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| number = ML13205A214 | | number = ML13205A214 | ||
| issue date = 07/30/2013 | | issue date = 07/30/2013 | ||
| title = | | title = Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station | ||
| author name = | | author name = | ||
| author affiliation = Wolf Creek Nuclear Operating Corp | | author affiliation = Wolf Creek Nuclear Operating Corp | ||
Line 9: | Line 9: | ||
| docket = 05000482 | | docket = 05000482 | ||
| license number = NPF-042 | | license number = NPF-042 | ||
| contact person = Lyon C | | contact person = Lyon C | ||
| case reference number = TAC MF2309 | | case reference number = TAC MF2309 | ||
| document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts | | document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts | ||
| page count = 29 | | page count = 29 | ||
| project = TAC:MF2309 | |||
| stage = Meeting | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:WCNOC-NRC WCNOC NRC Pre-submittal Pre submittal Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request July 30 30, 2013 Wolf Creek Nuclear Operating p g Corporation p | |||
1 | |||
Meeting Agenda | |||
* Meeting M ti PPurpose / Objectives Obj ti | |||
* Introductions | |||
* License Amendment Request (LAR) Content | |||
* Transition to Westinghouse Analysis Methodologies | |||
* RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaintyy Analysis y | |||
* Alternative Source Term (AST) | |||
* LAR Schedule | |||
* Summary 2 | |||
===Introductions=== | |||
* NRC | |||
* WCNOC Team | |||
* Westinghouse Support | |||
* Teleconference Attendees 3 | |||
WCNOC Ownership of Safety Analysis | |||
* WCNOC O Ownership hi off ththe S Safety f t AAnalysis l i iis d demonstrated t t d through the strength and application of the Quality Assurance (QA) Program | |||
- WCNOC technical oversight is provided by the QA processes and participation in NUPIC | |||
- WCNOC QA | |||
* T Transmittal itt l off Design D i Information I f ti - referenced f d tto the th source calculation, design basis document, or identified as a direct input | |||
* Owners Acceptance Review | |||
* Configuration Management updates, regulatory reviews, etc. | |||
* WCNOC/Westinghouse (WEC) Interface | |||
- On-site WEC staff responsible for core design and safety analysis | |||
- On-site On site WEC staff maintains qualifications in both the WCNOC and WEC QA programs. Proper independence is always maintained between the QA programs. 4 | |||
License Amendment Request Content | |||
* License Amendment Request (LAR) to revise the WCGS Technical Specifications (TSs) based on: | |||
- Transition to Westinghouse core design and safety analysis methodologies | |||
- Transition to Westinghouse Setpoint Methodology | |||
- Full Scope Implementation of Alternative Source Term (AST) 5 | |||
License Amendment Request Content | |||
* LAR is consistent with NEI 06-02, License Amendment Request (LAR) Guidelines template Attachments: | |||
I - Evaluation II - Proposed p TS Changes g ((Mark-up) p) | |||
III - Revised TS pages IV - Proposed TS Bases Changes (info only) | |||
V - Proposed COLR Changes (info only) 6 | |||
License Amendment Request Content | |||
* LAR content (cont.) | |||
(cont ) | |||
==Enclosures:== | |||
I - WCAP 17658 NP - Transition Licensing Report WCAP-17658-NP II - WCAP-17746-P - Setpoint Methodology for WCGS III - WCAP-17746-NP IV - WCAP-17602-P - Setpoint Calculations for WCGS V - WCAP-17602-NP VI - Full Scope Implementation of Alternative Source Term VII - CD-ROM containing Meteorological Data VIII - Proprietary Information Affidavit for WCAP-17746-P IX - Proprietary Information Affidavit for WCAP-17602-P 7 | |||
Transition to Westinghouse Analysis Methodologies | |||
* Core C D Designi and dS Safety f t Analysis A l i Methodology M th d l | |||
- The Non-LOCA safety analyses were analyzed with g | |||
Westinghouse, , NRC approved pp methods | |||
