L-2011-360, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request

Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request

ML11251A159
Person / Time
Site:	Saint Lucie
Issue date:	09/02/2011
From:	Richard Anderson Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2011-360
Download: ML11251A159 (46)

Text

0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 F*IL September 2, 2011 L-2011-360 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re:

St. Lucie Plant Unit I Docket No. 50-335 Renewed Facility Operating License No. DPR-67 Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request

References:

(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2010-259),

"License Amendment Request for Extended Power Uprate," November 22, 2010, Accession No. ML103560419.

(2) Email from T. Orf (NRC) to C. Wasik (FPL), "St. Lucie 1 EPU RAIs (Accident Dose)," June 21,2011.

(3) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-314),

"License Amendment Request for Extended Power Uprate," August 12, 2011, Accession No. ML11234A283 By letter L-2010-259 dated November 22, 2010 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. DPR-67 and revise the St. Lucie Unit I Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an Extended Power Uprate (EPU).

By email from the NRC Project Manager dated June 21, 2011 [Reference 2], additional information related to accident dose was requested by the NRC staff in the Accident Dose Branch (AADB) to support their review of the EPU LAR. The request for additional information (RAI) identified sixteen questions. The response to this RAI was provided in FPL letter dated August 12, 2011 [Reference 3].

an FPL Group company

St. Lucie Unit I L-2011-360 Docket No. 50-335 Page 2 of 2 The Reference 3 submittal included updated site meteorological data and associated revised atmospheric dispersion factors (X/Q's). The accident dose analysis calculations have been revised to incorporate the data submitted in Reference 3. Attachment I to this letter provides the results of the revised accident dose calculations.

As a result of the revised accident dose calculations, FPL is proposing to revise the TS to limit the radioactivity in the gas storage tanks to 165,000 curies noble gases. Attachment 2 contains a revision to the EPU proposed change to TS 3.11.2.6, Radioactive Effluents - Gas Storage Tanks.

The EPU LAR originally proposed to limit the radioactivity in the gas storage tanks to 202,500 curies noble gases. Attachment 3 contains the marked-up and clean pages to support the proposed TS revision.

In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the designated State of Florida official.

This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2010-259 [Reference 1].

This submittal contains no new commitments and no revisions to existing commitments.

Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.

1 declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.

Executed on

- Sj -Jre ar -AolI Very truly yours, Richard L. Anderson Site Vice President St. Lucie Plant Attachments (3) cc:

Mr. William Passetti, Florida Department of Health

St. Lucie Unit 1 L-2011-360 Docket No. 50-335 Page 1 of 39 Attachment I Supplemental Information Regarding Extended Power Uprate License Amendment Request Accident Dose Analysis Calculation Results The following information is provided by Florida Power & Light Company (FPL) in response to the U. S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI).

This information was requested to support Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie Nuclear Plant Unit 1 that was submitted to the NRC by FPL via letter (L-2010-259) dated November 22, 2010, Accession Number ML103560419.

In an email dated June 21, 2011 from NRC (Tracy Orf) to FPL (Chris Wasik),

Subject:

St.

Lucie 1 EPU RAIs (Accident Dose), the NRC requested additional information regarding FPL's request to implement the EPU. The RAI consisted of sixteen (16) questions from the NRC's Accident Dose Branch (AADB). By letter dated August 12, 2011, Accession Number ML11234A283, FPL provided responses to the RAI. The transmittal included updated meteorological data and revised atmospheric dispersion factors (X/Q's).

In addition to the supplemental information discussed below, Tables 2.9.2-21, MSLB Steam Release Rate, and 2.9.2-24 SGTR, Break Flow and Steam Releases, have been revised to correct typographical errors in the EPU LAR.

The following supplemental information is being provided based on the calculation results performed using the revised x/Q's.

LAR Attachment 5 Section 2.9.2 Radiological Consequences using Alternative Source Term (AST)

The control room unfiltered inleakage is changed from 500 cfm to 460 cfm for all events.

This change affects all references to control room unfiltered inleakage of 500 cfm in Section 2.9.2.

Section 2.9.2.2.4 Atmospheric Dispersion Factors (X/Q's)

The revised meteorological data is based on data collected in years, 1997, 1998, 1999, 2002, and 2003. This data was screened based on discussions with the NRC staff to be acceptable for use in determining X/Q's.

The references to ARCON96 and PAVAN are deleted.

Section 2.9.2.3.2 Analysis Parameters and Assumptions Release Inputs The engineered safeguards feature (ESF) assumption for leakage into the reactor auxiliary building (RAB) is changed to 4750 cc/hr, based on two times the current licensing basis value of 2375 cc/hr.

The time-dependent concentration to the total iodine in the refueling water tank (RWT) was determined from the tank liquid volume and leak rate. This iodine concentration ranged from a minimum value of 0 at the beginning of the event to a maximum value of 4.067E-05 gm-atom/liter at 30 days. Based on a backleakage of sump water, the RWT pH slowly increases from an initial value of 4.5 to a maximum pH of 4.968 at 30 days. The RWT elemental iodine fraction ranged from 0 at the beginning of the event to a maximum of 0.1245.

St. Lucie Unit 1 L-2011-360 Docket No. 50-335 Page 2 of 39 Loss of Coolant Accident (LOCA) Removal Inputs Based on the elemental iodine removal rate of 20 hW1, the DF of 200 is conservatively computed to occur at 2.331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />.

The particulate iodine removal rate is reduced by a factor of 10 when a DF of 50 is reached. Based on the calculated iodine aerosol removal rate of 6.07 hr-1, the DF of 50 is conservatively computed to occur at 2.334 hours0.00387 days <br />0.0928 hours <br />5.522487e-4 weeks <br />1.27087e-4 months <br />.

The following EPU LAR Attachment 5 Section 2.9.2 tables are being replaced as a result of the revised x/Q values: (pages 4 through 33 of 39)

Table 2.9.2 Summary of EPU Radiological Analysis Results Table 2.9.2 Onsite Atmospheric Dispersion Factors (x/Q) for Analysis Events

" Table 2.9.2 Release - Receptor Point Pairs Assumed for Analysis Events

" Table 2.9.2 Offsite Atmospheric Dispersion Factors (x/Q) for Analysis Events

" Table 2.9.2 Control Room Ventilation System Parameters

" Table 2.9.2 LOCA Direct Shine Dose Table 2.9.2 Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions

" Table 2.9.2 LOCA Time Dependent RWT pH

" Table 2.9.2 LOCA Time Dependent RWT Total and Elemental Iodine Concentration

" Table 2.9.2 LOCA Time Dependent RWT Elemental Iodine Fraction

" Table 2.9.2 LOCA Release Rate from Sump to RWT Vapor Space

" Table 2.9.2 Fuel Handling Accident (FHA) - Inputs and Assumptions Table 2.9.2 Main Steam Line Break (MSLB) - Inputs and Assumptions Table 2.9.2 MSLB Steam Release Rate Table 2.9.2 Steam Generator Tube Rupture Accident - Inputs and Assumptions Table 2.9.2 SGTR Break Flow and Steam Releases Table 2.9.2 Locked Rotor Accident - Inputs and Assumptions Table 2.9.2 CEA Ejection Accident - Inputs and Assumptions Table 2.9.2 IOMSSV - Inputs and Assumptions LAR Attachment 5 Section 2.9.3 Radiological Consequences of Gas Decay Tank Ruptures The control room unfiltered inleakage is changed from 500 cfm to 460 cfm for all events.

