ML20148T697

Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs

ML20148T697
Person / Time
Site:	Three Mile Island
Issue date:	09/11/1996
From:	Parfitt B GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20148T644	List: ML20148T680 ML20148T697 ML20148T736 ML20148T751
References
6612-96-023, 6612-96-023-R00, 6612-96-23, 6612-96-23-R, NUDOCS 9707090294
Download: ML20148T697 (5)

Text

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. s y Enclosure 4 NUCLEAN CalculatlOn Sheet Sob) set Calc. No, Rev. No.

ESTIMATED RM-G-22/23 READINGS WITH LOCA AT TS RCS 66t2-%023 0 LIMIT P & tember 6,19% f_,;) f._, ey),,)g

'Q t i

1. Problem Statement The reading on RM-G-22 and 23 during a LOCA at the Tech Spec RCS hu g estimated.

2 Results Summary Based on the assumptions made in this calculation, it is estimated that RM-G-22 and 23 will read approximately 22 R/hr dtIring a LOCA at the Tech Spec RCS limit.

~3. References 3.1 TMI ODCM 3.2 EPA 400 3.3 TDR 989 Rev 1, TMI-l Cycle 8 Reload ( The basis for FSAR Table 14.2-4).

4. Assumntions 4.1 The Tech Spec isotopic activity of the RCS was based on TS 3.1.4.3 which prevents operation when RCS dose equivalent iodine (DEI) is above 1 uCi/cc. The isotopic activities for RCS with 1% failed fuel in Reference 3.3 result in a DEI of 7.68 uCi/cc. To develop and RCS activity with a DEI of 1 uCi/ce, the isotopic activities in Reference 3.3 were divided by 7.68. The resulting mix has a DEI of I uCi/cc and is esemad to be the TS RCS activity.

4.2 The dose rate at the monitor was determined using dose factors for imme sion exposure in a uniform semi-infinite cloud. For noble gases, the gamma air dose factors in Referece 3.1 were used.

Gamma air dose factors were not available for the iodmes, so the TEDE dose factors from Reference 3.2 were used. This is conservative, since the gamma air dose factor would be expected to be higher than the TEDE dose factor.

3 4.3 , It is asmmad hat t the volume of the Reactor Building is 2.0E+6 ft and the volume of the RCS is 66,595 gallons.

4.4 It is assumed that the activity in the RCS is instantaneously released and dispersed into the Reactor Building when the LOCA occurs - .

0 9707090294 970701 PDR F ADOCK 05000289 PDR

. . 1 G;>u NUCLEAn Calculation Sheet Subject Calc. No. Rs v. No.  !

ESTIMATED RM-G-22/23 READINGS WITH LOCA AT TS RCS 6612 96-023 0 LIMIT i i

ortpmater Dese Revtewed by Date i PARFTIT September 6.19%

5. Data and Calculations 5.1 As discussed in Assumption 4.1, the factor used to convert 1% failed fuel to Tech Spec RCS activity I is calculated as follows:

FSAR 1% FF FSAR 1% FF RCS RCS i (SoTOPE ACTMTY DCF DEI i (uCug) (uCUg) h131 5.71E+00 1.48E+06 5.71E+00 b132 1.92E +00 5.35E+04 6.94E-02 L133 6.07E+00 4 00E+06 1.64E+00 b134 7.57E 01 3.73E+03 1.91E 03 k135 3.08E+00 124E+06 2.58E 01 TOTAL DEI 7.66E+00  !

DEI = (b137 ACTMTY)(b137 DCF) 6-131 DCF 5.2 The dose rate from each isotope at the monitor location is the product of the concentration (uCi/cc) and it dose conversion factor (mrad /hr/uCi/cc). The dose from each isotope is then summed to determme the total dose rate at the location. The calculation is summarized below:

ESTIMATED Rb" G-T! AND 23 DOSE RATE DURING LOCA AT TS RCS LIMIT RB VOLUME 2.00E+06 ft* .

