ML20237J957
| ML20237J957 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/30/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20237J946 | List: |
| References | |
| NUDOCS 8709040143 | |
| Download: ML20237J957 (156) | |
Text
{{#Wiki_filter:_ _ - - _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ - _ _ - _ -___. . _ _ _ - -- -__ - . EXECUTIVE SUfMARY L Three Mile Island Nuclear Station Unit 1. Effluent and Offsite Dose Report for. the Period of January 1,1987 to June 30, 1987 This report suinnarizes the radioactive liauid' and gaseous releases (effluents)- 4 from Three Mile Island Unit 1 and the calculated maximum hypothetical radiation exposure to the:public resulting from these releases.- This report covers the period of operation from January 1 to June' 30, 1987. Radiological. releases from the plant are cal'culated from sample analyses of gaseous releases from the plant and liquid sample analyses for discharges-to the Susquehanna-River. These monitors provide a means for accurate determination of the type and quantities of radioactive materials being released to the environment. Calculations of.the maximum hypothetical dose to an individual and the total population around Three Mile Island due to radioactive releases from the plant are made. utilizing environmental conditions that existed at the time of the i release. Susquehanna River flow data are used to calculate the maximum ! hypothetical doses to an individual and..the population downstream of TMI due to liquid releases. Actual or "real-time" meteorological data from an onsite tower is used to' determine the doses resulting from gaseous releases from the ; plant. . The use of real-time meteorological information pemits the determination of both the direction in which the release traveled and the ; dispersion of radioactive material in the environment. Utilizing gaseous effluent data and real-time meteorology the maximum hypothetical . dose to any individual and to the total population within 50 miles of the plant is calculated. Similarly, Susquehanna River flow and liquid effluent data are used to calculate a maximum hypothetical dose to an individual and a population dose from liquid effluents for any shoreline i exposure down to the Chesapeake Bay. Exposure to the public from consumption of water.and fish withdrawn from the Susquehanna River downstream of the plant is also calculated. Dose calculations for liquid and gaseous effluents are performed using a mathematical model which is based on the methods defined by the U.S. Nuclear Regulatory Commission. Liquid discharges made during the reporting period January 1 to June 30, 1987 tonsisted of 55 Curies of tritium, 0.00057 Curies of. noble gases (predominately Xe-133), and 0.017 Curies of-other beta and gamma emitters, ; predominately Co-58. The quantities of effluents are similar to average semiannual releases from previous Unit 1 operations. B709040143 B70828 PDR ADOCK 05000289 R PDR
)
During the reportitig period January 1 to June 30, 1987, the maximum hypothetical calculated whole body dose to an individual due to liquid effluents from Three Mile Island Unit 1 was 0.095 mrem. The maximum hypothetical calculated dose to any organ of an individual was 0.14 mrem to the liver. Airborne discharges made during thf s same time period consisted of 0.98 Curies of tritium, 640 Curies of noble gases, and 0.000099 Curies of iodines and no Curies of particulate. These releases are less than average semi-annual releases from previous Unit 1 operation. . l The maximum hypothetical calculated dose to any individual from noble gases l was 0.0088 mrem to the skin and 0.0031 mrem to the whole body. Airborne iodines and particulate are calculated to produce 0.0029 mrem to the Thyroid of the maximum hypothetical individual. The total maximum hypothetical whole body dose of 0.098 mrem, received by any ' individual from effluents from the TMI-1 for the reporting period is 510 times lower than the doses the average individual in the area of TMI-1 receives from ! natural background during the same time period. Natural background averages ; about 50 mrem whole body semi-annually in the TMI-1 area. In addition, average equivalent dose to the lung from natural radon for the same period is about 90 mrem per quarter. The calculated total whole body population dose from all plant releases is 0.75 man-rem. This is 140,000 times lower than the dose attributed to natural background radiation for the reporting period. The doses which could be received by the maximum hypothetical individual are each less than 2% of the annual limits established by the Nuclear Regulatory Commission in Appendix I of 10 CFR 50. i l l (' _ - _ _ _ _ _ _ _ _ _ _ _ _ _ -__________-__-___-_____-___a
EFFLUENT 6 WAITE DISPOSAL SEMIANNUAL REPCRT SUPPLEMENTAL INFORMATION FACILITY: TMI UNIT 1 LICENSE: DPR 50-289
- 1. REGULATORY LIMITS - - - REFER TO TMI UNIT i TECHNICAL SPECIFICATIONS
{ g g AND ACTIVATION CASES: C. PARTICULATE HALF-LIVES ) 8 DAYS: D.LIQUIDEFFLUlNTS:
- 2. MAXIMUM PERMISSIBLE CONCENTRATIONS - - - 10 CFR 20, APPENDIX B TABLE 11 PROVIDE THE MPCS USED IN DETERMINING ALLOWABLE RELEASE RATES OR CONCENTRATIONS.
- g. g g AND ACTIVATION GASES:
C. PARTICULATE HALF-LIVES ) 8 DAYS: D.LIQUIDEFFLUkNTS:
- 3. AVERAGE ENERGY fR 5NHSBs% HTIv1TNEfr APetiCABLE E-BAR BETA = 1.98E-01 E-BAR GAMMA = 1.80E-01 E-BAR BETA AND GAMMA = 3.78E-01
- 4. MEASUREMENTS AND APPROXIMATION 0F TOTAL RADI0 ACTIVITY k UMSTMETHifft#MOTEfMHililftt%fCWlffHlF g g g AND ACTIVATION GASES:H g g g , LIQUID SCINTILLATION C. PARTICULATE HPGE SPECTROMETRY GAS FLOW PROPORTIONAL, BETASPECTROMETRY L.LIQUIDEFFLUENTS: HPGE SPECTROMETRY, LIQUID SCINTILLATION
- 5. BATCH RELEASES PROVIDE THE FOLLOWING INFORMATION RELATING TO BATCH RELEASES OF RADIDACTIVITYMATERIALSINLIQUIDANDGASE0USEFFLUENIS.
A. LIQUID QUARTERi ! QUARTER 2
- 1. NUMBER OF BATCH RELEASES: 37 ! 27
- 2. TOTAL TIME PERIOD FOR BATCH RELEASES: (MIN.) 16422. ! 11290.
- 3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE: (MIN.) 825. ! 1055.
- 4. MERAGE TIME PERIOD FOR BATCH RELEASES: (MIN.) 444. ! 418.
- 5. MINIMUM TIME PERIOD FOR A BATClI RELEASE: (MIN.) 55. ! 145.
- 6. AVERACE STREAM FLOW DURING PERIODS OF RELEASE !
0F EFFLUENT INTO A FLOWING STREAM: (CFM) 2.26E+06 ' 2.54E+N B. GASE005 h' k TbE O iCHRELEASES:(MIN.) 73ff2. f28h5.
- 3. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- (MIN.) 29600. ! 17300.
- 4. AVERAGE TIME PERIOD FOR BATCH RELEASES: (MIN.) 2728. ! 1662.
- 5. MINIMUM TIME PERIOD FOR A BATCH RELEASE: (MIN.) 90. ! 67.
- 6. ABNORMAL RELEASES NUMBER OF RELEASES: ! N/A ' N/A
- 2. TOTAL ACTIVITY RELEAIED: (CURIES)
B. CASE 0VS
- 1. NUMBER OF RELEASES: 0 ! 5 2.TOTALACTIVITYRELEASED: (CURIES) 0.00 ' 112.35
= ,
TABLE 1A EFFLUENT AND WAITE DIIPOSAL IEMIANNUAL REPORT (1987) GAIE0VI EFFLUENTI-IUMMAT10N OF ALL RELEASEI j...______ _ .... _.
! UNIT!QUARTERiiQUARTER2iESTTOTALi i
! ! ! ERROR, % ! !
.!. _____.... . _ i !
A. FIIIl0N AND ACTIVATION GAIES s- ... ... . i
!1.TOTALRELEAIE ! CI ! 1.36E+00 ! 6.43E+02! 2.50E+0i!
i._______ . ... ..._... ._____ _! (
!2. AVG.RELEASERATE! ! ! ! 1
! FOR PERIOD
!UCI/I ! 1.74E-01 ! 8.18E+0i !
.._-_. . ..- ._ .. ___i
!3.PERCENTOFTECH.! ! ! !
! SPECIFICATION LIMIT! % ! * ! # !
. - -i B. 10 DINES
- i. .____ .... . _ i
!i. TOTAL 10 DINE ! ! ! ! !
! 1131 ! C1 ! (1.00E-08 8 9.81E-05 ! 2.50E+01 !
- ~ ..._____. .. .
.. ~
AVG. RELEASE RATE! ! ! !
! 0R PERIOD
!UCl/I! N/A
' 1.25E-05 !
i
!3.PERCENTOFTECH.! ! ! !
! SPECIFICATION LIMIT! % ! N/A ! * !
C. PARTICULATE
...... . . ... .. ....i
!1.PART.WITHHALF-! ! ! ! !
! LIVES)8DAVI ! CI ! (1.00E-04 ! (1.00E-04 ! 2.50E+0i !
.. ._____. . . _ _ _ _ _ _ . . ..._.. ___.i'
!2. AVG.RELEASERATE! ! ! !
!FORPERIOD !UCl/I ! N/A ! N/A !
i i____...__ ___...
!3.PERCENTOFTECH.! ! ! I
! SPECIFICATION LIMIT! % ! N/A ! N/A !
!4. GROII ALPHA ' ' ' '
! RAD 10 ACTIVITY
. . . . _Cl) (1.00E-ii ! (1.00E-ii )
D. TRITIUM i.. ____.. . .. i
!1.TOTALRELEASE ! Cl 8 6.02E-01 ! 3.74E-01 ' 2.50E+01Ii
!2. AVG. RELEAIE RATE! ! ! !
! FOR PERIOD !UCI/I ' 7.74E-02
- 4.75E-02 ! .i s ____. .. ---
i3.PERCENTOFTECH.! ! ! !
! SPECIFICATION LIMIT! % !
- a !
i . _' i NOTE: L L LESI THAN VALUES (O ARE IN UC1/ML. 1% TECH. SPEC.LIMITI: LIITED ON DOIE IUnnARY TAftE.
c , TABLE 1C biOb3 0 -bu - LElfAb CONTINU0VI MODE BATCH MODE i i i i 1 __..._g I
!NUCLIDESRELEASED! UNIT! QUARTER 1iQUARTER2IQUARTER1'lQUARTER2!
- i e i i... .____ _ ..___'
.._... . . . . . _ _ ___.___.. ..i
- 1. Fl!!IEN GAIES
= .___.... ..... .... . ._ . i !
! KR ' CI ! (8.00E-06 ! (8.00E-06 ! 1.20E+00! 1.42E-01!i e.- 85.___ ___. _ _ . .
! r?. 85M ! CI ! (5.00E-08 ! (5.00E-08 ! i.97E-03 ! 7.16E-02 ii i__..___.. - .. .. .. .
! KR 87 ! CI !(8.00E-08!(8.00E-08!(8.00E_08!(8.00E-08!,
i.. _ _ _ _ _ _ . . . . . _ . . . . _ . ____ - _ _ . _ KR 88
- i. __ .. '. CI __' (1.00E-07 ! (1.00E-07 ! 1.43E-03
. ___ .. ...i ! 3.90E-02 !
! XE133 8 CI ! (8.00E-08 ! 2.53E+02 ! 5.6tE-02 ! 3.46E+02 !i
! XE135 ! CI ! 4.97E-04 ! 2.77E+01 ! 3.23E-02! 1.35E+0ii i
..__! l i ... .
XE135M
! CI !(5.00E-07' 1.97E-04!(5.00E-07!(5.00E-07!
. _ . . .... ._ ._i XE138 ! CI !(3.00E-07!(3.00E-07!(3.00E-07!(3.00E-07!i !
i
! XE133M ! CI ! (2.00E-07 ! (2.00E-07 ! 7.64E 04 ! 1.25E+00!
i __... . . . _ . . _ _ . . _ _ _ . _ _ _..___i
! XE 131M i________. . ! Cl ! (3.00E-07 ! (3.00E-07 ! 6.iiE-02! 1.75E+00!.
! AR 41 i __.. t C1 ! (3.00E-07 ! (3.00E-07 ! 4.69E_04! 3.07E-01!
1 l l i.. _..... . .___ . . . . _ _ . . ____i : 3 ! l.T01 AL FOR PERIOD ! CI ' 4.97E-04 ! 2.80E+02 ! 1.36E+00
. ........__. ..... .. . ..! ! 3.63E+02I
- 2. 10 DINES i .
.. . .. . ..___i
! I 131 ! CI ! (1.00E-12 ! 9.59E-05 ! (1.00E-08 ! 2.24E-06 ! ;
i_ . . . . i I
! I 132 ! CI ! (1.00E 10 ! (1.00E-10 ! (1.00E-03 ! 3.86E-10 !
i._.. - . . . . _ _ _ _ . _ _ _ _ _ _ . - - . . _ _i i 1 133
! CI ! (1.00E-10 ! 4.4tE-07!(1.00E-08'-7.57E_07! j
- i. .. __. . .___
i i ._. .._ ..... . ___.__.i
! TOTAL FOR PERIOD ! Cl ! 9.00E+00 ? 9.63E-05 ! 0.00E+00 ! 3.00E-06!
. - . ._. - i
- 3. PARTICULATE
_ ._ ...__.. .... _ .. ____ __i
! SR 89 i . ! Cl !(1.00E-ii!(1.00E-11!(1.00E-08!(1.00E_08!.
i SR 90
! Cl ' (1.00E-11 ! (1.00E_11 ! (1.00E-08
_ . . . ... _ _ . _ _ . _ _.i ! (1.00E_08 !
! C! 134 ! CI l i-. . .
'_(1.00E-11!(1.00E-li'.(.1.00E-08!(1.00E-08! . . _ . _ ........;
I ! CS137 ! CI ! (i. M E li ! (1.00E-li ! (1.00E-08 ! (1.00E-08 !i
! BA140 ! CI !(1.00E-it'(1.00E-ii!(1.00E-0B!(1.00E-08!i
! LA 140 I i . . ' CI '.(.1.00E-11!(1.00E_11!(1.00E-08!(1.00E-08!
. . _ _ _ _ _ . _ _i l
l NOTE: ALL LESS THAN VALUES (O ARE IN UClhil.
l
. l TABLE 2A l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1987)
'19UID EFFLUENTS-SUMATION F ALL RELEASES l
l_. iUNITIQUARTER1IQUARTER2iESTTOTALi !
! ! ! ! ERROR, I ! ;
! _ .__. .... _e ,
A. FISSIDHANDACTIVATIONPRODUCTS
~~~
!Ei0iAUEllASE(EX.! ! ! !
! TRIT. GASES, ALPHA)! CI ! 1.12E-02 ! 5.92E-03! 2.50E+01 !
!2. AVG. DILUTED ! !- ! !
! CONC. DURING PRD. !UCl/ML! 9.52E-10 ! 5.24t'-10 !
!. ... . ... .. .__. . i
!3. PERCENT OF ! ! ! !
! APPLICABLE LIMIT % ! * ! * !
B. TRITIUM
- i. . . ___ ____i ti. TOTAL RELEASE ! CI ! i.46E+01 ! 4.03E+01 ! 2.50E+01 I i____ __..__.. ._- . __ i '
I2. AVG. DILUTED ! ! ! !
!! CONC. DURING PRD. ...__.
. !UCI/ML! 1.24E-06 !___! . 3.56E_06 !
!3. PERCENT OF ! ! ! !
! APPLICABLE LIMIT !% ! * ! # !
!. ... .. . i C. DISSOLVED AND ENTRAINED GASES
__. ___.___... ... ...... .________. . i
!i.TOTALRELEASE i_.. .
! Cl ! (1.00E-04 ' 5.66E-04 ! 2.50E+0iI
!2. AVG, DILUTED ' ' ' '
! CONC. DURING PRD. IUCI/MLi s.
N/A i 5.01E-iti __.i
!3.PERCENTOF ! ! ! !
APPLICABLE LIMIT.__...' ......- N/A ... D. GROSS ALPHA RADI0 ACTIVITY
- i. . .. . . . -. i
!1.TOTALRELEASE ! Cl 8 (1.00E-07 ! (1.00E-07 ! 2.50E+0iI
!E. VOL. OF WASTE ! ! ! ! !
! RELEASED (N0 DIL.) ! LITERS! 1.35E+07 ! 1.21E+07! i.00E+01!
i.._. . . ___- . .__i
!f. VOL. OF DILUTION! ! ! ! !
! WATER DURING PERIOD ! LITERS! 1.18E+10 ! 1.13E+10! 1.00E+01 !
N01E: ALL LESS THAN VALUES (() ARE D! UCl/ML. f l #1 TECH. SPEC. LIMITS: LISTED ON DOSE SUMARY TABLE.
TABLE 2B EFFLUENT AND WAITE DIIPOIAL TEMIANNUAL R RURT (1987) LIQUIDEffLUENTI CONTINUOUS H0DE BATCH NODE i .. . ... .: i i i e i i e
!NUCLIDEIRELEASEDiUNITiQUARTERi! QUARTER 2iQUARTERi!i QUARTER i2' i e i
~
e i i .. . i
! IR 89 ! CI ! (5.00E48 ! (5.00E-08 ! 1.51E-05!(5.00E-08i .
! IR 90 C1 i._______. . . ' . _ _ _ ! (5.00E-08 ! (5.00E-08 ' 6.42E-06 '.(5.00E48 _ .... i !
! Cf 134 ! CI ! 3.58E-04 ! 3.86E44 ! 5.2iE-04 ' 5.91E-04i i . .
! CI 137 ! Cl ! 1.62E-03 ? 1.84E-03 ! 1.00E-03 ! 1.33E-03 - _ ._i i .. - . . .
! I 131 ! C1 ! (1.00E-06 ! (1.00E-06 ! (1.00E-06 ' 1.i?E-05ii
! C0 58 ! CI ! 8.90E-05 ! (5.00E-07 ! 6.iBE-03 ! 1.03E-03i i... . .
l ! C0 60 , i- . ! CI ! (5.00E47 ! (5.00E-07 ' .i.38E-04 ! C.71E-05!i l ! FE 59 ' Cl ' (5.00E-07 ! (5.00E-07 ! (5.00E-07 8 (5.00E-07!e \ ! ! ! ZN 65
. ! CI ! (5.00E-07 ' (5.00E-07 8 (5.00E-07 ' .(.5.00E47
. . ..i !
! MN 54 ' CI ! (5.00E-07 ! (5.00E-07 ! 1.36E-05 ! (5.00E47 !i
- e. . . _.
! CR 51 ! CI ! (5.00E-07 ' (5.00E-07 ! 7.95E-05!(5.00E-07i .i i ____. . ....... ..
I ! ZR 95
- i. . ! CI !(5.00E-07!(5.00E-07'..2.58E-05!(5.00E-07!
. . ._ _i 8 C1 ! (5.00E-07 ! (5.00E-07 ! 1.86E-05 ! 1.68E-05i
!. .. NB 95 _ _ _ . _ _ . . . . . ...a i 60 99 ! Cl !(5.00E-07'(5.00E-07'(5.00E-07!(5.00E-07i ....-
, ! TC 99H ' C1 ! (5.00E-07 ! (5.00E-07 ! (5.00E-07 ! (5.00E-07 !i i... . .. .__.._ .
! BA140 ! CI !(5.00E-07!(5.00E-07!(5.00E-07!(5.00E-07ii i __ -- .
! LA 140 i .. .. .... ! CI. . . ' .(5.00E-07'(5.00E-078 (5.00E-07i ! 2.14E-05i
! CE 141 ! CI e ..__.'(5.00E-07!(5.00E-07'(5.00E-07'(5.00E-07!
! FE 55 ' CI ..'......(1.00E-06 ' (1.00E-06 ? 2.30E-04 ! 1.lBE-04 i !
i.-- .
! RU 103 ! Cl ! (5.00E-07 ! (5.00E-07 ! 3.14E-05 ! 2.33E-06!
i.... . ......... = .... ._i
! AG 110M ! Cl ' (5.00E-07 ! (5.00E-07 8 8.27E-04 ! 4.81E-04i
! IB 125 ! CI ! (5.00E-07 ' (5.0BE-07 ! 5.65E-05 ! 1.20E-05 !
. . . -i i- i
!TOTALFORPERIOD i__
! Cl ! 2.06E-03 ! 2.23E-03 i 9.15E-03 ' 3.70E43 !
e _ _ _ . . . . . . _ _ _ ._.
! XE133 ' Cl ! (1.00E-04 ! 9.45E-05 8 (1.00E-04 ! 4.58E-04 !i i .
I ! XE 135 ! CI ! (1.00E44 8 (1.00E-04 * (1.00E-04 ' f.15E-05 ! NOTE: ALL LESS THAN VALUES (O ARE IN UCI/ML.
.. ' ; .,a TABLE. 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.- Solid waste shipped off-site for burial or disposal (not irradiated fuel) l
- 1. Type of waste UNIT f,"$th TgTAL 3 -{S
- a. Spent resins , . filter sludges, m'
' evaporator bottoms, etc.
04.55 m3 Ci 21.65 Ci 5%
'b. Dry compressible waste, contaminated m3 61.90 m3 equipment, etc. r4 or so r4 ss
- c. Irraciatec components, control m-rod s , e tc.
Ci N/A N/A me
- d. Other (describe) Ci n/A N/A
- 2. Estimate of major nuell.de composition (by type of weste)
- n. A 53.20 %
n-7 97 33.03e Cs134 6 81 % cnnA 4.39 %
~
- b. co n8 '{4 . o f .,
Cr%1 I . ic - NJ63 3.63 % re1 o7 2. 62 % - v e 55 d.d9 % c.ji/ A %
- d. N/A y
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1p nk hments Tractor - Flatbed !Ianford-Richland, WA 2 Shitunents Tractor-Cask (Nupac 14/190M) Hanford-Richland. WA 9 Shipments Tractor - Closed Van Hanford-Richland , WA 1 Shiriment Tractor - (HN100 Series 3) 'Hanford-Richland, WA Note: All shipments were radioactive LSA B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation I Destination j N/A 4 i i.I l Note: Solidification Agent, when used, was cement
-S- 1 I
l _ _ _ _. _ _ _ _ _____--_________--__-_-__----------a
n .- THREE MILE ISLAND
, JOINT FREQUENCY TABLES FIRST QUARTER 1987 SITE: THREE MILE ISLD. 08/14/87 12:10 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:Sf DIRECTION:DIlO0A LAPCE:DT!!PA
_______________________'t.C'_34 __ _ _ _ _ . . . _ _ _ _ . . _ _ _ _ . . _ _ . . _ _ . . _ . _ _ . . . WIND SEEEDfMPH) WIND DIRECTION 1-3 4 7 8-12 13-13 19-24 .24 TOTAL N Y 8 10 10 4 0 33 NNE 3 2 5 2 0 0 12 NE O O O' 0 0 0 0 ENE O 2 0 0 0 0 2 E 3 3 0 0 0 0 6 ESE 2 7 0 0 0 0 9 SE 5 9 0 0 0 0 14 SSE 4 2 0 0 0 0 6 S 2 3 1 0 0 0 6 SSW 4 8 4 0 0 0 16 SW 6 5 1 0 0 0 12 WSW 7 1 0 0 0 0 8 W 3 2 4 5 3 0 17 WNW 3 8 16 3 0 0 30 NW 8 15 20 8 0 0 51 NNW 11 26 25 20 3 0 85 ! TOTAL 68 101 86 48 10 0 313 .) ________..________________________.____________.______________
' PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 95 HOURS OF MISSING DATA: 18 I
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : 87010101-87033124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 2 3 8 2 0 15 NNE O O O O O O O NE O 2 0 0 0 0 2 ENE O 1 0 0 0 0 1 E 3 1 1 0 0 0 5 ESE 1 3 0 0 0 0 4 SE 1 3 1 0 0 0 5 SSE 3 1 1 0 0 6 S 1 0 1 0 0 0 2 SSW 0 2 2 1 0 0 5 SW 3 1 0 0 0 0 4 WSW 0 0 0 0 0 0 0
. W 1 1 3 6 2 0 13 WNW 1 3 4 8 0 0 16 NW 1 0 10 7 2 0 20 NNW 3 0 8 6 4 2 23
_____._____.....___________._______.___.__..__________________ j TOTAL 16 22 34 37 10 2 121 PERIODS OF CALM (HOURS): 0 I VARIABLE DIRECTION 20 _ HOURS OF MISSING DATA: 18 ]I 1
)
I 1 l _. ________-__________O
THREE MILE ISLAND
,J0 INT FREQUENCY TABLES FIRST QUARTER 1987 SITE: THREE MILE ISLD. 08/14/67 12:14 BOURS AT R.ACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 1 0 1 0 0 2 NNE O O O 1 0 0 1 O O O O O O O NE ENE O 1 0 0 0 0 1 E O 2 0 0 0 0 2 ESE 1 1 0 0 0 0 2 SE O 2 1 0 0 0 3 O O O O O O O SSE S 0 1 0 0 0 0 1 SSW 0 1 0 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 1 1 1 1 1 0 5 0 1 1 3 0 0 5 WNW NW 0 1 1 5 2 0 9 0 1 3 3 1 2 10
.l NNW ~
2 7
.- --_ - -, ~'ff~~~~
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 5 HOURS OF MISSING DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 15 12 10 2 0 41 NNE 7 11 2 1 0 0 21 NE 5 16 5 0 0 0 26 ENE 4 13 0 1 0 0 18 E 7 17 1 0 0 0 25 ESE 2 12 12 6 0 0 32 SE 11 21 14 3 0 0 49 SSE 4 5 6 3 0 0 18 S 5 6 10 1 0 0 22 SSW 2 1 4 0 0 0 7 SW 2 4 0 0 0 0 6 WSW 4 2 3 0 0 0 9 W 1 6 14 15 1 0 37 WNW 0 6 24 57 11 1 99 NW 3 16 34 33 19 1 106 NNW 0 16 27 17 10 8 78 TOTAL 59 167 168 147 43 10 594
-----~~-- ----------------------------------------------------
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 92 HOURS OF MISSING DATA: 18
e i' . THREE MILE ISLAND-
. J0114T FREQUENCY TABLES FIRST QUARTER 1987 SITE: TEMI MILE ISLD. 08/14/87 12:18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAFSE:DT150A WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 52 22 3 1 0 82 NNE 9 14 5 0 0 0 28 NE 7 5 0 0 0 0 12 ENE 6 9 0 0 0 0 15 E 7 12 4 0 0 0 23 ESE 2 13 3 1 0 0 19 SE 5 24 3 0 0 0 32 SSE 3 7 1 2 0 0 13 S 3 10 6 2 0 0 21 SSW 8 12 0 1 0 0 21 SW 9 15 9 0 0 0 33 WSW 7 18 5 0 0 0 30 W 4 25 17 3 0 0 49 WNW 7 16 37 13 0 0 73 NW 7 15 46 29 10 1 108 I NNW 13 30 25 18 2 0 88
\ ................--........--.---........--..--.. -...---------
TOTAL 101 277 183 72 13 1 647
~
PbRIbbbbFbELM[bbbEb5 b VARIABLE DIRECTION 125 HOURS OF MISSING DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 87010101-87033124 l l STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 18 2 0 0 0 26 NNE 1 2 0 0 0 0 3 NE 3 1 0 0 0 0 4 l I ENE 5 2 0 0 0 0 7 E 5 4 0 0 0 0 9 ESE 6 4 0 0 0 0 10 SE- 9 4 0 0 0 0 13 SSE 9 8 0 0 0 0 17 ) S 11 0 0 0 0 0 11 ! SSW 7 7 0 0 0 0 14 ; SW 5 1 0 0 0 0- 6 i WSW 9 7 0 0 0 0 16 ; W 2 5 3 0 0 0 10 i i WNW 3 2 2 0 0 0 7 NW 6 5 0 0 0 0 11 NNW 4 23 13 2 0 0 42 TOTAL 91 93 20 2 0 0 206 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 85 HOURS OF MISSING DATA: 18
I THREE MILE ISLAND
,10114T FREQUENCY TABLES l FIRST QUARTER 1987 SITE: THREE MILE ISLD. 08/14/87 12:21 l
BOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: G DT/DZ ELEVATION:- SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND ! DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 5 1 0 0 0 9 NNE 1 1 0 0 0 0 2 NE 3 0 0 0 0 0 3 ENE 3 0 0 0 0 0 3 E 4 1 0 0 0 0 5 ESE 6 1 0 0 0 0 7 SE 13 2 0 0 0 0 15 0 0 SSE 22 1 0 0 23 S 26 1 0 0 0 0 27
'SSW 20 15 0 0 0 0 35 SW 13 4 0 0 0 0 17 WSW 8 8 0 0 0 0 18 W 11 4 0 0 0 0 15 WNW 7 1 0 0 0 0 8 NW 6 7 1 0 0 0 14 i NNW 6 13 1 0 0 0 20 i ______________________________________________________________
1 TOTAL 152 64 3 0 0 0 219 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 94 HOURS OF MISSING DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87033124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 22 101 50 32 9 0 214 JNE 21 30 12 4 0 0 67 NE 18 24 5 0 0 0 47 ENE 18 28 0 1 0 0 47 E 29 40 6 0 0 0 75 ESE 20 41 15 7 0 0 83 i SE 44 65 19 3 0 0 131 l i SSE 43 26 8 6 0 0 83 j S 48 21 18 3 0 0 90 1 ' SSW 41 46 10 2 0 0 99 SW 38 30 10 0 0 0 '8 WSW 35 36 8 0 0 0' /d l W 23 44 42 30 7 0 146 ! WNW 21 37 84 84 11 1 238 j NW 31 59 112 82 33 2 319 NNW 37 109 102 66 20 12 346 - TOTAL 489 737 501 320 80 15 2142 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 516 HOURS OF MISSING DATA: 18
._-___________________-_A
F. i 1 l
-- THREE !!ILE ISLAND UNIT 1 JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS FIRST QUARTER 1987 SITE: THREE MILE ISLD. UNIT: UNIT 1 08/14/87 13:04 HOURS AT EACH WIND SPEED AND DIRECTION 86123124-87032818 l PERIOD OF RECORD : -
STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l _________ ___ ___ ____ _____ _.... ___ _____ N 3 2 8 3 0 0 16 NNE 3 0 2 1 0 0 6 NE O O O O O O O ENE O 2 0 0 0 0 2 E O O O O O O O ESE 1 1 0 0 0 0 2 SE 4 1 0 0 0 0 5 SSE 1 2 0 0 0 0 3 S 2 2 0 0 0 0 4 SSW 2 1 0 0 0 0 3 SW 5 0 1 0 0 0 6 WSW 1 1 0 0 0 0 2 W 0 1 0 5 2 0 8 WNW 0 4 3 1 0 0 8 NW 3 4 9 0 0 0 16 NNW 5 8 11 10 3 0 37 1 TOTAL 30 29 34 20 5 0 118 PbkIbbbbFbILbiHbbkb) b VARIABLE DIRECTION 36 HOURS OF MISSING DATA: '1B HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86123124-87032818 STABILITY CLASS: B DT/DZ ELEVATION. SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 1 2 0 0 0 3 NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E 1 0 0 0 0 0 1 ESE O 1 0 0 0 0 1 , SE 1 0 0 0 0 0 1 l SSE O O O O O O O I S 0 0 0 0 0 0 0 SSW 0 1 0 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0- 0 W 0 0 0 3 2 0 5 i WNW 0 2 2 5 0 0 9 l NW 1 0 5 0 1 0 7 NNW 2 0 2 0 2 0 6 TOTAL 5 5 11 8 5 0 34 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 7 HOURS OF MISSING DATA: 18
. ., THREE MILE ISLAND UNIT 1 JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS FIRST QUARTER 1987 SITE: THREE MILE ISLD. UNIT: UNIT 1 08/14/87 13:07 l
HOURS AT EACH WIND SPEED AND DIRECTION ! PERIOD OF RECORD = 88123124-87032818 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DI1DOA LAP 3E.DT150A WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 2 0 0 0 0 2 O O O O O O O NNE O NE O O O O O O O O O O O O O ENE E O 1 0 0 0 0 1 O O O O O O O ESE SE O 2 0 0 0 0 2 O O O O O O O SSE 0 S 0 0 0 0 0 0 SSW 0 1 0 0 0 0 1 0 0 0 0 0 0 0 SW 0 WSW 0 0 0 0 0 0 W I O 1 0 1 0 3 WNW 0 0 1 2 0 0 3 NW 0 0 2 2 0 0 4 NNW 0 1 0 0 1 0 2 TOTAL 1 7 4 4 2 0 18 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 5 HOURS OF MISSING DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86123124-87032818 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 --_ -- ._ O 12 7 2 0 0 21 N j 9 10 0 0 0 0 19 NNE 0 0 25 1 NE 5 16 4 0 ! 3 8 0 0 0 0 11 ENE 0 10 E 4 6 0 0 0 8 4 0 0 0 13 ESE 1 0 25 SE 5 14 6 0 0 2 2 0 0 0 0 4 SSE 10 S 4 3 2 1 0 0 SSW 0 0 2 0 0 0 2 0 4 0 0 0 0 4 SW 0 0 6 I WSW 2 1 3 0 25 l W 1 5 11 7 1 0 ' 0 3 19 45 4 1 72 WNW 7 0 45 NW 0 11 11 16 0 3 9 2 3 0 17 NNW
-_ _._......--..._........_---- -.... - -._...--------_--_.--- 73 15 1 309 l TOTAL 36 106 78 PERIODS OF CALM (HOURS): 0 l VARIABLE DIRECTION 63 l HOURS OF MISSING DATA: 18 1
l
i . THREE MILE ISLAND UliIT 1 4 J0Zi4T FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS FIRST QUARTER 1987 SITE: THREE MILE ISLD. UNIT: UNIT 1 08/14/87 13:10 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86123124-87032818 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 13 8 2 0 0 25 NNE 6 9 3 0 0 0 18 NE 3 5 0 0 0 0 8 ENE 8 0 0 0 0 0 8 E 3 1 0 0 0 0 4 ESE 2 5 1 0 0 0 8 ! SE 4 13 2 0 0 0 19 SSE 5 2 0 0 0 0 7 S 2 10 4 2 0 0 18 SSW 1 8 0 0 0 0 9 SW 4 10 7 0 0 0 21 3 14 4 0 0 0 21 j WSW W 3 16 7 1 0 0 27 ; WNW 1 7 20 9 0 0 37 ! NW 4 9 20 16 7 1 57 l
! NNW 5 12 10 6 1 0 34 l TOTAL 56 134 86 36 8 1 321 / _________._________ ______________________________. ..______.
