ML072570202

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Calculation PM-1058, Rev. 0, Re-analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms.
ML072570202
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/28/2003
From: Rothstein H
Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
CC-AA-309-1001, Rev 0 PM-1058, Rev 0
Download: ML072570202 (23)
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004- PM 1058 Rev 0 MSLB CC-AA-309-1001 Exekrn. ATTACHMENT 1 Design Analysis Cover Sheet Revision 0 Nuclear I Last Page No.-%6, Analysis No. PM-1058 Revision 0 ý.

BJ-ECIECR No. PB 02-00838 Revision

Title:

Reanalysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms Station(s) Peach Bottom Atomic Power Component's)

StaionComonetss Station Unit No.: 2 and 3 NIA Discipline SEAQ Description Code/ MSL8 Keyword Safety Class S System Code 912 Structure N/A CONTROLLED DOCUMENT REFERENCES Document No. FromiTo Document No. From/To Calc. PM-740, Rev. 1A From UFASR; Section 14.6.5, Rev 18 From/To Cate. PM-738, Rev A From Is this Design Analysis Safeguards? Yes E] No 0 Does this Design Analysis Contain Unverified Assumptions? Yes E] No N ATI/AR#

Is a Supplemental Review Required? Yes [:] No ] If yes, complete Attachment 3 Preparer. Harold Rothstein 3/20/03 Print Name Date Reviewer Paul Reichert 3/20/03 Print Name Sign Name Date Method of Review [ Detailed Review [] Alternate Calculations f* Testing Review Notes:

Approver Harold Rothsteln /J/ i ....... 3/20/03 trw, E.tmflaAneisaOI~

Exelon Reiewe F_____

Approver ___eS3,40-Print Name Sign NeDat Description of Revision (list affected pages for partials):.

THIS DESIGN ANALYSIS SUPERCEDES: N/A

CAI.CUILATION NO. PM-1058 [ REV. NO. 0 1PAGE NO. 2 of 15 CALCULATION TABLE OF CONTENTS 1.0 PURPOSE/OBJECTIVE .................................................................... ............ ...... 3 2.0 M ETHODOLOGY AND ACCEPTANCE CRITERIA ............................................................... 3 2.1 General Description ....................................................... .............................................................. 3 2.2 Source Term M odel ..................................................................................................... ................ 3 2.3 Release M odel .................................................................................................................................. 4 2.4 Dispersion M odel ............................................................................................................................ 4 2.4.1 EAB and I.PZ .......................................................................................................................... 4 2.4.2 Control Room .......................................................................................................................... 4 2.5 Dose M odel ...................................................................................................................................... 5 2.5.1 EAB and LPZ ........................................................................................................................... 5 2.5.2 Control Room ................................................................................................................ .)

2.6 Acceptance Criteria ......................................................................................................................... 5 3.0 ASSUM PTIONS ............................................................................................................................. 7 3.1 Activity Release and Transport M odels ...................................................................................... 7 3.2 Control Room M odel ........................................................................................................................ 7 3.3 Site Boundary M odel ......................................................................................................................... 7 4.0 DESIGN INPUT ....................................................................................................... ....................... 8 4.1 M ass Release Data ............................................................................................................................. 8 422 Iodine Distribution ............................................................................................................................ 8 4.3 Noble Gas Distribution ............................................................................ ......................................... 8 4.4 Control Room Data ........................................................................................................................... 9 4.5 EAB and LPZ Data ........................................................................................................................... 9

5.0 REFERENCES

...................................... .................... 10 6.0 CALCULATIONS ....... ............................ . .... ........ . ............................ I 1 6.I Cloud Volumes, Masses, and Control Room Intake Transit Times .......................... II 6.2 Dispersion for Offsite Dose Assessment ............................................ 12 6.3 Release Isotopics and Quantification ...................................................................................... 12 6.4 Dose Assessment ............................................................................................................................ 13 7.0 SUM M ARY AND CONCLUSIONS 14 4........................................................

8.0 Owners Acceptance Review Checklist for External Design Analysis ....................................... 15 Attachments:

A. Spreadsheet performing MSLB Dose Assessment [pages A l-A6]

B. Computer Disclosure Sheet [pages BI -B1I

I CALCULATION NO. PM-1058 IREV.NO.

( PAGE NO. 3 of 15 1.0 PURPOSEIOBJECTIVE The purpose of this calculation is to determine the Control Room (CR), Exclusion Area Boundary (EAB), and Low Population Zone (LPZ) doses following a Main Steam Line Break (MSLB) Accident based on the assumptions on the break and resulting radiological releases to the Turbine Building as discussed in UFSAR [Reference 11 Sections 14.6.5 and 14.9.2.3, and the additional assumptions for use of Alternative Source Terms (AST) contained in Appendix D of Regulatory Guide (R. G.) 1.183 [Reference 6].

Inhalation Committed Effective Dose Equivalent (CEDE) Dose Conversion Factors (DCFs) from Federal Guidance Report No. 11 [Ref. 3] are used for calculation of normalized lodine-131 Dose Equivalent activity in this calculation.

As per UFSAR Section 14.6.5, this event involves the postulation that one main steam line instantaneously and circumferentially breaks outside the secondary containment at a location downstream of the outermost isolation valve. Closure of the Main Steam Isolation Valves (MSIVs) terminates the mass loss when the full closure is reached. No operator actions are assumed to be taken during the accident, so the normal air intake into the Control Room continues unfiltered during the duration of the event.

The mass of coolant released during the MSLB was obtained from reference 1, which bases analysis on 10.5-second closure of main steam isolation valve. Specifically, as per UFSAR Section 14.9.1.5 and the Reference 2 MSLB Calculation for Power Rerate, a release of 165,120 pounds of reactor water and 25,800 pounds of steam is used.

2.0 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 GeneralDescription The radiological consequences resulting from a design basis MSLB accident to a person at the EAB; to a person at the LPZ; and to an operator in the Control Room following an MSLB accident were performed using a Microsoft EXCEL spreadsheet, provided as Attachment A.

