Letter Sequence Approval |
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EPID:L-2022-LLA-0176, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) (Approved, Closed) |
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MONTHYEARML22335A5072022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) Project stage: Request ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - Project stage: Acceptance Review ML23065A3212023-03-28028 March 2023 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems Project stage: Approval ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems Project stage: Approval ML23297A2552023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - FRN Project stage: Other ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter Project stage: Other ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 Project stage: Approval ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 Project stage: Approval 2023-03-28
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Category:E-Mail
MONTHYEARML23362A0572023-12-28028 December 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - SUNSI Review of the Final Safety Analysis Report (FSAR) Revision OL-26 ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23121A0112023-04-28028 April 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Revise TS to Adopt TSTF-501-A Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control - EPID L-2023-LLA-0046 ML23114A2302023-04-24024 April 2023 NRR E-mail Capture - Regulatory Audit Question - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23107A1812023-04-17017 April 2023 NRR E-mail Capture - Regulatory Audit Questions - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23037A0022023-02-0303 February 2023 NRR E-mail Capture - Callaway - LAR to Adopt AST - EPID L-2021-LLA-0177 - Revised Schedule for Completion of the Project ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - ML22346A0132022-12-0909 December 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of LAR to Revise TS 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies - EPID L-2022-LLA-0165 ML22322A0062022-11-17017 November 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) Callaway - LAR for Proposed Changes to TS and Exemption Request Use of Framatome Gaia Fuel - L-2022-LLA-0150 & L-2022-LLE-0030 ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22280A1322022-10-0707 October 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway - License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-0 ML22278A0122022-10-0404 October 2022 NRR E-mail Capture - Draft - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-013 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information 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) ML22251A0122022-09-0707 September 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections - EPID L-2022-LLA-0110 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22216A0072022-07-0808 July 2022 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Draft Acceptance Review (Unacceptable for Review with Opportunity to Supplement) for Framatome Fuel Transition LAR and Exemption - EPIDs L-2022-LLA-0083 and L-2022-LLE-0019) ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0102022-06-0303 June 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood Ultimate Heat Sink Temporary Temperature Increase to 102.8 Degrees Fahrenheit ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22089A0222022-03-29029 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LAR to Adopt TSTF-505 and TSTF-439 - Follow Up Clarifications for the Audit Questions - EPID L-2021-LLA-0197 ML22087A4022022-03-28028 March 2022 NRR E-mail Capture - Callaway - Draft RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to Generic Letter 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22070A1362022-03-10010 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals - EPID L-2022-LLA-0024 ML22047A2312022-02-11011 February 2022 Email Between NRC NSIR and FEMA Regarding Callaway Sirens 021122 ML22003A0852022-01-0303 January 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules - EPID L-2021-LLA-0225 ML21334A5172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21335A0172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21308A0692021-11-0404 November 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Unit 1 - License Amendment Request - Adoption of Alternate Source Term and Revision of TSs - ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21125A0452021-05-0404 May 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Plant, Unit 1 - License Amendment Request - Final Resolution to Address Concerns of GSI-191 - EPID L-2021-LLA-0059 ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 ML20296A6332020-10-22022 October 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020 Lle 0140 (Covid 19)) - Revised Completion Schedule ML20205L4252020-07-22022 July 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Acceptance of Requested Licensing Action Request for One-Time License Amendment to Defer Upcoming Steam Generator Inspection (EPID L-2020-LLA-0142)(COVID-19) ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20153A7902020-05-29029 May 2020 Emai: RFI for Callaway EP Program Inspection ML20133K6742020-05-11011 May 2020 05000483, Request for Information 2020-002 ML20099G2422020-04-0808 April 2020 NRR E-mail Capture - Acceptance Callaway Containment Tendon COVID-19 Relief Request ML20097C8362020-04-0606 April 2020 NRR E-mail Capture - Accepted: Callaway TS Change 5.3.1 LAR EPID: L-2020-LLA-0046 2023-07-27
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
From: Mahesh Chawla Sent: Thursday, July 27, 2023 9:42 AM To: Elwood, Thomas B Cc: Jennifer Dixon-Herrity; Shilp Vasavada; Marie Pohida; Keith Tetter; Andrew Mihalik; Hanry Wagage; Gordon Curran; Matthew Hamm; Vijay K Goel; Summer Sun; Vic Cusumano; Phillip Sahd; Brian Wittick; Wendell Morton
Subject:
Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems (EPID L-2022-LLA-0176)
Attachments: Callaway audit questions L-2022-LLA-0176.docx
Dear Mr. Elwood,
By application dated December 1, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22335A507), Union Electric Company, doing business as Ameren Missouri (the licensee), submitted a license amendment request (LAR) for Callaway Plant, Unit No. 1. The proposed amendment request is submitted for NRC approval of a change (clarification) to the plant's licensing basis, i.e., the Technical Specification (TS) Bases and FSAR, to allow use of one train of the normal, non-safety related Service Water system to solely provide cooling water support for one of two redundant trains of TS-required equipment when both equipment trains are required to be Operable during cold shutdown/refueling conditions.
