|
---|
Category:Annual Operating Report
MONTHYEARRA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-21-0051, Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.462021-04-0505 April 2021 Shearon Harris Nuclear Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, and H. B. Robinson Steam Electric Plant - Annual Report of Changes Pursuant to 10 CFR 50.46 RA-20-0126, Annual Report of Changes Pursuant to 10 CFR 50.462020-05-27027 May 2020 Annual Report of Changes Pursuant to 10 CFR 50.46 MNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments RA-18-0022, Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.462018-05-24024 May 2018 Carolinas, LLC (Duke Energy) - Annual Report of Changes Pursuant to 10 CFR 50.46 MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017 Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017 RA-17-0027, Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.462017-05-25025 May 2017 Duke Energy Carolinas, LLC - Annual Report of Changes Pursuant to 10 CFR 50.46 MNS-17-020, Annual Radiological Environmental Operating Report2016-12-31031 December 2016 Annual Radiological Environmental Operating Report RA-16-0025, Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.462016-05-31031 May 2016 Duke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-15-0029, 10 CFR 50.46 - Annual Report for 20142015-07-0707 July 2015 10 CFR 50.46 - Annual Report for 2014 ML13142A3092013-05-13013 May 2013 2012 Annual Radiological Environmental Operating Report ML13135A1332013-04-25025 April 2013 Annual Radioactive Effluent Release Report ML12145A0502012-05-10010 May 2012 Annual Radiological Environmental Operating Report 2011, Cover Through Section 4 - Page 15 ML12145A0512012-05-10010 May 2012 Annual Radiological Environmental Operating Report 2011, Section 5 - Page 1 Through End ML12170A8672012-04-30030 April 2012 Annual Radioactive Effluent Release Report for 2011 ML11143A1192010-12-31031 December 2010 Annual Radiological Environmental Operating Report ML0914102022009-05-13013 May 2009 Annual Radiological Environmental Operating Report for 2008 Calendar Year ML0912806102009-04-28028 April 2009 2008 Annual Radioactive Effluent Release Report ML0908503472009-03-16016 March 2009 Duke Energy Carolinas, LLC (Duke), McGuire Nuclear Station, Units 1 and 2, Annual Commitment Change Report ML0808505592008-03-12012 March 2008 Annual Commitment Change Report NEI 99-04, McGuire Units 1 & 2, Annual Commitment Change Report2008-03-12012 March 2008 McGuire Units 1 & 2, Annual Commitment Change Report ML0710001582007-04-0303 April 2007 Annual Commitment Change Report for 2006 ML0713602092006-12-31031 December 2006 Annual Radiological Environmental Operating Report for Calendar Year 2006 ML0428802082004-09-30030 September 2004 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59, Changes, Tests, and Experiments. ML0415603492004-05-26026 May 2004 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model for the Period from January 1, 2003 to December 31, 2003 ML0414002862004-05-12012 May 2004 Annual Radiological Environmental Operating Report ML0313905552003-05-0505 May 2003 Annual Radiological Environmental Operating Report - 2002, 4.0 Evaluation of Dose ML0313905292003-05-0505 May 2003 Annual Radiological Environmental Operating Report - 2002 2023-04-26
[Table view] Category:Letter type:MNS
MONTHYEARMNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles MNS-18-042, Independent Spent Fuel Storage Installation (ISFSI)2018-06-28028 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-040, Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal2018-06-26026 June 2018 Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal MNS-18-039, Independent Spent Fuel Storage Installation (ISFSI)2018-06-19019 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable MNS-18-030, 2017 Annual Radiological Environmental Operating Report2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report MNS-18-029, Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A2018-05-0909 May 2018 Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-029, McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-2018-05-0909 May 2018 McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-028, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-18-018, McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes2018-02-22022 February 2018 McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes MNS-18-009, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-12018-01-31031 January 2018 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018 End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles MNS-17-042, McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report2017-10-0909 October 2017 McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report MNS-17-040, (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force ..2017-09-27027 September 2017 (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force .. MNS-17-038, Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate2017-09-25025 September 2017 Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate MNS-17-039, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-12017-09-19019 September 2017 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-1 MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017 Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017 MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017 Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval MNS-17-034, 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station.2017-07-24024 July 2017 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station. MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-016, Nuclear Regulatory Commission (NRC) Annual Commitment Change Report2017-05-18018 May 2017 Nuclear Regulatory Commission (NRC) Annual Commitment Change Report MNS-17-020, Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report2017-05-0505 May 2017 Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report MNS-17-019, McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report2017-04-28028 April 2017 McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report MNS-17-008, Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans2017-02-23023 February 2017 Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity. MNS-16-086, Emergency Plan, Revision 16-42016-12-0707 December 2016 Emergency Plan, Revision 16-4 MNS-16-078, Written Notification Joslyn Clark Overload Heater Element Part No. 24552016-10-19019 October 2016 Written Notification Joslyn Clark Overload Heater Element Part No. 2455 MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016 Response to Request for Additional Information to Relief Request 16-MN-003 MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping2016-08-10010 August 2016 Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016 License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping2016-06-23023 June 2016 Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping MNS-16-052, Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF76832016-06-16016 June 2016 Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF7683 MNS-16-042, Withdrawal of Relief Request Serial No. 15-MN-0022016-05-17017 May 2016 Withdrawal of Relief Request Serial No. 15-MN-002 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements MNS-16-041, Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051..2016-05-0505 May 2016 Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051.. MNS-16-036, Relief Request 16-MN-001, Limited Weld Examinations2016-04-28028 April 2016 Relief Request 16-MN-001, Limited Weld Examinations MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016 Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-026, Transmittal of Updated Final Safety Analysis Report, Revision 192016-04-0505 April 2016 Transmittal of Updated Final Safety Analysis Report, Revision 19 MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. 2018-07-03
[Table view] |
Text
Steven D. Capps ef'DUKE Vice President
~;ENERGY~
McGuire Nuclear Station Duke Energy MG01VP I 12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Serial No: MNS-17-037 10 CFR 50.59 (d)
August 10, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370 Renewed Facility License Numbers NPF-9 and NPF-17 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments Pursuant to 10 CFR 50.59( d)(2), attached is a summary report of evaluations performed at McGuire Nuclear Station (MNS) for changes occurring during the period from January 1, 2016, to March 31, 2017. These evaluations demonstrate that the associated changes do not meet the criteria for license amendments' as defined by 10 CFR 50.59(c)(2).
