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Category:Graphics incl Charts and Tables
MONTHYEARML24109A1102024-04-17017 April 2024 1 to the Updated Safety Analysis Report, List of Effective Pages ML24092A2152024-03-27027 March 2024 Email: Requests for Information to Support Deis L-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462021-12-15015 December 2021 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462018-12-12012 December 2018 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 ML16245A7202016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014 Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 ML14141A3992014-05-27027 May 2014 Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+) ML13105A1882013-04-10010 April 2013 Monticello Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 1 of 96 Through Page 57 of 96 L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End2013-04-10010 April 2013 Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel2008-10-16016 October 2008 Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0612402692006-06-0505 June 2006 Attachment 6 - Table R - Relocated Specifications for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402662006-06-0505 June 2006 Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402642006-06-0505 June 2006 Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402592006-06-0505 June 2006 Attachment 3 - Table M - More Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402552006-06-0505 June 2006 Attachment 2 - Table a - Administrative Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0613901442005-08-0404 August 2005 Web References for Monticello Dseis: Socioeconomics ML0520105032005-08-0101 August 2005 Xcel Energy - Migratory Bird Reporting Form and Flow Chart, Revised 2003 ML0520104582005-04-11011 April 2005 NCDC Listing of Nonattainment Status for Each County by Year, as of April 11, 2005 ML0434501802003-12-11011 December 2003 NMC Program Health Status Fleet Program at a Glance 2024-04-17
[Table view] Category:Letter type:L
MONTHYEARL-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) 2024-07-09
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-MT-16-050, Thirty-Day Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel2016-10-20020 October 2016 Thirty-Day Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014 Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-13-090, August 2013, 10 CFR 50.46 Thirty-Day Report2013-08-27027 August 2013 August 2013, 10 CFR 50.46 Thirty-Day Report L-MT-11-039, Submittal of 10 CFR 50.46 Thirty Day Report2011-07-0707 July 2011 Submittal of 10 CFR 50.46 Thirty Day Report ML0923803802009-09-0303 September 2009 LER 263/2008-005, Monticello, Partial Loss of Offsite Power Event with HPCI High Level Instrument Trip Failures L-MT-05-116, Day Special Report: Failure of Wide Range Radiation Monitor Electronic Process Flow Probe2005-11-30030 November 2005 Day Special Report: Failure of Wide Range Radiation Monitor Electronic Process Flow Probe ML0232904112002-11-0404 November 2002 30-Day Special Report, Inoperable Offgas Stack Wide Range Monitors 2016-10-20
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Xcel Energy@ Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 June 17, 2014 L-MT-14-054 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 June 2014, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
References:
- 1) NRC to NSPM, "Monticello Nuclear Generating Plant- Issuance of Amendment No. 176 to Renewed Facility Operating License Regarding Extended Power Uprate (TAG No. MD9990)," dated December 9, 2013.
- 2) NRC to NSPM, "Monticello Nuclear Generating Plant- Issuance of Amendment No. 180 to Renewed Facility Operating License Regarding Maximum Extended Load Line Limit Analysis Plus (TAG No.
ME3145)," dated March 28, 2014.
- 3) NSPM to NRC, "Report of Changes in Emergency Core Cooling System Evaluation Models," (L-MT-14-004) dated January 10, 2014.
Pursuant to 10 CFR 50.46(a)(3)(ii), the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, is providing this 30-day report concerning changes/errors identified in the Emergency Core Cooling System (ECCS) evaluation models for the Monticello Nuclear Generating Plant (MNGP). The MNGP Loss of Coolant Accident (LOCA) analyses of record (AORs) are contained in the General Electric Hitachi (GEH) reports submitted for the MNGP Extended Power Up rate and the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license amendments (References 1 and 2).
This 30-day report is being made due to the recent issuance of several GEH Nuclear Energy 10 CFR 50.46 Notification Letters. The changes/errors discussed within those notification letters result in a cumulative increase in Peak Cladding Temperature (PCT) that exceeds the 50°F reporting threshold of 10 CFR 50.46(a)(3)(i), and hence, are being reported in accordance with the regulation. The nature of these changes/errors and their effect on PCT is summarized in Table 1 of Enclosure 1. These changes result
Document Control Desk L-MT-14-054 Page 2 of 2 in an Adjusted PCT increase from the previously reported 2150°F (Reference 3) to 2170°F.
As prescribed by the regulation a proposed reanalysis schedule or an evaluation is needed to demonstrate the facility remains in compliance with 10 CFR 50.46 requirements. In accordance with 10 CFR 50.46(a)(3)(ii) the following evaluation is provided. The Adjusted PCT is 30°F below the 2200°F acceptance criterion of 10 CFR 50.46(b)(1). This provides sufficient margin to justify taking no further action.
