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Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23118A1652023-04-28028 April 2023 NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23065A2832023-03-0707 March 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000254/2023010 and 05000265/2023010 ML23013A1502023-01-17017 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002 ML23004A0262022-12-16016 December 2022 NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070) ML22348A0452022-12-14014 December 2022 NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09 ML22227A1152022-09-27027 September 2022 Request for Withholding Information from Public Disclosure ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22249A2332022-09-0606 September 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000254/2022011 05000265/2022011 ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22193A0412022-07-11011 July 2022 NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods ML22182A1992022-07-0101 July 2022 NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28 ML22178A1362022-06-28028 June 2022 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Quad Cities Station ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis ML22076A1122022-03-15015 March 2022 Request for Additional Information Related to the Amendment Request to Transition to GNF3 Fuels (EPID L-2021-LLA-0159) (Redacted) ML22059A9902022-03-0101 March 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Implement Prime Methodologies for Evaluating Thermal Overpower and Mechanical Overpower Limits for Non-Global Nuclear Fuels Fuel ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22039A1912022-02-0808 February 2022 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21342A3842021-12-0808 December 2021 NRR E-mail Capture - Request for Additional Information: Quad Cities 1 & 2 License Amendment Request Transition to GNF3 Fuel ML21294A0032021-10-26026 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding Transition to GNF3 Fuel ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21238A3142021-08-26026 August 2021 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000254/2021004; 05000265/2021004 ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20183A2852020-07-0101 July 2020 Request for Information for an NRC Triennial Baseline Bases Assurance Inspection (Team): Inspection Report 05000254/2020011 and 05000265/2020011 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20031C8332020-01-31031 January 2020 NRR E-mail Capture - Request for Additional Information for Quad Cities Request to Revise Technical Specifications to Increase the MSIV Leakage Rate (L-2019-LLA-0045) ML20021A0342020-01-17017 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2020002; 05000265/2020002 ML19134A2792019-05-15015 May 2019 Supplemental Information Needed for Acceptance of License Amendment Request to Increase Main Steam Isolation Valve Allowable Leakage Rates ML18346A4032018-12-0707 December 2018 10 CFR 50.59 (Evaluation of Changes, Tests and Experiments) Inspection Supplemental Request for Information (DRS-A.Shaikh) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17353A9492018-01-0909 January 2018 Supplemental Information Needed for Acceptance of License Amendment Request to Revise Technical Specification Requirements for Secondary Containment ML17355A0112017-12-20020 December 2017 NRR E-mail Capture - Request for Additional Information Regarding Relief Request I5R-11, Revision 2 ML17333A0822017-11-28028 November 2017 17 Quad Cities Nuclear Plant, Unit 2 - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000265/2018001 (DRS-M.Domke) ML17262A0892017-09-19019 September 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies (RS-17-051) ML17198A2292017-07-17017 July 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Set No. 2 (Cac. Nos. MF9675 and MF9676) (RS-17-051) ML17200A0882017-07-0707 July 2017 NRR E-mail Capture - Draft RAI for QC LAR Re Permanent Extension of Type a and Type C Leak Rate Testing Frequencies ML17180A1532017-06-29029 June 2017 Request for Additional Information Concerning Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MF9675 and MF9676) (RS-17-051) ML17159A6292017-06-0707 June 2017 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17072A0012017-02-0909 February 2017 NRR E-mail Capture - Draft RAI for QC LAR Re Loss of Voltage Relay Setting Change 2023-09-21
[Table view] |
Text
Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 19, 2017 Exelon Generation
- Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2-REQUEST FOR ADDITIONAL INFORMATION CONCERNING PERMANENT EXTENSION OF TYPE A AND TYPE C LEAK RATE TEST FREQUENCIES (RS-17-051)
(CAC NOS. MF9675 AND MF9676)
Dear Mr. Hanson:
By letter dated April 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17121 A449), Exelon Generation
- Company, LLC (EGC) submitted a license amendment request for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment would modify Technical Specification 5.5.12, "Primary Containment Leakage Rate Testing Program,"
to allow for the permanent extension of the Type A Integrated Leak Rate Testing and Type C Leak Rate Testing frequencies.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and response to the NRC staff's request for additional information (RAI) and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. A draft RAI was transmitted by email to Mr. Ken Nicely on September 14, 2017. A clarification call was held on September 18, 2017. No changes to the draft RAI were needed as a result of the clarification call. Based on a discussion with Mr. Ken Nicely, it was agreed that EGC will provide a response to the RAI within 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
B. Hanson If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627.
Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Kimberly J. Green, enior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION EXELON GENERATION COMPANY.
LLC QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 DOCKET NOS. 50-254 and 50-265 By letter dated April 27, 2017, Exelon Generation
- Company, LLC (EGC), submitted a license amendment request (LAR) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17121A449).