- All of the Westinghouse Non-LOCA methods are applicable to the WCGS | |||
- The Containment response analyses of record are not impacted | |||
- The SBLOCA and LBLOCA analyses of record are not impacted | |||
- The Core Design and Fuel Rod Design will be y | |||
evaluated for each reload cycle 8 | |||
Transition to Westinghouse Analysis Methodologies | |||
* Overview O i off Analysis A l i M Methodology th d l S Scope | |||
- Non-LOCA Safety Analyses | |||
* RETRAN-02 for Westinghouse g PWRs ((WCAP-14882-P-A)) | |||
was used for majority of the analyses | |||
* LOFTRAN (WCAP-7907-P-A) was used for some analyses | |||
* Other Codes that were used: | |||
- TWINKLE (WCAP-7979-P-A) | |||
- FACTRAN (WCAP-7908-A) | |||
- Non-LOCA Thermal-Hydraulics (T&H) Safety Analyses | |||
* VIPRE-01 (WCAP-14565-P-A) was used for the T&H analyses | |||
- RETRAN-02 (WCAP-14882-P-A) and WCAP-10698-P-A were used d ffor th the Steam St Generator G t Tube T b Rupture R t Margin M i to Overfill and Input to the Dose analyses 9 | |||
Transition to Westinghouse Analysis Methodologies | |||
* Overview O i off Analysis A l i M Methodology th d l S Scope ((cont.) | |||
t) | |||
- DNB Correlations used in the VIPRE-01 DNBR calculations | |||
* The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions above the first mixing vane grid | |||
* The ABB-NV DNB correlation was used for the T&H analyses of fuel regions below the first mixing vane grid | |||
* The WLOP DNB correlation was used for the T&H analyses that are outside the range of applicability of the WRB-2 and ABB-NV DNB correlations 10 | |||
Transition to Westinghouse Analysis Methodologies | |||
* Implementation off the Westinghouse Non-LOCA OC Safety Analysis Methodology resulted in five changes to the current WCGS TSs | |||
- SLs 2.1.1, Added the ABB-NV and WLOB DNB Correlations | |||
- TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low | |||
- TS 3.4.1, RCS Pressure, Temperature and Flow DNB Limits | |||
* The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm | |||
* The Thermal Design Flow - 361,200 gpm, replaces the MMF 11 | |||
Transition to Westinghouse Analysis Methodologies | |||
* IImplementation l t ti off theth Westinghouse W ti h Non-LOCA N LOCA Safety S f t Analysis Methodology results in five changes to the current WCGS TSs (cont.) ( ) | |||
- TS Table 3.7.1-1, OPERABLE MSSVs versus Maximum Allowable Power, the maximum allowable power for 4, 3, and 2 OPERABLE MSSVs was revised | |||
- TS 5.6.5, COLR | |||
* Added WCAP-9272-P-A, the Westinghouse Reload M th d l Methodology tto S Specification ifi ti 5 5.6.5 65b b. | |||
* Deleted the WCNOC methodologies from Specification 5.6.5 b. | |||
* WCAP-9272-P-A is the only methodology associated with a Tech Spec COLR parameter 12 | |||
Transition to Westinghouse Analysis Methodologies | |||
* Followup F ll ffrom th the 9/20/12 P Pre-Submittal S b itt l M Meeting ti | |||
- Provide a roadmap of which code was used to analyze each postulated accident - Attachment I of the LAR includes a roadmap | |||
- The Limitations, Restrictions and Conditions for the Westinghouse codes used in the Non-LOCA safety analyses are addressed in detail, including justifications in the LAR (Enclosure I, Appendix A) 13 | |||
Instrumentation Setpoint Uncertainty Analysis | |||
* Uncertainty U t i t Analysis A l i | |||
- Transition from the existing WCNOC Setpoint Methodology gy to the current Westinghouse g Setpoint p | |||
Methodology as applied to WCGS for RTS, ESFAS and LOP DG Start Instrumentation (WCAP-17746-P,, Enclosure II of LAR)) | |||
- Technical Specification Changes | |||
* TS 3.3.1,TS 3.3.2, and TS 3.3.5 Allowable Values were replaced with a Nominal Trip Setpoint | |||
* TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14 | |||
Instrumentation Setpoint Uncertainty Analysis | |||
* Uncertainty U t i t Analysis A l i ((cont.) t) | |||
- Calculations were performed for the RTS, ESFAS, and LOP DG Start instrumentation Functions using the current Westinghouse setpoint methodology (WCAP-17602-P, Enclosure IV of LAR)) | |||