2.2 Source Term Model No fuel damage is expected to result from a MSLB. Therefore, the activity available for release from the break is that present in the reactor coolant and steam lines prior to the break, with two cases analyzed, corresponding to the Reactor Coolant System Specific Activity limits in Technical Specification 3.4.6 and its Basis. Case 1 is for continued full power operation with a maximum equilibrium coolant concentration of 0.2 uCilgm dose equivalent 1-131. Case 2 is for a maximum coolant concentration of 4.0 uCi/gm dose equivalent 1-131, based on a pre-accident iodine spike caused by power changes. In determining 1-131 equivalence, inhalation CEDE DCFs from Ref. 3 are used. This accident source term basis meets the guidance in R.G. 1.183 for analysis of this event

I CALCULATION NO. PM-1058 I KEV..'O. 0 I PAGE NO. 4 of IS 2.3 Release Model The release model is identical to that historically used. The previously determined mass of reactor coolant release and mass of steam release, before the break is isolated by MSIV closure, are used. Reactor coolant radioactivity is based on the above reactor coolant concentrations.

Releases are assumed to be instantaneous and no credit is taken for dilution in turbine building air.

2.4 DispersionModel Offsite and Onsite X/Q determinations are handled differently, but conservatively in both cases.

2.4.1 EAB and LPZ EAB and LPZ XOQ's are determined using the original methodology in R.G. 1.5 [Ref. 51.

Specifically:

X, 0.0133 Q ryau where a, = horizontal standard deviation of the plume (meters) u = wind velocity (meters/second)

Horizontal standard deviations are taken from the PAVAN outputs for the EAB and LPZ included in Calculation PM-i055 [Ref. 91. Per Regulatory Guide 1.5, F stability and a 1 meter/sec wind speed are used.

2.4.2 Control Room For control room dose calculations, the plume was modeled as a hemispherical volume, the dimensions of which are determined based on the initial steam blowdown and that portion of the liquid reactor coolant release that flashed to steam.

Activity release is conservatively assumed to effectively occur at the Control Room intake elevation and, again conservatively, no credit is taken for plume buoyancy. A conservative translation time of the plume over the intake is assumed.

The activity of the cloud is based on the total mass of water released from the break, not just the portion that flashes to steam. This assumption is conservative because it considers the maximum release of fission products.

I CALCULATION NO. PM-I058 CREV. NO. 0 ýý AG EN\O. 5ýo fl 5 ... _

2.5 Dose Model Dose models for both onsite and offsite are simplified and meet R,G. 1.183 [Ref. 6]

requirements, providing results in units of Total Effective Dose Equivalent (TEDE). Dose conversion factors are based on Federal Guidance Reports 11 and 12 fRefs 3 &4).

2.5.1 EAB and LPZ Doses at the EAB and LPZ for the MSLB are based on the following formulas:

Dose,,, (rem) = Release (Curies) * - (sec/mr')

  • Breathing Rate (m'Isec)
  • Inhalation DCF (remr 05FiCi inhaled)

Q and Dose rne (rem) = Release (Curies) * - (sec/mrn)

  • Submersion DCF (rem,,, - m'/ Ci - sec)

Q and finally, DoseEDE (rem) = DoseCEM (rem) + DoseME (rem) 2.5.2 Control Room CR operator doses are determined somewhat differently, because steam cloud concentrations are used, rather than X/Q times a curie release rate. No CR filter credit is taken and, therefore, for inhalation, a dose for a location outside of the CR can be and is used. For cloud submersion, a geometry factor is used to credit the reduced plume size seen in the control room. This is a conservative implementation of RG 1.183 guidance. The formulas used are:

DosecErE (rem) = Plume Concentration (Ci/m 3 )

  • Transit Duration (see)
  • Breathing Rate (m 3/sce)
  • Inhalation DCF (rcmcen5 /Ci inhaled) and Dose EDF.

(rem) = Plume Concentration (Ci/m')

  • Transit Duration (see)
  • Submersion DCF (rem.. - m'/Ci -see) and finally, Dose"E (rem) = DosecEDE (rem) + DoseED 0 (rCm) 2.6 Acceptance Criteria Dose acceptance criteria are per 10CFR50.67 [Ref, 7] and R.G. 1.183 [Ref. 6] guidance.

Table 1 lists the regulatory limits for accidental dose to 1) a control room operator, 2) a person at the EAB, and 3) a person at the LPZ boundary.

CALCULATION NO. PM-1058 . REV. NO. 0 1 PAGE NO. 6 of 15 Table 1. Regulatory Dose Limits (Rem TEDE) per Refs. 7 and 6.

1-131 Dose CR EAB LPZ.

Equivalent (30 days) (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) (30 days Normal Equilibrium 5 2.5 2.5 Iodine Spike 5 25 25

CALCULATION NO. PM.1058 REV. NO. 0 PAGE NO. 7 of 15 3.0 ASSUMPTIONS 3.1 Activity Release and TransportModels

" Iodine activity distribution in the coolant is taken from UFSAR [Ref. 1] Section 14.6.5.2.1, assumption 2.

" Total release quantities from the break are taken from UFSAR [Ref. 1] Section 14.9.1.5, with Section 14.6.5 break flow and MSIV closure characteristics, including the conservativelO-second valve closure time in comparison to the less than or equal to 5 seconds isolation time limit of Surveillance Requirement 3.6.1.3.9 [Ref. 81.

  • Release from the break to the environment is assumed instantaneous. No holdup in the Turbine Building or dilution by mixing with Turbine Building air volume is credited.
  • The steam cloud Is assumed to consist of the initial steam blowdown and that portion of the liquid reactor coolant release that flashed to steam.

a The activity of the cloud is based on the total mass of water released from the break, not just the portion that flashes to steam. This assumption is conservative because it considers the maximum release of fission products.

9 The traction of liquid water contained in steam, which carries activity into the cloud, is assumed to be 2%, a conservatively high value consistent with current Boiling Water Reactor practice.

0 A conservatively high flashing fraction of liquid water released of 40% is assumed.

However, all activity in the water is assumed to be released.