This submittal document contains no regulatory commitments.
If there are any questions or if additional information is needed, please contact Brian Richards of Regulatory Affairs at (980) 875-5171.
Sincerely,
Steven D. Capps Attachment
U.S. Nuclear Regulatory Commission August 10, 2017 Page 2 xc:
C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis Ohe Tower 245 Peachtree Center Ave. NE, Suite 1200 Atlanta, GA 30303-1257 Electronic:
A. Hutto, NRC Senior Resident Inspector Andy.Hutto@nrc.gov M. Mahoney, Project Manager Michael. Mahoney@nrc.gov
I Attachment 1 McGuire Nuclear Station (MNS)
Changes Evaluated Under 10 CFR50.59
Attachment 1 Page 1 of 4 UFSAR Change in Support of Lifting Reactor Vessel Upper Internals Lift Rig Action Request 01983884 This evaluation addresses the proposed use of the Containment Building Polar Crane to lift the Reactor Vessel Upper Internals Lift Rig during Modes 1 through 4 to support inspection of the lift rig. The rig is to be lifted a total vertical distance of approximately 35 feet 7 inches above the stand. A load drop analysis of the lift rig has demonstrated that the consequences of a load drop meet the guidelines of NUREG-0612, Section 5.1. Handling of the lift rig in Modes 1 through 4 has been found to be consistent with the heavy lifts program guidelines and controls described in UFSAR Section 9.1.5. Consistent with the Nuclear Regulatory Commission (NRC) endorsed guidelines of NEI 08-05, a revision to the UFSAR was generated to describe the inclusion of this lift into the Heavy Lifts Program. This proposed activity does not require a change to the Technical Specifications. Responses to each of the eight questions from 10 CFR 50.59.c(2) have been addressed in the evaluation with the conclusion that this activity can be performed without prior approval from the NRC.
Revision to Methodology Report DPC-NE-2009-P-A Action Request 01991491 The proposed activity being evaluated is a revision to the fuel rod analysis methodology in the Westinghouse Fuel Transition methodology report (DPC-NE-2009-P-A). The proposed activity adds a mechanistically based Departure from Nucleate Boiling (DNB) propagation methodology to DPC-NE-2009-P-A. Specifically, methodology report DPC-NE-2009-P-A Revision 3a is being revised to implement Revision 1-A to WCAP-8963-P-A Addendum 1-A, Safety Analysis for the Revised Fuel Rod Internal Pressure Design Basis (Departure from Nucleate Boiling Mechanistic Propagation Methodology), which has been previously approved by the NRC. DPC-NE-2009 methods are considered part of the UFSAR via reference, and as such, are considered "as described in the UFSAR."
This 10 CFR 50.59 evaluation was performed in accordance with guidance in Revision 1 of NEI 96-07 endorsed by the NRC via Regulatory Guide 1.187. It was concluded that the proposed activity is not a departure from a method of evaluation described in the UFSAR and thus does not require NRC review and approval.
Attachment 1 Page 2 of 4 Allow Replacement of Digital Rod Position Indication (DRPI) Controller Engineering Change (EC) 113220 Action Request 02014647 EC 113220 involves replacement of obsolete Universal Input/Output (1/0) Controllers (UIOCs) in the DRPI system with new DRPI 1/0 Controllers (DIOCs). The function of the affected controller is to manage retrieval of the raw rod data to the main control room for further processing by the DRPI system.
The existing DRPI UIOCs no longer have spare parts available from the original manufacturer.
Additionally, ongoing failures of the existing controllers have significantly decreased the reliability of the DRPI system.
