ML13205A214
| 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 Pre-submittal Meeting WCNOC NRC Pre submittal Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request Transition License Amendment Request July 30 2013 July 30, 2013 Wolf Creek Nuclear Operating Corporation p
g p
1
Meeting Agenda M
ti P
/ Obj ti
- Meeting Purpose / Objectives
- Introductions License Amendment Request (LAR) Content
- License Amendment Request (LAR) Content
- Transition to Westinghouse Analysis Methodologies Methodologies
- RTS/ESFAS/LOP DG Start Instrumentation Setpoint Uncertainty Analysis y
y
- LAR Schedule 2
- Summary 2
Introductions
- NRC
- WCNOC Team
- Westinghouse Support
- Teleconference Attendees 3
WCNOC Ownership of Safety Analysis WCNOC O hi f th S f t A l
i i d t
t d
- WCNOC Ownership of the Safety Analysis is demonstrated through the strength and application of the Quality Assurance (QA) Program
- WCNOC technical oversight is provided by the QA processes and participation in NUPIC
itt l f D i
I f ti f
d t th
- Transmittal of Design Information - referenced to the source calculation, design basis document, or identified as a direct input
- Owners Acceptance Review
- Configuration Management updates, regulatory reviews, etc.
Configuration Management updates, regulatory reviews, etc.
- WCNOC/Westinghouse (WEC) Interface
- On-site WEC staff responsible for core design and safety analysis On site WEC staff maintains qualifications in both the WCNOC and 4
- 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 safety analysis methodologies
- Transition to Westinghouse Setpoint Methodology
- Full Scope Implementation of Alternative Source Full Scope Implementation of Alternative Source Term (AST) 5
License Amendment Request Content
Attachments:
I
- Evaluation II
- Proposed TS Changes (Mark-up) p g
(
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 )
- LAR content (cont.)
Enclosures:
I
- WCAP-17658-NP - Transition Licensing Report I
WCAP 17658 NP Transition Licensing Report 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 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 Transition to Westinghouse Analysis Methodologies C
D i
d S f t A l
i M th d l
- Core Design and Safety Analysis Methodology
- The Non-LOCA safety analyses were analyzed with Westinghouse, NRC approved methods g
pp
- All of the Westinghouse Non-LOCA methods are applicable to the WCGS The Containment response analyses of record are not
- 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
y 8
Transition to Westinghouse Analysis Transition to Westinghouse Analysis Methodologies O
i f A l
i M th d l S
- Overview of Analysis Methodology Scope
- Non-LOCA Safety Analyses
- RETRAN-02 for Westinghouse PWRs (WCAP-14882-P-A) g
(
)
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 d f th St G
t T b R
t M
i 9
were used for the Steam Generator Tube Rupture Margin to Overfill and Input to the Dose analyses 9
Transition to Westinghouse Analysis Transition to Westinghouse Analysis Methodologies O
i f A l
i M th d l S
(
t )
- Overview of Analysis Methodology Scope (cont.)
- DNB Correlations used in the VIPRE-01 DNBR calculations 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 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
- 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 10 10
Transition to Westinghouse Analysis Transition to Westinghouse Analysis Methodologies f
OC
- Implementation of the Westinghouse Non-LOCA Safety Analysis Methodology resulted in five changes to the current WCGS TSs 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 Limits
- The Minimum Measured Flow (MMF) was relocated to the COLR and revised from 371,000 gpm to 376,000 gpm 11 11
- The Thermal Design Flow - 361,200 gpm, replaces the MMF 11
Transition to Westinghouse Analysis Transition to Westinghouse Analysis Methodologies I
l t ti f th W
ti h
N LOCA S f t
- Implementation of the Westinghouse Non-LOCA Safety 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 and 2 OPERABLE MSSVs was revised
- Added WCAP-9272-P-A, the Westinghouse Reload M th d l t
S ifi ti 5 6 5 b 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 12
Transition to Westinghouse Analysis Transition to Westinghouse Analysis Methodologies F ll f
th 9/20/12 P S b itt l M ti
- Followup from the 9/20/12 Pre-Submittal Meeting
- 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 13 13
Instrumentation Setpoint Uncertainty Instrumentation Setpoint Uncertainty Analysis U
t i t A l
i
- Uncertainty Analysis
- Transition from the existing WCNOC Setpoint Methodology to the current Westinghouse Setpoint gy g
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 replaced with a Nominal Trip Setpoint
- TS Table 3.3.1-1, Overtemperature T, Note 1 and Overpower T, Note 2 14 14 14
Instrumentation Setpoint Uncertainty U
t i t A l
i (
t )
Instrumentation Setpoint Uncertainty Analysis
- Uncertainty Analysis (cont.)