- Implementation of the Westinghouse Setpoint Methodology resulted in two changes to the existing WCGS Trip Setpoints | |||
* TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low | |||
* TS 3.3.5, Degraded Voltage Function 15 | |||
Instrumentation Setpoint Uncertainty Analysis | |||
* TSTF TSTF-493-A, 493 A Revision R i i 4, 4 Option O ti A - Technical T h i l Specification Changes | |||
- Variation from Option A - Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint Methodology | |||
- TS changes h include i l d the th addition dditi off individual i di id l Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option p | |||
A of TSTF-493, Revision 4 16 | |||
Instrumentation Setpoint Uncertainty Analysis | |||
* Followup from the 9/20/12 Pre-Submittal Meeting | |||
- The level of detail of the setpoint methodology and setpoint calculations for WCGS is consistent with that in the Diablo Canyon y Power Plant ((DCPP)) | |||
submittal of March 7, 2013 (DCL-13-016) | |||
- WCNOC specific setpoint calculations are provided in WCAP WCAP-17602-P 17602 P (Enclosure IV of LAR) 17 | |||
Alternative Source Term | |||
* Full F ll S Scope IImplementation l t ti off the th AST | |||
- Radiological dose consequences analyses were performed for the accidents specified p p in Regulatory g y Guide (RG) 1.183 include: | |||
* Main Steamline Break (USAR Section 15.1.5.3) | |||
* Locked Rotor (USAR Section 15.3.3.3) 15 3 3 3) | |||
* Rod Ejection (USAR Section 15.4.8.3) | |||
* Steam Generator Tube Rupture (USAR Section 15.6.3.3) | |||
* Loss of Coolant Accident (USAR Section 15.6.5.4) | |||
* Fuel Handling Accident (USAR Section 15.7.4) 18 | |||
Alternative Source Term | |||
* Full Scope Implementation of the AST (cont.) | |||
- Radiological dose consequences analyses performed for additional accidents not specified in RG 1.183 include: | |||
* Loss of Non-Emergency AC Power (USAR Section 15 2 6 3) 15.2.6.3) | |||
* Letdown Line Break (USAR Section 15.6.2.1) | |||
* Waste Gas Decay Tank Failure (USAR Section 15.7.1) | |||
* Liquid Liq id Waste Tank Fail Failure re (USAR Section 15.7.2) 15 7 2) | |||
- Dose consequences analyses were performed using version 3.03 of the RADTRAD computer code d | |||
19 | |||
Alternative Source Term | |||
* Full Scope Implementation of AST (cont.) | |||
- No changes to the licensing basis EQ dose analyses - maintaining the TID TID-14844 14844 accident source term | |||
- No changes to the licensing basis NUREG-0737 evaluations other than the Control Room Habitability Envelope (CHRE) doses (III.D.3.4) and Technical Support Center doses (III (III.A.1.2) | |||
A 1 2) 20 | |||
Alternative Source Term | |||
* Atmospheric Dispersion Factors (X/Q) | |||
- New X/Q values were calculated | |||
* Offsite (EAB and LPZ) X/Q values were calculated using the PAVAN code consistent with RG 1.145 | |||
* Control Room and TSC X/Q values were calculated using the ARCON96 code consistent with RG 1 1.194 194 | |||
- Meteorological Data | |||
* Five years of WCGS site-specific meteorological data from 1/1/2006 through 12/31/2010 was collected | |||
* Data recovery for the 5-year period met the 90% recovery criterion of RG 1.23 21 | |||
Alternative Source Term | |||
* Current licensing basis changes | |||
- Revises USAR Chapter 15 dose analysis for 10 accidents | |||
((includes the 6 DBAs in RG 1.183)) | |||
- New Offsite, Control Room, and TSC atmospheric dispersion factors based on site-specific meteorological data from 2006 throughg 2010 | |||
- Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm | |||
- Revises the Control Building unfiltered inleakage from 300 scfm to 400 scfm | |||
- TS changes to address the update of the accident source term and associated DBAs | |||
- TS changes to address the adoption of TSTF TSTF-51-A, 51 A Revision 2 22 | |||
Alternative Source Term | |||
* Technical T h i lS Specification ifi ti Ch Changes | |||
