L-96-012, Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity: Difference between revisions

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{{Adams
#REDIRECT [[L-96-012, Monthly Operating Repts for Dec 1995 for St Lucie Nuclear Power Plant Units 1 & 2]]
| number = ML20136G315
| issue date = 12/19/1996
| title = Rev 1 to Unit 1 RCS & SG Isotopic Concentrations,Pre- Incident Spike Concentrations & Iodine Spike Appearance Rates Corresponding to 0.35 & 0.5 Uci/Gm RCS Specific Activity
| author name = Lavie S
| author affiliation = DUQUESNE LIGHT CO.
| addressee name =
| addressee affiliation =
| docket = 05000334
| license number =
| contact person =
| document report number = ERS-SFL-96-012, ERS-SFL-96-012-R01, ERS-SFL-96-12, ERS-SFL-96-12-R1, NUDOCS 9703180002
| package number = ML20136G263
| document type = ARCHIVE RECORDS, OPERATIONS SUPPORT-CALCULATIONS
| page count = 26
}}
 
=Text=
{{#Wiki_filter:RTL: A9.621A Form: FIE 1.1031 a
y fass 1
2 3 Health Physics Department REVISION Subject U1 RCS and Steam Generator Isotopic Concentrations, PAGE 1 OF Pre-incident Spike Concentrations, and lodine Spike Appearance ERS-S FL-96-012 3g Rates Corresponding to 0.35 and 0.5 pCi/gm RCS Specific Activity.
Reference RCM RP EPP T/S 3/4.4.8 EM DCP RIP Review Category nd 2 10 CFR 50.59 E RSC Req'd RSC Not Reg'd Required 2
Purpose This package determines RCS and steam generator isotopic concentrations that correspond to the technical specification specific activity limits 0.35 pCi/gm and 0.5 pCi/gm. These values are being prepared in support of a future change in the RCS specific activity T/S limit from 1.0 Ci/gm Also determined are the transient lodine spike T/S graph (pre-incident iodine spike) and the iodine spike appearance rates for use with concurrent iodine spikes.
N O TE: This calculation package documents th e evalu ation de scribed above. This packag e DOES NOT,in of itself, provide autority for any revision in a structure, system, or component; nor changes in procedures. tests, and experiments described in the plant licensing basis. The data and/or conclusions of this package shall not be extended to other purposes without explicit concurrence from Radiological Engineering.
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E Assumptions E Results O Illustrations 4p E Methodology E References E Printouts I6 For RSC IE 1, O Code Listings E BV RECORDS CENTER O DIR, RadOps-1 E Author: S.F. LaVie E CALCULATION FILE O DIR, RadOps 2 O
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RTL: n/a Form: RE 1.103 3 a92 MU Y [ nir==mne Lkpt ERS-SFL-96-012 b A
H.m Physics Department page 2 DISCUSSION BVPS Unit 1 RCS and secondary activity are limited by technical specifications. 2 TS 3/4.4.8 speci-fies that the specific activity of the reactor coolant shall be limited to:
a.
s 1.0 Cl/ gram DOSE EQUIVALENT l-131, and b.
s 100/E Cl/ gram in addition, the TS provides a graph of DOSE EQUIVALENT l-131 primary coolant specific activity limit versus percent rated thermal power for transient conditions. DOSE EQUIVALENT l 131 is defined as being that concentration of I-131 which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131,1-132,1133,1-134, and 1135 actually present. The thyroid dose conver-sion factors used for this calculation shall be based on ICRP-30. The basis of this TS will be revised A
to reference DCFs based on ICRP-30 in lieu of those currently referenced.
TS 3/4.7.1.4 specifies that the specific activity of the secondary coolant system shall be s 0.10 Ci/
gram DOSE EQUIVALENT l 131.
Note that the technical specifications do not provide isotopic activity limits. However, such values are needed for various design basis radiological assessments. The Unit 1 UFSAR5 does not tabulate isotopic activities for the more significant radionuclides expected in the RCS and secondary side that correspond to 1.0 Ci/gm. These values were generated by SWEC15 as part of the control habitability effort in support of the Unit 2 licensing.
USNRC Generic Letter 95-05, Voltage Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking, provided an option for licensees to 5
reduce the RCS technical specification activity as a means of increasing allowable MSLB-induced primary-to-secondary leakage in implementing alternate tube plugging criteria. The generic letter provide sample RCS activity technical specifications. The generic letter does provide that reductions to below 0.35 pCi/gm require special justification with regard to lodine spike release rates.
The purpose of this calculation package is to generate, for new proposed RCS activity T/S of 0.35 Ci/
gm and 0.5 Ci/gm DOSE EQUIVALENT l-131:
RCS isotopic concentrations that correspond to both of these overall activity limits, a
pre-incident spike concentrations SG liquid and vapor space isotopic concentrations that correspond to the secondary activity revised T/S transient I-131 activity graph lodine appearance rate factors for concurrent iodine spike cases a
Although the secondary side equilibrium activity is a direct function of the RCS activity, the generic letter did not explicitly identify modifications to this technical specification as an option. Since the initial activity in the steam generators is a relatively minor contributor to offsite or control room dose, reduc-ing the 0.1 pCi/gm technical specification will not be pursued further herein.
1
 