, RCS VOLUME 66595 gal FSAR RMG-22/23 l 1% FF TS RCS RB RB DCF DOSE ,

RCS 1 uC1/cc DEI ISOTOPE ACTIVITY CONC MIEgg RATE (uCi/cc) (uCi/cc) (uCi) (uCi/cc) uCUcc (Redhr) 0.53 6.90E-02 KR43M 1.74E+07 3.07E-04 2.20E+03 6.77E-04 2.43 3.16E 01 KR45M 7.98E+07 1.41E-03 1.40E+05 1.98E 01 9.75 1.27E+00 KR45 3.20E+06 5.65E-03 1.96E+03 1.11E 02 1.28 1.67E-01 KR47 4.20E+07 7.42E-04 7.04E+05 5.22E 01

, 3.95 5.14E 01 KR48 1.30E+08 2.29E-03 1.73E+06 3.97E+00 2.88 3.49E-01 XE 1312 a.60E+07 1.55E 03 1.78E+04 2.77E 02 4.22 5.49E 01 XE 133M 1.39E+08 2.45E 03 3.73E+04 9.13E 02 392.00 5.10E+01 XE 133 1.29E+10 2 27E-01 4.03E+04 9.15E+00

. 0.49 6.32E 02 XE-135M 1.59E+07 2.81E-04 3.83E+05 1.08E.01 8.37 1.09E+00 XE 135 2.75E+08 4.85E 03 2.19E+05 1.06E+00 0.69 9.01E 02 XE-138 2.27E+07 4.01E 04 1.0$E+06 4.22E-01 '

5.71 7.43E 01 1-131 1.87E+08 '3.31E 03 2.20E+05 7.28E O'1.

1.92 2.50E 01 1-132 6.30E+07 1.11E-03 1.40E+06 . 1.56E+00 6.07 7.90E 01 1-133 1.99E+08 3.52E 03 3.50E+05 1.23E+00 0.76 9.86E 021-134 2.48E+07 4.39E44 1.60E+06 7.02E 01 3.08 4.01E 01 1-135 1.01E+08 1.79E 03 9.50E+05 1.70E+00 443.92 5.78E+01 TOTAL 21.5 4

- - . . . - . - - . ~ - . . . - . - - - . . - . . - - - . . _ . . . - - . . ~ . - - . - . . - . . - . . - . .

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! h TMi Radio 6ogical contmie Departmental Procedure 6610 PLN-4200.01

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1 Offsite Dose Calculation Manual (ODCM) 12 l l

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TABLE 4.3 i . i i Does Factors for Nolde Genes and De.cghters*

i-Gamma Beta i Total Body Sidn Does Gamma Air Beta Air I Does Factor (a) Factor (b) Does Factor Dose Factor  !

j Ki 1 5 Mi N, i

!- Radio- (mrom/yr per (rmm/yr per (mrad /yr, pet (mrad /yr per nuctide aci/mi act/m3 --.

acl/m; aci/mi Kr-83m 7.58E 02" -

1.93E + 01 2.00E+02 l

Kr-86m 1.17E + 03 1.46E + 03 1.23E + 03 1.97E +03 Kr 85 1.61 E +01 1.34E + 03 1.72E+01 1.96E + 03 g j i

Kr 47 5.9eE+03 9.73E +03 . 6.17E +03 1.03E + 04 Kr-88 1.47E + 04 '2.37E +03 1.52E +04 2.RBE +03 Krse 1.eeE +04 1.01E +04 1.73E +04 1.00E+04 Kr-90 1.50E+04 7.29E+03 1.SSE +04 7.83E +03

- Xe-131m 9.15E +01 4.7eE+02 1.5eE+02 1.11E+03 i Xe 133m 2.51E +02 k94E+02 3.27E+02 1.4aE +03 i'

Xe-133 2.94E + 02 3.00E +02 3.53E+02 1.06E+03 Xe-136m 3.12E +03 7.11E+02 3.3eE +03 7.30E +02 Xe-136 1.81E +03 1.seE+03 1.93E+03 '2.4eE+03 Xe-137 1.48E+03 1.22E +04 1.51E +0S 1.27E +04 Xe 138 8.83E +03 4.'13E + 03 9.21E +03 4.75E+03

]

Ar 41 8.44E+03 2.eeE +03 9.30E +03 3.2eE + 03  !

