Letter Sequence Request |
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MONTHYEARML0928004262009-10-16016 October 2009
RAI Related to License Amendment Request to Modify Clinton Power Station in Support of the Use of Isotope Test Assemblies
Project stage: RAI
ML0928003742009-10-16016 October 2009
RAI Related to License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies
Project stage: RAI
ML0930302182009-11-0202 November 2009
Request for Additional Information Related to License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies
Project stage: RAI
RS-09-150, Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies2009-11-0404 November 2009
Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies
Project stage: Request
RS-09-146, Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Lsotope Test Assemblies2009-11-17017 November 2009
Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Lsotope Test Assemblies
Project stage: Request
RS-09-160, Additional Information Supporting the Request for a License Amendment to Modify the Operating License in Support of the Use of Lsotope Test Assemblies2009-11-20020 November 2009
Additional Information Supporting the Request for a License Amendment to Modify the Operating License in Support of the Use of Lsotope Test Assemblies
Project stage: Request
ML0931706632009-11-23023 November 2009
Withholding Information from Public Disclosure, ME1643
Project stage: Other
ML0931706902009-11-23023 November 2009
Request for Withholding Information from Public Disclosure - Ltr. Dated 11/12/2009
Project stage: Withholding Request Acceptance
ML0932208462009-12-0202 December 2009
Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing and Order
Project stage: Other
RS-09-167, Supplemental Safety Analysis Report Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Isotope Test Assemblies2009-12-0909 December 2009
Supplemental Safety Analysis Report Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Isotope Test Assemblies
Project stage: Supplement
RS-09-179, Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Lsotope Test Assemblies2009-12-16016 December 2009
Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Lsotope Test Assemblies
Project stage: Request
ML0934800502009-12-17017 December 2009
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
RS-09-181, Submittal of Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies2009-12-28028 December 2009
Submittal of Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies
Project stage: Request
RS-10-010, Additional Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Lsotope Test Assemblies2010-01-11011 January 2010
Additional Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Lsotope Test Assemblies
Project stage: Request
ML1002000052010-01-15015 January 2010
License Amendment, Modify CPS License Condition 2.B.(6) and Create New License Conditions 1.J, 2.B.(7) and 2.C.(25) as Part of a Pilot Program to Irradiate Cobalt (Co)-59 Target to Produce Co-60
Project stage: Other
ML1002607272010-02-0101 February 2010
Public Version - Correction Letter for License Amendment 190 Request to Modify Facility Operating License in Support of the Use of Isotope Test Assemblies (Tac ME1643)
Project stage: Approval
RS-12-082, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2012-05-14014 May 2012
Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)
Project stage: Other
2009-12-17
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Category:Letter type:RS
MONTHYEARRS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
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RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023
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RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023
Supplemental Information Related to Request for Partial Site Release
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
RS-23-073, Request for Partial Site Release2023-06-0707 June 2023
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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
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Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023
Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air
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Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
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RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023
Application to Adopt TSTF-332, ECCS Response Time Testing
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022
Notice of Intent to Pursue Subsequent License Renewal Applications
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
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Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock
RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022
Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves
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Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022
Constellation Radiological Emergency Plan Addendum Revision
RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022
Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan
RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022
Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock
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RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022
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RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021
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RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021
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RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
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2023-09-07
[Table view] |
Text
Exelon Generation 4300 Winfield Road Nuclear Warrenville, IL 60555 RS-09-179 10 CFR 50.90 December 16,2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies
References:
- 1. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assernblies,"dated June 26, 2009
- 2. Letter from U. S. NRC to Mr. Charles G. Pardee (Exelon Generation Company, LLC), "Clinton Power Station, Unit No. 1 - Request for Additional lnformation Related to License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies (TAC No. ME1643)," dated November 2,2009 (ADAMS Accession No. ML093030218)
- 3. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated November 20, 2009
- 4. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated November 17, 2009 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating license for Clinton Power Station (CPS), Unit 1. Specifically, the proposed change would modify CPS License Condition 2.8.(6) and create new License Conditions 1.J and 2.8.(7) as part of a pilot program to irradiate cobalt (Co)-59 targets to
December 16,2009 U. S. Nuclear Regulatory Commission Page 2 produce Co-60. In addition to the proposed license condition changes, EGC also requests an amendment to Appendix A, Technical Specifications (TS), of the CPS Facility Operating License. This proposed change would modify TS 4.2.1, "Fuel Assemblies," to describe the Isotope Test Assemblies (ITAs) being used. In Reference 2, the NRC requested that EGC provide additional information in support of their review of Reference 1. The NRC request for additional information and the specific EGC responses were provided in Reference 3.