- Definition of DOSE EQUIVALENT I-131 | |||
* Revised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11 | |||
- Definition of DOSE EQUIVALENT XE-133 | |||
* Revised to only allow the use of the dose conversion factors EPA Federal Guidance Report No. 12 | |||
- Specification 5.5.12, Explosive Gas and Storage Tank Radioactivity Monitoring ProgramProgram | |||
* Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole bodyy exposure p limit to 0.1 rem ((current limit is 0.5 rem) 23 | |||
Alternative Source Term | |||
* Technical T h i lS Specification ifi ti Ch Changes ((cont.) t) | |||
- Adoption of TSTF-51-A, Revision 2, Revise q | |||
Containment Requirements during g Handling g Irradiated Fuel and Core Alterations | |||
* Allows the elimination of the TS requirements for certain g | |||
Engineered Safetyy Feature ((ESF)) systems y to be OPERABLE, after a sufficient radioactive decay has occurred | |||
* Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24 | |||
Alternative Source Term | |||
* E l Enclosure VI off LAR - Sections S ti 1 - DESCRIPTION 2 - PROPOSED CHANGES 3 - BACKGROUND 4 - TECHNICAL ANALYSIS 5 - RG 1.183 CONFORMANCE TABLE 6 - RG 1.145 CONFORMANCE TABLE 7 - RG 1.194 CONFORMANCE TABLE 8 - RIS 2006-04 TABLE 9 - PROPOSED TS MARKUPS 10 - RETYPED TS PAGES 11 - PROPOSED BASES MARKUPS (information only) 12 - PROPOSED TRM and BASES MARKUP (information only) 25 13 - PROPOSED USAR CHANGES (information only) | |||
Alternative Source Term | |||
* Followup from the 9/20/12 Pre-Submittal Meeting | |||
- Meteorological Data - One gap in the recorded data was due to the data logger failure (5/30/2007 through 6/7/2007) | |||
- Provide a detailed plant drawing that shows the potential release paths - site plan provided consistent with the guidance in RIS 2006-04 (Enclosure VI of the LAR) 26 | |||
Alternative Source Term | |||
* Followup from the 9/20/12 Pre-Submittal Meeting (cont) 27 | |||
Schedule | |||
* Submit LAR to NRC August 13, 2013 | |||
* NRC Acceptance Review (30 days per LIC-109) | |||
* Requested Approval Date December 15, 2014 | |||
* Start of Refueling Outage 20 January 5, 2015 | |||
* Cycle 21 Startup February 9, 2015 28 | |||
Summary | |||
* WCNOC iintends t d tto submit b it a LAR on 8/13/13 tto revise i | |||
the WCGS TSs based on: | |||
- Transition to the Westinghouse core design and safety analysis methodologies | |||
- Transition to the Westinghouse Setpoint Methodology | |||
- Full Scope Implementation of the Alternative Source Term (AST) | |||
* Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015) | |||
* Questions/Comments 29}} |
Latest revision as of 16:38, 4 November 2019
ML13205A214 | |
Person / Time | |
---|---|
Site: | Wolf Creek ![]() |
Issue date: | 07/30/2013 |
From: | Wolf Creek |
To: | Office of New Reactors |
Lyon C | |
References | |
TAC MF2309 | |
Download: ML13205A214 (29) | |
Text
WCNOC-NRC WCNOC NRC Pre-submittal Pre submittal Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request July 30 30, 2013 Wolf Creek Nuclear Operating p g Corporation p
1
Meeting Agenda
- Meeting M ti PPurpose / Objectives Obj ti
- Introductions
- License Amendment Request (LAR) Content
- Transition to Westinghouse Analysis Methodologies
- RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertaintyy Analysis y
- LAR Schedule
- Summary 2
Introductions
- NRC
- WCNOC Team
- Westinghouse Support
- Teleconference Attendees 3
WCNOC Ownership of Safety Analysis
- WCNOC O Ownership hi off ththe S Safety f t AAnalysis l i iis d demonstrated t t d through the strength and application of the Quality Assurance (QA) Program
- WCNOC technical oversight is provided by the QA processes and participation in NUPIC
- T Transmittal itt l off Design D i Information I f ti - referenced f d tto the th source calculation, design basis document, or identified as a direct input
- Owners Acceptance Review
- Configuration Management updates, regulatory reviews, etc.
