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Category:Letter type:RS
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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-23-077, 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-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel 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-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 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-22-049, 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-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval 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-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors 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-21-009, Proposed Relief Request Associated with Code Case N-9212022-01-18018 January 2022 Proposed Relief Request Associated with Code Case N-921 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-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) RS-21-110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-19019 October 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-103, Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station2021-09-28028 September 2021 Updated Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations for Byron Station and Dresden Nuclear Power Station RS-21-097, Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning2021-09-15015 September 2021 Withdrawal of Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3, and Previously Submitted Licensing Actions in Support of Decommissioning 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-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E 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 2023-08-30
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARRS-11-124, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-07-28028 July 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 SVPLTR 09-0044, Day Response on Inadvertent Control Rod Withdrawal2009-09-21021 September 2009 Day Response on Inadvertent Control Rod Withdrawal SVPLTR 09-0027, Written Follow Up Report on Release of Radionuclide2009-07-0606 July 2009 Written Follow Up Report on Release of Radionuclide RS-08-073, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima22008-05-23023 May 2008 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima2 ML0216407762002-06-0707 June 2002 Offsite Dose Calculation Manual (OCDM) Required Action Not Met During Units 2/3 Main Chimney Particulate, Iodine, and Noble Gas Sampling System Inoperability ML17252A3201977-11-23023 November 1977 LER 77-047/03L-0 for Dresden Unit 3 Regarding During Normal Unit 3 Operation, Surveillance Program Review Revealed Violation of T.S.1.0.CC.b Maximum Combined Interval Time by 3.5 Days for HPCI Monthly Valve and Pump Operability ML17252A2881977-05-0303 May 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-8 ML17252A2911977-04-22022 April 1977 License Event Report - Rod Withdrawal at Approx. 44% Power, Discovered Rod Block Monitor Channels 7 and 8 Automatically Bypassed ML17252A2901977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-10 ML17252A2711977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-9 ML17252A2721977-04-20020 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-7 ML17252A2751977-03-23023 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2821977-03-0202 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2581977-01-20020 January 1977 Transmittal of Reportable Occurrence Report No. 50-249/1976-36 ML17252A2701976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 IR 05000249/20190761976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 ML17252A2461976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B ML17252A2451976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-25 in Accordance with Technical Specifications, Section 6.6.B ML17252A2391976-10-22022 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-20 in Accordance with Technical Specifications, Section 6.6.B ML17252A2411976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-18 in Accordance with Technical Specifications, Section 6.6.B ML17252A2401976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-19 in Accordance with Technical Specifications, Section 6.6.B ML17252A2231976-10-12012 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-15 in Accordance with Technical Specifications, Section 6.6.B ML17252A2261976-09-30030 September 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-17 in Accordance with Technical Specifications, Section 6.6.B ML17252A2361976-07-0101 July 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-1 ML17252A2101976-02-0505 February 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-3 in Accordance with Technical Specifications, Section 6.6.B IR 05000249/19750361975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1761975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1711975-08-15015 August 1975 Report of A.O. Per Section 6.6.A of the Technical Specifications Isolation Condenser High Flow Sensor Setpoint Drift IR 05000249/19750321975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A1741975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A4471975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings IR 05000249/19750311975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings ML17252A7861975-03-27027 March 1975 Report of Abnormal Occurrence Per Section 6.6.a of the Technical Specification - Exceeding Set-point on Main Stream Line Hi Hi Rad ML17252A8271975-02-14014 February 1975 Report of Abnormal Occurrence Per Section 6.6.A of the Technical Specification - Reactor Feed Pump 3C Pump Casting Vent Line Weld Leak ML17252A8361975-01-14014 January 1975 Report of 4 Inch Recirculation Bypass Line Inspection 2011-07-28
[Table view] |
Text
Exel6n N u c l ear Exelon Generationwww.exeloncorp.com 4300 Wir I Road L 60555 RS-11-124 July 28, 2011 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19 NRC Docket No. 50-237
Subject:
Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14
References:
1.Letter from J. L. Hansen (Exelon Generation Company, LLC(EGC))to U. S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated October 29, 2010 2.Letter from General Electric Hitachi Nuclear Energy (GEH) to EGC, "10 CFR 50.46 Notification Letter 2011-02 for Dresden (Units 2 & 3)," dated July 1, 2011 3.Letter from GEH to EGC, "10 CFR 50.46 Notification Letter 2011-03 for Dresden (Units 2 & 3)," dated July 6, 2011 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, LLC (EGC), is submitting this letter and its attachment to notify the NRC of changes or errors discovered in the Dresden Nuclear Power Station (DNPS), Unit 2 plant specific emergency core cooling system (ECCS) evaluation for Global Nuclear Fuel (GNF) GE14 fuel that have been determined to be significant. This submittal meets the requirements of 10 CFR 50.46(a)(3)(ii) for submittal of a report within 30 days.