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 64 HOURS OF MISSING DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86123124-87032818 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 12 1 0 0 0 15 NNE 1 2 0 0 0 0 3 NE 2 0 0 0 0 0 2 ENE 3 0 0 0 0 0 3 E 4 0 0 0 0 0 4 ESE 2 1 0 0 0 0 3 SE 3 2 0 0 0 0 5 SSE 3 4 0 0 0 0 7 S 4 0 0 0 0 0 4 SSW 4 3 0 0 0 0 7 SW 1 0 0 0 0 0 1 WSW 5 4 0 0 0 0 9 , W 2 3 1 0 0 0 6 ; WNW 3 1 1 0 0 0 5 NW 3 1 0 0 0 0 4 , NNW 2 15 9 1 0 0 27 !
.. ___ .......___.....____.______ _____ ------__________.____ j TOTAL 44 48 12 1 0 0 105 )
PERIODS OF CALM (HOURS): 0 ! VARIABLE DIRECTION 48 ) HOURS OF MISSING DATA: 18
}
l THREE MILE ISLAND UNIT 1
, JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS FIRST QUARTER 1987 SITE: THREE MILE ISLD. UNIT: UNIT 1 08/14/87 13:13 HCLRS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 88123124-87032818 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH)
WIND DIR{CIlgN };} 4;? 8:12 11:18 19:23 323 19I % N 1 2 0 0 0 0 3 NNE 1 0 0 0 0 0 1 NE O O O O O O O ENE O O O O O O O E 3 1 0 0 0 0 4 ESE 4 0 0 0 0 0 4 SE 12 2 0 0 0 0 14 SSE 10 1 0 0 0 0 11 S 16 1 0 0 0 0 17 SSW 11 6 0 0 0 0 17 SW 6 1 0 0 0 0 7 WSW 8 4 0 0 0 0 12 W 3 2 0 0 0 0 5 WNW 3 0 0 0 0 0 3 i NW 1 1 1 0 0 0 3 NNW 2 2 1 0 0 0 5 i _________________________________....__...__________....______ TOTAL 81 23 2 0 0 0 106 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 57 HOURS OF MISSING-DATA: 18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86123124-87032818 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 8 44 26 7 0 0 85 NNE 20 21 5 1 0 0 47 NE 10 21 4 0 0 0 35 ENE 14 10 0 0 0 0 24 E 15 9 0 0 0 0 24 ESE 10 16 5 0 0 0 31 SE 29 34 8 0 0 0 71 SSE 21 11 0 0 0 0 32 S 28 16 6 3 0 0 53 SSW 18 20 2 0 0 0 40 SW 16 15 8 0 0 0 39 WSW 19 24 7 0 0 0 50 W 10 27 20 16 6 0 79 WNW 7 17 46 62 4 1 137 f NW 12 26 48 34 15 1 136 l NNW 16 41 42 19 10 0 128 TOTAL 253 352 ?27 142 35 2 1011 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 280 HOURS OF MISSING DATA: 18
l THREE MILE ISLKiD JOINT FREQUENCY TABLES SECOND QUARTER 1987 07/29/87 13:37 ! SITE: THREE MILE ISLD. BOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040101-87063024 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 _. ._ ..... 10 5 1 0 0 19 N 3 0 0 0 7 2 3 2 NNE 1 0 0 17 1 9 6 NE 8 8 0 0 0 16 ENE O 2 4 8 5 1 0 18 E 3 0 0 25 ESE 1 4 17 5 7 0 0 0 13 SE 1 O 1 1 3 0 0 5 SSE 0 0 6 3 2 0 1 S 30 4 0 13 10 7 0 0 ' SSW 6 2 0 0 21 SW 2 11 6 4 1 0 0 0 11 WSW 8 0 0 0 23 W 5 10 5 15 16 1 0 0 37
. WNW 7 0 0 66 NW 7 28 24 7 23 29 3 0 0 62 NNW 45 150 146 34 1 0 376
) ~ TOTAL
~ ~
~~ ~ '~~~~"~~~ "~~~~~~~ "~~~~~~
5555665 65 6IL5[566555i88 6 VARIABLE DIRECTION 8 HOURS OF MISSING DATA: HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040101-87063024 STABILITY CLASS: B DT/DZ SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B ELEVATION: WIND SPEED (MPH) WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 1 1 1 1 0 0 4 N O 3 0 0 0 0 3 NNE 0 0 0 0 5 O 5 NE 0 0 0 4 O 2 2 ENE 8 9 1 0 21 1 2 E 7 1 1 0 12 1 2 ESE 4 1 0 0 8 O 3 SE 1 0 0 6 1 3 1 SSE 0 0 0 5 1 1 3 S 3 5 1 0 0 10 SSW 1 0 11 1 1 1 0 14 SW 1 0 0 0 4 WSW 2 1 2 5 4 0 0 0 11 W 3 0 0 17 5 1 8 WNW 8 4 2 0 21 3 4 NW 3 3 0 0 13 4 3 NNW 50 56 25 5 0 158 TOTAL 22 ~~~~""~"~"~~~""~~"~~~"
~ ~
~
E555665 65 6IL5iS6655II 43
"~ ~ 6 VARIABLE DIRECTION 8
HOURS OF MISSING DATA:
THREE MILE ISLAND JOINT FREQUENCY TABLES bECOND QUARTER 1987 l SITE: THREE MILE ISLD, 07/29/87 13:37 ; l BOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF BICORD = 87040181-87063024 l STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND >24 TOTAL ! DIRECTION 1-3 4-7 8-12 13-18 19-24 ___ ____. O 4 2 0 0 0 6 N 0 0 2 NNE O 1 1 0 . 0 0 0 5 ! 1 3 1 NE 0 0 0 0 2 ENE O 2 O 1 5 2 0 0 8 E 0 0 6 ESE O O 5 1 O 2 2 1 0 0 5 SE 0 0 2 SSE ; O O 1 0 4 0 1 0 0 5 S 0 SSW 0 1 5 0 0 6 1 2 2 0 0 0 5 SW 0 0 2 WSW 0 0 2 0 2 1 3 0 0 0 6 W 0 0 .15 1 3 8 3 WNW 0 0 8 NW 1 1 4 2 0 2 4 4 0 0 10 NNW
.__..._ ____.-_..._-_-__....__-_-_...-_-_ .0 ...... 0.. ..___.__ 93 TOTAL 7 27 44 15 .) ..__. ......._._.____.._._.. __.-_._..... __.. ......_..._....
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 10 HOURS OF MISSING DATA: 8 ( c HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : 87040101-87063024 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 ___ _____ 7 14 11 1 0 0 33 N 0 0 27 NNE 3 11 13 0 6 19 11 0 0 0 36 NE 0 41 5 21 13 2 0 ENE 0 62 7 23 29 3 0 E 0 109 ESE 6 42 56 5 0 4 24 22 3 1 0 54 SE 0 18 4 10 3 1 0
' SSE 0 12 S 1 5 6 0 0 1 21 24 4 0 0 50 SSW 39 SW 9 16 12 0 1 1 14 10 1 1 0 0 26 WSW 0 0 37 l W 7 13 15 2 8 14 11 8 1 0 42 WNW 3 0 46 NW 5 15 8 15 4 8 9 2 0 0 23 )
NNW .
-___...._______. .. ___.____.. ..._____.._______... ..._______ 655 TOTAL 91 266 244 47 6 1
~~ ~~~~
~ ~ ~ ~~~~
'kkIbbbbFUILE[EbbE55I P E VARIABLE DIRECTION 142 HOURS OF MISSING DATA: 8 I
________ - a
THREE MILE ISLAND JOINT FREQUENCY TABLES
.SECOND QUARTER 1987 SITE: THREE MILE ISLD. 07/29/87 13:41 BOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040101-87063024 STABILITY CLAS8: E DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 29 13 0 0 0 51 NNE 7 20 3 0 0 0 30 NE 9 23 1 0 0 0 33 ENE 10 16 4 0 0 0 30 E 16 21 5 0 0 0 42 ESE 8 12 1 0 0 0 21 l 4 6 2 0 0 0 12 SE SSE 4 3 0 0 0 0 7 S 7 8 5 0 0 0 20 ; SSW 10 32 24 4 0 0 70 SW 14 43 6 1 0 0 64 WSW 10 28 2 0 0 0 40 W 10 19 8 0 0 0 37 WNW 8 23 13 3 1 0 48 NW 7 15 12 7 0 0 41
- NNW 6 24 6 1 0 0 37 3
TOTAL 139 322 105 16 1 0 583 3 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 196 HOURS OF MISSING DATA: 8 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040101-87063024 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 3 1 0 0 0 6 NNE 2 1 0 0 0 0 3 NE 2 1 0 0 0 0 3 ENE 4 5 0 0 0 0 9 E 7 8 0 0 0 0 15 ESE 9 3 1 0 0 0 13 SE 6 1 0 0 0 0 7 SSE 11 4 0 0 0 0 15 0 S 8 3 0 0 0 11 SSW 6 7 2 0 0 0 15 SW 15 8 0 0 0 0 23 WSW 16 6 0 0 0 0 22 W 12 12 0 0 0 0 24 WNW 10 3 0 0 0 0 13 NW 5 10 2 0 0 0 17 NNW 7 9 1 0 0 0 17 TOTAL 122 84 7 0 0 0 213 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 109 HOURS OF MISSING DATA: 8
-' = THREE MILE ISLAND l
, JOINT FREQUENCY TABLES SECOND QUARTER 1987 j SITE: THREE MILE ISLD. 07/29/87 13:47 1
BOURS AT EACE WIND SPEED AND DIRECTION PERIOD W RECORD-= 87040181-87063024 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND DIRECTION 13 4-7 8 12 13-18 19 24
>24 TOTAL N 5 1 0 0 0 0 6 NNE 2 0 0 0 0 0 2 NE O 1 0 0 0 0 1 ENE 2 2 0 0 0 0 4 E 3 4 1 0 m 0 8 ESE 2 0 0 0 0 0 2 SE 6 0 0 0 0 0 6 SSE 2 0 0 0 0 0 2 S 7 1 0 0 0 0 8 SSW 12 2 0 0 0 0 14 SW 7 0 0 0 0 0 7 WSW 6 1 0 0 0 0 7 W 8 3 0 0 0 0 11 WNW 6 2 0 0 0 0 8 NW 7 6 0 0 0 0 7 NNW 2 3 0 0 0 0 5 i _________________________________.. __________________________
TOTAL 77 20 1 0 0 0 98
\ .____.__......_____________________...__.____._______.__.___._
PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 65 HOURS OF MISSING DATA: 8 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040101-87063024 STALILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP100B DIRECTION:DIl00B LAPSE:DT150B WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 27 62 33 3 0 0 125 NNE 16 39 19 0 0 0 74 NE 19 61 19 1 0 0 100 ENE 21 56 27 2 0 0 106 E 36 63 54 19 2 0 174 ESE 27 63 87 10 1 0 188 SE 21 41 37 5 1 0 105 SSE 23 21 5 6 0 0 55 S 27 24 14 2 0 0 67 SSW 30 79 70 16 0 0 195 SW 48 91 27 4 2 1 173 WSW 54 50 7 1 0 0 112 W 46 63 38 2 0 0 149 WNW 43 61 56 18 2 0 180 NW 35 73 58 35 5 0 206 NNW 30 72 52 13 0 0 167 TOTAL 503 919 603 137 13 1 2176 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 653 HOURS OF MISSING DATA: 8
THREE MILE ISLAND UNIT 1 JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS SECOND QUARTER 1987 SITE: THREE MILE ISLD. 08/18/87 12:37 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040116-87062615 STABILITY CLASS: A DT/DZ t ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A 1 ................................................................ I WIND SPEED (MPH) l WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 4 5 3 0 0 0 12 NNE 2 3 1 0 0 0 6 NE 1 3 0 0 0 0 4 1 ENE O 1 0 0 0 0 1 E 2 1 0 0 0 0 3 ESE 1 0 0 0 0 0 1 SE 1 2 1 0 0 0 4 SSE 2 0 0 0 0 0 2 S 2 1 0 0 0 0 3 SSW 2 3 1 0 0 0 6 SW 3 8 3 1 1 0 16 WSW 3 2 0 0 0 0 5 W 2 3 3 0 0 0 8 l WNW 5 5 3 0 0 0 13 NW 4 5 2 1 0 0 12 i NNW 4 2 4 1 0 0 11 1 TOTAL 38 44 21 3 1 0 107 1: .............................................................. ! PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 54 HOURS OF MISSING DATA: 15 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040116-87062615 l STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A I WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 1 0 0 0 1 NNE O O O O O O O NE 1 0 0 0 0 0 1 ENE O O O O O O O E O 1 0 0 0 0 1 ESE O O O O O O O SE 1 1 0 0 0 0 2
- SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 1 SW 0 1 3 0 0 0 4 WSW 0 2 0 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 1 2 0 0 0 3 NW 0 1 1 2 1 0 5 NNW 0 0 0 0 0 0 0 TOTAL 2 7 8 2 1 0 20 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 7 HOURS OF MISSING DATA: 15
. 't .
THREE MILE ISLAND UNIT 1 JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS SECOND QUARTER 1987 SITE: THREE MILE ISLD. 08/18/87 12:40 BOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040116-87062615 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECI}gN };3 j;? 8;}2 }3;}8 }9;23 323 JgJAp N O e e e e e O NNE O O O O O O O NE e e 0 0 0 e e ENE O O O O O O O E O O O O O O O ESE O O 4 0 0 0 4 SE O O 1 0 0 0 1 SSE O O O e e 0 e S 0 0 1 0 0 0 1 : SSW 0 2 0 0 0 0 2 SW 0 1 1 0 0 1 3 WSW 0 0 0 0 0 0 0 W 2 2 0 0 0 0 4 UL*W 0 0 1 2 0 0 3 NW 0 0 0 0 0 0 0 I NNW 0 0 0 0 0 0 0 TOTAL 2 5 8 2 0 1 18
/ ____ ______.__._._____.____ ____._____...__________._______...
PERIODS OF CALMfHOURS): 0 VARIABLE DIRECTION 4 HOURS OF MISSING DATA: 15 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : 87040116-87062615 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 0 3 1 0 0 7 NNE 2 2 1 0 0 0 5 NE 3 1 0 0 0 0 4 J ENE 1 2 2 0 0 0 5 i 0 0 0 7 ( E 2 4 1 ESE 2 4 7 0 0 0 13 ] SE 2 7 4 0 0 0 13 - SSE 1 4 2 0 0 0 7 S 3 7 0 0 0 0 10 l SSW 1 4 2 0 0 0 7 SW 5 6 2 0 1 0 14 WSW 3 4 1 0 0 'O 8 W 1 0 1 0 0 0 2 l WNW 5 2 1 5 1 0 14 ! 0 2 2 2 0 0 6 j NW NNW 0 2 2 0 0 0 4 j ___..___________._______________________.._________________.._ l TOTAL 34 51 31 8 2 0 126 l PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 51 HOURS OF MISSING DATA: 15 i ) l
)
THREE MILE 85 LAND UNIT 1 JOINT FREQUEWCY TABLES SPECIFIC BATCd RELEASE PERIODS SECOND QUARTER 1987 SITE: THREE MILE ISLD. 08/16/87 12:55 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040116-87062615 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A WIND SPEED (MPH) WIND DIREgIjgN };3 3:7 8;12 }3;18 19 24 323 JgIAL N 4 8 4 0 0 0 16 NNE 1 8 1 0 0 0 10 NE 2 7 0 0 0 0 9 ENE 3 4 0 0 0 0 7 E 4 2 0 0 0 0 6 ESE 8 2 0 0 0 0 10 SE O 1 0 0 0 0 1 SSE O 1 0 0 0 0 1 S 1 2 0 0 0 0 3 SSW 3 10 1 0 0 0 14 SW 7 14 0 1 0 0 22 1 WSW 5 8 0 0 0 0 13 : W 4 2 6 1 0 0 13 WNW 4 4 5 2 1 0 16 NW 1 1 1 4 0 0 7 l NNW 3 6 3 0 0 0 12 TOTAL 50 80 21 8 1 0 160 -f ...__......__....__.___.....__.___..______..... .__.____....._ PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 53 HOURS OF MISSING DATA: 15 HOURS AT EACH WIND SPEED AND DIRECTION g PERIOD OF RECORD = B7040116-87062615 STABILITY CLASS: F DT/DZ {> ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A j WIND SPEED (MPH) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 2 0 0 0 0 3 NNE O 1 0 0 0 0 1 NE O O O O O O O ENE O O O O O O O E 1 1 0 0 0 0 2 ESE 2 1 0 0 0 0 3 SE 2 0 0 0 0 0 2 SSE 6 0 0 0 0 0 6 l S 1 2 0 0 0 0 3 i SSW 1 1 0 0 0 0 2 SW 1 0 0 0 0 0 1 WSW 1 0 0 0 0 0 1 W 2 3 0 0 0 0 5 WNW 0 1 0 0 0 0 1 NW 2 1 0 0 0 0 3 NNW 0 2 0 0 0 0 2
..__...___._.___....___......_____________._______.______...__ l TOTAL 20 15 0 0 0 0 35 i PERIODS OF CALM (HOURS): 0 i VARIABLE DIRECTION 21 l HOURS OF MISSING DATA: 15 i s l l
.. THREE MILE ISLAND UNIT 1 JOINT FREQUENCY TABLES SPECIFIC BATCH RELEASE PERIODS SECOND QUARTER 1987 SITE: THREE MILE ISLD. e8/18/87 12:58 BOURS AT EACH WIND SPEED AND DIRECTION PERIOD RECORD = 87040116-87062615 STABILI CLASS: G DT/DZ ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT15eA WIND SPEED (MPH)
WIND D]RECIjgli };} 3:Z 8:12 13:18 19:23 223 IQJAL N 2 e e 0 e e 2 NNE O O O O O O O NE O O O O O O e ENE O 1 0 0 0 0 1 E e 2 e e e a 2 ESE 1 0 0 0 0 0 1 SE O O e 0 0 0 0 SSE O O O O O O O S e e 0 e 0 e O SSW , 1 2 0 0 0 0 3 SW , 1 0 e 'e e e 1 WSW r 0 0 e 0 e e e W e e 0 e e e 0 WNW 0 0 0 0 0 0 0 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 - 1 TOTAL TJ 5 0 0 0 0 12 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 6 HOURS OF MISSING DATA: 15 i HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87040116-87062615 STABILITY CLASS: ALL DT/r2 ELEVATION: SPEED:SP100A DIRECTION:DIl00A LAPSE:DT150A ___.. ................,.....s.5......__ _______._______..__ _____ WIND SPEED (MPH) WIND DIRECTION 1-3 4* 8-12 13-5.8 19-24 >24 TOTAL N - 14 15 11 1 0 0 41 NNE 5 14 3 0 0 0 22 NE . 7 11 0 0 0 0 18 ENE i 4 8 2 0 0 0 14 i E 9 11 1 0- 0 0 21 ESE 14 7 11' C 0 0 32 SE 6 11 6 > 0 0 0 23 SSE 9 5 2 0 0 0 16 ) S 7 12 1 0 0 0 20 SSW 8 22 5 0 0 0 35 SW 17 20 9 2 2 1 61 WSW 12 16 7 0 0 0 29 ; W 11 le 10 1 0 0 32 WNW 14 13 12 9 2 0 50 NW r 9 10 6 9 1 0 35 l NNW 7 12 9 1 0 0 29 TOTAL 153 207 89 23 5 1 478 PERIOD 3 0F CALM (HOURS): 0
< , VARIA31E DIRECTION 196 HOURS,GF MISSING DATA: 15 I
t l io -
INTERPRETATION OF DOSE SlM4ARY TABLE 1 The Dose Summary Table presents the maximum hypothetical doses.to an individual and the general population resulting from the release of gaseous and liquid effluents from TMI-1 during the first quarter reporting period of ) 1987. .l A. Liquid (Individual) j L: The first two lines present the maximum hypothetical dose to an l, individual. Presented are the whole body and critical organ doses.
. Calculations are performed on the forr age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for TMI are drinking water, consumption of fish, irrigated cow cilk, irrigated -
goat milk, irrigated. beef, and standing on the shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The. irrigation pathways apply to the sewage sludge. The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant discharge, while occupying an area of shoreline influenced by the plant discharge and consuming the milk and beef fed irrigated vegetation. After calculating the doses to all age groups for all eight organs resulting fom the three pathways described above, the Dose Summary Table presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose. For the first quarter of 1987 the calculated maximum whole body dose received by anyone would have been 4.4E-2 mrem to an adult. Similarly, the maximum organ dose would have been 6.5E-2 mrem to the liver of a teenager. B. Gaseous (Individual) There are seven major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume, (2) inhalation, consumption of
.(3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground.
Lines 3 and 4 present the maximum plume exposure at or beyond the site boundary. The notation of " air dose" is interpreted to mean that these doses are not to an individual, but are considered to be the maximum dose that would have occurred at or beyond the site boundary. The Dose Summary Table presents the distance in meters to the location in the affected sector (compass point) where the theoretical maximum plume q exposure occurred. It should be noted that real-time meteorology was used in all dose calculations for gaseous effluents. Lines 5 and 6 present the dose which could act.ually be received by an individual from the noble gas effluents for the first quarter of 1987. The calculated maximum whole body dose received by anyone from noble gases would have been 2.4E-6 mrem. Similarly, the maximum dose to the skin would have been 7.3E-5 mrem.
The iodines and particulate section described in line 7 represents the maximum exposed organ due to iodine and particulate. This does not include any whole body plume exposure which would be separated out by lines 5 and 6. The doses presented in this section again reflect the maxima exposed organ for the appropriate age group. The first quarter 1987 iodines and particulate would have resulted in a maximum dose of 1.7E-5 mrem to the total body of a teenager residing 3000 meters from the site in the NNE sector. No other organ of any age group would have received a greater dose. C. Liquid and Gaseous (Population) Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations. Liquid person-rem is based upon the population encompassed within the region from the TMI outfall extending down to the Chesapeake Bay. The person-rem for gaseous effluents are based upon the 1980 population and consider the population out to a distance of 50 miles around TMI. Population doses are sumed over all distances and sectors to give an aggregate dose. Based upon the calculations performed for the first quarter, liquid effluents resulted in a whole body population dose of 9.1E-2 person-rem. The maximum critical organ population dose to the liver was 0.10 person-rem. Gaseous effluents resulted in a whole body population dose of 8.7E-4 person-rem. Maximum critical organ population dose to the skin was 2.1E-3 person-rem. I 1 1 i
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INTERPRETATION OF DOSE
SUMMARY
TABLE The Dose Summary Table presents the maximunt hypothetical doses to an individual and the general population resulting from the release of gaseous
)
and liquid effluents from TMI-1 during the second quarter reporting period of 1987. A. Liquid (Individual) The first two lines present the maximum hypothetical dose to an individual. Presented are the whole body and critical organ doses. Calculations are performed on the four age groups and eight organs recommended in Regulatory Guide 1.109. The pathways considered for TMI are drinking water, consumption of fish, irrigated cow milk, irrigated goat milk, irrigated beef, and standing on the shoreline influenced by TMI effluents. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMI. The irrigation pathways apply to the sewage sludge. The " receptor" would be that individual who consumes water from the Susquehanna River and fish residing in the plant discharge, while occupying an area of shoreline influenced by the plant discharge and consuming the milk and beef fed irrigated vegetation. After calculating the doses to all age groups for all eight organs resulting form the three pathways described above, the Dose Summary Table presents the maximum whole body dose and affected age group along with the organ and associated age group that received the largest dose. For the second quarter of 1987 the calculated maximum whole body dose received by anyone would have been 5.1E-2 mrem to an adult. Similarly, the maximum organ dose would have been 7.4E-2 mrem to the liver of a teenager. B. Gaseous (Individual) There are seven major pathways considered in the dose calculations for gaseous effluents. These are: (1) plume, (2) inhalation, consumption of (3) cow milk, (4) goat milk, (5) vegetables, (6) meat, and (7) standing on contaminated ground. j i Lines 3 and 4 present the maximum plume exposure at or beyond the site j boundary. The notation of " air dose" is interpreted to mean that these 1 doses are not to an individual, but are considered to be the maximum dose j that would have occurred at or beyond the site boundary. The Dose 1 Summary Table presents the distance in meters to the location in the ' affected sector (compass point) where the theoretical maximum plume ; exposure occurred. It should be noted that real-time meteorology was I used in all dose calculations for gaseous effluents. Lines 5 and 6 present the dose which could actually be received by an individual from the noble gas effluents for the second quarter of 1987. The calculated maximum whole body dose received by anyone from noble gases would have been 3.1E-3 mrem. Similarly, the maximum dose to the skin would have been 8.7E-3 mrem. l l 1 I J
. * :, , 3 ,
The iodines and particulate section described in line 7 represents-the maximum exposed organ due to iodine and particulate. This does not include any whole body pluma exposure which would be separated out by 11nes. 5 and 6. The doses presented in this section again reflect the. maximum exposed organ for the appropriate age group. The second quarter 1987 fodines and particulate would have resulted in.a maximum dor? of 2.9E-3 mrem to the thyroid of an infant residing 750 meters from the site in the NE sector. No other organ of any age group would have received a greater dose.
.C.. Liquid and Gaseous (Population)
Lines 8 - 11 present the person-rem doses resulting from the liquid and gaseous effluents. These doses are summed over all pathways and the affected populations. Liquid person-rem is based upon.the population encompassed within the region from the TMI outfall: extending down to the Chesapeake Bay. The person-rem for gaseous effluents are based upon the . 1980 population and consider the population out to a' distance of 50 miles ' around TMI. Population doses are sunened over all distances and sectors to give'an aggregate dose. Based upon the calculations performed for the second quarter, liquid effluents resulted in a whole body population dose of 0.56 person-rem. The' maximum critical. organ population dose to the liver was 0.59.
. person-rem. Gaseous effluents resulted in a whole body population dose of 9.6E-2 person-rem. Maximum critical organ population dose to the skin
- was 0.32 person-rem.
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ATTACHMrNT I Summary of Changes to ODCM (Offsite Dose Calculation Manual) The ODCM'was revised (Rev. 7) effective May 15, 1987. This revision was to delete items in the ODCM that were not required by the Technical Specifications. Specifically Tables 8, 9,10,11, and 12 were deleted. Changes .to reflect deletion of these tables as well as other administrative changes were accomplished in this revision. Tables 8, 9, and 10 Tables 8, 9 and.10 are contained in the Radiological Environmental Monitoring Program (REMP) and will still be effective but not required by the ODCM. Table 11 Table 11 (cyrogenic air samples) is deleted in the ODCM but contained in the REMP and used on an as needed basis. Table 12 Table 12 listed the sampling stations. These stations are defined in Tables
~1-7 (0DCM). Therefore, Table 12 is redundant and not required.
i 3 1 l
~
.. . INPUT TO THE SEMI-ANNUAL EFFLUENT ATTACHMENT II REPORT FOR THE FIRST HALF 1987 - CHANGES TO THE TML-1 PROCESS CONTROL PROGRAM (PCP)
Revisions 8 and 9 to the TMI-l PCP (OP 1104-281) were issued 3/19/87 and 6/16/87 respectively. Commentary on the changes for each revision are provided below. In addition a copy of the current revision (Rev. 9) is ) provided. A. Changes introduced by Revision 8
- 1. Section 1.0 - Discussion
- a. Page 4.0, Last Paragraph This paragraph has been added for administrative purposes to tie the applicable solidification procedures to the PCP. This addition was felt to be warranted in order to provide traceability of paperwork as a waste package is processed. It also provides assurance that the stability requirements of 10 CFR 61 are met.
- 2. Section 2.0 - References
- a. Page 4.0, Step 2.6 and 2.7 The Topical Report for Mobile Incontainer Dewaterirl and Solidification System (MDSS) developed by Westinghouse Hittman has been approved by the NRC and included as a reference.
- b. Page 5.0, Step 2.8 The specific Tech. Spec. for the PCP has been added as a reference.
- c. Page 5.0, Step 2.9 The GPUN Radiation Protection Plan has been added as a reference.
- 3. Section 4.0 - Test Solidification of 4 to 10 wt% Boric Acid (Concentrated Waste)
- a. Page 7.0, Note af ter 4.2 Guidance has been given to the technician performing the verification test to ensure tare weights are obtained for use in the calculations. In addition the technician is directed to round off to the nearest gram.
I i 1.0 0501A/0013A
.: 7. . . :b. Page 9.0, Step 4.2.22 i
The technician must now perform a more rigorous testing of the ,~ verification test sample to ensure complete solidification.
~
- Testing now includes challenging the hardness with_ a 10 pound weight applied. by a 1/4 inch diameter rod. This is equivalent to a 200 psi load applied to the surface and provides assurance that the compressive strengths required for stability will be met,
- c. Page 9.0, Step 4.2.24 A verification of the actual quantities of solidification media used during.the full scale solidification is now performed to ensure sufficient material is added so that the final liner contents is greater than 85%.
- 4. Section 5.0 - Test Solidification of > 10 to 20 wt% Boric Acid (Concentrated Waste)
- a. Page 11.0, Note af ter 5.2 Guidance has been given to the technician performing the verification test to ensure tare weights are obtained for use in the calculatio~ns. In addition the technician is directed to round off to the nearest gram.
- b. Page 13.0, Step 5.2.22 The technician must now perform a_more rigorous testing of the verification test sample to ensure complete solidification.
