ML13205A214

From kanterella
Jump to navigation Jump to search

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
ML13205A214
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 07/30/2013
From:
Wolf Creek
To:
Office of New Reactors
Lyon C
References
TAC MF2309
Download: ML13205A214 (29)
v • d • e


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
  • Summary 2

Introductions

  • NRC
  • 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
  • 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

was used for majority of the analyses

  • Other Codes that were used:

- TWINKLE (WCAP-7979-P-A)

- FACTRAN (WCAP-7908-A)

- Non-LOCA Thermal-Hydraulics (T&H) Safety 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.

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

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)
  • 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
  • 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
Retrieved from "https://kanterella.com/w/index.php?title=ML13205A214&oldid=2060561"