2.9.3.2.4 Source Term and Dose Models, Assumptions, and Parameters The following sentence is added to the third paragraph after the sentence containing the 50 second isolation assumption. "Studies have confirmed that the waste gas decay tank (WGDT) rupture event will generate sufficient count rates for the control room outside air intake radiation monitor based isolation to occur well within this 50 second isolation assumption."

St. Lucie Unit 1 L-2011-360 Docket No. 50-335 Page 3 of 39 2.9.3.2.6 Results The Technical Specification limit for WGDT inventory is changed to 165,000 Dose Equivalent Curies Xe-1 33. This limit will yield an exclusion area boundary dose of 0.099997 rem TEDE.

The following EPU LAR Attachment 5 Section 2.9.3 tables are being replaced as a result of the revised x/Q values: (pages 34 through 39 of 39)

Table 2.9.3 RADTRAN-NAI Pathway Description, Tables o

Pathway 2 - Control Room Unfiltered Inleakage Pathway o

Pathway 5 - Control Room Exhaust Pathway Table 2.9.3 WGDT Failure x/Q Tables o

x/Q Table 1 - EAB o

X/Q Table 2 - LPZ o

x/Q Table 3 - Control Room HVAC Intake via N or S Fresh Air Intake Summary -

Bounding St. Lucie HVAC x/Q Table o

X/Q Table 4 - Control Room Unfiltered Inleakage x/Q via Louver L-1 1 or 2L-1 1 Table 2.9.3 Dose Consequences for Waste Gas Decay Tank Failure

" Table 2.9.3 WGDT Source Term - Technical Specification DE Xe-1 33 Curies

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 4 of 39 Table 2.9.2-1 Summary of EPU Radiological Analysis Results Allowable Control AOR Unfiltered EAB LPZ Control Case Control Room Dose(1 )

Dose 2

(

Room IDose(

2)

Room Inleakage (rem TEDE)

(rem TEDE)

(re Dose(s)

(cfm)

(rem TEDE)

(rem TEDE)

LOCA 460 1.14 2.51 4.79 4.69 MSLB - Outside of ML-Ousdof460 0.27 0.77 4.63 4.80 Containment (1.2% DNB)

MSLB - Outside of ML-Ousdof460 0.30 0.81 4.72 4.97 Containment (0.29% FCM)

MSLB - Inside of MSB-Isd f460 0.41 0.87 4.67 4.92 Containment (21% DNB)

MSLB - Inside of Contin e (.

460 0.63 1.21 4.62 4.91 Containment (4.5% FCM)

SGTR Pre-accident Iodine 460 0.37 0.37 4.67 3.03 Spike Acceptance Criteria 25(3)

< 25(3) 5(4)

< 5(4)

SGTR Concurrent Iodine 460 0.18 0.28 2.24 0.60 Spike Locked Rotor (19% DNB) 460 0.37 0.87 4.38 2.53 IOMSSV (6) 460 0.03 0.03 0.39 0.30 Acceptance Criteria

• 2.5 (3)

• 2.5 (3) 5 (4)

< 5(4)

FHA - Containment 460 0.56 0.58 1.43 1.23 FHA - Fuel Handling 460 0.56 0.55 3.47 3.02 Building CEA Ejection -

Containment Release (9.5 460 0.28 0.55 3.30 2.74

% DNB, 0.5 % FCM)

CEA Ejection - Secondary Side Release (9.5 % DNB, 460 0.29 0.71 3.26 2.60 0.5 % FCM) 1 Acceptance Criteria 6.33

< 6.33 1

)(4 4 )

(1) Worst 2-hour dose (2) Integrated 30-day dose (3) RG 1.183, Table 6 (4) 10CFR50.67 (5) AOR control room dose from CLB AST results (6) Acceptance criteria from References 1 and 2

St. Lucie Unit 1 Docket No. 50-335

.L-2011-360 Page 5 of 39 Table 2.9.2-7 Onsite Atmospheric Dispersion Factors (X/Q) for Analysis Events This table summarizes the X/Q values (sec/M3) for the control room that apply to the'various accident scenarios. For the intakes, values are presented for the unfavorable intake prior to control room isolation, the midpoint between the intakes during isolation, as well as values for the favorable intake following manual restoration of filtered control room make-up flow. These values are not corrected for control room occupancy factors but do include credit for dilution where allowed. Based on the layout of the site, the only cases that credited dilution are the releases from the plant vent stack. However, dilution is not credited during the time period when the control room intakes are isolated for these cases.

A comparison of EPU X/Q values to the pre-EPU X/Q values from Reference 1 is presented in the shaded row below each release-receptor pair (positive values indicate that EPU X/Q values are higher).

• Indicates credit for dilution taken for this case.

1. The atmospheric dispersion factors corresponding to ADVs were determined to be more limiting than those from the MSSVs for all time periods. Therefore, the more limiting ADV values have been used throughout the analyses for all secondary releases. No distinction is made between automatic steam relief from the MSSVs and controlled releases from the ADVs for radiological purposes.

Table 2.9.2-7 Onsite Atmospheric Dispersion Factors (X/Q) for Analysis Events Release Release Receptor 0-2 hr 2-8 hr 8-24 hr 1-4 days 4-30 Receptor Point Point X/Q X/Q X/Q X/Q days X/Q Pair Stack/Plant N CR Vent intake Stack/Plant S CR B

Ve t

intke 6.93E-04 4.88E-04 2.19E-04 1.46E-04 1.28E-04 Vent intake

7.

1-5

-Y 4

v 25/

V587 3.79%.~

Stack/Plant Midpoint C

between 3.91E-03 CR intakes D

RWT Ntake 1.37E-03 intake E RWTS CR E

RVVT 1.12E-03 9.10E-04 3.84E-04 2.93E-04 2.37E-04 intake

__________ ~

~

~

1_ 8 2._____

9/0___

P V3.OA.

