ML16236A097

Operating Corporation - August 25, 2016, Core Design and Safety System Analysis Methodology Transition License Amendment Request Revised

ML16236A097
Person / Time
Site:	Wolf Creek
Issue date:	08/25/2016
From:	Wolf Creek
To:	Office of Nuclear Reactor Regulation
Lyon C, 415-2296
References
CAC MF8119
Download: ML16236A097 (49)

Text

WCNOC-NRC Pre-application Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request Revised August 25, 2016 Wolf Creek Nuclear Operating Corporation 1

Meeting Agenda

• Meeting Purpose / Objectives

• Introductions

• History of Original LAR

• Revised LAR content Transition to Westinghouse Analysis Methodologies Alternative Source Term (AST)

• LAR Schedule - WCAP-17504 approval for use

• Summary 2

Introductions

• NRC

• WCNOC / Westinghouse Team 3

History of Original LAR

• Original LAR submitted August 13, 2013

• LAR withdrawn June 18, 2014

• NRC issued RAIs on December 13, 2013, March 5, 2014, April 3, 2014 and April 30, 2014 RAIs issued on December 13 and March 5 were previously responded to A response to all applicable RAIs has been included in the revised LAR and integrated into the text, where appropriate 4

Revised LAR Content

• Revised LAR based on:

- Transition to Westinghouse core design and safety analysis methodologies

- Full Scope Implementation of Alternative Source Term (AST)

- AST uses input data from the safety analysis transients and thus they are being submitted together

• Revised LAR no longer based on:

- Transition to Westinghouse Setpoint Methodology (WSM) for RTS/ESFAS

• WSM will be used for Revised Thermal Design Procedure uncertainties 5

Revised LAR Content

• LAR remains consistent with NEI 06-02, License Amendment Request (LAR)

Guidelines template

• Attachments:

I - Evaluation II - Proposed TS Changes (Mark-up)

III - Revised TS pages IV - Proposed TS Bases Changes (info only)

V - Proposed COLR Changes (info only) 6

Revised LAR Content (cont.)

Enclosures:

I - WCAP-17658-NP - Transition Licensing Report II - WCAP-18083-P - RTDP Uncertainty Calcs for WCGS III - WCAP-18083-NP IV - Full Scope Implementation of AST V - CD-ROM containing Meteorological Data VI - NRC RAI Responses - Proprietary VII - NRC RAI Responses - Non-Proprietary VIII - Supplemental Info to Support NRC RAI Responses IX - Proprietary Information Affidavit for WCAP-18083-P X - Proprietary Information Affidavit for Enclosure VI 7

Transition to Westinghouse Analysis Methodologies

• Core Design and Safety Analysis Methodology

- The Non-LOCA safety analyses were analyzed with Westinghouse, NRC approved 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 evaluated for each reload cycle 8

Transition to Westinghouse Analysis Methodologies

• Overview of Analysis Methodology Scope

- Non-LOCA Safety Analyses RETRAN-02 for Westinghouse 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 for the Steam Generator Tube Rupture Margin to Overfill and Input to the Dose analyses 9

Transition to Westinghouse Analysis Methodologies

• Overview of Analysis Methodology Scope (cont.)

- 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 of the Westinghouse Non-LOCA Safety Analysis Methodology resulted in six changes to the WCGS TSs

- SLs 2.1.1, Added the ABB-NV and WLOP DNB Correlations

- TS 3.1.9, RCS Boron Concentration - New LCO

- TS 3.3.1, RTS Function 10, Reactor Coolant Flow- Low

- TS 3.4.1, RCS Pressure, Temperature and Flow DNB Limits 11

Transition to Westinghouse Analysis Methodologies

• Implementation of the Westinghouse Non-LOCA Safety Analysis Methodology results in six changes to the 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 Methodology to Specification 5.6.5 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

• New TS 3.1.9 was added to address Westinghouse NSAL-00-016 which was covered as a part of the transition

