L-2011-467, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request

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Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request
ML11320A286
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 11/14/2011
From: Richard Anderson
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2011-467
Download: ML11320A286 (44)
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FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 November 14, 2011 L-2011-467 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 2 Docket No. 50-389 Renewed Facility Operating License No. NPF-16 Response to NRC Accident Dose Branch Request for Additional Information Reqarding Extended Power Uprate License Amendment Request

References:

(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021),

St. Lucie Unit 2, "License Amendment Request for Extended-Power Uprate,"

February 25, 2011, Accession No. ML110730116.

(2) Email from T. Orf (NRC) to C. Wasik (FPL), "St. Lucie 2 EPU draft RAIs -

Accident Dose branch (AADB)," August 31, 2011.

(3) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-404),

St. Lucie Unit 2, "Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request," October 5, 2011, Accession No. ML11290A065.

(4) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-360),

St. Lucie Unit 1, "Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request," September 2, 2011, Accession No. ML11251A159.

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

St. Lucie Unit 1, "Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request," August 12, 2011, Accession No. ML11341A283.

By letter L-2011-021 dated February 25, 2011 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. NPF-16 and revise the St. Lucie Unit 2 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).

an FPL Group company

L-2011-467 "Page 2 of 2 In an email from the NRC Project Manager dated August 31, 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 License Amendment Request (LAR). The request for additional information (RAI) identified twelve questions (AADB-1 through AADB-12). Reference 3 provided FPL's response to AADB-1 through AADB-1 1. Attachment 1 to this letter provides the FPL response to RAI AADB-1 2. In addition, Attachment 1 provides supplemental information to incorporate the revised atmospheric dispersion factors (x/Q's) and dose calculation results based on the site meteorological data provided in FPL letter L-2011-314 [Reference 51.

  • 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. 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. A proposed revision to the St. Lucie Unit 1 Gas Storage Tanks TS was submitted by FPL letter L-2011-360 [Reference 4].

This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2011-021 [Reference 1].

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

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

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.

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

Executed on q/- g'W'#n aer - ;-. 1)

Very truly yours, Ric ard L. Anders Site Vice President St. Lucie Plant Attachments (3) cc: Mr. William Passetti, Florida Department of Health

L-2011-467 Attachment 1 Page 1 of 37 Response to NRC Accident Dose Branch Request for Additional Information The following information is provided by Florida Power & Light (FPL) in response to the U.S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support the review of the Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie Unit 2 that was submitted to the NRC by FPL via letter L-2011-021, February 25, 2011, Accession No. ML110730116.

In an email dated August 31, 2011 from T. Orf (NRC) to C. Wasik (FPL),

Subject:

St. Lucie 2 EPU draft RAIs - Accident Dose branch (AADB), the NRC staff requested additional information regarding FPL's request to implement the EPU. The RAI consisted of twelve questions from the AADB. The responses to AADB-1 through AADB-1 1 were provided in FPL letter L-201 1-404, dated October 5, 2011, Accession No. ML11290A065. The response to RAI AADB-12 is provided below.

AADB-12 The NRC staff is relying on the accuracy of the information presented in Table 2.9.2 for the review of the radiological inputs and assumptions for the EPU design basis accident analyses. The NRC staff notes that there are several instances in Table 2.9.2 where primary and secondary activity concentration is shown as mCi/gm instead of pCi/gm.

The NRC staff review is proceeding based on the assumption that these instances represent typographical errors. Table 2.9.2-23 indicates two different times for the termination of SG tube leakage. The NRC staff review is proceeding based on the assumption that the time to terminate SG tube leakage for the EPU analysis is 12.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Please review and correct as necessary the information presented in Table 2.9.2 to ensure that it is accurate.

Response

EPU LAR Attachment 5, Table 2.9.2-23 is revised to correct the typographical errors and to clarify the time for termination of SG tube leakage. In addition, the following supplemental information is being provided to incorporate the revised atmospheric dispersion factors (x/Q's) and dose calculation results based on the site meteorological data submitted by FPL letter L-2011-314, dated August 12, 2011, Accession No. ML11234A283.

LAR Attachment 5, Section 2.9.2, Radiological Consequences Analyses Using Alternative Source Terms (AST)

The control room unfiltered inleakage is changed from 425 cfm to 395 cfm for all events.

This change affects all references to control room unfiltered inleakage of 425 cfm in Section 2.9.2.

Section 2.9.2.2.1.1 Common Input Parameters and Assumptions - Source Terms FPL letter L-2011-404, dated October 5, 2011, Accession No. ML11290A065 provided the response to RAls AADB-1 through AADB-1 1. As a result of the response to AADB-8, FPL is correcting an identified error in the statement of reference to the method of determining high burnup fuel gap release adjustment factor and is replacing the paragraph in EPU LAR Attachment 5, Section 2.9.2.2.1.1 in its entirety, after the four bullets providing the source term tables with the following paragraphs:

L-2011-467 Attachment 1 Page 2 of 37 Consistent with the method of Reference 9 accepted in Reference 10, a high burnup adjustment factor for gap release of affected assemblies will be implemented. The St.