6'ý ot

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 6 of 39 Table 2.9.2-7 (continued)

Onsite Atmospheric Dispersion Factors (X/Q) for Analysis Events Release Release Receptor 0-2 hr 2-8 hr 8-24 hr 1-4 days 4-30 Receptor Point Point X/Q X/Q X/Q X/Q days X/Q Pair Midpoint F

RW1T between 1.34E-03 CR intakes

___F40,7*,%,

FHB Closest N CR Point intake FHB Closest S CR 2.01 E-03 1.44E-03 6.25E-04 4.34E-04 3.33E-04 Point intake FHB Closest Midpoint I

Pbetween 3.27E-03 CR intakes N CR J

Louver L-7B Ntake 4.80E-03 intake K

Louver L-7A intke 3.61 E-03 2.87E-03 1.20E-03 9.07E-04 7.13E-04 intake Midpoint L

Louver L-7A between 5.03E-03 CR intakes N CR M#

Closest ADV Ntake 6.30E-03 intake N#

Closest ADV SCR 1.62E-03 1.32E-03 5.06E-04 3.88E-04 3.30E-04 intake f2,

476%

21 Midpoint 0#

Closest ADV between 2.84E-03 CR intakes Closest Main N CR P

Steam Line intake 5.13E-03 Point

&k~~~~#~~-

r~ &

~g

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 7 of 39 Table 2.9.2-7 (continued)

Onsite Atmospheric Dispersion Factors (X'Q) for Analysis Events Release Receptor Release Receptor 0-2 hr 2-8 hr 8-24 hr 1-4 days 4-30 Pair Point Point X/Q X/Q XIQ X/Q days X/Q Closest Main Q

Steam Line intke 1.49E-03 1.19E-03 4.67E-04 3.57E-04 2.98E-04 Pointintake Point Closest Main Midpoint R

Steam Line between 2.50E-03 Point CR intakes Closest N CR S

Feedwater intake 7.29E-03 Line Point Closest T

Feedwater SnCR 1.76E-03 1.41 E-03 5.72E-04 4.29E-04 3.57E-04 Line Point Closest Midpoint U

Feedwater between 3.17E-03 Line Point CR intakes Containment N CR V

Maintenance intake 1.90E-03 Hatch Containment W

Maintenance SnCRe 8.22E-04 6.57E-04 2.87E-04 1.92E-04 1.74E-04 Hatchintake Hatch Containment Midpoint X

Maintenance between 1.21 E-03 Hatch CR intakes Steam Jet Air N CR 3.E Ejector (1) intake 3.02E-03 WK27/

(1) Based on recent meteorological and plant configuration data, the X/Q for the steam jet air ejector release point was determined to be higher than the X/Q for the condenser release point that was provided in Reference 1.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 8 of 39 Table 2.9.2-8 Release-Receptor Point Pairs Assumed for Analysis Events (Refer to Table 2.9.2-7 for Release/Receptor Pair Locations)

Event Prior to Control During Control After Initiation Room Isolation Room Isolation of Filtered Air Makeup LOCA:

- Containment Leakage (SBVS)

A C

B

- Containment (SBVS Bypass)

S U

T

- ECCS Leakage J

L K

- RWT Backleakage D

F E

- Cont. Purge/H2 Purge A

C B

FHA:

Containment Release V

X W

FHB Release G

I H

MSLB:

Outside Containment - Intact SG M

0 N

Outside Containment - Faulted M

0 N

SG Inside Containment (SBVS)

A C

B Inside Containment (SBVS S

U T

Bypass)

SGTR Y (Prior to Reactor Trip) 0 N

M (After Reactor Trip)

Locked Rotor M

0 N

CEA Ejection:

- Secondary Release M

0 N

- Inside Containment (SBVS)

A C

B

- Inside Containment (SBVS S

U T

Bypass)

IOMSSV M

0 N

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 9 of 39 Table 2.9.2-9 Offsite Atmospheric Dispersion Factors (X/Q) for Analysis Events EAB X/Q LPZ XIQ Time Period (sec/m3)

(sec/m3) 0-2 hours 9.84-05 9.56E-05 0-8 hours 5.53-05 5.34E-05 8-24 hours 4.15-05 3.99E-05 1-4 days 2.22E-05 2.12E-05 4-30 days 9.06E-06 8.55E-06 The above table summarizes the maximum X/Q values for the EAB and LPZ. Note that the 0-2 hour EAB X/Q value was used for the entire event.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 10 of 39 Table 2.9.2-10 Control Room Ventilation System Parameters Parameter EPU Value Pre-EPU Value Control Room Volume 96,228 ft3 62,318 ft3 Normal Operation Filtered Makeup Flow Rate 0 cfm Same Filtered Recirculation Flow Rate 0 cfm Same Unfiltered Makeup Flow Rate 920 cfm Same Unfiltered Inleakage 460 cfm 500 cfm Emergency Operation Isolation Mode:

Filtered Makeup Flow Rate 0 cfm Same Filtered Recirculation Flow Rate 1760 cfm*

2000 cfm Unfiltered Makeup Flow Rate 0 cfm Same Unfiltered Inleakage 460 cfm 500 cfm Filtered Makeup Mode:

Filtered Makeup Flow Rate 504 cfm*

450 cfm Filtered Recirculation Flow Rate 1256 cfm*

1550 cfm Unfiltered Makeup Flow Rate 0 cfm Same Unfiltered Inleakage 460 cfm 500 cfm Filter Efficiencies:

Particulates 99%

Same Elemental iodine 95%

Same Organic iodine 95%

Same

• Control room emergency ventilation flow rates conservatively consider over/under frequency/voltage of the emergency diesel generators, as well as tolerance in the control room ventilation flow rate test acceptance criteria.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 11 of 39 Table 2.9.2-11 LOCA Direct Shine Dose Direct Shine Dose Source(rm (rein)

Containment 0.027 Filters 0.094 External Cloud 0.078 Total 0.199 - 0.20

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 12 of 39 Table 2.9.2-12 Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Release Inputs:

Core Power Level 3030 MWt (-3020 + 0.3%)

2754 MWt (2700 + 2%)

Core Average Fuel Burnup 49,000 MWD/MTU 45,000 MWD/MTU Fuel Enrichment 1.5 - 5.0 w/o 3.0 - 4.5 w/o Initial RCS Equilibrium Activity 1.0 piCi/gm DE 1-131 and 1.0 pCi/gm DE 1-131 and 518.9 iiCi/gm DE Xe-1 33 (Table 2.9.2-2) 1 00/E-bar gross activity Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment Containment Leakage Rate 0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.5% (by volume)/day Same after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.25% (by volume)/day Same LOCA release phase timing and duration RG 1.183, Table 4 Same Core Inventory Release Fractions (gap release RG 1.183, Sections 3.1 and 3.2 Same and early in-vessel damage phases)

ECCS Systems Leakage Sump Volume (minimum) 67,394 ft3 55,460 ft3 (difference based on thermodynamic conditions and delivered RWT inventory)

ECCS Leakage to RAB (2 times allowed 4750 cc/hr 4510 cc/hr value)

Flashing Fraction Calculated - 5.5%

Calculated - 7.5%

Used for dose determination - 10%

Used for dose determination - 10%

Chemical form of the iodine in the sump 0% aerosol, 97% elemental iodine, and Same water 3.0% organic iodine Release ECCS Area Filtration Efficiency Elemental iodine - 95%

Same Organic iodine - 95%

Same Particulates - 99% (100% of the Same particulates are retained in the ECCS fluid)

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 13 of 39 Table 2.9.2-12 (continued)

Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value RWT Back-leakage Sump Volume (at time of recirculation) 67,394 ft3 57,140 ft3 ECCS Leakage to RWT (2 times allowed 2 gpm Same value)

Flashing Fraction (elemental iodine 0 % based on temperature of fluid reaching Same assumed to be released into tank space RWT based upon partition factor)

RWT liquid/vapor Elemental Iodine Table 2.9.2-17 Different based on RWT/sump conditions partition factor Elemental Iodine fraction in RWT Table 2.9.2-16 Different based on RWT/sump conditions Initial RWT Liquid Inventory (minimum) 44,147 gallons 38,842 gallons Release from Sump to RVVT Vapor Space Table 2.9.2-18 Different based on RWT/sump conditions Release from RWT Vapor Space to 1.07 cfm Not explicitly used as model input; the vent flow Environment concept was incorporated into effective sump to atmosphere iodine flow determination used in pre-EPU model.