0 For offsite dose calculations, the release Is treated per Regulatory Guide 1.5 [Ref. 51.

Buoyancy effect of the cloud was conservatively ignored.

  • For the control room dose calculations,

> the plume is modeled as a hemispherical volume. This is consistent with the assumption of no Turbine Building credit. It is also reasonable for the more likely release paths through multiple large openings above the Turbine Building operating deck.

  • > dispersion of the activity of the plume is conservatively ignored.

)' The cloud is assumed to be carried away by a wind of speed 1 m/s. Credit is not taken for decay.

3.2 Control Room Model

  • Inhalation doses are determined based on concentrations at the intake, and exposures for the duration of plume traverse.

, Extemal exposure doses are determined based on concentrations at the intake, exposures for the duration of plume traverse, and a geometry factor credit based on the control room envelope volume of 176,000 cubic feet.

3.3 Site Boundary Model This model is as discussed in Subsection 2.5 above.

CALCULATION NO. PM-1058 REV. NO. 0 PAGE NO. 8 of 15 4.0 DESIGN INPUT 4.1 Mass Release Data

  • The mass of steam released is 25,800 lb. [Section 14.9.1.5 of Ref. 1 and Ref. 2]
  • The mass of liquid water released is 165.120 lb. [Section 14.9.1.5 of Ref. 1 and Ref.

2]

4.2 Iodine Distribution The PBAPS UFSAR [Ref. 1] Section 14.6.5.2.1. provides the following design basis concentrations of significant radionuclides contained in the coolant:

Iodine Isotope a

Activity (uCilcc) 1-131 0.17 1-132 1.02 1-133 1.04 1-134 1.47 1-135 1.30 4.3 Noble Gas Distribution The MSLB Power Rerate Calculation [Ref. 2] provides the following Noble Gas concentrations for potentially significant radionuclides contained in the coolant:

--sotiopeas l Noble a Concentration Kr-83M 1.92E-03 Kr-85M 3.44E-03

"- Kr-85 1.13E-05 Kr-87 1.1 3E-02 Kr-88 I 1.13E-02 Kr-89M 7.33E-02 Xe-131M 8.46E-06 Xe-133M 1.63E-04 Xe-133 4.62E-03 Xe-135M 1.47E-02 Xe-135 1.24E-02 I Xe- 137 8.46E-02 Xe-138 5.02E-02

I CALCULATIONNO. PM-1058 REV.NO. 0 PAGE NO. 9 of 15 4.4 Control Room Data

& Control Room Envelope = 176,000 ft. [Ref. 10O

  1. No Emergency Filtration Credit taken.

4.5 EAB and LPZ Data

" EAB Distance from Release, m 915 (Ref. 1]

" LPZ Distance from Release, m 7300 [Ref. 1]

I CALCULATION NO. PM-M5 I REV. NO. 0 PAGENO. 10 of 15

5.0 REFERENCES

1. PBAPS UFSAR, Rev. 18.
2. PBAPS Calculation PM-740, Rev. 1A, "Power Rerate MSLB Dose Verification and Rerated Doses".
3. Federal Guidance Report No. 11 "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion".

1988.

4. Federal Guidance Report No. 12, "External Exposure to Radionuclides in Air, Water, and Soil", 1993.
5. Regulatory Guides 1.5, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accidents for Boiling Water Reactors," 3/10/71.
6. Regulatory Guide 1.183, "Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors", July 2000.
7. 10 CFR Part 50.67, "Accident Source Term".
8. PBAPS Technical Specification 3.6.1.3, "Primary Containment Isolation Valves",

Surveillance Requirement 3.6.1.3.9.

9. Design Analysis No. PM-1055, Rev. 0 "Calculation of Alternative Source Terms Onsite and Offsite X/Q Values".
10. PBAPS Calculation PM-738, Rev. A, "Power Rerate Control Rod Drop Dose Verification and Rerated Doses".

ICALCULATION NO. PM-1058 [EV. NO. 0 PAGE NO.I of 15 I 6.0 CALCULATIONS No or minimal fuel damage is expected for the limiting MSLB. As discussed in section 2, two iodine concentrations will be used (0.2 pCi/g and 4.0 pCVg) [per Refs. 6 and 8] when determining the consequences of the main steam line break. All of the radioactivity in the released coolant is assumed to be released to the atmosphere instantaneously as a ground-level release. No credit is taken for plateout, holdup, or dilution within facility buildings.

The spreadsheets in Attachment A perform this analysis using data and formulations discussed above. The following summarizes parameters and their treatment in the spreadsheet.

6.1 Cloud Volumes, Masses, and Control Room Intake Transit Times As stated in Section 3.1, the cloud is assumed to consist of the Initial steam blowdown and that portion of the liquid reactor coolant release that flashes to steam. The flashing fraction (FF) is derived as follows:

FF x (steam enthalpy at 212 F) + (1-FF) x (liquid enthalpy at 212 F) =

(liquid enthalpy at temperature of steam at reactor vessel outlet)

A 548 F vessel outlet temperature is used, with liquid enthalpy of 546.9 BTU/lb.

At 212 F, a steam enthalpy of 1150.5 BTU/Ib and a liquid enthalpy of 180.17 BTU/lb are used (these enthalpies are taken from the ASME Steam Tables).

Substituting, FF =(546.9 - 180.17) / [(1150.5 - 180.17)] = .378 For conservatism, a value of .40 or 40% is used below.

Mass of water carrying activity into the cloud is calculated as the sum of the fraction of water in.

the steam and the liquid blowdown.

The mass steam released = 25,800 lb The mass liquid water released = 165,120 lb Flashing fraction for calculating cloud volume = 40%

The mass water contained in steam released = (25,800 Ib)

  • 2%

= 516 lb The mass of water carrying activity into the cloud = 516 + 165,120 lb

= 165,636 lb

= (165.636 lb)(453.59 glib)

= 7.5131 E7 g The mass of steam in the cloud (25,800 - 516) + 40%*165,120 lb

=25.284 + 66,048

= 91,332 lb

C-ALCU-kLATION NO. PM-1058 1REV. NO. 0 !PAGENO.