RTL: n/2 Fcrm: RE 1.103-3 fMP2
)
-UN M ERS-SFL-96 012 Heam Physics Depanment Page 3 METHODOLOGY 1.
RCS Concentrations Corresponding to 0.35 and 0.5 Cl/gm Dose Equivalent 1131 The technical specification definition of dose equivalent 1-131 was stated above. Mathematically, this definition is expressed as:
1 I A e DCF, i
d e.1131 = 3 DC %
Ill where*
Dose equivalent 1-131, pCi/gm d.e.1131
=
A, = RCS activity, pCi/gm, for isotope i (I-131 to 1-135)
DCF,= Dose conversion factor, for isotope i Since this application desires that the d.e.1131 be 0.35 pCi/gm or 0.5 Cl/gm, it is necessary to i
ratio the input activities:
0.35 Aio 33 - A; (2a]
d e.1131 0.5 A
-Ai (2b]
j in3 d e.1131 where:
A RCS activity, pCi/gm, for isotope i, for 0.35 Ci/gm d.e.t-131 mix lo.35
=
A RCS activity, Ci/gm, for isotope i, for 0.5 Ci/gm d.e.l 131 mix io.s
=
Note that all radionuclides in the mix, including noble gases are included in this ratioing.
2.
RCS Concentrations Corresponding to 21 and 30 pCi/gm Dose Equivalent I-131 The pre-incident iodine spike is based on the minimum transient 1-131 technical specification.
The generic letter directed that the graph of the transient RCS activity TS be reduced by the same factor that the steady state d.e.1-131 specification was reduced. 60 x 0.35 = 21,60 x 0.5 =
: 30. These values can be determined using a variation of equations 2a,2b:
21 A,,- Ai i
d.e.1131 30 Aiso - Ai d e.1131
 
rte n/a Form: RE 1.103-3 A92 NM ERS-SFL-96-012 Ak HealthPhysicsDepartment Page 4 where:
Ain = RCS activity, Ci/gm, for isotope i, for pre-incident spike based on 0.35 Ci/gm de.l.131 A
RCS activity, pCygm, for isotope 1, for pre-incident spike based on 0.5 Ci/gm de.l 131 io
=
3 3.
SG Liquid Concentrations Corresponding to 0.1 Cl/gm Dose Equivalent 1-131 The technical specification definition of dose equivalent 1-131 was stated above. Mathematically, this definition is expressed as:
I A e DC6 i
d.e.1131 = i DC5i3i I4l where:
d.e.1131 Dose equivalent I-131, pCi/gm l
=
A, = SG liquid activity, pCi/gm. for isotope i (1131 to I-135)
DCF,= Dose conversion factor, for isotope i Since this application desires that the d.e.1131 be 0.1 Ci/gm, it is necessary to ratio the input activities:
i 0.1 i
^io1"^i
[5]
d e.1131 where:
A hi = SG liquid activity, pCi/gm, for isotope i, for 0.1 Ci/gm d.e.l-131 mix Note that only radiolodines are included since it is assumed that no noble gases are retained in the SG liquid.
4.
SG Steam Concentrations The noble gas concentrations in the steam phase are a function of the noble gas release rate from the primary and the steaming rate of the generators. No holdup of noble gases is as-sumed. Thus, the noble gas concentrations are not dependent on the secondary activity, but rather are a function of the RCS activity. Note that the concentrations are based on all three steam generatdrs and as such, are applicable to the the main steam header. The concentrations are applicable to the activity in the steam phase in a single SG only if one assumes that the primary-to-secondary leakage is evenly distributed between SGs.
4', Primary-to-Secondary Leak Rate AING Tctal Steaming Rate
 
RTL n/a Form: RE 1.103-3 A91 M
ERS-SFL 96-012 A h Health Physics Departrnent Page 5 4
where:
j A, = RCS activity, Cl/gm, for isotope i A
SG steam phase activity, Ci/gm, for Isotope i ina
=
The lodine concentration in the steam phase are based on the iodine concentrations in the liquid i
phase, adjusted for partitioning:
l J
A;,,,, d,.0.01 (7]
i o, where.
li SG steam phase iodine activity, Ci/gm, for isotope I (i-131 to 1-135)
A,an,
=
Ah3 SG liquid phase activity, Ci/gm, for isotope i, see equation 5
=
5.
lodine Spiking Appearance Factors Most of the material in this section is extracted from Review oflodine Spike Data from PWR 7
Power Plants in Relation to SGTR with MSLB, EPRI Report TR-103680, December 1993. Other j
references.s.'
were also reviewed.
s Equilibrium concentrations of iodines can be expressed as:
R C = Co. e-A.t + M. A {3_,-x.t)
[8]
t i
i where:
C, = lodine concentration at time t, Ci/gm Co= lodine concentration at t=0, Cl/gm R=
Constant release rate, Ci/hr I
M=
Mass of water in primary system, gm A- = loss rate constant for iodine, hr4 t=
time, hr This expression can be re-arranged to solve for R:
R = MA(C - Co. e-A.t) t 1
(93 1 - e-A.t if one recognizes that the concentrations multiplied by mass yield activity, the expression can be written in a different form:
R-- ^'~^0**
1 - e-A*'
 