The supported equipment/systems affected by the proposed change are the Residual Heat Removal system and Control Room Air Conditioning system, as applicable during Modes 5 and
- 6. The applicable/affected TS Limiting Conditions of Operation (LCOs) are TS LCO 3.4.8, "RCS Loops - Mode 5, Loops Not Filled," TS LCO 3.7.11, "Control Room Air Conditioning System (CRACS)," and TS LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level."
On March 28, 2023 (ML23065A321), the U.S. Nuclear Regulatory Commission (NRC) staff issued a letter indicating their plans for a regulatory audit and setup of online reference portal request to the licensee. The audit plant included the request for documents and the audit questions from the NRC staff. The regulatory audit was conducted from April 11 through 12, 2023, during which licensee provided the pertinent information for the subject application. The NRC staff has developed following additional audit questions (attached), for which they would like the licensee to provide the requested information.
Contact me to arrange a teleconference with the NRC staff to provide your response to this request. Thanks Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-8371 Docket No. 50-483
OFFICE DORL/LPL4/PM DORL/LPL4/BC JDixon-NAME MChawla Herrity DATE 7/27/23 7/27/23
Hearing Identifier: NRR_DRMA Email Number: 2182 Mail Envelope Properties (SA1PR09MB84153E5C554046E536474871F101A)
Subject:
Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems (EPID L-2022-LLA-0176)
Sent Date: 7/27/2023 9:42:09 AM Received Date: 7/27/2023 9:42:00 AM From: Mahesh Chawla Created By: Mahesh.Chawla@nrc.gov Recipients:
"Jennifer Dixon-Herrity" <Jennifer.Dixon-Herrity@nrc.gov>
Tracking Status: None "Shilp Vasavada" <Shilp.Vasavada@nrc.gov>
Tracking Status: None "Marie Pohida" <Marie.Pohida@nrc.gov>
Tracking Status: None "Keith Tetter" <Keith.Tetter@nrc.gov>
Tracking Status: None "Andrew Mihalik" <Andrew.Mihalik@nrc.gov>
Tracking Status: None "Hanry Wagage" <Hanry.Wagage@nrc.gov>
Tracking Status: None "Gordon Curran" <Gordon.Curran@nrc.gov>
Tracking Status: None "Matthew Hamm" <Matthew.Hamm@nrc.gov>
Tracking Status: None "Vijay K Goel" <Vijay.Goel@nrc.gov>
Tracking Status: None "Summer Sun" <Summer.Sun@nrc.gov>
Tracking Status: None "Vic Cusumano" <Victor.Cusumano@nrc.gov>
Tracking Status: None "Phillip Sahd" <Phillip.Sahd@nrc.gov>
Tracking Status: None "Brian Wittick" <Brian.Wittick@nrc.gov>
Tracking Status: None "Wendell Morton" <Wendell.Morton@nrc.gov>
Tracking Status: None "Elwood, Thomas B" <TElwood@ameren.com>
Tracking Status: None Post Office: SA1PR09MB8415.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 2279 7/27/2023 9:42:00 AM Callaway audit questions L-2022-LLA-0176.docx 39958 Options Priority: Normal
Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Regulatory Basis When a licensee proposes to use a nonsafety-related system for a limited duration to address the unavailability of a corresponding safety-related system, typically compensatory measures are identified and to a certain extent, are incorporated into the Technical Specifications (TS).
