ML20092P678

TMI-1,Post-Accident Containment Atmosphere Sampling Radiological Analysis

ML20092P678
Person / Time
Site:	Three Mile Island
Issue date:	06/04/1984
From:	Mahgerefteh M GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20092P672	List: ML20092P676 ML20092P678
References
TDR-529, TDR-529-R, TDR-529-R00, NUDOCS 8407090246
Download: ML20092P678 (26)

Text

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ATTACMNr 3 TDR NO. 529 REVWNNINo. O suooET i TECHNICAL DATA REPORT ACTIVITY NO. 412032 PAgg i op 2/ j PROJECT:

DEPARTMENT /SECTION r . els )

i RELEASE DATE REVISION DATE I DOCUMENT TITLE:

TMI-1; Post Accident Containment Atmosphere Sampling Radiological Analysis l l

ORIGINATOR SIGNATURE DATE APPROVAL (S) SIGNATURE DATE l blatUd b/rh/,d/$,

5l$Nlf4 ,8 N! W -

S'ESN i l l

APPROVAL FOR EXTERNAL DISTRIBUTION DATE

]'W W (,-4 84 Does this TDR include recommendation (s)? Ove 5 No if yee. TFWR/TR #

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• DISTRIBUTION ABSTRACT:

This report evaluates the radiological condition, and its G. R. Bond compliance with IiUREG-0737, of the existing TMI-l nuclear T. G. Broughton sampling facility for obtaining and analyzing the Post T. Y. Byoun Accident Contain=ent Building atmosphere sample, f- D. K. Croneberger J. P. Donnachie (T:'I Personnel exposure during the post accident containment L. W. Harding atmosphere sampling activities is evaluated.

1. J. W. Langenbach J. D. Luoma FISULTS A iD CO:ICLUSIO:IS M. :'ahgerefteh R. P. Shaw (TMI) The existing sampling system is in compliance with the limits J. D. Snell set by liUP2G-0737.

J. A. Tangen K P. S. Walsh The radiation exposure to personnel during the sampling J. Wetmore activities are:

R. F. Wilso= BOM MEUU R. J. Toole (T:C) h'

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With Hydrogen Recombiners 1.1 1.7 l Contribution i

Without Hydrogen Reco=biners 0.6 1.7 These "esults demonstrate that TMI-l Containment Atmosphere Sampling System is in compliance with ITUPIG-0737 limits of 5 Re= whole body and 75 Re= extremity.

8407090246 840702 PDR ADOCK 05000289 G PDR oCOVPR PAGE ONLy 4o000o30 4.s3

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TDR No. 529 Re v. O Page 2 of 26 4

99EE WORK PAGE ON HOW TO RUN THIS JOB AND PLEASE KEEP UPDATED TABLE OF CONTENTS Page

1.0 INTRODUCTION

................................................. 4 2.0 METHODS AND DATA............................................. 5 2.1 Source Terms............................................ 5 2.2 Dose Acceptance Criteria................................ 6 2.3 Post Accident Containment Sampling Activity Scenario.... 8 2.4 Radioactive Exposure to Personnel While Sampling. . . . . . . . 10 2.4.1 Dose Rate Due to Airborne Activity from the Co nt a i nm e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.4.2 Dose Rate Due to Containment Direct Shine........ 11 2.4.3 Dose Rate Due to All Piping in the Sample ' Room. . . 12 2.4.4 Dose Rate Due to the Sample Bomb................. 13 2.4.5 Dose Rate Due to the Sample Syringe. . . . . . . . . . . . . . 13 2.4.6 Dos e Rate Due to the Hydrogen Recombiners. . . . . . . . 14 2.4.7 Radiation Exposure During ' Sample Analyses. . . . . . . . 16-2.5 Dose Received by Personnel During Post-Accident Activities.............................J ................. 17 3.0

SUMMARY

AND RESULTS.......................................... 18 l

4.0 REFERENCES

...................................................(19 i

r TDR No. 529 Re v . O Page 3 o f 26 LIST OF TABLES Page Table 1 Source Terms............................................. 7 Table 2. Dose Rate Due to the Sample Station Piping.............. 23 Table 3. Dose Rate Due to Containment Shine...................... 24 Table 4. Dose Rate Due to the Sample Syringe...................... 24 Table 5. Dose Rate Due to the Sample Bomb......................... 24 Table 6 Dose Rate Due to the Hydrogen Recombiner................. 24 Table 7. Radioactive Exposure During Post-Accident Sampling......