Testing now includes challenging the hardness with a 10 pound weight applied by a 1/4 inch diameter rod. This is equivalent to a 200 psi load applied to the surface and provides assurance that the compressive strengths required for stability will be met.
- c. Page 13.0, Step 5.2.24 A verification of the actual quantities of solidification media used during the full scale solidification is now performed to ensure sufficient material is added so that the final liner contents is greater than 85%.
-5. Section 6.0 - Test Solidification of Waste Oil (12 - 40%)
- a. Page 14.0, Note af ter 6.2 Guidance has been given to the technician performing the verification test to ensure tare weights are obtained for ur in the calculations. In addition the technician is directed to round off.to the nearest gram.
I. )- 2.0 0501A/0013A l - __ _
ATTACHMENT II
. . , . b. The technician must now perform a more rigorous testing of the i verification test sample to ensure complete solidification.
Testing now includes challenging the hardness with a 10 pound weight applied by a 1/4 inch diameter rod. This is equivalent to a 200 psi load applied to the surface and provides assurance that the compressive strengths required for stability will be met.
- 6. Section 7.0 - Test Solidification of Used Precoat J
- a. General The entire section has been revised to reflect the changes l introduced by the governing Westinghouse-Hittman Procedure l F421-P-006, Revision 0 (Dated 4/9/86). In addition, the i
administrative changes added to Sections 4.0, 5.0 and 6.0 are ! also included in this section.
- 7. Section 8.0 - Test Solidification of Bead Resin
- a. General The entire section has been revised to reflect the changes introduced by the governing Westinghouse-Hittman Procedura ';
F421-P-005, Revision 0 (Dated 4/9/86). In addition, the administrative changes added to Sections 4.0, 5.0 and 6.0 are also included in this section. l
- 8. Section 10.0 - Acceptance Criteria
- a. Page 22.0, Note in Section 10.1 The challenge test of the verification sample has been changed to now use a 10 pound load applied to the sample surface.
This test more adequately tests the compressive strengths of the sample.
- 9. Attachment 2 - Solidification Calculation Sheet for 4 to 10 wt%
S>ric .".fd
- a. Page E2-2, Footnote 3 This footnote has been added to flag the technician that the quantities of cement and additives for the full scale solidification should be based on actual waste volumes added to the solidification liner in the event that the maximum waste volume cannot be reached.
I l i 3.0 0501A/0013A . l 1 1 i __ _ __ _ ___a
ATTACHMENT II
. . . . , 10. Attachment 2 - Solidification Calculation Sheet for > 10 to 20 wt%
Boric Acid
- a. Page E4-2, Footnote 3
.This footnote has been added to flag the technician that the quao+.ities of cement and additivies for the full scale solidification should be based on actual waste volumes added to the solidification liner in the event that the maximum waste volume cannot be reached.
- 11. Attachment 5 - Class A Unstable and Stable, Class B and C Test Solidification Data Sheet for Waste Oil
- a. Page ES-1, Section I A calculation has been added to determine the percent of oil used in the solidification. The steps subsequently have been renumbered, as well as in Attachment 6.
- 12. Attachment 7 - Class A Unstable and Stable, Class B and C Test Solidification Data Sheet for Used Precoat
- a. General The entire attachment has been revised as a result of the change to Section 7.0.
- 13. Attachment 8 - Solidification Calculation Sheet for Used Precoat
- a. General The entire attachment has been revised as a result of the change to Section 7.0.
- 14. Attachment 9 - Class A Unstable and Stable, Class B and C Test Solidification Data Sheet for Bead Resin
- a. General The entire attachment has been revised as a result of the changes to Sectior, 8.0.
- 15. Attachment 10 - Solidification Calculation Sheet for Bead Resin
- a. General The entire attachment has been revised as a resu'it of the ,
changes to Section 8.0. 4.0 0501 A/0013A l (- l - I
h
, B .- "Chanq9s introduced'by' Revision 9 ATTACHK NT II
- 1. Section 4.0 - Test. Solidification of 4 to 10 wt% Boric Acid (Concentrated Waste) r a. Page 7-.0, Step 4.1.2 A space for a Quality Assurance representative has been.added in order to document which individual was contacted.
- b. Page 9.0, Step 4.2.22 The technician as well as GPUN Management must now verify the acceptance criteria of the verification test' has been met.
This provides~an independent verification to ensure the process will produce a's acceptable waste form.
- 2. Section 5.0 - Test Solidification of > 10 to 20 wt% Boric Acid (Concentrated Waste)
- a. Page 10.0, Step 5.1.2 A space for a Quality Assurance representative nas been added in order to document which individual was contacted. l
- b. Page 13.0, ' Step 5.2.22 The technician as well as GPUN Management must now verb y the acceptance criteria of the verification test has been met.
This provides-an independent verification to ensure the process will produce an acceptable waste form.
- 3. Section 6.0 - Test Solidification of Waste Oil (12 - 40% Oil)
- a. Page 13.0, . Step 6.1.2 A space for a Quality Assurance representative has been added in order to document which individual was contacted.
b .' Page 15.0, Step 6.2.14 The technician as well as GPUN Management must now verify the acceptance criteria of the verification test has been met. This provides an independent verification to ensure the process will produce an acceptable waste form.
- 4. Saction 7.0 - Test Solidification of Used Precoat
- a. Page 16.0, Step 7.1.3 A space for a Quality Assurance representative has been added in order to document which individual was contacted.
I 5.0 0501A/0013A ; I L L. -
ATTACHMENT II
; , , , b. Page 18.0, Step 7.2.18 The technician as well as GPUN Management must now verify the acceptance criteria of the verification test has been met.
This provides an independent verification to ensure the process will produce an acceptable waste form.
- 5. Section 8.0 - Test Solidification of Bead Resin I
- a. Page 19.0, Step 8.1.3 l A space for a Quality Assurance representative has been added j in order to document which individual was contacted.
)
- b. Page 21.0, Step 8.2.22 '
The technician as well as GPUN Management must now verify the acceptance criteria of the verification test has been met. This provides an independent verification to ensure the process will produce an acceptable waste form.
- 6. Section 9.0 - Alternate Test Solidification Programs
.a. Page 22.0, Step 9.1.4 A space for a Quality Assurance representative has been added in order to document which individual was contacted. l
- 7. Attachment 1 - Class A Unstable and Stable, Class B and C Solidification Data Sheet for 4 to 10 wt% Boric Acid
- a. Page El-4, Section V1, Independent Verification by GPUN Management Signoffs have been added for independent verification of meeting the acceptance criteria for the verification test. An additional signoff has been added to verify that calculations performed using this attachment are correct. This independent verification provides added assurance that stability of the waste form will be achieved.
- 8. Attachment 2 - Solidification Calculation Sheet for 4 to 10 wt%
Boric Acid
- a. Page E2-1, Section VI Independent Verification by GPUN Management A signoff has been added to verify calculations performed by this attachment to again provide assurance that the solidifi-cation media and additives used for the full scale solidification will result in a waste form consistent with the Westinghouse-Hittman Topical Report.
l l 6.0 0501A/0013A , i
)
i
This footnote has been added to flag the technician that the quantities of cement and additives for the full scale solidi-fication should be based on actual waste volumes added to the solidification liner in the event that the maximum waste volume cannot be reached.
- 9. Attachment 3 - Class A Unstable and Stable, Class B and C Test Solidification Data Sheet > 10 to 20 wt% Boric Acid
- a. Page E3-4, Section VI, Independent Verification by GPUN Management Signoffs have been added for independent verification of meeting the acceptance criteria for the verification test. An additional signoff has been added to verify that calculations performed using this attachment are correct. This independent verification provides added assurance that stability of the waste form will be achieved.
10.0 Attachment 4 -' Solidification Calculation Sheet for > 10 to 20 wt% Boric Acid
- a. Page E4-2, Section IV, Independent Verification by GPUN Management A signof f has been added to verify calculations performed by this attachment to again provide assurance that the solidifi-cation media and additives used for the full scale solidification will result in a waste form consistent with the Westinghouse-Hittman Topical Report.
- 11. Attachment 5 - Class A Unstable and Stable, Class B and C Test Solidification Data Sheet for Waste Oil
- a. Page ES-1, Chemistry Parameters Chemistry parameters and balance calibration data have been included. These have been added to be consistent with other attachments and provide traceability of sample results and balance certification.
- b. Page ES-2, Section III, Independent Verification by GPUN Management Signof fs have been added for independent verification of meeting the acceptance criteria for the verification test. An additional signoff has been added to verify that calculations performed using this attachment are correct. This independent verification provides added assurance that stability of the j waste form will be achieved.
7.0 0501A/0013A
r: . 1 ATTACHMENT II j c ,,o 12. Attachment 6 - Solidification Calculation Sheet for Waste Oil j 1
- a. Page E6-2, Section III, Independent Verification by GPUN Management j 1
A signof f has been added to verify calculations performed by this attachment to again provide assurance that the solidifi-cation media and additives used for the full scale solidification will result in a waste form consistent with the Westinghouse-Hittman Topical Report.
- 13. Attachment 7 - Class A Stable, Class B and C Test Solidification Data Sheet for used precoat 1 J
- a. Page E7-2, Section IV, Independent Verification by GPUN {
Management Signof fs have been added for independent verification of meeting the acceptance criteria for the verification test. An additional signoff has been added to verify that calculations performed using this attachment are correct. This independent verification provides added assurance that stability of the waste form will be achieved.
- 14. Attachment 8 - Solidification Calculation Sheet for Used Precoat l
- a. Page E8-2, Section III, Independent Verification by GPUN Management ,
A signoff has been added to verify calculations performed by this attachment to again provide assurance that the solidifi-cation media and additives used for the full scale solidification will result in a waste form consistent with the Westinghouse-Hittman Topical Report.
- 15. Attachment 9 - Class A Stable, Class B and C Test Solidification Data Sheet for Bead Resin
- a. Page E9-1, Section IV, Independent Verification by GPUN t Management Signof f s have been added for independent verification of meeting the acceptance criteria for the verification test. An additional signoff has been added to verify that calculations performed using this attachment are correct. This independent verification provides added assurance that stability of the waste form will be achieved.
8.0 0501A/0013A . l
ATTACHMENT II
. . 16. Attachment 10 - Solidification Calculation Sheet for Bead Resin
- a. Page E10-2, Section III, Independent Verification by GPUN Management l A signoff has been added to verify calculations performed by this attachment to again provide assurance that the solidifi-cation media and additives used for the full scale solidification will result in a waste form consistent with the Westinghouse-Hittman Topical Report.
9.0 0501 A/0013A I
9 .t Number Nuclear = -t Radiological Controls Department 9100-PLN 4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 Applicabikty/ Scope TMI-1 Only. Calculate offsite doses due to Responsible Office radioactive effluents for demonstrating compliance with TMI-1 Tech. Soecs.10 CFR 20. and 10 CFR 50. ADDendiX I. 9140 This docurnent is irDportant to safety 5 Yes O No Effective Date 5/15/87 List of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 7 El-3 6 E2-20 6 E9-1 7 2.0 6 E2-1 6 E2-21 6 3.0 6 E2-2 6 E2-22 6 4.0 7 E2-3 6 E2-23 6 5.0 7 E2-4 6 E2-24 6 6.0 3 E2-5 6 E2-25 6 7.0 6 E2-6 6 E3-1 6 8.0 6 E2-7 6 E3-2 6 9.0 6 E2-8 6 E4-1 6 . 10.0 6 E2-9 6 E4-2 6 11.0 6 E2-10 6 ES-1 6 12.0 6 E2-11 6 ES-2 6 13.0 6 E2-12 6 E5-3 6 ' 14.0 6 E2-13 6 E6-1 7 15.0 6 E2-14 6 16.0 6 E2-15 6 E6-2 ' %., 7J E6,- 17.0 18.0 7 E2-16 -
\ 7 6 E2-17 -
-5 7 El-1 6 E2-18 E7-1 7 El-2 6 E2-19 6 E8-1 7 Signature Concurring Organization Element Date Originator ,$,f ///42 0 $r "- -
Radiological Enaineer. TMI-1 U/ 3N Concurred by d.d Env. Controls I'Y~N M) .y//, [wf Rad. Eno. Coroorate E~ MU Rp,,b Rad. Eng. Manager, TMI-1 O 'd 'N [/M/h-( W{ ~ " " Manager, Rad. Controls THI-1 i ao
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8 Environmental Controls [ AOOO105( 2 84 1.0 Document ID: 0940c L -___________---______--------___________________m
T % Numb:r Nu21 ear 'st-i Radiological Controls Department 9100-PLN-4200.01 i Title Revision No. Offsite Oose Calculation Manual (00CM) 6 i I l i Offsite Oose Calculation Manual l i For i I Three Mile Island Nuclear Station i Unit 1 k s s
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Numbe7 Nuclear rMI-i Radiological Controls Department 9100-PLN 4200.31 I Title Revesson No. 6 Offsite Oose Calculation Manual (OOCM) Table of Contents Page Section 6.0 Introduction 7.0 1.0 LIQUID EFFLUENTS SETPOINTS Liquid Effluent Monitor Setpoints 7.0 1.1 2.0 GASEOUS EFFLUENTS SETPOINTS
'8.0 Noble Gas Monitor 3.0 2.1 l Other Isotope Setpoints 9.0 2.2 10.0 3.0 00SE ASSESSMENT (Licuid)
Liquid Effluents 10 CFR 20 Limits 10.0 3.1 Liquid Effluents 10 CFR 50 Appendix I 10.0 3.2 12.0 3.3 AlternativeDoseCalculationMethodologh(forgM Llauid Effluents h 12.0 4.0 00SE ASSESSMENT (Gaseous) 12.0 4.1 Gaseous Effluents - 10 CFR 20 Limits 12.0 4.1.1 Noble Gases Total Body Dose 12.0 4.1.1.1 12.0 ! 4.1.1.2 Skin Dose 13.0 { 4.1.2 Iodines and Particulate Gaseous Effluents - 10 CFR 50 Appendix I 14.0 4.2 14.0 4.2.1 Noble Gases 5 14.0 l 3 4.2.2 lodines and Particulate I
;; 16.0 4.2.3 Alternative Calculational Methodologies s*
16.0 7 5.0 LIQUID WASTE TREATMENT SYSTEM l l l S.1 Operability 16.0 h 16.0 7 5.2 Representative Sampling Prior to Discharge i k 3.0 A ggps2 l
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Number MNuclear TMI-i Radiological Controls Department 9100-PLN-4200.01 Revision No. Title Offsite Dos & Calculation Manual (ODCM) 7 Table of Contents (Cont'd) Section Page 6.0 GASEOUS WASTE TREATMENT SYSTEM 16.0 6.1 Operability 16.0 7.0 SOLID WASTE MANAGEMENT SYSTEM PROCESS CONTROL PROGRAM 17.0 l 8.0 ENVIRONMENTAL MONITORING INFORMATION
17.0 REFERENCES
18.0 Appendix A: Site Specific Dispersion Values El-1 Appendix 8: Dose Conversion Factors E2-1 4 Appendix C: Bioaccumulation Factors E3-1 TABLES Table E4-1 Dose Factors for Noble Gases and Daughters E4-1 Table E4-2 Dose Parameters for dadiciodines and Radioactive E4-2 Particulate, Gaseous, Effluents Table E5-1 Pathway Dose Factors Due to Radionuclides Other E5-1 Than Noble Gases Table 1 th E6-1 THINS REMP Station Locations - Alr Rak'kttfate and Air Iodine p$e Table 2 THINS REMP Station Locations - Direct Radiation E6-1 (TLD) Table 3 THINS REMP Station Locations - Surface Water E6-3 l l Table 4 THINS REMP Station Locations - Aquatic Sediment E6-3 1 Table 5 THINS REMP Station Locations - Milk E6-4 l I Table 6 THINS REMP Station Locations - Fish E6-4 l l Table 7 THINS REMP Station Locations - Food Products E6-5 l l N71050 (06-86) i 4.0 0940c
l Number Nuclear m -1 Radiological Controls Department 9100-PLN-4200.01 I Title Revision No. 7 Offsite Dose Calcuiatton Manual (00CM) 1 \ l \ Table of Contents (Cont'd) Page Section TABLES (Cont'd) MAP 1 fMINS Locations of Radiological Environmental E7-1 Monitoring Program Stations within 1 Mile of the Site MAP 2 THINS Locations of Radiological Environmental E8-1 Monitoring Program Stations within 5 miles of the Site MAP 3 TMINS Locations of Radiological Environmental E9-1 Monitoring Program Stations Greater than 5 miles from the Site 4fth'< I I I N71050 (06-86) 5.0 0940c
e Numo:r Radiological t ois Oeoartment 9100 PLN 4200.01 ! Revision No. Title ; 3 Offsite Dose Calculation Manual (00CM) i j INTRODUCTION ! I This Offsite Oose Calculation Manual (00CM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents, for purposes of demonstrating compliance with 10 CFR 20, 10 CFR 50 Appendix I, and the technical specifications. Additionally, it provides the l calculational methodology for determining liquid and gaseous effluent monitoring Instrumentation alarm / trip setpoints. The operational Radiological Environmental Monitoring Program's (REMP) sampling locations and descriptions are also included to provide augmentation to the 00CH. 1
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Number Nuslear mt-i Radiological Controls Department 9100-PLN 4200.01 i Title Revision No. 6 Offsite Dise Calculation Manual (00CM) 1.0 LIOUID EFFLUENTS 1.1 Licuid Effluent Monitor Setpoints The liquid effluent line monitors are set such that the concentration (s) of isotope (s) in the liquid effluents will not exceed the concentration limits specified in 10 CFR 20, Appendix B Table II, Col 2. ll To meet the above limit, the alarm / trip setuoints for liquid effluent j monitors and flow measuring devices are set to assure that the following : equation is satisfied: i cf <C (eq 1.1) M where: C= the effluent concentration limit implementing 10 CFR 20 for thelsite, in C1/ml. c= the setpoint, in Ci/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The setpoint is proportic(lal to the volumetric flow of the effluent line and inversely por$naltothevolumetricflow of the dilution stream plus t ken stream. The setpoint value is such that if it were,e t would result in concentrations exceeding the 10 CFR 20;1]M for the unrestricted area, f= flow set point as measured at the radiation monitor location, in l' volume per unit time, but in the same units as F below. F= flowrate of dilution water measured prior to the release point, in volume per unit time. The setpoint concentration is reduced such that concentration contributions from multiple release points aculd not combine to exceed 10 CFR 20 limits. The setpoint concentration is converted to setpoint scale units using appropriate calibration factors. This section of the OOCH is implemented by the Radiation Monitor System a Setpoints procedure and for batch releases the Releasing Radioactive E Liquid Haste procedure. s I E l e
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7.0 I$%2ps2
NumbCr ' I Nuclear TMt-i Radiological Controls Department 9100 DLN 4200.. Revision No. i Title 6 Offsite Daae Calculation Manual (00CM) 2.0 GASEOUS EFFLUENT MONITORING SETPOINTS ! 2.1 Noble Gas Monitors The gaseous effluent monitor setpoints are established to assure that concentrations of isotopes in gaseous effluents do not exceed the limits ! set in 10 CFR 20. The setpoints are established so as to satisfy the more restrictive i setpoint conc. in the following equations: t (eq 2.1.1) l C< 500 l (Fj) x (Kj) x (X/Q) and 3000 (eg. 2.1.2) c< (L1 + 1.1 Mi) x (X/Q) x (Fi) where: l c = setpoint concentration, in uCi k Fj = effluent flowrate at t or, in ::/sec Kj = total body dose in mrem /yr :er pCi/m3 from Table E4-1 l l X/O - highest sector annual average atmospheric discersion factor at the unrestricted area boundary, in sec/m3. from Apoendix A Table A-1 . for station vent releases and A-2 for all other releases. Li = skin dose factor due to ceta emissions from isotope i, in mrem /yr per pC1/m3 from Table E4-1, ;l>; Hj = air dose factor due to gamma emissions from isotope i, in mrad /yr per pCl/m3 from Table E4-1. 'l 1.1 = mrem skin dose per mrad air dose. 500 = annual whole body dose limit for unrestricted areas, in mrem /yr.
~-.
e E 3000 = annual skin dose limit for unrestricted areas, in mrem /yr g The setpoint concentration is further reduced such that the concentration j'
;; contributions from multiple release points would not combine to exceed 10 i CFR 20 limits 1 !
1 8, l
- AOOO105011 82 )
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Number Nuclear ! mt-i l Radiologic 31 Controll CeDartment 9100 PLN 4200.:! ) Rev$on No. j ! Title Offsite 11m m Calculation Manual (ODCM) 6 l The setpoint concentration is converted to setpoint scale units using appropriate calibration factors. This section of the 00CM is implemented by the Radiation Monitor System i Setpoints procedure and the Releasing Radioactive Gaseous Waste procedure. l j l 2.2 Other Isotopes Setpoints for monitors which detect isotopes other than noble gases are , also established to assure that concentrations of these isotopes in j gaseous effluents do not exceed tne limits in 10 CFR 20. l i Setpoints are estaolisned so as to satisfy the following equations: ! (eg. 2.2) c< 1500 (F) x (P t ) x (Dv) 4 where: c = setpoint concentration, in act/cc ; I F = effluent flowrate at tne monitor, in :c/sec ! Pj = pathway dose garameter, in, 4 ::e - Ci/m3 for the inhalation i pathway and mc -mrem per. for re food and ground pathway l from Taole E4-2. yr ] 1500 - annual dose limi to any organ from particulate and iodines and ' radionuclides (other than noDie gases) with half lives greater than eight days. Dy = the annual average atmospheric dispersion factor for the worst-case ,
)
Sector; maximum X/Q, in sec/m3, for the inhalation pathway at the unrestricted area, and maximum D/Q, in m-2, for the food and ground pathway at the nearest existing food and ground pathway locations. Dispersion factors may be read or inter::clated from Table A-1 { 4 (Appendix A) for releases from the station vent and Table A-2 (Appendix A) for all other releases. 9 The setpoint concentration is further reduced such that concentration j E contributions from multiple release points would not combine to exceed 10 ; 2 CFR 20 limits. A The setpoint concentration is converted to setpoint scale Units using l
' appropriate calibration factors. ij k l!
This section of the OOCH is implemented by the Radiation Monitor Systems i g Setpoints procedure and the Releasing Radioactive Gaseous Haste procedure. l 1 AOOO105G 11 8 2 3.0 0C820 L___.._____.___.___ _ _ . _
Number y ENuclear Title j
,,,,,,,,,c,i;";;oisoep,rtment 9100-PLN_4200.01 Revision No.
6 Offsite Dare Calculation Manual (00CM) 3.0 DOSE ASSESSMENT (LIQUID EFFLUENTS) 3.1 Liauid Effluents _10 CFR ?" :,'mits For purposes of demonstrating wmpliance with 10 CFR 20 the following equation must be satisfied: I (Cg + MPCj) <1 (eg 3.1) ! i where: Ci = the concentration of isotope, i, in the liquid effluent after dilution, in pC1/ml. MPC) = the maximum permissible concentration of isotope 1 in liquid affluent in an unrestricted area per 10 CFR 20, Appendix 8. Table 1 II, Col 2 3.2 Liquid Effluents - 10 CFR 50 Appendix I The dose from liquid effluent k the consumption of fish and drinking water. Other H bute negligibly at Three Mile Island. The dose contr " rom all rad cnuclides in liquid effluents i released to the unrestricted area is calculated using the following expression: FW FW j ,
,. j Dose j = E E (Att) X (Cjt) (AW X ppt X 0.2) (eg. 3.2)
X i j X FR t) + ( AFi j I where: , Dose j = the cumulative dose commitment to :ne total body or any organ, j, from the liquid effluents for the total time period, in mrem. i Att =. the length of the 8th time period over which Cjt and F# are averaged for all liquid releases, in hours. Ci = the average concentration of radionuclides, i, in undiluted q g liquid effluent during time period att from any liquid
; release, in pCi/ml.
=
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!! : NOTE: For Sr_89, Sr-90, conservative concentration values :
9 : will be used in the dose calculation based on similar . g : past plant conditions. LLD values are not used in :
- dose calculations.
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Number r"t-1 i Nu21 ear Radiological Controls Department 9100 PLN 4200.01 Revision No. Title 6 OffsiteOdrCalculationManual(00CM) FW4 = undiluted liquid waste flow, in gpm. FPt = plant dilution water flowrate, in gpm FRt = river flowrate, in gpm. DF = dilution factor as a result of mixing effects in the near i field of the discharge structure, taken to be 5. (0.2 = inverse of the OF value) AW the site-related ingestion cose commitment factor to l t j and AFjj = the total Cody or any organ, j, for each identified l principle gamma and beta emitter, in mrem /hr per C1/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway. Values for AHi j are determined by the following equation: , (eg 3.2.1) AHjj = (1.14E5) x (Uw) x (DFjj) where: 1.14E5 = (1.0E6 pCi/pCl) x (1.0E3 ml/<g) + (8760 hr/yr)
= Water consumption rate for a: ult from Reg. Guide 1.109 Uw (Rev. 1), taken to be 730 Kg/jr.
DFi j dose conversion factor for n ,
=
body and fo " or; r. 4 ([de,1,foradultstotal j, in mrem /pC1, from j Appendix S g de 1.109 (Rev. 1)) l
/alues for AFjj are determined by the folicwing equation:
x (BFj) (eg 3.2.2) AFjj = (1.14E5) x (Uf ) x (DFjj) whore: 1.14E5 = defined aeove adult fish consumption, assumed to be 21 Kg/yr from Uf= Reg. Guide 1.109. 0Fi j = dose conversion factor for nuclide, 1, for adult total
,[;
body and for " worst case" organ, j, in mrem /pC1, from f= Appendix B Table B-le (from Reg. Guide 1.109 (Rev. 1)). l 3 Bioaccumulation factor for nuclide, i, in fish, in g BFj = pC1/Kg per pCill from Appendix C Table C-1 (Reg. k Guide 1.109 (Rev. 1)). e5
-7 '
(UCIS8F W -1 NadioloQical Contro 1 C00artment 9100 PLN 4200 01 Revision No. Tity 4[] i Offsite Na Calculation Manual (ODCM) 6 i 3.3 Alternative Oose Calculation Methodolet;y for Liquid Effluants As In al'dernative, models in, or based upon, those presented in Regulatory i Guide 1.109 (Rev. 1) may be ased to make a comprehensive dose assessment. Default parameter values from Reg. Guide 1.109 (Rev. 1) and/or actual site , specific cata would be used wnere applicable. , 4.0 DOSE ASSEESMENT_(GASEOUS EFFLUENTS) 4.1 Gaseo_us Effluents 10 CFR 20 Limits 4.1.1 Noble Gases For noble gases, the following equations apply for total body i and skin dose rate at the unrestricted area boundary: ! I i 4.1.1.1 Total Body i (ea. 4.1.1.1) I Dose Ratetb E (Ki ) x (II ) x (01) ; i where: l Dose Ratetb = average total body ::se rate in current year (mrem / year). Kj = total body dose factor que to gamma emissions for eacn identified noble gas rad onuclide, in mrem /yr ::er pCi/m3 from Tacle E4 1. l
^
II - average annu - lue at the site bouncarv for worspq% M ', in sec/m3 '/alues are l i obtained(DMI able A-1 f 0r releases from station
~
vent, and Table A-2 for all others. I Qj = Release rate of radionucde, i, in C1/sec. 4.1.1.2 Skin ; Dose Rates k E (Li + 1.1 Mj) X (ITQ) X (Qj) ( ea . 4.1.1. 2 ) ! 3 !
- i
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where: Dose Ratey, - average skin dose rate in current year h (mrem / year) e
- i k t I e
AOOO1050tt 32 12 ) OCE20 1
Number Nuclear t"t-i Radiological Controls Department 9100 PLN-4200.01 l Revision No. Title 6 Offsite Sa Calculation Manual (00CM) Lj = skin dose factor due to beta emissions for each identified noble gas radionuclides, in mrem /yr per pC1/m3 from Table E4-1. l Mj . air dose factor due to gamma emissions for eacn identified noble gas radionuclides, in mrad /yr per C1/m3 from Table E4-1. l 1.1 - mrem skin dose per mrad air dose. Converts air dose j to skin dose. ! Qj . release rate of radionuclides, i, in pCl/sec. l 4.1.2 Iodines and Particulate For lodine and particulate isotopes, the following equation applies: Dose RateIp = I Pj Dy Q3 (eg 4.1.2) I where: Dose Rate Ip - averace n'.chrateinthecurrentyear Pj = e parameter f:r radionuclides other than f, noble gases for tne inhalation pathway, in mrem /yr per Ci/m3. and for the food and i ground plane pathways, in m2 - mrem /yr per pCl/sec from Table E4-2. The dose factors are il based on the critt:al individual organ and most ! restrictive age group. Dv = the annual average atmospheric dispersion parameter, for the worst-case sector, for estimating the dose to the critical receptor; X/Q for the inhalation pathway, in sec/mJ, and j i D/gforthefoodandgroundplanepathways,in
- m. For H-3, only X/Q's are used for all pathways. Dispersion factors may be read or ;
e interpolated from Table A-1 (Appendix A) for E station vent releases and Table A-2 (Appendix A) 2 for all other releases. j E Qj - release rate of radionuclides, i, in pCl/sec. I a-l A0001CSO 11 -8 2 13.0 X8:2 b_------------------ l
Numb:r ' I
.(UCl88F Radiological Controls Department 9100 PLN 4E0 21 Revision No. p Title 6
Offsite Dose calculation Manual (00CM) 1 4.2 Gaseous Effluents - 10 CFR 50 Appendix I i 4.2.1 Noble Gases I The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using tne i following expressions:
, 1 Dose f - (3.17E-8) x C (Mj) x(IT6) 4 (01) (ea. 4.2.1.1) ]
i and Oose 6 = (3.17E-8) x I (Nj) x (f7Q) x (Q1) (eq. 4.2.1.2)
]
i where: Doser . mrad gamma dose during any specified time period. mrad ceta dose during any specified time period. l Ooser3 f Mt. air aose factor due : gamma emissions for each identified noble gas "scionuclide, in mrad /yr per ; aCi/mJ, from Table El-Nt = air dose factor due :o ceta emissions for each ' identified noble gas radionuclides, in mrad /yr per pCi/m3, from Table E4 ' Y ' _ W Wncentration, for 'the X/Q = the annual worst-case s or any area at or ceyond the unrestricted area boundary, in sec/m3 Values may be read or interpolated from Table A-1 (Appendix A) for releases from the station vent and Table A-2 (Appendix A) for all other releases. l
'i release of noble gas radionuclides, i, in C1, over ,l Qi = ij the specified time period. ! .
I 5 3.17E inverse of the number of seconds in a year. 1 I i i
)
2 4.2.2 Iodines and Particulate i l 4
; The dose to an individual from radioiodines and radioactive
~ materials in particulate form with half-lives greater than 8 i j
h days in gaseous effluents released from the site to an unrestricted area is determined by solving the following g expression: A000105011 8 2 14.0 ?05:D
. j l
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Numte l l
@ Nuclear ,,,,,io,icaisiisoeoertment 9 - "*"
Revision No.