• TS changes are in accordance with TSTF-453-T, Rev. 2, Addition of New Tech Spec on RCS Boron Limits and Revisions to Tech Spec 3.3.1 to address RWFS 13

Transition to Westinghouse Analysis Methodologies

• Transition includes Revised Thermal Design Procedure (RTDP) instrument uncertainty previously controlled by WCNOC

• Enclosure II - WCAP-18083-P - RTDP Uncertainty Calcs for WCGS

• Previously, these RTDP parameter uncertainties were submitted and reviewed by NRC as part of the instrumentation setpoint methodology transition

• WCAP-18083-P relies on NRC approval of WCAP-17504-P, WESTINGHOUSE GENERIC SETPOINT METHODOLOGY

• Our understanding is that there are Conditions in the Draft Safety Evaluation for WCAP-17504-P, and these will be generically addressed within the LAR 14

Instrumentation Setpoint Uncertainty Analysis

• Change requests associated with RTS/ESFAS TSTF-493, Option A, have been removed from the revised LAR 15

Alternative Source Term

• Full Scope Implementation of the AST

- Radiological dose consequences analyses performed for the accidents specified in Regulatory Guide (RG) 1.183 include:

Main Steamline Break (USAR Section 15.1.5.3)

Locked Rotor (USAR Section 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) 16

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)

Letdown Line Break (USAR Section 15.6.2.1)

Waste Gas Decay Tank Failure (USAR Section 15.7.1)

Liquid Waste Tank Failure (USAR Section 15.7.2)

- Dose consequences analyses were performed using version 3.03 of the RADTRAD computer code 17

Alternative Source Term

• Full Scope Implementation of AST (cont.)

- No changes to the licensing basis EQ dose analyses - maintaining the TID-14844 accident source term

- No changes to the licensing basis NUREG-0737 evaluations other than the Control Room Habitability Envelope (CRHE) doses (III.D.3.4) and Technical Support Center doses (III.A.1.2) 18

Alternative Source Term

• Atmospheric Dispersion Factors (/Q)

- /Q values were calculated Offsite (EAB and LPZ) /Q values were calculated using the PAVAN code consistent with RG 1.145 Control Room and TSC /Q values were calculated using the ARCON96 code consistent with RG 1.194

- Meteorological Data Five years of WCGS site-specific meteorological data was collected Data recovery for the 5-year period met the 90%

recovery criterion of RG 1.23 19

Alternative Source Term

• Current licensing basis changes

- Revises USAR Chapter 15 dose analysis for 10 accidents (includes the 6 DBAs in RG 1.183)

- Offsite, Control Room, and TSC atmospheric dispersion factors based on site-specific meteorological data

- Revises the CRHE unfiltered in-leakage from 20 scfm to 50 scfm

- Revises the Control Building unfiltered in-leakage 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-51-A, Revision 2 have been removed from the revised LAR

- A modification to the control room HVAC system isolation dampers will be implemented to eliminate a local TCA 20

Alternative Source Term

• Technical Specification 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

- TS SR 3.3.7.6, CREVS Instrumentation - Hi rad channel response time testing - New Identified while responding to RAIs and reviewing other AST submittals

- Specification 5.5.12, Gas and Storage Tank Radioactivity Monitoring Program Revises the limit of radioactivity contained in each gas storage tank to be less than the revised dose limit of 0.1 rem (current limit is 0.5 rem)

- Specification 5.5.18, Control Room Habitability Program Revised to recognize TEDE terminology 21

Alternative Source Term

• Enclosure IV of LAR - Sections 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) 13 - PROPOSED USAR CHANGES (information only) 22

Schedule

• Submit LAR to NRC 4th Qtr 2016

• Requested Approval Date February 23, 2018

• Start of Refueling Outage 22 March 17, 2018 23

Summary

• WCNOC intends to submit a LAR in 4th qtr 2016 to revise the WCGS TSs based on:

- Transition to the Westinghouse core design and safety analysis methodologies

- Full Scope Implementation of the Alternative Source Term (AST)

• Schedule dependent upon NRC approval and issuance of acceptable for use letter for WCAP-17504

• Scope of LAR reduced; largely repetitive to what has been previously reviewed; RAIs addressed

• Request NRC approval prior to February 23, 2018 to allow for implementation during RFO 22 24

Closing

• Questions?