- WCNOC/Westinghouse (WEC) Interface
- On-site WEC staff responsible for core design and safety analysis
- On-site On site WEC staff maintains qualifications in both the WCNOC and WEC QA programs. Proper independence is always maintained between the QA programs. 4
License Amendment Request Content
- Transition to Westinghouse core design and safety analysis methodologies
- Transition to Westinghouse Setpoint Methodology
- Full Scope Implementation of Alternative Source Term (AST) 5
License Amendment Request Content
I - Evaluation II - Proposed p TS Changes g ((Mark-up) p)
III - Revised TS pages IV - Proposed TS Bases Changes (info only)
V - Proposed COLR Changes (info only) 6
License Amendment Request Content
- LAR content (cont.)
(cont )
Enclosures:
I - WCAP 17658 NP - Transition Licensing Report WCAP-17658-NP II - WCAP-17746-P - Setpoint Methodology for WCGS III - WCAP-17746-NP IV - WCAP-17602-P - Setpoint Calculations for WCGS V - WCAP-17602-NP VI - Full Scope Implementation of Alternative Source Term VII - CD-ROM containing Meteorological Data VIII - Proprietary Information Affidavit for WCAP-17746-P IX - Proprietary Information Affidavit for WCAP-17602-P 7
Transition to Westinghouse Analysis Methodologies
- Core C D Designi and dS Safety f t Analysis A l i Methodology M th d l
- The Non-LOCA safety analyses were analyzed with g
Westinghouse, , NRC approved pp methods
- All of the Westinghouse Non-LOCA methods are applicable to the WCGS
- The Containment response analyses of record are not impacted
- The SBLOCA and LBLOCA analyses of record are not impacted
- The Core Design and Fuel Rod Design will be y
evaluated for each reload cycle 8
Transition to Westinghouse Analysis Methodologies
- Overview O i off Analysis A l i M Methodology th d l S Scope
- Non-LOCA Safety Analyses
- RETRAN-02 for Westinghouse g PWRs ((WCAP-14882-P-A))
was used for majority of the analyses
- LOFTRAN (WCAP-7907-P-A) was used for some analyses
- Other Codes that were used:
- TWINKLE (WCAP-7979-P-A)
- FACTRAN (WCAP-7908-A)
- Non-LOCA Thermal-Hydraulics (T&H) Safety Analyses
- VIPRE-01 (WCAP-14565-P-A) was used for the T&H analyses
- RETRAN-02 (WCAP-14882-P-A) and WCAP-10698-P-A were used d ffor th the Steam St Generator G t Tube T b Rupture R t Margin M i to Overfill and Input to the Dose analyses 9
Transition to Westinghouse Analysis Methodologies
- Overview O i off Analysis A l i M Methodology th d l S Scope ((cont.)