Lucie Unit 2 EPU assumption is that two high burnup assemblies may exceed the Regulatory Guide (RG) 1.183 Footnote 11 combined burnup and kw/ft limits. Therefore, a high burnup adjustment/increase of 0.922% is applied to the release fractions for all non-LOCA events in which fuel damage causes the inventory of the fuel rod gaps to be released into the reactor coolant. The value of 0.922% is calculated in accordance with the methods outlined in Reference 9 and accepted in Reference 10 for St. Lucie Unit 1.

With 217 fuel assemblies in the core, the maximum number of high burnup rods represents [2/217] x 100 = 0.922% of the core. Doubling the gap fractions of 0.922% of the core would yield a core-wide adjustment factor of:

High Burnup Adjustment Factor = (2)(0.00922) + (1-0.00922) = 1.00922 This adjustment factor was applied to the gap release fractions in the RADTRAD-NAI release fraction timing files ("rft" file).

For the fuel handling accident (FHA), in which 100% of the rods in the dropped assembly are assumed to be damaged, high burnup is addressed by increasing the gap release fraction of the entire assembly by a factor of two.

Section 2.9.2.2.4 Atmospheric Dispersion Factors (X/Q)

The revised meteorological data are based on data collected in years, 1997, 1998, 1999, 2002, and 2003. The data were 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 following input parameters are changed as follows:

" Third paragraph - leakage to the reactor auxiliary building (RAB) is changed from assumed to start at 20.3 minutes to assumed to start at 22.3 minutes;

" Fourth paragraph - backleakage to the refueling water tank (RWT) is changed from assumed to start at 20.3 minutes to assumed to start at 22.3 minutes;

" Fifth paragraph -

o The maximum iodine concentration at the beginning of the event is changed from 4.079 E-05 gm-atom/liter to 4.088 E-05 gm-atom/liter; o The maximum pH is changed from 4.862 to 4.864; and o The maximum RWT elemental iodine fraction is changed from 0.1699 to 0.1694.

The next to the last paragraph is revised to correct an editorial error. The last sentence incorrectly discussed the control room inleakge, as opposed to the purge release to the environment. The last sentence, "The release is modeled for 30 seconds at 425 cfm until isolation occurs," is replaced with, "The purge release to the environment is modeled for 30 seconds at 2500 cfm until purge isolation occurs."

L-2011-467 Attachment 1 Page 3 of 37 Section 2.9.2.13 References The following two new references are added:

9. L-2007-085, Letter from Florida Power & Light Company to the USNRC,

Subject:

St.

Lucie Unit 1, Docket No. 50-335, Proposed License Amendment, Alternative Source Term and Conforming Amendment, July 16, 2007 (ML070000250), as supplemented by References 3 through 8.

10. Letter to Mr. J. A. Stall (Florida Power & Light Company) from Ms. Brenda L. Mozafari (NRC), St. Lucie Plant, Unit 1 - Issuance of Amendment Regarding Alternative Source Term (TAC No. MD6173), dated November 26, 2008 (ML082682060).

The following EPU LAR Attachment 5 Section 2.9.2 tables are being replaced as a result of the revised x/Q values: (pages 5 through 37 of 37)

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

" Table 2.9.2 Control Room Ventilation System Parameters

  • Table 2.9.2712 - Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions

" Table 2.9.2 LOCA Time Dependent RWT pH

-. Table 2.9.2 LOCA Time Dependent RWVT Total and Elemental Iodine Concentration

  • Table 2.9.2 LOCA Time Dependent RWT Liquid Temperature
  • Table 2.9.2 LOCA Time Dependent RW-T Elemental Iodine Fraction
  • Table 2.9.2 LOCA Time Dependent RVV-T Partition Coefficient
  • 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 MSLB Intact Steam Release Rate
  • Table 2.9.2 Locked Rotor Accident - Inputs and Assumptions
  • Table 2.9.2 CEA Ejection Accident - Inputs and Assumptions

" Table 2.9.2 FWLB - Inputs and Assumptions

" Table 2.9.2 FWLB Steam Generator Tube Leakage

" Table 2.9.2 Letdown Line Rupture - Inputs and Assumptions

L-2011-467 Attachment 1 Page 4 of 37 LAR Attachment 5 Section 2.9.3 Radiological Consequences of Gas Decay Tank Ruptures As discussed in EPU LAR Attachment 5, Section 2.9.3.2.4, Source Term and Dose Models, Assumptions and Parameters, the gas decay tank rupture is a site analysis. As such, the calculations and results presented in FPL letter L-2011-360 dated September 2, 2011 (ML11251A159), for St. Lucie Unit 1, are applicable to St. Lucie Unit 2. No new tables are provided with this submittal.

