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MONTHYEARML14232A0232014-10-21021 October 2014 Request for Additional Information, Submittal of Reactor Vessel Internals Aging Management Program Consistent with MRP-227-A Project stage: RAI W3F1-2015-0005, Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program2015-01-19019 January 2015 Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program Project stage: Response to RAI ML15107A4112015-04-22022 April 2015 Request for Additional Information Regarding the Reactor Vessel Internals Aging Management Program Project stage: RAI ML15170A3792015-06-18018 June 2015 PWROG-15054-NP, Revision 1, Waterford, Unit 3, RAI Response for Applicant Action Items 1, 2, and 7. Project stage: Other ML15170A3782015-06-18018 June 2015 PWROG-15039-NP, Revision 0, Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability. Project stage: Other W3F1-2015-0038, Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program2015-06-18018 June 2015 Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program Project stage: Response to RAI W3F1-2015-0052, Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program2015-07-0909 July 2015 Response to Request for Additional Information Regarding Reactor Vessel Internals Aging Management Program Project stage: Response to RAI ML15267A7972015-10-0606 October 2015 Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals Project stage: Approval 2015-10-06
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Category:Response to Request for Additional Information (RAI)
MONTHYEARML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 “Risk-Informed Categorization and Treatment for Repair ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0041, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System2021-06-0202 June 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L W3F1-2020-0062, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62020-12-15015 December 2020 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 W3F1-2020-0043, Response to NRC Request for Additional Information Regarding License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2020-07-0606 July 2020 Response to NRC Request for Additional Information Regarding License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2020-0033, (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.8.1, A.C. Sources Operating2020-05-29029 May 2020 (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.8.1, A.C. Sources Operating CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary W3F1-2019-0056, Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-12019-07-31031 July 2019 Revision to Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1 W3F1-2019-0054, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-12019-07-22022 July 2019 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1 W3F1-2019-0040, Response to U. S. Nuclear Regulatory Commission Second Round Request for Additional Information Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side2019-07-11011 July 2019 Response to U. S. Nuclear Regulatory Commission Second Round Request for Additional Information Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Intern W3F1-2019-0039, (Waterford 3) - Response to Request for Additional Information Regarding Relief Request W3-ISI-0322019-07-0808 July 2019 (Waterford 3) - Response to Request for Additional Information Regarding Relief Request W3-ISI-032 W3F1-2019-0005, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update2019-02-15015 February 2019 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Proposed Change to Technical Specification 3/4.7.4 for Ultimate Heat Sink Design Basis Update W3F1-2019-0011, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Request WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay2019-02-0404 February 2019 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding Relief Request WF3-RR-19-1 for Application of Dissimilar Metal Weld Full Structural Weld Overlay W3F1-2019-0002, (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across2019-01-19019 January 2019 (Waterford 3) - Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request Regarding Use of the Tranflow Code for Determining the Pressure Drops Across W3F1-2018-0067, Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-0312018-11-19019 November 2018 Response to NRC Request for Alternative to ASME Code Case N-770-2, Successive Examinations, Relief Request W3-ISI-031 W3F1-2018-0059, (Waterford 3) - Response to NRC Request for Additional Information Regarding License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position ...2018-10-18018 October 2018 (Waterford 3) - Response to NRC Request for Additional Information Regarding License Amendment Request to Update the Results for the Inadvertent Loading of a Fuel Assembly Into the Improper Position ... CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station W3F1-2018-0020, Responses to Request for Additional Information Set 18 Regarding the License Renewal Application2018-04-23023 April 2018 Responses to Request for Additional Information Set 18 Regarding the License Renewal Application ML18101A0962018-04-10010 April 2018 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2018007) and Request for Information W3F1-2017-0039, Responses to Request for Additional Information Set 17 Regarding the License Renewal Application2017-05-12012 May 2017 Responses to Request for