RTL: n/a Form: RE 1.103-3 a9.2 MM ERS-SFL-96-012 Ak HeemPhysicsDepartment Page 6 This form is identical to that described by Adams and Atwood", and by Essig before the ACRS.
8 At equilibrium, the exponential terms in expression (g] reduce to 0, yleiding:
R=C.M.A
[11]
' The loss rate constant, )., is expressed as:
A=F.E L
M +p + d
[12]
where:
F=
cleanup system flow rate, gm/hr E=
fractional cleanup efficien(.y 1
1g
=
L=
leak rate from RCS, gm/hr 1
).,
decay constant for I-131, hr
=
The cleanup system flow rate is typically expressed in units of gpm. The flow rates in the let-down and charging system (which determines the purification flow rate) are based on relatively 3
cool, low pressure water. Thus, it is appropriate to assume a density of 1.0 gm/cm.
The technical specification leak rate from the RCS is expressed in gallons per day. The density 2
of RCS water at T,ya = 577F and P = 2235 psig can be found from steam tables via interpola-3 tion of specific volume data (ft /lb):
2000 psia 2250 psia 2500 psia 570 F 0.02206 0.02196 0.02186 l 577 0.02221 l
580 F 0.02243 0.02232 0.02221 3
a ft /lb specific volume = 0.72 gm/cm density.
0.02221
' Note: The above treatment of RCS density may appear contrary to other applications in which 3
the leakage was assumed to have a density of 1.0 gm/cm. It must be noted that the intent of the above calculation is to determine an equilibrium iodine appearance rate during normal operations. Thus, it is appropriate to correct for density in this application.
n 4
 
RTL: nh Fum: RE 1.1033 A92 MNM ERS-SFL-96-012 d Ah HodhPhyksDepartment page 7 INPUT DATA / ASSUMPTIONS i.
RCS and Secondary Uquid Concentrations at 1% F.F.
[4, 5,13]
RCS SG Liquid Nuclide Cl/gm Cl/gm Kr-83m 4.34E 01 0
4 Kr-85m 2.12E+00 0
Kr-85 1.12 E+01 0
Kr 87 1.21 E+00 0
Kr-88 3.23E+00 0
Kr-89 1.02E-01 0
Xe 131m 1.09E-01 0
Xe-133m 3.11 E+00 0
Xe-133 2.65E+01 0
Xe-135m 1.10E+00 0
i Xe 135 3.25E+00 0
Xe-137 1.65E 01 0
xe-138 6.80E-01 0
1-131 2.54E+00 3.20E-03 1132 8.85E-01 5.68E-04 l-133 3.96E+00 4.18E-03 1-134 5.54E 01 1.00E-04 l135 2.13E+00 1.53E-03 The values tabulated above are from the Unit 2 UFSAR and. Reference 13. This refer-ence notes that it is appropriate to use the Unit 2 values in pCilgm rather than the pCi/cc values in the Unit 1 UFSAR table 148-6. This assumption wasjustified on the basis of a comparison of Unit 1 UFSAR Table 148-5 and Unit 2 UFSAR Table 11.1-3, which tabu-late the assumptions used in calculating the RCS activities. The significant input param-eters in these two tables are comparable and it is reasonable to assume that the outputs would be comparable as well. Note that differences in the SG liquid concentrations is due to condensate polishing at Unit 2.
2, lodine Dose Conversion Factors (mrem /pCi)
[3]
i 1131 1.08E-3 l-132 6.44E-6 l-133 1.80E-4 1134 1.07E-6
/1 1135 3.13E 5 The dose conversion factors listed above are for thyroid CDE as defined in ICRP-30 and are taken from Federal Guidance Report No.11'. This represents a change from the previous TS definition of Dose Equivalent I 131, which willbe revised as a result of this effort.
 