Containment or Hydrogen Purge Release 500 cfm for 30 sec (H2 purge) 42,000 cfm for 5 sec (cont purge)

Removal Inputs:

Containment Particulates/Aerosol Natural 0.1/hour Same Deposition (only credited in unsprayed regions)

Containment Elemental Iodine Natural/Wall 2.89/hour Same Deposition Containment Spray Region Volume 2,155,160 ft3 Same Containment Unsprayed Region Volume 350,840 ft3 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 14 of 39 Table 2.9.2-12 (continued)

Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value 23,389 cfm (during spray operation, equal Flow rate between sprayed and unsprayed to 4 x unsprayed volume per hour) containment volumes 11,695 cfm (after sprays are secured, equal to 2 x unsprayed volume per hour)

Spray Removal Rates:

Elemental Iodine 20/hour Same Time to reach DF of 200 2.331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br /> 3.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Particulate Iodine 6.07/hour 6.43/hour Time to reach DF of 50 2.334 hours0.00387 days <br />0.0928 hours <br />5.522487e-4 weeks <br />1.27087e-4 months <br /> 2.60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> Spray Initiation Time 80.0 seconds 64.5 seconds Spray Termination Time 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Same Control Room Ventilation System (See Table 2.9.2-10)

Time of automatic control room 50 seconds Same isolation Time of manual control room air intake 1.5 hrs Same opening Secondary Containment Filter Efficiency Particulates - 99%

Same Elemental iodine - 95%

Same Organic iodine - 95%

Same Secondary Containment Drawdown Time 310 seconds Same Secondary Containment Bypass Fraction 9.6%

Same Containment or Hydrogen Purge Filtration 0%

Same Transport Inputs:

Containment Release Nearest Containment penetration to CR Same Secondary Containment release prior to ventilation intake drawdown Containment Release Plant stack Same Secondary Containment release after drawdown

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 15 of 39 Table 2.9.2-12 (continued)

Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Containment Release Nearest Containment penetration to CR Same Secondary Containment Bypass Leakage ventilation intake ECCS Leakage ECCS exhaust louver Same RWT Backleakage RWT Same Containment or Hydrogen Purge Plant Stack Same Personnel Dose Conversion Inputs:

Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 16 of 39 Table 2.9.2-13 LOCA Time Dependent RWT pH Time Time RWT pH (hours) 0.00 4.500 0.40 4.500 0.50 4.500 1.0 4.501 5.0 4.505 10.0 4.511 15.0 4.517 25.0 4.528 50.0 4.555 75.0 4.580 100.0 4.604 125.0 4.626 150.0 4.648 200.0 4.687 250.0 4.724 300.0 4.758 350.0 4.789 400.0 4.818 450.0 4.845 500.0 4.871 550.0 4.895 600.0 4.918 650.0 4.939 700.0 4.960 720.0 4.968

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 17 of 39 Table 2.9.2-14 L OCA TimA RWT Total Iodine RWT Elemental Iodine Time Concentration*

Concentration (hours)

[I]aq

[I2]aq

_ 4m-atomiliter)

(gm-atomlliter) 0.00 0.OOE+00 0.OOOE+00 0.40 0.OOE+00 0.OOOE+00 0.50 1.67E-08 3.142E-12 1.0 1.OOE-07 1.122E-10 5.0 7.59E-07 6.173E-09 10.0 1.56E-06 2.487E-08 15.0 2.35E-06 5.339E-08 25.0 3.85E-06 1.320E-07 50.0 7.30E-06 3.960E-07 75.0 1.04E-05 6.904E-07 100.0 1.31E-05 9.771E-07 125.0 1.56E-05 1.241E-06 150.0 1.78E-05 1.477E-06 200.0 2.16E-05 1.865E-06 250.0 2.48E-05 2.151E-06 300.0 2.76E-05 2.355E-06 350.0 3.OOE-05 2.493E-06 400.0 3.20E-05 2.582E-06 450.0 3.38E-05 2.631 E-06 500.0 3.54E-05 2.651_E-06 550.0 3.68E-05 2.648E-06 600.0 3.81 E-05 2.627E-06 650.0 3.92E-05 2.594E-06 700.0 4.03E-05 2.551 E-06 720.0 4.07E-05 2.532E-06 Includes radioactive and stable iodine isotopes

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 18 of 39 Table 2.9.2-16 LOCA Time Dependent RWT Elemental Iodine Fraction.

Time (hr)

Elemental Iodine Fraction 0.0 0.OOOE+00 0.40 0.OOOE+00 0.50 3.763E-04 1.0 2.242E-03 5.0 1.627E-02 10.0 3.181E-02 15.0 4.551E-02 25.0 6.850E-02 50.0 1.085E-01 75.0 1.333E-01 100.0 1.492E-01 125.0 1.596E-01 150.0 1.663E-01 200.0 1.725E-01 250.0 1.731E-01 300.0 1.707E-01 350.0 1.665E-01 400.0 1.613E-01 450.0 1.557E-01 500.0 1.498E-01 550.0 1.438E-01 600.0 1.379E-01 650.0 1.322E-01 700.0 1.267E-01 720.0 1.245E-01

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 19 of 39 Table 2.9.2-18 LOCA Release Rate from Sump to RWT Vapor Space Time Adjusted Iodine Release Times Rate (hours)

(cfm) 0.0 0.0 0.40 7.973E-07 10.0 8.637E-06 25.0 4.886E-05 75.0 1.545E-04 125.0 2.636E-04 200.0 3.895E-04 300.0 4.995E-04 450.0 5.563E-04 600.0 5.687E-04

St. Lucie Unit I Docket No. 50-335 L-2011-360 Page 20 of 39 Table 2.9.2-19 Fuel Handling Accident (FHA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level Before Shutdown 3030 MWt (-3020 + 0.3%)

2754 MWt (2700 + 2%)

Core Average Fuel Burnup 49,000 MWD/MTU 45,000 MWD/MTU Discharged Fuel Assembly Burnup 45,000 - 62,000 MWD/MTU Same Fuel Enrichment 1.5 - 5.0 w/o 3.0 - 4.5 w/o Maximum Radial Peaking Factor 1.65 1.7 Number of Fuel Assemblies in the Core 217 Same Number of Fuel Assemblies Damaged 1