12 of 15 The release is assumed to be a hemisphere with a uniform concentration. The cloud dimensions (based on 91,332 lb of steam at 14.7 psi and 212 OF, vg = 26.799 ft3 Ilb) are calculated as follows:

Volume = (91,332 lb)(26.799 ft/b)

= 2,447,600 fft

= (2,447,600 3 f 3)i(35.3 ftl/m3)

= 69,337 m The volume of a hemisphere Is n d3 /12. Thus, the diameter of the hemispherical cloud is 64.2 meters.

The period of time required for the cloud to pass over the control room intake, assuming a wind speed of 1 m/s is 64.2 s (=(64.2 m)/(1 m/s)).

Therefore, at a wind speed of 1 m/s, the base of the hemispherical cloud will pass over the control room intake in 64.2 seconds.

6.2 Dispersion for Offsite Dose Assessment As discussed in Section 2.4.2 the following formulation was used for Offsite Dose X/Q assessment, with F Pasquill Stability and a 1 rn/sec wind speed.

= 0.0133 Q eyu where a = horizontal standard deviation of the plume (meters) u = wind velocity(meters/second)

As calculated in the PAVAN run in Reference 9, at the 1040 meter EAB distance oy is 38.3, and at the 7300 meter LPZ distance a. is 222.6. The resulting EAB and LPZ XIQs are 3.47E-04 and 5.97E-05 sec/m3 , respectively.

6.3 Release Isotopics and Quantification The iodine isotopic distribution given in Section 4.2 is used. The concentrations of this mix are adjusted to 1-131 equivalence, using the inhalation Committed Effective Dose Equivalent (CEDE) Dose Conversion Factors (DCFs) from Federal Guidance Report No. 11 I[Ref. 31. This is a more conservative set of DCF assumptions for Control Room and off-site dose calculation than the use of ICRP 2 DCFs. It is also more conservative for these calculations than use of R.

G. 1.109 or Federal Guidance Report No. 12 [Ref. 4) DCFs.

This 1-131 equivalent mix is adjusted to the activity yielding the two design basis MSLB accident reactor coolant activities of 0.2 p.Ci/cc and 4.0 gCi/cc. The released activities are these concentrations times the 7.51E+07 grams of water carrying activity released, with the assumption that TS activities are based on laboratory temperature and pressure conditions.

CALCULATIONNO. PM-1058 REV. NO. 0 PAGE NO. 13 of I5 For the Noble Gases, the isotopic distribution given in Section 4.3 is used. The released activities are these concentrations times the 25,800 lb mass of steam released, converted to

1. 17E+07 grams using the 453.59 g/lib conversion factor.

6.4 Dose Assessment Doses at the EAB and LPZ distances, and in the Control Room are calculated in Attachment A using the formulas in Section 2.5. Concentrations at the receptor locations are that in the steam plume for the Control Room or based on the release times the applicable X/O for the EAB and LPZ.

Doses are calculated for inhalation (rem CEDE) and plume submersion (rem EDE) and totaled to yield rem TEDE. The breathing rate of 3.47E-04 m3/sec is per RG 1.183 guidance without the round-off.

The resulting calculated doses are in the spreadsheet and in the Summary and Conclusions Section below.

. CALCULATION N 0. PM-1058 I REV, NO. 00 I PAGE NO. 14 of 15 I I REV. NO.

7.0

SUMMARY

AND CONCLUSIONS

  • Accidental doses from a design basis MSLB were calculated for the control room operator, a person at EAB, and a person at LPZ. The results are summarized in the Table below. The doses at the Control Room, EAB, and LPZ resulting from a postulated design basis MSLB do not exceed, and are a small fraction of, the regulatory limits.

Location Case I Case 2 (normal equilibrium (Iodine spike limit of 0.2 LCi) limit of 4.0 4Ci)

Dose (rem TEDE) ---- i Dose (rem TEDE) 4 LIMITS CR: 5.0; EAB&LPZ: 2.5 CR: 5.0; EAB&LPZ: 25

~1 7.99E-02 -- t -

1.60E+00 LPZ 1.38E-02 2.75E-01 CR 1.62E-01 3.23 E+00

[_CALCULATION NO. PM-1058 REV. NO. 0 1 PAGE NO. 15 of 15 8.0 Owners Acceptance Review Checklist for External Design Analysis Page I of 1 DESIGN ANALYSIS NO. PM-1058 REV: 0 Yes No N/A

1. Do assumptions have sufficient rationale? * [

2, Are assumptions compatible with the way the plant is operated and with the j 0 licensing basis?

3. Do the design inputs have sufficient rationale? 0 0
4. Are design inputs correct and reasonable? 0 *
5. Are design inputs compatible with the way the plant is operated and with the 0 licensing basis?
6. Are Engineering Judgments cleady documented and justified? 0 0
7. Are Engineering Judgments compatible with the way the plant is operated 0 0 and with the licensing basis?
8. Do the results and conclusions satisfy the purpose and objective of the design 0 analysis?
9. Are the results and conclusions compatible with the way the plant is operated 0 0 and with the licensing basis?
10. Does the design analysis include the applicable design basis 0 0 documentation?
11. Have any limitations on the use of the results been identified and 0 transmitted to the appropriate organizations?
12. Are there any unverified assumptions? o'0 0
13. Do all unverified assumptions have a tracking and closure mechanism in F-0 0 place?

EXELON REVIEWER: -DAE

Calculation PM-1058, Rev. 0 Attachmem' A Page Al of A6 AI B J Cv D EA,. F ce G H PagK PBAPS MSLB Dose Spreadsheet Case 1: JReactor Coolant at maximum value (DE 1-131 of 0.2 uCicc) permitted for 2 . . .continued full power operation 3 69,337 _Volume of cloud__ (cubic meters) .. Case2: Reactor Coolant at maximum value permitted (DE 1-131 of 4.0 uCi/cc) 7.51E4-071 Mass of water in reactor coolant release (grams) ____ corresponding to an assumed pre-accident spike 6

5 1.17E+07 Mass of steam release (grams) [ . _. " _

1 reactor coolant density..............

when activity is measured (grams/cc) .............. . ....