t)
- DNB Correlations used in the VIPRE-01 DNBR calculations
- The WRB-2 DNB correlation will continue to be used as the primary DNB correlation for the T&H analyses of fuel regions above the first mixing vane grid
- The ABB-NV DNB correlation was used for the T&H analyses of fuel regions below the first mixing vane grid
- The WLOP DNB correlation was used for the T&H analyses that are outside the range of applicability of the WRB-2 and ABB-NV DNB correlations 10
Transition to Westinghouse Analysis Methodologies
- Implementation off the Westinghouse Non-LOCA OC Safety Analysis Methodology resulted in five changes to the current WCGS TSs
- SLs 2.1.1, Added the ABB-NV and WLOB DNB Correlations
- TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low
- TS 3.4.1, RCS Pressure, Temperature and Flow DNB Limits
- The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm
- The Thermal Design Flow - 361,200 gpm, replaces the MMF 11
Transition to Westinghouse Analysis Methodologies
- IImplementation l t ti off theth Westinghouse W ti h Non-LOCA N LOCA Safety S f t Analysis Methodology results in five changes to the current WCGS TSs (cont.) ( )
- TS Table 3.7.1-1, OPERABLE MSSVs versus Maximum Allowable Power, the maximum allowable power for 4, 3, and 2 OPERABLE MSSVs was revised
- Added WCAP-9272-P-A, the Westinghouse Reload M th d l Methodology tto S Specification ifi ti 5 5.6.5 65b b.
- Deleted the WCNOC methodologies from Specification 5.6.5 b.
- WCAP-9272-P-A is the only methodology associated with a Tech Spec COLR parameter 12
Transition to Westinghouse Analysis Methodologies
- Followup F ll ffrom th the 9/20/12 P Pre-Submittal S b itt l M Meeting ti
- Provide a roadmap of which code was used to analyze each postulated accident - Attachment I of the LAR includes a roadmap
- The Limitations, Restrictions and Conditions for the Westinghouse codes used in the Non-LOCA safety analyses are addressed in detail, including justifications in the LAR (Enclosure I, Appendix A) 13
Instrumentation Setpoint Uncertainty Analysis
- Uncertainty U t i t Analysis A l i
- Transition from the existing WCNOC Setpoint Methodology gy to the current Westinghouse g Setpoint p
Methodology as applied to WCGS for RTS, ESFAS and LOP DG Start Instrumentation (WCAP-17746-P,, Enclosure II of LAR))
- Technical Specification Changes
- TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14
Instrumentation Setpoint Uncertainty Analysis
- Uncertainty U t i t Analysis A l i ((cont.) t)
- Calculations were performed for the RTS, ESFAS, and LOP DG Start instrumentation Functions using the current Westinghouse setpoint methodology (WCAP-17602-P, Enclosure IV of LAR))
- Implementation of the Westinghouse Setpoint Methodology resulted in two changes to the existing WCGS Trip Setpoints
- TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low
- TS 3.3.5, Degraded Voltage Function 15
Instrumentation Setpoint Uncertainty Analysis
- TSTF TSTF-493-A, 493 A Revision R i i 4, 4 Option O ti A - Technical T h i l Specification Changes
- Variation from Option A - Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint Methodology
- TS changes h include i l d the th addition dditi off individual i di id l Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option p
A of TSTF-493, Revision 4 16
Instrumentation Setpoint Uncertainty Analysis
- Followup from the 9/20/12 Pre-Submittal Meeting
- The level of detail of the setpoint methodology and setpoint calculations for WCGS is consistent with that in the Diablo Canyon y Power Plant ((DCPP))
submittal of March 7, 2013 (DCL-13-016)
- WCNOC specific setpoint calculations are provided in WCAP WCAP-17602-P 17602 P (Enclosure IV of LAR) 17
- Full F ll S Scope IImplementation l t ti off the th AST
- Radiological dose consequences analyses were performed for the accidents specified p p in Regulatory g y Guide (RG) 1.183 include:
- Main Steamline Break (USAR Section 15.1.5.3)
- Locked Rotor (USAR Section 15.3.3.3) 15 3 3 3)
- Rod Ejection (USAR Section 15.4.8.3)
- Steam Generator Tube Rupture (USAR Section 15.6.3.3)
- Loss of Coolant Accident (USAR Section 15.6.5.4)
- Fuel Handling Accident (USAR Section 15.7.4) 18
- Full Scope Implementation of the AST (cont.)