These compensatory measures are intended to minimize challenges to the nonsafety- related system and to pre-stage mitigating measures as appropriate. For example, in NUREG-0800, Branch Technical Position 8-8, Onsite (Emergency Diesel Generators) And Offsite Power Sources Allowed Outage Time Extensions (ADAMS Accession No. ML113640138), discusses the use of an alternate power source and lists expected compensatory measures. Likewise, an appropriate duration and compensatory measure might aid in justifying the use of the nonsafety-related service water system (SWS) for the safety-related essential water system (ESW), based on the following considerations:
- 1. Based on staff review of operating pressurized water reactor (PWR) and advanced PWR low power and shutdown probabilistic risk assessments, the staff recognizes the increased risk associated given a postulated loss of residual heat removal (RHR) when (1) the reactor coolant system (RCS) is breached and the steam generators cannot be used for decay heat removal and (2) reduced inventory operation when the time to RCS boiling is short requiring short times for operator actions such as inventory addition and containment closure. Industry guidance and key shutdown voluntary initiatives are addressed in NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management, December 1991 (as referenced in RG 1.201 for 10 CFR 50.69 and in SECY 97-168). NUMARC 91-06 states, Activities which may impact the core cooling system/components should be scheduled during periods of low decay heat or maximum coolant inventory or during defueled conditions. If such activities must be scheduled during periods of high decay heat or REDUCED INVENTORY (defined as three feet below the reactor vessel flange), then CONTINGENCY PLANS should be established.
- 2. In case of a Loss of Offsite Power, SWS will not have an alternate power supply, while one ESW train can be supplied by at least one required emergency diesel generator (EDG).
- 3. Regulatory Issue Summary 2013-05, NRC Position on the Relationship Between General Design Criteria and Technical Specification Operability, states that [I]t is the staffs position that failure to meet GDC [General Design Criteria], as described in the licensing basis (e.g., nonconformance with the CLB [Current Licensing Basis] for protection against flooding, seismic events, tornadoes) should be treated as a nonconforming condition and is an entry point for an operability determination if the nonconforming condition calls into question the ability of SSCs to perform their specified safety function(s) or necessary and related support function(s). 10 CFR 50.36 (c)(2)(i) states: Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. TS Limiting Condition for Operation (TS LCO) 3.4.8 (Mode 5, Loops Not Filled) and TS LCO 3.9.6 (Mode 6 with water level < 23 feet above the top of reactor vessel flange) require that two RHR loops shall be operable, and one RHR loop shall be in operation.
The definition of OPERABLE in Callaway TS states: A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water,
lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
The nonsafety-related SWS and its support systems (such as nonsafety-related alternating current (AC) power) are not specifically analyzed for protection from hazards and events such as tornadoes, internal and external floods, missiles, pipe breaks, internal fires, and seismic events compared to the ESW system.
- 4. The license amendment request (LAR) does not provide qualitative or quantitative risk information to support the use of a nonsafety-related system without alternative power supplies. While such risk information is not expected for shutdown conditions, risk-information is typically provided to justify extended outage times. A limited duration and compensatory measures would somewhat constrain the risk, even if it cant be formally evaluated.
Audit Questions Given the foregoing discussion, discuss the appropriate duration and compensatory measures for using the non-safety related SWS to address the unavailability of one train of safety-related ESW to maintain two trains of operable RHR during operations while in low vessel inventory and identify those that should be included in TS, for example in a note or by reference. This discussion should address the following considerations.
- 1. Discuss the expected duration of one train of ESW outage. Discuss why an ESW outage must take place during reduced inventory conditions as opposed to periods of greater coolant inventory consistent with industry guidance. Additional justification would be needed for no duration limits or for unusually long duration limits (no justification was provided in the LAR).
- 2. Describe the compensatory measures to protect the nonsafety-related SWS and its support systems (such as nonsafety-related AC power) from internal hazards such as internal fires, internal floods, and operator error, which can occur due to maintenance during shutdown.
- 3. Describe what compensatory measures will be taken if severe weather is predicted since the nonsafety-related SWS and its support systems are not protected against high winds and other external hazards.
- 4. Accumulator injection is listed by the licensee as a defense-in-depth makeup method for adding water to the RCS in response to prior audit questions 7 and 14. Given the nitrogen cover gas in the accumulator, please discuss the results of analysis to show that, for the configuration proposed in the LAR, the entrainment of nitrogen in the RCS does not impact RCS level instrumentation, RHR function in decay heat removal mode, or mitigation of a loss or interruption of RHR, especially during a reduced inventory condition.