ML17158C160

Rev 1 to EC-RADN-0531, Secondary Containment Isolation Setpoints.

ML17158C160
Person / Time
Site:	Susquehanna
Issue date:	05/23/1996
From:	Kalter C, Mackay T, Matchick D PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17158C159	List: ML17158C158 ML17158C160 ML18017A053 ML18017A291
References
EC-RADN-0531, EC-RADN-0531-R01, EC-RADN-531, EC-RADN-531-R1, NUDOCS 9705200151
Download: ML17158C160 (62)

Text

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Run time: 'l1:03 a.m. Checked:

CASEs Refueling Floor High Exhaust Duct Rad Honftor Response GEONETRY 7: Cylindrical source from side - cylindrical shields Distance to detector......... X 90.691 Source length................ L 609.6 Dose point height from base.. Y 304.8 Source cylinder radius....... T1 70.211 Thickness of second shield... T2 0.159 Hicroshield inserted air gap. air 20.321 Source Volune: 9.44063e+6 cubic centimeters HATER IAL DENSITIES (g/cc):

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Page 2 File: RFHEDRH2.MSH CASE: Refueling Floor High Exhaust Duct Rad Monitor Response BUiLDUP FACTOR based on TAYLOR method.

Using the characteristics of the materials in shield 1.

IHTEGRATiOH PARAMETERS:

Number of lateral angle segments (Htheta)..... 21 Nunber of azimuthal angle segments (Hpsi)..... 21 Nurher of radial segments (Hradius)........... 21 SOURCE NUCLlDES:

Nuclide Curies Nuclide Curies Huclide Curiae 1.131 3.7460e-03 i-132 5.1197e.04 i-133 9.9882e-04 1.134 0.0000e+00 i.135 1.1990e-04 Kr-83m 4.8081e-05 Kr-85 1.0281e-01 Kr-85m 1.4482e-03 Kr-87 1.1102e.07 Kr-88 2.8973e-04 Xe.131m 7.8168e 03 Xe-133 1.5360e+00 Xe.133m 2.8218e.02 Xe-135 4 '758e.01 Xe.135m 4.1123e-04 4

RESULTS!

Group Energy Activity Dose point flux Dose 'rate

¹ (Mev) (photons/sec) MeV/(sq cm)/sec (mr/hr) 1 2.4028 3.878e+06 3.811e+01 5.830e-02 2 2.0696 4.016e+06 3.425e+01 5.511e-02 3 1.3860 8.561e+06 4.942e+01 8.839e-02 4 1.0040 1.034e+07 4.434e+01 8.550e-02 5 .6932 9.250e+07 2.960e+02 6.099e-01 6 .5915 5.470e+08 1.576e+03 3.257e+00 7 .3778 2.102e+08 4.245e+02 8;726e-01 8 .2422 1.490e+10 1.994e+04 3.872e+0'1 9 .2004 2.051e+08 2.294e+02 4.232e-01 10 .1484 4.056e+07 3.444e+01 5.925e.02 11 12 13 14 15 16 17 18 19 20 TOTALS: 1.603e+10 2.266e+04 4.423e+01

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, CASE: Refueling Floor Wall Exhaust Duct Rad Honftor Response CEOHETRY 7: CylindricaL source from side - cylindrfcal shields Distance to detector....... .. ~ ~ X 99.083 Source length................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ L 609.6 Dose point hefght from base... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Y 304.8 Source cylinder radius. ~ ~ ~ ~ ~ ~ ~ ~ T1 78.603 Thickness of second shield.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ T2 0.159

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Page 2 FIle: RFNEORH2.HSN CASE: Refueling Floor Wall Exhaust guet Rad Honitor Response BUILOUP FACTOR: based on TAYLOR method.

Using the characteristics of the materials in shield 1.