25 List of Figures Figure 1. Sample Control Panel and Sample Room Location. . . . . . . . . . . . 20 Figure 2. CATPASS Sample Room Piping.............................. 21 Figure 3 Hydrogen Recombiner System............................... 22 I

s TDR No. 529 Rev. O Page 4 of 26

1. INTRODUCTION The purpose of this TDR is to evaluate radiaton exposures during a post accident containment atmosphere sampling utilizing existing TMI-l facilities. The f acilities to be examined are the containment atmosphere sample station (located in the intermediate building) and the counting room. Based on time-and-motion data during the post accident condition, the personnel radiation exposure for compliance with the radiation criteria set by NUREG 0737, II B.3 is evaluated.

NRC requires the licensee to have the capability to promptly obtain (within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) a containment atmosphere sample under accident conditions without incurring a radiation exposure to any individual in excess of 5 rem whole body and 75 rem extremity.

The radiation source term data used in this report are the same as those stipulated in Regulatory Guides 1.3 and 1.4. Radiation' dose rates are analyzed by using the computer code ISOSHLD-II (Ref. 1), which employs a point kernel integration method.

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Rev. 6 l Page 5 of 26  !

2.0 METHODS AND DATA a

2.1 Source Terms An isotopic core inventory for 310 effective full power days in an equilibrium cycle with a power level of 2552 MWt was utilized for the development of the source terms (Ref. 2). The source terms are presented in Table 1. This inventory is conserva-tive for the use of the present study because the TMI-l rated core power level is 2535 MWt.

The activity assumed for the containment atmosphere source term calculations is based on 100% of the noble gas core inventory and 25% of the halogen core inventory (in accordance with Regulatory Guide 1.3 or 1.4). The containment source term is shown in Table 1.

Table 1 presents the containment activity concentra-tion for the time period immediately after a postulated accident.

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t TDR No. 529 I

. Rev. 0 l Page 6 of 26 The. free volume of the containment is 2x10 6 cubic feet.

In this report the source at T=30 min was used.

2.2 Dose Acceptance Criteria 1 Criterion of GDC19, Appendix A, 10CFR Part 50 requires that radiation protection be provided such that the dose to personnel should not be in excess of .

5 rem Whole Body 75 rem Extremities 9

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TDR No. 529 Rev. O Page 7 of 26 Table la Source Terms Containment Airborne Isotope Decay Constant Source Activity (1,2) Concentration (sECi/cc)

(1/Sec) Ci T=o T=30 min.

Br-84 0.360-3(3) 3.93 + 6 6.94 + 1 3.63 + 1 Kr-83m 0.101-3 9.26 + 6 1.63 + 2 1.36 + 2

-85m 0.437-4 2.19 + 7 3.8 7 + 2 3.58 + 2

-85 0.438-4 5.30 + 5 9.3 6 + 0 8.65 + 0

-87 0.152-3 4.00 + 7 7.06 + 2 5. 3 7 + 2

-88 0.686-4 5.60 + 7 9.89 + 2 8.74 + 2 Xe-131m 0.668-6 4. 3 8 + 5 7.73 + 0 7.73 + 0

