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: ML17158C160 ML18017A053 ML18017A291 PLA-4607, Forwards Response to 970212 RAI Re Proposed TS Amend for Secondary Containment Isolation Radiation Monitor Setpoints. Calculations Encl for Review
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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2. TYPE:

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EC-N -o

%4 REVISION

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5. TRANSMITTAL¹+~654~ 'I'6. UNIT:~ '%7. QUALITYCLASS:

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'2'6. DISCIPLINE:

>9. DESCRIPTION:

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10. Alternate Number:

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13. Application:

"~14 Affected Systems:

IfN/A then line 15 is mandatory.

r15. NON-SYSTEM DESIGNATOR:

KA,O'4

16. Affected Documents:

SUPERSEDED BY:

EC-

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23. ACCEPTED BY PP&L/DATE Print Name Si nature Prfnt Name Si nature NR-DCS SIGNATURE/DAT TO BE COMPLETED BY NUCLEARRKCOROS ADDA NEW COVER PAGE FOR EACH REVISION FORM NEPM~%221-t

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ENGINEERING CAI CULATIONSTUDY REVISION DESCRIPTION SHEET REVISiON NO:

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¹138}

File Ref:

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Checked:

CASEs Refueling Floor High Exhaust Duct Rad Honftor Response GEONETRY 7: Cylindrical source from side - cylindrical shields Distance to detector.........

Source length................

Dose point height from base..

Source cylinder radius.......

Thickness of second shield...

Hicroshield inserted air gap.

X L

Y T1 T2 air 90.691 609.6 304.8 70.211 0.159 20.321 Naterial 0

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.001220

.001220 7.860 Source Volune: 9.44063e+6 cubic centimeters HATERIAL DENSITIES (g/cc):

Source Shield 2 Air gap

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).....

Nunber of azimuthal angle segments (Hpsi).....

Nurher of radial segments (Hradius)...........

21 21 21 SOURCE NUCLlDES:

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

i-133 Kr-83m Kr-87 Xe-133 Xe.135m 9.9882e-04 4.8081e-05 1.1102e.07 1.5360e+00 4.1123e-04 RESULTS!

Group

¹ 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 Energy (Mev) 2.4028 2.0696 1.3860 1.0040

.6932

.5915

.3778

.2422

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.1484 Activity (photons/sec) 3.878e+06 4.016e+06 8.561e+06 1.034e+07 9.250e+07 5.470e+08 2.102e+08 1.490e+10 2.051e+08 4.056e+07 Dose point flux MeV/(sq cm)/sec 3.811e+01 3.425e+01 4.942e+01 4.434e+01 2.960e+02 1.576e+03 4.245e+02 1.994e+04 2.294e+02 3.444e+01 Dose 'rate (mr/hr) 5.830e-02 5.511e-02 8.839e-02 8.550e-02 6.099e-01 3.257e+00 8;726e-01 3.872e+0'1 4.232e-01 5.925e.02 TOTALS:

1.603e+10 2.266e+04 4.423e+01

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RFWEDRH2.NSH September 24, 1992 12l05 p.m.

- ¹138)

File Ref:

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Checked:

f2-D5g OOZ CASE: Refueling Floor Wall Exhaust Duct Rad Honftor Response CEOHETRY 7: CylindricaL source from side - cylindrfcal shields Distance to detector.......

Source length.................

Dose point hefght from base...

Source cylinder radius.

Thickness of second shield....

,Hicroshfeld inserted air gap..

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~ 001220

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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.

0%- 92 DAO-007

'7+ '

INTEGRATION PARAHETERS:

Nwher of lateral angle segments (Ntheta).....

21 Nwher of azimuthal angle segments (Npsi).....

21 Nunber of radial segments (Nradius).........;.

21 Nuclide Curies SOURCE NUCLIOES:

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

e 1.2519e.03 6.0262e.05 1.3915e 07 1.9251e+00 5.1542e.04 RESULTS:

Group

¹ Energy Activity (HeV)

(photons/sec)

Oose point flux Hey/(sq cm)/sec Oose rate (mr/hr) 1 2

3 4,

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 2.4028 2.0696 1.3860 1 '040

~6932

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.1484 4.860e+06 5.033e+06 1.073et07 1.296e+07

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9.925e-01 4.405e+01 4.815e.01 6.745 e-02 TOTALS:

2.009e+10 2.579e+04 5.032e+01 4

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¹138) elle Rel:

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Checked:

CASE: Railroad Access Shaft Exhaust Duct Rad Honitor Response GEOHETRY 7: Cylindrical source from side - cylindricaL shields Distance to detector......