INTEGRATION PARAHETERS:

Nwher of lateral angle segments (Ntheta)..... 21 Nwher of azimuthal angle segments (Npsi)..... 21 Nunber of radial segments (Nradius).........;. 21 SOURCE NUCLIOES:

Nuclide Curies Nuclide Curies Nuclide Curies e e 1-131 4.6951e.03 6.4167e-04 I.133 1.2519e.03 1-134 0.0000e+00 I 135 1.5027e-04 Kr-83m 6.0262e.05 Kr-85 1.2885e-01 Kr-85m 1.815 1e-03 Kr-87 1.3915e 07 Kr-88 3.5367e-02'.132 3.6314e-04 Xe-131m 9.7972e-03 Xe-133 1.9251e+00 Xe-133m Xe.135 5.6097e-01 Xe-135m 5.1542e.04 RESULTS:

Group Energy Activity Oose point flux Oose rate

¹ (HeV) (photons/sec) Hey/(sq cm)/sec (mr/hr) 1 2.4028 4.860e+06 4.337e+01 6.635e.02 2 2.0696 5.033e+06 3.8980401 6.272e-02 3 1.3860 1.073et07 5.624e+01 1.006e.01 4, 1 '040 1.296e+07 5.045e+01 9.729e-02 5 ~ 6932 1. 159e+08 3.368e+02 6.939e-01 6 .5915 6.856e+08 1.792u03 3.704e+00.

7 .3778 2.634e+08 4.829e+02 9.925e-01 8 .2422 1.868e+10 2.268e+04 4.405e+01 9 .2004 2.570e+08 2.610w02 4.815e.01 10 .1484 5.084e+07 3.920e+01 6.745 e-02 11 12 13 14 15 16 17 18 19 20 TOTALS: 2.009e+10 2.579e+04 5.032e+01 4

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Run time: 2:21 p.m. Checked:

CASE: Railroad Access Shaft Exhaust Duct Rad Honitor Response GEOHETRY 7: Cylindrical source from side - cylindricaL shields Distance to detector...... ~ .................. X 46.751 cme Source Length...... ... L 609.6 Dose point height from base.................. Y 304.8 Source cylinder radius............. Tl 26.271 Thickness of second shield......... ......... T2

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Sht ~<of Reviewed APPENDIX E Determination Of Secondary Containment Isolation

'etpoints For Post Power Uprate Conditions

PPQL Porm 2454 (10/83)

Cat.8973401 Dept.

Date ~~

Approved by~~ok 195~

PENNSYLVANIA POWER fc LIOHT COMPANif ER No She.~oe Reviewed The purpose of this Appendix is to evaluate secondary containment isolation setpoints for uprated power conditions. Isolation setpoints are evaluated using methods and models given in Appendices A, B, C and D and power uprate radiation source terms.

From Appendix A, the source term activity concentration for this setpoint analysis is the activity released for the realistic fuel handling accident divided by the refueling floor Zone IIIvolume of 7.56xl0" cm'. For uprated power, the activity released to the refueling Qoor for the realistic fuel handling accident is given in' Table 1 of SSES Calculation EC-RADN-1010 (Reference 11). Using this input data, the activity source terms for power uprate are evaluated in Table E-1. A comparison of the pre-power uprate and post-power uprate sources is also given in Table E-l.

Post-power uprate analytical setpoints for secondary containment isolation are evaluated for the Refueling'.

Floor High Exhaust, Refueling Floor Wall Exhaust and Railroad Access Shaft Exhaust radiation monitors..

The MICROSHIELD computer code is used to evaluate dose rates at the monitors resulting Rom the realistic basis fuel handling accident. The models for these radiation monitors are given in Appendices B, 4 and D ofthis calculation. Usmg these models and the post-power uprate sources given in Table E-l, calculated dose rates at the radiation monitors are given in the attached MICROSHIELD output files. These results are summarized below:.