-133m 0.348-5 3.07 + 6 , 5.42 + 1 5.39 + 1

-133 0.151-5 1.27 + 8 2.24 + 3 2.23 + 3

-135m 0.743-3 3.26 + 7 5.76 + 2 1.51 + 2

-135 0.209-4 2.09 + 7 3.69 + 2 3.5 5 + 2

-138 0.296-2 1.17 + 8 2.07 + 3 1.00 + 1 I-131 0.997-6 1.84 + 7 3.25 + 2 3.24 + 2

-132 0.832-4 2.16 + 7 3.81 + 2 3.2 9 + 2

-133 0.917-5 3.20 + 7 5.6 5 + 2 5.56 + 2

-134 0.218-3 4.00 + 7 7.06 + 2 4.77 + 2

-135 0.287-4 3.18 + 7 5.62 + 2 5.61 + 2

1) Based on 100% noble gas core inventory and 254 ha.1. ogen core inventory

2) See Ref. 2 ,

3) Read as 0.36 x 10-3 l

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. o TDR No. 529 Re v. O Page 8 of 26 2.3 Post Accident Containment Sampling Activity Scenario The following represents the time and motion scenario for the activities of the personnel performing the containment atmosphere sampling.

Figure 1 shows the location of the remote sample panel, air station, sample station and the heat trace switch in the intermediate building.

1 Three min and thirty sec. from Lab to the sample panel.

2. Forty sec. at the air station (The air station is located in the remote sample panel room).

3. Six min. and fifty sec. at the remote sample panel.

4. Ten sec. total to turn the heat trace switch on and off.

5. Three min. and forty-five sec. from the sample panel to the Lab.*

6. Three min. and thirty sec. from the' Lab to the l sample panel.* i l

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r TDR No. 529 Re v. O Page 9 o f 26

7. Six min, and forty sec. at the sample station

( for 45 sec. of which the sample panel piping is filled with the containment atmosphere and the personnel is standing 3 feet away from the piping).

8. Fifteen sec. holding the sample bomb with one hand (in a kneeling position) .

9. Fif teen sec. holding the syringe with both hands (in a kneeling position) .

10. Fifteen sec. holding the syringe with one hand to place in shield (in a kneeling position) .

11. Five min, stay time in general area for mis-cellaneous tasks (for example filling out-procedure).

• While enroute from Lab to the sample panel or vice versa the personnel pass by the hydrogen recombiner for a period of 30 sec each way for each trip.

TDR No. 529 Re v. O Page 10 of 26

12. Three min. and forty-five sec. from the sample panel to the lab.

2.4 Radioactive Exposure to the Personnel While Sampling Figure 2 shows the containment atmosphere sample piping . The sample bomb in Figure 2 is a 40 cc container with 9/16 inch and 2-5/8 inch inside diameter and height respectively. During sample removal a 5 cc syringe is used to extract 3 cc of containment sample from the sample bomb.

2.4.1 Dose Rate Due to the Airborne From the Containment.

Technicians are expected to follow plant procedure for protective respirator requirements (RCP-1613) to reduce inhalation doses during the sampling.

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TDR No. 529 Re v. O Page 11 of 26 According to GPU calculation (Ref. 5), the maximum exposure due to the airborne activity in the vicinity of the containment is 200 aren/hr. This was based on Atmospheric Dilution Factor (I/QL ) of 3.44 x 10-3 ,,cj,3 with wind speed of 0.782 m/sec and Pasquill Type of "F" con- ,

dition.

2.4.2 Dose Rate Due to the Containment Direct Shine.

Table 3 presents the dose rate due to the direct shine from the containment at dif-ferent distances from the surface of con-tainment. These results were based on 100%

noble gas and 254 halogen core inventory release and homogenous distribution in the containment free volume. Table 3 shows the dose rate from the containment direct shine with 42 inches of concrete shielding (which is the thickness of the containment wall Ref. 3) and 66 inches of concrete shielding

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TDR No. 529

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Rev. O Page 12 of 26 (for additional wall thickness when there are other walls between the receptor and the containment wall). In this study for the direct shine from the the containment, dose rate of 2.29 res/hr is used when the technician is in the sample room or heat trace switch room whereas a dose rate of 5 ares /hr is used for all other locations.

