ML20147A039
| ML20147A039 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/15/2020 |
| From: | Duke Energy Progress |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20147A016 | List:
|
| References | |
| RA-20-0134 | |
| Download: ML20147A039 (4) | |
Text
Page 1 Information Removed from Amendment 63 of the Updated Final Safety Analysis Report Shearon Harris Nuclear Power Plant, Unit 1 (HNP)
Impacted Related Discussion Sections/Tables/Figures Sections The original reactor vessel head (RVH) was replaced 3.5.1.1.2.1.1; 3.9.4.1; 3.9.4.3; during refueling outage 22 (RFO-22). The 4.5.1.3; 4.5.2.1; 5.2.3.1; 5.2.3.2.2; replacement RVH includes integrated control rod 5.2.4.2.1; 5.3.1.2; 5.3.1.3.2; drive mechanism (CRDM) latch housings that are 5.3.3.1; 5.3.3.3; 5.3.3.5; 5.3.3.7; welded to the head penetration nozzles with a full 15.4.8.1.1; 18.2.2.3 penetration butt weld that eliminates the lower canopy welds of the original design. The CRDMs were Tables replaced during RFO-22 as well. The replacement 3.2.1-1; 3.5.1-4; 3.9.2-1; 5.2.1-1; CRDM integrated rod travel housing is a one-piece 5.2.3-1; 5.2.3-2; 5.3.1-1; 5.3.1-2; design that eliminates the top cap. Information 5.3.3-1 related to the original RVH that is no longer applicable to the HNP design was replaced by Figures information pertinent to the new RVH.
3.9.4-1; 3.9.4-2; 5.3.3-1 Section The Boraflex Monitoring Program was removed since 18.1.1.12 Boraflex is no longer credited in the HNP criticality analysis for spent fuel storage racks. This change is associated with Renewed Operating License Amendment No. 167 (ADAMS Accession No. ML18204A286).
Section Information related to operating organization 13.1.2 personnel functions, responsibilities, and authorities was updated to reflect current organizational structure.
Sections High-energy line breaks (HELBs) inside the Reactor 3.6.2.1.1.3; 3.6A.2.1.2.2; 3.6A.2.3; Auxiliary Building (RAB) have been analyzed and 3.6A.6.4 evaluated using a new GOTHIC-based computer model and other supporting calculations. Content has Tables been revised to clarify that Generic Letter 87-11 no 3.6A-4; 3.6A-13 longer requires a minimum of two arbitrary intermediate breaks to be postulated between Figures terminal piping ends. Tables and figures showing pipe 3.6A-12-CALC; 3.6A-12-PLOT-C; whip restraints, break identification numbers, and 3.6A-12-PLOT-D; 3.6A-12-PLOT-F; break locations were revised to delete terminal-end 3.6A-12-PLOT-G; 3.6.A-25-CALC; breaks exempted by the analysis and to correct 3.6A-25-PLOT-A; 3.6A-25-PLOT-B; administrative errors.
3.6A-25-PLOT-C Section The seismic monitoring magnetic tape recorder and 3.7.4 analog playback system were replaced with a digital recorder and digital display system. Information was Table updated to reflect this change.
3.7.4-1
Page 2 Impacted Related Discussion Sections/Tables/Figures Sections Vendor-generated Chapter 15 dose consequence 15.0A.1.1; 15.1.5.3; 15.1.5.3.3; analyses were replaced by applying the in-house dose 15.1.5.3.5; 15.1.5.3.6; 15.2.6.3.4; computational tool, LOCADOSE, to generate dose 15.2.6.3.5; 15.3.3.3; 15.3.3.3.2; results using Alternative Source Term (AST) 15.3.3.3.3; 15.3.3.4; 15.4.3.2.3; methodology consistent with the current HNP 15.4.7.3; 15.4.8.3.3; 15.6.2.3.1.2; licensing basis. This includes revising the Main Steam 15.6.2.3.1.4; 15.6.2.3.1.5; Line Break (MSLB) analysis to eliminate the fuel 15.6.3.4; 15.6.3.4.3; 15.6.3.4.6; failure source term dose analysis case to reflect that 15.6.3.4.7; 15.6.5.4.2; 15.6.5.5; per Regulatory Guide 1.183, Appendix E, Assumptions 15.6.5.5.1; 15.6.5.5.2; 15.6.5.5.3; for Evaluating the Radiological Consequences of a 15.6.5.5.4; 15.6.5.5.5; 15.7.1.3.2; PWR Main Steam Line Break Accident, and the NRC-15.7.1.3.3; 15.7.4.2.5; 15.7.4.2.6 approved AST methodology for HNP, when no fuel failure is predicted to occur due to the MSLB accident Tables then two iodine spiking cases should be evaluated in 15.1.5-5; 15.1.5-6; 15.2.6-6; lieu of assuming a fuel failure case.