Same Delay Before Spent Fuel Movement 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Same FHA Source Term for a Single Assembly Table 2.9.2-5 Different based on power, burnup and enrichment High Burnup Fuel Adjustment Factor 2.0 Same Water Level Above Damaged Fuel Assembly 23 feet minimum Same Iodine Decontamination Factors Elemental iodine-285 Same Organic iodine - 1 Same Noble Gas Decontamination Factor 1

Same Chemical Form of Iodine In Pool Elemental iodine - 99.85%

Same Organic iodine - 0.15%

Same Chemical Form of Iodine Above Pool Elemental iodine - 57%

Same Organic iodine - 43%

Same Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System 50 seconds Same Isolation Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Same Control Room Unfiltered Inleakage 460 cfm 500 cfm Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 21 of 39 Table 2.9.2-20 Main Steam Line Break (MSLB) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (-3020 + 0.3%)

2754 MWt (2700 + 2%)

Core Average Fuel Burnup 49,000 MWD/MTU 45,000 MWD/MTU Fuel Enrichment 1.5 - 5.0 w/o 3.0 - 4.5 w/o Maximum Radial Peaking Factor 1.65 1.7

% DNB for MSLB Outside of Containment 1.2%

1.8%

% DNB for MSLB Inside of Containment 21%

29%

% Fuel Centerline Melt for MSLB Outside of 0.29%

0.43%

Containment

% Fuel Centerline Melt for MSLB Inside of 6.1%

Containment Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment Initial RCS Equilibrium Activity 1.0 tiCi/gm DE 1-131 and 1.0 p.Ci/gm DE 1-131 and 518.9 piCi/gm DE Xe-133 (Table 2.9.2-2) 100/E-bar gross activity Initial Secondary Side Equilibrium Iodine Activity 0.1 1iCi/gm DE 1-131 (Table 2.9.2-3)

Same Release Fraction from DNB Fuel Failures RG 1.183, Section 3.2 Same Release Fraction from Centerline Melt Fuel Failures RG 1.183, Section 3.2, and Section 1 of Same Appendix H High Burnup Fuel Adjustment Factor 1.04608 1.03687 Steam Generator Tube Leakage 0.25 gpm per SG (Table 2.9.2-22) 0.25 gpm per SG Time to Terminate SG Tube Leakage 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours Steam Release from Intact SGs Table 2.9.2-21 Different based on different thermodynamic conditions Intact SG Tube Uncovery Following Reactor Trip Time to tube recovery 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour Flashing Fraction 6%

5%

Unaffected SG5-100 Steam Generator Secondary Side Partition Coefficient Faulted SG - None Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 22 of 39 Table 2.9.2-20 (continued)

Main Steam Line Break (MSLB) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Time to Reach 212 OF and Terminate Steam Release 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 10.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> Containment Volume 2.506E+06 ftW Same Containment Leakage Rate 0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.5% (by volume)/day Same after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.25% (by volume)/day Same Particulates - 99%

Same Secondary Containment Filter Efficiency Elemental iodine - 95%

Same Organic iodine - 95%

Same Secondary Containment Drawdown Time 310 seconds Same Secondary Containment Bypass Fraction 9.6%

Same 406,715 Ibm 411,500 Ibm RCS Mass Minimum mass used for fuel failure dose contribution to maximize SG tube leakage activity.

Minimum - 120,724.1 Ibm (per SG)

Minimum - 105,000 Ibm (per SG)

Maximum - 226,800 Ibm (per SG)

Maximum - 205,000 Ibm (per SG)

Maximum mass used for faulted SG to maximize SG Secondary Side Mass secondary side dose contribution. Minimum mass used for intact SG to maximize steam release nuclide concentration.

Particulates - 0%

Same Chemical Form of Iodine Released from SGs Elemental iodine - 97%

Same Organic iodine - 3%

Same Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System 50 seconds Same Isolation Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Same Control Room Unfiltered Inleakage 460 cfm 500 cfm Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 23 of 39 Table 2.9.2-20 (continued)

Main Steam Line Break (MSLB) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same Aerosols - 0.1 hr-1 Same Containment Natural Deposition Coefficients Elemental Iodine - 2.89 hr-Same I Organic Iodine - None Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 24 of 39 Table 2.9.2-21 MSLB Steam Release Rate Intact SG Steam Release Time Rt (hours)*Rate (hours)*

(Ibm /min) 0 5225 0.50 2687 0.75 2687 1.39 2687 2.00 2711 4.00 2711 6.00 2711 8.00 2711 10.50 2711 12.40 0.00 Flow rates are applied until the next time point.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 25 of 39 Table 2.9.2-23 Steam Generator Tube Rupture Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (-3020 + 0.3%)

2754 MWt (2700 + 2%)

1.0 p.Ci/gm DE 1-131 and 1.0 pCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 pCi/gm DE Xe-133 100/E-bar gross activity (Table 2.9.2-2)

Initial Secondary Side Equilibrium Iodine Activity 0.1 pCi/gm DE 1-131 (Table 2.9.2-3) 0.1 piCi/gm DE 1-131 Maximum Pre-Accident Spike Iodine Concentration 60.Ci/gm DE 1-131 Same Maximum Equilibrium Iodine Concentration 1.0pCi/gm DE 1-131 Same Iodine Spike Appearance Rate 335 times Same Duration of Accident-Initiated Spike 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Same Break Flow and Steam Releases See Table 2.9.2-24 Different based on different thermodynamic conditions and isolation time Break Flow Flashing Fraction Prior to Reactor Trip - 17% (Hot Leg)

Prior to Reactor Trip - 17%

Following Reactor Trip - 6% (Hot Leg)

Following Reactor Trip - 5%

Time to Terminate Break Flow 45 minutes 30 minutes Steam Generator Tube Leakage Rate 0.25 gpm per SG Same Time to Terminate Tube Leakage 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Same Time to Re-cover Unaffected SG Tubes 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Same Flashed tube flow - none Same Steam Generator Secondary Side Partition Coefficients Flashed tube flow-100 Same Non-flashed tube flow - 100 Same Time to Reach 212 OF and Terminate Steam Release 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 10.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> RCS Mass Pre-accident Iodine Spike: 406,715 Ibm Pre-accident Iodine spike-423,700 Ibm Concurrent Iodine Spike: 474,951 Ibm Concurrent Iodine spike -452,000 Ibm

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 26 of 39 Table 2.9.2-23 (continued)

Steam Generator Tube Rupture Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value SG Secondary Side Mass Minimum -120,724 Ibm (per SG)

Minimum - 105,000 Ibm (per SG)

Maximum - 226,800 Ibm (per SG)

Maximum - 260,000 Ibm (per SG)

Minimum used for primary-to-secondary Minimum used for primary-to-secondary leakage leakage to maximize secondary nuclide to maximize secondary nuclide concentration.

concentration. Maximum used for initial Maximum used for initial secondary inventory secondary inventory release to maximize release to maximize secondary side dose secondary side dose contribution, contribution.

Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System Isolation 522.7 seconds (Hot Leg Break Rx trip + 50 Sec) 409.2 seconds Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Control Room Unfiltered Inleakage 460 cfm 500 cfm Breathing Rates Offsite RG 1.183, Section 4.1.3 Same Control Room RG 1.183, Section 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 27 of 39 Table 2.9.2-24 SGTR Break Flow and Steam Releases Ruptured SG Ruptured SG Unaffected Time Event Description Break Flow Steam SG Steam (hr)*

(EBrelomw)

Release Release (Ibm/min)

(Ibm/min) 0 Event Initiation 2544.83 111000 110730 0.131 Reactor Trip 1724.28 4920 100 0.75 Ruptured SG Isolated 0.00 130 3760 1.00 Unaffected SG tubes Re-26.00 0

3760 covered 1.50 Manual Realignment of CR 39.00 0

3760 Intakes 2.00 X/Q Change 39.00 0

3760 8.00 X/Q Change 39.00 0

2320 Termination of SG Releases at 0

0 0

212F

• Flow rates are applied until the next time point.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 28 of 39 Table 2.9.2-28 Locked Rotor Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (-3020+0.3%)

2754 MWt (2700 + 2%)

Core Average Fuel Burnup 49,000 MWD/MTU 45,000 MWD/MTU Fuel Enrichment 1.5 - 5.0 w/o 3.0 - 4.5w/o Maximum Radial Peaking Factor 1.65 1.7 Percent of Fuel Rods in DNB 19%

13.7%

High Burnup Fuel Adjustment Factor 1.04608 1.03687 Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment 1.0 pCi/gm DE 1-131 and 1.0 ýtCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 pCi/gm DE Xe-1 33 1 00/E-bar gross activity (Table 2.9.2-2)

Initial Secondary Side Equilibrium Iodine Activity 0.1 1iCi/gm DE 1-131 (Table 2.9.2-3) 0.1 iiCi/gm DE 1-131 Release Fraction from Breached Fuel RG 1.183, Section 3.2 Same Steam Generator Tube Leakage 0.5 gpm (Table 2.9.2-31) 0.5 gpm Time to Terminate SG Tube Leakage 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours Secondary Side Mass Releases to Environment Table 2.9.2-29 Different based on different thermodynamic conditions SG Tube Uncovery Following Reactor Trip Time to tube recovery 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Same Flashing Fraction 5%

Same Steam Generator Secondary Side Partition Flashed tube flow - none Same Coefficient Non-flashed tube flow - 100 Same Time to Reach 212 OF and Terminate Steam Release12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 10.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> Minimum - 406,715 Ibm Minimum - 411,500 Ibm RCS Mass (9060 ft3 at system conditions of 2250 psia and Minimum mass used for fuel failure dose 578.5°F) contribution to maximize SG tube leakage activity.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 29 of 39 Table 2.9.2-28 (continued)

Locked Rotor Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value SG Secondary Side Mass Minimum - 120,724 Ibm (per SG)

Minimum - 105,000 Ibm (per SG)

Maximum - 226,800 Ibm (per SG)

Maximum - 205,000 Ibm (per SG)

Minimum used for primary-to-secondary leakage Minimum used for primary-to-secondary leakage to maximize secondary nuclide concentration.

to maximize secondary nuclide concentration.

Maximum used for initial secondary inventory Maximum used for initial secondary inventory release to maximize secondary side dose release to maximize secondary side dose contribution, contribution.

Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System 50 seconds Same Isolation Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Same Control Room Unfiltered Inleakage 460 cfm 500 cfm Breathing Rates Offsite RG 1.183 Section 4.1.3 Same Onsite RG 1.183 Section 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same Control Room Model 96,228 fto volume 62,318 ftW volume 504 cfm Makeup Flow 450 cfm Makeup Flow

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 30 of 39 Table 2.9.2-30 CEA Ejection Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (-3020 + 0.3%)

2754 MWt (2700 + 2%)

Core Average Fuel Burnup 49,000 MWD/MTU 45,000 MWD/MTU Fuel Enrichment 1.5 - 5.0 w/o 3.0 - 4.5 w/o Maximum Radial Peaking Factor 1.65 1.7 Percent of Fuel Rods in DNB 9.5%

Same Percent of Fuel Rods with Centerline Melt 0.5%

Same Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment 1.0 jiCi/gm DE 1-131 and 1.0 OCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 ýiCi/gm DE Xe-133 100/E-bar gross activity (Table 2.9.2-2)

Initial Secondary Side Equilibrium Iodine Activity 0.1 [tCi/gm DE 1-131 (Table 2.9.2-3) 0.1 '.Ci/gm DE 1-131 Release Fraction from DNB Fuel Failures Section 1 of Appendix H to RG 1.183 Same Release Fraction from Centerline Melt Fuel Failures Section 1 of Appendix H to RG 1.183 Same 1.04608 1.03687 High Burnup Fuel Adjustment Factor1.401038 10 fuel assemblies 8 fuel assemblies Steam Generator Tube Leakage 0.5 gpm (Table 2.9.2-29) 0.5 gpm Time to Terminate SG Tube Leakage 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours Secondary Side Mass Releases to Environment Table 2.9.2-25a Different based on different thermodynamic conditions SG Tube Uncovery Following Reactor Trip Time to tube recovery 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Same Flashing Fraction 5%

Same Flashed tube flow - none Same Steam Generator Secondary Side Partition Coefficient Flashed tube flow -

100 Same Non-flashed tube flow - 100 Same Time to Reach 212 OF and Terminate Steam Release 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 10.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> Minimum -- 406,715 Ibm Minimum - 411,500 Ibm RCS Mass Minimum mass used for fuel failure dose Minimum mass used for fuel failure dose contribution to maximum SG tube leakage activity, contribution to maximum SG tube leakage activity.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 31 of 39 Table 2.9.2-30 (continued)

CEA Ejection Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Minimum - 120,724 Ibm (per SG)

Minimum - 105,000 Ibm (per SG)

Maximum - 226,800 Ibm (per SG)

Maximum - 205,000 Ibm (per SG)

Minimum used for primary-to-secondary leakage Minimum used for primary-to-secondary leakage SG Secondary Side Mass to maximize secondary nuclide concentration.

to maximize secondary nuclide concentration.

Maximum used for initial secondary inventory Maximum used for initial secondary inventory release to maximize secondary side dose release to maximize secondary side dose contribution, contribution.