~
Title 6 Offsite nets Calculation Manual (ODCM) Doseo - (3.17E-8) xERi Dy Qi (eq. 4.2.2) l l 1 where: Doseo= dose to an individual from radiolodines and i radionuclides in particulate form, with half lives greater than 8 days, in mrem, during any desired time period. , Ria the dose factor for each identified radionuclides, 1, ' I in, mrem /yr per Ci/m3 for the inhalation pathway ! and m2. mrem /yr per pCi/sec for other pathways, I l from Table E5-1. ] Since there is minimal or no elemental lodine released from the cendensor off-gas air ejectoir (see NUREG 0017) all Iodine R$ values in Taele E5-1 for j all pathways, except the inhalation Datnway, are i considered to be zero when performing dose ! calculations for relea:es from tne condensor off-gas i ; air ejector. Only ca':; ate the dose due to the l inhalation oathway fr' :ondensor off-gas air ejector l iodines. Dy = the annual average a:mosche c dispersion parameter. for the worst-case sec;3r, Qr estimating the dose to an individual 90 t46 cr ical location; X/Q, in sec/m3, fo M@69thway:paa'1ation In the case ofpathway, H-3 only and D/Q I m-2, for ep X/Q's are sed for all cathways. Dispersion factors may be read or interpolated from Table A-1 (Appendix A) for station vent releases and Table A-2 i (ADpendix A) for all otner releases. Qj = release of radiolodines, and radioactive materials ; in particulate form in gaseous effluents, i, with , half-lives greater than 8 days, in pCi, cumulative over the specified time period. E
~
- 3.17E 8 inverse of the number of seconds in a year. ;
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l a i AOOO 105011 - 8 2 15 3 00828
Number rMr-i i 4UCl68r Radiological Controls Department 9100 PLN 4200.01 Revision No. Title 6 Offsite Oose Calculation Manual (00CM) 4.2.3 Alternative Calculational Methodologies ; As an alternative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Reg. Guide 1.109 (Rev. 1) and/or actual site specific data can be used where applicable. l Dispersion parameter values for such analyses may be drawn from Table A-1 and A-2 or may be computed from site meteorological l l i data for the specified time period using acceptable models sucn I as tnose presented ',n Regulatory Guide 1.111. i i S.0 LIQUID WASTE TREATMENT SYSTEM l S.1 Operability The Liquid Waste Treatment System as described in Section 11 of the Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is availaple to perform its intended function: a) MiscellaneousWasteEvaporator(WLbeUk) or Reactor Coolant Evaporator (WDL-Z1A) Q b) Waste Evaporator Co t em nerali:er (WDL-K3 A or B) { c) Waste Evaporator Con'densate Storage Tans (WDL-T 11 A or B) d) Evaporator Condensate Pumps (WOL-P 14 A or 8) S.2 Representative Sampling Prior to Discharge i All liquid releases from the Liquid Waste Treatment SystemToare made provide through the Waste Evaporator Condensate Storage Tanks. thorough mixing and a representative sample, the contents of the tank are recirt.ulated using one of the Waste Evaporator Condensate Transfer Pumps. 6.0 GASEOUS WASTE TREATMENT SYSTEM 6.1 Operability Operability of the Gaseous Waste Treatment System is defined as the { 5 ability to remove gas from the vent header / tank gas spaces and store it s under a higher pressure in the Waste Gas Decay Tanks for subsequent release. i a-l 9
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NumbIr Radiological o rois Department 9100-PLN-4200.01 Title Revision No. Offsite nota Calculation Manual (00CM) 7 7.0 SOLID WASTE MANAGEMENT SYSTEM - PROCESS CONTROL PROGRAM , (The Process Control Program is available as a separate document, see LIL 133, dated June 24, 1981.) 8.0 ENVIRONMENTAL MONITORING INFORMATION i The Radiological Environmental Monitoring Program shall be conducted as outlined ! in the THINS Unit 1 Technical Specifications. Sampling locations will be as i indicated in Tables 1 through 7 and as depicted on the maps. ; l l l 4 l l
\ l
\ l c
1 ~ g ii 1 3 7 2 A000105011 92 17.0 0940c
Numb:r Nuslear tst-i Radiological Controls Deoartment 9100-PLN 4200.01 l Revision No. Tetle 6 Offsite Oose Calculation Manual (00CM) References i
- 1. Boegli, J.S., H.L. Britz, R.R. Bellamy, and R.L. Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Pcwer Plants".
NUREG-0133. October 1978.
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I". U.S. NRC Regulatory Guide 1.109 (Rev 1). October 1977. I
- 3. " Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Nuclear Safety Conformance to the Design Objectives of 10 CFR 50, Appendix I"...
Associates. May 1976.
- 4. Technical Specification for the Three Mile Island Nuclear Generating Station Unit 1, Appendment No. 72, Operating License No. OPR-50, Docket No. 50-289.
August 1981.
- 5. NUREG -0017, PB-251 718, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR."
- 6. G.R. Hoenes, J.K. Soldat, " Age-Specific Radiation Jose Commitment Factors For A One-Year Chronic Intake". NUREG - 0)72. Novemeer 1977. Regulator Guide 1.109 Supplement. t
- 7. " Environmental Radiation Doses From Difficult-To-Measure Nuclides", EPRI i NP-3840, RP 1560-3 Final Report January 1985.
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Numb r i N -1 NUCISar Rad!', logical Controls Department 9100 PLN 4200.01 i Revision No. D' 6 Offsite Oose Calculation Manual (00CM) l t l l l l Ti,\1 Appendix A f< Site Specific Dispersion Va1Jes I i 5 s 2
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Number i THE-I ( Radiological Controls Department 9100-PLN-4200.01 Title Revision No. 6 Of'fstte Oost Calculation Manual (00CM) , Atmospheric Olspersion Factors For Three teile Island Unit i Release - Station Vent Table A-l Annual Olltance (Meters) Season - Annual Mean E70-secle3 5ector 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 11 M i -07 4.0,:-07 P.4'.:-07 l l . 5" :- 0 11 6.8:l l-08 8 .: 3 :-( l .li ? -( 8.ll7 :-09 !i. OE4 4 . ' 31:- 0i u i .Li ' O
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N J.11 :-(i . 98E-0'l 1.17E-09 2.04 :-lQ ll :-10 7.87 :-11 2 12 E ' 8.97 '- 10 '
.1 9 l1 ; 4.0 :' P 4.0 m: , .6,' :-Ci .57 :-O'l 9.13 :-10 4.lil' :lQ 4.' il :-10 1.74 :1 ) 97 :- 1.30 '- l ' i t ' 7 :' , - ,
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.114-09 1.36 : -O'l i S 1. <0 -O . .721:-09 1 35 :-04 4 U.i :-li) . 0 i, :-10 1 36 :-l') 3 57' li n 20 ill 6 25 :-IP 3 lo '- ,
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Title Revision No. l l 0# site Oose Calculation Manual (00CM) 6 i l I Atanspheric Dispersion Factors For Three Mlle Island Unit 1 telease . Ground Table A-2 . Annual Olstance (MeterF) Season - Annaal Mean E70-sec/M 1 Sector 610 2443 4022 5631 7240 17067 24135 40225 54315 72405 f n 4.2S:-00 5 6 :-0 P . 7" :-0 6' > :-0 , 1.19 :-O ' i.71-07 31 : 07 P.00 :-0 -
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.16E-0 ; 4.49E-00 J.46f-09 1.52E-09 6.2'.2-10 1 02E 10 1 24 :1 ii.31 :-IP 3.92E-12 mm I 31 :-07 21E-0 i 4.67 :-Oil < .h ' -09 i Sil :-09 6.49':-10 i :6&lo i 30 :- i, 57 :-I P 4.0 :-IP n': i 05 :-07 1 24 :-O'l 1 64 :-0'l ".5 : 10 4, W: 10 1 74E-10 3W-il 1.30 :- i , . 57 :-IP 40 :-l?
E NI: 1.10 :-07 '/.60 :-04 .T2 :-Oi, 3.oi :-lo 4.# :-10 1 ( 31:- 10 4 17J-il 1. 3t i '- l' o.90 :-IL 4.2 -lJ E 1 63 :-07 6.12 :-01. <
' ,4 '-C'i :-00 7. -10 2 69 :- 10 6 14E-Il 2.0 :-l .02 -l 6 3< :-12 ES : I 60E-07 1 24 : J.l 2 :-0'l 30 :-00 7 87 :-10 2.98 : 10 Bif-il 2 20 :-l I.13 :-il 1 00':- 12 l 5 : 2 25E-07 1. 5 5l: -01 :L s2 :-00 .62 :-O' t 9.83 :-80 3.72 :-10 50E-Il 2.78 l-11 1.41 :-l ' '
8.74 ;-12 55 : 210(-07 I 930 08 .50 :-04 o 10 -O' i 2 f4 :-09 1 04 :-09 $G10 23 :-11 1.05 :-l 6 54 ' 12 5 n 10t-07 ~ 1 01L-08 3.91':-09 J.14 :-09 i: 3 :-09 5 43 :-10 8 87E-ll I 08 :-11 5.50 :-IP 3.41 -42 l 55W 6.32T-0i 5 8T :-09 2.25 :-09 2L :-09 7. L4,:- 10 3 T5 :-i0 5 dE-Il 6 24 :-12 3.16 :-10 I 97 :-12 SW 6 82bO8 4 fT!:-09 i.07 :-09 4.9;. :-10 2.98 :- 10 1 13 :-10 2 sif Tl 8 42 : 12 4 27 :-10 2 65 :- 12 usa 0 73i-08 6 . 1 11:-09 l.52 :-09 7 05 :-10 4.25 :-10 I 64t 10 3 edi-il i 20 :-11 6 09 :-10 3 78 :-12 w 50E-07 I 03 :-08 2.34 :-04f I 08 :-09 6 55 :- 10 .AM-10 6 Esi-il I 85 :-il 9 37 IP 5 82 :- 12 l mww 35E-07~TO-:-09 2.11 :-O'i 9.74 :-10 5 90 :- 10 h- '1 '- 10 $ 'CE Il I 66Gli 8.44 :-l; 5 24 l- 12 NW I T9GU 7 531:-09 l 11 :-O'l 7 61, :-10 4.71 M W ll :- 10 4 OE Il 1 35i-il 6 83 :-1; 4 24 :-12 NNu i 07E-07 9 871:-09 3.83 -0;i 2 . 0' :-09i _le M 5 a2 :-10 8 HE lL I 06E-il 5 38 -l; 3 34 :-12 y a e
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Revision No. , 6 Offsite Dose Calculation Manual (00CM) i Appendix 8-la ! I f Page 1 of 3 j i INHALATION DOSE FACTORS FOR ADULTS * (MREM PER PCI INHALED) ! l NUCLIOE BONE LIVER T. 800Y THYROIO KIONEY LUNG GI-LLI 1.58E_07 1.58E-07 1.58E_07 1.58E-07 1.58E-07 1.58E-07 H 3** NO DATA 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E_07 4.26E-07 4.26E-07 C 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E_06 1.28E.06 1.28E-06 ; NA 24 1.65E-04 9.64E.06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 P 32 NO DATA 1.25E-08 7.44E-09 2.85E-09 1.8CE-06 4.15E-07 CR 51 NO DATA 9.67E-06 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 1.55E-10 2.29E 11 NO DATA 1.63E-10 1.18E-06 2.53E-06 MN 56 NO DATA 7.54E-07 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 FE 59 1.47E_06 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E_04 1.33E.05 CO 58 NO DATA 3.56E_05 CO 60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 1.81E-06 NO DATA 2.23E-05 1.67E_06 NI 63 5.40E-05 3.93E-06 ____________________.____._______.___._______.- 4(0 DATA 7.00E-07 1.54E_06 NI 65 1. 92 E-10 2.62E.11 1.14F-11 ' 0 OATA 1.83E-10 7.69E 5.78E 10 8.48E-07 6.12E-06 CU 64 NO DATA 6.68E-06 1.29E-05 5.8 OATA 8.62E-06 1.08E-04 ZN 65 4.05E-06 8.14E-12 5.65E-13 NO DATA 5.27E_12 1.15E-07 2.04E-09 ZN 69 4.23E-12 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 BR 83 NO DATA NO DATA 2.05E-13 3.91E-08 NO DATA NO DATA NO DATA BR 84 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E.24 BR 85 NO DATA NO DATA 2.08E-06 1.69E.05 7.37E-06 NO DATA NO DATA NO DATA RB 86 NO DATA 4.18E-19 4.84E.08 2.41E-08 NO DATA NO DATA NO DATA RB 88 NO DATA 3.20E_08 2.12E.08 NO DATA NO DATA NO DATA 1.16E-21 RB 89 NO DATA 4.37E-05 1.09E-06 NO DATA NO DATA 1.75E_04 SR 89 3.80E-05 NO DATA 9.02E-05 1.24E-02 7.62E-04 NO DATA NO DATA 1.20E-03 n SR 90 NO DATA
- 7.74E-09 3.13E.10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 91 NO DATA 5.38E-06 2 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E_06 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 E Y 90 2. 61 E-07 5 .......-_____________.____ _________ ______._____...______-_-_..__ ___._______...__--- 1.66E.10 91M 3.26E-11 NO DATA 1.27E.12 NO DATA NO DATA 2.40E-07 i Y 4.31 E_05 W Y 91 5.78E-05 NO DATA 1.55E_06 NO DATA NO DATA 2.13E-04 1.96E.06 9.19E-06 l
Y 92 1.29E_09 NO DATA 3.77E.11 NO DATA NO DATA
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i \ . . Number . I e Nuslear 7"t-' Radiological Controls Department 9100 PLN 4200.01 Revision No. I Title i 6 Offsite Dose Calculation Manual (00CM) Appendix 8-la (Cont'd) ! i Page 2 of 3 INHALATION OOSE FACTORS FOR AOULTS* , (MREM PER PCI INHALED) ; T. BODY THYROIO KIONEY_ LUNG GI-LLI . BONE _ LIVER NUCLIOE. NO DATA 6.06E_06 5.27E_05 93 1.18E-08 NO DATA 3.26E 10 NO DATA 1.38E-05 Y 2.91E-06 NO DATA 6.77E-06 2.21E-04 i ZR 95 1.34E_05 4.30E-06 6.54E-05 1.13E-09 NO DATA 3.71E.09 9.84E-06 ZR 97 1.21E 08 2.45E-09 NO DATA 9.67E-07 6.31E-05 1.30E-05 ........- NS 95 1.76E-06 9.77E-07 5.26E-07 3.10E-05 2.87E-09 NO DATA 3.64E-08 1.14E-05 MO 99 NO DATA 1.51E-08 5.20E-07 4.63E 12 NO DATA 5.52E-12 9.55E.08 TC 99H 1.29E-13 3.64E-13 1.35E-13 4.99E-08 1.36E-21 TC 101 5.22E 15 7.52E 15 7.38E-14 NO DATA 1.38E-05 8.23E-08 NO DATA 7.29E-07 6.31E-05 RU 103 1.91E-07 NO DATA 6.02E-06 3.89E 11 NO DATA 1.27E-10 1.37E-06 RU 105 9.88E.11 NO DATA _____..-_-_ ...--_.----___---_----------------_-_______ NO DATA 1.67E-05 --_--__-.....-_-_----------_-- 1.17E-03 1.14E-04 RU 106 8.64E-06 NO DATA 1.09E-06 3.78E.05 7.43E-07 NO DATA 2. 06 5.79E-04 AG 110M 1.35E-06 1.25E-06 1.26E-05 1.58E-06 6.75 2.18E-04 58 125 6.67E-06 7.44E-08 8.83E-06 5.84E-0 E-06 3.92E_05 TE 125M 4.27E-07 1.98E-07 _____._--____-_____-.----_...-.....- __ 4.11E-07 5.72E-06 1.20E-04 1.87E-05 ! , TE 127M 1.58E_06 7.21E-07 1.96E-0 7.17E-06 i 3.87E-11 1.32E-10 6.37E-10 8.14E-07 i TE 127 1.75E-10 8.03E.11 1.98E-07 4.30E-07 4.57E-06 1.45E_04 4.79E-05 l TE 129M 1.22E-06 5.84E-07 __-a ; 2.34E-11 2.42E-07 1.96E-08 6.22E-12 2.99E-12 1.55E-12 4.87E-12 TE 129 3.86E_08 1.82E-05 6.95E-05 ; 8.74E-09 5.45E-09 3.63E-09 6.88E-09 TE 131M 1.17E_12 5.46E-12 1.74E-07 2.30E-09 TE 131 1.39E-12 7.44E-13 4.49E-13
.__ ___..__.....__. . _.._____.___...---__---___-__ 2.37E 08 1.82E-07 3.60E 05 6.37E-05 TE 132 3.25E-08 2.69E-08 2.02E-08 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 130 5.72E-07 1.68E-06 6.60E-07 7.85E-07 7.66E-06 NO DATA 3.15E-06 4.47E-06 2.36E-06 1.49E-03 I 131 1.43E-05 6.48E-07 NO DATA 5.08E-08 l I 132 1.45E-07 4.07E-07 1.45E-07 i.!1E-06 i 1.85E-06 5.65E_07 2.69E-04 3.23E-06 NO DATA a I 133 1.08E-06 3.44E-07 NO DATA 1.26E.10 i 8.05E-08 2.16E-07 7.69E.08 3.73E-06
! I 134
= __------ _ --_....--_.-_______.__--_-____ ______ ____-----_-_______________
1.39E-06 NO DATA 6.56E-07 ... . 2 3.35E.07 8.73E-07 3.21E_07 5.60E.05 I 135 NO DATA 3.59E-05 1.22E-05 1.30E.06 f CS 134 4.66E-05 1.06E-04 9.10E_05 1.46E_06 l $ 1.38E_05 NO DATA 1.07E-05 1.50E_06 i l 0 CS 136 4.88E-06 1.83E-05 ;
- - - - - - . _ _ _ _ . . _ _ . _ _ _ - - _ . . _NO_OATA _ . _ - _2.78E-05
- . _ _ _ _9.40E-06
_ _ _ _ -1.05E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 2.33E-13 i 4.05E_08 NO DATA 6.00E-08 6.07E-C9 4.14E-08 7.76E-08 4.70E.07 1.12E_07 , @ CS 138 3.42E-12 NO DATA 7.78E-14 g i 1.17E-10 8.32E_14 1
. . . . . _ _ - - - - _ _ . - . . . . _ _ _ _ _ _ . _ _ _ _ _ _ . _ - - . _ _ - - - - - _ _ - - - _ _ _. _1
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l Number h]gy THI-1 Radiological Controls Decartment 9100 PLN 4200.01 l Revision No. Title 6 Offsite Dose Calculation Manual (00CM) - --t Appendix B-la (Cont'd) . t Page 3 of 3 INHALATION DOSE FACTORS FOR AOULTS* (MREM PER PCI INHALED) Il{, ; BONE LIVER f. 800Y THYROIO KIONEY__ LUNG GI-LLI NUCLIOE 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73F-05 BA 140 4.88E-06 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA 141 1.25E-11 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 BA 142 3.29E-12 -___----- _____-_____-_-_-__-______--_---___-__-_-----___----___-_-_-____---______-_-5.73E-05 4.308-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 LA 140 2.64E_07 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 l' LA 142 1.50E-05 2.49E_06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 CE 141 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 143 2.33E-08 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 CE 144 4.29E-04 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 143 1.17E-06 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 PR 144 3.76E-12 7.62E-07 e. 56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 NO 147 6.59E_07 8.85E 10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 W 187 1.06E-09 NPh3h h$hhk-Oh h bbk bh Ihhk-Oh 0bkhI b$hhh Oh $$h0h Oh 5$4hk Oh i
- Dose factors of internal exposure are for continuous intake over a one_ year ]l period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose f actor for nuclides not included in this table may be obtained from NUREG-0172, 00CM Reference 6.
Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed througn the skin. 0 l b ^ W 2pez E2-4 l
I Number I MUSl gar mI-I r Radiological Controls Department 9100-PLN 4200.01 ! Revision No. Title 6 Offsite Dose Calculation Manual (00CM) l Appendix B-Ib Page 1 of 3 l j INHALATION DOSE FACTORS FOR TEENAGER
- N l (MREM PER PCI INHALED) L 1 1
~UNG GI-LLI NUCLIOE BONE LIVER T. BODY THYROIO KIdf 1.59E-07 1.59E-07 1.59E-07 1.59E-07 i if 3** NO DATA 1.59E-07 1.59E-07 6.09E-07 H
6.09E-07 6.09E-07 6.09E_07 6.09E-07 } C 14 3.25E-06 6.09E-07 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 NA 24 1.7"C-06
..__-____________.-___________________-________ NO DATA NO .___________._____
DATA 1.16F-05 32 2.36E-04 1.37E-05 8.95E-06 NO DATA 3.75E-07 P 1.69E-08 9.37E-09 3.84E-09 2.62E-06 CR 51 NO DATA NO DATA 8.35E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 , MN 54 NO DATA 6.30F-06 i NO DATA 2.24E-10 1.90E-06 7.18E-06 i MN 56 2.12E IO 3.15E_11 7.99E-07 FE 55 FE 59 NO DATA 4.18E-06 1.99E-06 2.98E-06 4.62E-06 6.93E-07 1.79E-06 NO DATA NO DATA NO DATA NO DATA 1.55E-05 1.91E-04 2.23E-05 il
. . . . . . - _ - - _ - _ - _ - _ - _ _ . _ _ NO __ . - - . NO DATA
. -DATA
- - - - -1.68E-04
- - . . . . . 1.19E-05 CO 58 NO DATA 2.59E_07 3.47E-07 3.24E-05 2.48E.06 NO DATA NO DATA 1.09E-03 CO 60 NO DATA 1.89E_06 3.84E-05 1.77E-06 2.47E-06 NO DATA N0 OATA NI 63 7.25E-05 5.43E-06
___-__.___-_______._____.--__---__---_-----___-_ -_--_- _-__-__-_--_-..._____~___.--__, NO DATA NO DATA 1.17E-06 4.59E-06 l NI 65 2.73E-10 3.66E-11 1.59E-11 7.68E-06 8.01E.10 1.39E-06 CU 64 NO DATA 2.54E 10 1.06E.10 NO DATA 5.83E-06 1.08E-05 1.55E-04 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA
-_________________________..____...._____.._________-__.______________ 3.56E-08 NO DATA 7.53E-12 1.985-07 ZN 69 6.04E-12 1.15F-11 8.07E-13 LT E-24 NO DATA NO DATA NO DATA BR 83 NO DATA NO DATA 4.30E-08 LT E-24 NO DATA NO DATA NO DATA BR 84 NO DATA NO DATA 5.41E-08
- . - - . _ _ _ . . . _ _ . _ _ _ _ . - _ _ _ _ _ _ _ . . . . _ _ _ _ _ NO _ _DATA
_ _ _ _ _NO_ DATA _ _ _ _ _LT _ _E-24 NO DATA 2.29E-09 NO DATA l BR 85 NO DATA NO DATA NO DATA NO DATA 2.21E-06 i BR 86 NO DATA 2.38E-05 1.05E-05 3.65E-15 ( NO DATA NO DATA NO DATA RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA 4.22E-17 4.40E-08 2.91E-08 NO DATA RB 89 NO OATA NO DATA NO DATA 3.02E-04 4.64E-05 SR 89 5.43E-05 NO DATA 1.56E-06 9.56E-05 8.35E-04 NO DATA NO DATA 2.06E-03 a SR 90 1.35E-02 NO DATA
; _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ . - _ - -3.24E-05 4.39E-10 NO DATA NO DATA 7.59E 06
________----______________ATA 1.10E-08 NO D 1.49E-05 5 SR 91 5.08E-11 NO DATA NO DATA 3.43E-06 g SR 92 1.19E.09 NO DATA NO DATA 3.66E-05 6.99E-05 1.00E.08 NO DATA g Y 90 3.73E-07 NO DATA
- .____________.._____________-._-___ NO DATA NO DATA 4.00E_07 3.77E_09 4.63E-11 NO DATA 1.77E_12 Y 91M NO DATA NO DATA 3.67E_04 5.11E-05 ,
Y 91 8.26E_05 NO DATA 2.21E.06 2.06E-05 5.36E-11 NO DATA NO OATA 3.35E_06 Y 92 1.84E-09 NO DATA
.__-__....wmm-e_-.--m____me._--___m-_&_e-_e_.._me_em____ge.______m.e__-e--__---wo-4 E2-5
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Nus' lear Radiological C:ntrols Deoartment 9100 PLN 4200.01 Revmon No Title 6 l Offsite Dose Calculation Manual (00CM) , Appendix B-lb (Cont'd) Page 2 of 3
, I INHALATION DOSE FACTORS FOR TEENAGER * .
(MREM PER PCI INHALED) T. 800Y THYROIO KIONEY_ LUNG GI_LLI__ NUCLIDE BONE _ LIVER NO DATA 1.04E-05 7.24E-05 l 1.69E-08 NO DATA 4.65E-10 NO DATA ' Y 93 8.42E-06 3.36E-04 1.86E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 7.88E-05 1.57E-09 NO DATA 5.15E-09 1.62E-05 ZR 97 1.72E-08 3.40E-09
.. _____________... ________________.. __.-___________..________ .____..__.___________,l 1.21E-05 7.08E-07 NO DATA 1.25E-06 9.39E.05 NB 95 2.32E-06 1.29E-06 1.92E-05 3.36E-05 !
2.11E_08 4.03E-09 NO DATA 5.14 -08 MO 99 NO DATA ' 12 1.44E_07 7.66E-07 l 1.73E-13 4.83E-13 6.24E-12 NO DATA . TC 99M 1.90E-13 8.34E-08 1l09E-16 7.40E-15 1.05E 14 1.03E-13 N 1.36E-05 TC 101 A 9.29E_07 9.79E-05 RU 103 2.63E-07 NO DATA 1.13E-05 RU 105 1.40E.10 NO DATA 1.12E-0Q{ODATA 5.42E-11 N 1.76E-10 2.27E-06 ______..____-._____-__---------_____.___________-__---__._____.-_.. 2.38E-05 2.01E-03 1.20E-04 RU 106 1.23E-05 NO DATA !.55E-06 NO DATA 3.41E-05 9.99E-07 NO DATA 3.13E-06 8.44E-04 AG 110M 1.73E-06 1.64E-06 3.42E_04 1.24E-05 1.01E-07 2.15E-06 8.80E_09 0.0 SB 125 9.23E-06 NO DATA 6.70E-05 9.38E-06 6.10E-07 2.80E-07 8.34E-08 1.75E-07 TE 125M
. _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . . - - - _ _ _ _ . - - _ - - _ _ _ . . . . . . - _ _ _ _ _ _ _ _ _1.99E-05 2.73E-07 5.48E-07 3.17E-06 2.07E-04 TE 127M 2.25E-06 1.02E-06 1.40E.06 1.01E-05 1.t4F-10 5.52E-11 1.77E-10 9.10E_10 TE 127 2.51E-10 5.49E-06 2.47E-04 5.06E-05 l 1.74E-06 8.23E-07 2.81E_07 5.72E-07 TE 129M
____ . ..__________.. .._______. ...... __-._---__ ___________ 3.32E-11 _______-. 4.12E-07__--...----._-!l 2.02E-07 4.22E-12 2.20E-12 6.48E-12 TE 129 8.87E.12 9.06E-09 5.49E-08 2.97E-05 7.76E-05 i TE 131M 1.23E-08 7.51E-09 5.03E-09 1.89E-09 1.55E-12
- 72E-12 2.92E-07 TE 131 1.97E.12 1.04E-12 6.30E-13 .
3.07E-08 2.44E-07 5.61E-05 5.79E-05 I TE 132 4.50E 08 3.63E-08 2.74E-08 1.14E_06 1.86E-04 3.44E-06 NO DATA I 130 7.80E.07 2.24E-06 8.96E_07 8.11F-07 6.14E-06 3.30E-06 1.83E-03 ' 05E-05 NO DATA i I 131 4.43E-06 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.29E 06 7.78E-07 3.65E-04 4.49E-06 NO DATA n I 133 1.52E-06 2.56E-06 NO DATA 2.55E-09 1.05E-07 4.94E-06 4.58E-07 5 I 134 1.11E-07 2.90E-07 8.69E-07 4.36E-07 7.76E-05 1.86E-06 NO DATA 2I 135 4.62E-07 1.18E-06 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 6.28E-05 1.41E-04 1.36E-06
$ CS 134 1.71E-05 NO DATA 1.38E.05 2.22E-06
- CS 136 6.44E-06 2.42E-05
_______ _____ .._...._______________. NO OATA 3.80E-05 1. 51 E_05 1.06E-06 CS 137 8.36E-05 1.06E-04 3.89E-05 3.38E 11 5.58E-08 NO DATA 8.28E-08 9.84E-09 5.82E-08 1.07E-07 8.06E
$C5138 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E 07
- BA 139 1.67E_10 - - .
l____...........-.........-_---__---_..__-_-___.._ E2-6
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_ _ _ _ _ _ _ _ _ _ _ _ _ - l
Number mt > l Nuclear Radiological Controls Deoartment 9100 PLN 4200.01 Revision No. Title 6 Offsito 00se Calculation Manual (00CM),, Appendix 8-lb (Cont'd) Page 3 of 3 INHALATION DOSE FACTORS FOR TEENAGER * (MREM PER PCI INHALED) T. B00Y THYROIO KIONEY LUNG ._ GI_LLI NUCLIOE BONE LIVER 4.40E.07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA 140' 6.84E-06 8.38E-09 9.33E-14 5.93E.13 NO DATA 1.23E_14 4.11E-07 l BA 141 1.78E-11 1.32E-14 5.99E-20 4.63E-15 2.84E-13 NO DATA 3.92E_15 2.39E-07 BA 142 4.62E-12 l 2.68E-05 6.09E.05 2.95E-08 7.82E.09 NO DATA NO DATA LA 140 5.99E-08 1.27E.06 1.50E.06 5.31E-11 1.32E.11 NO DATA NO DATA LA 142 1.20E-10 7.67E-05 1.58E-05 2.37E-06 2.71E-07 NO DATA 1.11E-06 CE 141 3.55E-06 ._ .. _______________________.._______ ________________________________...______.-- 1.63E-05 3.19E-05 3.32E-08 2.42E-08 2.70E_09 NO DATA 1.08E-08 CE 143 1.51E-04 1.67E-03 1.08E-04 6.11E-04 2.53E-04 3.28E_05 NO DATA CE 144 6.04E-05 2.67E_05 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 PR 143 ______________________... ______-_____________...______-_-__________ 2.19E-07 ___...__ 2.94E.14 2.20E-12 2.72E-13 NO DATA 26E-12 PR 144 5.37E-12 4.65E-05 2.28E-05 1.07E-06 6.41E-08 NO DATA 4.28E-07 l ND 147 9.83E-07 5.92E_06 2.21E_05 1.22E-09 4.29E.10 NO DATA NO DATA W 187 1.50E-09
.25E-08 8.11E-06 1.65E_05 4.23E-08 3.99E-09 2.21E_09 NO DATA WP 239
- Dose factors of internal exposure are for copt htakeoveraone-year period and include the dose commit gD y1 r period; from Reg. Guide 1.109, 00CM Reference 2. Addition $
c :or for nuclides not included in this table may be obtained from NUR 0172, 00CM Reference 6.
