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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 ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 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 ML23052A0652023-02-21021 February 2023 NRR E-mail Capture - Dresden Units 2 and 3 - Request for Additional Information for Alternative Request RV-23H ML23037A9192023-02-0707 February 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000237/2023011 and 05000249/2023011 ML23013A1502023-01-17017 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002 ML23019A0132023-01-12012 January 2023 NRR E-mail Capture - Final RAI Dresden 2 and 3 - License Amendment Pertaining to GNF3 Fuel Transition 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 ML22290A0842022-10-13013 October 2022 NRR E-mail Capture - Dresden 2 and 3 - RAI License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22227A1152022-09-27027 September 2022 Request for Withholding Information from Public Disclosure ML22270A1032022-09-27027 September 2022 Notification of NRC Baseline Inspection and Request for Information (05000249/2022004) 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 ML22203A0442022-07-21021 July 2022 Request for Additional Information (RAI) ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22199A2422022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Dresden 2 and 3 Proposed Alternative Related to Sblc Nozzle Inspection for the Sixth Inservice Inspection Interval 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 ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis 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 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 ML21244A4012021-08-10010 August 2021 (Final) Request for Information (RAI) Dresden, Units 1, 2, 3, and ISFSI Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50 Appendix E 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 ML21097A2602021-04-0808 April 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21096A1752021-04-0606 April 2021 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000237/2021011; 05000249/2021011 ML21063A3202021-03-0202 March 2021 RAIs for Dresden, Units 2 and 3, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (EPID L-2020-LLA-0239) (E-mail) 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) ML20337A4242020-12-0202 December 2020 Information Request for the Cyber-Security Full Implementation Inspection, Notification to Perform Inspection 05000237/2021401 and 05000249/2021401 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20231A7432020-08-18018 August 2020 Request for Additional Information (IOLB/HFT-RAI-1) Dresden MSIV LAR ML20224A3532020-08-11011 August 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000249/2020004 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 2023-09-21
[Table view] Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) 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)) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (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 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 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 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 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 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 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-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval 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-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval 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 ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 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 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 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 ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report 2024-02-05
[Table view] |
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- i' Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB..IECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXELON GENERATION COMPANY'S REQUEST TO AMEND STANDBY LIQUID CONTROL TECHNICAL SPECIFICATIONS (TAC NOS. ME2567 THRU ME2670)
Dear Mr. Pacilio:
By letter to the Nuclear Regulatory Commission (NRC) dated November 10, 2009, Exelon Generation Company, LLC submitted a request to amend the technical specifications (TSs) to extend the completion time for Condition B of TS 3.1.7 from 8 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the Dresden, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 21, 2010, it was agreed that you would provide a response by October 12,2010.
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. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1055.
Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION DRESDEN NUCLEAR POWER STATION, UNITS 1 AND 2 AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-237, 50-249, 50-254, AND 50-265 In reviewing the Exelon Generation Company's (EGC's) submittal dated November 10, 2009 (Agencywide Documents Access and Management System Accession No. ML093140516),
related to your request to amend Technical Specification (TS) 3.1.7, "Standby Liquid Control (SLC) System," for the Dresden Nuclear Power Station (DNPS), Units 1 and 2, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review:
Question 1 Identify adequate defense-in-depth for mitigation of anticipated transient without scram (ATWS) events for the extended 72-hour completion time period.
The SLC system mitigates an ATWS event by delivering a concentrated borated solution to the reactor pressure vessel to shutdown the reactor. The TS Required Action being modified addresses the condition where both SLC trains are inoperable. In the event of an ATWS during this condition, there is no system available to inject concentrated borated solution into the reactor pressure vessel in a timely manner to achieve shutdown. The licensee submittal addresses the low probability of an ATWS event due to the reliability and diversity of the control rods, and also discusses the recirculation pump trip feature which reduces reactor power.
However, there is no mechanism identified to assure safe shutdown to subcritical conditions as normally ensured by the operation of one of the two SLC trains.
Question 2 Clarify the intended reliance on emergency operating procedure (EOP) actions as an alternate means of boration and provide evaluations that justify any credited actions related to the requirements of Title 10 of the Code of Federal Regulations, Section 50.67, "Accident source term," as appropriate.