L-2011-467 Attachment 1 Page 5 of 37 Table 2.9.2-1 Summary of EPU Radiological Analysis Results Allowable Control AOR Unfiltered EAB LPZ Control Control Case Control Room Dose(1 ) Dose 2 o(2) Room Inleakage (rem TEDE) (rem TEDE) Dose( 5 )

(cfm) (rem TEDE) (rem TEDE)

LOCA 395 1.26 2.74 4.64 4.46 MSLB - Outside of 395 0.27 0.76 4.36 4.69 Containment (1.2% DNB)

MSLB - Outside of Containm e (2 395 0.30 0.81 4.45 Containment (0.29% FCM) 4.77 MSLB Contin- Inside of e (1 395 0.41 0.88 4.46

-Containment (21 % DNB) 4.96 MSLB - Inside off395 IVSB-Isd 0.64 1.23 4.45 4.92 Containment (4.5% FCM)

SGTR Pre-accident Iodine 395 0.38 0.37 4.13 2.57 Spike 395_0.38 0.37__13_2.5 Acceptance Criteria < 25() _<25 < 5(4) (4)

SGTR Concurrent Iodine 395 0.18 0.18 1.53 0.66 Spike 395 0.18 0.18_1.53 0.66 Locked Rotor (19.7% DNB) 395 0.37 0.92 4.35 2.81 FWLB16) 395 0.015 0.019 0.63 0.82 Letdown Line Rupture(6) 395 0.32 0.31 2.77 2.57

- Acceptance Criteria <2.5 (3) < 2.5 (3) < 5(4) < 5(4)

FHA - Containment 395 0.60 0.58 1.28 0.81 FHA - Fuel Handling 395 0.60 0.58 3.01 1.63 Building CEA Ejection -

Containment Release 395 0.29 0.57 2.86 2.78 (9.5 % DNB, 0.5 % FCM)

CEA Ejection - Secondary Side Release (9.5 % DNB, 395 0.31 0.73 3.12 2.87 0.5 % FCM)

Acceptance Criteria < 6.3(3) g 6.3(3) <5(4) _ (4)

NOTES:

(1) Worst 2-hour dose (2) Integrated 30-day dose (3) RG 1.183, Table 6 (4) 10 CFR 50.67 (5) AOR control room dose from CLB AST results (6) Acceptance criteria from References 1 and 2

L-2011-467 Attachment 1 Page 6 of 37 Table 2.9.2-7 Onsite Atmospheric Dispersion Factors (X/Q) for Analysis Events This table summarizes the x/Q values (sec/m 3) 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 (xIQ) 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 xlQ x/Q days x/Q Pair Stack/Plant N CR Vent intake B* Vent Vent intke intake 6.70E-04 4.58E-04 2.02E-04 1.40E-04 1. 13E-04

__ _ _ _ 5I '*!3 -*4 0°%'t*"i . yoi.Y..

.......... i6:67t } ':23750/o!

Stack/Plant Midpoint C between 3.96E-03 CR intakes N CR D RWT iNta intake 1.37E-03 S CR E RWI- intke 1.04E-03 8.49E-04 3.64E-04 2.73E-04 2.32E-04 intake

L-2011-467 Attachment 1 Page 7 of 37 Table 2.9.2-7 (continued)

Onsite Atmospheric Dispersion Factors (y/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 RWT between 1.34E-03 CR intakes FHB Closest N CR Point intake FHB Closest S5CR H Point inak intake 1.87E-03 1.36E-03 5.88E-04 4.OOE-04 3.06E-04

~ ~&~t ~ps~ S ~.54~V~ :§%Ž~43 .6 0.33%,.

FHB Closest Midpoint between 3.29E-03 CR intakes J Louver 2L-7B NCR 4.80E-03 intake S CR K Louver 2L-7A -- inak intake 4.32E-03 3.72E-03 1.64E-03 1.34E-03 1.07E-03 Z. -~~jl IUUlfO ,jc5 ,

Midpoint L Louver 2L-7A between 5.06E-03 CR intakes M# Closest ADV N CR 6.71 E-03 intake S CR N# Closest ADV inak 1.89E-03 1.53E-03 6.02E-04 4.55E-04 3.89E-04 intake Midpoint 0# Closest ADV between 3.13E-03 CR intakes