15.3.3-6; 15.3.3-7; 15.4.3-5; 15.4.3-6; 15.4.8-5; 15.4.8-6; 15.6.2-2; 15.6.3-6; 15.6.3-13; 15.6.5-15; 15.6.5-16; 15.6.5-17; 15.6.5-18; 15.7.1-2; 15.7.4-2; 15.7.4-4 Sections Beginning with the cycle 23 core design, non-LOCA 4.2.2.3; 4.3.1.1; 4.3.1.3; 4.3.1.4.1; nuclear design and safety analyses were performed 4.3.1.4.2; 4.3.1.5; 4.3.1.6; using Duke Energy methods approved for use by 4.3.2.2.1; 4.3.2.2.2; 4.3.2.2.3; license amendments issued by the NRC. The changes 4.3.2.2.4; 4.3.2.2.5; 4.3.2.2.6; made reflect the transition to the Duke nuclear 4.3.2.2.7; 4.3.2.2.8; 4.3.2.2.9; design and safety analysis methods used to confirm 4.3.2.3; 4.3.2.3.1; 4.3.2.3.2; the acceptability of postulated Chapter 15 accidents, 4.3.2.3.5; 4.3.2.4.11; 4.3.2.4.13; and to describe the nuclear software used to 4.3.2.4.15; 4.3.2.5; 4.3.3; 4.3.3.1; calculate nuclear physics data core power 4.3.3.2; 7.7.1.3.1 distributions. The change to Section 7.7.1.3.1 reflects the removal of the reference to the PDC-3 core Tables monitoring software.
4.1.1-2; 4.3.2-1; 4.3.2-2; 4.3.2-3; 4.3.2-21; 4.3.2-38; 4.3.2-39 Section Information related to redundant safety grade flow 9.2.2.5 instrumentation for detecting loss of component cooling water to the oil coolers of the reactor coolant pump motors was removed. The removal of these sentences removed redundant, irrelevant, and incorrect statements. The abandoned flow switches do not perform a design function.
Page 3 Impacted Related Discussion Sections/Tables/Figures Section Information related to containment jib crane was 18.2.6.2 removed due to the cranes permanent removal.
Tables 6.1.1-2; 6.2.5-4 Sections A new GOTHIC containment model was created for 6.2.1.1.3.2, Appendix 6.2A; the HNP Chapter 6 containment analysis. The new 9.2.1.3.1; 9.2.5.3.1 GOTHIC model replaced the existing CONTEMPT analysis of record, and the FSAR was updated Tables accordingly. Additionally, information related to 6.2.1-50; 9.2.1-5; 9.2.1-10; material thermal conductivity, volumetric heat 9.2.1-11 capacity, average node spacing, and heat rejection was removed on the basis that it was excessively detailed information.
Sections Information related to the power range high negative 3.9.1.1.2; 7.2.1.1.2 neutron flux rate trip was removed as aligned with the update to the HNP Technical Specifications per Tables License Amendment No. 175 (ADAMS Accession No.
7.2.1-1; 7.2.1-3 ML19225C069). Additionally, parameter values associated with Core Thermal Overpower Trips were removed and point to the Core Operating Limits Report in accordance with changes to the HNP Technical Specifications per License Amendment No.
161 (ADAMS Accession No. ML17250A202).