** Tritium dose factors include an increase of 50% to account for the additional l amount of this nuclide absorbed through the skin. ,
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I i Number
"' I E, Nuclear l
I Radiological Controls Department 9100 PLN 4200." Revision No. ] f Title 6
}
Offsite Dose Calculation Manual (00CM) ) l Appendix B-1c j
! e I
Page 1 of 3 l INHALATION 00SE FACTORS FOR CHILO* il ; (MREM PER PCI INHALED) l i f T. BODY THYROID KIONEY_ LUNG GI-LLI NUCLIOE BONE LIVER i 3** NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 1.82E-06 l( i H 1.82E-06 1.82E-06 1.82E-06 1.82E-06 C 14 9.70E-06 1.82E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 NA 24 4.35E-06 4.35E_06 NO DATA 1.14E-05 ________-_______________--_________5 32 7.04E-04 3.09E-05 2.67E-0 NO DATA NO DATA 2.93E-07 P 4.17E-08 2.31E-08 6.57E-09 4.59E 06 CR 51 NO DATA NO DATA 6.19E-06 2.57E-06 NO DATA 2.71E-06 4.26E-04 MN 54 NO DATA 1.16E_05 ___
.._______________. __________________-----__-_..-_.-_______________.-________st__- 3.33E-05 4.48E-10 8.43E-il NO DATA 4.52E-10 3.55E-06 MN 56 NO DATA NO DATA 3.00E-05 7.75E-07 i FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA 1.91E-05 1
4.51E-06 NO DATA NO DATA 3.43E-04 FE 59 5.59E_06 9.04E-06
- _ _ . _ _ _ _ . . . _ _ _ - _ _ . _ - - - - _ _ _ - _ . -N _ _ _ A
- _2.99E-04
_ _ _ _ _ 9.29E-06 CO 58 NO DATA 4.79E-07 8.55E-0? NO DATA 2.60E.05 6.12E-06 NO O A 1.91E-03 CO 60 NO DATA 3.55E-06 s 7.43E-05 1.71E.06 7.56E-06 N ATA NI 63 2.22E-04 1.25E-05 10 DATA 2.21E-06 2.27E-05 NI 65 8.08E-10 7.99E-11 4.44E 1 OATA 1.63E-09 2.59E-06 9.92E-06 CU 64 NO DATA 5.39E.10 2.90E_10 NO DATA 4.41E-06 1.90E-05 NO DATA 1.93E-05 2.69E_04 ZN 65 1.15E-05 3.06E-05 NO DATA 1.58E_11 3.84E.07 2.75E-06 ZN 69 1.81E-11 2.61E-11 2.41E_12 NO DATA NO DATA NO DATA LT E-24 BR 83 NO DATA NO DATA 1.28E_07 LT E-24 NO DATA NO DATA NO DATA BR 84 NO DATA NO DATA 1.48E-07
...__.__.....____ ___-___. ..-_-___.__ -______________ NO DATA
--NO______-_-________
DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA 2.16E-06 NO DATA NO DATA NO DATA R8 86 NO DATA 5.36E-05 3.09E_05 4.66E-09 NO DATA NO DATA NO DATA RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 5.11E-10 -- _-___- RB 89 NO DATA 9.33E 08 7.83E_08 4.52E-05 4.66E_06 NO DATA NO DATA 5.83E-04 SR 89 1.62E-04 NO DATA NO DATA 3.99E-03 9.28E-05 NO DATA 1.74E_03 NO DATA g SR 90 2.73E-02 e __.... _--____________-___..__________...--___ ......______-..-_____.. NO DATA 1.44E-05 4.70E-05 .--__ E SR 91 3.28E-08 NO DATA 1.24E-09 NO DATA 6.55E-05 1.42E-10 NO DATA NO DATA 6.49E-06 2 SR 92 3.54E-09 NO DATA NO DATA NO DATA 7.07E 05 7.24E 05 3 Y 90 1.11E.06 NO DATA 2.99E-08 5 ____. ___. _________-. _-_____-.._. 4.98E-12 _ ... NO _______. DATA NO _ _____________________ DATA 7.60E 07 4.64E_07 _ iY 91M 1.37E.10 NO DATA NO DATA 7.10E-04 4.97E_05 6.59E_06 NO DATA 4Y 91 2.47E-04 NO DATA NO DATA 6.46E_06 6.46E-05 1.57E-10 NO DATA
} Y_ . -92_ _ .5,50E_09 NO DATA
- i. E2-8
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Number Nuclear 'st-' Radiological Controls Department 9100-PLN-4200.01 Revision No. Title 6 Offsite Dois Calculation Manual (OOCH) Appendix 8-lc (Cont'd) Page 2 of 3 INHALATION 00EE FACTORS FOR CHILO* l (MREM PER PCI INHALED) BONE LIVER T. BODY THYROIO KIONEY LUNG GI-LLI NUCLIOE 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 Y 93 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 !.65E-05 ZR 95 9.49E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 k[bkhk [I33k$bh i$h k$bk IIbbk$bh l kh hh h$3hk$bh k$5kk$bh Uhhh$bh 3.42E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 4.81E-13 9.41E-13 1.56E-ll NO DATA 1.37E-11 2.57E-07 1.30E-06 TC 99M
----.-------------------------------------- ....------------------------------+-------
1.58E-07 4.41E-09 TC 101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU 103 7.55E-07 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU 105 4.13E-10 NO DATA
-----------------------------------------------------------------3.87E-03 RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 2.37E-05 1.16E-04 3.08E-06 2.47E-06 NO OATA 5.74E-06 1.48E-03 2.71E-05 AG 110M 4.56E-06 2.05E-07 5.59E-06 2.46E-08 0.0 6.27E-04 1.09E-05 l 58 125 2.66E-05 6.29E-07 2.47E-07 'O DATA 1.29E-04 9.13E-06 TE 125M 1.82E-06 5.20E-07 ,..o hh$ U72E-05 4.00E-04 1.93E-05 l hk5hh h$hbk$bh b 35h5bh h$ hk$bh 5 1.52E-05 TE 127 7.49E-10 2.57E-10 1. 5,30E-10 1.91E-09 2.71E-06 1.85E-06 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE 129H 5.19E-06 8 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE 129 2.64E-11 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE 131H 3.63E-08 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE 131 5.87E-12 -----------------
TE 132
.-----------------------------------------------------------2E-04 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.0 3.72E-05 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 130 2.21E-06 7.6BE-07 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 l I 132 5.72E-07 1.48E-06
;:; I 133 4.48E-06 5.49E-06 2.0BE-06 1.04E-03 9.13E-06 NO DATA 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 5 I 134 3.17E-07 1.20E-06 a I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06
$ CS 134 1.76E-04 1.13E-06 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06
- CS 136 1.76E-05 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS 137 2.45E-04 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 k CS 138 1.71E-07 2.66F-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 BA 139 4.98E-10 l ---------------------------------------------------------....-------------------- ---,
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Number IHI~' hbOBY Radiological Controls Department 9100 PLN 4200.01 Revision No. Title 6 Offsite Oose Calculation Manual (00CM) Appendix 8 1c (Cont'd) Page 3 of 3 INHALATION DOSE FACTORS FOR CHILO* l' ', (MREM PER PCI INHALED) T. BODY THYROID KIONEY__ LUNG CI-LLI NUCLIDE BONE LIVER 5.71E-09 4.71E-04 2.75E-05 BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 7.44E-08 1.72E-12 NO DATA 2.56E.14 7.89E-07 BA 141 5.29E-11 2.95E.14 4.44E_07 7.41E-10 9.73E.15 7.54E.13 NO DATA 7.87E-15 BA 142 1.35E-11 NO DATA 4.94E.05 6.10E-05 LA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA 2.05E-05 3.49E.11 NO DATA NO DATA 2.35E-06 LA 142 3.50E-10 1.11E.10 1.53E 05 7.83E-07 NO DATA 2.31E-06 1.47E-04 CE 141 1.06E-05 5.28E-06 2.26E-08 3.12E.05 3.'44E.05 CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 1.05E-04 9.77E-05 NO DATA 3.17E 04 3.23E.03 CE 144 1.83E-03 5.72E-04 1.17E-04 2.63E-05 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.llE 07 PR 143 NO DATA 2.54E-12 4.23E_07 5.32E 08 PR 144 1.61E.11 4.99E-12 8.10E_13 2.22E-05 1.84E-07 NO DATA '.30E-06 8.87E_05 ND 147 2.92E-06 2.36E-06 1.11E_05 2.46E 05 1.17E-09 NO DATA NO DATA W 187 4.41E-09 2.61E-09 ______________......__..... _____. __________ NO DATA
......____1.57E-05 2.63E-08 1.73E.05 NP 239 1.26E-07 9.04E-09 6.35E.09 I
- Dose factors of internal exposure are for continuous intake over a one-year '
period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose factor for nuclides not included in this table may be obtained from NUREG-0172, OOCH Reference 6. I
** Tritium dose factors include an increase of 50% to account for the addition amount of this nuclide absorbed through the skin.
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Number THI_i !
.MU2168r Radiological Centrols Department 9100 PLN 4200.H Revmon No.
Title 6 Offsite Dose Calculation Manual (00CM) Appendix 8-id Page 1 of 3 l INHALATION DOSE FACTORS FOR INFANT * (MREM PER PCI INHALE 0) i BONE LIVER T. B,00Y THYROID KIONEY LUNG GI-LLI NUCLIOE 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E.07 4.62E-07 ;l H 3** NO DATA 3.79E-06 14 1.89E_05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 C 7.54E-06 NA 24 7.54E-06 7.54E_06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 P 32 1.45E-03 2.55E-07 NO DATA 6.39E-08 4.11E_08 9.45E-09 9.17E_06 CR 51 NO DATA 7.14E 04 5.04E-06 MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 __________.______________ _____-________________________.... _________________e....___ 1.10E-09 1.58E-10 NO DATA 7.86E.10 8.95E-06 5.12E-05 MN 56 NO DATA 7.82E-07 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.2iE-05 1.68E-05 6.77E_06 NO DATA NO DATA 7.25E-04 1.77E_05 FE 59 9.69E-06 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E_06 CO 58 NO DATA 2.28E-05 i 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 CO 60 NO DATA NI 63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 I.73E-06 )
)
2.03E.10 8.79E-11 NO DATA 5.80E-06 3.58E-05 1 NI 65 1.71E-09 NO O 2.84E-09 6.64E_06 1.07E-05 l CU 64 NO DATA 1.34E-09 5.53E-10 NO 4.47E-05 2.22E-05 2.32E_05 4.62E-04 3.67E-05 ZN 65 1.38E_05 6.91E-11 5.13E DATA 2.87E 11 1.05E-06 9.44E-06 ZN 69 3.85E.11 NO DATA LT E_24 j
- 2. NO DATA NO DATA BR 83 NO DATA NO DATA LT E-24 NO DATA NO DATA NO DATA l BR 84 NO DATA NO DATA 2 l 1.46E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.17E 06 1.36E_04 6.30E-05 NO DATA NO DATA NO DATA i RB 86 NO DATA 2.42E-07 3.98E.07 2.05E-07 NO DATA NO DATA NO DATA l RB 88 NO DATA 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08
,R8 89 NO DATA 2.29E-07 4.57E-05 SR 89 2.84E.04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 1.85E-03 NO DATA NO DATA 8.03E_03 9.36E.05 g SR 90 2.92E-02 NO DATA 2.47E 09 NO DATA NO DATA 3.76E-05 5.24E-05 i
- SR 91 6.83E-08 NO DATA '
2.79E_10 NO DATA No DATA 1.70E-05 1.00E_04 2.5R 92 7.50E-09 NO DATA 1.92E_04 7.43E-05 2.35E-06 NO DATA 6.30E_08 NO DATA NO DATA
@ Y 90 l
1.68E_06 2.91E-10 NO DATA 9.90E_12 NG DATA NO DATA 1.99E_06 g YY 91M 91 4.20E-04 NO DATA 1.12E.05 NO DATA NO DATA 1.75E_03 5.02E 05 l 9.04E-05 l l Y 92 1.17E-08 NO DATA 3.29E_10 NO DATA NO DATA 1.75E_05 l
!. ^00 0982per E2-11
Number . Nuclear r"t-i Radiological Controls Department 9100-PLM.4200.01 ! i Revision No. Title 6 Offsite Dose Calculation Manual (00CN) Appendix 8-Id (Cont'd) Page 2 of 3 INHALATION DOSE FACTORS FOR INFANT
- l (MREM PER PCI INHALED)
BONE LIVER T. BODY THYROIO KIONEY LUNG GI-LLI NUCLIOE 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E_04 Y 93 1.07E-07 NO DATA 1.99E-05 1.45E_05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 95 8.24E-05 1.00E-04 ZR 97 1.07E_07 1.83E-08 8.36E_09 NO DATA 1.85E-08 7.88E-05 ____________________________________________________________________42E-04 4.59E-06 2.70E-06 NO DATA 3.37E-06 3. 9.05E-06 NB 95 1.12E_05 3.48E-05 MO 99 NO DATA 1.18E-07 2.31E_08 NO DATA 1.89E-07 9.63E_05 TC 99M 9.98E.13 2.06E-12 2.66E-11 NO DATA 2.22E_11 5.79E-07 1.4)E-06 4.65E-14 5.88E-14 5.80E_13 NO DATA 6.99E-13 4.17E-07 6.03E-07 TC 101 1.44E-06 NO DATA 4.85E_07 NO DATA 3.03E-06 3.94E-04 1.tSE_05 RU 103 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E 10 1.12E-05 3.46E_05 RU 105 _____________ _________________________________________________________________________3 7.77E-06 NO DATA ~.61E-05 8.26E-0 1.17E-04 , RU 106 6.20E-05 NO DATA ' 7.13E-06 5.16E-06 3.57E-06 NO DATA 30E-06 2.62E-03 2.36E-05 AG 110M 3.69E-05 3.41E-07 7.78E_06 4.45E-08 0.0 1.17E_03 1.05E-05 l l SB 125 3.40E_06 1.42E-06 4.70E-07 1.16E-06 NC OATA 3.19E_04 9.22E-06 TE 125M 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E_05 TE 127M 1.19E-05 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 127 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E_05 1.20E-03 4.93E-05 TE 129M Tkih9 hIhhh_55 hI48k$55 5 h..ikkt I5$3hkS5b hI 4h$0h 5$hhk$hh 7.62E-08 3.93E-08 M 5.a8E-08 1.89E_07 1.42E-04 8.51E-05 TE 131H 1.24E-11 5.87E-12 3 12 1.13E-11 2.35E-ll 1.47E_06 5.87E-06 TE 131 2.66E_07 1.69E-07 1.26E 07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE 132 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 130 4.54E-06 3.17E-05 1.40E-05 1.06E_02 3.70E_05 NO DATA 7.56E_07 I 131 2.71E_05 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 i I 132 1.21E-06 ' 1.37E_05 4.00E-06 2.54E-03 1.60E 05 NO DATA 1.54E-06 n I 133 9.46E_06 I 134 6.58E-07 1.34E_06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 2.76E-06 5.43E_06 1.98E-06 4.97E-04 6.05E_06 NO DATA 1.31E-06
. I 135 2.83E-04 5.02E 04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07
$ CS 134 4.03E-05 8.40E-06 1.02E-06
! O CS 136 3.45E-05 9.61E-05 3.78E-05 NO DATA g CS .....__________..___________________________________________________________________7 137 3.92E-04 4.37F-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-0 4.67E-08 6.26E-07 CS 138 3.61E_07 5.58E-07 2.84E-07 NO DATA 2.93E-07 BA 139 1.06E 09 7.03E 13 3.07E 11 NO DATA 4.23E 13 4.25E 3.64E_05
._________________________-06 __________..____
l E2 12 ^000 5682 D 82 l-
Numeer , MUClear t-i Radiological Controls Department 9100-PLN 4200.01 ! Revision No. Title l 6 ) Offsite Dose Calculation Manual (00CM) i i Appendix B-Id (Cont'd) : l Page 3 of 3 l INHALATION DOSE FACTORS FOR INFANT * . (MREM PER PCI INHALE 0) I ! l T. BODY THYROIO KIDNEY LUNG GI_LLI NUCLIDE BONE LIVER 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 140 4.00E-05 4.00E_08 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 < BA 141 1.12E-10 7.70E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 8A 142 2.84E-11 2.36E-14 _______________________________________________________O DATA 1.20E-04 6.06E-05 LA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA N 5.87E-06 4.25E-05 LA 142 7.36E-10 2.69E-10 6.46E-Il NO DATA NO DATA 1.54E-05 1.19E-05 1.42E-06 NO DATA 3.75E_06 3.69E_04 CE 141 1.98E-05 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 143 2.09E-07 1.38E-07 1.06E-04 8.65E-04 1 ? 3.84E_04 7.03E-03 CE 144 2.28E-03 2.66E-05 1.41E_06 3.09E-04 PR 143 1.00E_05 3.74E-06l) _________________________________________________________30E 1.72E 12 J. 12 1.15E-06 3.06E-06 PR 144 3.42E-Il 1.32E-Il NO DATA 2.23E-05 3.57E-07 NO DATA 2.25E_06 2.30E_04 l NO 147 5.67E-06 5.81F-06 2.54E-05 l 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E 05 W 187 9.26E-09 _____________________________I _________________________________________________________73E-08 1.34E-08 NO DATA 4 4.25E-05 1.78E-05 l NP 239 2.65E-07 2.37E-08 J l
- Dose factors of internal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose factor for nuclides not included in this table may be obtained from NUREG-0172. ODCM Reference 6.
Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin. 1 I 5 i 6 S i 2 l b i E2 13
^*0 WB 2 p e:
P
1 Numbee Radiological o trols Department 9100.PLN 4200.01 Title Revision No. 6 Offsite Dose Calculation Manual (00CM) . Appendix 8-le Page 1 of 3 INGESTION Dv5E FACTORS FOR ADULTS
- l' l (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY THYROIO (IONEY LUNG GI_LLI H 3 NO DATA 1.05E_07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 , C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E 07 ! NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E_06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E_05 7.46E-06 NO DATA NO DATA NO DATA 2.17E 05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05
...__ ..._____.._. _.._________ ________.____.______________.__________________1._____
MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E_07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E_06 3.40E-05 1.67E-06 NO DATA NO DATA NO DATA 1.51E_05 1 C0 58 NO DATA 7.45E_07 4.02E-05 CO 60 NO DATA 2.14E.06 4.72E-06 NO DATA NO DATA NO DATA 4.36E-06 NO DATA NO DATA 1.88E-06 NI 63 1.30E-04 9.01E-06 NO DATA 6.86E-08 3.13E-08 NC DATA NO DATA 1.74E_06 N1 65 5.28E-07 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E_06 CU 64 NO DATA ZN 65 4.84E_06 1.54E-05 6.96E-06 Nq. 1.03E-05 NO DATA 9.70E-06 i ____________________._____________________Wg a . ____________________ 1.37E-09 40') g1.jhE . y_NODATA 2.96E-09 ZN 69 1.03E_08 1.97E-08 . BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 5.21E-08 NO DATA NC CATA NO DATA 4.09E-13 BR 84 NO DATA NO DATA 2.14E_09 NO DATA NC CATA NO DATA LT E_24 BR 85 NO DATA NO DATA 4.16E-06 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA RB 86 NO DATA 6.05E-08 3.21E-08 NO DATA NC OATA N0 OATA 8.36E-19 j RB 88 NO DATA RB 89 NO DATA 4.01E-08 2.82E.08 NO DATA NO DATA NO DATA 2.33E-21 8.84E_06 NO DATA NO DATA NO DATA 4.94E-05 SR 89 3.08E-04 NO DATA SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 n
~
5.67E-06 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 l SR 91 NO DATA 9.30E_08 NO DATA NO DATA NO DATA 4.26E-05 a SR 92 2.15E-06 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 E Y 90 9.62E-09 NO DATA 5 __.-___.._____ ___________.______._____._-____ .__________.___________.___...___.__-_. 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 l 9.09E-Il NO DATA l g YY 91M 91 1.41E-07 NO DATA 3.77E_09 NO DATA NO DATA NO DATA 7.75E-05 f 1.48E_05 l l l Y 92 8.45E-10 NO DATA 2.47E 11 NO DATA NO DATA NO DATA I 2
^0006082 p s2 E2 14
e . Numb;r Nuclear r"t-i Radiolo9tcal Controls Department 9100-PLN 4200.01 Revision No. Title 6 Offsite Dose Calculation Manual (00CM) Appendix 8-le (Cont'd) Page 2 of 3 l INGESTION DOSE FACTORS FOR ADULTS * (MREM PER PCI INGESTED) T. BODY THYROID KIONEY LUNG GI-LLI NUCLIDE BONE LIVER 7.40E-Il NO DATA NO DATA NO DATA 8.50E-05 Y 93 2.68E-09 NO DATA NO DATA 3.09E-05 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 . ZR 95 5.12E-10 NO DATA 1.05E-04 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA
-----_-_----------------_----_-------_----_-_-_-TA 3.42E-09 NO DATA 2.10E-05 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DA NO DATA 9.76E-06 NO DATA 9.99E-06 MO 99 NO DATA 4.31E-06 8.20E-07 4.13E-07 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 TC 99M 2.47E-10 ,
6.59E-09 1.87E-10 1.10E-21 TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA NO DATA 1.99E-07 NO DATA 9.42E-06 RU 105 1.54E-08 NO DATA 6.08E-09
--------------------------------------------_---TA 5.31E-06 NO DATA 1.78E-04 RU 106 2.756-06 NO DATA 3.48E-07 NO DA NO DATA 6.04E-05 AG 110M 1.60E-07 1.48E-07 8.79E-08 V :.91E-07 1.97E-05 1 0.0 1.38E-06 [
58 125 1.79E-06 2.00E-08 Q4 1.07E-05 TE 125M 2.68E-06 9.71E-07 41 @904) E-07 '.09E-05 NO DATA
--------------------------------------------------6 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-0 2.75E-05 NO DATA 2.27E-05 8.68E-06 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA TE 127 4.80E-05 NO DATA 5.79E-05 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06
.32E-07 NO DATA 2.37E-08 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.62E-08 a.63E-08 NO DATA 2.79E-09 TE 131 1.97E-08 8.23E-09 6.22E-09 TE 132
---------------------------------------_-----57E-05 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1. NO DATA 7.71E-05 1.89E-04 3.48E-06 NO DATA 1.92E-06 ,
I 130 7.56E-07 2.23E-06 8.80E-07 1.95E-03 1.02E-05 NO DATA 1.57E-06 l I 131 4.16E-06 5.95E-06 3.41E-06 {
--_------_--_----_-_---__---------------------__--5 1.90E-0 8.65E-07 NO DATA 1.02E-07 l I 132 2.03E-07 5.43E-07 1.90E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 )
a I 133 1.42E-06 2.47E-06 7.53E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 3 I 134 1.06E-07 2.88E-07 1.03E-07
= ---------------------------......------------_-------_------_-----..------------------
1.86E-06 NO DATA 1.31E-06 2 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 4.79E-05 1.59E-05 2.59E-06 l 6.22E-05 1.48E-04 1.21E-04 NO DATA E CS 134 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 1 0 CS 136 6.51E-06 2.57E-05 --__--------_-------_------- - g C-S-------_ 137 7.97E-05 1.09E-04 7.14E-05 NO DATA -_70E-05
- 3. 1.23E-05 2.11E-06 NO DATA 8.01E-08 7.?!E-09 4.65E-13 132 5.52E-08 1.09E-07 5.40E-08
@ CS NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 1 ~)9 9.70E-08 6.91E-11 2.84E-09 l
E2 15 ^N00GB2Ps2 A - - -_____m__.._
Number I Nurlear mt-1 l Radiological Controls Department 9100 PLN-4200.01 ' Title Revision No. 6 Offsite Oose Calculation Manual (00CM) i ( Appendix 0-le (Cont'd) 1 Page 3 of 3 INGESTION DOSE FACTORS FOR AOULTS* l l (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIONEY LUNG GI-LLI 2.03E-05 2.55E-08 1.33E-06 NO DATA B.67E-09 1.46E-08 4.18E-05 BA 140 2.22E_17 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 BA 142 2.13E_08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 140 2.50E-09 ,4.25E-07 LA 142 1.28E.10 5.82E_11 1.45E-Il NO DATA NO DATA NO DATA 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 141 , 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 143 1.65E-04 CE 144 4.88E-07 2.04E-07 2.62E_08 NO DATA 1.21E_07 NO DATA 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E 05 PR 143 1.25E-11 1.53E-12 NO DATA ' 05E 12 NO DATA 4.33E-18 PR 144 3.01E-11 . ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 1.25E_09 NO DATA 3.49E-05 1.03E-07 8.61E-08 3.01E-08 NO NO DATA NO DATA 2.82E-05 W 187 NP h39 5$5hE Oh 55I7E_ 0 h 3 6hE-lb NO DAhA 240E5bh
- Dose factors of internal exposure are for continuous intake over a one-year '
period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose f' actor for nuclides not included in this table may be obtained from NUREG-0172, 00CM Reference 6. l . E s n i 5 2
?
l 8 l l E? 16
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t , Number ; Nuclear m -1 Radiological Controls Department 9100_PLN 4200.01 i Title Revision No. 6 Offsite Dese Calculation Manual (00CM) Appendix B-lf Page 1 of 3 I INGESTION 00SE FACTORS FOR TEENAGER
- l' (MREM PER PCI INGESTED)
T. BODY THYROIO KIONEY LUNG _GI-LLI j NUCLIOE BONE LIVER ( i H 3 NO DATA 1.06E-07 1.06E-07 1.06E_07 1.06E_07 1.06E_07 1.06E-07 I C 14 4.06E-06 8.12E-07 8.12E-07 8.12E_07 8.12E_07 8.12E_07 8.12E-07 i NA 24 2.30E-06 2.30E-06 2.30E_06 2.30E_06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E_05 NO rTTA NO DATA NO DATA 2.32C-05 3.60E_09 2.00E_09 7.89E 10 5.14E-09 6.05E_07 CR 51 NO DATA NO DATA 5.90E-06 1.17E_06 NO DATA 1.76E_06 NO DATA 1.21E-05 MN 54 NO DATA _____________________________________________________________________________1.04E MN 56 NO DATA 1.58E-07 2.81E_08 NO DATA 2.00E_07 NO DATA 2.68E-06 6.25E_07 NO DATA NO DATA 1.70E_06 1.16E_06 FE 55 3.78E-06 FE 59 5.87E-06 1.37E_05 5.29E_06 NO DATA NO DATA 4.32E_06 3.24E-05 _____________________________________________________________________________1.34E C0 58 NO DATA 9.72E-07 2.24E_06 NO DATA NO DATA NO DATA 2.81E-06 6.33E-06 NO DATA NC OATA NO DATA 3.66E-05 CO 60 NO DATA NI 63 1.77E-04 1.2SE_05 6.00E 06 NO DATA NO DATA NO DATA 1.99E-06 ______________________________ ______________________________________________-.J ______ NI f5 7.49E-07 9.57E_08 4.36E-08 NO DAI NO DATA NO DATA 5.19E-06 i' 8.92E_06 CU 64 NO DATA 1.15E-07 5.41 E-08 nN0 'A4m%t 2.91E-07 1.28E-05 NO NO DATA DATA 8.47E_06, ZN 65 5.76E-06 2.00E_05 JE-O hM3 UATA
'*g)ayskup'\y y ______________________________________________Y '
2.80E-08 U 796E_09NO DATA 1.83E_08 NO DATA 5.16E_08 ZN 69 1.47E_08 LT E-24 5.74E-08 NO DATA NO DATA NO DATA 8R 83 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E_24 BR 84 NO DATA NO DATA l BR 8b bbbki ~hbbIf 3$bbE_b9 Nbbkhk Nbhkk Nbbkhk L E h4 2.98E_05 1.40E_05 NO DATA NC OATA NO DATA 4.41E_06 RB 86 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA ' NO DATA 7.30E-15 RB 88 NO DATA _________ _____________________________________________________________________________8.4 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 4.40E-04 1.26E_05 NO DATA NO DATA NO DATA 5.24E_05 SR 89 NO DATA 2.33E_04 2.05E_03 NO DATA NO DATA NO DATA a SR 90 8.30E-03 NO DATA
~
_____________________________________E-07 8.07E_06 3.21 NO DATA NO DATA NO DATA 3.66E_05 SR 91 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E_05
- SR 92 3.05E_06 NO DATA 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 E Y 90 _________
_____________________________________________________________________________6.09 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA
. gY 2.01E_07 NO DATA 5.39E_09 NO DATA NO DATA NO DATA 8.24E_05 Y 91 3.32E_05 l
Y 92 1.21E_09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA E2-17 ^ C DGB2P"
Numtcr Nuclear = -1 Radiological Controls Department 9100 PLN 4200.01 Revision No. Title 6 Offsite Dose Calculation Manual (00CM) Appendix 8 1f (Cont'd) { l Page 2 of 3 . INGESTION 005E FACTORS FOR TEENAGER * (MREM PER PCI INGESTED) T. BODY THYROIO KIONEY LUNG GI-LLI NUCLIOE BONE LIVER 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 Y 93 3.83E-09 NO DATA NO DATA 3.00E-05 I 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 ZR 95 7.11E-10 NO DATA 1.27E-04 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA __.-- ---.__.--..__.--_.._--__.---_--- ..--__-__-.._____-_______..-_-_--__----_.------- NO DATA 1.95E-05 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 Nb 95 1.38E-05 NO DATA 1.08E-05 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.20E-08 NO DATA 1.38E-08 5.14E.10 6.08E-07 TC 99M 3.32E-10 9.26E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 TC 101 3.60E-10 5.12E-10 2.13E-05 1.09E-07 NO DATA 8.99E-07 JO DATA RU 103 2.55E-07 NO DATA NO DATA 1.76E-05 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 RU 105 :
. - _ - - - _ _ _ . _ - _ _ . _ _ _ - - - _ . . _ _ _ . . . . . . . _ . . . - . . - - - - - -NO . . DATA
- _ . . . . .1.88E-04 3.92E-06 NO DATA 4.94E-07 NO DATA ' 56E-06 RU 106 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 AG 110M 2.05E-07 1.94E-07 1.93E-05 2.71E-08 5.80E-07 2.37E-09 0.0 2.18E-06 SB - 125 2.4dE-06 NO DATA 1.13E-05 1.38E-06 5.12E-07 1.07E-0 90 DATA TE 125M 3.83E-06 n.h 5$Ihh-06 IIhh'06 3.92E-05 NO DATA 2.41E-05 I hh i2hM 96hhS06 343k$6 0 NO DATA 1.22E-05 l 1.58E-07 5.60E-08 3. 09E-07 6.40E-07 TE 127 6.32E-05 NO DATA 6.12E-05 i TE 129M 1.63E-05 6.05E-06 2. 5.26E-06
' 38E-07 NO DATA 2.45E-07 !
TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E.08 . 1.76E-06 ' 22E-05 NO DATA 9.39E-05 ; TE 131M 2.44E-06 1.17E-06 9.76E-07 . 2.15E-08 > 22E-07 NO DATA 2.29E-09 TE 131 2.79E-08 1.15E-08 8.72E-09 . 2.12E-05 NO DATA 7.00E-05 TE 132 3.49E.06 2.21E-06 2.08E-06 2.33E-06 1.19E-06 2,43E-04 4.59E-06 NO DATA 2.29E-06 I 130 1.03E-06 2.98E-06 1.62E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA I 131 5.85E-06 ------_---------_-_.-.----- I 132 2.79E 07
-----_-_---------_----_----------E-06 7.30E-07 2.62E-07 2.46E-05 1.15 NO DATA 3.18E-07 4.16E_04 5.98E-06 NO DATA 2.58E-06 a I 133 2.01E-06 3.41E-06 1.04E-06 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I I 134 1.46E-07 3.87E-07 j = _ _ _ . . _ - _ . - - _ - _ _ - - . . . _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _NO_ DATA _ _ - - _ 1.74E-06 1.01E-04 2.48E-06 l 2I 135 6.10E-07 1.57E-06 5.82E-07 NO OATA 6.26E-05 2.39E-05 2.45E-06 8.37E-05 1.97E-04 9.14E-05 $ CS 134 2.27E-05 NO DATA I.84E-05 2.90E-06 2.72E-06
- CS 136 8.59E-06 3.38E-05 g C-_S_ -137 - - . . . - _ . . . _ _ . - _ - - - _ . _ _ _ _ _ . - . . - - _ _ - - . . . . . _ 1.97E-05 _ _ _ - - - - 2.12E-06 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-il l l CS 138 7.76E-08 1.49E-07 1.24E-06 >
4.05E-09 NO DATA 3.22E-11 6.74E-11
- BA 139 1.39E-07 9.78E-11 l ......--......--___... __--.-.-_... __ ______.--....___ ____-_-_--___.---..-^ __----...