__ *~.__ __ __- _ __ __ _ __ __ _ __ __

L-2011-467 Attachment 1 Page 8 of 37 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 xIQ x/Q days x/Q Pair Closest N CR P Feedwater intake 7.29E-03 Line Point Closest Q Feedwater intake 1.95E-03 1.57E-03 6.56E-04 4.75E-04 3.99E-04 Line Point Closest Midpoint R Feedwater between 3.33E-03 Line Point CR intakes Containment N CR S Maintenance intake 1.90E-03 Hatch Containment S CR T Maintenance intake 8.28E-04 6.57E-04 2.92E-04 1.93E-04 1.76E-04 Hatch t .:,35%

,8.06%~ t>;;:,2<82 /-o *- 12;87/0" 36. 43/0 Containment Midpoint U Maintenance between 1.27E-03 Hatch CR intakes 2fW.~4 4~Q~2Yo ~ -

Steam Jet Air

-Ejector (

N CR intake 302E03 NOTES:

(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.

L-2011-467 Attachment 1 Page 9 of 37 Table 2.9.2-9 Offsite Atmospheric Dispersion Factors (x/Q) for Analysis Events Time Period EAB X/Q LPZ X/Q 3

TimePeriod (sec/m ) (sec/m3 )

0-2 hours 1.05E-04 1.01 E-04 0-8 hours 5.98E-05 5.74E-05 8-24 hours 4.52E-05 4.32E-05 1-4 days 2.46E-05 2.33E-05 4-30 days 1.02E-05 9.62E-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.

L-2011-467 Attachment 1 Page 10 of 37 Table 2.9.2-10 Control Room Ventilation System Parameters Parameter EPU Value Pre-EPU Value Control Room Volume 97,215 ft 3 Same Normal Operation Filtered Makeup Flow Rate 0 cfm Same Filtered Recirculation Flow Rate 0 cfm Same Unfiltered Makeup Flow Rate 1000 cfm Same Limiting Unfiltered Inleakage 395 cfm 435 cfm Emergency Operation Isolation Mode:

Filtered Makeup Flow Rate 0 cfm Same 1

Filtered Recirculation Flow Rate 1760 cfm( ) 2000 cfm Unfiltered Makeup Flow Rate 0 cfm Same Limiting Unfiltered Inleakage 395 cfm 435 cfm Filtered Makeup Mode:

Filtered Makeup Flow-Rate 504 cfm(1) 450 cfm 1

Filtered Recirculation Flow Rate 1256 cfm0 ) 1550 cfm Unfiltered Makeup Flow Rate 0 cfm Same Limiting Unfiltered Inleakage 395 cfm 435 cfm Filter Efficiencies:

Particulates 99% 99%

Elemental iodine 95% 99%

Organic iodine 95% 99%

(1) 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.

L-2011-467 Attachment 1 Page 11 of 37 Table 2.9.2-12 Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value 7 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 .Ci/gm DE 1-131 and 1.0 ýtCi/gm DE 1-131 and 518.9 ý.Ci/gm DE Xe-133 (Table 2.9.2-2) 100/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 Time of Recirculation 22.3 minutes 20 minutes Sump Volume (minimum) 57,683 ft3 55,739 ft3 ECCS Leakage to RAB (2 times allowed 1.08 gph 1.28 gph value)

Flashing Fraction Calculated - 5.7% Calculated - 3.4%

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)

L-2011-467 Attachment 1 Page 12 of 37 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) 57,683 ft3 58,894 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 partition Table 2.9.2-17 Different based on RWT/sump conditions factor Elemental Iodine fraction in RWT Table 2.9.2-16 Different based on RWT/sump conditions Initial RWT Liquid Inventory (minimum) 65,350 gallons 52,345 gallons Release from Sump to RWT Vapor Space Table 2.9.2-18 Different based on RWT/sump conditions Not explicitly used as model input; the vent flow Release from Rw'r Vapor Space to 0.98 cfm concept was incorporated into effective sump to Environment atmosphere iodine flow determination used in pre-EPU model.

Containment or Hydrogen Purge Release 2500 cfm for 30 sec (H2 purge) Same

L-2011-467 Attachment 1 Page 13 of 37 Table 2.9.2-12 (continued)

Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Removal Inputs:

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

Containment Elemental Iodine Natural/Wall 2.89/hour Same Deposition Containment Spray Region Volume 2,125,000 ft3 Same Containment Unsprayed Region Volume 375,000 ft3 Same Flow rate between sprayed and unsprayed 12,500 cfm Same containment volumes Spray Removal Rates:

Elemental Iodine 20/hour Same Time to reach DF of 200 3.07 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 3.06 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Particulate Iodine 6.52/hour 6.40/hour Time to reach DF of 50 2.643 hours0.00744 days <br />0.179 hours <br />0.00106 weeks <br />2.446615e-4 months <br /> 2.65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> Spray Initiation Time 80 seconds (0.0222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br />) 60 seconds (0.0167 hours0.00193 days <br />0.0464 hours <br />2.761243e-4 weeks <br />6.35435e-5 months <br />)