2.4.3 Dose Rate Due to All Piping in the Sample Room.

Figure 2 shows the general arrangement of the containment post accider.t sample piping in the sample room. The outside diameter of ,this piping is either 1/2 or 1/4 inch.

The analysis conservatively assumed _that the entire radius of the piping.is filled with containment post accident atmosphere with no credit for piping _ wall thickness shielding. The dose rates due to this piping at different distances are. presented in Table 2.

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TDR No. 529 Rev. O Page 13 of 26 2.4.4 Dose Rate Due to the Sample Bomb.

The sample bomb is a 40 cc container which contains the containment atmosphere for sample removal. Dose rates due to the sample bomb at different distances from the sample bomb surface are computed and pre-sented in Table 5.

Design modification to remove the sample bomb and installation ot small cask at the low point of the piping is recommended by TDR 494 Rev. 2 (Ref. 4). This recommendation is Deing implemented at the plant. Implementation of this modification ,

in the containment atmosphere sample system will decrease the total radiation exposure by the dose contribution of the sample bomb.

2.4.5 Dose Rate Due to the Sample Syringe.

Sample syringe is a 5 cc container which is used to withdraw 3 cc of the containment atmospnere sample from the sample bomb for

TDR No . 52 9 l Rev. O  :

Page 14 of 26 -

l l post accident sampling and analysis. The l dose rates due to the sample syringe both unshielded and with 1/8 inch lead shielding are computed and are presented in Table 4.

2.4.6 Dose Rate Due to the Hydrogen Recombiner The hydrogen recombiner is a device which is used to decrease the containment hydro-l gen concentration during high level hydro-t i gen generation in the containment. This is accomplished by drawing the containment ,

l atmosphere and heating it to a high temper-

! ature at which free hydrogen is recombined with oxygen to form water vapor. The gas l

l and water vapor are then cooled and re-l turned to the contair. ment (Ref. 6).

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TDR No. 529 Re v. O Page 15 of 26 In order to compute the dose contribution from the hydrogen recombiners to the per-l l sonnel while enroute to conduct the con-l tainment post accident sampling the recombiner is divided into two parts (see

! Figure 3), these ares i

1) Radiation source contained within the seven inch thick steel well.

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2) Radiation source external to the vessel well.

The dose rate due to each part of the hy-drogen recombiner at dif ferent distance j from the vessel surface are computed and presented in Table 6. In this analysis it is conservatively assumed that both re-combiners (HRRIA and HRR1B) are operating and the distance of the technician from the HRRIA and HRRIB recombiners, is 10 and 20 feet, respectively, while in transit.

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TDR No. 529 Rev. 0 -

Page 16 of 26 2.4.7 Radiation Exposure During Sample Analyses The containment atmosphere sample analyses consists of: (1) Gamma scan analyis, and (2) Hydrogen analysis. The total radiation exposure during this time will be approximately .072 rem whole body dose and 0.92 rem extremities. Details of these results are given below.

Radiation source Exposure Work and Dose Rate Per Activity Description Stay Time ( Rem /h r) (Rem)

Gamma scan 10 min

• Airborne from Analysis (1 min containment = 0.2 contact)

• Containment 3.6-2 (W.B.)

direct shine = 0.005 0.46 (Extremity)

• Syringe = 9.95-3 (3 ft)

• Syringe (contact) = 2.75 + 1 Hydrogen 10 min.

• Airborne from Analysis (1 min containment = 0.2 3.6-2 ( W.B. )

contact

• Containment direct shine = 0.005 0.46 (Extremity)

• Syringe = 9.95-3 (3 ft) *

• Syringe (contact) = 2.7 5 + 1

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TDR No. 529 Re v. O Page 17 of 26 2.5 Dose Received by Personnel During Post Accident Activities i

j All the actions and motions of the personnel during the post accident containment building atmosphere sampling have been accounted for. The exposure for both the whole body and extremities due to each source is presented in Table 7. The sample syringe is placed in a syringe carrier which is shielded with 1/8 inch lead lining. The technician keeps the syringe in the syringe carrier one foot away from his body while in transport. The integrated whole body and extremity doses, including dose contribution from the hydrogen recombiners, during sample removal and analyses are 1.1 rem and 1.7 rem respectively. The integrated whole body dose during sample removal and analyssa without the contribution from the hydrogen recombiners is 0.6 rem.