- Radiological dose consequences analyses performed for additional accidents not specified in RG 1.183 include:
- Letdown Line Break (USAR Section 15.6.2.1)
- Waste Gas Decay Tank Failure (USAR Section 15.7.1)
- Liquid Liq id Waste Tank Fail Failure re (USAR Section 15.7.2) 15 7 2)
- Dose consequences analyses were performed using version 3.03 of the RADTRAD computer code d
19
- Full Scope Implementation of AST (cont.)
- No changes to the licensing basis EQ dose analyses - maintaining the TID TID-14844 14844 accident source term
- No changes to the licensing basis NUREG-0737 evaluations other than the Control Room Habitability Envelope (CHRE) doses (III.D.3.4) and Technical Support Center doses (III (III.A.1.2)
A 1 2) 20
- Atmospheric Dispersion Factors (X/Q)
- New X/Q values were calculated
- Control Room and TSC X/Q values were calculated using the ARCON96 code consistent with RG 1 1.194 194
- Meteorological Data
- Five years of WCGS site-specific meteorological data from 1/1/2006 through 12/31/2010 was collected
- Data recovery for the 5-year period met the 90% recovery criterion of RG 1.23 21
- Current licensing basis changes
- Revises USAR Chapter 15 dose analysis for 10 accidents
((includes the 6 DBAs in RG 1.183))
- New Offsite, Control Room, and TSC atmospheric dispersion factors based on site-specific meteorological data from 2006 throughg 2010
- Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm
- Revises the Control Building unfiltered inleakage from 300 scfm to 400 scfm
- TS changes to address the update of the accident source term and associated DBAs
- TS changes to address the adoption of TSTF TSTF-51-A, 51 A Revision 2 22
- Technical T h i lS Specification ifi ti Ch Changes
- Definition of DOSE EQUIVALENT I-131
- Revised to only allow the use of the dose conversion factors from EPA Federal Guidance Report No. 11
- Definition of DOSE EQUIVALENT XE-133
- Revised to only allow the use of the dose conversion factors EPA Federal Guidance Report No. 12
- Specification 5.5.12, Explosive Gas and Storage Tank Radioactivity Monitoring ProgramProgram
- Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole bodyy exposure p limit to 0.1 rem ((current limit is 0.5 rem) 23
- Technical T h i lS Specification ifi ti Ch Changes ((cont.) t)
- Adoption of TSTF-51-A, Revision 2, Revise q
Containment Requirements during g Handling g Irradiated Fuel and Core Alterations
- Allows the elimination of the TS requirements for certain g
Engineered Safetyy Feature ((ESF)) systems y to be OPERABLE, after a sufficient radioactive decay has occurred
- Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24
- E l Enclosure VI off LAR - Sections S ti 1 - DESCRIPTION 2 - PROPOSED CHANGES 3 - BACKGROUND 4 - TECHNICAL ANALYSIS 5 - RG 1.183 CONFORMANCE TABLE 6 - RG 1.145 CONFORMANCE TABLE 7 - RG 1.194 CONFORMANCE TABLE 8 - RIS 2006-04 TABLE 9 - PROPOSED TS MARKUPS 10 - RETYPED TS PAGES 11 - PROPOSED BASES MARKUPS (information only) 12 - PROPOSED TRM and BASES MARKUP (information only) 25 13 - PROPOSED USAR CHANGES (information only)
- Followup from the 9/20/12 Pre-Submittal Meeting
- Meteorological Data - One gap in the recorded data was due to the data logger failure (5/30/2007 through 6/7/2007)
- Provide a detailed plant drawing that shows the potential release paths - site plan provided consistent with the guidance in RIS 2006-04 (Enclosure VI of the LAR) 26
- Followup from the 9/20/12 Pre-Submittal Meeting (cont) 27
Schedule
- Submit LAR to NRC August 13, 2013
- NRC Acceptance Review (30 days per LIC-109)
- Requested Approval Date December 15, 2014
- Start of Refueling Outage 20 January 5, 2015
- Cycle 21 Startup February 9, 2015 28
Summary
the WCGS TSs based on:
- Transition to the Westinghouse core design and safety analysis methodologies
- Transition to the Westinghouse Setpoint Methodology
- Full Scope Implementation of the Alternative Source Term (AST)
- Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015)
- Questions/Comments 29