On December 9,2009, EGC and the NRC conducted a conference call to discuss the responses provided in Reference 3 and some additional clarification of these responses were provided informally. During this conference call additional information was requested concerning the EGC response to RAI 2. This additional information is provided in the attachment to this letter.
EGC has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in Reference 4. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. No new regulatory commitments are established by this submittal.
If you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2804.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 16'h day of December 2009.
ManageF Licensing Exelon Generation Company, LLC Attachments: Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies
ATTACHMENT Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies In Reference 1, Exelon Generation Company, LLC (EGC) provided responses to a request for additional information from the NRC in support of their review of a proposed license amendment request for Clinton Power Station (CPS), Unit 1 (Reference 2). In RAI 2 the NRC stated the following.
"Attachment 4, Section 4.3, "Evaluation of Design-Basis Accidents," of Reference 1 it states: The CPS Design-Basis Accidents (DBAs) to be evaluated are identified in Chapter 15.0 of the Clinton Power Station (CPS) Updated Safety Analysis Report (USAR). The Control Rod Drop Accident (CRDA), Main Steamline Break (MSLB) accident outside containment, Fuel Handling Accident (FHA), and Loss-of-Coolant Accident (LOCA) are licensed under Title 10 of the Code of Federal Regulations (10 CFR) Section 50.67, "Accident Source Term," per Regulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." In Reference 2, it states that the information needed includes a description of the analyses used to evaluate the impact of the proposed change on radiological consequences of DBAs in the CPS design bases. The proposed change only evaluates the impact on the DBAs described above. Please provide the information requested in Reference 2 for all DBAs in the CPS design bases or justify why this information is not needed."
EGC responded that in addition to the Design Basis Accidents (DBAs) analyzed in Reference 2, the CPS design bases include eight limiting fault accidents or DBAs.
These DBAs have been analyzed and were listed by Updated Safety Analysis Report (USAR) location. The response concluded that for each of the eight limiting fault accidents addressed in the Attachment to Reference 1, the radiological consequences are unchanged for a core operating with lsotope Test Assemblies (ITAs) for a DBA in which no fuel failures occur as a result of the event.
Following the review of this response by the NRC reviewer, additional clarification was requested concerning the evaluation of these 8 DBAs. The reviewer specifically requested that EGC (1) verify that the evaluation of these DBAs address the potential for failure of the isotope rods as well as fuel rods, and (2) identify the dose analysis licensing basis for these DBAs. The following provides the requested information.
Recirculation Pumrs Seizure (USAR 15.3.3)
The results of the CPS Recirculation Pump Seizure design basis radiological analysis concludes no fuel failures or isotope rod failures result due to the event. Therefore, the radiological consequences are unchanged for operation with ITAs. While the consequences of the events identified previously do not result in any fuel or isotope rod failures, radioactivity is nevertheless discharged to the suppression pool as a result of SRV activation. However, the mass input, and hence activity input, for this event is much less than those consequences evaluation for the Main Steam Line Isolation Valve Closure event (see USAR Section 15.2.4.5). Therefore, the radiological exposures noted in Section 15.2.4.5 cover the consequences of this event. The dose to personnel in unrestricted areas is shown to be within the limits of 10 CFR 20 applicable to CPS operation (as well as 10 CFR 50 and 40 CFR 190). These limits are more restrictive than 10 CFR 100 guidelines.