99%gne: E2 '8 l t -- - - - - - ----- -
Number ENuclear ,,,,,,o,,caiPoltrolsDepartment 9100-PLN 4200.01 Revision No. Title 6 Offsita Dose Calculation Manual (00CM) Appendix B-1f (Cont'd) Page 3 of 3 INGESTION DOSE FACTORS FOR TEENAGER * (MREM PER PCI INGESTED) BONE LIVER T. BODY THYROID KIONEY LUNG GI_LLI NUCLIOE 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 a.38E-05 BA 140 1.43E-13 BA 141 6.71E-08 5.01E 11 2.24E-09 NO DATA 4.65E-11 3.43E-11 2.99E 08 2.99E 11 1.84E_09 NO DATA 2.53E_11 1.99E 11 9.18E BA 142 ______-20 LA 140 3.48E-09 1.71E-09 4.55E_10 NO DATA h0 DATA NO DATA 9.82E-05 7.95E-11 1.98E_11 NO DATA NO DATA NO DATA 2.42E_06 LA 142 1.79E_10 2.54E-05 CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.35E-09 1.71E_06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 143 1.75E-04 CE 144 6.96E_07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 5.23E-09 6.52E-10 NO DATA 3.04E_09 NO DATA 4.31E-05 PR 143 1.31E-08 1.76E-11 2.18E-12 NO DATA ' 31E-11 NO DATA 4.74E-14 PR 144 4.30E_11 . 3.68E_05 NO 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 1.46E_07 1.19E-07 4.17E-08 N NO DATA NO DATA 3.22E-05 W 187 5 h6h$bh I khh$Ib h ATA h25h5b bbkhk 2Ihhhbh NP 23h
- Dose factors of internal exposure are for continuous intake ever a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose factor for nuclides not included in this table may be 00tained from NUREG-0172. 00CM Reference 6. ,
5 s n 5 I e E2 19 ^ 0 1982 P s: l l l I
._________-_______-____-___a
+
. l Number 1 Nuslear Tst-i Radiological Controls Department 9100-PLN-4200.01 Title Revisen No.
6 OffsiteDoieCalculationMsnual(00CH) Appendix 8-1g Page 1 of 3 . INGESTION DOSE FAC~.)RS FOR CHILO* lJl i (MREM PER PCI INGESTED) 1 NUCLIOE BONE LIVER T. B00Y THYROIO KIONEY__ LUNG GI_LLI H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 l MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8. 9,8E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 NI 65 2.22E-06 2.09F-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 N0 DATA 1.15E-05 2N 65 1.37E-05 3.85E-05 2.27E-05 NO DATA 2.30E-05 NO LATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71F 07 NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1. TA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 9. -09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31F_06 RB 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E_09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E_03 NO DATA 3.77E_05 NO DATA NO CATA NO DATA 5.11E-05 a SR 90 1.70E~02 NO DATA 4.31E_03 NO DATA NO DATA NO DATA 2.29E-04 l ! ____________________________._________________________________________________________ l
~
SR 91 2.40E_05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 3.62E-07 NO DATA NO DATA NO DATA 1.71E_04 s SR 92 9.03E_06 NO DATA NO DATA NO DATA 1.17E-04 e Y 90 4.11E_08 NO DATA 1.10E-09 NO DATA 0 ..___________ ______________________ .._______________________________________________ j . Y Y 91M 91 3.82E_10 6.02E-07 NO DATA NO DATA 1 39E-11 1.61E_08 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 7.48E_07 8.02E-05 I Y 92 3.60E_09 NO DATA 1.03E_10 NO DATA NO DATA NO DATA 1.04E-04 E2-20 ^0*3 D682 P"
Number Nuclear TMt-i Radiological Controls Department 9100-PLN 4200.01 j Revision No. Title 6 Offsite Dose Calculation Manual (00CM) Appendix B-1g (Cont'd) Page 2 of 3 INGESTION DOSE FACTORS FOR CHILO* (MREM PER PCI INGESTED) LIVER T. BODY THYROID KIONEY LUNG _ GI-LLI NUCLIOE BONE 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 Y 93 1.14E-08 NO DATA 2.55E-08 2.27E-08 N0 DATA 3.65E-08 NO DATA 2.66E-05 i ZR 95 1.16E-07 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 2R 97 6.99E-09 ------------------------
-------------------------------------------------------------9 NB 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-0 NO DATA 1.62E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 MO 99 NO DATA 1.33E-05 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06 TC 99M 9.23E-10 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 TC 101 1.07E-09 1.89E-05 RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU 105 6.452-08 NO DATA
-------------------------------------------------------------5 RU 106 1.17E-05 NO DATA 1.46E-06 NO DATA '.58E-0 NO DATA 1.82E-04 2.91E-07 NO DATA i.78E-07 NO DATA 4.33E-05 AG 110M 5.39E-07 3.64E-07 1.50E-06 6.63E-09 0.0 3.99E-06 1.71E-05 SB 125 7.16E-06 5.52E-08 1.52E-06 3.20E-06 'C
. OATA NO DATA 1.10E-05 TE 125M 1.14E-05 3.09E-06
----------------------------------------------------------E-05 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24 NO DATA 2.34E-05 1.0iE-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 127 4.71E-07 1.27E-07 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129M 4.87E-05 1.36E-05 ---------------
TE 129 1,34E-07 3.74E-08 3.18E-08 t
---------------TA
.92E-07 NO DA 8.34E-06
- 2. c.41E-05 NO DATA 1.01E-04 l TE 131M 7.20E-06 2.49E-06
- 2. SE-08 2.51E-07 NO DATA 4.36E-07 TE 131 8.30E-08 2.53E-08
----------------------------------------------------------E-05 TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15 NO DATA 4.50E-05 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 l 1 130 2.92E-06 5.90E-06 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 131 1.72E-05 1.73E-05
---------------------------------------------------------5E-06 I 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.2 NO DATA 1.73E-06 2.77E-06 1.36E-03 1.22E-05 N0 DATA 2.95E-06 a I 133 5.92E-06 7.32E-06 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 E I 134 4.19E-07 ---------------
g
-----------------------------------------------------------TA 2.79E-04 4.83E-06 NO CA 2.40E-06 s ----------1.75E-06 I 135 3.15E-06 1.49E-06 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 s CS 134 2.34E-04 3.84E-04 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS 136 2.35E-05 6.46E-05 g ------_-----_ --------_---------------------_------_------_ -----_------------------ 1.96E-06
-S 137 3.27E-04 3.13E-04' 4.62E-05 NO DATA 1.02E-04 3.67E-05 C 1.46E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 CS 138 2.28E-07 1.30E-10 2.39E-05 BA 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 l
l ----139-------- -------------------------------------------------_------------------ --- Ei-21 4x gre2
Numt:Cf
~"I-t Nuclear Radiological Controls Department 9100-PLN 4200.31 f
Title Revision No. 6 Offsite Oose Calculation Manual (00CM) Appendix B-lg (Cont'd) Page 3 of 3 INGESTION DOSE FACTORS FOR CHILO* (MREM PER PCI INGESTED) , 7 BODY THYROID KIONEY__ LUNG GI-LLI NOCLIOE BONE LIVER 4.85E-06 NO DATA 2.37E-08 4.34E-08 a.21E-05 BA 140 8.31E-05 7.28E-08 1.14E-07 1.12E 10 6.51E-09 NO DATA 9.69E-11 6.58E-10 BA 141 2.00E-07 3.70E-11 1.14E-09 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 BA 142 NO DATA NO DATA 9.84E-05 --_ LA 140 1.01E-08 3.53E-09 1.19E-09 NO DATA NO DATA NO DATA NO DATA 3.31E-05 LA 142 5.24E-10 1.67E-10 5.23E-11 8.68E-09 NO DATA 2.47E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 1.59E-09 NO DATA 5.55E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 CE 144 2.08E-06 6.52E-07 4.24E-05 1.95E-09 NO DATA 6.39E-09 NO DATA PR 143 3.93E-08 1.18E-08 2.11E-11 NO DATA 8.59E-08 PR 144 1.29E-10 3.99E 11 6.49E-12 NO DATA 1.75E-09 NO DATA '.24E-08 NO DATA 3.58E-05 NO 147 2.79E-08 2.26E-08 3.57E-05 1.14E-07 NO DATA NO DATA NO DATA W 187 4.29E-07 2.54E-07
-------_--_-_-_---_-------------------------_--ATA 2.65E-10 NO D 1.09E-09 NO DATA 2.79E-05 NP 239 5.25E-09 3.77E-10
' Dose factors of internal exposure are for continuous intake over a one-year i i
period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, 00CM Reference 2. Additional dose factor for nuclides not included in ; this table may be obtained from NUREG-0172, 00CM Reference 6. I l 5 5 5 2 h 1 i
!. * ** M 8 2 0
- 2 E2-22 I
i
I , Number l } Nuslear rst i Radiological Controls Department 9100-PLN-4200.01 i Revision No. I Title 6 l Offsite Dose Calculation Manual (00CM) Appendix B_lh Page 1 of 3 I INGESTION DOSE FACTORS FOR INFANT
- ll (MREM PER PCI INGESTED) I LIVER T. BODY THYROID KIONEY LUNG GI-LLI NUCLIOE BONE I
3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 f H 3 NO DATA 3.08E-07 5.06E-06 5.06E-06 5.06E-06 5.36E-06 5.06E_06 i C 14 2.37E-05 5.06E-06 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 NA 24 1.01E-05 1.01E-05 ____________-__-._-__--_-___ ..__-__--____ ________.-__--____---- __.-___-________-_.. 2.30E-05 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA P 32 1.70E-03 4.11E-07 NO DATA 1.41E_08 9.20E-09 2.01E-09 1.79E-08 CR 51 NO DATA 7.31E-06 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA MN 54 NO DATA
..._________-__-__- ...__. ____-__-__ __...-_-_-__ -_-____-__--_-__--____---_____-____ 7.43E-05 MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 55 1.39E-05 8.98E-06 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 FE 59 3.08E-05 5.38E-05 8.98E_06 NO DATA 'C
. DATA NO DATA 8.97E-06 CO 58 NO DATA 3.60E-06 2.55E_05 NO DATA NO DATA NO DATA 2.57E-05 CO 60 NO DATA 1.08E-05 2.20E-05 NO DATA NC DATA NO DATA 1.95E-06 NI 63 6.34E-04 3.92E-05 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NG DATA NO DATA 4.05E-05 i' 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 CU 64 NO DATA 6.09E-07 l 2.91E-05 A 3.06E-05 NO DATA 5.33E-05 ZN 65 1.84E-05 6.31E-05 N ATA 6.98E-08 NO DATA 1.37E-05 ZN 69 9.33E-08 1.68E-17 NO DATA NO DATA NO DATA LT E-24 BR 83 NO DATA NO DATA NO DATA NO DATA LT E_24 BR 84 NO DATA NO DA' A 3.82E-07 NO DATA
---....-__-_--_-__---_-__._.__-_--_-------_ --__-__-_-_--__-__----_-_-_-----_-_-__---- LT'E_24 1.94E-08 NO DATA NO DATA NO DATA BR 85 NO DATA NO CATA NO DATA 4.35E-06 1.70E-04 8.40E-05 NO DATA NO DATA RB 86 NO DATA NO DATA 4.85E-07 4.98E.07 2.73E-07 NO DATA NO DATA RB 88 NO DATA NO DATA 9.74E-08 2.86E-07 1.97E-07 NO DATA NO DATA RB 89 NO DATA NO DATA 5.16E-05 7.20E-05 NO DATA NO DATA SR 89 2.51E-03 NO DATA 2.31E-04 4.71E-03 NO DATA NO DATA NO DATA a SR 90 1.85E_02 NO DATA
~
1.SiE-06 NO DATA NO DATA NO OATA 5.92E-05 SR 91 5.00E-05 NO DATA 2.07E-04 7.13E-07 NO DATA NO DATA NO DATA g SR 92 1.92E-05 NO DATA NO DATA 1.20E-04 2.33E-09 NO DATA N0 DATA g Y 90 8.69E-08 NO DATA a ..._-_____-_____________--_-.-_-________-___-. .___-_-__________-___-__-_ ._.-______._ 2.76E-11 NO DATA NO DATA NO DATA 2.70E_06 Y 91H 8.10E-10 NO DATA 8.10E-05 i.. Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA NO DATA 1.46E_04 2.15E-10 NO DATA NO DATA Y 92 7.65E_09 NO DATA __-__m___---___e--ee
--___-_-M-_me_.-e__-__.e_____me-_--__-_ ---__..e___em_--_e-_---__
^ %82P82 E2-23
i Number l Nuclear mt-i Radiological Controls Department 9100 PLN 4200.01 Revision No. Title 6 Offsite Dose Calculation Manual (ODCM) Appendix 8-lh (Cont'd) Page 2 of 3 l INGESTION DOSE FACTORS FOR INFANT * (MREM PER PCI INGESTED) T. BODY THYROIO KIONEY__ LUNG GI-LLI NUCLIOE BONE LIVER NO DATA NO DATA NO DATA 1.92E-04 Y 93 2.43E-08 NO DATA 6.62E-10 5.41E_08 NO DATA 2.50E_05 2R 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 1.16E_09 NO DATA 2.56E-09 NO DATA 1.62E-04 2R 97 1.48E-08 2.54E-09
...._______________.._ ._____.._____________________________________ ________________ 1.46E_05 1.00E-08 NO DATA 1.24E_08 NO DATA NB 95 4.20E-08 1.73E-08 1.12E-05 6.63E-06 NO DATA 5.08E-05 NO DATA MO 99 NO DATA 3.40E-05 1.15E-06 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 TC 99M 1.92E_09 ,
NO DATA 3.40E-08 1.56E-09 4.86E-07 l TC 101 2.27E-09 2.86E-09 2.83E_08 NO DATA 3.08E-06 NO DATA 1.80E-05 RU 103 1.48E-06 NO DATA 4.95E_07 1.00E-06 NO DATA 5.41E-05 RU 105 1.36E_07 NO DATA 4.58E-08 NO DATA _____________ _________ _________________.-_.-.________________________________ 1.83E-04 ___ 2.41E-05 NO DATA 3.01E-06 NO DATA : 85E-05 NO DATA RU 106 .04E-06 NO DATA 3.77E-05 AG 110M 9.96E_07 7.27E-07 4.81E-07 NO DATA 1.54E-08 0.0 7.72E-06 1.64E-05 [ S8 125 1.23E-05 1.19E-07 2.53E-06 7.84E-06 N0 DATA NO DATA 1.11E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 _ _ _ - - _ _ _ _ _ - _ . . . _ - _ _ . - _ - _ _ _ _ _ _ _ _ _ - _ _ . - - . . . . _ _ _ _ _ _ _ _2.36E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA TE 127M 5.85E-05 NO DATA 2.10E-05 j 127 1.00E_06 3.35E_07 2.15E-07 8.14E-07 2.44E-06 TE 5.97E-05 1.54E-05 3.84E-05 2.50E-04 N0 DATA l TE 129H 1.00E-04 3.43E.05 : 7.37E-07 NO DATA 2.27E-05 i TE 129 2.84E-07 9.79E_08 6 1.03E-04 i
. 4E-05 4.21E-05 N0'OATA TE 131M 1.52E-05 6.12E-06 5 4.50E-07 NO DATA 7.11E-06 TE 131 1.76E-07 6.50E-08 4 E-08 1.57E-07 l
- - - _ - - - - . _ - _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .3.81E-05 1.03E_05 9.61E-06 1.52E_05 6.44E-05 NO DATA TE 132 2.08E-05 1.45E-05 NO DATA 2.83E-06 I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 l I 131 3.59E-05 4.23E-05
---- ___________________________________ ________________. ____.._______.____________ 2.73E-06 !
1.66E.06 3.37E-06 1.20E_06 1.58E-04 3.76E.06 NO DATA I 132 3.08E-06 i 1.25E_05 1.82E_05 5.33E_06 3.31E_03 2.14E_05 NO DATA n I 133 1.84E-06 i 8.69E-07 1.78E-06 6.33E_07 4.15E-05 1.99E-06 NO DATA I I 134 , 2.62E-06 7.24E.06 2.64E_06 6.49E_04 8.07E-06 NO DATA l g I 135 3.64E-05 1.81E-04 7.42E-05 1.91E_06 ' 5 CS 134 3.77E-04 7.03E-04 7.10E.05 NO DATA 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E.06 CS 136 4.59E-05 1.35E-04 g -_______________.-__....... 5.22E-04 6.11E_04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06
-S 137 C
3.90E_07 6.09E-08 1.25E-06 4.81E-07 7.82E-07 3.79E-07 NO DATA k CS 138 3.51E-10 3.54E-10 5.58E-05 BA 8.81E-07 5.84E-10 2.55E-08 NO DATA l __.-_139-_-___..__.. ________________... _.-______.__________________-_. _______________.
^0009982 pe2 E2-24
t Number I
'Mt-'
l l Nuclear Radiological Controls Department 9100_PLN_4200.01 Revision No. Title 6 Offsite Dos's Calculation Manual (00CN) Appendix 8-lh (Cont'd) Page 3 of 3 INGESTION DOSE FACTORS FOR INFANT * (MREM PER PCI INGESTED) LIVER T. BODY THYROID KIONEY_ LUNG GI_LLI NUCLIOE BONE 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA 140 1.71E-04 5.19E-06 2.91E_10 1.34E_08 NO DATA 1.75E-10 1.77E-10 BA 141 4.25E-07 7.59E-07 1.53E-10 9 06E-09 NO DAT/. 8.81E-11 9.26E-11 BA 142 1.84E-07 2.14E-09 NO DATA NO DATA 9.77E-05 LA 140 2,11E-08 8.32E-09 NO DATA NO DATA 6.86E-05 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA LA 142 2.48E_05 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA CE 141 __________________.__.6.___ .
.._______________________________________________________86E-09 1.12E_09 NO DATA 2. NO DATA 5.73E-05 CE 143 1.48E-08 9.82E-06 4.93E_07 NO DATA 1.'71 E_04 CE 144 2.98E-06 1.22E_06 1.67E-07 NO DATA 4.03E-09 NO 1.13E-08 NO DATA 4.29E_05 PR 143 8.13E-08 3.04E_08 3.__-________________..____________
TA 3.34E.11 NO DATA 4.925-06 PR 144 2.74E-10 1.06E-10 NO DATA :.19E-08 N0 DATA 3.60E-05 ND 147 5.53E-08 5.68E-08 6.28E-07 .17E-07 NO DATA NO DATA NO DATA 3.69E 05 W 187 9.03E-07 -__-__-_-_-______--- 5.61E-10 NO DATA 98E-09 O N DATA 2.87E_05 NP 239 1.11E-08 9.93E-10 . i f Dose factors of internal exposure are for continuous intake over a one-year
- j period and include the dose commitment over a 50-year period; from Reg. Guide 1.109, ODCM Reference 2. Additional dose factor for nuclides not included in this table may be obtained from NUREG-0172. 00CM Reference 6.
E' s 9 5 2 9 I e
!. *** C09 2 F *
- E2_25
Numbcr m -' Nuclear Radiological Controls Department 9100-PLN 4200.01 I Revision No. Title 6 Offsite Dose Calculation Manual (00CM) i l Appendix C Bioaccumulation Factors 5 i N a l 5 i E31
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1 NumbCr Nuclear m i Radiological Centrols Department 9100-PLN 4200.01 , 4 Revision No. f Titse - l 6 Offsite Oose Calculation Manual (0DCM) C-1 BI0 ACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFI (pCi/kg per pCi/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E+03 9.lE+03 2.0E+02 f NA 1.0E+02 P 1.0E+05 2.0E+04 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 C0 5.0E+01 2.0E+02 NI .h)E+02 1.0E+02 4.0E+02 Cup; h ;2.0E+03 3E+01 I.0E+04 ZNM S 3.3E+02 BR 4.2E+02 RB 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 I 2R 3.3E+00 6.7E+00 1.0E+02 l NB 3.0E+04 ! MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 - RU l.0E+01 3.0E+02 RH 1.0E+01 3.0E+02 ;
**SB 1.0E+00 1.0E+00 TE 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W l.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 g
l 7
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- Bioaccumulation factor values are taken from Reg. Guide 1.109. 00CM Reference 2.
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** Sb bioaccumulation factor value is taken from EPRI NP-3840, ODCH Reference 7.
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Number m -i i Nuclear Radiological Controls Department 9100 PLN 4200.01 i Revision No. Title 6 Offsite Dona calculation Manual (00CM) l 1 i i TABLE E4-1 i DDSE FACf0R$ FOR N08tt GASES AND DAUGHTER $' ; Gamee total body 8 eta Gasma Air Beta Air j Dose Factor (a) Skin Oose Factor (b) Oose Factor Oose Factor Kg Lt Nt N1 (aReelyr per pCl/m3 ) (aRee/yr per pCl/m3) (mRadlyr per pC1/m3) (mRadlyr per pCl/m3) Radlonuclide
- 7. 56 E-02" --- 1.93E,01 2.84E+02 KR-83e 1.97t+03 1.17E,03 1.46E*03 1.23E+03 KR-45e 1.72[,01 1.95E,03 -
Kr-85 1.61E,01 1.34E+03 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-87 1.52E,04 2.93E+03 Kr 84 1.47E 04 2.37E 03 1.66E,04 1.0lt,04 1.73E+04 1.06E.04 Kr-89 1.63E,04 7. 8 3E+03 Kr-90 1.56t+04 7.29E*03 i 9.15E,01 4.76E,02 1.56E.02 1.11E.03 re-131m 1.48E 03 I re-133a 2.51E 02 9.94E,02 3.27E.02 1.05E 03 I xe-133 2.94E+02 3.06E+02 3.53E.02 3.12E.03 7. lit.02 3, 36 E .03 7.39t+02 l re.135e 2.46E.03 I 1 81E.03 i.86E+03 1 92E.03 Xe-135 1.27E 04 i xe-137 1,42E,03 1.22E 04 1.51!.03 4.13E.03 9 21E 03 4.75E,03 l xe-138 8.A3E.03 3.28E,03 Ar-41 8.84E+03 2.69E,03 9.3CE.03 1 Dose factors are for immersion esposure in uniform seal-infini
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vn h 4 realenuclides that may te detected in gaseous effluents. Ocse factor values are taken f t i L,1CM Reference 2.
"7.56E-02 7.56 a 10 2 tal Total body dose factor for gasuna penetration secth of 5 cm into the becf (D) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/-M i
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Nuclear ms-i Radiological Contro11 Deparbent 9100 Pt.N-4200.01 i Title Revision No. Offsite onne calculation Manual (00CM) 6 l Table E4-2 00SE PARAMETERS FOR RA0f0100!NES AND RADIOACifvE FARTICUL. ATE IN GA5E(XJS EFFLUENT 5' Fg Pg Pg Pt Inhalation Pathway & Ground Pathways Radio- Inhalatton Pathway Fgod & Cround Pathways Radio- F (m' ates/yr per pCl/sec) nucilde (stes/yr per pC1/eJ) ( .aRee/yr per pC1/sec) nuclide (ares /yr per pCl/eJ) 2.4E+03 Sn-126 1.2E+06 l.lE+09 H3 6.5E+02** 1.lE.09 Cr-51 3.6E+02 1.lE+07 50-125 1.5E+04 2.5E+04 1.lE+09 fe-127a 3.st+04 7.4E 10 Mn-54 1.3E+09 Fe 59 2.4E+04 7.0E+08 Te-129a 3.2E+04 5.7E+08 fe-132 1.0E+03 7.2E+07 . Co-58 1.lE+04 3.2E+04 4.6E*09 Cs-134 7.0E+05 5. 3t40 l Co 60 5.4E+08 6.3E+04 1.7E 10 Cs-136 1.3E+05 , 2N 65 4.7E+IO Rb 86 1.9E+05 l.6E+10 Cs-137 6.lE+05 5.6E+04 2.4E,08 Sr 49 4.0E+05 1.0E+10 Ba-140 4.lE+07 9.5E 10 Co-141 2.2E,04 8.7E+07 Sr 90 6.5E+08 y-91 7.0E+04 1.9E+09 Co-144 1.5E+05 2.2E,04 3.5E+08 No-239 2.5E+04 2.5E+06 2r 95 1.5E+07 1.lE 12*** nn 95 1.3E+04 3.6E+08 I-131 3.3E+08 I-132 1.7E 05 1. l E.02"
- MO 99 2.6E+02 9.6E,09'**
1.6E 04 3.4E.10 1-133 3.6E+06 Ru 603 5.6E-10*** 1.6E+05 4.4E+11 1-134 4.5E+04 Ru 106 7.0E 05 2. 2 E +07 "
- Ag llos 3.3E+04 l.5E.10 1-135 4.8E+07 untdent. 4.1E+07 9.5E 10 Cd il5a 7.0E.04 I
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- The listed dose parameters are for radionuclides, other than noole gases that may te detected in gaseous effluents.
Pt factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media and are j based on the most restrictive age group (infant) critical organ. Additional .tose parameters for nuclides not included ; In Table 2 2 may be calculated using the methodology described in NUREG-0133. 00CM Reference 1. l
" Tettlus dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed througn f the son. i l
*" The Food Pathway component of the P1 Fcr>d plus Ground Pathsays may te further reduced by a f actor as large as 2.0 to allow for the half-year growing season and a second factor as large as 2.0, to allow for 50% of the todtne effluent in organte fore. These reductions confors to Reg. Guide 1.109. 00CM Reference 2
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Number a -' ENuclear Radiological Controls Department 9100 PLN 4200.Cl Revision No. Title 6 Offsite Dona Calculation Manual (00CM) l Table E5-1 1 Pathway Dose Factors Due to Radionuclides Other Than Noble Gates
- l Cow-Milk-Infant All vegetation Innalation Pathway Meat Pathway Ground Plane Pathway Pathway Pathway
( mReelyr 3 (s2. eelyr ) (m2.mReelyr ) (m2 lyr ) (e2. en/yr > Der uC1/e3 Der uC1/19C Der uC1/14C Der uC1/leC Der uC1/let RadlonuCllde P .1
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T.33 :00 0 :0: .! 7 '0' H-3 :C C-14 3Ml u': h 08 :0'. 4 :i l3 0 1.33E07 3 :01. di :0' d
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.' 7 'O Na-24 1. , :(d- <
I..iid D 2.'Oh u. :1 L. i P-: , . :0' I O 6.'l8 :0' 5 . 3 11:06 f. . . :01 , ?. ' " Cr-t 1.JO b. 7 7.i0:0 I.56':09 .70 :01 u un-54 I.57 L , o Mn-56 1P3 :D - 0 I.03 :06 .45 :0 l . . I .
- 1. ' Pt 4.24 :08 0 .25 :0 i .(t l0 Fe-05. 1 4.0l 'l :0 Fe-b9 I P7 lG , 6.44 :08 3 09i:0' :0 9.44.'07 4.27 :0 7.01 l0 d.:o l0 Co-58 1.'O :Of' '
3.6 :08 2.44 'IU ?.25 :05 P.d b :0 ' Co-00 7 061:0i , 2.88 :10 0 .46 :i0 9 21 :1o N1-N 20T6' , 0 3.32 :05 . .I :01 .42 :0:, N1-1& 3 91:06
- 0. 9 '05
. 671:04 I . IT 705 6.62 l05 4.5 ;06 Co-ot 4.99 :10 0 :09 0 94F05 1.05 :09 8.28':08
^ Zn-o59 1 . 321:04 0 0 9.07 :-09 1 .M, A3 Z n-4 0 6 81 :03 0 l'. Lb '00 er-1 3 4.73 :0P l-l i 0 2.27 l05 0 h.'
Br-. 4 5 471:0P 0 0 0 0 Br. l5 2.39fo 2.47E10 5.39E08 I RD-86 I 98EOS 6.39E04 9 87E06 Rb-88 5 62E02 0 3 63E04 0 0 ~l 0 1 40lD5 0 0 ', RD-89 3.45E02 2 15 :06 5.200.08 2.42E04 1 36 :10 4 . 311:T7 - ~ Sr-89 a 99 3.66 :12 1 01 :08 4.27 :10 0 :ll Sr-90 3 92 :05 6.39 l06 1 74 :05 6.59 :-10 2 42Ed'6 Sr-91 6 ii '01 I 61 '04 Sr-92 2 42 :05 0 8 T6(05 . 5.93E05 5 12E03 1 13 :06 7 88 '07 f-90 2 68E05 _.. s#2.34 :-IS I 89':-05 Y-91M 2 ale 03 0 1 121'05 v.91 2 6fE06 2.41E08 6 04MMOM f 5 271:06 2 87 :09 5.3h :04 i 2 39E0h 0 W 2JdN;VM i YiL 1 1 24E01 , f42 > ' ' ' 2 06 :04 5 2? :06 y.'iD 3.88 'Oh I 40 -0 7 a
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6.00 :08 T 73:01 8.76-:05 10F ,09 .
Ir-% 2.23 :06 5:,6 :04 1.49E07 3.5l :05 8.64 :-l 3. 32 f6 {
Zr.C 3.74 (08 Ng ')5 6. I J ;0h 2. 3.i l09 ! .5 I h}EO(6<, L ~" 2.: 91:04 i.98[07 2 U ID5 3: 4C08
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Radiological Controls Department 9100 PLN 4200.01 stevision No. 6 Offttte e 2 calculation Manual (OOCM) Table E5-1 (Cont'd) Patheny Dose Factors Oue to Radionuclides Other Than Notte Gases
- Cow-81t ik-Inf ant All ve9etation Inhalation Patthesy Meat Pathway Ground Plane Pathway Pathway Pathway Rt Rt Rt Rg R,
( mRee/yr (o2 mRee/yr ) (m2 eRee/yr } (e2 aRee/yr ) (e2.aRee/yr 3 RadioeuCllde Der uC1/e3 } Der uC1/see Der uC1/sec oor uCl/sec Der uCl/sec Tc-99M 4.80:01 0 2.03t05 2.olt04 6.32E03 Tc-601 .4:l ;0 O 2 til :04 0 0 Au- 01 TO' - 4.15E09 1.2P l0ll l .45 '05 4 . 61 ,
- 04 Ru- 0 ' d.
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0 6.9L :0'- :l.F l0 1.1 Os Ru- 0 4
- 'O' it.io :l '> 4 . 8,. :01 '- ;
- 06 . 3l l '1 As- inM U.d 1 l0 i .i,3 :D _38 , ,0' .
.ii :10 J.2
Cd- l'M J' 7 :0 , .52 0 u n. 07 , Sn- P l, P :0 J.! 3 :10 P. 71L ;10 . 04 , ;i. J . 5' Sb-lh J'.3P .01. i il4 :07 a$ :0' I.o!. ) ' 3 Te-1; 1M 4.7" '0!' .L4 :0 ; .05 : 04 l.i,li :) h.0 Te-1; 'M l.40 :04. ' l .1' l ;0 1 04 :05 1. ,
- ) 1,.0 To-IP7 5.W ;0i .71 A4 3.l5 :0: l 1.03 ;'),. o.50 ,
Te-1;?el I.' 0 :0d. u.83 :0t 2.22 :0: 1.'4 :-)d ' > . 3:, D i Te-lW 2.i': :0<. 0 2 99 :04 2.. 2 Mi? 4 80 '-u2 To-l: M 3.tG :0! 1.22C04 j.Il :06 2.. 6:01 . .72 :07 - Te-l: 'I 8.: I :0: 0 2.33 l07 0 .04 :-14 Tu-1:2 3.?7E0' l.16 :07 4.80 :06 7 90 '07 .04 :07 ;
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- 1.8eE00 3. 32 :-04 3.22 :06 4.2L :Oli i .. h5 :07 )
-1: 1 1.62 :0' 2.60':09 'i~01 :07 4. 9! :) > , l T :10 I
-1: 2 1 93-:05 0 '~
"*1.06 :0'i 6. M :0 'o l03 I
-1: l 4 41:00 :04 o :08 3 ll 64 :06 6 46E01 6 6:;
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-1: 4 !l.06f04 0 }'TE:05 0 2.s . -0 3 i
-1: 5 91':05 0 I 42 :06 9.61 :06 4.T2':06 I
- Cs-1: 4 6 10-:06 1.4:- '09 WOET)9 6.421:10 3.08i:10 i Cs-l: 6 1.71 :05 5 . 0'i :07
- 64F0& a M 6 611:09 2.69. :0#, !
Cl-137 0 05':05 1.32 :09 i Th20MT \ 5 . 9 41:10 3.i? :10 l C5-l)8 11T$iO2 0 _ WARELTW" ! 0 9.91 ' il f 84-139 !>.76E04 0 a W@ + ME05 ! 2.951: 05 . 05jo0 _ { 84 140 1 74E06 5.00E W 1- ou 2 26C07 ! 2.75':08 a. 9;:08 ' l B4-141 4 74E03 0 v_ _a J ' 4 7E04 1 0 0 t Ba-142 164f67 0 4' Tf04
- 0 0 L,4-140 2 25 :05 6.72E02 2 . 1 01:07 2.28 :05 3.80E07 La-142 7.57 :04 0 8 52 l05 6. 71 . -06 l . D10 Co-141 5.43 :05 1.45 :07 1.48 :07 1.4: :07 4 71 :00
[ Ce-143 1.27 ;05 3.07 :02 2.5) :06 1.8! n ;06 l.6; :0'l R
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' ' ' Number Nuclear m RadiclociCal Controls Depar? men? 9100-PLN-4200.01 Revision No.