Sections Content has been updated to reflect the approval of 15.0; 15.0.3.1; 15.0.3.2; 15.0.3.3; Duke Energy methodologies per License Amendment 15.0.3.4; 15.0.4; 15.0.5; 15.0.6; Nos. 157, 164, and 171 (ADAMS Accession Nos.
15.0.7; 15.0.8; 15.0.10.3; ML17102A923, ML18060A401, and ML19290F980, 15.0.11.2; 15.0.11.2.1; respectively). Content related to previous 15.0.11.2.4; 15.0.11.3; 15.0.13; Framatome, Inc. methods and computer codes that 15.1.1; 15.1.3; 15.1.5; 15.2.3; are no longer applicable following the 15.2.8; 15.3.1; 15.3.2; 15.3.3; implementation of Duke Energy methods has been 15.4.1; 15.4.2; 15.4.3.1; 15.4.3.2; removed.
15.4.3.3; 15.4.4; 15.4.6; 15.4.7; 15.4.8; 15.5.1; 15.6.1; 15.6.3 Tables 15.0.3.6; 15.0.13-1; 15.0.3-5; 15.0.6-2; 15.0.8-1; 15.1.3-1; 15.1.3-2; 15.1.3-3; 15.1.3-4; 15.1.5-3; 15.2.3-1; 15.2.3-2; 15.2.3-3; 15.2.3-4; 15.2.3-5; 15.2.3-6; 15.2.8-1; 15.2.8-2; 15.2.8-3; 15.2.8-4; 15.2.8-5; 15.2.8-7; 15.2.8-8; 15.3.2-1; 15.3.2-2; 15.3.2-3; 15.3.2-4;
Page 4 Impacted Related Discussion Sections/Tables/Figures 15.3.3-1; 15.3.3-2; 15.3.3-3; 15.3.3-4; 15.3.3-5; 15.4.1-1; 15.4.1-2; 15.4.1-3; 15.4.1-4; 15.4.2-1; 15.4.2-2; 15.4.2-2a; 15.4.2-3; 15.4.2-4; 15.4.2-5; 15.4.3-1; 15.4.3-2; 15.4.3-3; 15.4.3-4a; 15.4.3-6; 15.4.3-7; 15.4.3-8; 15.4.3-9; 15.4.6-2; 15.4.7-1; 15.4.8-1; 15.4.8-2; 15.4.8-3; 15.4.8-4b; 15.5.1-1; 15.5.1-2; 15.5.1-3; 15.5.1-4; 15.6.1-1; 15.6.1-2; 15.6.1-3; 15.6.1-4 Figures 15.0.5-4; 15.0.5-5; 15.0.5-6; 15.1.3-1; 15.1.3-2; 15.1.3-3; 15.1.3-4; 15.1.5-1; 15.1.5-2; 15.1.5-3; 15.1.5-4; 15.1.5-5; 15.1.5-6; 15.2.3-1; 15.2.3-2; 15.2.3-3; 15.2.3-4; 15.2.3-5; 15.2.3-6; 15.2.3-7; 15.2.3-9; 15.2.3-10; 15.2.3-11; 15.2.3-12; 15.2.8-1 through 15.2.8-32; 15.3.2-1; 15.3.2-2; 15.3.2-3; 15.3.2-4; 15.3.2-5; 15.3.2-6; 15.3.2-7; 15.3.3-1 through 15.3.3-13; 15.4.1-1; 15.4.1-2; 15.4.1-3; 15.4.1-4; 15.4.2-1; 15.4.2-2; 15.4.2-3; 15.4.2-5; 15.4.2-6; 15.4.2-7; 15.4.2-8; 15.4.2-9; 15.4.2-10; 15.4.3-1; 15.4.3-2; 15.4.3-3; 15.4.3-4; 15.4.3-6; 15.4.3-7; 15.4.3-8; 15.4.3-10; 15.4.3-11; 15.4.3-12; 15.4.3-13; 15.4.3-14; 15.4.3-15; 15.4.8-9 through 15.4.8-16; 15.5.1-1 through 15.5.1-14; 15.6.1-1 through 15.6.1-7