~..................

Source Length.........

Dose point height from base..................

Source cylinder radius.............

Thickness of second shield.........

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Hicroshield inserted air gap.................

X L

Y Tl T2 air 46.751 609.6 304.8 26.271 0.159 20.321 cme Haterfal 0

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\\

1.061e+01 9.542 e+00 7.377e+07 1.23de+01 8.267e+07 4.40de+02

1. 787e+02 S.SS To+03 6.384 e+01 9.528e+00 Dose rete (er/br) 1.624 e.02 1.53Se-02 2.4d2e 02 2.383e.02 1.703e.07 9.10Se-01 2.440e-01 7.079m'07 1.7T8e-07 7.639e.02 TOTAL,gt

.2.244 F09 6.319e+03 7.233m07

PP&L Form 2454 (10/B3)

Cat.4973401 Dept.

Date~~ 19'5 hppeoved by Reviewed PROJECT Sht ~<of PENNSYLVANIA POWER rc LZOHT COMPANY ER No.

APPENDIX E Determination OfSecondary Containment Isolation

'etpoints For Post Power Uprate Conditions

PPQL Porm 2454 (10/83)

Cat.8973401 Dept.

PENNSYLVANIA POWER fc LIOHT COMPANif Date~~ 195~

Approved by~~ok Reviewed ER No She.~oe The purpose ofthis 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 floorZone IIIvolume of7.56xl0" cm'. For uprated power, the activity released to the refueling Qoor for the realistic fuel handling accident is given in' Table 1 ofSSES Calculation EC-RADN-1010 (Reference 11). Using this input data, the activity source terms for power uprate are evaluated in Table E-1. Acomparison ofthe 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 MICROSHIELDcomputer 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 MICROSHIELDoutput files. These results are summarized below:.

Radiation Monitor Refueling Hoor High Exhaust Refueling Hoor Wall Exhaust Railroad Access Shaft Exhaust Calculated Dose Ra'te/Analytical Setpoint For Realistic Basis Fuel Handling Accident (mr/hr) 33.7 38.3

.9.4

PPfrh Iona 24S4 {10/83)

Cat. t97340l

)

Der's Date ~ag Q hprcoveck by~+,~~ok Reviewed PENNSVLVAMTA~WER fs LIGHT COXPAMT PROJECT ER No, sss.DMss Table E-1 EVALUATIONOF REFUELING FLOOR ACTIVITYCONCENTRATIONS FOR FUELHANDLING ACCIDENTFOR POWER UPRATE ISOTOPE ActivityReleased (Ci)

ZonelH Concentration (pCi/cc)

Prc-Power Uprate4'ctiVityReleased (Ci) 44 ZoneIH Concentration (pCi/cc) 4'44 Post-Power Uprate I-131 I-132 I-'133 I-134 I-134 KR-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135, Xe-135m Xe-137 Xe-138 3.0 4.1

.96

.385 11.6 823.

8.894 2.32 62.6 22.6 3584.

3.3 0

3.96&X 5.423-5 1.0584 1.270-5 5.0934 1.5344 1.089-2 1.176-8 3.069-5 8.2804 2.989-3 1.627-1 4.741-2 4.356-5 10.98 8.8 1.4 2,5 32.5 5.05-3 9.424

'0.89 409.

10440.

2392.

124.5 1.1244 1.4524 1.168M 1.851-5 3.300-5 4.299M 7.8044 6.680-8 1.247M 4.0&64 5.410-3 1.386-1 3.164-2 1.646-3 Pre-power upratc sources are evaluated in Appendix A.

Post-power upratc activityreleased is obtained &omTable I ofCalculation EC-RADN-1010 (Reference 11)

The activityconcentration is thc activityreleased divided by the Zone HIvolume of7.56x10'4 cm'.

g Run date:

Run time:

CASE:

Microshield 3.12 (PENNSYLVANIA POWER

&, LIGHT-1 RFHEPOST'.MSH May 22, 1996 7:10 p.m.