RTL: nh Fcrm: RE 1.103-3 A92 DuquBSM M ERS-SFL-96-012 A k HeahhPhysicsDepartment page 8 3.
Total Steam Flow = 3.85E6 x 3 = 1.155E7 lbm/hr
[4]
4.
Decay Lambda, sec1
[14) l131 9.9783E 7 1-132 8.3713E-5 l-133 9.2568E 6 l-134 2.1963E-4 l135 2.9129E-5 J
5.
RCS Mass = 1.91E8 gm (4) j Note: Table 148-5 of the Unit 1 UFSAR Identifies the Reactor Coolant liquid volume to be 9387 ft' With the specific volume of 0.02221 ft'/lbm, the mass of the RCS is 4.256E5 lb, or 1.917E8 gm. The Unit 2 value was 1.91E8 gm. Since the values in datum I were based on 1.91E8 grams, this latter value will be used herein. In support of the Unit 1 analysis for control room habitability, NED directed SWEC to use 3.9ES lbm as the RCS liquid volume. This is equal to 1.77E8 grams, or about 7% less than that established for Unit 2. TheJustification for this value was not documented. Although the smaller value has been used in several analyses performed since, it now seems appropriate to use the larger value in this application.
CALCULATION 1.
RCS Concentrations Corresponding to 0.35 and 0.5 pCi/gm Dose Equivalent I-131 The following table implements expression (1):
1% FF RCS isotope Cl/gm DCF
" Dose" l131 2.54E+00 1.08E-03 2.74E-03 1132 8.85E-01 6.44E 06 5.70E-06 l-133 3.96E+00 1.80E 04 7.13E-04 1134
- 5.54E-01 1.07E-06 5.93E-07 l135 2.13E+00 3.13E-05 6.67E-05 A
Sum 3.53E-03 / 1.08E 3 = 3.268 pCi/gm The dose equivalent 1-131 associated with 1% F.F. RCS equilibrium concentration is 3.268 Ci/
gm. Using expressions (2a] and [2b], ratio the 1% F.F. equilibrium concentrations to obtain the values appropriate for 0.35 pCi/gm dose equivalent, and the 0.5 Ci/gm dose equivalent:
 
RTL.: M2 Ferm: RE 1.133-3 &92 i
N'D
'%%.uquesne Lkpt ERS-SFL-96-012 d
. m.a,o. e.-
page 9 RCS Equlilbrium Concentrations, Cl/gm Corresponding to l
0.35 Cl/gm 0.5 Cl/gm isotope 1% F.F.
d.e.1 131 d.e.1 131 Kr-83m 4.34E-01 4.65E-02 6.64E-02 Kr-85m 2.12E+00 2.27E 01 3.24E-01 Kr-85 1.12E+01 1.20E+00 1.71 E+00 Kr 87 1.21 E+00 1.30E-01 1.85E-01 Kr-88 3.23E+00 3.46E 01 4.94E-01 Kr-89 1.02E-01 1.09E 02 1.56E-02 Xe 131m 1.09E-01 1.17E-02 1.67E-02 Xe-133m 3.11 E+00 3.33E-01 4.76E-01 Xe 133 2.65E+01 2.84E+00 4.05E+00 l
Xe-135m 1.10E+00 1.18E 01 1.68E-01 Xe 135 3.25E+00 3.48E 01 4.97E 01 Xe-137 1.65E-01 1.77E-02 2.52 E-02 g
Xe-138 6.80E-01 7.28E 02 1.04E 01 1131 2.54E+00 2.72E-01 3.89E-01 1132 8.85E-01 9.48E-02 1.35E-01 1133 3.96E+00 4.24E.01 6.06E-01 l134 5.54E-01 5.93E 02 8.48E-02 1-135 2.13E+00 2.28E 01 3.26E 01 2.
RCS Concentrations Corresponding to 21 and 30 Cl/gm Dose Equivalent 1-131 Using the dose equivalent I-131 concentration from above and expressions [3a] and (3b], the 1%
F.F. equilibrium concentrations can be ratioed to obtain the values appropriate for 21 Ci/gm dose equivalent, and the 30 Cl/gm dose equivalent (transient technical specification concentra-tions corresponding to the 0.35 Ci/gm dose equivalent, and the 0.5 Ci/gm dose equivalent).
RCS Transient Concentrations, Cl/gm Corresponding to 21 pCl/gm 30 Ci/gm J
-Isotope 1% F.F.
d.e.1-131 d.e.1-131 1-131 2.54E+00 1.63 E+01 2.33E+01 s
1-132 8.85E-01 5.69E+00 8.12 E+00 l
l133 3.96E+00 2.54E+01 3.64E+01 I-134 5.54E-01 3.56E+00 5.09E+00 1135 2.13E+00 1.37E+01 1.96E+01 l
j
 
RTL: W2 Ferm: RE 1.103-3 &91 N4Dy muieLight ERS-SFL-96-012 b AhHoa Physk:s Department page 10 3.
SG Liquid Concentrations Corresponding to 0.1 Cl/gm Dose Equivalent 1131 The following table implements expression (4):
1% FF isotope Cl/gm DCF
" Dose" l131 3.20E-03 1.08E-03 3.46E-06 l132 5.68E-04 6.44E-03 3.66E-09 l133 4.18E 03 1.80E-04 7.52E-07
'g l-134 1.00E 04 1.07E-06 1.07E-10 l-135 1.53E 03 3.13E-05 4.79E-08 Sum 4.26E-06/1.08E 3 = 3.944E 3 Ci/gm l
The dose equivalent 1-131 steam generator liquid concentration associated with 1% F.F is 3.944E-3 Ci/gm. Using expression (5), ratio the 1% F.F. equilibrium concentrations to obtain the values appropriate for 0.1 Ci/gm dose equivalent.
SG Liquid Equilibrium Concentrations, pCl/gm Corresponding to i
0.1 Cl/gm isotope 1% F.F.
d.e.1-131 1131 3.20E-03 8.11 E-02 l
I132 5.68E-04 1.44E-02 l133 4.18E 03 1.06E-01 1
1-134 1.00E-04 2.54E 03 l135 1.53E 03 3.88E-02 4.
SG Steam Concentrations As noted above, the noble gas steam phase concentrations at equilibriura are a function of the primary-to-secondary leakrate, the steam flow rate, and the RCS concentrations. The concen-trations are found using expression (6).
- A Primary-to-Secondary Leak Rate AiNG i
Total Steaming Rate The total steaming rate (datum 3) 1.155E7 lbm/hr = 5.239E9 gm/hr. As noted above, the density 3
3 of the RCS liquid is 0.72 gm/cm,450 gpd = 1.703E6 cm / day = 5.110E4 gm/hr.
A'NG %. 5.110E4gm / hr 5.239E9 gm / hr Aiga = Aj e 9.754E -6
 