In Reference 1, EGC provided the NRC with the annual 10 CFR 50.46 Report for DNPS, Units 2 and 3. On June 28, 2011, EGC received notification from GEH that errors had been discovered in the GEH methodology used to analyze the ECCS loss of coolant accident (LOCA) response for DNPS and Quad Cities Nuclear Power Station (QCNPS). The errors are associated with the way the GEH methodology distributes gamma energy deposition within GNF fuel.The DNPS, Unit 3 core does not contain GNF fuel, so these errors apply only to the GE14 fuel that remains in the DNPS, Unit 2 core. The errors reported in References 2 and 3 result in an increase in the analyzed PCT for GE14 fuel of 75°F and 10°F, respectively. Since the current GE14 licensing basis PCT is 21 10°F for DNPS, Unit 2, the revised licensing basis PCT, July 28, 2011 U. S. Nuclear Regulatory Commission Page 2 accounting for these errors, is 2195°F. The revised PCT remains within the 2200 °F acceptance criterion of 10 CFR 50.46; however, since the absolute magnitude of the errors is greater than 50 °F, this report must be submitted to the NRC within 30 days of the notification in accordance with the requirements of 10 CFR 50.46(a)(3)(il).
The attachment to this letter provides updated information regarding the PCT value for the GE14 fuel in DNPS, Unit 2. Note 12 of the attachment provides details related to errors discussed above.
There are no commitments contained in this letter. If there are any questions concerning this letter, please contact Mitchel Mathews at (630) 657-2819.
Attachment:
Dresden Nuclear Power Station Unit 2 - 10 CFR 50.46 Report 30-Day Report for GE14 Fuel cc:Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46(a)(3)(ii) 30-Day Report for GE14 Fuel Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30-Day Report for GE14 Fuel PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLES:
Page 1 of 6 Dresden Nuclear Power Station, Unit 2 SAFER/GESTR-LOCA July 22, 2011 22 ANALYSIS OF RECORD Evaluation Model:
Calculation:
Fuel Analyzed in Calculation:
Limiting Fuel Type:
Limiting Single Failure:
Limiting Break Size and Location:
Reference Peak Cladding Temperature (PCT):
The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984.
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 2, GE Nuclear Energy, September 2003.
9x9-2, ATRIUM-9B and GE14 GE14 Diesel Generator 1.0 double-ended guillotine break in a recirculation suction pipe.