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 isolation 30 seconds Same Time of manual control room air intake 1.5 hrs Same opening 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 Containment or Hydrogen Purge Filtration 0% Same

L-2011-467 Attachment 1 Page 14 of 37 Table 2.9.2-12 (continued)

Loss-of-Coolant Accident (LOCA) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Transport Inputs:

Containment Release Secondary Containment release prior to Nearest Containment penetration to CR Same drawdown ventilation intake Containment Release Secondary Containment release after Plant stack Same drawdown Containment Release Secondary Containment Bypass Leakage Nearest Containment penetration to CR Same ventilation intake ECCS Leakage ECCS exhaust louver Same RVVT 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

L-2011-467 Attachment 1 Page 15 of 37 Table 2.9.2-13 LOCA Time Dependent RWT pH Time (hours) RWTpH 0.00 4.500 0.37 4.500 0.50 4.500 1.0 4.500 5.0 4.504 10.0 4.508 15.0 4.511 25.0 4.519 50.0 4.538 75.0 4.556 100.0 4.573 125.0 4.589 150.0 4.605 200.0 4.635 250.0 4.663 300.0 4.690 350.0 4.714 400.0 4.738 450.0 4.760 500.0 4.781 550.0 4.802 600.0 4.821 650.0 4.839 700.0 4.857 720.0 4.864

L-2011-467 Attachment 1 Page 16 of 37 Table 2.9.2-14 LOCA Time Dependent RWT Total and Elemental Iodine Concentration RWT Total Iodine RWT Elemental Iodine Time Concentration* Concentration (hours) [I]aq [12]aq (gm-atom/liter) (gm-atom/liter) 0 0 0.OOOE+00 0.37 0.000E+00 0.OOOE+00 0.50 1.692E-08 3.224E-12 1.0 8.276E-08 7.682E-11 5.0 6.052E-07 3.972E-09 10.0 1.248E-06 1.623E-08 15.0 1.879E-06 3.544E-08 25.0 3.107E-06 9.046E-08 50.0 5.998E-06 2.907E-07 75.0 8.655E-06 5.358E-07 100.0 1.111E-05 7.948E-07 125.0 1.337E-05 1.052E-06 150.0 1.548E-05 1.299E-06 200.0 1.926E-05 1.749E-06 250.0 2.257E-05 2.132E-06 300.0 2.549E-05 2.450E-06 350.0 2.808E-05 2.710E-06 400.0 3.040E-05 2.918E-06 450.0 3.248E-05 3.083E-06 500.0 3.436E-05 3.211E-06 550.0 3.607E-05 3.307E-06 600.0 3.764E-05 3.377E-06 650.0 3.907E-05 3.426E-06 700.0 4.038E-05 3.455E-06 720.0 4.088E-05 3.462E-06 Includes radioactive and stable iodine isotopes

L-2011-467 Attachment 1 Page 17 of 37 Table 2.9.2-15 LOCA Time Dependent RWT Liquid Temperature Time (hr) Temperature (OF) 0 104.5 0.37 104.5 0.50 104.5 1.0 104.5 5.0 104.5 10.0 104.5 15.0 104.5 25.0 104.5 50.0 104.5 75.0 104.5 100.0 104.5 125.0 104.5 150.0 104.5 200.0 104.5 250.0 104.5 300.0 104.5-350.0 104.5 400.0 104.5 450.0 104.5 500.0 104.5 550.0 104.5 600.0 104.5 650.0 104.5 700.0 104.5 720.0 104.5

L-2011-467 Attachment 1 Page 18 of 37 Table 2.9.2-16 LOCA Time Dependent RWT Elemental Iodine Fraction Time (hr) Elemental Iodine Fraction 0 0.OOOE+00 0.37 0.000E+00 0.50 3.811E-04 1.0 1.856E-03 5.0 1.313E-02 10.0 2.601E-02 15.0 3.773E-02 25.0 5.822E-02 50.0 9.694E-02 75.0 1.238E-01 100.0 1.431E-01 125.0 1.573E-01 150.0 1.679E-01 200.0 1.816E-01 250.0 1.889E-01 300.0 1.923E-01 350.0 1.930E-01 400.0 1.920E-01 450.0 1.899E-01 500.0 1.869E-01 550.0 1.834E-01 600.0 1.795E-01 650.0 1.754E-01 700.0 1.711E-01 720.0 1.694E-01

L-2011-467 Attachment 1 Page 19 of 37 Table 2.9.2-17 LOCA Time Dependent RWT Partition Coefficient Elemental Iodine Partition Time (hr) Coefficient 0 41.88 0.37 41.88 0.50 41.88 1.0 41.88 5.0 41.88 10.0 41.88 15.0 41.88 25.0 41.88 50.0 41.88 75.0 41.88 100.0 41.88 125.0 41.88 150.0 41.88 200.0 41.88 250.0 41.88 300.0 41.88 350.0 41.88 400.0 41.88 450.0 41.88 500.0 41.88 550.0 41.88 600.0 41.88 650.0 41.88 700.0 41.88 720.0 41.88