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r TDR No. 529 Rev. O Page 18 of 26

3.

SUMMARY

OF RESULTS ,

a. Exposures. The radiation exposures to the l technician during post accident containment atmosphere sampling activities are:

Whole Body Dose Extremity (Rem) (Rem) l l With Hydrogen Recombiners Contribution 1.1 1.7 Without Hydrogen Recombiners Contribution 0.6 1.7 These values are in compliance with the limits set by NUREG 0737.

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l b. Shielding requirement. As shown in Table 4, the dose rate from the syringe is 0.093 Rem /hr, without shielding, at one foot distance. Since it takes 4 min. and 45 sec. to transport the syringe, the whole body dose due to the unshielded syringe is 0.0074 rem. Hence the syringe can be carried un-shielded and radiation exposure to the technician will still be within acceptance criteria of 5 rem dose limit.

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4. REFERENCES

1. BNWL-236, UC-34 " User's Manual for ISOSHLD Code",

June 1966.

2. Midland Final Safety Analysis Report, Table 11.1-2, Total Core Fission Product Activity versus Time in Equilibrium Cycle.

3. TMI-l FSAR update 7/82.

4. TDR 494 "TMI-It Post-Accident Sampling Radiological Analysis", 5/10/84, Rev. 2.

5. GPU Calculation No. Al20-5412-016. "TMI-1; Post LOCA Airborne and Direct Shine Dose", 2/1/83.

6. "Thormal Hydrogen RecombinersSystem Operation and Maintenance Manual" Rockwell International, January 30, 1980, Rev. 2.

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TDR No. 529 Re v. O Page 23 of 26 Table 2: Dose Rate Due to the Sample Station Piping (Rem /hr)

Pipe 1 ft. 2 ft. 3 ft. 5 ft. 10 ft.

6 ft. long 7.15 - 1 2.99 - 1 1.60 - 1 6.63 - 2 1.82 - 2 1/4" OD 3 ft. long 5.57 - 1 1.96 - 1 9.42 - 2 3.58 - 2 2.92 - 3 1/4" OD 2 ft. long 4.42 - 1 1.41 - 1 6.53 - 2 2.42 - 2 6.22 - 3 1/4" OD 2 ft. long 1.78 + 0 5.68 - 1 2.63 - 1 9.74 - 2 2.50 - 2 1/2" OD 10" long 1.01 + 0 2.86 - 1 1.28 - 1 4.66 - 2 1.19 - 2 1/2" OD 6" long 6.25 - 1 1.74 - 1 7.80 - 2 2.83 - 2 7.20 - 3 1/2" OD

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TDR No. 529 Kev. O rage 24 of 26 Table 3: Dose Rate Due to Containment Shine (Rem /hr) 1 ft* 2 ft 3ft 5ft 10 ft 50 f t Containment 2.58 + 0 2.52 + 0 2.45 + 0 2.29 + 0 2.02 + 0 9.66 - I with 42" concrete Co ntainment 8.54 - 3 8.37 - 3 3.20 - 3 7.73 - 3 7.34 - 3 3.63 - 3 with 66" concrete Ta ble 4 - Dose Rate Due to Sample Syringe (Rea/hr)

(3 cc Containment Atmosphere Source) 1_ c m,* 3 cm 1ft 1. 5 f t 3ft Unshielded 2.75 + 1 7.00 + 0 9.27 - 2 3.84 - 2 9.95 - 3 1/8" Pb Shield 1.90 + 1 5.56 + 0 8.72 - 2 3.61 - 2 9.37 - 3 Table 5: Dose Rate Due to the Sample Bomb (Rem /hr)