2110 OF Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30-Day Report for GE14 Fuel Page 2 of 6 MARGIN ALLOCATION A.PRIOR LOSS OF COOLANT ACCIDENT (LOCA)
MODEL ASSESSMENTS 10 CFR 50.46 report dated December 6, 2001 (See Note 1
)OPCT =0°F 10 CFR 50.46 report dated November 25, 2002 (See Note 2
)APCT =0°F 10 CFR 50.46 report dated November 25, 2003 (See Note 3
)APCT =0°F 10 CFR 50.46 report dated November 24, 2004 (See Note 4
)OPCT =0°F 10 CFR 50.46 report dated November 16, 2005 (See Note 5
)OPCT =0°F 10 CFR 50.46 report dated November 9, 2006 (See Note 6
)APCT =0°F 10 CFR 50.46 report dated October 31, 2007 (See Note 7
)APCT =0°F 10 CFR 50.46 report dated October 30, 2009 (See Note 10)
APCT =0°F 10 CFR 50.46 report dated October 29, 2010 (See Note 11)
APCT =0°F Net PCT 2110°FB.CURRENT LOCA MODEL ASSESSMENTS Gamma energy deposition error 1 (See Note 12) 75°F Gamma energy deposition error 2 (See Note 12) 10°F Total PCT change from current assessments EDPCT = 85°F Cumulative PCT change from current assessments APCT I = 85°F Net PCT 2195°F Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30
-Day Report for GE14 Fuel Page 3 of 6 Assessment Notes 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.Prior LOCA Model Assessment The annual 50.46 report provided information on the LOCA model assessments for SAFER LevelN olume table error and Steam Separator pressure drop error. In the referenced letter, the impact of these two GE LOCA errors was reported to be negligible.
[
Reference:
Letter from Robert J.Hovey (RHLTR: #03-0077)(Exelon)to USNRC,"Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 25, 2003.]
4.Prior LOCA Model Assessment The referenced annual 50.46 report provided information on reload of GE14 fuel for Dresden Unit 2 Cycle 19 and the impact of postulated hydrogen-oxygen recombinationon PCT. GE determined that there was no PCT impact due to the reload of GE14 fuel and the postulated hydrogen -oxygen recombination.
[
Reference:
Letter from Danny Bost (SVPLTR: #04-0075) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 24, 2004.]
Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30
-Day Report for GE14 Fuel Page 4 of 6 5.Prior LOCA Model Assessment The referenced letter provided the annual 50.46 report for Units 2 and 3. The letter reported the PCT impact of reload of GE14 fuel for D3C19. Also, the letter reported the GE LOCA evaluation for Unit 3, which implemented the lower sectional replacement and T-box clamp repairs. GE determined that there was no PCT impact due to the reload of GE14 fuel and the lower sectional replacement and T-box clamp repairs.
[
Reference:
Letter from Danny Bost (SVPLTR: #05-0044)(Exelon)to USNRC, "Plant Specific ECCS Evaluation Changes -
10 CFR 50.46 Report," November 16, 2005.]
6.Prior LOCA Model Assessment The referenced letter provided the annual 50.46 report for Units 2 and 3. The letter reported the PCT impact of the reload of GE14 fuel for D2C20. The letter also reported an evaluation of increased leakage of less than 5 gpm at pump runout conditions in the core spray line flow due to crack growth identified during the D2R19 outage.
Additionally, a GE evaluation of the small break for impact due to top-peak axial power shape was reported in this letter.
The impact due to these changes on the licensing basis PCT was reported as zero.
[
Reference:
Letter from Danny Bost (SVPLTR: #06-0054) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 9, 2006.]
7.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter reported D3C20 startup with the first reload of Westinghouse Optima2 fuel and implementation of the Westinghouse LOCA analysis. No error was reported for GE LOCA applicable to operation of GE14 fuel in the Unit 2 and Unit 3 cores.
[
Reference:
Letter from Danny Bost (SVPLTR: #07-0049) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 31, 2007.]
8.Prior LOCA Model Assessment (not applicable to this 30-day report)
The referenced letter provided the 30-day 10 CFR 50.46 report for Dresden unit 2. The 30-day 10 CFR 50.46 report was submitted for Dresden unit 2 due to the non-conservative modeling of Low Pressure Core Spray (LPCS) performance for Unit 2.
Dresden Unit 3 was not affected. Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit reduction was implemented at Dresden Unit 2 in order to meet all 10 CFR 50.46 criteria while maintaining a PCT at or below the licensing basis value of 2150 OF for the entire Cycle 21 operation. This note only pertains to Westinghouse SVEA-96 Optima2 fuel.
Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30-Day Report for GE14 Fuel Page 5 of 6
[
Reference:
Letter from Jeffrey Hansen (RS-08-073) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima2," May 23, 2008.]