7 64.2 seconds for cloud to pass over CR Intake for wind speed of I m/second M8 176000 Volume Of Control Room Envelope (cubic feet) . .

9 1_.0 Halogens _ Case 1 Case 2 11 Activity Release Reteas Distribution i Normalized Case I Case 2 Case 1 Case 2 Cloud Cloud 12 Isotope (UFSAR 1FGR--1-131 DE Normalized Normlized Activity Activity Concentration Concentration .....

Sect. 14.6.5)1 D6F1 Activity Act*iviy Activity Release Release _ _,

14 15 uCi/cc Rem/Ci uCl/cc uCUcc uCi/cc Ci Ci Cu/rn3 Ci/r 3 1.131 1 0.17 3.29E+04 1.70E-01 8.07E-02 1.61E+00 6.07E+00 1.21E+02 8.75E-05 1.75E-03 17 381E+02'

.i.02 1.18E-02 5.61E-03 1.12E-01 3.64E+01 7.28E+02 5.25E-04 1.05E-02 ......

18 1.04 S1-133 ,5-.85E -03 ": 1.85E-01 8.78E-02 1.76E+00 3.71E+01 7.42E402 5.35E-04 1.07E-02 _ ....

19 1-134 1.47 1131 0 5.85E-03 2.78E-03 5,56E-02 5.25E+01 1.05E+03 7.57E-04 1.51E-02 20 1-135 1 .3 1.23 E +03 4 .8 6 E -0 2 4 .2 1E -01 2 .3 1 .E-0 2 .OOE -0 1 2 4 6 2 E *- 1

4 4 .00 E +0 0 !

4.l.

h--01 -16E0 I.

__2E_2_6E_0_134_0 22 . r................l-sp iked" apmeu 21 Noble Gases 23 _ .

24 I Calc. Ca se 1 Ca se 22_ __......_ _

25 _PM-740-A - Release Release ...........

-fTable3 Case l Case2 Cloud Cloud isotope N *e Aciovity- Activity Concentratiort Concentration ..... _ _

___-.~Activity Release Release-]-. . -- _____.

u*./--

..........- C Ci CiUm3 rCim3 iI 32 30i .~~~-- ~~~----.--i 1 ~ 3 lr ~ .-..-- ~ . -- --- -_T __ _

3`1i Kr-83M 1 .92E-03 2.25E-02 2.25E-02 3.24E-07 3.24E-07 _

32__Kr-85M 3.44E-03 -4.03E-02 4.03E-02 5.8..E. 5:81E-07 I

33. K r-8 5 1.13 E -0 5 1.32 E  :-4. 3 2E 04.- 91E -0 9 I 1.Q 1E-09 1 ........... _'._ _

34 r87 " -213E-02 1.321-01 .32E-01 1.91E-06 1.91E-086g " " __ _

35 .. .Kr:88 1~1 3,E-0 1.32E-01 1.32E-01 1 91. -06 1.91E-06 , _ _ _ ---

396 Kr 733E-02 8.5E-018E-01E-01 -O124E-05 I.24E-(5 t

1.43E-09 ---- -

Xe-131Mi ,46E-06 9.90E-05: 9.90E-05 . 1.43E-09 39* Xe-133M; 1.63E-04 1.91 E-03 1.91E-03 2.75E-08 j 2.75E-08 I _

X e - 13 3 4 .6 2 E -0 3 5 .4 1E -0 2 1 5 .4 1E -0 2 7 0.8 E-0 7 7 .B OE-07 _ _.. . . . .... . . ....

4TY Xe-135M 1.47E-02 " E-_- 1i.72E-01 2.48E-06 2.48E-06 -

4 2: Xe 135 1.24E-02 1.45E-1 1.45E-01 2.09E-06 2.09E-06 Xe-137. 8.46E-02 9.90E-11 9.9E-0i 1.43E-05 1.43E-05 ',

43 Xe-1381 5.02E2:5.87E1 5.87E-01 ,47E-06 8.47E-0_ _ _

44

Calculation PM-1058, Rev. 0 Attachment A Page A2 of A6 Calculation PM-1058, Rev. 0 Attachment A Page A2ofA6 A J B C D"" E F G I J I K 45 Inhalation Doses .2. ... ..........

46- - Curies Released Case 1 Dose (rem CEDE) Case 2 Dose (rem CEDE) 47 j to the Environment - - [(inhalation) ..- Taon) 48 Isotope VCase IDCF 1 Case 2 ILPZ - CR EAB CR EAB LPZ 1

49 1-131. 6.07E+00 -. 21E+02 3.29E+04 6.41E-02 2.41E-02 4,14E-03 1.28E+00 4.81E-01 8.28E-02 50 3 3.64E+01 7.28E02 3.81E+02 I 4.46E-03 1.67E-03 2.88E-04 I 8.91E-02 3.34E-02 5.75E-03 51 i__1-133 3.71E+01 7.42E+02 5.85E-03 6.97E-02 2.81E-02 4.50E-03 1.39E+00 5.23E-01 19.00E02 52 - -131,- 15.25E+01-1.05E+03 1.31E+02 2.21E-03 8.2+E-04 1.42E-04 4.42E-02 1.66E-02 I 2.85E-03 53 . I-135" E 1I9.28E+02 1.23E.03 1.83E-02 6.88E-03 1.18E-03 3.67E-0 1.38E-01 2.37E-02 54 - Totals 1.59E1-01 5..E-02 1.02E-02 3.18E O 1.19E4+00 2.05E-01 55 _______________ ____

56Eternal Dses ____ 11 5 _ ". ,asrdejR___sedCase 1 Dose (reem EDE) Case 2 Dose (rem EDE) 58 to the Environment I (External) _ _ [(ExteraI) 59 Isotope Case 1 V Case 2 DCF' CR EAB LPZ CR . EA.B LPZ 60 1-131 6.07E+00 1.21E+02 6.73E-02 .91E-05 1 42E-04 2.4.4E-05 j 3.82E-04 2.84E-03 4.88E-04 61 1-132 . 3.,-E+01 7.28E+02t4.14E-01 7.06E-04 ' 5.24E-03 .9.E-04 "1.41E-02 1.0E-01 1.80E-02 F62 -377 64 631145.25E+01 1-135 :;__4.654E+01 1.05E+3 9,28E+02 4.81E-01 i 1.89E-04 4" *-25E 1.095-01