RTL: n/2 Ferm: RE 1.103-3 492 Dgmie M ERS-SFL-96-012 b Ak Heahh Physicsoepartment p,g, 33 Steam Phase SG Noble Gas Concentrations, Cl/gm RCS SG RCS SG Nuclide 0.35 de 1131 Steam 0.5 del 131 Steam Kr-83m 4.65E 02 4.53E 07 6.64E-02 6.48E 07 Kr-85m 2.27E 01 2.21 E-06 3.24E-01 3.16E 06 Kr 85 1.20E+00 1.17E 05 1.71 E+00 1.67E-05 Kr 87 1.30E 01 1.26E-06 1.85E 01 1.81 E-06 Kr-88 3.46E-01 3.37E-06 4.94E 01 4.82 E-06 Kr 89 1.09E-02 1.07E-07 1.56E-02 1.52E 07 Xe-131 m 1.17E-02 1.14E 07 1.67E-02 1.63E 07 Xe 133m 3.33E-01 3.25E-06 4.76E-01 4.64E-06 Xe 133 2.84 E + 00 2.77E-05 4.05E+00 3.95E 05 Xe 135m 1.18E-01 1.15E-06 1.68 E-01 1.64E 06 Xe-135 3.48E-01 3.40E 06 4.97E-01 4.85E-06 Xe-137 1.77E-02 1.72E-07 2.52 E-02 2.46E 07 Xe-138 7.28E-02 7.10E-07 1.04E-01 1.01E 06 The iodine concentrations are based on the liquid phase lodine concentrations reduced to j
account for partititioning using expression (7].
1 I
Alodine -A,=@
i g.
Steam Generator Concentrations, pCl/gm Liquid Steam Nuclide Phase Phase I131 8.11 E-02 8.11 E-04 l-132 1.44E-02 1.44E 04 l133 1.06E-01 1.06E-03 g
1-134 2.54E 03 2.54E-05 l-135 3.88E-02 3.88E-04 5.
lodine Spiking Appearance Factors j
The iodine spiking appearance rates are determined using expressions (11) and (12). A MathCad worksheet was used. See Attachment 3.
6.
Transient lodine Spike Technical Specification Graph j
GL 95-05 provided the following:
"... Revise Figure 3.4-1 to lower the line by a factor corresponding to the reduction in specific activity. The lowered line should parallel the original...."
The language here is not particularly clear. It is not possible to maintain the lines parallel if a factor is to be used. As the line proceeds to the left, the difference (i.e., value of the factor) increases, separating the lines, in order for the lines to remain parallel, the difference between
 
RTL: n/a Fum: REa.103-3 AS?
Nd 1
7 [@rusutrie Udit ERS-SFL-96-012 A pag'e 12 A
Health Physics Department the original line (between 70 and 100% power) and the new line reduced by a factor of 50% and 65% (in this case,30 Cl/gm and 39 Ci/gm) must be subtracted from the original line.
Since the requirement for the lines to be parallel is explicit, this analyst will assume that factor was intended to mean difference.
l contains a graph showing the lines associated with 0.35,0.5, and 1.0 Cl/gm. This graph was prepared using EXCEL, first plotting the 1.0 Ci/gm line from the current Figure 3.4-1, and then subtracting the differences 60-(0.35 x 60) = 39,60-(0.5 x 60) = 30.
RESULTS contains tables that summarize the results obtained above for the two proposed specific activity limits. Attachment 2 contains the graph of the transient activity.
)
REFERENCES 1.
DLC, Unit 1 Technical Soecifications.
2.
DLC, Unit 2 Technical Soecifications.
j 3.
USEPA. Limitina Values of Radionuclide intake and Air Concentration and Dose Conversion Eactors for Inhalation. Submersion. and Ingestion. Federal Guidance Report No.11, EPA-520/1-b 88-020 4.
DLC, Uodated Final Safety Analvsis Reoort Unit 1 5.
DLC, Uodated Fina! Safety Analvsis Reoort Unit 2.
6 USNRC, Voltage Based Reoair Criteria for Westinahouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking. Generic Letter 95-05 7
Postma, A.K., Review of lodine Soike Data from PWR Power Plants in Relation to SGTR with MSLB. EPRI Report TR-103680,1993 8
Essig, T, Radiation Protection Persoective on Steam Generator Generic Letter on Alternate Reoair Criteria fARCL presentation materials for ACRS presentation on August 3,1994.
9 Westinghouse, Comments on the Three individual StafLMembers Technical Concerns with the NRC Positions Described la the Generic Letter on the Voltage-Based Reoair Criteria for Westinghouse Steam Ge.rerator Tubes. Itr NTD-NRC-94-4329 dtd 10/31/94 10 Raghuram, S, etal, [qdicts Behavior in Steam Generator Tube Ruoture Accidents. NUREG/CR-2683 11 Adams,J, Atwood, C, The lodine Soike Release Rate During a Steam Generator Tube Ruoture.
Nuclear technology v94, June 1991
: 12. Keenan, J.H. and Keyes, F.G., Steam Tables: Thermodynamic Prooerties of Water includina Vaoor. Liauid. and Solid Phases. Wiley & Sons, New York 1969
: 13. SWEC, Technical Soecification and Pre-accident lodine Soike Concentrations for BVSP 1.
12241-UR(B)-451
: 14. DLC, Table of Half-Lifes and Decav Constants. ERS-SFL-93-018
 