Particulates - 95%

Same Chemical Form of Iodine Released to Containment Elemental iodine - 4.85%

Same Organic iodine - 0.15%

Same Particulates - 0%

Same Chemical Form of Iodine Released from SGs Elemental iodine - 97%

Same Organic iodine - 3%

Same Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System 50 seconds Same Isolation Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Same Control Room Unfiltered Inleakage 460 cfm 500 cfm Breathing Rates RG 1.183 Sections 4.1.3 and 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same Control Room Model 96,228 ftW volume 62,318 ftW volume 504 cfm Makeup Flow 450 cfm Makeup Flow Containment Volume 2.506E+06 ft" Same Containment Leakage Rate 0 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.5% (by volume)/day Same after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.25% (by volume)/day Same Particulates - 99%

Same Secondary Containment Filter Efficiency Elemental iodine - 95%

Same Organic iodine - 95%

Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 32 of 39 Table 2.9.2-30 (continued)

CEA Ejection Accident - Inputs and Assumptions Secondary Containment Drawdown Time 310 seconds Same Secondary Containment Bypass Fraction 9.6%

Same Aerosols - 0.1 hr 1 Same Containment Natural Deposition Coefficients Elemental Iodine - 2.89 hr1 Same Organic Iodine - None Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 33 of 39 Table 2.9.2-32 IOMSSV Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (3020 + 0.3%)

2754 MWt (2700 + 2%)

1.0 pCi/gm DE 1-131 and 1.0 pCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9.iCi/gm DE Xe-1 33 100/E-bar gross activity (Table 2.9.2-2)

Initial Secondary Side Equilibrium Iodine Activity 0.1 piCi/gm DE 1-131 (Table 2.9.2-3) 0.1 iiCi/gm DE 1-131 Steam Generator Tube Leakage 0.5 gpm (Table 2.9.2-33) 0.5 gpm Time to Terminate SG Tube Leakage 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours Secondary Side Mass Releases to Environment Entire inventory in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Same Steam Generator Secondary Side Partition Coefficient None Same Maximum - 226,800 Ibm per SG Maximum - 205,000 Ibm per SG Maximum mass used for initial secondary Maximum mass used for initial secondary SG Secondary Side Mass inventory release to maximize secondary side inventory release to maximize secondary side dose contribution.

dose contribution.

Atmospheric Dispersion Factors Offsite Table 2.9.2-9 Different based on meteorological data Onsite Table 2.9.2-7 Different based on meteorological data Control Room Ventilation System Time of Control Room Ventilation System 50 seconds Same Isolation Time of Control Room Filtered Makeup Flow 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Same Control Room Unfiltered Inleakale 460 cfm 500 cfm Breathing Rates:

Offsite RG 1.183 Section 4.1.3 Same Onsite RG 1.183 Section 4.2.6 Same Control Room Occupancy Factor RG 1.183 Section 4.2.6 Same

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 34 of 39 Table 2.9.3-3 RADTRAD-NAI Pathway Description Tables Pathway Description Pathway Compartment RADTRAD-NAI Number Connections Pathway Type WGDT Leakage 1

1 to 2 Filtered Control Room Unfiltered Inleakage 2

2 to 3 Filtered Control Room Filtered Makeup 3

2 to 3 Filtered Control Room Normal HVAC Intake 4

2 to 3 Filtered Control Room Exhaust 5

3 to 2 Filtered Pathway I - WGDT Leakage to Environment Pathway Time Flow Rate Filter Efficiency (hours)

(cfm)

Aerosol Elemental Organic 0.0 1e6 0

0 0

720.0 1e6 0

0 0

Pathway 2 - Control Room Unfiltered Inleakage Pathway Time Flow Rate Filter Efficiency (hours)

(cfm)

Aerosol Elemental Organic 0.0 460 0

0 0

720.0 460 0

0 0

Pathway 3 - Control Room Filtered Makeup Pathway Time Flow Rate Filter Efficiency (hours)

(cfm)

Aerosol Elemental Organic 0.0 0.0 0.0 0.0 0.0 0.01389 0.0 0.0 0.0 0.0 1.5 450.0 0.0 0.0 0.0

+12%

• 720.0 450.0 0.0 0.0 0.0

+12%

Pathway 4 - Control Room Unfiltered Normal Intake Pathway Time Flow Rate Filter Efficiency (hours)

(cfm)

Aerosol Elemental Organic 0.0 920.0 0.0 0.0 0.0 0.01389 0.0 0.0 0.0 0.0 1.5 0.0 0.0 0.0 0.0 720.0 0.0 0.0 0.0 0.0 12% is to account for the potential impact on ventilation flow rates of surveillance test tolerances and overlunder frequency of the emergency diesel generators.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 35 of 39 Table 2.9.3-3 RADTRAD-NAI Pathway Description Tables (continued)

Pathway 5 - Control Room Exhaust Pathway Time Flow Rate Filter Efficiency (hours)

(cfm)

Aerosol Elemental Organic 0.0 1380.0 0.0 0.0 0.0 0.01389 460.0 0.0 0.0 0.0 1.5 964.0 0.0 0.0 0.0 720.0 964.0 0.0 0.0 0.0

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 36 of 39 Table 2.9.3-6 WGDT Failure X/Q Tables X/Q Table 1 - EAB St. Lucie Time Unit I X/Q Unit 2 X/Q Bounding (hours)

(sec/m3)

(sec/m3)

EAB X/Q (sec/m 3) 0.0 9.84E-05 1.05E-04 1.05E-04 720.0 9.84E-05 1.05E-04 1.05E-04 X/Q Table 2 - LPZ St. Lucie Time Unit I X/Q Unit 2 X/Q Bounding (hours)

(sec/m3)

(sec/m 3)

LPZ X/Q (sec/m 3 )

0.0 9.56E-05 1.01E-04 1.01E-04 2.0 5.34E-05 5.74E-05 5.74E-05 8.0 3.99E-05 4.32E-05 4.32E-05 24.0 2.12E-05 2.33E-05 2.33E-05 96.0 8.55E-06 9.62E-06 9.62E-06 720.0 8.55E-06 9.62E-06 9.62E-06 X/Q Table 3 - Control Room HVAC Intake via N or S Fresh Air Intake Summary - Bounding St. Lucie HVAC XIQ Table L-7A/ 2L-7A L-7B/ 2L-7B St. Lucie Time HVAC X/Q to HVAC to HVAC Bounding X/Q X/Q HVAC X/Q (hours)

(seclm3 )

(sec/m3)

(sec/m 3)

(sec/m3) 0 2.390E-03 3.770E-03 3.735E-03 3.770E-03 0.01389 2.390E-03 3.770E-03 3.735E-03 3.770E-03 1.5 6.925E-04 3.770E-03 3.735E-03 3.770E-03 2

4.875E-04 3.195E-03 3.045E-03 3.195E-03 8

2.185E-04 1.390E-03 1.327E-03 1.390E-03 24 1.460E-04 1.101E-03 1.039E-03 1.101E-03 96 1.280E-04 8.870E-04 8.305E-04 8.870E-04 720 1.280E-04 8.870E-04 8.305E-04 8.870E-04

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 37 of 39 Table 2.9.3-6 WGDT Failure X/Q Tables (continued)

X/Q Table 4 - Control Room Unfiltered Inleakage X/Q via Louver L-11 or 2L-11 St Lucie Unit I Unit 2 Unit 1 Unit I Unit 2 Unit 2 Bounding Stack Stack L-7A X/Q L-7B X/Q L-7A X/Q L-7B X/Q Inleakage Time X/Q X/Q X/Q (hours)