L-2011-467 Attachment 1 Page 20 of 37 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 0.37 5.485E-07 10.0 5.524E-06 25.0 3.235E-05 75.0 1.104E-04 125.0 2.026E-04 200.0 3.278E-04 300.0 4.659E-04 450.0 5.694E-04 600.0 6.223E-04

L-2011-467 Attachment 1 Page 21 of 37 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 (See Table 2.9.2-10)

Time of Control Room Ventilation Isolation 30 seconds Same 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 395 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

L-2011-467 Attachment 1 Page 22 of 37 Table 2.9.2-20 Main Steam Line Break (MSLB) - Inputs and Assumptions InputlAssumption 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 Containment Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment Initial RCS Equilibrium Activity 1.0 pCi/gm DE 1-131 and 1.0 ý.Ci/gm DE 1-131 and 518.9 pCi/gm DE Xe-1 33 (Table 2.9.2-2) 100/E-bar gross activity Initial Secondary Side Equilibrium Iodine Activity 0.1 ýiCi/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 1.00922 None Steam Generator Tube Leakage 0.25 gpm per SG (Table 2.9.2-22) 0.25 gpm per SG 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Flashing Fraction 6% 5%

Steam Generator Secondary Side Partition Coefficient Unaffected SG - 100 Same Faulted SG - None Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Containment Volume 2.50E+06 ft3 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

L-2011-467 Attachment 1 Page 23 of 37 Table 2.9.2-20 (continued)

Main Steam Line Break (MSLB) - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value 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 420,090 Ibm 423,700 Ibm RCS Mass Minimum mass used for fuel failure dose contribution to maximize SG tube leakage activity.

Minimum - 121,970.5 Ibm (per SG) Minimum - 105,000 Ibm (per SG)

Maximum - 219,009 Ibm (per SG) Maximum - 260,000 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 resulting from primary-to-secondary leakage.

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 (See Table 2.9.2-10)

Time of Control Room Ventilation Isolation 30 seconds Same 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 395 cfm 435 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 Aerosols -0.1 hr"1 Same Containment Natural Deposition Coefficients Elemental Iodine - 2.89 hr-1 Same Organic Iodine - None Same

L-2011-467 Attachment 1 Page 24 of 37 Table 2.9.2-21 MSLB Intact Steam Release Rate Time Intact SG Steam Rt Release (hours)*Rate (hours)* (Ibm /min) 0.0 9087.1 0.5 5124.4 2.0 2690.3 8.0 2611.7 9.0 2478.3 10.0 2393.3 11.0 2301.7 12.0 2213.3 12.4 0.0

  • Flow rates are applied until the next time point.

L-2011-467 Attachment 1 Page 25 of 37 Table 2.9.2-22 MSLB Steam Generator Tube Leakage Time Intact SG Faulted SG (hours)* Tube Leakage Tube Leakage (Ibm /min) (Ibm /min) 0 1.58 2.00 0.50 1.67 2.00 1.00 1.75 2.00 1.50 1.83 2.00 2.00 1.86 2.00 4.00 1.90 2.00 6.00 1.94 2.00 9.00 1.97 2.00 11.00 2.00 2.00 12.40 0.00 0.00 Flow rates are applied until the next time point.

L-2011-467 Attachment 1 Page 26 of 37 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 pCi/gm DE 1-131 and 1.0 p.Ci/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 ptCi/gm DE 1-131 Maximum Pre-Accident Spike Iodine Concentration 60 pCi/gm DE 1-131 Same Maximum Equilibrium Iodine Concentration 1.0 pCi/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 Table 2.9.2-24 Different based on different thermodynamic conditions and isolation time Prior to Reactor Trip - 15.5% Prior to Reactor Trip - 17%

Break Flow Flashing Fraction Following Reactor Trip - 7.5% Following Reactor Trip - 5%

Time to Terminate Break Flow 45 minutes 30 minutes Steam Generator Tube Leakage Rate 0.25 gpm pei" SG 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 Flashed tube flow - 100 Same Steam Generator Secondary Side Partition Coefficients Non-flashed tube flow - 100 Same Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS Mass Pre-accident Iodine Spike: 420,090 Ibm Pre-accident Iodine spike - 423,700 Ibm Concurrent Iodine Spike: 386,354 Ibm Concurrent Iodine spike - 452,000 Ibm

L-2011-467 Attachment 1 Page 27 of 37 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 -121,970.5 Ibm (per SG) Minimum - 105,000 Ibm (per SG)

Maximum - 219,009 Ibm (per SG) Maximum - 260,000 Ibm (per SG)

Maximum mass used for faulted SG to maximize secondary side dose contribution.