Additional Information Set 17 Regarding the License Renewal Application W3F1-2017-0027, Responses to Request for Additional Information Set 16 Regarding the License Renewal Application2017-05-0202 May 2017 Responses to Request for Additional Information Set 16 Regarding the License Renewal Application ML17114A4322017-04-21021 April 2017 Responses to Request for Additional Information for the Environmental Review (SAMA Round 2) Regarding the License Renewal Application W3F1-2017-0026, Responses to Request for Additional Information Set 15 Regarding the License Renewal Application2017-04-11011 April 2017 Responses to Request for Additional Information Set 15 Regarding the License Renewal Application W3F1-2017-0023, Responses to Request for Additional Information Set 14 Regarding the License Renewal Application2017-03-30030 March 2017 Responses to Request for Additional Information Set 14 Regarding the License Renewal Application W3F1-2017-0015, Responses to Request for Additional Information Set 13 Regarding the License Renewal Application2017-03-16016 March 2017 Responses to Request for Additional Information Set 13 Regarding the License Renewal Application W3F1-2017-0018, Supplement to Response to RAI on License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System Subgroup Relays to Surveillance.2017-02-27027 February 2017 Supplement to Response to RAI on License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System Subgroup Relays to Surveillance. ML17054D2392017-02-23023 February 2017 Responses to Request for Additional Information Set 12 Regarding the License Renewal Application ML17024A2392017-02-0707 February 2017 Alternatives RAI-AL-3 Lanning 2014_Correspondence Lanning-Entergy to Buckley-Entergy ML17038A2642017-02-0707 February 2017 Surface Water Resources (Sw)Rai SW-11 Usace NNOD-SP (Mississippi River) 796 Permit ML17034A3232017-02-0707 February 2017 Aquatic Resources (AR)- RAI AR-7 Ensr 2005_W1&2 PIC ML17030A1872017-02-0707 February 2017 Aquatic RESOURCES-RAI AR-6 LPDES Permit Modification_2008 ML17038A2772017-02-0707 February 2017 Surface Water Resources (SW) RAI SW-11 Ldwf Letter of No Objection ML17037D0552017-02-0707 February 2017 Groundwater Resources (Gw) RAI GW-1 WF3 Groundwater Monitoring Program_Five-Year Review ML17018A2052017-02-0707 February 2017 Air Quality RAI AQ-2 USGS Gage 07374000 at Baton Rouge ML17037D0362017-02-0707 February 2017 Cumultive Impacts (Cu) RAI CU-1 Reasonably Foreseeable Future Projects within WF3 Area ML17038A4362017-02-0707 February 2017 Responses to Request for Additional Information for the Environmental Review ML17024A1702017-02-0707 February 2017 Alternatives RAI AL-1 Power Replacement Suitable Sites ML17018A1862017-02-0707 February 2017 Air Quality- RAI AQ-2 Temperature Analysis Mississippi River ML17037D2822017-02-0707 February 2017 Surface Water Resources (Sw)Rai SW-1 WF3 Surface Water Withdrawals_Discharges_2011-2015 ML17024A1932017-02-0707 February 2017 Alternatives RAI AL-3 - Enercon 2015b_Calc Supporting Section 07_01 Alternatives ML17024A2472017-02-0707 February 2017 Aquatic Resources RAI AR-4 -Entergy 2005_WF3 316(b) Proposal for Information Collection ML17038A2802017-02-0707 February 2017 Surface Water Resources (SW) RAI SW-11 U.S. Coast Guard Permit CG-2554.pdf 2024-04-10
[Table view] Category:Topical Report
MONTHYEARML21312A4782021-11-0505 November 2021 NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator ML15170A3792015-06-18018 June 2015 PWROG-15054-NP, Revision 1, Waterford, Unit 3, RAI Response for Applicant Action Items 1, 2, and 7. ML15170A3782015-06-18018 June 2015 PWROG-15039-NP, Revision 0, Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability. ML0608603342006-03-31031 March 2006 Responses to NRC Requests for Additional Information on WCAP-16208-P, Rev. 1, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions for Waterford, Unit 3 ML0527101642005-09-22022 September 2005 Westinghouse - Meeting Slides 9/22/05 ML0512604192005-03-31031 March 2005 CENPD-279, Supplement 16, Annual Report on Combustion Engineering ECCS Performance Evaluation Models for Pwrs. ML0423902142004-08-20020 August 2004 Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120) ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. W3F1-2003-0020, Submittal of Second Reactor Vessel Surveillance Capsule Report2003-03-28028 March 2003 Submittal of Second Reactor Vessel Surveillance Capsule Report ML0223901832002-08-15015 August 2002 Combustion Engineering Owners Group Request for Review of CE Owners Group Report WCAP-15691 Rev 03, Joint Applications Report for Containment Integrated Leak Rate Test Interval Extension. ML19066A0851986-04-30030 April 1986 CPC and Methodology Changes for the CPC Improvement Program (CEN-310-NP-A 8605270198) 2021-07-19
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Text
Attachment 4 to W3F1 -2015-0038 PWROG-15039-NP
WESTINGHOUSE NON-PROPRIETARY CLASS 3 PWROG-15039-NP Revision 0 Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability PA-MSC-0983, Revision 1, Task 7 Kurt D. Bevington*
Containment and Radiological Analysis Eugene T. Hayes*
Radiation Engineering and Analysis June 3, 2015 Reviewer: Arzu Alpan*
Radiation Engineering and Analysis Approved: Laurent P. Houssay*, Manager Radiation Engineering and Analysis Approved: James P. Molkenthin*, Program Director PWR Owners Group PMO
- Electronically approved records are authenticated in the electronic document management system.
Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA
© 2015 Westinghouse Electric Company LLC All Rights Reserved
WESTINGHOUSE NON-PROPRIETARY CLASS 3 iii ACKNOWLEDGEMENTS This report was developed and funded by the PWR Owners Group under the leadership of the participating utility representatives of the Materials Committee.
June 3, 2015 PWROG-1 5039-NP PWROG-15039-NP June 3, 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 iv LEGAL NOTICE This report was prepared as an account of work performed by Westinghouse Electric Company LLC. Neither Westinghouse Electric Company LLC, nor any person acting on its behalf:
- 1. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or
- 2. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this report.
COPYRIGHT NOTICE This report has been prepared by Westinghouse Electric Company LLC and bears a Westinghouse Electric Company copyright notice. As a member of the PWR Owners Group, you are permitted to copy and redistribute all or portions of the report within your organization; however all copies made by you must include the copyright notice in all instances.
DISTRIBUTION NOTICE This report was prepared for the PWR Owners Group. This Distribution Notice is intended to establish guidance for access to this information. This report (including proprietary and non-proprietary versions) is not to be provided to any individual or organization outside of the PWR Owners Group program participants without prior written approval of the PWR Owners Group Program Management Office. However, prior written approval is not required for program participants to provide copies of Class 3 Non-Proprietary reports to third parties that are supporting implementation at their plant, and for submittals to the NRC.
PWROG-15039-NP June 3, 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 V TABLE OF CONTENTS MRP 2013-025 GUIDELINES TO DEMONSTRATE MRP-227-A APPLICABILITY FOR WATERFORD UNIT 3 REACTOR INTERNALS AGING MANAGEMENT FUEL DESIGN / FUEL MANAGEMENT ASSESSMENTS ............................................ 1-1 1.1 WATERFORD UNIT 3 EVALUATION FOR QUESTION 2 ................................. 1-1 1.1.1 Components Located Beyond the Outer Radius of the Reactor C o re ................................................................................................... 1-2 1.1.2 Components Located Above the Reactor Core ................................... 1-2 1.1.3 Components Located Below the Reactor Core ................................... 1-3 2 R E F E R E NC E S ............................................................................................................. 2-1 PWROG-15039-NP JRne 3, 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-1 MRP 2013-025 GUIDELINES TO DEMONSTRATE MRP-227-A APPLICABILITY FOR WATERFORD UNIT 3 REACTOR INTERNALS AGING MANAGEMENT FUEL DESIGN / FUEL MANAGEMENT ASSESSMENTS Applicant/Licensee Action Item 1 from the U.S. Nuclear Regulatory Commission (NRC) staff's final safety evaluation of MRP-227-A, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," [1] states that:
"The MaterialsReliability Program indicated that each applicant/licenseewas responsible for assessingits plant's operatinghistory and demonstratingthat the approved version of MRP-227 is applicable to the facility. Each applicant/licensee shall refer, in particular,to the assumptionsregardingplant design and operating history made in the FMECA and functionality analyses for reactorsof their design (i.e., Westinghouse, CE, or B&W) which support MRP-227, and each applicant/licenseeshall describe the process used for determiningplant-specific differences in the design of their reactorvessel integrity components or plant operatingconditions, which result in different component inspection categories."
In the Reference 2 Request for Additional Information (RAI) 2, the NRC provided the following question to Entergy Operations, Inc. regarding the reactor vessel internals aging management program submitted for Waterford Unit 3 (WF3).
RAI-2-B:
"Pleaseexplain if WF3 has ever utilized atypical design or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representativefor thatplant, including power changes/upratessuch as the extended power uprate implemented in 2005. ... "
1.1 WATERFORD UNIT 3 EVALUATION FOR QUESTION 2 Westinghouse has evaluated the Waterford Unit 3 reactor internals components with regard to fuel designs and fuel management according to industry guideline MRP 2013-025 [3].
