ML070110027

Notice of Meeting Handouts with FPL Adoption of AST at St. Lucie

ML070110027
Person / Time
Site:	Saint Lucie
Issue date:	01/10/2007
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
RG-1.183
Download: ML070110027 (13)

Text

FPL Nuclear Division ALTERNATIVE SOURCE TERM Pre-Submittal Meeting St. Lucie Nuclear Plant January 10, 2007 FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division ATTENDEES FOR FP&L

" Terry Patterson Licensing Manager

" Vincent Rubano Engineering Manager

" Jack Hoffman Engineering Manager

" Chris Wasik Engineering

" Jay Kabadi Engineering

" Kathy Ward Engineering

" Ken Frehafer Licensing

" Mark Pope Contractor (Numerical Applications, Inc.)

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FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division PURPOSE OF PRE-SUBMITTAL MEETING

" Achieve common understanding of the proposed scope of the St. Lucie application

" Gain understanding regarding regulatory positions on specific issues

" Understand the level of detail of information expected in the application 3

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division AGENDA

" Reason for Adopting the Alternate Source Term

• Scope of Implementation

• Specific Aspects of the Analyses

• Overview of Changes to the Licensing Basis

" Proposed Technical Specification Changes

• Submittal Content

• Schedules

• Summary 4

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F-PL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division REASON FOR ADOPTING AST METHODOLGY

" To update the St. Lucie accident dose analyses using a consistent basis for all events

• To obtain margin for Control Room inleakage 5

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SCOPE OF IMPLEMENTATION

• Full Implementation of Reg. Guide 1.183

" Unit 1 accidents analyzed:

- Loss-of-Coolant Accident

- Main Steam Line Break

" DNB and FCM Failures

" Breaks Inside and Outside of Containment

- Control Rod Ejection

• Containment and Secondary Release Events

- Seized Rotor 6

3

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SCOPE OF IMPLEMENTATION Unit 1 accidents analyzed (continued):

- Fuel Handling Accident

• Separate analysis for Containment and Fuel Handling Building Releases

- Steam Generator Tube Rupture

• Pre-Accident and Concurrent Iodine Spikes

- Stuck Open MVSSV 7

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SCOPE OF IMPLEMENTATION Unit 2 accidents analyzed:

- Loss-of-Coolant Accident

- Main Steam Line Break

" DNB and FOMV Failures

" Breaks Inside and Outside of Containment

- Control Rod Ejection

• , Containment and Secondary Release Events

- Seized Rotor

- Feedwater Line Break 4

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SCOPE OF IMPLEMENTATION Unit 2 accidents analyzed (continued):

- Fuel Handling Accident

• Separate analysis for Containment and Fuel Handling Building Releases

- Letdown Line Break

- Steam Generator Tube Rupture (CLB)

• Pre-Accident and Concurrent Iodine Spikes 9

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES

" AST analysis philosophy

• St. Lucie-specific source term inventories calculated using ORIGEN 2

• Dose Equivalent 1-131 is based upon thyroid DCFs*

• Updated control room and offsite X/Q values based upon Reg. Guide 1.145 using meteorological data from 1996 -

2001

• Consistent with approved Unit 2 SGTR dose analysis tor 30% tube plugging (Amendment 138 to NPF-16) 10 5

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES

• 10% of the total iodine activity in the EGGS leakage outside containment assumed airborne

• LOGA dose contribution from the EGGS back-leakage to RWT considered the effects of sump pH, back-leakage temperature reduction, and total iodine distribution within the tank

• Conservative SBVS drawdown time

• Analysis inputs and atmospheric steam releases are set conservatively to bound plant configurations FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES

• Preliminary dose analyses support Control Room unfiltered inleakage rates of 500 cfm for Unit 1 and 400 cfm for Unit 2

" Control Room unfiltered Inleakag e assumed to enter at the intake midpoint during control room isolation, then through the more favorable intake following manual alignment based on radiation monitors*

" Steam Generator tube leakage of 0.25 gpm/SG during accidents at accident conditions. [This is greater than the value of 0.15 gpm/SG used in the original submittal. The proposed operational leakage is

-0.1 gpm/SG per St. Lucie TSTF-449 LAs.]

• Control room, EGGS, and SBVS filter efficiencies based upon Tech.

Spec. values with a safety factor of 2 applied per Reg. Guide 1.52, Rev. 3 Cositntoth approved Unit 2 St3TRdoseanalysistor30%tubeplugging(Amendmndr t 138toNPF-16) 12 6

r-PL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES

" Aerosol deposition value of 0.1/hr based on IDCOR 11.3 and confirmed with NUREG/CR-6189

" Containment sump pH confirmed via calculations considering NUREG/CR-5950 13 FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES Summary of St. Lucie Unit 1 Alternative Source Term Evaluation Preliminary Results (500 CFM)

Event EAB LPZ CR LOCA 1.08 2.55 4.75 MSLB - DNB (38%) inside cont.* 0.56 0.83 4.59 MSLB - FCM (9%) inside cont.* 0.56 0.86 4.71 MSLB - DNB (2.5%) outside cont.* 0.35 0.87 4.59 MSLB - FCM (0.6%) outside cont.* 0.38 0.92 4.77 Seized Rotor 0.20 0.29 1.41 Stuck Open MSSV 0.02 0.02 0.24 Fuel failures maximized to approach dose limit. The unfiltered inleakage value bounds the value for inleakage from both Louver L-1 1 and intake midpoint.