(Louver (Louver (Louver (Louver (Louver (Louver L-11) 2L-11)

L-11)

L-11) 2L-11) 2L-11)

(sec/m3)

(sec/m 3)

(sec/m3)

(sec/m 3)

(sec/m3)

(sec/m 3)

(sec/m3) 0 2.55E-03 2.60E-03 3.56E-03 2.72E-03 3.61 E-03 2.90E-03 3.61 E-03 2

1.78E-03 1.84E-03 2.83E-03 2.06E-03 2.92E-03 2.17E-03 2.92E-03 8

7.94E-04 8.09E-04 1.17E-03 8.51E-04 1.23E-03 8.98E-04 1.23E-03 24 5.37E-04 5.62E-04 8.92E-04 6.37E-04 9.38E-04 6.83E-04 9.38E-04 96 4.62E-04 4.59E-04 7.14E-04 4.88E-04 7.66E-04 5.17E-04 7.66E-04 720 4.62E-04 4.59E-04 7.14E-04 4.88E-04 7.66E-04 5.17E-04 7.66E-04

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 38 of 39 Table 2.9.3-7 Dose Consequences for Waste Gas Decay Tank Failure TEDE Dose (rem)

Dose Contribution EAB LPZ CR 30 Days 30 Days 30 Days WGDT Failure 0.055 0.053 0.269 Acceptance Criteria 0.1*

0.1*

5**

Control Room Unfiltered Inleakage = 460 cfm The 0.1 REM (TEDE) 30 day dose limit is specified in NUREG-0800, BTP-1 1-3 Rev 3 (March 2007) Position B.1.A for the EAB. The LPZ limit is assumed in this calculation to be the same value.

• • The 5.0 REM (TEDE) CR limit is not specified in either the BTP or Reg Guide 1.183 for this event, but is the specified Control Room limit for all other AST events.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 Page 39 of 39 Table 2.9.3-8 WGDT Source Term - Technical Specification DE Xe-133 Curies DE Xe-133 WGDT Inventory EAB Dose (Ci)

(Limit = 0.1 Rem TEDE)

Design Basis 90,921 0.055 TS 165,000 0.099997

St. Lucie Unit 1 L-2011-360 Docket No. 50-335 Page 1 of 2 Technical Specifications Section 3.11.2.6 Radiological Effluents - Gas Storage Tanks Revision To Proposed Change Submitted By FPL Letter L-2010-259 Regarding Extended Power Uprate License Amendment Request Description of the Change EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, Item 28. TS 3/4.11.2.6, RADIOACTIVE EFFLUENTS - GAS STORAGE TANKS, proposed that LIMITING CONDITION FOR OPERATION (LCO) 3.11.2.6 be changed from "less than or equal to 285,000 curies noble gases (considered as Xe-1 33)." to "less than or equal to 202,500 curies noble gases (considered as Xe-1 33)."

By email from the NRC Project Manager dated June 21, 2011, additional information related to accident dose was requested by the NRC staff in the Accident Dose Branch (AADB) to support their review of the EPU LAR. The request for additional information (RAI) identified sixteen questions. The response to this RAI was submitted to the NRC by FPL letter L-2011-314, dated August 12, 2011 (Accession No. ML11234A283). The FPL letter contained revised atmospheric dispersion factors (X/Q's) that were based on updated site meteorological data provided on a compact disc (CD) that was enclosed with the letter.

The revised X/Q's were inputs to a revision to dose analysis calculations. As a result of the revised calculations, the quantity of radioactivity contained in each gas storage tank is being reduced to less than or equal to 165,000 curies of noble gas.

LCO 3.11.2.6 is changed from "... less than or equal to 285,000 curies noble gases..." to"...less than or equal to 165,000 curies noble gases..."

Note that the change described is from the current TS value for curies noble gases, not the EPU LAR proposed value of 202,500 curies noble gases. The marked up TS page in Attachment 3 contains this proposed change and the EPU LAR proposed change that is being revised.

The remaining changes proposed for TS 3/4.11.2.6 remain valid.

Basis for the change:

The gas storage tank inventory source term required to generate an exclusion area boundary (EAB) dose of 0.1 rem total effective dose equivalent (TEDE) is the basis for a proposed TS limit of 165,000 curies noble gas (considered as Dose Equivalent Xe-1 33).

The limit of 0.1 rem is consistent with Branch Technical Position 11-5, Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure, of Standard Review Plan Chapter 11, Radioactive Waste Management, of NUREG-0800.

FPL letter (L-2011-314) submitted revised atmospheric dispersion factors (x/Q's) based on updated site meteorological data provided on a compact disc (CD) that was enclosed

St. Lucie Unit 1 L-2011-360 Docket No. 50-335 Page 2 of 2 with the letter. The revised X/Q's were utilized in accident dose calculation to determine the dose at the EAB. To ensure that the dose at the EAB does not exceed 0.1 rem TEDE, the radioactivity in each of the gas storage tanks has been reduced from the current TS value of "285,000 curies noble gases (considered as Xe-1 33)" to a limit of "165,000 curies noble gases (considered as Xe-133)." The revised radioactivity limit being proposed in also reduced from the EPU LAR proposed limit of 202,500 curies noble gases (considered as Xe-1 33).

No Significant Hazards Consideration This change reduces the quantity of radioactivity in each gas storage tank to ensure that the EAB dose is less than or equal to 0.1 rem TEDE. The change was the result of revised accident dose analysis calculation results which used the x/Q values that were determined from updated meteorological data. The change is conservative as it is a reduction in the radioactivity in the tanks. As such, the conclusions of EPU LAR Section 5.2, No Significant Hazards Consideration, Item F. Reactor Coolant System Specific Activity remain valid. Accordingly, the proposed change

1) does not involve a significant increase in the propbability or consequences of an accident previously evaluated, 2) does not create the possibility of a new or different kind of accident from any previously evaluated, and 3) does not result in a significant reduction in a margin of safety.

Environmental Evaluation This change is a conservative change to reduce the radioactivity in the gas storage tanks. The change is a reduction in the proposed TS radioactivity limit change provided in the EPU LAR. The environmental considerations evaluation contained in the EPU LAR remain valid. Accordingly, the proposed license amendment is eligible for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed license amendment.

St. Lucie Unit 1 Docket No. 50-335 L-2011-360 ATTACHMENT 3 Supplemental Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Marked Up and Clean Technical Specification Pages This coversheet plus two pages

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 286.0GO curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

165,000 ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank when reactor coolant system activity exceeds 518.9 piCifgram DOSE EQUIVALENT XE-i 33 ST. LUCIE - UNIT 1 3/4 11-15 Amendment No. 59, 69

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 165,000 curies noble gases (considered as Xe-1 33).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank when reactor coolant system activity exceeds 518.9 pCi/gram DOSE EQUIVALENT XE-1 33.

ST. LUCIE - UNIT 1 3/4 11-15 Amendment No.,5, 69,