.* 7.42E+-02

.05 48E0 1.6E0 2.95E-01 1.18E-03 6.41E-04 1.40E-03 8.76E-03 4.76E-03 2.41"E-04 1.51E-03 8.18E-04 3.78E-03 2.3E-02 1.28E-02 2.80E-02 1.75E-0.1

.75E 9.51E-02 4.82E-03 302E-02 1,64E-02 65 Kr-83M 2.25E-0.2 2.25E-02 5.55E-06 i 5.84E-12 4.33E-11 7.45E-12 5.84E-12 4.33E-11 7.45E-12 68 Kr-85Mt 403E-02 4.03E-02 2.77E-02 5.21E-08 3.87E-07 6.66E-08 ÷521E-08 3.87E-07 6.66E-08 67"- 1-32E-04E 1.32E-04 4.40E-04, 2.72E-12 2.02E-11 3.48E-12 2.72E-12 2.02E-1.1 3.48E-12 68 Kr-87 1.32E-1 13E. 01 1.52E-01 9.43E-07 - 7.OOE-06 1.20E-06 9.43E-07 7.OOE-06 1120E-06 6._9_9 Kr-88 , 1.32E-01I 1.32E-0l 3.77E-01 "2.34E-06 1.73E-05 2.98E-06 .2.34E-06 1.73E-05 2.98E-06 70 Kr-89 '.-01 8.58E-01 o.O0E+00 0.OOE+00 0.OOE+00 O.00E+00 0.00E+00 O.OOE+O0 O.OOE400 71 Xe-131M _  : 9.90E-O519.90E-05 1.44E-03 6.67E-12 4.95E-11 8.51E-12 6.67E-12 14.95E-11 8.51E-12 72 Xe-133M 1.91E-03 1.91E-03 5.07E-03 I 4.53E-10 3.36E-09 5.78E-10 4.53E-10 3.36E-09 5-78E-10 73 Xe-133A 5.41E-02 5.41E-02 5.77E-03  ; 1.46E-08 1.8E-07 1.86E-08 t.46E-O8 1.08E-07 1.86E-08 74 "Xe135M .... . 1.-7E--1. 1.72E-01 7.55E-02 6.08E-07 4.51E-06

  • 7.76E-07 6.08E-07 4.51 E-06 7.76E-07 75 Xe-13511 1.45E-0 1 1.45E-01 4.40E-02 2.99E-07 2.22E-06 382E.07 2.99E-07 2.22E-06 3.82E-07 76 Xe-137 9.E0--1 9.90E-01 0.0E÷00 0.00E+00 0.OOEL00 O.00E400 0.OE+*00 0.00E+00 0.00E+00 7"-'7- Xe-138  : 5,87E-O1! 5.87E-01 -2.13E-01O1 5.87E-06 4.36E-05. 7.49E-06 5.87E-06 436E,05 7.49E-06 78 Sub-total I "_, 2.75E-03 2.04E-02 !3.5 3 5.47E-02 4.06E-01 6.99E-02 7-'9Tot (rei TEDE) , *1.62E-01 7.99E.02 1.38E4)2 3.23E400 1.60E400 2.75E-01 81 DoseConversion Factor (rem/Curde) from Federal Guidanoe Report (FGR) 11 per Reg. Guide 1.183 T2Dose Cower'siot Factor (m-n,;-m -/de-seon) from FGR 12 per Reg. Guide 1.183 _._ _

83 347E-4 BEathlng rate (m Regulatory Guide 1.183 tvUthout round-off) perod)-pe 84 5.05E-02 Control Room Geomeb'y FactorperReg. Guide 1.183, Regulatory Position 4.2.7 _

85 3.83E'01 EAB r,, (meters) for F stability, (taken from PAVAN runs In Ref. 9) _ ..  :

86-2--26Eý02 LPZ a. (meters) far F stability, (taken from PAVAN runs in Ref.9) .....

871 __l.00 Wind Speed ( m/s¶)j.

3

.. t .1 88 3.47E-04 X/Q (seconds/m ) at EA Boundary 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> based on RG 15 methodology I 89 5.97E-05 YQ (seoondedm at Low Population Zone- 0-2 based on RG 1.5 melloxxdo ., [

Calculation PM-1058, Rev. 0 Attachment A Page A3 of A6

3 69337 IVolume of cloud _

4 75131000 . IM Lass.of. water i

=-25800'453.59 M oassof steam _- _

6 .1.. reactor coolant -

.7 64.2 .tseconds for ciot. __

8 176000 _ Votume of Cant1

_9 Halogens - .-- . .. -.-.-.-.-. ____

10 1T Activity I

......... . Dislrbutibn _ Normalized Case 1 "

  • 13 Isotope (UFSAR FGR 11 .- I-13"IDE Normalized 14 Sect,. 14.6.5) DCF' i Activity Activity 15 uCi/cc Re!nCi. ...-.-

17 1-131 0.17 32900 .=C16-B16-C$16 =D16*-.2/D$21

.-132 .1.02 .381 .... ,=C17817/C$16 0D17*02.0$21 187 1-133 1.04 5846 =C18B18C$16 =D18*02/$21 19 ........ 1,.....4131

.- . =C19B19C$16 019.02..2-1-135 1.3 .11230 -=C20"820/C$16 0=D200.2/D$21 21 '---------SUM( 1 620)-ME16:E20) 22 t .non-spiked' 23 Noble Gases. - Cae -

24 )ac. Case I Case 2_ _ _ _ _ _

7-K PM-740-A Release T-obte Case I Case 2 Cloud Cloud ___

5- I pe Noble Gas 1 Actt Activity Concentration Concentration

....... tRelease Release 29 uCigm , Ci Ci Ci/m,

.K ... .. .0b09*2- I

=s31.A0o.o00o1 0.02246903424 -C3-I/A3 =D311$AS3 __

Kr-85M _ 0.00344 I =B32*$A$5*0.00-1;0.04025701968 I=C32/$A$3 =D32/$A3 1

KrD. 000011  ;=B33'SAS5*0.000001 0 0D001322396280-C33/WA3 =033/SA.S3 Kr-87 . . O 00113 t-B35-A$5" 000001 01322396206 [C34/$A$3 .