Minimum mass used for all SG's for primary to secondary leakage nuclide transport, to maximize steam release nuclide concentration 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 (See Table 2.9.2-10)

Time of Control Room Ventilation System Isolation 314 seconds (Hot Leg Break Rx trip + 30 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 395 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

L-2011-467 Attachment 1 Page 28 of 37 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 19.7% 13.7%

High Burnup Fuel Adjustment Factor 1.00922 None Core Fission Product Inventory Table 2.9.2-4 Different based on power, burnup and enrichment 1.0 ýtCi/gm DE 1-131 and 1.0 p.Ci/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 ýiCi/gm DE Xe-133 1O0/E-bar gross activity (Table 2.9.2-2)

Initial Secondary Side Equilibrium Iodine Activity 0.1 p.Ci/gm DE 1-131 (Table 2.9.2-3) 0.1 jACi/gm DE 1-131 Release Fraction from Breached Fuel RG 1.183, Section 3.2 Same Steam Generator Tube Leakage 0.5 gpm (Table 2.9.2-30) 0.5 gpm 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 6% 5%

Steam Generator Secondary Side Partition Flashed tube flow - none Same Coefficient Non-flashed tube flow - 100 Same Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Minimum - 420,090 Ibm Minimum - 423,700 Ibm RCS Mass Minimum mass used for fuel failure dose contribution to maximize SG tube leakage activity.

L-2011-467 Attachment 1 Page 29 of 37 Table 2.9.2-28 (continued)

Locked Rotor Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Minimum - 121,970.5 Ibm (per SG) Minimum - 105,000 Ibm (per SG)

Maximum - 219,009 Ibm (per SG) Maximum - 260,000 Ibm (per SG)

Maximum mass not used since this event has no SG Secondary Side Mass faulted SG.

Minimum mass used for all SG's to maximize steam release nuclide concentration resulting from primary-to-secondary leakage.

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 (See Table 2.9.2-10)

Time of Control Room Ventilation Isolation 30 seconds Same 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 395 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

L-2011-467 Attachment 1 Page 30 of 37 Table 2.9.2-31 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 piCi/gm DE 1-131 and 1.0 iiCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 ýtCi/gm DE Xe-1 33 100/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 pCi/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 1.00922 None 2f assemblies None High Burnup Fuel Adjustment Factor 2 fuel None Steam Generator Tube Leakage 0.5 gpm (Table 2.9.2-33) 0.5 gpm Secondary Side Mass Releases to Environment Table 2.9.2-32 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 6% 5%

Flashed tube flow - none Same Flashed tube flow - 100 Same Steam Generator Secondary Side Partition Coefficient Non-flashed tube flow - 100 Same Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

L-2011-467 Attachment 1 Page 31 of 37 Table 2.9.2-31 (continued)

CEA Ejection Accident - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Minimum - 420;090 Ibm Minimum - 423,700 Ibm RCS Mass Minimum mass used for fuel failure dose contribution to maximum SG tube leakage activity.

Minimum - 121,970.5 Ibm (per SG) Minimum - 105,000 Ibm (per SG)

Maximum - 219,009 Ibm (per SG) Maximum - 260,000 Ibm (per SG)

Maximum mass not used since this event has no SG Secondary Side Mass faulted SG.

Minimum mass used for all SG's to maximize steam release nuclide concentration resulting from primary-to-secondary leakage.

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 (See Table 2.9.2-10)

Time of Control Room Ventilation System 30 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 395 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

L-2011-467 Attachment 1 Page 32 of 37 Table 2.9.2-31 (continued)

CF=A E~i~etinn Ar~ridInt - Innift* *anr A.*iimnfinn_*

Input/Assumption EPU Value Pre-EPU Value 3

Containment Volume 2.500E+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 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 hr' Same Organic Iodine - None Same

L-2011-467 Attachment 1 Page 33 of 37 Table 2.9.2-34 FWLB - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (3020 + 0.3%) 2754 MWt (2700 + 2%)

1.0 1.Ci/gm DE 1-131 and 1.0 piCi/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 pCi/gm DE 1-131 Steam Generator Tube Leakage 0.25 gpm per SG (Table 2.9.2-36) 0.25 gpm per SG Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Steam Release from the Intact SG Table 2.9.2-35 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Flashing Fraction 6% 5%

Steam Generator Secondary Side Partition Coefficient Unaffected Faulted SG SG - 100

- None Same Minimum - 121,970.5 Ibm Minimum - 105,000 Ibm Maximum- 219,009 Ibm Maximum - 260,000 Ibm 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 resulting from primary-to-secondary leakage..