(.2 cm Wall Thickness) 1 cm* 3 cm 6 inch 1ft 1.5 ft 3ft 9.83 + 1 4.36 + 1 4.36 + 0 1. 21 + 0 5.65 - 1 1.46 - 1 Table 6: Dose Rate Due to the Hydrogen Recombiner (Rem /hr)

Contac t 1ft 2ft 3ft 5ft 10 ft 20 f t Reaction Chamber and Heating coil 6.10 + 0 3.60 + 0 2.33 + 0 1.60 + 0 8.08 + 0 2.66 -'1- 7.51 - 2 Cooling Coil and Piping 4.54 + 3 3.80 + 2 1.66 + 2 9.36 + 1 4.14 + 1 1.19 + 1 3.18 + 0 Total 4.55 + 3 3.84 + 2 1.68 + 2 9.52 + 1 4.22 + 1 1.22 + 1 3.20 + 0 Note:

• Distance from the outside surface

TDR No. 529 Rev. O Page 25 of 26 Table 7: Radioactive Exposure Durino Post-Accident Activities Red. Exposure Stay Radiation Sources Radiation level During the Work Description Time (Rest /h r) (Rem)

Travel from Lab to 7 min . Airborne from containment 0.2 0.024 (W.E.)

the remote sample . Containment direct shine 0.G)5 panel (Two trips)

Travel time in the 1 min . Hydrogen recombiner 15.5 0.258 (W.8.)

vicinity of the hydrogen recombiner (Two trips)

Time opent at air station 40 sec . Airborne from containment 0.2 0.0023 (W.B.)

. Containment direct shine 0.005 Time spent at the 6 min & . Airborne from containment 0.2 0.023 (W.B.)

remote sample panel 50 see . Containment direct shine 0.005 Time to switch heat 10 see . Airborne from containment 0.2 0.0069 (W.B.)

trace (on and off) . Containment direct shine 2.29

. Airborne from containment 0.16 Time spent at the 6 min & . Airborne from containment 0.2 0.293 (W.B.)

samle station 40 sec . Containment direct shine 2.29

. All piping (assume the sample 1.31 piping is full with con-tainment atmosphere for 45 see and personrel is standing 3 ft away from the piping)

Time to draw sample from 45 sec . Airborne from containment 0.2 sample station (draw . Containment direct shine 2.29 3 ce sample from 40 cc . All pipings 3.35 sample bomb) . Sample bomb 1.21 0.09 (W.B. )

. Sample syringe .0927

. Sample bomb 98.3 (contact)

(hold sample bomb with

, one head for 15 sec) 0.75 (extremity)

. Sample syringe 27.5 (contact)

(hold sample syringe with both hand for 15 see)

. Sagle syringe 27.5 (contact)

(hold sample syringe with one hand to plee in shield for 15 see) i l

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i i * * "o TDR No. 529 Rev. O Page 26 of 26 Table 7: Radioactive Exposure Durina Post-Amident Activities (continued)

Red. Exposure Stay Radiation Sources Radiation level During the Work De scription Time (Ree/hr) (Rem)

Additional time spent in 5 min . Airborne from containment 0.2 0.017 (W.B.)

general area (e.g. . Containment direct shine 0.315 reading procedure filling out forms)

Travel from sample station 7 min & . Airborne from containment 0.2 0.0311 (W.B.)

to Lab (Two trips) 30 sec . Containment direct shine O.CD 5

. Syringe with 1/8 in. lead 0.087 shield (transport time for the syringe is 3 min.

45 sec. )

Travel time in the 1 min . Hydrogen recombiner 15.5 0.258 (W.B.)

vicinity of the bydrogen recombiner (Two trips) 20 min . See section 2.4.7 0.072 (W.8.)

0.92 (Extremity)

Total done including 1.1 Rem (W.8) contribution from 1.7 Rem (extremity)

Hydrogen recombinera Total dose excluding 0.6 Rem (W.B. )

contribution from 1.7 Rem (extremity)

Hydrogen recombiners l

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