=D34/SAS3___ __

36 - r-80.0113 35SAS5WS0,000001 10.1322396286_--C3S/SAS3--

37 ....r-------.... 0.0733 ,B36 50000001 0.8578021926 =C36/SA$3 =D36ISA$3 _______

1--311M-- -0*0.0-0-0-00-8,46 =837SAS50.000001 0 0O099004182 ='C37SA$W3 =037/$AS3 ___

38 Xe-133M 0.000163 5500001 000190752738 8 A3 _ =D38/SAS3___

39 Xe-133 0.00462 =B39SA$050.00001 0.05406611364 =C39/$A$3 =D39/$A53 40 Xe--i35M 0.0147 =40$A$5 .000001 0.172028543,4 C40/$AS3 _ =040/$A$3I___

41 _Xe-135 X.. 137 . 0.0124  :=B41"A5"0.000011 0.1451125128 =C41/$A$3  ;=-041/SAS3 --. -

42 i0.0846 6=B42S$A$5*0.000001 10.9900418212 =C42/SAS3 =042/SA3 1 tXe-138 0.0502 '=B43-$A$5*0.000001 0.5874716244 =C43/$AS3 =D431$A$3_____

I II I

CaWalion PM-1058, Rev. 0 .Attachmwt* A Page A4 of A6 A 8 ( c D E .F G" 45 Inhalation Doses f "- - _

- _Curi1 Releas-, Case I Dose (ren CEDE)

Ito the Environment (Inhalation) 48 isotope .CeCase Is DF CR___ EA13 49 - 1.131 =G1-6 I=18 32900 - 116*$E4955ii833$A$7 C49$E49$A$83$A$88 50 1-132 =G17 =H17 381 =117$E0S0A$8]3$A$7 I=C50ESO$A$83S$AS88 51 1-133 .=G18 . =H18 5846 4=18E51"$A$83$A$7 I=C51$E51S*$A$83*SA$88 32- kH=G19

-19 131 =I19"$E52A$83A7 -=C52_$E52S$AS83*$AS88 593 . .13, . .G2- .*'* . ............... ........... : . .... * =H20 . ... 1230 .... -. . _suc__S m:F~

=l20"$E53$SAS83*SA$7 ......S.....:.

I=C53"SE53SA$83S$A$88 3F- Totals SUMI(F419:FS3) *SUMfG49:053)

.xn-iboi-*"

56 Eiternaloe

ýs z~

I~ ~ ----_ --

57 Curies Released ,_Case 1 Dose (rem EDE) 5 '- totheEnvironment . 1" _ (Exteral) 2 59 Isotope Case I - - -Case 2 DCF CR EA 60' -- 1-131 ,0=C,9_ iDA9 0.0 4 =I16"SE60*$A$84"$A$7 =C60S$E6("$A$88 61* 1-132 ____50_. ___'0.44 117"$E61*$AS84"A$7 =C VE61 A88 62 i133 -=C51 =051 0.10878 =i18*SE62"$A$84"SA$7 =C62'$E62*$A$88 6 - 0.481 =i19*SE63*$A$84"$A$7* I=6C* -63*$A$88 64 . -15D. -. 53 10.29526 820$E64i$A$84*$A$7

=C64*$E64*SA$88 0.02246903424 0.02246903424 0.00000555 =E31$E65"SA$84*$A$7 :=C65$E65s$A$88

_ý 012 4 9 3 2 __

68 87 004025701968 010"425701 0.027676

-8 -E32SE66**A$84'*-*7 =C66$SE668$A$88 67 Kr-85 0 0001-322396286 10.00013223962846.00040 E33 SrA54$ 7 T=6S~5S8 -

28 0.1322396286 0.15244_____ SE68*$AS84*$A$7 =C68S$E68*SA$88 69 K-r--~8~8_ C0. 132239628 -01322396286 0.3774 =E35 SE69$A84'$A$7 =C69SE69-A$88 70 IKr-89 ___10857802192 '10.8578021926 0 E36*SE70*$AS84*$AS7 =C70"$E70*$AS88 71"* Xe-131M . . 0.00009900418212 0.000099004182 0.0014393 ... E3E7$A$84-" =C71*SE71S$A$88 72 Xe- 133M 10.001907527386 ;0.001907527386 0.005069 =E38*SE72*$A$84S$A$7 =C72"$E72*$A$88 73 Xe-133 '0.05406611364 0.05406611364 0.005772  :,-E39*SE73'SA$84*$A7 =C73SE73°$A$88 7.4 Xe-13,M b172285434 0.17-20285434 10.07548 ___ .=E40 SE74*_A$S4'A7=C74$E74*A$88 75 Xe--135 10.1451125128 10.1451125128 :0.04403 E75SAS84"$7 C75$E75$A$88

.7"- Xe-137 0.9900415212 - 0'..90--2128 .0.E42*$E7"AS84"$A$7 =C76*$E765*$A$88 T7 - 13 ,0.5874716244 ;0.5874716244 0.21349 =E43*SE77S*A$84$A$7 j=CT77SE77*$AS88 8 -=SUM(FSO:F77) -=SUM(G60:G77) 7Total (rem TEDE) - . ]

--- -- * =SUM(F544+F7) '=SUM(G54+G7B) 81 'Dose Conves r

~..........

2 Dose Conversior ____ ____ ________________

83 0.000347 Bre.athing. _ __

89-o, ..... (*s ___.-.. .........

. .. .*-.----t 87 " :Wnd Speed(rnVs }. _ _ - _._ _

88 =0.0133YAS851AS87 --_(s d"Ij .