RTL: n/a Farm: RE 1.103 3 fM2 AD 7 f a..ys_W Ud1t -
ERS SFL 96-012 A
Ony.,c.o.p.nm.ni page 13 ATTACHMENTS 1.
RCS and SG Concentrations Corresponding to 0.35 pCi/gm and 0.5 Cl/gm 2.
Transient Activity Graph 3.
lodine Spiking Appearance Rate i
i
 
.. ~
RTL: n/a Fctm: RE 1,103 3 fr92 pg W
ERS-S FL-96-012 Tgp% s nneny.e.o p.. n, page 14 j
4 Intentionally Blank
\\
1
 
RTL: nh Form: RE 1.103 3 A92 i
ggDuquBSrie M Attachm:nt 1 ERS-SFL-96-012 A A k Heam Phy*a Deputment page 15 J
Isotopic Concentrations, C1/gm, Corresponding to 0.35 Ci/gm Dose Equivalent 1-131 Steam Generators Liquid
* Steam **
Nuclide RCS Phase Phase Kr-83m 4.65E-02 4.53E-07 Kr-85m 2.27E 01 2.21 E-06 Kr-85 1.20E+00 1.17E-05 Kr-87 1.30E 01 1.26E-06 Kr-88 3.46E-01 3.37E 06 Kr 89 1.09E 02 1.07E-07 Xe-131 m 1.17E 02 1.14E-07 Xe-133m 3.33E-01 3.25E-06 Xe-133 2.84E+00 2.77E 05 Xe-135m 1.18E-01 1.15E-06 Xe 135 3.48E-01 3.40E-06 Xe 137 1.77E-02 1.72E-07 Xe-138 7.28E-02 7.10E-07 l-131 2.72E 01 8.11 E-02 8.11 E 04 l-132 9.48E-02 1.44E-02 1.44E-04 l-133 4.24E-01 1.06E-01 1.06E 03 l134' 5.93E-02 2.54E-03 2.54E 05 l135 2.28 E-01 3.88E-02 3.88E-04
* Based on SG Specific Activity TS of 0.1 Ci/gm d.e.1131
** Noble gases based on RCS 0.35 Ci/gm d.e.1-131. lodines based on 0.01 times liquid phase concentrations (0.1 Ci/gm d.e.
1-131)
RCS Pre-incident Spike Concentrations, Ci/gm Corresponding to 21 pCi/gm d.e.1131 l131 1.63E+01 1-132 5.69E+00 1133 2.54E+01 1134 3.56E+00 1135 1.37E+01 Concurrent lodine Spike Appearance Rates, Cl/sec (500 x Equilibrium Rate)
Corresponding to 0.33 Ci/gm d.e.1-131 1131 0.49 l132 0.92 1133 1.10 1-134 1.34 l-135 1.02
 