Refueling Floor High Exhaust Duct Rad 5138)File Ref:

Date:

By:

Checked:

Monitor POSTPU SRC GEOMETRY 7: Cylindrical'source from side - cylindrical shields Distance to detector...........

Source length..................

Dose point height from base....

Source cylinder radius.........

Thickness of second shield.....

Microshield inserted air gap...

~

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"'1 T2

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~ air 90.691 609.6 304.8 70.211 0.159 20.321 cm.

II Source Volume: 9.44064e+6 cubic centimeters MATERIAL DENSITIES (g/cc):

Material Air Aluminum Carbon oncrete drogen on Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium.

Water Zirconium Source Shield 2

.001220 7.860 Air gap

.001220

~

~

Microshield 3.12 MMMZ5 M (PENNSYLVANIA POWER R LIGHT Page 1

File RFWEPOST.MSH Run date:

May= 22,: 1996 Run time: 7:09: p.m.

CASE: Refueling'loor Wall Exhaust Duct

~ v,~~-oQQ) pose sq

- 0138)File Ref:

Date:

BY:

Checked:

Rad Monitor POST PU GEOMETRY 7: Cylindrical source from side - cylindrical shields Distance to detector........

Source length.......;.......

Dose point height from base.

Source cylinder radius......

Thickness of second shield..

Microshield inserted air gap

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T1 T2air 99.083 609.6 304.8 78.603 0.159 20.321 Source Volume: 1'.18323e+7 cubic centimeters MATERIAL DENSITIES (g/cc):

Material Air Aluminum Carbon Concrete Hydrogen Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium

, Water Zirconium Source Shield 2

.001220 7.860 Air gap

.001220

'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).....

Number of azimuthal angle segments (Npsi).....

Number of radial segments (Nradius)...........

21 21 21 SOURCE NUCLIDES:

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

Group I

.1 2

3 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19

.20 Energy (MeV) 2.4028 2.1062 1.4111 1.0113

.7091

.5534

.3828

.2423

.2113

.1484 TOTALS:

Activity (photons/sec) 1.956e+07 1.738e+07 2.569e+07 2.944e+07 1.838e+08 1.049e+09 1.244e+08 1.248e+10 3.467e+08 1.425e+08 1.442e+10 Dose point flux MeV/(sq cm)/sec 1.745e+02 1.368e+02 1.369e+02 1.154e+02 5.423e+02 2.630e+03 2.307e+02 1.517e+04 3.703e+02 1.099e+02 1.961e+04 Dose rate (mr/hr) 2.670e-01 2.186e-01 2.438e-01 2.222e-01 1.113e+00 5.412e+00 4.741e-01

2. 945e+01 6.925e-01 1.891e-01 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).....

Number of azimuthal angle segments (Npsi).....

Number of radial segments (Nradius)...........

21 21 21 SOURCE NUCLIDES:

Nuclide I-131 I-134 Kr-85 Kr-88 Xe-133m Curies 1.4857e-04

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

Group

¹ 1

2'3 4S.'

6:

-. 7:

8 9 i 10, 11 12 13 14 15 16 17.

18 19 20 Energy (MeV) 2.4028 2.1062 1.4111 1.0113

~.7091

5534

.3828

,.2423

.2113

'1484 Activity (photons/sec) 2.184e+06 1.941e+06 2.870e+06 3.289e+06

.2.053e+07

1. 172e+08 1.389e+07,.

'1;395e+09 3;873 e+07 1.592e+07 Dose point flux MeV/(sq cm)/sec 4.271e+01 3.349e+01 3.352e+01 2.826e+01 1.331e+02" 6;468e+02.

5.673e+01

~

3.715e+03 9.060e+01 2.671e+01 Dose rate (mr/hr) 6.533e-02 5.352e-02

. 5.968e-02 5.442e-02 2.733e-01

'1.331e+00 1.166a-01 7.216e+00 1.694e-01 4.595e-02 TOTALS:

1.611e+09

4. 807ei03 9.385e+00