Title 6 Offette Doam calculation Manual (ODCN) i Table (5-1 (Cont'd) Pathway Dose Factors Due to Radionuclides Other Than Nocle Geses' Co b ilk-Infant All Vegetation Inhalation Pathway Meat Pathway Ground Plane Pathway Pathway Pathway Rg Rg Rg Rg Rg: ( mace /yr (al mRee/yr 3 (a2 mRealyr ) (el mReelyr ) (e2 mas @ ) eadlonuclide oer uCl/e3 ) eer uCl/sec per uC1/sec oor uCI/see per uCt/seca Co-led 1.19(07 1 78t08 7 71t07 1.26t08 l.ittle Pr-143 4.3" :05 4.10E07 0 8.90E05 1.87[08 Pr-144 4.2 :03 0 2.031:03 0 0 Md-147 3.2 :05 1 . 7 61:07 9.77 :06 6.6510' , 1
.11 E 0dl A187 9.09 '04 3 en :00 2.64 T6 3.01 :0< , n .45b i hP-239 6.3F: 2.64 :03 6 90E06 ~
1.63 :05 .62 :0' ' Pu-239 1.94 i0 0 2.14167 2.20 :0'J .13 :l '.
' The listed dose parameters are for radionuclides, other tnan nocle gases tnat may be detected in gaseous effluents. Ri factors include all nonataospheric patnuay transport parameters, the receptor's asage of pathway media, and are based on the most restrictive age group (Infant or child) critical organ. Additional dose parameters for nuclides not included in this table may be c %ssing tne methodology described In NUREG-0133, 00CM Reference 1. g t
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Title 7 Offstte base Calculation Manual (00CM) Table 1 TMINS REMP STATION LOCATIONS-AIR PARTICULATE AND AIR IODINE NUREG Distance Azimuth Map No. Station Code A1-1 0.4 mi. O' 1 El-2 0.4 95 2 1.3 253 3 H2-1 2.6 358 4 A3-1 2.3 159 5 H3-1 9.8 127 6 G10-1 12.6 180 7 J15-1 13.5 305 8 Q15-1 Table 2 THINS REMP STATION LOCATIONS-DIRECT RADIATION (TLD) NUREG Distance Azimuth Map No. Station Code I Al-1 0.4 mt. O' 1 0.3 9 Al-4 5 0.6 25 10 B1-1 0.4 26 11 B1-2 l 0.5 15 12 B1-3 0.3 54 13 [ Cl-2 : 0.2 74 14 01-1 El-1 0.2 - . y 95 15
% 95 2 El-2 98 16 El-4 17 F1-2 1 0.2 109 0.3 129 18 G1-3 0.5 167 19 H1-1 ,
0.3 167 20 1 H1-9 0.8 184 21 J1-1 l 0.3 189 22
- J1-3 ,
2 0.4 188 23 J1-4 0.2 208 24 E Ki-4 K1-5 0.2 202 25 2 26 L1-1 0.1 235 3 27 N Mi-1 0.1 249 j< N1-3 P1-1 0.1 0.4 270 293 28 29 0.2 290 30 g PI-2 0.2 318 31 Q1-2 0.2 335 32
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'"o Nuclear m -i Radiological Controls Department 9100-PLN-4200.01 Revision No.
Title 7 0*fsite Doss Calculation Manual (00CM) Table 2 (Cont'd) NUREG Map No. Distance Azimuth Station Code 1.6 mi. 48' 33 C2-1 34 1.1 200 K2-1 3 1.3 253 H2-1 4 2.6 358 A3-1 5 2.3 159 H3-1 35 2.6 338 R3-1 36 4.8 18 B5-1 37 4.5 42 C5-1 38 ES-1 4.6 81 107 39 FS-1 4.7 40 G5-1 4.8 131 41 4.1 157 H5-1 42 4.9 182 J5-1 43 5.0 200 K5-1 44 4.1 228 L5-1 45 4.3 249 M5-1 46 4.9 268 NS-1 47 4.9 285 P5-1 48 l 5.0 318 05-1 339 49 RS-1 4.9 65 50 06-1 5.2 51 6.8 86 E7-1 52 8.5 , 308 Q9-1 ,', 5 53
> 21 810-1 G10-1 G15-1 h 14.4 127 124 180 6
54 7 l i J15-1 12.6 8 13.5 305 015-1 329 55 R15-2 12.4 a E a e h l l ! l 8 e A000105011 8. 0940c E6-2
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Nuclear mt-i Radiological Controls Department 9100-PLN-4200.01 ! Revision No. l Title 7 ! Offsite D ie Calculation Manual (00CM) ) i Table 3 ) J THINS REMP STATION LOCATIONS-SURFACE WATER l NUREG Azimuth Mao No. j Station Code Distance 284' 56 PI-3 (R) 0.1 mi. 0.5 188 57 J1-2 (R) 182 58 J2-1 (R) 1.5 2.5 355 59 A3-2 (R) 165 60 H3-2 (R) 2.9 157 61 H5-2 (R,F) 4.2 308 52 09-1 (R,F) 8.5 14.4 124 54 G15-1 (R,F) 62 13.6 128 G15-2 (F) 124 63 G15-3 (F) 14.8 14.7 178 64 , J15-2 (F) 122 65 F15-1 (R) 12.6 (R) - Raw Water (F) - Finished Water Table 4 THINS REMP STATION LOCATIONS-A0UATIC SEDIMENT NUREG Map No. Distance Azimuth Station Code 6* 66 i Al-2 0.8 mi. ! 0 67 Al-3 0.5 ! 68 G1-1 p 137 Ki-3 J2-1 h.' .5 n
- 202 182 214 69 58 71 jj L1-3 0.2 ! I l
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' ' ' - Number Nuclear mt-1 Radiological Controls Department 9100-PLN-4200.01 Title Revision No.
7 Offsite N r Calculation Manual (00CM) a Table 5 THINS REMP STATION LOCATIONS-MILK NUREG Distance Azimuth Map No. Station Code A2-1 (MG) 1.2 mi. 5* 72 015-2 (MG) 10.0 68 73 D2-1 (M) 1.1 65 74 G2-1 (M) 1.4 125 75 P7-1 (M) 6.7 293 76 K15-2 (M) 12.8 208 77 F3-1 (M) 2.3 104 78 E2-2 (M) 1.1 93 79 (MG) - Goat Milk (M) = Cow Milk j Table 6 THINS REMP STATION LOCATIONS-FISH Station Code Station Designation TM-AQF-IND t p S ijnDischarge {ljp ('f no TM-AQF-BKG Discharge AQF = Fish l l h o I
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Nder tat-i Radiological Controls Department 9100-PLN-4200.01 Revision No. Title 7 Offsite h a Calculation Manual (00CM) Table 7 THINS REMP STATION LOCATIONS-F000 PRODUCTS NUREG Distance Azimuth Map No. Station Code 1.1 mi. 65* 74 02-1 1.4 125 75 G2-1 A9-2 9.3 357 80 P3-1 2.6 293 81 A15-1 10.5 10 82 El-3 0.7 90 83 E2-1 1.1 80 84 H1-2 0.9 150 85 E6-1 5.9 100 86 M15-2 13.6 253 87 01-3 0.5 65 88 _ ' A2-1 1.2 5 72 P7-1 6.7 293 76 12.8 208 77 K15-2 D15-2 10.0 68 73 F3-1 2.3 104 78 E2-2 1.1 93 79 B15-1 10.3 12 89 e
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, e ENuclear w -i Operatino Procedure
"""6'r 1104-28I Title Revision No.
Wste Solidification Process Control Program 9 App'icability/ Scope Responsible Office TMI-I Division Plant Oos. Dir. This document is within QA plan scope X Yes ,_, No Effective Date Safety Reviews Required . X Yes No Important to Safety Environmental Impact Related
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X Yes Yes [ No No 06/16/87
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CONTROLLED COPY. FOR . List of Effective Pages E IN UNIT 10 . Page Revision Page R,_evi s ion Page Revision Rev on 1.0 9 El-1 8 E9-1 8 2.0 8 El-2 8 E9-2 9 3.0 8 El-3 8 E10-1 8 4.0 8 El-4 9 E10-2 9 5.0 8 E2-1 8 E10-3 8 6.0 8 E2-2 9 E11-1 7 7.0 9 E2-3 7 E12-1 9 8.0 9 E3-1 8 9.0 8 E3-2 8 - 10.0 9 E3-3 8 hs 11.0 9 E3-4 9 ids\ Q g 12.0 13.0 8 9 E4-1 E4-2 8 9 iF g 14.0 9 E4-3 7 ('- I 15.0 16.0 9 9 ES-1 ES-2 9 9 D g- , 17.0 9 E6-1 8 J ^ 18.0 9 E6-2 9 19.0 9 E6-3 7 20.0 9 E7-1 8 21.0 9 E7-2 9 j 22.0 9 E8-1 8 j 23.0 9 E8-2 9 24.0 9 E8-3 8 ll Signature l Concurring Organizational Element l Dat ' e _- Oriainatorll d i d h w - I Oriainator I 6 $L Concurred ll C l l , By ll k ,,&c.dkoOO s l Procedure Owner j ( - f.7) ll . l l ll / E Ns hf m i PRG _ l4/11ff7 ll l _ l 11 I I Approved ll M l Approver l 6 -- E 7 By ll U l 1 - - - . . _ _ _ . . . l l 1.0 1372c
l s e Nuslear "u*'r 1MI_i Operating Procedure 1104_2g1 Title Revision No. Waste Solidification Process Control Program 8 r Table of Contents Section Page 1.0 DISCUSSION 4.0
2.0 REFERENCES
4.0 3.0 LIMITS AND PRECAUTIONS 5.0 4.0 TEST SOLIDIFICATION OF 4 TO 10 WT% BORIC ACID 6.0 (CONCENTRATED WASTE) 4.1 Prerequisites 6.0 4.2 Procedure 7.0 { 5.0 TEST SOLIDIFICATION OF > 10 TO 20 WT% BORIC ACID 10.0 (CONCENTRATED WASTE) 5.1 Prerequisites 10.0 5.2 Procedure 11.0 6.0 TEST SOLIDIFICATION OF WASTE OIL 6.1 6.2 Prerequisites Procedure
# 13.0 13.0 14.0 7.0 TEST SOLIDIFICATION OF USED PREC0AT 15.0 7.1 Prerequisites 15.0 7.2 Procedures 16.0 8.0 TEST SOLIDIFICATION OF BEAD RESIN 18.0 8.1 Prerequisites 18.0 8.2 Procedure 19.0 9.0 ALTERNATE TEST SOLIDIFICATION PROGRAMS 21.0 9.1 Prerequisites 21.0 9.2 Procedure 22.0 2.0 137::
I
- t Nuslear TMI-i Operating Procedure 1104-28I Title Revision No.
Weste Solidification Process Control Program 8 Table of Contents (Cont'd) Section Page 10.0 ACCEPTANCE CRITERIA 22.0 l ATTACHMENT 1 Class A Unstable and Stable, Class B and C Test El-1 Solidification Data Sheet for 4 to 10 wt% Boric ! Acid l ATTACHMENT 2 S)lidification Calculation Sheet for 4 to 10 wt% E2-1 Baric Acid ATTACV9fN' .1 C, ass A Unstable and Stable, Class B and C Test E3-1 d S9lidification Data Sheet for > 10 to 20 wt % Boric Acid ATTACHMENT 4 Solidification Calculation Sheet to E4-1 ) 20 wt % Boric Acid l ATTACHMENT 5 Class A Unstable and 5 ass B and C Test ES-1 Solidification Data She or Haste 011 ATTACHMENT 6 Solidification Calculation Sheet for Waste 011 E6-1 ATTACHMENT 7 Class A Stable, Class B and C Test Solidification E7-1 Calculation Sheet for Used Precoat ATTACHMENT 8 Solidification Calculation Sheet for Used Precoat E8-1 ATTACHMENT 9 Class A Stable, Class B and C Test Solidification E9-1 Data Sheet for Bead Resin ATTACHMENT 10 Solidification Calculation Sheet for Bead Resin E10-1 1 ATTACHMENT 11 Test Solidification using Westinghouse - Hittman Ell-1 l Procedure FIGURE 1 Percent Solids of pH Adjusted Waste vs. Water / E12-1 Cement Ratio l' l 3.0 '37:: I
e r Nuslear TsI-i Operatina Procedure 1104-28I Title Revision No. ; Waste Solidification Process Control Program 8 1.0 DISCUSSION The purpose of the Process Control Program (PCP) for incontainer solidification is to provide a program which will assure a solidified product with no free standing liquid prior to transportation for disposal and which meets the re-quirements of 10 CFR 61.56, Waste Characteristics, i The PCP's for each waste stream included in this procedure are based on labora- l tory testing, the results of which are included in " Topical Report Cement Solidified Weste to Meet the Stability Requirements of 10 CFR 61" prepared by Westinghouse - Hittman. These PCP's are valid for all liner types using elec-tric or hydraulic mixing heads provided by Hittman. The appropriate portions of this document shall be considered complete only when I used with the operating procedures (OP 1104-28A for borated and oily wastes or OP 1104-28C for resin) for full scale solidification. This document describes the methodology for determining the acceptable ratio of waste, cement and additive that will result in an acceptable product for transportation and ultimately burial. The Solidification Data / Calculation Sheets convert these ratios into the recommended quantity of cement and additive that should be mixed with Class A unstable waste and the recommended quantity of cement and additive which must be mixed with Class A Stable and Class B or C wastes.
2.0 REFERENCES
2.1 Westinghouse - Hittman F421-P-004, P ntrol Program for Incontainer Solidification of 4 to 20 wt7. Borj i 2.2 Westinghouse - Hittman STD , Process Control Program fu Incon- I tainer Solidification of ste 2.3 Westinghouse - Hittman F421-P-006, Process Control Program for Incontainer I Solidification of Powdered Resins 2.4 Westinghouse - Hittman F421-P-005, Process Control Program for Incontainer Solidification of Class A Unstable or Stable, Class B and C Resin at Maximum Packaging Efficiency 2.5 Westinghouse - Hittman STD-R-05-007 Topical Report Cement Solidified Waste to Meet the Stability Requirements of 10 CFR 61 I 2.6 Westinghouse - Hittman STD-R-05-011 Topical Report Mobile Incontainer l Dewatering and Solidification System (MDSS) 2.7 NRC Letter from Charles E. Rossi, Assistant Director, Division.of PHR I Licensing-A to R.J. Leduc, Director of Engineering Westinghouse Hittman - )
" Acceptance of Referencing of Licensing Topical Report STD-R-05-011, i Hittman Mobile Incontainer Dewatering and Solidification System (MDSS)". jl Dated Oct. 31, 1986. ll 4.0 137::
I J
Nuclear Ts!-i Operating Procedure
,_ 1104-28I Title Revision No.
Waste Solidification Process Control Program 8 2.8 Tech. Spec. Section 3.22.3, Solid Radioactive Waste 2.9 GPUN Radiation Protection Plan 3.0 LIsITS AND PRECAUTIONS 3.1 As' required by Tech Spec 4.22.3.1.2, the PCP shall be used to verify the solidification of at least one representative test specimen from at least l' every tenth batch of each type of wet radioactive waste (e.g., evaporator bottoms, oily waste, resin and precoat sludge). 3.2 For the purpose of the PCP a batch is defined as that quantity of waste required to fill a disposable liner to the appropriate level on the waste level indicator. 3.3 If any test specimen fails to solidify, solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the Process Control Program, and a subsequent test veri-fies solidification., Solidification of the batch may then be resumed using the alternate solidification parameters determined. 3.4 If the initial test specimen from a batch of waste fails to verify solidt-fication then representative test specimens sh 11 be collected from each consecutive batch of the same type of waste the three (3) consecu-tive initial test specimens demonstrate 1 ation. The Process Centrol Program shall be modified as I to assure solidification of subsequent batches of waste. 3.5 For high activity wastes, such spent resin or used precoat, where handling of samples could result in personnel radiation exposures which are inconsistent with the ALARA principle, representative non-radioactive samples will be tested. These samples should be as close to the actual waste physical and chemical properties as possible. Typical expended
)
mixed bed resin shall be used to simulate the spent bead resin and the appropriate mix of anion to cation powdered resin shall be used to simu- { I late used precoat. 3.6 All Chemicals used to condition or solidify waste or simulated waste in solidification tests shall be the actual chemicals used in full scale solidification. j l' 3.7 A Test Solidification Data Sheet will be maintained for each test sample solidified. Each Data Sheet will contain pertinent information of the test sample and the liner numbers solidified based on the test sample. j l l ! 1 5.0 13M: l l \
Nu21 ear Tm-i Operating Procedure 1104_281 Title Revision No. ; Waste Solidification Process Control Program 8 3.8 Samples should be drawn at least six hours prior to the planned full scale waste solidification to allow adequate time to complete the required testing and verification of solidification for Class A unstable waste. 28 hours should be allowed, if practical, for Class A stable, Class 9 and C wastes. 3.9 The tank containing the waste to be solidified should be mixed by recircu-lating the tank contents for at least three volume changes prior to sampling to assure a representative sample, 3.10 If the contents of more than one tank are to be solidified in the same liner then representative samples of each tank should be drawn. These samples should be of such size that when mixed together they form samples of standard size. If the contents of a particular tank represents X percent of the total waste quantity to be solidified tnen the sample of that tank should be of such size to represent X percent of the composite samples. 3.11 An RWP must be obtained and used for performing test solidification of radioactive samples. . 4.0 TEST SOLIDIFICATION OF 4 TO 10 WJA@h CID (CONCENTRATED WASJ D 4.1 Prerequisites NOTE: This PCP Test Solidification Procedure is applicable to Class A Unstable, Class A Stable. Class B and C Waste Forms. 4.1.1 A sufficient size sample of concentrated waste (approx. I liter) has been drawn and the following parameters analyzed for by Plant Chemistry:
- Boron !
l
- pH
)
- Total Solids
- Gamma Scan NOTE: The total solids and gamma scan are used for information ;
purposes only to track waste characteristics and are not j to be used in the Process Control Program calculattens. l 6.0 1E:
l 1 s . U2 I TMI-l Operating Procedure 1104.28I Titic Revision No. Waste Solidification Process Control Program g NOTE: The Concentrated waste sample shall be kept heated (> 100'F) ! unless previously neutralized. The acceptable pH range for concentrated waste is 7.4 to 9.2. 4.1.2 The Ops Quality Assurance Group has been contacted to inform th6,n of the pending Test Solidification to see if they care to witness the test. 00A Monitor Co-tacted Name / Date / Time 4.1.3 The . appropriate portions of Attachment I have been completed including waste classification, chemictry information, balance calibration data ano the sequential shmple number. 4.2 Procedure NOTE: Tare weights of waste, cement, additives, etc. should be obtained during performanc of the following procedure. Round off to the nearest m. 4.2.1 Calculate the weig ent of Boric Acid on Attachment 1. 4.2.2 MEASURE 500 . ntreated concentrated waste into a contaire-4.2.3 RECORD the weight and volume on Attachment 1. 4.2.4 ADD 50 wt% sodium hydroxide (NaOH) until the pH is between 8 to 8.5 for Class A unstable, Class A stable, B and C solidifica. tion. 4.2.5 RECORD the weight of NaOH used and the 3djusted pH on Attachment 1. 4.2.6 If large (i.e., foam causing) quantitles of detergents are present, TREAT the tample with an anti _ foaming agent until thE foam disappears. 4.2.7 RECORD the weight of anti _ foaming agent used on Attachment 1. 4.2.8 If oli is present in stable waste in a quantity greater than 19 by volume, reduce the quantity of oil to less than 1% by skimming. For unstable waste if oil is present and the volu c is between 3 and 12*, of the volume of Waste, TREAT with an 7.0 137::
Nn21 ear 1sl.1 1 Operatino Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 9 l emulsify;ng agent such as Maysol 776 (20% of the volume of oil). Oil in concentrations > 12% by volume may not be solidified by this procedure. (Refer to Section 6.0 765t Solidification of Haste 011). NOTE: The density of Haysol 776 is I.0 g/ml; the volume in ml is equal to the weight in grams. 4.2.9 RECORD the % oil and the quantity of any (mulsifying agent used on Attachment 1. 4.2.10 Record the volume and calculate the weight of the treated Sample on Attachment 1. 4.2.11 Calculate the percent solids in the sample by completing items (9), (10), (11) and (12) in Section II of Attachment 1. 4.2.12 For the test' solidification of the concentrated waste, measure into a mlsing vessel 40 ml of pretreated waste. NOTE: Test solidific should be conducted using a 1,000 ml disposable or similar size container. 4.2.13 RECORD t clume AND weight of the treated sampie on Attachmenf 1. 4.2.14 Calculate the water in the sample by completing items (15). (1E' and (17) in Section III of Attachment 1. 4.2.15 Using Figure 1 and the percent solids from the Test Solidifice-tion Data Sheet. Item (12), DETERMINE the water /cenent rati ! then CALCULATE and WEIGH out the required quantity of Portland l Type I cement. I 4.2.16 RECORD the weight of cement on Attachment 1. I I i 4.2.17 CALCULATE and WEIGH out the required quantity of metso beads, i i.e., anhydrous sodium metasilicate (ASMS), into a separate { j vessel. 4.2. 3 RECORD the weight of ASMS on Attachment 1. ' i l I s.0 13 :: )
Nuzlear "" THr_i Operating Procedure 1104_28! Title Revision No. Waste Solidification Process Control Program 8 1 4.2.19 Slowly A00 the cement to the test sample while it is being mixed. NOTE: Mixing should be accomplished by stirring with an electric ' mixing motor with blade or manually with a rigid stirrer untti a homogeneous mixture is obtained, approximately one minute. 4.2.20 After All the cement is added, slowly ADD the ASMS to the test sample while it is being mixed. 4.2.21 After sufficient mixing (2 minutes after ali the ASMS is added) so that a homogeneous mixture is obtained, SEAL the sample and CURE at 120 1 5'F for 24 hours for Class A Stable, Class B or C or at room temperature for Class A unstable. NOTE: If at any time during the 24 hour cure, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be disqualified without at least 24 hours of cure. 4.2.22 Verify the Acceptance Criteria (Sect 1 as been met and sign and date Attachment 1. 4.2.23 When the Acceptance Criteri en met per Section 10, - calculate the required qua a of cement and additives for the full scale solidificati n using a liner type applicable for this waste type (as determined by Radwaste Operations Engineer _ ing) and the Solidification Calculation Sheet for 4 to 10 wt% Boric Acid (Attachmer.t 2). NOTE: The liner shall be solidified using OP 1104-28A, Radio active Waste Solidification - Hittman. 4.1.24 Complete Section VI of Attachment 2 upon completion of the j solidification if cement remains in the hopper. 9.0 127::
Nu21 ear 1m_i
""*b" Operatino Procedure 1104 28I Title Revision No.
Waste Solidification Process Control Program g 5.0 TEST SOLIDIFICATION OF > 10 TO 20 wt% BORIC ACID (CONCENTRATED WASTE) 5.1 Prerequisites NOTE: This PCP Test Solidification Procedure is applicable to Class A Unstable, Class A Stable, Class B and C Haste Forms. 5.1.1 A sufficient size sample of concentrated waste (approx. I liter) ' has been drawn and the following parameters analyzed for by Plant Chemis+ry: '
- Boron
- pH
- Total Solids Gamma Scan NOTE: The total solids and gamma scan are used for information purposes only to track waste cha,rActeristics and are not to be used in the Process Coqtro? Program calculations.
__________________.________.___________.gyQ_____._________._______-_...___.
+N
_ _ NOTE: _ _ _ _The _ _Concentrated _ _ _ _ _wagte_ _sample _ _ _shall _ _be_kept
. _heated
___ (> 130'F) unless previously ne0tralized. The acceptable pH range for concentrated waste is 7.4 to 9.2. 5.1.2 The Ops Quality Assurance Group has been contacted to inform them of the pending Test Solidification to see if they care to witness the test. OQA Monitor Contacted Name / Date / _ Time 5.1.3 The appropriate portions of Attachment 3 have been completed including waste classification, chemistry information, balance calibration data and the sequential sample number. 10.0 1372:
I' . . l Nuclear Tsi_i Operatino Procedure 1104 28I Title ' Revision No. Waste Solidification Process Control Program 9 5.2 Procedure NOTE: Tare weights of waste, cement, additives, etc. should be obtained during performance of the following procedure. Round off to the nearest gram. 5.2.1 Calcu! ate the weight percent of Boric Acid on Attachment 3. 5.2.2 MEASURE 500 gms of untreated concentrated waste into a container. 5.2.3 RECORD the weight and volume on Attachment 3. 5.2.4 ADD 50 wt% scitum hydroxide (NaOH) until the pH is between 12 and 12.5 5.2.5 RECORD the weight of NaOH used and the adjusted pH on Attachment 3. 5.2.6 If large (i.e. , foam causing) ities of detergents are present, TREAT the sample n anti-foaming agent. 5.2.7 RECORD the weight o caming agent used on Attachment 3. 5.2.8 if oil is presen table waste in a quantity greater than 1.. by volume, red: e e quantity of oil to less than 1% ty skimming. For unstable waste if oil is present and tne volutt is between 3 and 12% of the volume of waste, TREAT with an emulsifying agent such as Maysol 776 (20% of the volume of oil). Oil in concentrations > 12% by volume may not be solidified by this procedure. (Refer to Section 6.0 Tes: Solidification of Waste O'1). NOTE: The density of Maysol 776 is 1.0 g/ml; the volume in ml is I equal to the weight in grams. 5.2.9 RECORD the 1 oil and the quantity of any emulsifying agent used on Attachment 3. 5.2.10 Record the volume and calculate the weight of the treated san;ie on Attachment 3. 5.2.11 Calculate the percent solids in the sample by completing iteI; (9), (10), (11) and (12) in Section II of Attachmer.t 3. 11.0 1372:
Nu21 ear' ""***' Tsi_i Operating Procedure 1104 281 Title Revision No. Haste Solidification Process Control Procram 8 5.2.12 For the test solidification of the concentrated waste, measure into a mixing vessel 400 ml of treated waste. NOTE: Test solidification should be conducted using a 1,000 ml disposable beaker or similar size container. 5.2.13 RECORD the volume AND weight of the sample on Attachment 3. 5.2.14 Calculate the water in the sample by completing items (15), (16) and (17) in Section III of Attachment 3. 5.2.15 Using Figure 1 and the percent solids from the Test Solidifica-tion Data Sheet, Item (12), DETERMINE the water / cement ratio then CALCULATE and HEIGH out the required quantity of Portland Type I cement. 5.2.16 RECORD the weight of cement on Attachment 3. 5.2.17 CALCULATE and HEIGH out the required quantity of anhydrous sodium metasilicate (ASMS) into a separate vessel. 5.2.18 RECORDtheweightofASMSonj \ ment 3. 5.2.19 Slowly ADD the cement t St sample while it is being mixed. NOTE: Mixing should b plished by stirring with an electric mixing motor wit lade or manually with a rigid stirrer until a homogeneous mixture is obtained, approximately one minute. 5.2.20 After all the cement is added, slowly ADD the ASMS to the test sample while 't is being mixed. 5.2.21 After sufficient mixing (2 minutes after all the ASMS is added) 50 that a homogeneous mixture is obtained, SEAL the sample and CURE at 120 1 5'F for 24 hours for Class A Stable, Class B or C 1 or at room temperature for Class A Unstable. NOTE: If at any time during the 24 hour cure, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be dis-qualified without at least 24 hours of cure.
AUCl68r Tm _ i Operating Procedure 1104_28I Title Revision ho. Waste Solidification Process Control Program g 5.2.22 Verify the Acceptance Criteria (Section 10.0) has been met and i sign and date Attachment 3. ' 5.2.23 When the Acceptance Criteria has been met per Section 10, calculate the required quantities of cement and additives for the full scale solidification using a liner type applicable for this waste type (as determined by Radwaste Operations Enginte - ing) and the Solidification Calculation Sheet for > 10 to 20 Boric Acid (Attachment 4). NOTE: The liner shall be solidified using OP 1104-28A, Radioactive Haste Solidification - Hittman. 5.2.24 Complete Section VI of Attachment 4 upon completion of the solidification if cement remains in the hopper. 6.0 TEST SOLIDIFICATION OF WASTE OIL (12 - 40% 011) 6.1 Prerequisites NOTE: This PCP Test So cation Procedure is applicable to Class A Unsta ass A Stable, Class B and C waste fccms. 6.1.1 A suffic 2e sample (approx. 500 ml.) each of pH adjusted concen waste and waste oil have been drawn. The concen-trated e shall be within a pH range of 7.4 to 9.2. NOTE: The pH of the concentrated waste will be adjusted in the tank before the test solidification. 6.1.2 The Ops Quality Assurance Group has been contacted to inform them of the pending Test Solidification to see if they care to witness the test. OQA Monitor Contacted { Name / Date / Time j 6.1.3 A sequential sample number has been assigned to the test and included on Attachment 5. - 6.1.4 A determination has been made as to the waste class of the pending full scale solidification by Rad *aste Ops. Engineerin; 13.0 137:: L_____ __-- _ - !
Nuslear i 1m _ i
""*b" i t
i Operating Procedure 1104 28I Title Revision No. Waste Solidification Process Control Program g 6.1.5 The balance calibration data has been included on Attachment 5. 6.2 Procedure NOTE: Tare weights of waste, cement, additives, etc. should be l ,; obtained during performance of the following procedure, i Round off to the nearest gram. 6.2.1 Measure into a mixing vessel 210 ml of concentrated waste and 140 ml oil. NOTE: Test so'idifications should be conducted using a 1000 ml disposabis beaker or similar size container. 6.2.2 Record the wast $ volumes ad and calculate the percent oil by volume on Attachment 5. 1 6.2.3 2 gms) of Maysol 776. . 1 6.2.4 MEASUREout/8.0m RELORD the q f the emulsifier on Attachment 5. i 6.2.5 ADD the Mayso 776 to the waste and mix until a homoge.neous mixture is obtained, at least five (5) minutes. NOTE: Mixing should be accomplished by stirring with an electric mixer with blade or manually with a rigid stirrer. Any signs of pure oil may be an indication that the er.lsion is breaking down. Should this occur, contact Radwaste Ops. Engineering for further instructions. ; 6.2.6 If large (i.e., foam causing) quantities of detergents are present, treat, the sample with anti-foaming agent until the foam disappears. 6.2.7 Record the amount of anti foaming agent used on Attachment 5. 6.2.8 MEASURE out 447.3 gms of Portland Type I cement and 51.8 gms cf anhydrous sodium metasilicate (ASMS). 6,2.9 PECORD the quantitles of cement and ASMS on Attachmer.t 5. 14.0 137::
MUClear im _ i
""*b" Operating Procedure 1104 28I Title Revision No.