RTL: n/a Ferm: RE1.103-3 A92 t
Attachm2nt 1 i
M
'A f n.. m a le @
ERS-SFL-96-012 [L m yu o. e.m page 16 Isotopic Concentrations, pCl/gm, Corresponding to 0.5 Cl/gm Dose Equivalent 1131 Steam Generators Liquid
* Steam **
Nuclide RCS Phase Phase Kr-83m 6.64E-02 6.48E 07 Kr 85m 3.24E 01 3.16E 06 Kr-85 1.71 E+00 1.67E 05 Kr-87 1.85E 01 1.81 E-06 i
Kr-88 4.94E-01 4.82E-06 i
Kr-89 1.56E-02 1.52E-07 Xe-131m 1.67E-02 1.63E-07 Xe 133m 4.76E-01 4.64E-06 Xe 133 4.05E+00 3.95E-05 Xe 135m 1.68E-01 1.64E-06 Xe-135 4.97E-01 4.85E-06 Xe-137 2.52 E-02 2.46E 07 Xe-138 1.04E 01 1.01 E-06 l131 3.89E-01 8.11E 02 8.11 E-04 l132 1.35E 01 1.44E-02 1.44E 04 l133 6.06 E-01 1.06E-01 1.06E 03 1134 8.48E 02 2.54E-03 2.54E-05 l135 3.26E-01 3.88E 02 3.88E-04
* Based on SG Specific Activity TS of 0.1 Cl/gm d.e.1-131
** Noble gases based on RCS 0.5 Ci/gm d.e.1-131. lodines based on 0.01 times liquid phase concentrations (0.1 pCi/gm d.e.1-131)
RCS Pre-incident Concentrations, Ci/gm Corresponding to 30 pCi/gm d.e.1131 b
l-131 2.33E+01 1132 8.12E+00 1-133 3.64E+01 1134 5.09E+00 1135 1.96E+01 Concurrent lodine Spike Appearance Rates, Cl/sec (500 x Equilibrium Rate)
Corresponding to 0.5 Ci/gm d.e.1131 1-131 0.70 1-132 1.31 1-133 1.57 l-134 1.92 1-135 1.46
 
ERS-SFL-96-012 Attachmtnt 2 Pagel 7 i
N
\\
\\
~
250 T&
9 E 200
\\
3 1.0 uCVgm DOSE EQUIVALENT l-131 Steady State b
No 5
v>
~
150 1
\\
\\
d
\\
f 0.5 uCi/gm DOSE EQUIVALENT l-131 Steady State if 4
a.
E
\\
100 ss 1
0.35 uCVgm DOSE EQUIVALENT l.131 Steady State 8
\\
50 0
20 30 40 50 60 70 80 90 100 Percent of RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >0.35, >0.5, >1.0 uCl/ gram DOSE EQUIVALENT l-131 EC961202.XLS
 
Intentionally Blank e
 
ERS-SFL-96-012 d Attachm:nt 3 Pagd (j
IODINE SPIKE MODEL -Initial 0.35 uCl/gm @ Unit 1 The purpose of this sheet is to determine concurrent iodine spike appearance factors for reduced initial T/S activity. See text for derivation of formulae.
First, setup some unit conversions:
ORIGIN,1 Ci := 3.7 10'0 sec '
UCI := 1.0 10-6 Cl Assign some input parameters:
RCS Mass =
M.: 1.91 10 gm Purification Flow Rate =
F := 60 b 1.0 9 8
min cm Purification Efficiency (DF=10)=
E.
0.9 The parameters above are from Westinghouse letter DMW-D-3050 (Attachment G to SWEC 12241-UR(B)-224)
~
RCS T/S Leakage =
L = 450 I 0.72 U*
day 8
cm 9.9783 10-7 8.3713 10-5
-1 Decay Constants (ERS-SFL-93-018)
Ad :=
9.2568 10-8 sec 2.1963 10'"
2.9129 10-5 0.272 0.0948 RCS Concentrations @ 0.35 pCi/gm =
c,35 =
0.424 1
o 0.0593 0.228 4
YC961204.MCD
 
ERS-SFL-96-012 d
, Pags Zo A := F E L-
+
+Ad Where, F = purification system flow rate, E = purification efficiency, M = RCS mass, L = RCS leak rate, ).d = radioactive decay constant, ). = loss,1/hr.
-2 6.8073 10 3.6585 10" 1
hr' '
l=
9.7805 10 8.5515 10" 1.6935 10 '
~
The EPRI report provided the following expression for the appearance rate:
R = (C.35 M A O
Where, C = concentration, UCi/gm, R = eq. spike rate, C1/sec. (The arrow operator directs Mathcad to treat this as an array operation). The equilibrium rates are given below:
-4 9.8237 10
~8 1.8401 10
-8 R=
2.2002 10 sec
~8 2.6905 10
-8 2.0485 10 The concurrent iodine spike assumption is 500 x the equilibriuni spike:
4.9118 10 '
~
9.2005 10" S := R 500 S=
1.1001 sec 1.3452 1.0243 g
YC961204.MCD
 
ERS-SFL-96-012 d Page ZI IODINE SPIKE MODEL-Initial 0.5 uCl/gm @ Unit 1 The purpose of this sheet is to det' ermine concurrent lodine spike appearance factors for reduced initial T/S activity. See text for derivation of formulae.
First, setup some unit conversions:
ORIGIN.= 1 Cl := 3.7 10'O.sec~ '
uCi.= 1.0 10-6 Ci f
Assign some input parameters:
60 h 1.0 9*- - -
8 RCS Mass =
M := 1.91 10 gm Purification Flow Rate =
F2 min 8
em Purification Efficiency (DF=10)=
E2 0.9 The parameters above are from Westinghouse letter DMW-D-3050 (Attachment G to SWEC 12241-UR(B)-224)
RCS T/S Leakage =
L.= 450 b 0.72. 9*
day 8
cm I
9.9783 10~ 7 8.3713 10-8 Decay Constants (ERS-SFL-93-018)
Ad2 9.2568 10-6
.sec '
~
2.1963 10'#
2.9129 10-5 1
0.389 0.135
~
RCS Concentrations @ 0.5 Cl/gm =
C.5 :=
0.606 0
0.0848 O.326 YC961205.MCD
 