9.Prior LOCA Model Assessment (not applicable to this 30-day report)
The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter reported implementation of Westinghouse revised LOCA report to document evaluation of the non-conservative modeling of Low Pressure Core Spray (LPCS)
performance for Unit 2. Dresden Unit 3 was not affected by this error. This note only pertains to Westinghouse SVEA-96 Optima2 fuel.
[
Reference:
Letter from David Wozniak (SVPLTR:#08-0059 (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 31, 2008.]
10.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter updated the vessel leakage between the lower shroud and the downcomer.
Westinghouse evaluated this change and demonstrated that all 10 CFR 50.46 criteria were satisfied. This evaluation resulted in maximum PCT impact due to the change in vessel leakage of 2 OF for Optima2 fuel with the licensing basis PCT of 2152 IF. The vessel leakage was reported by GE to have an insignificant impact on the PCT transientportion of the LOCA event. Therefore, a PCT impact of 0°F is reported for GE14 fuel with the licensing basis PCT remaining at 2110 OF. Note: The new Westinghouse analysis is documented in Revision 5 of the Dresden LOCA Report and contains the same information as stated above and transmitted to the NRC in the Reference.
[
Reference:
Letter from Timothy Hanley (SVPLTR: #
09-0052 (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 30, 2009.]
11.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3.
The letter reported the replacement of core spray lower sectional piping in Dresden Unit 2 during D2R21. Both GEH and Westinghouse evaluated the core spray leakage due to this modification and concluded that the PCT impact was 0 OF. The letter also identified a change in input for modeling bypass hole flow coefficient in the Westinghouse LOCA analysis. The impact on PCT due to this change was determined by Westinghouse to be 12 IF. For D2C22, Westinghouse established a MAPLHGR limit for the fresh bundles to accommodate the change. For 10 CFR 50.46 reporting purposes, the PCT impact is conservatively applied to all bundle types including the fresh bundles. This PCT update Attachment Dresden Nuclear Power Station, Unit 2 10 CFR 50.46 30-Day Report for GE14 Fuel Page 6 of 6 will remain in effect only until the MAPLHGR limits for all bundles in future Dresden Unit 2 and Unit 3 cores are evaluated for the change in bypass hole flow coefficient. The latter issue only pertains to Westinghouse SVEA-96 Optima2 fuel.
[
Reference:
Letter from Jeffrey Hansen (RS-10-191, Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report", October 29, 2010.]
- 12. Current LOCA Model Assessment General Electric Hitachi Nuclear Energy (GEH) reported errors in the LOCA methodology associated with the GE14 fuel in Dresden Nuclear Power Station (DNPS), Unit 2 (i.e., References 1 and 2). DNPS, Unit 3 is not affected because it does not have GNF fuel loaded in the core. GEH identified two errors. In Reference 1, GEH reported an error related to the way input coefficients are used to direct the deposition of gamma radiation energy produced by the fuel. Accounting for this error results in a PCT increase of 75 °F. In Reference 2, GEH reported an error related to the contribution of
heat from gamma ray absorption by the fuel channel. The gamma ray absorption by the channel was found to have been minimized. Correcting this error results in a PCT increase of 10 F. The cumulative impact of the absolute values for both errors is 85 F.
When added to the prior licensing basis PCT, the revised ECCS-LOCA licensing basis becomes 2195 °F, which is less than the 10 CFR 50.46 acceptance criterion of 2200 F.
DNPS, Unit 2 has one batch of twice burned GE14 fuel remaining in the core. The GE14 fuel is scheduled to be discharged in the fall 2011 refueling outage (i.e., D2R22).
These errors apply only to the GE14 fuel in the DNPS, Unit 2 core. The LOCA analysis for the Westinghouse fuel in the DNPS, Unit 2 core is not affected by the errors discussed in this note.
References:
1.Letter from General Electric Hitachi Nuclear Energy (GEH) to Exelon Generation Company, LLC (EGC), "10 CFR 50.46 Notification Letter 2011-02 for Dresden (Units 2 & 3)," dated July 1, 2011 2.Letter from GEH to EGC, "10 CFR 50.46 Notification Letter 2011-03 for Dresden (Units 2 & 3)," dated July 6, 2011