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 (See Table 2.9.2-10)

Time of Control Room Ventilation Isolation 30 seconds Same 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 395 cfm 500 cfm

L-2011-467 Attachment 1 Page 34 of 37 Table 2.9.2-34 (continued)

FWLB - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value 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

L-2011-467 Attachment 1 Page 35 of 37 Table 2.9.2-36 FWLB Steam Generator Tube Leakage Time Intact SG Faulted SG Tube Leakage Tube Leakage (hours)* (Ibm /min) (Ibm /min) 0 1.58 2.00 0.50 1.67 2.00 1.00 1.75 2.00 1.50 1.83 2.00 2.00 1.86 2.00 4.00 1.90 2.00 6.00 1.94 2.00 9.00 1.97 2.00 11.00 2.00 2.00 12.40 0.00 0.00

  • Flow rates are applied until the next time point.

L-2011-467 Attachment 1 Page 36 of 37 Table 2.9.2-37 Letdown Line Rupture - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value Core Power Level 3030 MWt (-3020 + 0.3%) 2754 MWt (2700 + 2%)

1.0 [Ci/gm DE 1-131 and 1.0 ýtCi/gm DE 1-131 and Initial RCS Equilibrium Activity 518.9 jCi/gm DE Xe-1 33 100/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 PLCi/gm DE 1-131 Iodine Spike Appearance Rate 500 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 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Flashing Fraction 6% 5%

Steam Generator Tube Leakage Rate 0.5 gpm (Table 2.9.2-41) 0.5 gpm Time to 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 /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Secondary Side Mass Releases to Environment Table 2.9.2-40 Different based on different thermodynamic conditions Broken Line Flashing Fraction 25.9% Same Time to Terminate Break Flow 1800 seconds 1920 seconds Broken Line Flow Rate Table 2.9.2-42 Different based on different thermodynamic conditions RCS Mass 386,354 Ibm 452,000 Ibm SG Secondary Side Mass Minimum - 121,970.5 Ibm (per SG) Minimum - 210,000 Ibm (Total)

Maximum - 219,009 Ibm (per SG)

Maximum mass not used since this event has no faulted SG Minimum mass used for all SG's to maximize steam release nuclide concentration resulting from primary-to-secondary leakage. I

L-2011-467 Attachment 1 Page 37 of 37 Table 2.9.2-37 (continued)

Letdown Line Rupture - Inputs and Assumptions Input/Assumption EPU Value Pre-EPU Value 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 (See Table 2.9.2-10)

Time of Control Room Ventilation System Isolation 30 seconds Same 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 395 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

L-2011-467 Attachment 2 Page 1 of 2 Technical Specifications Section 3.11.2.6 Radioactive Effluents - Gas Storage Tanks Revision To Proposed Change Submitted By FPL Letter L-2011-021 Regarding Extended Power Uprate License Amendment Request Description of the Change EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specifications Changes, Item 25, 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" to "less than or equal to 202,500 curies noble gases."

By email from the NRC Project Manager dated August 31, 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 twelve questions. The response to eleven of the twelve AADB RAIs was submitted to the NRC by FPL letter L-2011-404, dated October 5, 2011 (Accession No. ML11290A065). FPL letter L-2011-404 referenced FPL letter L-2011-314, dated August 12, 2011 (Accession No. ML11234A283), which 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 change proposed by the original EPU LAR.

" 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-133). 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 NUREG-0800, Standard Review Plan Chapter 11, Radioactive Waste Management.

L-2011-467 Attachment 2 Page 2 of 2 FPL letter L-2011-314, dated August 12, 2011 (ML11234A283), submitted revised atmospheric dispersion factors (X/Q's) for the St. Lucie plant site based on updated site meteorological data provided on a compact disc (CD) that was enclosed 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 is 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 presents a reduction in the radioactivity in the tanks. As such, the conclusions of EPU LAR Attachment 1, Section 5.2, No Significant Hazards Consideration, Item G. 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 conservative in that it reduces the radioactivity in the gas storage tanks.

This change presents a reduction in the proposed TS radioactivity limit change provided in the EPU LAR, Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specifications Changes, Item 25, TS 3/4.11.2.6, RADIOACTIVE EFFLUENTS

- GAS STORAGE TANKS. 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.

L-2011-467 Attachment 3 ATTACHMENT 3 Marked Up and Clean Pages for Technical Specification 3/4.11.2.6 Revision To Proposed Change Submitted By FPL Letter L-2011-021 Regarding Extended Power Uprate License Amendment Request 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 2-8, curies noble gases (considered as Xe-1 33).

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 49 -

518.9 pCi/gram DOSE EQUIVALENT XE-1 33 ST. LUCIE - UNIT 2 3/4 11-15 Amendment No.43

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-133).

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 2 3/4 11-15 Amendment No.4-

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