No further reanalysis or other actions are planned. provides additional information on the nature of the changes, and also on the previous changes and errors, and their effect on the MNGP LOCA analysis. This information is being submitted in accordance with the requirements of 10 CFR 50.46(a)(3)(ii) for the MNGP.
If you have any questions or require additional information, please contact Mr. Richard Loeffler at (763) 295-1247.
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments.
Karen D. Fili, Site Vice-President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT TABLE 1 -
SUMMARY
OF MONTICELLO LOCA CHANGES AND ERRORS INVOLVING CHANGES IN PEAK CLADDING TEMPERATURE (PCT)
(3 Pages Follow)
L-MT-14-054 Page 1 of 3 Table 1 - Summary of Monticello LOCA Changes and Errors Involving Changes in Peak Cladding Temperature Licensing Basis Applicable Analysis or Error Description Ref.
PCT(°F)
GE14 NEDC-33322P, Revision 3, Safety Analysis Report for Monticello 1&2 < 2140 Constant Pressure Power Uprate PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (1 0 CFR 50.46 Notification Letter 2012-01, Revision 1)
This change is due to the application of an NRC-approved 3 + 10 procedure to estimate the change in Peak Clad Temperature (PCT) due to the change in fuel properties from GESTR to
- PRIME primarily to address inaccuracies in fuel pellet thermal conductivity as a function of exposure.
SAFER04A E4-Maintenance Update Changes (1 0 CFR 50.46 Notification Letter 2014-01)
This change is for a new version (E4) of SAFER04A that 4 +0 resolves several accumulated observations that are code maintenance items. Sensitivity calculations show these items have an insignificant effect on calculated PCT.
SAFER04A E4-Mass Non-Conservatism (10 CFR 50.46 Notification Letter 2014-02)
This change is due to a logic error that occurs when upper plenum liquid mass and core spray flow rate are low. System mass is gradually lost due to core spray being discarded, 5 + 15 resulting in marginally less ECCS flow credited as reaching the core.
L-MT-13-054 Page 2 of 3 Licensing Basis Applicable Analysis or Error Description Ref.
PCT(°F)
GE14 SAFER04A E4-Minimum Core DP Model (10 CFR 50.46 Notification Letter 2014-03) 6 + 20 This change is due to the use of a minimum differential pressure that could be non-conservative offering inappropriate steam cooling benefit above the core two-phase level.
SAFER04A E4-Bundle/Lower Plenum CCFL Head (1 0 CFR 50.46 Notification Letter 2014-04) 7 - 15 This change is due to the counter current flow limitation (CCFL) calculation representing the pressure head slightly different from that of the calculated water level in the bundle.
Sum of absolute value of changes during the current reporting period. 50 Sum of absolute value of changes since last Analysis of Record (AOR). 60 Algebraic sum of changes during the current reporting period. + 20 Algebraic sum of changes since last A OR. + 30 Current Adjusted Peak Cladding Temperature < 2170 The GE Hitachi Notification Letters that result in the submittal of this 10 CFR 50.46 30-day report are those listed above that have been issued for the year 2014 (i.e.,
those that are listed below the heavy black line in the above table).
L-MT-13-054 Page 3 of 3 References
- 1. GE Report: NEDC-33322P, Revision 3, "Safety Analysis Report for Monticello Constant Pressure Power Uprate," dated October 2008. [Submitted as Enclosure 5 of letter L-MT-08-52, dated November 5, 2008.]
- 2. NSPM to NRC letter, "Monticello Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement for Analytical Methods Used to Address Thermal Conductivity Degradation and Analytical Methods Limitations (TAG Nos. MD9990 and ME3145)," (L-MT-13-053) dated July 8, 2013.
- 3. GE Hitachi (GEH) 10 CFR 50.46 Notification Letter 2012-01, Revision 1, "PRIME Fuel Properties Implementation for Fuel Rod T I M Performance, replacing GESTR Fuel Properties," dated July 30, 2013.
- 4. GEH 10 CFR 50.46 Notification Letter 2014-01, "SAFER04A E4-Maintenance Update Changes," dated May 21, 2014.
- 5. GEH 10 CFR 50.46 Notification Letter 2014-02, "SAFER04A E4-Mass Non-Conservatism," dated May 21, 2014.
- 6. GEH 10 CFR 50.46 Notification Letter 2014-03, "SAFER04A E4-Minimum Core DP Model," dated May 21, 2014.
- 7. GEH 10 CFR 50.46 Notification Letter 2014-04, "SAFER04A E4-Bundle/ Lower Plenum CCFL Head," dated May 21, 2014.
- 8. NSPM to NRC letter, "Report of Changes in Emergency Core Cooling System Evaluation Models," (L-MT-14-004) dated January 10, 2014.