- 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 existing WCGS Trip Setpoints
- TS 3.3.1, RTS Function 10, Reactor Coolant Flow-Low
- TS 3.3.5, Degraded Voltage Function 15 15
Instrumentation Setpoint Uncertainty Instrumentation Setpoint Uncertainty Analysis TSTF 493 A R i i 4 O ti A
T h i l
- TSTF-493-A, Revision 4, Option A - Technical Specification Changes
- Variation from Option A - Nominal Trip Setpoint Variation from Option A Nominal Trip Setpoint specified in the single column format based on the Westinghouse Setpoint Methodology TS h i
l d th dditi f i di id l
- TS changes include the addition of individual Surveillance Requirement footnotes to the applicable instrumentation Functions in accordance with Option p
A of TSTF-493, Revision 4 16 16
Instrumentation Setpoint Uncertainty 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 Power Plant (DCPP) y
(
)
submittal of March 7, 2013 (DCL-13-016)
- WCNOC specific setpoint calculations are provided in WCAP-17602-P (Enclosure IV of LAR) provided in WCAP 17602 P (Enclosure IV of LAR) 17
Alternative Source Term F ll S I
l t ti f th AST
- Full Scope Implementation of the AST
- Radiological dose consequences analyses were performed for the accidents specified in Regulatory p
p g
y Guide (RG) 1.183 include:
- Main Steamline Break (USAR Section 15.1.5.3)
- Locked Rotor (USAR Section 15 3 3 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) 18 18 18
- Full Scope Implementation of the AST (cont.)
- Radiological dose consequences analyses performed for additional accidents not specified in 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)
Liq id Waste Tank Fail re (USAR Section 15 7 2)
- Liquid Waste Tank Failure (USAR Section 15.7.2)
- Dose consequences analyses were performed using version 3.03 of the RADTRAD computer d
code 19 19
- Full Scope Implementation of AST (cont.)
- No changes to the licensing basis EQ dose analyses maintaining the TID 14844 accident analyses - maintaining the TID-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 A 1 2)
Support Center doses (III.A.1.2) 20 20 20
- Atmospheric Dispersion Factors (X/Q)
- New X/Q values were calculated
- Offsite (EAB and LPZ) X/Q values were calculated using
- Control Room and TSC X/Q values were calculated using the ARCON96 code consistent with RG 1 194 the ARCON96 code consistent with RG 1.194
- 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 21 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 through 2010 g
- Revises the CRHE unfiltered inleakage from 20 scfm to 50 scfm
- Revises the Control Building unfiltered inleakage from 300 scfm to 400 scfm 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 22 22
- TS changes to address the adoption of TSTF-51-A, Revision 2 22
h i l S ifi ti Ch
- Technical Specification Changes
- Definition of DOSE EQUIVALENT I-131
- Revised to only allow the use of the dose conversion factors 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 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 Program Tank Radioactivity Monitoring Program
- Revises the quantity of radioactivity contained in each gas storage tank to be less than the amount that would result in a whole body exposure limit to 0.1 rem (current limit is 0.5 23 23 y
p
(
rem) 23
h i l S ifi ti Ch
(
t )
- Technical Specification Changes (cont.)
- Adoption of TSTF-51-A, Revision 2, Revise Containment Requirements during Handling q
g g
Irradiated Fuel and Core Alterations
- Allows the elimination of the TS requirements for certain Engineered Safety Feature (ESF) systems to be g
y
(
) y OPERABLE, after a sufficient radioactive decay has occurred
- Changes were not applied to the TS Section 3.8 Electrical TSs (conservative) 24 24 24
l VI f LAR S
ti Enclosure VI 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) 25 25 11 PROPOSED BASES MARKUPS (information only) 12 - PROPOSED TRM and BASES MARKUP (information only) 13 - PROPOSED USAR CHANGES (information only) 25
- 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) 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 28
Summary WCNOC i t d t b
it LAR 8/13/13 t i
- Transition to the Westinghouse core design and 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)
Source Term (AST)
- Request NRC approval by 12/15/14 to support Cycle 21 operation (Feb. 2015) 29
- Questions/Comments 29