Radiation Monitor Calculated Dose Ra'te/Analytical Setpoint For Realistic Basis Fuel Handling Accident (mr/hr)

Refueling Hoor High Exhaust 33.7 Refueling Hoor Wall Exhaust 38.3 Railroad Access Shaft Exhaust .9.4

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PENNSVLVAMTA ~WER fs LIGHT COXPAMT ER No, Date ~ag Q PROJECT sss.DMss hprcoveck by~+,~~ok Reviewed Table E-1 EVALUATIONOF REFUELING FLOOR ACTIVITYCONCENTRATIONS FOR FUEL HANDLING ACCIDENT FOR POWER UPRATE Prc-Power Uprate Post-Power Uprate ISOTOPE ActivityReleased 4'ctiVity ZonelH Released ZoneIH (Ci) Concentration (Ci) 44 Concentration (pCi/cc) (pCi/cc) 4'44 I-131 3.0 3.96&X 1.1244 I-132 4.1 5.423-5 10.98 1.4524 I-'133 1.0584 8.8 1.168M I-134 I-134 .96 1.270-5 1.4 1.851-5 KR-83m .385 5.0934 2,5 3.300-5 Kr-85m 11.6 1.5344 32.5 4.299M Kr-85 823. 1.089-2 7.8044 Kr-87 8.894 1.176-8 5.05-3 6.680-8 Kr-88 2.32 3.069-5 9.424 1.247M Kr-89 8.2804

'0.89 Xe-131m 62.6 2.989-3 4.0&64 Xe-133m 22.6 1.627-1 409. 5.410-3 Xe-133 4.741-2 10440. 1.386-1 Xe-135, 3584. 4.356-5 2392. 3.164-2 Xe-135m 3.3 124.5 1.646-3 Xe-137 Xe-138 0 Pre-power upratc sources are evaluated in Appendix A.

Post-power upratc activity released is obtained &om Table I of Calculation EC-RADN-1010 (Reference 11)

The activity concentration is thc activity released divided by the Zone HI volume of 7.56x10'4 cm'.

Microshield 3.12 (PENNSYLVANIA POWER &, LIGHT- 5138) gRun 1

RFHEPOST'.MSH date: May 22, 1996 File Ref:

Date:

By:

Run time: 7:10 p.m. Checked:

CASE: Refueling Floor High Exhaust Duct Rad Monitor POSTPU SRC GEOMETRY 7: Cylindrical'source from side - cylindrical shields Distance to detector........... X 90.691 cm.

length..................

~ ~ 0 Source ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . L 609.6 II Dose point height from base.... Y. 304.8 cylinder radius.........

"'1 Source 70.211 Thickness of second shield..... T2 0.159 Microshield inserted air gap... ~ ~ ~ air 20.321 Source Volume: 9.44064e+6 cubic centimeters MATERIAL DENSITIES (g/cc):

Material Source Shield 2 Air gap Air .001220 .001220 Aluminum Carbon oncrete drogen on 7.860 ~ ~

Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium.

Water Zirconium

~ pose v,~~-oQQ) sq Microshield 3.12 MMM Z5 M (PENNSYLVANIA POWER R LIGHT - 0138)

Page .  : 1 File Ref:

File  : RFWEPOST.MSH Date:

Run date: May= 22,: 1996 BY:

Run time: 7:09: p.m. Checked:

CASE: Refueling'loor Wall Exhaust Duct Rad Monitor POST PU GEOMETRY 7: Cylindrical source from side - cylindrical shields Distance to detector........ t t X 99.083 length.......;.......

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Source ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ L 609.6 Dose point height from base. ~ ~ t ~ ~ ~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~ Y 304.8 Source cylinder radius...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ T1 78.603 Thickness of second shield.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ T2 0.159 Microshield inserted air gap ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ air 20.321 Source Volume: 1'.18323e+7 cubic centimeters MATERIAL DENSITIES (g/cc):

Material Source Shield 2 Air gap Air .001220 .001220 Aluminum Carbon Concrete Hydrogen Iron 7.860 Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium Water Zirconium

'V

~l" -Who~- o %~4 e~ ~>.

Page 2 Pile: RFWEPOST.MSH CASE'= RefueEing Floor Wall Exhaust Duct Rad Monitor POST PU BUILDUP PACTOR: based oa TAXLOR method.

Using the characteristics. of the materials in shield 1.