Page 17 of 19 of Attachment 1 states the following:
By letter dated October 10, 2002, EGC requested an amendment to the DNPS and QCNPS TSs regarding the adoption of an alternate source term (AST) methodology. The [Nuclear Regulatory Commission] NRC approved the requested license amendment by letter and safety evaluation (SE) dated September 11, 2006. As part of the proposed [alternate source term] AST methodology, EGC proposed the use of the SLC system to inject sodium Enclosure
-2 pentaborate into the [reactor pressure vessel] RPV following a [Ioss-of-coolant accident] LOCA in order to maintain suppression pool pH above 7 (Le., In order to ensure against re-evolution of elemental iodine). As such, the SLC is required to be operable in Mode 3 to ensure that offsite doses remain within the limits of 10 CFR 50.67, "Accident source term" following a loss-of-coolant accident (LOCA) involving significant fission product releases. However, additional redundancy for the control of suppression pool pH control following a LOCA is established by the DNPS and QCNPS Emergency Operating Procedures (EOPs).
The EOPs describe the actions and criteria for manual addition of boron into the condensate systems, should [reactor protection system] RPS, control rods, the control rod drive system, and the SLC be unable to perform the specifed [sic]
design functions. Therefore, the proposed SLC [completion time] CT extension will not impact the ability of DNPS and QCNPS to comply with the requirements of 10 CFR 50.67.
The license amendment request (LAR) describes alternative means for boration as additional redundancy in support of defense-in-depth measures to justify the proposed extension of the TS 3.1.7 completion time. These alternative means of boration consist of actions in the EOPs.
Page 4 of Attachment 1 of the LAR states that the SLC system is required to be operable to ensure that offsite doses remain within 10 CFR 50.67 limits following a LOCA. The SLC system is credited for maintaining pH balance in the suppression pool at or above 7 following a LOCA to ensure that iodine will be retained in the suppression pool.
The NRC staff has identified that the proposed alternate means of boration are not currently included in the DNPS and QCNPS licensing basis. The LAR indicates that the licensees intend to credit the referenced EOP actions as an alternate boration pathway to meet the requirements of 10 CFR 50.67. If so, then additional justification is required to support reliance on these actions as a credited alternate boration pathway. The NRC document "Guidance on the Assessment of a BWR [boiling-water reactor] SLC System for pH Control," dated February 12, 2004 (ADAMS Accession No. ML040640364) provides an approach that is acceptable to the NRC staff for evaluating the alternative controls of the suppression pool pH against appropriate methodologies.
If Exelon's intent is not to credit a new alternate boration pathway, then clarification is needed regarding the use of the EOP actions as an alternative means of boration with respect to defense-in-depth as related to 10 CFR 50.67. Please provide the following information:
- 1) Does the alternate injection path require actions in areas outside the control room?
- 2) Confirm that these areas will be accessible during the design basis accidents in your licensing bases (LOCA, Main Steamline Break etc.)?
- 3) What additional personnel will be required?
- 4) Confirm that these actions can be completed within a timeframe consistent the current licensing basis.
- 3 Question 3 Please demonstrate how General Design Criteria (GDC) 26, "Protection Systems Fail-Safe Design," and GDC 27, "Redundancy of Reactivity Control," regulatory requirements are met during the requested extended outage time for both trains of SLC inoperable.
Question 4 The Notices of Enforcement Discretion (NOEDs) referenced in the application provide lists of compensatory actions and additional committed actions. The NRC's basis for the NOEDs considered the compensatory measures to reduce the probability of a plant transient while ensuring the availability of other safety related equipment. Please describe how each compensatory action is addressed in the proposed change or demonstrate why it is not necessary. (Compensatory actions: 1) both ATWS recirculation pump trip systems would be protected, 2} the reactor protection system (RPS) would be protected, and 3) all production risk activities would be prohibited)
September 23, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555 SUB~IECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXELON GENERATION COMPANY'S REQUEST TO AMEND STANDBY LIQUID CONTROL TECHNICAL SPECIFICATIONS (TAC NOS. ME2567 THRU ME2670)
Dear Mr. Pacilio:
By letter to the Nuclear Regulatory Commission (NRC) dated November 10, 2009, Exelon Generation Company, LLC submitted a request to amend the technical specifications (TSs) to extend the completion time for Condition B of TS 3.1.7 from 8 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the Dresden, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 21,2010, it was agreed that you would provide a response by October 12, 2010.
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. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1055.
Sincerely, IRA!
Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 RlF RidsNrrDorlLpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLATHarris Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource MBlumberg, NRR KDesai, NRR RidsRgn3MailCenter Resource RidsNrrDoriDpr Resource AHowe, NRR JGall, NRR ADAMS Accession No.: ML102660195 NRR-088 LPL3,-2/F)M I LPL3-2/LA -2/BC LPL3-2/PM NAME CGratton THarris/BTully fo Ison CGratton DATE 9/23/10 9/23/10 9/23/10 OFFICIAL RECORD COpy