Waterford Unit 3 has not utilized atypical fuel designs or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representative, including power changes/uprates that have occurred over the operating lifetime of the unit. This conclusion is based on comparisons of the Waterford Unit 3 core geometry and operating characteristics with the MRP-227-A applicability guidelines for CE-designed reactors specified in MRP 2013-025 [3].
PWROG-15039-NP June 3, 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-2 Performing the MRP 2013-025 [3] guideline assessment using a calendar years basis is not required but would provide bounding results. Demonstrating that the fluence guideline compliance requirement is met based on effective full-power years, as was done in this evaluation, is acceptable and provides a technically robust and accurate assessment of plant-specific historical operating conditions.
Specifically, the following comparisons with the MRP-227-A applicability guidelines in MRP 2013-025 [3] were established for the key reactor internals components at Waterford Unit 3.
1.1.1 Components Located Beyond the Outer Radius of the Reactor Core Guideline 1 - The reactor has been operated with out-in fuel management for 30 effective full-power years or less and all future operation will use low-leakage fuel management.
Comparison -Waterford Unit 3 initiated low-leakage fuel management strategy in the third fuel cycle following 2.0 effective full-power years of operation and has been implementing low-leakage core designs since that time.
Guideline 2 - For operation going forward, the average power density of the reactor core (as defined in MRP 2013-025 [3]) shall be less than 110 W/cm 3 .
Comparison - For the last five operating fuel cycles (Cycles 15 through 19), Waterford Unit 3 has been operating at a rated power level of 3716 MWt. For the 217 fuel assembly Waterford Unit 3 core geometry, the 3716 MWt power level corresponds to a core power density of 104.1 W/cm 3. This level of power generation is also representative of anticipated future operation.
Guideline 3 - For operation going forward, the nuclear heat generation rate figure of merit (HGR-FOM) (as defined in MRP 2013-025 [3]) shall not exceed 68 W/cm 3.
Comparison -For the last five operating fuel cycles at Waterford Unit 3, the HGR-FOM at key baffle locations has ranged between [ ]a~c. This range of HGR-FOM is representative of anticipated future operation.
1.1.2 Components Located Above the Reactor Core Guideline 1 - Considering the entire operating lifetime of the reactor, the average power density of the core (as defined in MRP 2013-025 [3]) shall be less than 110 W/cm 3 for a period of more than two effective full-power years.
Comparison -Over the operating lifetime of the Waterford Unit 3 reactor, the rated core power level, including power uprates, has varied between 3390 MWt and 3716 MWt. This variation of rated power level corresponds to a power density range of 95.0 W/cm 3 to 104.1 W/cm 3.
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WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-3 WESTINGHOUSE NON-PROPRIETARY CLASS 3 1-3 Guideline 2 - Considering the entire operating lifetime of the reactor, the distance between the top of the active fuel stack and the bottom of the fuel alignment plate (FAP) shall be greater than 12.4 inches for a period of more than two effective full-power years.
Comparison - For the Waterford Unit 3 reactor internals and fuel assembly geometry, the nominal distance between the top of the active fuel stack and the bottom of the FAP averaged over the first 19 fuel cycles of operation was I ]a~c. During that period of time, the nominal distance between the FAP and the top of the active fuel was greater than 12.4 inches.
1.1.3 Components Located Below the Reactor Core Based on the discussion provided in MRP 2013-025 [3], plant-specific applicability of MRP-227-A for components located below the reactor core with no further evaluation required is demonstrated by meeting the MRP-227-A, Section 2.4 criteria.
PWROG-15039-NP June 3, 2015 Revision 0
WESTINGHOUSE NON-PROPRIETARY CLASS 3 2-1 2 REFERENCES
- 1. Materials Reliability Program:PressurizedWater Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.
- 2. U.S. NRC Letter, "Waterford Steam Electric Station, Unit 3 - Request for Additional Information Regarding the Reactor Vessel Internals Aging Management Program (TAC No. MF3247)," October 21, 2014. (NRC ADAMS Accession No. ML14232A023)
- 3. EPRI Letter MRP 2013-025, "MRP-227-A Applicability Template Guideline,"
October 14, 2013. (NRC ADAMS Accession No. ML13322A454)
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