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Category:Letter
MONTHYEARIR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24129A1352024-05-0808 May 2024 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, and TSTF-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24083A0022024-03-22022 March 2024 IEMA-OHS Comment Dresden HI-STORM Exemption EA & Fonsi SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24061A1702024-03-0101 March 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS ML24179A2232024-02-12012 February 2024 ILT 23-1 (2024-301) SVP Letter - 24-007 ILT Exam Submittal 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) 2024-08-09
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.- Dresden GeneratingtationExelnem Exelon Generation www.exeloncorp.com Nuclear Dresden Generating Station 6500 North Dresden Road Morris, IL60450-9765 Tel 815-942-2920 November 25, 2003 10 CFR 50.46(a)(3)(ii)
RHLTR: #03-0077 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report
Reference:
Letter from R. J. Hovey (Exelon Generation Company, LLC) to U. S. NRC, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated November 25, 2002 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for.
light-water nuclear power reactors," paragraph (a)(3)(ii), Exelon Generation Company (EGC),
LLC, is submitting this letter and its attachment to meet the annual reporting requirements.
Dresden Nuclear Power Station Units 2 and 3 is maintaining the same emergency core cooling (ECCS) model as reported in the referenced letter. Two minor errors were discovered by the fuel vendor (General Electric (GE)). The first error involved incorrect initial water levels used in the SAFER model. The second error involved an incorrect initial steam separator pressure drop input used in the SAFER model. GE Determined the peak clad temperature (PCT) impact of these errors on all fuel types in Dresden Units 2 and 3 to be negligible. The PCTs of record are being provided as an attachment to this letter.
If there are any questions concerning this letter, please contact Mr. Jeff Hansen at (815) 416-2800.
Respectfully,
/u.
Robert J Hovey Site Vice Presiden Dresden Nuclear Power Station
Attachment:
Dresden Nuclear Power Station Units 2 and 3 - 10 CFR 50.46 Report cc: Regional Administrator - NRC Region III u0 NRC Senior Resident Inspector - Dresden Nuclear Power Station
Attachment Dresden Nuclear Power Station Units 2 and 3 10CFR50.46 Report PLANT NAME: Dresden Nuclear Power Station, Unit 2 ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 10/24/2003 CURRENT OPERATING CYCLE: 18 ANALYSIS OF RECORD Evaluation Model: The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume ll, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984.
Calculations:
"SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2," NEDC-32990P, Revision 1, GE Nuclear Energy, September 2001.
Fuel: 9x9-2, ATRIUM-9B and GE14 Limiting Fuel Type: GEl4 Limiting Single Failure: Diesel Generator Limiting Break Size and Location: 1.0 Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT) PCT= 21100 F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated December 6, 2001 (See Note 1) l APCT = 00 F 10 CFR 50.46 report dated November 25, 2002 (See Note 2) l APCT = 00 F Net PCT l 2110 F B. CURRENT LOCA MODEL ASSESSMENTS SAFER LevelNolume Table Error (See Note 3) APCT = 0 F SAFER Initial Steam Separator Pressure Drop Error (See Note 4) APCT = 0 0F Total PCT change from current assessments XAPCT = 0 F Cumulative PCT change from current assessments E APCT I=
0°F Net PCT 2110 F
fAttaci hmnt Dresden Nuclear Power Station Units 2 and 3 10CFR50.46 Report PLANT NAME: Dresden Nuclear Power Station, Unit 3 ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 10/24/2003 CURRENT OPERATING CYCLE: 18 ANALYSIS OF RECORD Evaluation Model: The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume 1II, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984.
Calculations:
"SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2," NEDC-32990P, Revision 1, GE Nuclear Energy, September 2001.
Fuel: 9x9-2, ATRIUM-9B and GE14 Limiting Fuel Type: GE14 Limiting Single Failure: Diesel Generator Limiting Break Size and Location: 1.0 Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT) PCT = 21100 F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated November 25, 2002 (See Note 2) APCT =0 0 F Net PCT 2110 F B. CURRENT LOCA MODEL ASSESSMENTS SAFER LevelNolume Table Error (See Note 3) APCT = 0F SAFER Initial Steam Separator Pressure Drop Error (See Note 4) APCT = 00F Total PCT change from current assessments YAPCT = 00 F Cumulative PCT change from current assessments E APCT I= 0F Net PCT 2110 0F
Attachment Dresden Nuclear Power Station Units 2 and 3 10 CFR 50.46 Report
- 1. Prior LOCA Model Assessment The 50.46 letter dated December 6, 2001 reported a new LOCA analysis to support extended power uprate (EPU) and transition to GE14 fuel for Dresden Unit 2 Cycle 18.
The same report assessed impact of errors in Framatome ANP LOCA analysis model for Dresden Unit 3 Cycle 17 at pre-EPU power level.
[
Reference:
Letter from Preston Swafford (PSLTR: #01-0122) (Exelon) to USNRC, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," December 6, 2001.]
- 2. Prior LOCA Model Assessment Unit 3 implemented GE LOCA analysis and GE14 fuel with Dresden Unit 3 Cycle 18 startup on October 25, 2002. Therefore, both Dresden Units 2 and 3 are being maintained under the same LOCA analysis. In the referenced letter, the impact of GE LOCA error in the WEVOL code was reported for Dresden Units 2 and 3 and determined to be negligible.
[
Reference:
Letter from Robert J. Hovey (RHLTR: #02-0083) (Exelon) to USNRC, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 25, 2002.]
- 3. Current LOCA Assessment GE reported that an error was found in the initial level/volume table for SAFER. The level/volume tables were generated with incorrect initial water levels. This resulted in an incorrect volume split in the nodes above and below the water surface, and incorrect initial liquid mass. GE determined that the PCT impact of this error on all fuel types in the Dresden reactors to be negligible.
[
Reference:
10 CFR 50.46 Notification Letter, 2003-01, May 6, 2003.]
- 4. Current LOCA Assessment GE reported that an error was found in the initial steam separator pressure drop input to the SAFER model. The calculation of this value for some plant/fuel types applied the wrong loss coefficient or erroneously included a term to account for the hydrostatic pressure. These errors resulted in a higher initial steam separator pressure drop and overly restricted the flow through the separator during the LOCA event. GE determined that the PCT impact of this error on all fuel types in the Dresden reactors to be negligible.
[
Reference:
10 CFR 50.46 Notification Letter, 2003-03, May 6, 2003