-- .t6 -= -.---...

Calculation PM-1058. Rev. 0 Attachment A Pago ASof A6 H I ,,,I I .,K 1 value (DE 1-131 of 0.2 uCilcc) permitted for continued full power operation 2

3 value permitted (DE 1-13! of 4.0 uCi/cc) corresponding to an assumed pre-accident spike 4

.. .... .i.

Case I Case 2 Release S Release Case 2 _Claud Cloud Activity Concentration Concentraton Release J Ci. cu/m

  • C~hm3

=F16"SA$4"0.000001/$AS6 =G16t$A3 =H'16/$A$3 _

F17"AS40.00001i,$AS6 =G7'f$AS3 171$A.$3

= A40.000~A 76="GS-*- 38/*A3

=F 19$A$.r.000001/$A$6 =G19/$A$3 =H 19SAS3_

=F20"$A$4"0.000001./$AS6 '---G20/A$3 =H20ISA$3 .

o ~..... ......

-- -------- -- I ____ - - ---------- _____ -___ ___ _

__ - ~ '~~zi

Calculation PM-1058. Rev. 0 Attachmnent A Page A6 of A6 H JK 45 ______

46_ ____ Case 2 Dose (rmCEE (inhalation) ______

48 PZCREAB LPZ

-49 =6g9SE49SAS83'$AS89 -J16'SE49-$A$83-AS7 =D49*$E49*$A83*$A488 =D49S$E49*$AS83*SAS89 50C5OS$E5OSAS83'SAS89 =J17-$EW0SAMYSMAS7 W.0E0SSXA8 15S5SS3A8 52 l 2 AS- -2E 3 A 8- =J18 S 5 S 8 S $ A $83 S$A

= 052 1E5 2*S

[- S88 I=D05 21E 5 2 S$A S8 3 *$A 589 53=053*1E53'SAS83S-;AS89 F=j-aSE5SAS8-$AS7 =

[DS3*SE53*SAS83*SA88 =D5&3SE53*$ASS3*SAS89 5-4 UMH9H3____]SUMQ49 .153) j=SUM(J4Sl:JS3) SUMý(K4A53) 56 57 T ------ **--~-~-- Casme2 Dose rm EDE) _ _____

59 LPZ CR ____ EAS LZ L__

P__

60O C W0SE60SA-$81 =J6$SE60$AS84*$AS7 -=6$E6OI$A$88 I D60*SE6O*SA$9 76-1C6S6SA8 -rSE61r5AS84SAs7 =D61iE61*SAS88 - D61_5E6i*SAS89___

6F2 =16262 2SAS89 =J 18$E62rSA$84S$A$7 '-D62S$E62*$AS88 D682'SE62SAS89 63 -C3'E63A$9 i9S6$S84S =D63*1E63$AS$B8 D3E3A8 64 =C64SE-64S$AS8g =J20S$E64*$A$84*$AS7 =D64*$E64*5A$88 D064*SE64S$A$89 65 =C65*$E65*$A$89 &ViA 7E5A8$$ TýO65SWE65$A 8 -- D65*$E655$A$89 66 =C66S$E66*SAS09 !F32*$E66'SA$84S$A$7 D66'$E6$8 D6586Al 67 C6P5E67A589 -F33E67$A$84*SA$7 =D67*$E67'SA$88 D7ESA8 6 CTd68$ýE-68S$A$89 =F34*$E68*SA$84*SAS7 jf=D $6BSEBBSA8B j=DW*$E68'SAS89 6 C69*$E69*$AS89 :F35*$E69S584,$A$7 I=D69*$E69'SA588 .=D69*$E69SA$89 -

70 =C70-$E70OSA589- -- =F3(6SE7O$A$a4*$A.S7 t D70*SE70*SA$8 ___ 70*$E70S$AS89 71 =C1$7-AIF37?SE71SA584SA$7 t--D71SE71S*AU8 - 1 OVESA8 72 C7*$72'A$9 F38*$E72*$A$84S$AS7 - =072V5E72-$AS88 ----- =O72*SE72*SA$89 _

73 'C'7'3*$E-7-3S'A$89 =F39$EI3*$AS84*$AS7 '=D73S$E73*SAS88 - =D73*SE73*SAS89 74 =C74S$E74$A$89 :F40*SE74S$A$8-45A -- =D74-$E74S$A$88 ____ D74*$E74*SMS9 75=C5S75A$9F41 5E75-SA$8V5AS7 -l=D75iE;75S$AS88 __ 075S$E75*SA$89 -

76 C?6SE7'5A$89F42*SE7fr$AS8.4$A$7  :=076SE765$AS88 =D76$E7665A$89 __

77 =C77*SE77S$A$89 F4SrAS$S7  :=077*$E77*$A$88 __=771F77-$A$89 78 =;SldM(jBO:H77)  :-SUM(160:177) -Sum(jwJffi77 79 ~SMH4H8 SM147) -- ]=SUM(J54.tJ78 ___SUM(KG0:K77)

__ SUM(K54+K78) 50- ---- -. -------- - - - - - -----

83------------............._ ----- _ ___ _ _-

843__ ___

89- ..----. i_ _ _

1I R..V NO. 00 REV. NO. II PAGENO.

PAGE.NO..... Of BI B1 of B1 I I CALC. I AT.ON NO PM-1058 Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation / Amergen Date: February 5, 2003 Project: Peach Bottom Atomic Power Station MSLB AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: PM-1058, Rev. 0 Attachment A spreadsheet NIA N/A Status [ ] Prelim.

[X] Final

___ Void WGI Prequalification [ ] Yes

[XI No Run No.

Description:

Analysis

Description:

Spreadsheet used to perform dose assessment for MSLB, as described in calculation.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: H. Rothstein On: December, 2002 Run by: H. Rothstein ~ <l4~

Checked by: P. Reichert Approved by: H. Rothstein Remarks: WGI Form for Computer Software Control This spreadsheet is relatively straight-forward and was hand checked. Attachment includes the spreadsheet in both normal and formula display mode and so is completely documented.

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