ERS-SFL-96-012 d
' Page 22 J
A := F E L
+
+1 d Where, F = purification system flow rate, E = purification efficiency, M = RCS mass, L = RCS leak rate, to = radioactive decay constant, A = loss,1/hr.
-2 6.8073 10 3.6585 10 '
~
-2 hr~ 1 A=
9.7805 10
~I 8.5515 10
-1 1.6935 10 i
The EPRI report provided the following expression for the appearance rate:
R.= (C.5 M Aj O
J-i i
Where, C = concentration, UCl/gm, R = eq. spike rate, Cl/sec. (The arrow operator directs Mathcad to treat this as an array operation). The equilibrium rates are given below:
~8 1.4049 10
~8 I
2.6204 10 Cl
-8 R=
3.1446 10
~8 3.8474 10 l
2.929 10~8 t
The concurrent iodine spike assumption is 500 x the equilibrium spike:
~I 7.0247 10 1.3102 S := R 500 S=
1.5723 sa 1.9237 5
1.4645 YC961205.MCD 4
1 o
 
ERS-SFL-96-012 Attachm:nt 3 Paos 23 NOTE: This case performed to confirm algorithm against previous values supplied by Westinghouse IODINE SPIKE MODEL -- Initial 1.0 uCi/gm @ Unit 2 The purpose of this sheet is to determine concurrent iodine spike appearance factors for reduced initial T/S activity. See text for derivation of formulae.
First, setup some unit conversions:
ORIGIN := 1 Cl := 3.710'0 sec' '
uCi := 1.010'8 Ci Assign some input parameters:
s RCS Mass =
M := 1.91 10 gm Purification Flow Rate =
F := 60 9" 1.0 9*
min cm Purification Efficiency (DF=10)=
E := 0.9 1.8 0.63 RCS Concentrations @ 1%FF Ci/gm =
C pp :=
2.9 0.39 1.5 The parameters above are from Westinghouse letter DMW-D-3050 (Attachment G to SWEC 12241-UR(B)-224)
RCS T/S Leakage =
L := 1.0 gat -0.72 gm min em' 9.9783 10'7 8.371310~ 5 Decay Constants (ERS-SFL-93-018)
).d:=
9.2568 10-8 sec" 2.196310'd 2.9129 10-5 1.49 10'3 1.43 10'8 DCF :=
2.69 10-4 RG1.109 Adult Thyroid Inhal DCFs=
3.73 10-8 5.6 10-s YC961206.MCD
 
~. _ _ -
ERS-SFL-96-012 Page 2 tj C pp DCF Del 131 :=
Del 131 = 2.387 uCi
: DCF, gm 7.541 10"I C pp 1.0 b 2.6393 10 '
~
C.0 :=
C 3'o =
1.2149 b
1 Del 131 gm 1.6339 10 '
~
6.2842 10''
EPRI Report, Review ofIodine Spike Data from PWR Power Plants in Relation to SGTR with MSLB, TR-103680, provided the following expression for lodine loss constant:
A := F E L
+ g+ A d Where, F = purification system flow rate, E = purification efficiency, M = RCS mass, L = RCS leak rate, ( = radioactive decay constant, A = loss,1/hr.
-2 6.8662 10 3.6644 10''
A=
9.8394 10"I hr' '
8.5574 10 '
~
1.6993 10~
The EPRI report provided the following expression for the appearance rate:
R := (C,94Aj 3
Where, C = concentration, uCl/gm, R = eq. spike rate, C
: c. (The arrow operator directs Mathcad to treat this as an array operation). The e rf rium r tes are given below:
~3 2.7471 10
~3 5.1313 10 R=
6.3424 10''
sec
-3 7.4181 10 YC961206.MCD
~
5.6658 10 s
 
. ~ _..
ERS-S FL-96-012
- Attachment 3 Pago 25 l
1.3735 l
2.5656 S := R 500 S=
3.1712.S 3.709 i
2.8329 1.36 2.52 S Westinghouse letter DMW-D-3050 provided the following values W :=
3.075 l
3.68 g ?.805 3
The difference (%) is:
' O.996' 1.811 diff :=
~
100-diff =
3.128 l
4 W
i 0.789 O.994 The differences are all less than 3% Based on trials calculating backwards from the Westinghouse results, the differences are nuclide specific, suggesting that Westinghouse may 1
used decay constants from another reference. The close correlation on 1-131 suggest that there may be differences in how Westinghouse ratioed the other Isotopes to obtain de I-131. TID 14844 and RG1.109 DCFs were used herein The RG1.109 values provided the closest fit.
.j YC961206.MCD l
 
1 s
1 4
I i
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4 i
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4 k
4 1
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Revision as of 13:32, 8 January 2025

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