25

BACKUP SLIDES 26

Transition to Westinghouse Analysis Methodologies

• Safety Limits (SLs) changes 27

Transition to Westinghouse Analysis Methodologies

• New Reactivity Control Systems TS 3.1.9 28

Transition to Westinghouse Analysis Methodologies

• New Reactivity Control Systems TS 3.1.9 29

Transition to Westinghouse Analysis Methodologies

• New Reactivity Control Systems TS 3.1.9 30

Transition to Westinghouse Analysis Methodologies

• Insert New TS 3.3-9 31

Transition to Westinghouse Analysis Methodologies

• New 3.3-9 32

Transition to Westinghouse Analysis Methodologies

• New 3.3-9 (Continued) 33

Transition to Westinghouse Analysis Methodologies

• Insert 3.3-15A and B 34

Transition to Westinghouse Analysis Methodologies

• Insert to TS 3.3.1 35

Transition to Westinghouse Analysis Methodologies

• TS Table 3.3.1-1, Function 10 36

Transition to Westinghouse Analysis Methodologies

• TS 3.4.1 changes 37

Transition to Westinghouse Analysis Methodologies

• TS 3.4.1 changes (Continued) 38

Transition to Westinghouse Analysis Methodologies

• TS Table 3.7.1-1 39

Transition to Westinghouse Analysis Methodologies

• Specification 5.6.5 b.

40

Transition to Westinghouse Analysis Methodologies

• Specification 5.6.5 b. (cont.)

41

Transition to Westinghouse Analysis Methodologies

• COLR Change 42

Alternative Source Term

• Definition of DOSE EQUIVALENT I-131 43

Alternative Source Term

• Definition DOSE EQUIVALENT XE-133 44

Alternative Source Term

• SR 3.3.7.6 45

Alternative Source Term

• SR 3.3.7.6 (Continued) 46

Alternative Source Term

• TS 5.5.12 47

Alternative Source Term

• TS 5.5.18 48

List of Acronyms AC Alternating Current RTS/ESFAS Reactor Trip System/Engineered Safety AST Alternative Source Term Features Actuation System COLR Core Operating Limits Report RWFS Rod Withdrawal from Subcritical CREVS Control Room Emergency Ventilation SBLOCA Small Break LOCA System CRHE Control Room Habitability Envelope SL Safety Limits DBA Design Basis Accident SR Surveillance Requirement DNB Departure from Nucleate Boiling TCA Time Critical Action EAB Exclusion Area Boundary TEDE Total Effective Dose Equivalent EPA Environmental Protection Agency EQ Environmental Qualification TID Technical Information Document LAR License Amendment Request T&H Thermal - Hydraulic LBLOCA Large Break LOCA TS Technical Specifications LCO Limiting Condition of Operation TSC Technical Support Center LPZ Low Population Zone TSTF Technical Specification Task Force MSSV Main Steam Safety Valve USAR Updated Safety Analysis Report NEI Nuclear Energy Institute WCGS Wolf Creek Generating Station Non-LOCA Non- Loss of Coolant Accident WCNOC Wolf Creek Nuclear Operating NRC Nuclear Regulatory Commission Corporation NSAL Nuclear Safety Advisory Letter WSM Westinghouse Setpoint Methodology NSSS Nuclear Steam Supply System Chi RAI Request for Additional Information RG Regulatory Guide RCS Reactor Coolant System RFO Refueling Outage RTDP Revised Thermal Design Procedure RTS Reactor Trip System 49