The proposed amendment would modify Technical Specification 5.5.12, "Primary Containment Leakage Rate Testing Program,"
to allow for the permanent extension of the Type A Integrated Leak Rate Testing and Type C Leak Rate Testing frequencies.
By letter dated July 17, 2017 (ADAMS Accession No. ML 17198A229),
EGC supplemented the LAR with additional information in response to the U.S. Nuclear Regulatory Commission (NRC) staff's requests (ADAMS Accession Nos. ML 17180A 153 and ML 17198A229).
The NRC staff has reviewed the additional information and has determined that further information below is needed to support the NRC staff's continued technical review of the LAR. RAI 5-A Section 4.2.6 of EPRI [Electric Power Research Institute]
TR [Topical Report)-1009325, Revision 2-A, states that "[p]lants that rely on containment overpressure for net positive suction head (NPSH) for emergency core cooling system (ECCS) injection for certain accident sequences may experience an increase in CDF [core damage frequency),"
therefore requiring a risk assessment.
In response to request for additional information (RAI) 5, EGC described the probabilistic risk assessment (PRA) modeling to estimate the change in risk from loss of NPSH to the ECCS pumps and provided a LiCDF estimate of 2.4E-8/year.
- a. As described in the RAI response, the risk analysis appears to assume a total loss of containment heat removal for all accident scenarios that were considered, such as transients, loss-of-coolant
- accident, anticipated transient without scram, special initiators, etc., which are listed in Table 5-1 of the RAI response.
However no justification was provided for scenarios with containment decay heat removal available.
Explain and justify why the loss of containment overpressure impacting NPSH for the ECCS injection is not a concern in any accident scenario with containment decay heat removal available.
Alternatively, if any additional accident scenarios are identified to contribute to the risk increase, provide an updated estimate of LiCDF. b. The RAI response attempts to explain the PRA modeling for scenarios "post containment failure" and for scenarios with "successful pool venting" in Figures 5-4 and 5-5. Since the containment would already be failed due to the postulated pre-existing containment leak, further PRA modeling appears unnecessary and the application of the model described in Figure 5-1 to those post containment failure scenarios may result in a reduction in the risk estimate.
The RAI response also states that for "successful pool venting,"
only sources outside the containment are credited.
Clarify how the PRA model described in the response to RAI 5 correctly captures the risk impact from accident scenarios "post containment failure" and those with "successful pool venting."
Enclosure c. In response to RAI 5.c, .6LERF (large early release frequency) resulting from loss of NPSH was equated to .6CDF. If a new method to estimate
.6LERF is deemed necessary in response to items a or b above, describe and justify any credit taken for reducing
.6LERF below the value for .6CDF. RAI 8-A Background RAI 8 requested that EGC explain how it determined that the identified leakage near the containment structure was groundwater and is not impacting the structural integrity or tightness of the containment.
In its response, EGC explained the leakage was not groundwater but did not address how it was determined the leakage was not impacting containment.
The response contained no information regarding the leakage location relative to containment, and no discussion of whether or not the leakage is contained within the sand pocket drain lines. If the leakage is contained within the sand pocket drain lines (i.e., no indications of leakage through concrete in the general vicinity of the drains),
the NRC staff understands how it can be determined the leakage is not impacting the containment.
- However, if leakage is occurring through concrete in the general area of the drains, the leakage could be impacting inaccessible portions of containment.
The response did not provide enough information for the NRC staff to determine that the leakage is contained within the drains, or if the leakage is outside the drain lines (as implied in Notes 2 and 4) that the leakage is not impacting containment.
Request For both units, explain how EGC determined that the identified leakage is not impacting the structural integrity or leak-tightness of the containment.
The explanation should include whether or not the leakage is contained such that it is not impacting containment and how it was determined that the leakage is not impacting inaccessible portions of the containment (e.g., location of leakage precludes it from contacting containment, minimal amount of leakage or sporadic nature of leakage limits possibility of corrosion).
B. Hanson
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION CONCERNING PERMANENT EXTENSION OF TYPE A AND TYPE C LEAK RATE TEST FREQUENCIES (RS-17-051)
(CAC NOS. MF9675AND MF9676) DATED SEPTEMBER 19, 2017 DISTRIBUTION:
PUBLIC RidsAcrs_MailCTR Resource RidsNrrDorl Resource RidsNrrDorlLpl3 Resource RidsNrrDeEseb Resource RidsNrrDraApla Resource RidsNrrLASRohrer Resource RidsNrrPMQuad Cities Resource RidsRg3MailCenter Resource
- BLehman, NRR MBiro, NRR JEvans, NRR ADAMS Accession No.: ML 17262A089 OFFICE DORL/LPL3/PM DORL/LPL3/LA NAME KGreen SRohrer DATE 9/19/17 9/19/17 DORL/LPL3/BC DWrona 9/19/17 OFFICIAL RECORD COPY NRR-106 DORL/LPL3/PM KGreen 9/19/17