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FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES Summary of St. Lucie Unit 1 Alternative Source Term Evaluation Preliminary Results (500 CFM)

Event EAB LPZ CR Control Rod Eject - Sec. Release 0.20 0.29 1.41 Control Rod Eject. - Contain. Release 0.17 0.30 1.49 SGTR - Pre-Accident Iodine Spike 0.38 0.37 3.75 SGTR - Concurrent Iodine Spike 0.09 0.09 0.69 FHA - Containment Release 0.27 0.26 0.59 FHA -Fuel Building Release 0.27 0.26 1.13 15 F=PL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES Summary of St. Lucie Unit 2 Alternative Source Term Evaluation Preliminary Results (400 CFM)

Event EAB LPZ CR LOCA 1.17 2.70 4.94 MSLB - DNB3 (38%) inside cont.* 0.63 0.95 4.63 MVSLB - FCM (9%) inside cont.* 0.64 0.98 4.66 MVSLB - DNB3 (2.5%) outside cont.* 0.40 1.01 4.94 MSLB - FCM (0.6%) outside cont.* 0.43 1.06 4.84 Seized Rotor 0.24 0.35 1.89 Feedwater Line Break 0.01 0.01 0.61

• Fuel failures maximized to approach dose limit. The unfiltered inleakage value bounds the value for inleakage from both Louver L-1 1 and intake midpoint.

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FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES

-Summary of St. Lucie Unit 2 Alternative Source Term Evaluation Preliminary Results (400 CFM)

Event EAB LPZ CR Control Rod Eject - Sec. Release 0.24 0.36 1.87 Control Rod Eject. - Contain. Release 0.18 0.33 1.54 SGTR - Pre-Accident Iodine Spike 0.23 0.22 2.27*

SGTR - Concurrent Iodine Spike 0.06 0.06 0.53*

FHA - Containment Release 0.29 0.28 0.70 FHA - Fuel Building Release 0.29 0.28 1.20 Letdown Line Break 0.36 0.35 1.80

• SGTR event previously approved by NRC. Results shown based on revised SG tube leakage limits and are consistent with unfiltered inleakage limits.

17 FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES Consideration of High Burnup Rods

" Less than 150 rods in Unit 1 (<0.4% of core) are projected to exceed the burnup limits upon which the Reg. Guide 1.183 gap release fractions are based

• With a maximum of 150 rods exceeding the Reg. Guide 1.183 burnup limit, the analyses will assume 1408 rods (8 equivalent fuel assemblies) are affected

" The impact of high burnup rods was evaluated by doubling the gap release fractions for all 1408 rods (-.3.7% of core) 18 9

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SPECIFIC ASPECTS OF THE ANALYSES Consideration of High Burnup Rods

" Results of high burnup evaluation show a 3.7% increase in radiological consequences of fuel failure events (MSLB, ORE, Locked Rotor), and -85% increase in results of the Fuel Handling Accident

" Sufficient margin to the dose acceptance criteria exists to apply this conservative approach in addressing high burnup concerns 19 FPL Nuclear Division St. Lucie Nuclear Plant - Alternative Source Term OVERVIEW OF LICENSING BASIS CHANGES

" Updated radiological analyses with TEDE acceptance criteria

" Accident analyses dose calculations based on primary-to-secondary leakage of 0.25 gpm/SG at accident conditions 20 10

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division PROPOSED TECHNICAL SPECIFICATION CHANGES

• The definition of Dose Equivalent 1-131 in Section 1.1 to be revised to reference Federal Guidance Report No. 11 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"

1989, as the source of thyroid dose conversion factors.

" TS Bases change to incorporate accident analyses leakage of 0.25 gpm/SG

• The leakage rate acceptance criterion for secondary containment bypass leakage paths (i.e. Shield Building Bypass Leakage) stated in TS 6.8.4.h, "Containment Leakage Rate Testing Program," to be reduced from 27% to 9.6% for Unit 1 and from 12% to 9.6% for Unit 2.

21 FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division PROPOSED TECHNICAL SPECIFICATION CHANGES

• Ventilation Filter Testing for filters credited in the AST analysis to be added/revised consistent with RG 1.52, Rev. 3 and the assumptions of the AST analysis

- Filter Testing of the Unit 2 Eccs Area Ventilation System to be added to Technical Specification 6.8.4, Ventilation Filter Testing Program, with HEPA testing criteria of > 99.95% and charcoal adsorber testing criteria of > 97.5%

efficiency

- Current HEPA filter testing criteria for Unit 1 Eccs Area Ventilation System and both unit's SBVS to be revised from > 99% to > 99.95% efficiency

- Current Unit 2 SBVS charcoal adsorber testing criteria to be revised from >

95% to > 97.5% efficiency

- Current ventilation filter testing criteria for Eccs and SBVS filters to be moved to Technical Specification 6.8.4, Ventilation Filter Testing Program 22 I1I

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SUBMITTAL CONTENT

" Licensing Technical Report which presents the analysis assumptions and documents conformance with Reg. Guide 1.183

• Table addressing NRC Regulatory Issue Summary 2006-04 issues

• Analyses key input parameters and results tables

• TS changes Note: Meteorological data and accident dose calculations available upon request. [Met. data previously provided and accepted for Unit 2 in Amendment 138 (Unit 2 30% SGTP).]

23 FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division SCHEDULES

• Unit 1 submittal by 06/2007

• Unit 2 submittal by 06/2007 24 12

FPL St. Lucie Nuclear Plant - Alternative Source Term Nuclear Division

SUMMARY

• Full scope implementation of AST

• Addresses control room inleakage issue

• Conformance with RG 1.183

• Addresses NRC RIS 2006-04 concerns 25 13