operational concepts, and performance objectives identified in the licensees safeguards contingency plan.
Issue:
The license amendment request does not appear to address how Monticello Nuclear Generating Plant (Monticello) will continue to be protected against the Design Basis Threat (DBT) or provide any detailed information regarding the physical security compensatory measures that will be taken to ensure the plant remains adequately protected for the duration of the temporary configuration change to the plant. On page 9 of 22, Alternate Fuel Oil Supply System, the first paragraph mentions that the hoses from the FRAC tanks penetrating the protected area (PA) fencing will have security compensatory measures implemented as determined by the Security Plan. The first paragraph also mentions that the FRAC system will be located outside the PA and the fuel transfer system will be located inside the PA. The
submittal does not provide a description of where outside the PA the FRAC system will be located (e.g., will it be in the owner-controlled area near the large or small vehicle barrier system?). It also does not describe where the fuel transfer system will be located within the PA (will the location interfere with interlocking/overlapping fields-of-fire?). Page 11 of 22, top of page states in part: security measures will be implemented during the time the hose is run through the door of the Diesel Generator Building. Page 11 of 22, AFOSS Weather Operational Considerations, second paragraph states in part: the tank can be quickly refilled the hoses removed and the Diesel Generator Building door closed.
Request:
(1) Describe how Monticello will continue to be protected against the DBT with the security compensatory measures for the duration of the temporary configuration change to the plant.
(2) Describe how the hoses will penetrate the PA fence line (e.g., through open gates, penetration(s) through the fence line fabric) and describe the security compensatory measures that will be provided and implemented within the site procedures. Also, describe how the intrusion detection system (IDS) and assessment system at the PA barrier will continue to provide its intended functions for the duration of the temporary plant configuration.
(3) Describe how changes to the IDS will be inspected and tested during implementation of any changes. Confirm whether the testing of IDS will conform to Regulatory Guide 5.44, Perimeter Intrusion Alarm Systems, Revision 3, (Agencywide Documents Access and Management System Accession No. ML003739217), Section 3, Recommended Testing Procedures, Testing Option I or II.
(4) Provide detailed descriptions of where the FRAC and fuel oil transfer systems will be located and whether these locations will interfere with the site protective strategy.
(5) Describe the security compensatory measures for the Diesel Generating Building that will be implemented per site procedures to protect against unauthorized access and control.
RAI 3
Regulatory Basis:
10 CFR 73.58, Safety/security interface requirements for nuclear power reactors, states that:
(a) Each operating nuclear power reactor licensee with a license issued under part 50 or 52 of this chapter shall comply with the requirements of this section.
(b) The licensee shall assess and manage the potential for adverse effects on safety and security, including the site emergency plan, before implementing changes to plant configurations, facility conditions, or security.
(c) The scope of changes to be assessed and managed must include planned and emergent activities (such as, but not limited to, physical modifications, procedural changes, changes to operator actions or security assignments,
maintenance activities, system reconfiguration, access modification or restrictions, and changes to the security plan and its implementation).
(d) Where potential conflicts are identified, the licensee shall communicate them to appropriate licensee personnel and take compensatory and/or mitigative actions to maintain safety and security under applicable Commission regulations, requirements, and license conditions.
Issue:
The submittal did not appear to address safety/security interface.
Request:
Describe how safety/security interface is being addressed for this temporary plant change in accordance with 10 CFR 73.58.
RAI 4
Regulatory Basis:
NUREG-1764 Guidance for the Review of Changes to Human Actions, provides guidance for reviewing changes to human actions that are credited for safety. NUREG-1764 provides guidance in Sections 3 and 4 for verifying those deterministic aspects of design have been appropriately considered. NUREG-1764 says that deterministic aspects include verifying that the change meets current regulations and does not compromise defense-in-depth.
Issue:
The submittal states that procedures will be in place and training will be provided to the operators as determined by the Systematic Approach to Training (SAT) process. It is not clear in the submittal if there are any operator actions for this new alignment.
Request:
Provide a list of any revised operator actions that will be required to transfer oil from the alternate fuel oil storage system, as well as any timing analyses for those operator actions.
Hearing Identifier: NRR_DRMA Email Number: 1689 Mail Envelope Properties (SA9PR09MB464009CC5CE7B01DF039348B99B49)
Subject:
RAI RE: Monticello Fuel Oil Storage Tank Inspection (EPID L-2021-LLA-0231 Sent Date: 6/24/2022 1:42:18 PM Received Date: 6/24/2022 1:42:00 PM From: Kuntz, Robert Created By: Robert.Kuntz@nrc.gov Recipients:
"Scott, Sara" <sara.scott@xcelenergy.com>
Tracking Status: None "Loeffler, Richard A." <rick.a.loeffler@xcelenergy.com>
Tracking Status: None Post Office: SA9PR09MB4640.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 11841 6/24/2022 1:42:00 PM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: