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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
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
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-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023
Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
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
Request for Partial Site Release
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
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
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
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
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
RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station
RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022
Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans
RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022
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
RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022
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
RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V
RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
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
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 Actuated P
RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022
Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement
RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022
Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC
RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022
Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021
Proposed Changes to Decommissioning Trust Agreements and Master Terms
RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021
Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021
Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes
RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021
Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values
RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021
Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel
RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021
Application to Adopt TSTF-273, Safety Function Determination Program Clarifications
RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021
Proposed Alternative to Utilize Code Case N-893
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021
Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-069, Third Inservice Inspection Interval Relief Request I3R-182021-06-28028 June 2021
Third Inservice Inspection Interval Relief Request I3R-18
RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021
Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations
RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021
Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments
RS-21-037, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 22021-03-23023 March 2021
Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2
RS-21-028, Fitness for Duty Performance Data Reports - Annual 20202021-02-26026 February 2021
Fitness for Duty Performance Data Reports - Annual 2020
RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021
Amended Decommissioning Trust Agreements
RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021
License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021
Request for License Amendment to Revise Degraded Voltage Relay Allowable Values
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
2023-09-07
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Text
AmerGen Energy Company, LLC AmerGen..
An Exelon/British Energy Company Clinton Power Station RR.3 Box 228 Clinton, IL 61727-9351 RS-03-066 March 28, 2003 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 License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3
References:
(1) Letter from K. R. Jury (Exelon Generation Company, LLC) to U.S. NRC, "Request for License Amendment to Appendix A, Technical Specifications to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3," dated November 16, 2001 (2) Letter from K. R. Jury (Exelon Generation Company, LLC) to U.S. NRC, "Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3," dated October 4, 2002 In Reference 1, AmerGen Energy Company (AmerGen), LLC submitted a request for changes to the Facility Operating License No. NPF-62 and Appendix A to the Facility Operating License, Technical Specifications (TS), for Clinton Power Station (CPS) to revise suppression pool water level and upper containment pool water level requirements in Mode 3. Specifically, the proposed changes in Reference 1 requested the revision of the allowable operating range for the suppression pool water level and the modes of applicability for the upper containment pools.
The affected specifications are TS Section 3.6.2.2, "Suppression Pool Water Level," and TS Section 3.6.2.4, "Suppression Pool Makeup (SPMU) System." Additional information concerning the proposed changes was provided in Reference 2. Furthermore, the NRC requested additional follow-up information regarding the information provided in the above references. The attachment to this letter provides the requested information.
1-Dd
March 28, 2003 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions related to this information, please contact Mr. Timothy A.
Byam at (630) 657-2804.
Sincerely, Keith R. Jury Director - Licensing and Regulatory Affairs Mid-West Regional Operating Group AmerGen Energy Company, LLC Attachments: Affidavit Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3 cc: Regional Administrator - NRC Region Ill NRC Project Manager, NRR - Clinton Power Station NRC Senior Resident Inspector - Clinton Power Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
ATTACHMENT I Affidavit STATE OF ILLINOIS COUNTY OF DUPAGE )
IN THE MATTER OF AMERGEN ENERGY COMPANY, LLC ) Docket Number CLINTON POWER STATION, UNIT 1 ) 50-461
SUBJECT:
Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3 AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information and belief.
Keith R. Jury 0 Director - Licensing and Regulatory Affairs Mid-West Regional Operating Group AmerGen Energy Company, LLC Subscribed and sworn to before me, a Notary Public in and for the State above named, this ;28 day of
.I2003.
Notary u Ii
ATTACHMENT 2 Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3 Question 1 In the calculation of the entrapped drywell volume (inside the weir wall), is the volume of structures and equipment within this volume deducted? If so, what assurance is there that the assumptions in the analysis will remain valid?
Response I Yes, the volume of equipment and structures in the bottom of the drywell has been deducted in the analysis that determines the entrapped drywell volume. The volume of equipment and equipment foundations credited in the Clinton Power Station (CPS) drywell fill volume calculation is 876 cubic feet. This is equivalent to about 1.5 percent of the entrapped drywell volume and is equivalent to 1.4 inches of suppression pool water level. Removing or replacing permanent plant equipment would require a plant modification in accordance with procedure CC-AA-10, "Configuration Control Process Description." An integral part of the configuration control process is to identify any calculations that are impacted by the design change. The determination of the entrapped drywell volume, including the equipment and structures that are deducted from the gross volume, are documented in a CPS calculation. If the entrapped drywell volume is revised as part of the design change process, this calculation would be required to be identified as impacted.
Question 2 Why is there no large-break-LOCA-with-suppression-pool-bypass calculation?
Doesn't this calculation determine the minimum operator response time to limit break flow in order to minimize entrapped water in the drywell volume? Doesn't this analysis also determine the time necessary to refill the suppression pool from an external source to make up for continued steaming from the vessel and ECCS makeup to the vessel? (See Section 4.3.7 of the Grand Gulf letter to the NRC dated February 25, 2002.)
Response 2 CPS Updated Safety Analysis Report (USAR) Section 6.2.1.1.5 describes the analysis of the steam bypass of the suppression pool. USAR Subsection 6.2.1.1.5.4 describes the analysis without crediting containment spray and heat sinks and describes the limiting break as being a small primary system break. USAR Section 6.2.1.1.5.4 establishes that the small break LOCA was the basis for the CPS licensing basis bypass leakage analysis. USAR Section 6.2.1.1.5.5 then describes the analysis of a small break LOCA with credit for containment spray and heat sinks. The analysis described in this section establishes the limiting bypass leakage. CPS Safety Evaluation Report (Reference 1)
Section 6.2.1.7, concluded that the proposed bypass leakage was acceptable. It also determined that the analyses could be considered to cover all break sizes. This conclusion is consistent with the comparison between CPS and the response of other Mark III plants to Humphrey concern 5.1.
The GOTHIC analysis described in the proposed license amendment request (Reference 2) modeled a small break with controlled depressurization as described in the CPS USAR. In addition, a sensitivity analysis was performed using GOTHIC to Page 1 of 3
ATTACHMENT 2 Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3 determine the effect a large break (2.5 ft2) would have on the containment pressure assuming the same bypass leakage area. The area of a CPS main steam safe end is 2.55 ft2 and the area of the main steam pipe is slightly smaller. This sensitivity analysis was performed for the reduced vessel pressure case with two different sets of assumptions. The assumptions used for the base case (small break LOCA) and each of the two sensitivity cases are as follows:
Base Case: A small break (0.05 square feet), 250 psia starting vessel pressure, AN4K = 1.0 ft2, containment spray does not operate, operators do not control RPV level as described for the base analysis for the proposed amendment, and no credit is taken for the condensation caused by the ECCS fluid spilling into the drywell.
Sensitivity Case 1: A large break (2.5 square feet), 250 psia starting vessel pressure, AN'K = 1.0 ft2, containment spray operates, and operators control RPV level as described for the base case analysis for the proposed amendment.
Sensitivity Case 2: A large break (2.5 square feet), 250 psia starting vessel pressure, ANIK = 1.0 ft2, containment spray does not operate, operators do not control RPV level, and the bottom of the drywell floods.
In both Sensitivity Cases 1 and 2, the peak containment pressure is less than in the base case. In all cases, the peak pressure is less than the containment design pressure. In Case 2, the containment spray initiation setpoint is not reached. In none of the three cases is make-up required from outside the containment to maintain a minimum of 2 feet of vent coverage.
Based on the results of these analyses, it was not necessary to determine an operator action time to limit the amount of water that collects in the bottom of the drywell.
Question 3 Why is there no analysis of the "dump time" vs. "pump time" for the revised suppression pool makeup system? (See the same Grand Gulf letter to the NRC, Section 4.3.8.) (See Clinton FSAR Section 6.2.7.1.j)
Response 3 The dump time versus pump time calculation that was prepared for the current configuration is not adversely affected by the proposed license amendment request and therefore was not discussed in Reference 2. This is because the volume that is dumped is smaller in the Reference 2 analysis than the amount assumed for the current configuration; however, the line size, minimum head of water that serves as a forcing function, and initiating signals are unchanged. With the upper containment pool gates installed and the reactor cavity not drained, the dump time is more than 2 minutes shorter than the pump time. The calculation that documents the development of the GOTHIC model for the revised suppression pool makeup system addresses the reduced Page 2 of 3
ATTACHMENT 2 Additional Information Supporting the License Amendment Request to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3 dumping time due to the smaller volume of water to be dumped. The additional margin provided with the upper pool drained was not specifically calculated.
Reference:
- 1. NUREG-0853, "Safety Evaluation Report related to the operation of Clinton Power Station, Unit No. 1, Docket 50-461," dated February 1982.
- 2. Letter from K. R. Jury (Exelon Generation Company, LLC) to U. S. NRC, "Request for License Amendment to Appendix A, Technical Specifications to Revise Suppression Pool Water Level and Upper Containment Pool Water Level Requirements in Mode 3," dated November 16, 2001 Page 3 of 3