• Does factors are for immersion suposure in uniform somWnAnite doud of noble gas radionucHdes that may be I detected ingessous ofEueras. Does facnor values are taken from Regidplary Guide 1.100 (Rev.1), Table B 1. i "7.58E 02 = 7.56 x 10%

(a) Total body does factor for gemme pensastion depIh of 5 cm into the body ,

(b) Sidn does factor et a tissue depth or tissue donety thicknees of 7 mg/cm2, 120.0 .

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. N j Table 5-3 Dose Conversion Factors (DCF) and Derived Response Levels (D External Exposure Due to Immersion in Contaminated Air

< DCP DRL6 Radionuclide rem per pCicm'8 h pCi cm.a h H 0.0E+00 0.0E+00 C-14 0.0E+00

! Na 22 0.0E+00

" 1.3E+03 7.8E-04 Na-24 2.7E+03 i

P-32 3.7E-04 0.0E+00 0.0E+00

~

P-33 0.0E+00 I S-35 0.0E+00

! 0.0E+00 0.0E+00 Cl 36 4.8E-06 l K-40 2.1E+05 9.2E+01 1.1E-02 K-42 1.7E+02 6.0E-03

Ca-45 9.3E-09 1.1E+08 Sc-46 1.2E+03 Ti-44 8.4E-04

' 7.7E+01 1.3E-02 V-48 1.7E+03 i

Cr-51 5.8E-04 1.8E+01 5.6E-02 i '

Mn-54 5.0E+02 2.0E-03 Mn 56 1.1E+03 9.4E-04 Fe-55 1.3E-02 7.FE+01

' Fe-59 7.0E+02 .

1.4E-03 O. 58 5.8E+02 1.7E-03 Co-00 1.5E+03 6.7E-04 Mi 63 0.0E+00

0.0E+00

' Cu-64 1.1E+02 9.2E-03 Zn-65 ~ 3.4E+02 2.9E-03 Ge-68 5.2E-02

- 1.9E+01 Se-75 2.3E+02 4.4E-03 Kr-85 1.3E+00 7.8E-01 Kr-85m 9.3E+01 . .

1.1E-02 Kr-87 5.1E+02 2,0E-03 Kr-88 1.3E+03 7.8E44 5 25

. h%

l Table 5-3, Continued DCF* DRL' Radionuclide rem per pCi cm' h ,

pCi em' h

} Sb 126 1.6E+03 6.2E-04 Sb-127 3.9E+02 2.6E-03 Sb-129 8.6E+02 .1.2E-03 Te-127m 1.8E+00 5.6E-01 Te-129 3.1E+01 3.2E-02 l

Te-129m 2.0E+01 5.1E-02

! Te-131m '

8.5E+02 1.2E-03

Te-132 1.2E+02 8.0E-03 '

Te-134 5.1E+02 2.0E-03 I-125 6.3E+00 . 1.6E-01 I-129 4.8E+00 2.1E-01 I-131 2.2E+02 4.6E-03 I-132 1.4E+03 7.4E-04 I-133 3.5E+02 2.9E-03 I-134 1.6E+03 6.4E-04 i I-135 9.5E+02 1.1E-03 Xe-131m 4.9E+00 2.0E-01 Xe-133 2.0E+01 5.0E-02

~

Xe-133m 1.7E+01 5.9E-02 Xe-135 1.4E+02 7.0E-03 Xe-135m 2.5E+02 4.1E-03 Xe-137 1.1E+02 . 9.2E-03 Xe-138 7.1E+02 1.4E-03 Cs-134 9.1E+02 1.1E-03 Cs-136 1.3E+03 7.8E-04 Cs/Ba-137' 3.5E+02 2.9E-03 Cs-138 1.4E+03 6.9E-04 Ba-133 2.1E+02 ,

4.8E-03 Ba-139 2.1E+01 4.SE-02 Ba-140 '1.1E+02 9.3.E-03 5-27 4