Both the existing UIOC and the proposed replacement DIOC are digital components, and therefore, digital considerations apply to this 50.59 evaluation.
The activity was evaluated per 10 CFR 50.59, following the guidance provided in NEI 96-07 and NEI 01-01. The conclusion of the Evaluation is that the proposed activity may be implemented under 10 CFR 50.59 without requiring prior NRC review or approval.
Revision to Methodology Report DPC-NE-2009-P-A Action Request 02047562 The proposed activity being evaluated is a revision to the fuel rod analysis methodology in the Westinghouse Fuel Transition methodology report (DPC-NE-2009-P-A). The proposed activity replaces the existing ZIRLO cladding corrosion model in DPC-NE-2009 Revision 3b with a cladding corrosion model applicable to both ZIRLO and Optimized ZIRLO. This revision is necessary because Optimized ZIRLO cladding will be used with robust fuel assembly fuel beginning with McGuire 2 Cycle 25 (M2C25).
Specifically, methodology report DPC-NE-2009 Revision 3c implements WCAP-12610-P-A and CENPD-404-P-A, Addendum 1-A (Optimized ZIRLO) and Addendum 2-A (Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO), both of which have been previously approved by the NRC. DPC-NE-2009 methods are considered part of the UFSAR via reference, and as such, are considered "as described in the UFSAR."
This 10 CFR 50.59 evaluation was performed in accordance with guidance in Revision 1 of NEI 96-07 endorsed by the NRC via Regulatory Guide 1.187. It was concluded that the proposed activity is not a departure from a method of evaluation described in the UFSAR and thus does not require NRC review and approval.
Attachment 1 Page 3 of 4 Tune Distributed Control System (DCS) Controls Due to Hot Leg Streaming EC 404368 Action Request 02050448 This activity is a temporary engineering change for cycle M1 G25 on Unit 1 DGS for a robust tuning of reactor and feedwater controls. The tuning is desired to improve the Upper Plenum Anomaly (UPA) impact on two non-safety related control features. The UPA was observed during initial cycle run on M1 G25, whereby hot leg streaming perturbations have resulted in rod movement and excessive thermal power oscillations. The UPA impact is distracting to the operator and prevents full power operation.
The results of the review demonstrate that the activity does not adversely affect design functions described in the UFSAR nor any other aspect of the current licensing basis.
All eight questions were answered negatively with appropriate justifications evaluating the activity for accidents and malfunctions that could be initiated, impact on radiological consequences and fission product barriers, and use of approved methodologies. The potential impact upon the analysis of an accident was shown to be satisfactory with no increase in consequence. Therefore, this activity does not require a license amendment request to obtain prior NRG approval.
Allow Use of Upgraded VIPRE Code for Analysis Action Request 02073877 Duke Energy is upgrading the version of the VIPRE-01 thermal-hydraulics computer code from mod 2 as modified by Duke Energy to mod 2.5 as modified by Duke Energy (mod2.5adke). This code is used by the Duke Energy safety analysis group to simulate thermal-hydraulic conditions in the core to determine whether a rod or group of rods is undergoing DNB. The code remains substantially the same. However, the default water properties functions, which approximate the steam tables for VIPRE, have been modified slightly by the code vendor to better match with the steam tables. It is possible this change could result in more or less margin (i.e., the results might show more or less boiling in the core). Therefore, this code change screened in to the evaluation.
The computer code was examined to determine whether changes in aggregate made a substantive difference to the results during the Software Quality Assurance process. This process determined that results were within 0.5% of previous results. Per NEI 96-07 Section 4.3.8.1, "Licensees may change one or more element of a method of evaluation such that results move in the nonconservative direction without prior NRG approval, provided the revised result is 'essentially the same' as the previous result. Results are 'essentially the same' if they are within the margin of error for the type of analysis being performed." As provided by the vendor code manual, the uncertainty of the VIPRE computer code is between 1 and 5%. The change to the results is within code uncertainty. Therefore, this 50.59 evaluation concluded that the results are essentially the same, that they do not represent a departure from a method of evaluation, and that no prior NRG approval is required.
Attachment 1 Page 4 of 4 UFSAR Change in Support of Correcting Errors in Analysis for Steam Generator Tube Rupture (SGTR)
Action Request 02083777 A set of updates to the MNS UFSAR Tables 15-12 and 15-24 has been prepared. These updates are based on a revised Alternative Source Terms (AST) analysis of the MNS SGTR in which two errors were corrected. The corrections results in a lowering of the partition factors for ruptured steam generator (SG) boil-off and intact SG tube leakage. Although the corrections had adverse impact, the revised AST analysis of the MNS yielded radiation doses none of which equated to more than a minimal increase in the consequences of an accident or equipment malfunction. With the corrections, the AST analysis conforms to the NRC guidelines for AST analyses of the SGTR in a manner consist with the plant current license basis. The revised analysis may be put into place and the UFSAR updated without prior NRC review pursuant to 10 CFR 50.59.