INTEGRATION PARAMETERS:

Number of lateral angle segments (Ntheta)..... 21 Number of azimuthal angle segments (Npsi)..... 21 Number of radial segments (Nradius)........... 21 SOURCE NUCLIDES:

Nuclide Curies Nuclide Curies Nuclide Curies .

I-131 1.3300e-03 I-132 1.7181e-03 I-133 1.3820e-03 I-134 0.0000e+00 I-135 2.1902e-04 Kr-83m 3.9047e-04 Kr-85 9.2340e-03 Kr-85m 5.0867e-03 Kr-87 7.9040e-07 Kr-88 1.4755e-03 Xe-131m 4.8347e-03 Xe-133 1.6340e+00 Xe-133m 6.4013e-02 Xe-135 3.7438e-01 Xe-135m 1.9476e-02 RESULTS:

Group Energy Activity Dose point flux Dose rate I (MeV) (photons/sec) MeV/(sq cm)/sec (mr/hr)

.1 2.4028 1.956e+07 1.745e+02 2.670e-01 2 2.1062 1.738e+07 1.368e+02 2.186e-01 3 1.4111 2.569e+07 1.369e+02 2.438e-01 1.0113 2.944e+07 1.154e+02 2.222e-01 5 .7091 1.838e+08 5.423e+02 1.113e+00 6 .5534 1.049e+09 2.630e+03 5.412e+00 7 .3828 1.244e+08 2.307e+02 4.741e-01 8 .2423 1.248e+10 1.517e+04 2. 945e+01 9 .2113 3.467e+08 3.703e+02 6.925e-01 10 .1484 1.425e+08 1.099e+02 1.891e-01 11 12 13 14 15 16 17 18 19

.20 TOTALS: 1.442e+10 1.961e+04 3 . 829e+01

~-Qp5N- o5$ 4 Wasc Page; 2 .File: RASPOSTP.MSH CASH: Railroad" Access Shaft Duct Rad Monitor - POST PWRUP SOURCE

~ ~ ~ %~

4

.:.=.-,=.,:- BUILDUP FACTOR: based on TAYLOR method.'-

Vsing-.the characteristics of the materials in shield 1.

INTEGRATION PARAMETERS:

Number of lateral angle segments (Ntheta)..... 21 Number of azimuthal angle segments (Npsi)..... 21 Number of radial segments (Nradius)........... 21 SOURCE NUCLIDES:

Nuclide Curies Nuclide Curies Nuclide Curies I-131 1.4857e-04 I-3.32 1.9192e-04 I-133 1.5438e-04 I-134 '0.0000e+00 I-135 2.4466e-05 Kr-83m 4.3618e-05 Kr-85 1.0315e-03 Kr-85m 5.6823e-04 Kr-87 8.8294e-08 Kr-88 1.6482e-04 Xe-131m 5.4007e-04 Xe-133 1.8254e-01 Xe-133m 7.1508e-03 Xe-135 4.1821e-02 Xe-135m 2.1756e-03 RESULTS:

Group Energy Activity Dose point flux Dose rate

¹ (MeV) (photons/sec) MeV/(sq cm)/sec (mr/hr) 1 2.4028 2.184e+06 4.271e+01 6.533e-02 2 2.1062 1.941e+06 3.349e+01 5.352e-02

'3 1.4111 2.870e+06 3.352e+01 . 5.968e-02 4 1.0113 3.289e+06 2.826e+01 5.442e-02 S.' ~

.7091 .2.053e+07 1.331e+02" 2.733e-01 6: ;5534 1. 172e+08 6;468e+02. '1.331e+00

-. 7: .3828 1.389e+07,. 5.673e+01 ~

1.166a-01 8 . , .2423 '1;395e+09 3.715e+03 7.216e+00 9i .2113 3;873 e+07 9.060e+01 1.694e-01 10, '1484 1.592e+07 2.671e+01 4.595e-02 11 12 13 14 15 16 17.

18 19 20 TOTALS: 1.611e+09 4. 807ei03 9.385e+00