ATTACHMENT Additional Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies Recirculation P u m Shaft
~ Break (USAR 15.3.4)
The results of the CPS Recirculation Pump Shaft Break design basis radiological analysis concludes no fuel failures or isotope rod failures result due to the event.
Therefore, the radiological consequences are unchanged for operation with ITAs. While the consequences of this event do not result in any fuel or isotope rod failures, radioactivity is nevertheless discharged to the suppression pool as a result of SRV activation. However, the mass input, and hence activity input, for this event is much less than those consequences identified in radiological consequences evaluation for the Main Steam Line Isolation Valve Closure event (see USAR Section 15.2.4.5). Therefore, the radiological exposures noted in Section 15.2.4.5 cover the consequences of this event.
The dose to personnel in unrestricted areas is shown to be within the limits of 10 CFR 20 applicable to CPS operation (as well as 10 CFR 50 and 40 CFR 190). These limits are more restrictive than 10 CFR 100 guidelines.
Feedwater Line Break Outside Containment (USAR 15.6.61 The results of the CPS Feedwater Line Break Outside Containment radiological analysis concludes no fuel failures or isotope rod failures result due to the event. Therefore, the radiological consequences are unchanged for operation with ITAs. The calculated exposures for the realistic analysis are a small fraction of 10 CFR 100 guidelines.
Main Condenser Offaas Treatment Svstem Failure (USAR 15.7.1.1)
The CPS Main Condenser Offgas Treatment System Failure design basis radiological analysis is based on a 100,000 ~Cilsecafter 30 minutes delay noble gas source term.
Particulates such as cobalt have no effect on the accident consequences. Therefore, the radiological consequences are unchanged for operation with ITAs. This design basis accident was evaluated against the guidelines of 10 CFR 100.
Malfunction of Main Turbine Gland Sealina Svstem (USAR 15.7.1.2)
The CPS Malfunction of Main Turbine Gland Sealing System design basis accident occurs outside the containment and does not involve any barrier integrity aspects including isotope rod failures. Therefore, the radiological consequences are unchanged for operation with ITAs. This accident was evaluated against the guidelines of 10 CFR 100.
Failure of Main Turbine Steam Air Eiector Lines (USAR 15.7.1.3)
The CPS Failure of Main Turbine Steam Air Ejector Lines design basis accident analysis concludes there is no radiological release due to the event. Therefore, the radiological consequences are unchanged for operation with ITAs. Since there is no release as a result of this event, there is no evaluation against the requirements of 10 CFR 100 or 10 CFR 50.67.
Liquid Radwaste Tank Failure (USAR 15.7.3)
The CPS Liquid Radwaste Tank Failure design basis accident analysis is based on a 100,000 ~Cilsecafter 30 minutes delay noble gas source term. Particulates such as cobalt have no effect on the accident consequences. Therefore, the radiological
ATTACHMENT Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies consequences are unchanged for operation with ITAs. This accident was evaluated against the guidelines of 10 CFR 100.
Cask Droo Accident (USAR 15.7.51 The CPS Cask Drop Accident analysis determined that a dropped cask would not rupture, and no radiological release is associated with this event. Therefore, the radiological consequences are unchanged for operation with ITAs. Since there is no radiological release as a result of this event, there is no evaluation against the requirements of 10 CFR 100 or 10 CFR 50.67.
The Control Rod Drop Accident, Main Steam Line Break Accident, Fuel Handling Accident, and Loss of Coolant Accident were analyzed under the Alternative Source Term methodology and therefore, are evaluated against the requirements of 10 CFR 50.67.
References:
- 1. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S.
NRC, "Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated November 20, 2009
- 2. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S.
NRC, "License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated June 26,2009