Waste Solidification Process Control Program 9 6.2.10 Slowly ADD the cement to the test sample while it is being mixed and mix until a homogeneous mixture is obtained but in no case less than one (1) minute. 6.2.11 After all the cemert is added, slowly ADD the ASMS to the test sample while it is being mixed. 6.2.12 MIX for two (2) minutes after all the ASMS is added and homo _ geneous mixture is obtained. 6.2.13 Seal the sample and cure at 120 1 5'F for 24 hours for Class A Stable, Class B or C or at room temperature for Class A Unstable. NOTE: If at anytime during the 24-hour cure time, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be disqualified without at least 24 hours of cure. 6.2.14 VerifythekcceptanceCriteria(Section10.0) has been met and sign and date Attachment 5. 6.2.15 When the Acceptance Criteria has been met per Section 10, calcul?te the required quantities of cement and additives for the full scale solidification using a liner type applicable for this waste type (as determined by Radwaste Operations Engineer-ing) and the Solidification Calculation Sheet for Waste Oil (Attachment 6). ____________________________.____________,__ d _________-_________________ NOTE: The liner shali be solidi W ng CP 1104-28A, Radica::1 >e ; Waste Solidification - .. I 7.0 TEST SOLIDIFICA". ION OF USED PREC0A 7.1 Prerequisites NOTE: This PCP Test Solidification Procedure is applicable to ' Class A Stable, Class B and C Waste Forms. 7.1.1 A sufficient size sample of used precoat (approx. 500 cl) has been drawn and the following parameters analyzed for by Plan Chemistry: ) e pH (of sluice water) 15.0 137':
F Nuslear Tsi_i
""**r Operatino Procedure 1104 28I Title Revision No, 1
Waste Solidification Process Control Procram 9 o Gamma Scan NOTE: Where high activity waste could pose personnel radiation exposure problems when performing the test solidification, expended powdex with an appropriate anion / cation ratio shall be substituted. The ratio shall be determined by Redwaste Operations Engineering. A small sample of use precoat (= 20 mis) shall be taken for isotopic analysis. NOTE: Tne g;rma scan is to be used for information purposes only to track waste characteristics and is not to be used in the PCP calculations. 7.1.2 The sample has 5 t to verify < 1% oil by volume. 7.1.3 The Ops Quality Assurance Group has been contacted to inform them of the pending Test Solidification to see if they care to witness the test. OQA Monitor Contacted Name / Date / Time 7.1.4 The appropriate portions of Attachment 7 have been coTp'eted including the balance calibration data and the secuential sars'e number. 7.2 Procedure g NOTE: Tare weights of waste, e additives, etc. Should be obtainee during perf f the following procedure. Round off to tne ne gram. 7.2.1 NEASURE out 381.1 gms of dewatered powdered resin and 151.5 g s of water and place into separate containers. NOTE: Test solidification should be conducted using a 1.000 ml disposable beaker or similar size container.
......_______...._-__._________.___ _..____.--_______..___---______:t_____._.
7.2.2 RECORD the volume and weight of the powered resin on Attaches
- 7.
16.0 137::
Nuslear TM1 i Operating Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program g 7.2.3 ADD t*? water to the powered resin and RECORD the weight of water added and the total volume of waste slurry (water plus resin) on Attachment 7. 7.2.4 If any foam is present, TREAT the sample with an anti-foaming agent. 7.2.5 RECORD the quantity of anti-foaming agent used on Attachment 7. 7.2.6 If oil is present and the volume is between 3 and 12% of the volume of waste, TREAT with an emulsifying agent such as Maysol 776 (20% of the volume of oil). Oil in concentrations > 12. by volume may not be solidified by this procedure. Contact Radwaste Operations Engineering for guidance. NOTE: The density of Maysol 776 is 1.0 gm/ml; the volume in mi is eaual to the ' ght in gms. 7.2.7 REC ity of oil present and the amount of Maysol adde o the sample on Attachment 7. 7.2.8 RECORD the initial pH of the sample on Attachment 7. , 7.2.9 f MEASURE out approximately 10 grams of calcium hydroxide Ca(OH)2. also known as hydrated lime. 7.2.10 Slowly ADD the calcium hydroxide to the powdered resin slurry. two (2) grams at a time. MJX for three (3) minutes betaeen additions until the pH is at least 11.5. ADD an additiona! three (3) grams of calcium hycroxide. This final adaition ma,. or may not alter the pH of the slurry. l NOTE: Mixing should be accomplished by stirring with an electric I mixing motor with Llade or manually with a rigid stirrer until a homogeneous mixture is obtained approximately one l (1) minute. 7.2.11 RECORD the quantity of calcium hydroxide added to the slurry and the final pH on Attachment 7. i 7.2.12 MEASURE out 444 gms of Portland Type 1 cement. l -
)
7.2.13 RECORD the amount of cement on Attachment 7. I 17.0 13:2: L_________--___._-----
(UClear m _i
""*b
- Operating Procedure 1104_28I Title Revision No.
Waste Solidification Process Control Program 9 7.2.14 Slowly ADD the cement to the test sample while it is being mixed. 7.2.15 MIX for two (2) minutes after all the cement is added to obtain a homogeneous mixture. , 7.2.16 RECORD the final sample volume on Attachment 7. 7.2.17 Seal and allow the sample to CURE for 24 hours at 120 t 5'F. NOTE: If at anytime during the 24-hour cure time, the sample meets the acceptance criteria, the liner solidification may proceed. However, no test solidification shall be dis-qualified without at least 24 hours of cure. 7.2.18 Verify the acceptance criteria (Section 10.0) has been met, sigr and date Attacnment 7. 7.2.19 When the AcGeptance Criteria has been met per Section 10, calculate the required quantities of cer..ent and additives using a liner type applicable for this waste type (as cetermined by Radwaste Operations Engineering) ang4heSolidificationCalcula_ tionSheetforUsedPrtr$at(AtacJg;V8). 6 N37E: Tne liner snall be# Y'5tfYedusinoOP 1104_280, Prira , f ResinandPrecoat*fbc'essing_Hittman. ' 8.0 TEST SOLIOUICATION Or BEAD RESIN 8.1 Prerequisites NOTE: This PCP Test Solidification Procedure is applicable to Class A Stable, Class B and C Waste forms. 8.1.1 A sufficient size sample of bead resin (approx. 500 ml) has bee-drawn and the following parameters analyzed for by Plant Chemis_ try:
- pH (of sluice water)
- Gamma Scan l
18.0 137::
i Nuslear 1si-i I Operatino Procedure 1104_281 Title Revision No. l Haste Solidification Process Control Program 9 l _-_-------- . -_ -_----__. -=:--___---..._--__-___.__---._____............--. NOTE: Where high activity waste could pose personnel radiation exposure problems when performing the test solidification, expended non_ radioactive resin shall be substituted. The source of this resin shall be determined by Radwaste Operations Engineering. A small sample of spent resin (= 20 mis) shall be taken for isotopic analysis. NOTE: The gamma scan is to be used for information purposes onl, to track waste characteristics and is not to be used in the PCP calculations. 8.1.2 The sample has $?! co verify < 1% oil by volume. 8.1.3 The Ops Quality Assurance Group has been contacted to inform them of the r7nding Test Solidification to see if they care t; witness the* test. 00A Monitor Contacted gy Name / Date / Time 8.1.4 The appropriate portions k c ment 9 have been completed ation data and sequential sample includingthebalanc,eg*A number. ,g ypgs . 8.2 Procedure v-NOTE: Tare weights of waste, cement, additives, etc. should te obtained during performance of the following procedure. Round off to the nearest gram. 8.2.1 MEASURE tato a mixing vessel 240 gm of dewatered resin. NOTE: Test solidification should L2 ;onducted using a 1,000 ml disposable beaker or similar size container. NOTE: Tap the beaker gently to consolidate the resin prior-to ' measuring the volume. i 19.0 1372:
Nuzioar 1MI.,
"u=" r Operating Procedure 1104_28I Title Revision No.
Waste Solidification Process Control Program 9 ! 8.2.2 RECORD the weight and volume of the sample (resin and water) on Attachment 9. 8.2.3 HEIGH out 2.1 gms of EC-3 into a separate vessel. 8.2.4 RECORD the weight of EC-3 on Attachment 9. 8.2.5 HEIGH out 84.3 gms of water and record the weight on Attachment 9. 8.2.6 ADD the water to the vessel containing the EC-3 and mix thoroughly. 8.2.7 ADD the water /EC-3 mixture to the bead resin and mix thorougly. 8.2.8 If any foam is present, TREAT the sample with an anti. foaming agent. 8.2.9 RECORD the quantity of anti-foaming agent used on Attachmer.t 9. 8.2.10 If oil is present and the volume etween 3 and 127. of the i volume of waste, TREAT with a fying agent such as Maysol 776 (207. of the volume of 11 in concentrations > 127. by volume may not be 5 y this procedure. Contact Radwaste Operatio ring for guidance. NOTE: The density of Maysol 776 is 1.0 gm/ml; the volume in ml is equal to the weight in gms. 8.2.11 RECOP.i the quantity of oil and the volume of emulsifier used on Attachment 9. 8.2.12 RECORD the initial sample pH cn Attachment 9. 8.2.13 MEASURE out approximately 11.5 gms of Calcium Hydroxide Ca(OH)2, also known as hydrated lime. 8.2.14 Slowly ADD the Ca(OH)2 to the resin sample two (2) grams at a time. Mix for three (3) minutes between additions until the o u of the slurry is at least 11.5. ADD three (3) additional gms of l Ca(OH)2 This final additional may or may not alter the pH of the slurry. 8.2.15 RECORD the quar +ity of calcium hydroxide added to the slurry an: l the final pH on Attachment 9. \ l 20.0 1372; L_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
US I THI_1 Operating Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 9 8.2.16 MEASURE out 178.2 gms of Portland Type I cement into a separate vessel. 3 8.2.17 RECORD the weight of the cement on Attachment 9. 8.2.18 Slowly ADD the cement to the test sampie while it is being mixed. 8.2.19 MIX for two (2) minutes after all the cement is added to obtain a homogeneous mix. 8.2.20 RECORD the final samole volume on Attachment 9. 8.2.21 SEAL the sample and allow the sample to CURE for 24 hours at 120 ; 5'F. NOTE: If at anytine during the 24_ hour cure time, the sample meets the acceptance criteria, the liner solidification may proceed. Howsver, no test solidification shall be dis-qualified.witnaut at least 24 hours of cure. 8.2.22 VERIFY the acceptance cr la (Section 10.0) has been met, sign and date Attachment
.e 8.2.23 WhentheAccept(p iteria has caen met per Section 10.0, CALCULATEth{(grotredcuantitlesofcementandadditivesustr; alinert[Aapplicableforthi' waste type (as determined by Radwaste Operations Engineerit,) and the Solidification Calcula-tion Sheet for Bead Resin (At'.achment 10).
NOTE: Tne liner shall be solidified using OP 1104-232, Pr inia ry Resin and Precoat Processing - Hittman. 9.0 ALTERNATE TEST SOLIDIFICATION PROGRAMS NOTE: The PCP Test Solidification presented in this procedure should cover the majoritj of the waste processing require _ ments of TM!_1. In the event a different waste stream requires processing or a w?'te stream covered by this procedure but not having the appropriate waste form or liner type, a P^P Test Solidification can be performed using a current procedure provided by Westinghouse - Hittaar. l 21.0 1372:
Nuslear ry.i "ua'r Or,erating Procedure 1104 281 Title i Revision No. Haste Solidification Process Control Program 9 _ 9.1 Prerequisites 9.1.1 A procedure is available for the particular waste stream to be processed. 9.1.2 _This procedure has been verified current by the Radwaste Oos. Fanager or his designee and will be reviewed by the Radwaste Engineer prior to its 'Jse. 9.1.3 The sample required by this procedure has been obtained and app'icable chemistry parameters analyzed for by Plant Chemistry. 9.1.4 The Ops Quality Assurance Group has been contacted to inform them of the pending Test Solidification to see if they care to witness the test. 00A Monitor Contacted Name / Date / Time ! 9.1.5 Balance calibration data has been included on Attachment 11. 9.1.6 Attachment 11 has bee ed. 9.2 Procedure l 9.2.1 Performed t licable portions of the Westinghouse - Hit:ca-procedure. 10.0 ACCEPTANCE CRITERIA 10.1 Solidification Acceptability 10.1.1 The sample solidification is considered acceptable if there is not visual or crainable free water. 10.1.2 The samnie solidification is considered acceptable if it resi:* . penetration. I 22.0 '37:: ) l _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ .
. . (
( lENualear m .1 Operating Procedure
" umber Tit,' 1104 281 ]
i Revision No. l i Waste Solidification Process Control Program 9 1
~ '
~~~~~s5iiI-~~5$ica~i~e'?a~~nina~ tion shaii~be~~~~~istancetoTtni or res pound load applied to the surface of the solidified product usirg a 1/2 inch diameter metal rod. The solidification shall be considered acceptable if the metal probe cannot i break the surface and penetrate to the sample core. Normal denting of the surface is acceptable.
The rod tolerances are as follows:
+1 lb Weight 10 lbs -0 lb
+0 in Diameter 1/2 inch _1/4 in 10.2 Solidification Unacceptability 10.2.1 If the waste fails any of the criteria set forth in Section 10.1 the solidification will be termed unacceptable and a new set of solidificat kn parameters will need to be established under the procedures in Sectic, 10.3.
10.2.2 If the test solidification l> unacceptable then the same test procedure must be followed each subsequent batch of the same type of waste until thr secutive test samples are solici_ fled. 10.3 Alternate Solidific eters i 10.3.1 If a test ple for Class A unstable waste fails to provide acceptable solidification of waste the following procedures should be followed.
- a. Mix 454.5 gms of cement and 45.5 gms of ASMS with 400 mis of water to ensure that the probism is not a bad batch of cement.
- b. Add additional 50 wt.7. NaOH to raise the pH above 8 but !
less than 9.2 for borated wastes. C. If the waste (other than %ste oil) is only partially f solidified, use lower waste to ce"ent and Metso ratios. l l Using the recommended qui.ncities of cement and Metso Bcadi, reduce the waste sample to 373 ml and continue recuci ; :ne sample volume by 25 ml, until the accettaollity criteria of Section 10.1 are met. I i 23.0 127;c I L i
l Nuclear mr i "umb'r Operating Procedure 1104-281 Title Revision No. Waste Solidification Process Control Program l 9
- d. If the waste oil mixture is only part1&lly solidified try using lower waste to cement ratios. Reduce the quantity of waste by 25 ml. and the emulsifier by I ml., (This will result in a slightly higher concentration of emulsifier in the waste) and proceed with the test solidification.
Continue with similar reductions until a satisfactory product is achieved. 10.3.2 For Class A stable, Class B and C waste test samples that fail to solidify, Contact Radwaste Operations Engineering for resolu-tion. ja 24.0 13 % :
9
- NuSlear THI_i Operatina Procedure 1104-281 1 Title Revision No.
Waste Solidification Process Control Program 8 y ATTACHMENT I Page 1 of 4 l CLASS A UNSTABLE AND STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET FOR 4 TO 10 WT% BORIC ACID 4 Chemistry Parameters Balance Cal, Info. Liner No.: Sample Date CMTE No. Sample No.: Boron ppm Serial No. Date: > Total Solids ppm Cal. Due Date Waste Class pH Total Act. mCl/cc I. PRECONDITIONING: Weight Percent of Boric Acid (in decimal form): Boron (opm) x .01 ( ) x .01 1748 - 1748 - (1) Weight of Untreated Sample: g gms (2) Volume of Untreated Sample: mis (3) Weight oi 50% NaOH Added to Ad gms (4) within range per Section 4.2. pH of treated sample: Welght of Anti-foam Added: gms (5)
% 0111 : %
Weight of Emultifier Added: gms (6;
)
i Volume of treated ample: mis (7) Weight of treated sample: (2) + (4) + (5) + (6) - ( ) + ( ) +( )+( ) - gmt (8) { I i El-1 1372:. l
Nuslear TxI-i Operatina Procedure 1104-28I Title Revision No.
~
Waste Solidification Process Control Program 8 ATTACHMENT 1 (Cont'd) Pagt 2 of 4 II. DETERMINATE 0l.' 0F PERCENT SOLIDS OF SAMPLE: Weight of Boric Acid in Untreated Sample: l' (2) x (1) -( ) x ( ) - gms (9) Weight of 50% NaOH: (4) x 0.5 - ( ) x 0.5 - gms (10) Weight of Solids in Treated Sample: (5) + (6) + (9) + (10) = ( )+( )+( ) + ( ) -
% gms (11)
Percent Solids in Treated Sample: 100 x (11) + ['t)) . , 100 x ( ) + [( }). % (12) III. DETERMINATION OF WATER IN SAMPLE FOR SOLIDIFICATION: Volume of Treated Sample to be Solidified: ml (13) Weight of Treated Sample to be Solidified: gms (14) Weight of Water in Sample Contributed by Waste:
~
)
- 12) x (14) x [1 - (1)] - {
,( 8) ,
1 L)x( ) x [1 - ( )) = gms (15)
. () .
Weight of Hater in Sample Contributed By 50% NaOH: j 1 (4) x (14) x 0.5 = l (8) , ( ) x ( ) x 0.5 - ( ) gms (16) Total Weight of Water in Sample: , (15) + (16) - ( ) +( ) . gms (17) El-2 137 : l
.__________________-_______D
, . l Nuclear THI-i Operatino Procedure 1104-28I Title Revision No.
Haste Solidification Process Control Program 8 ATTACHMENT 1 (Cont'd) Page 3 of 4 IV. DETERMINATION OF QUANTITY OF PORTLAND TYPE I CEMENT AND METSO BEADS TO USE FOR SAMPLE SOLIDIFICATION: Using figure I find the % rAlds in sample (12), and DETERMINE the Hater /Cemen'. Ratio: (18) Weight of Cemer.t to Use: (17) - ( ) - (18) ( ) gms (19) Weight of Metso Beads to use: (19) x 0.15 - ( ) x 0.15 - gms (20) l Test Solidification Performed By: a Name T34te Time 1 V. SAMPLE INSPECTION l Sample cured for: \ Hours Cured Temp. Cured
~
Verified By Date Sample contains "No Free Liquid": Verified By Date Sample " Resists Penetration": Verified By Date El-3 137 c
Nu21 ear m _i
""*"r Operating Procedure 1104-28I Title Revision No.
Haste Solidification Process Control Pro 4 ram 9 ATTACHMENT I (Cont'd) Page 4 of 4 Additional batches solidified based on this sample solidification: l 1 Liner Waste Liner Waste Liner Haste .f No. Vol. Date No. Vol. Date No. Vol. Date
- 2. S. 8.
- 3. 6. 9. .
- 4. 7. 10.
FOOTNOTES:
- 1. Maximum allowable oil content for stable waste is 17. by volume. I VI. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT Test Sample Meets Acceptanta Criteria (Section 10) Name / Date / Time Test Solidification Data Sheets (Calculations) Reviewed a
/ Date / Time
/
l k El-4 137 : l _ _ ___ _____________
f' Nuclear THI i Operatino Procedure
""*b'r 1104-28I Title .
Revision No. Waste Solidification Process Control Program 8 ATTACHMENT 2 Page 1 of 3 SOLIDIFICATION CALCULATION SHEET FOR 4 TO 10 WT1. BORIC ACID Liner Type to be used j I. Volume of Untreated Waste to Add to Liner 1,3: (3) Max. Treated Haste Vol. (7) x from Solidification Data Tables - ( )
~( ) x _
ft3 (21) II. Volume of Additives to Add to Liner: NaOH: (4) x 4.86 x (21) - ( ) x 4.86 x( )- gals (22) (3) () Anti-foam: (5) x 7.48_ x (21) - ( ) x 7.48 x( )- gals (23) (3) () Emulsifier: (6) x 7.48 x (21) - ( ) x 7.48 x( )= gals (24) (3) () III. Volume of Treated Waste to be SolidifiedI : (22) + (23) + (24) ( )+ ( )+( ) (21) + ?.48 - ( )+ 7.48 - ft3 (25) 9b IV. Cement Quantity for Full Scale Solidificat (19) x 62.4 x (25) - ( ) x 62.4 x lbs (26) (13) ( ) (26) + 94 - ( ) + 94 - bags 2 V. ASMS Quantity for Full Scale Solidification: (26) x .15 - ( ) x .15 - lbs (27) (27) + 100 - ( ) + 100 - bags 2 E2-1 1372c
ENuziear TxI_i Operating Procedure 1104_28I = Title Revision No. WasteSolidifica'tibProcessControlProgram 9 ATTACHMENT 2 Page 2 of 3 VI. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT SOLIDIFICATION CALCULATION SHEETS REVIEHED Name / Date / Time FOOTNOTES I The volume of treated waste to be solidified in a single liner cannot exceed the maximum treated waste volume listed on the attached Solidification Data Tables. 2 Round off up to the nearest whole bag. 3 Use the actual waste volume added to the liner in Steps / Equations 22, 23 and 24 if the waste volume added to the liner is less than the value obtained in Step / Equation 21. VII. DETERMINATION OF THE QUANTITY OF CEMENT ADDED TO WASTE: Quantity of Cement Added to Hopper: lbs (28) Quantity of Cement Left in Hopper: lbs (29) Quantity of Cement Added per ft.3 Waste: (28) _ (29) = ( )-( )= lbg cement / (25) ( ) \ fta waste NOTE: Minimum Quantity of Cement Allowable for 4 to 10 Ht. % Boric Acid Class A Unstable Haste is 62 lbs./ft.3 For Stable waste solidification all the cement must be added to the liner. Quantity'of Cement Added Heets Minimum Requirements for unstable waste forms: t Verified By Date The recommended minimum treated waste volume and minimum solidified waste volume meet the requirements of the Solidification Data Tables for STABLE waste forms. Verified By Date l E2-2 1372c l 4 i
g _ l Nuzioar THI_i Operating Procedure 1104-281 Title .. Revision No. Haste So11d1Fication Process Control Program 7 ATTACHMENT 2 (Cont'd) Page 3 of 3 SOLIDIFICATION DATA TABLES I FOR 4 TO 10 NT% BORIC ACIO HN-100 HN-100 LVM. Series 3 . Series 31 l l Usable Liner ! Vol. (cu. ft.) 141.1 157.5 Max. Treated Waste Vol. (cu. ft.) 104.4 116.6 Max. Solidified Waste 141.1 157.5 Vol. (cu. ft.) , Recommended Min. I Treated Waste Vol. 98.1 103.8 (cu. ft)2 k l Min. Solidified Waste l Vol. (cu. ft)2 132.6 140.2 Max. Rad. Level 12 12 R/hr Contact
- 1. For less than A2 quantities of LSA waste. For greater than A2 quantities of LSA waste, the maximum treatad waste volume is 11'.4 cu. ft. due to weight l limitations. I
- 2. These minimums are required when shipping to Barnwell, to comply with the 15%
maximum void space criteria for liners containing solidified stable waste forms. I l J l i E2-3 1372c . )
Nuclear 1sI-i
"""*'r
("serating Procedure 1104-281 Title ~ Revision No. Weste Solidification Process Control Procram 8 ATTACHMENT 3 Page 1 of 4 CLASS A UNSTABLE AND STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET > 10 TO 20 WT% BORIC ACID Chemistry Parameters Balance Cal. Info._ Liner No.: Sample Date CMTE No. Sample No.: Boron ppm Sertal No.__ Date: Total Solids ppm Cal. Due Date Waste Class pH Total Act. pC1/cc I. PRECONDITIONING Weight Percent of Boric Acid (in decimal form): Boron (ppm) x .01 ( ) x .01 - (1) 1748 - 1748 Weight of Untreated Sample: gms (2) Volume of Untreated S&mple: mis (3) Weight of 50% NaOH Added to Adjust pH per Section 5.2.4: gms (4) pH of treated sample: Weight of Anti-foam Added: gms (5)
% Oill : %
Weight of Emulsifier Added: gms (6) Volume of treated sample: mis (7) Weight of treated sample: (2) + (4) + (S) + (6) - ( )+( )+( ) +( )- gms (8) i E3-1 137::
Nuslear TsI-i Operating Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 8 ATTACHMENT 3 (Cont'd) Page 2 of 4 II. DETERMINATION OF PERCENT SOLIDS OF SAMPLE Weight of Boric Acid in Untreated Sample (2) x (1) .( ) x ( ) - gms (9) Weight of 50% NaOH: (4) x 0.5 . ( ) x 0.5 gms (10) Weight of Solids in Treated Sample: (5) + (6) + (9) + (10) . l ( ).( ).( >.( Percent Solids in Treated Sample:
)-
gg8 gms (11) 100 x (11) + [(8)] - 100 x ( ) + [( )) - % (12) l III. DETERMINATION OF WATER IN SAMPLE FOR SOLIDIFICATION: Volume of Treated Sample to be Solidified: ml (13) e i Weight of Treated Sample to be Solidified: gms (14) Weight of Water in Sample Contributed by Waste: I2) x (14) x [1 - (1)] -
,( 8) ,
h( ) x( ) x [1 - ( )) - gms (15) { i Height of Water in Sample Contributed by 50% NaOH:
~ ~
(4) x (14ix0.5 - ( ) x ( i x 0.5 - gms (16) h (8) , ( ) Total Height of Water in Sample: (15) + (16) - ( )+ ( )- gms -(17) E3-2 137 c
Nuslear THI-i Operating Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 8 ATTACHMENT 3 (Cont'd) Page 3 of 4 IV. DETERMINATION OF QUANTITY OF PORTLAND TYPE I CEMENT AND ME.TSO BEADS TO USE FOR SAMPLE SOLIDIFICATION: Using Figure I, find the % solids in sample (12), and DETERMINE the Hater / Cement Rativ: (18) Weight of Cement to Use: (17) ( ) (18) = ( ) - gms (19) Weight of Metso Beads to use: (19) x 0.15 - ( ) x 0.15 - gms (20) Test Solidification Performed By: Name AN
$ "' Time tf_
V. SAMPLE INSPECTION W Sample cured for: Hours Cured Temp. Cured Verified By Date Sample contains "No Free Liquid": Verifle. By Date l Sample " Resists Penetration": Verified By Date II E3-3 137::
Nuslear TM1.i
- b'r Operatina Procedure 1104-28I Title Revision No.
Waste Solidtftcation Process Control Program 9 ATTACHMENT 3 (Cont'd) Page 4 of 4 Additional batches solidified based on this sample solidification: Liner Waste Liner Waste Liner Waste l No. Vol. Date No. Vol. Date No. Vol. Date
- 2. 5. 8.
- 3. 6. 9.
- 4. 7. 10.
FOOTNOTES:
- 1. Maximum allowable ott content for Stable Waste is 17. by volume.
IV. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT Test Sample Meets Acceptance Criteria (Section 10) Name / Date / Time Test Solidification Data Sheets (Calculations) Reviewed Name / Date / Time _
\
E3-4 1372c L____________________________________________.___________
g, gp Number Operatino Procedure 1104-28I Title Revision No. Haste Solidification Procet Control Program 8 ATTACHMENT 4 Page 1 of 3 SOLIDIFICATION CALCULATION SHEET FOR > 10 TO 20 Wi% BORIC ACID Liner type to be used I. Volume of Untreated Waste to Add to Linerl 3: (3) Max. Treated Waste Vol. (7) x from Solidification Data Tables - ( ) ( ) x - ft3 (21) II. Volume of Additives to Add to Liner: g NaOH: (4) x 4.86 x (21) = ( ) x 4.86 x( )- gals (22) (3) ( ) Anti-foam: (5) x 7.48 x (21) = ( )a d x( )= gals (23) Emulsifier: (6) x .48 x 7 48 x( )- gals (24) III. Volume of Treated Waste to be SolidifiedI : (22) + (23) + (24) ( )+( )+ ( ) (21) + 7.48 - ( )+ 7.48 ft3
= (25)
IV. Cement Quantity for Full Scale Solidification: (19) x 62.4 x (25) - ( ) x 62.4 x ( )- Ibs (26) (13) ( ) 11 (26) + 94 - ( ) 94 - bags 2 V. ASMS Quantity for Full Scale Solidification: (26) x .15 - ( ) x .15 - lbs (27) i I (27) + 100 - ( ) 100 - bags 2 s 1 EC-1 137:: l I
Nuslear ,,_, Numeer Operating Procedure 1104_28I Title Revision No. Waste Solidification Process Control Program 9 ATTACHMENT 4 Page 2 of 3 SOLIDIFICATION CALCULATION SHEET FOR > 10 TO 20 WT% BORIC ACID VI. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT SOLIDIFICATION CALCULATION SHEETS REVIEWED Name / Date / Time FOOTNOTES I The volume of treated waste to be solidified in a single liner cannot exceed the maximum treated waste volume listed on the attached Solidification Data Tables. 2 Round off up tc the nearest whole bag. 3 Use the actual waste volume added to the liner in steps / equations 22, 23 and 24 if the/ Equation Step waste volume
- 21. added to the liner is less than the value obtained in VII. DETERMINATION OF THE QUANTITY OF CEMENT ADDED TO WASTE:
Quantity of Cement Added to Hopper: k Ibs 1 (28) Quantity of Cement left in Hop ibs (29) Quantity of Cement Added per f . Waste: (28) _ (29) = _( )-( ) = lbs cement / (25) ( ) ft3 waste _ _ _ NOTE: Minimum Quantity of Cement Allowable for >10 to 20 Ht. 1 Boric Acid Class A Unstable Waste is 60 lbs./ft.3 For STABLE waste solidif'ications all the cement must be added to the liner. 1 Quantity of Cement Added Meets the Minimum Requirements for unstable waste forms: l I 1 Verified By Date ; l l The recommended minimum tteated waste volume and minimum solidified was i meet the requirements of the Solidification Data Tables for STABLE waste forms. Verified By Date E4_2 1372:
Nuslear TMI_i Operatino Procedure 1104-28I Title Revision No.
. Waste Solidification Process Control Program 7 ATTACHMENT 4 (Cont ;) Page 3 of 3 SOLIDIFICATION DATA TABLES FOR > 10 TO 20 WT1 BORIC ACID HN-100 HN-100 LVM Series 3 Series 3I Usable Liner l Vol. (cu. ft.) 141.1 157.5 1
Max. Treated Haste Vol. (cu. ft.) 101.3 113.1 Max. Solidified Waste 141.1 157.5 Vol. (cu. ft.) Recommended Min. Treated Haste Vol. 95.2 100.7 (cu. ft)2 Min. Solidified Waste Vol. (cu. ft)2 132.6 140.2 Max. Rad. Level 12 12 R/hr Contact I- Fer less than A2 quantities of LSA waste. For greater than A2 quantities of i LSA waste, the maximum treated waste volume is 106 cu. ft. due to weight I limitations. l 2-These minimums are required when shipping to Barnwell, to comply with the 157. maximum void space criteria for liners containing solidified stable waste forms.
.c f h(*?h 4$5N E4-3 1372:
1
Nuslear 1,1 ,
" umber Operating Procedure 1104-28I Title Revision No.
Haste Solidificaticq Process Control Procram 9 ATTACHMENT 5 Page 1 of 2 CLASS A UNSTABLE AND STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET FOR WASTE OIL Chem. Parameters (Conc.~ Waste) Balance Cal. Info Liner No.: j Sample Date CMTE No.: Sample No.: Boron ppm Serial No.: Date: Total Solids opm Cal. Due Date: Waste Class: pH Total Act pCi/cc I. SAMPLE PREPARATION h Volume of 011 to be Sol 1difit'Qi}$O ei hi mis (1) Volume of Concentrated Waste added to the oll: mis (2) Total Volume of Sample: mis 1 7. Oil by Volune: 1 (1) x 100 - ( ) x 100 - 7. (3) (1) + (2) l ( )+( )
)
Weight of 50 wt7. NaOH added to sample to raise pH > 5 gms (4) Quantity of Emulsifier to Add to Sample: mis (5) Quantity of Ant) Foam Added to Sample: $ mis (6) i Quantity of Portland Type 1 Cement Added to Sample: gms (7) ; i Quantity of Anhydrous Sodium Metasilicate Added I to Sample: gms (8) Test Solidification Perfor:ned By: Name Date Time - 4 E5-1 1372.
Nualear 1MI_i Operating Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 9 ATTACHMENT 5 (Cont'd) Page 2 of 2 II. SAMPLE INSPECTION Sample cured for: Hours Cured Temp. Cured Verified By Date Sample contains "No Free Liquid": Verified By Date Sample " Resists Penetration" y Verified By Date l Additional batcFes solidified cased on this sample solidification: Liner Waste Liner Waste Liner Waste No. Vol. Date No. Vol. Date No. Vol. Date i
- 2. 5, 8.
3, 6. 9.
- 4. 7. 10.
III. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT Test Sample Meets Acceptance Criteria (Section 10) Name / Date / Time Test Solidification Data Sheets (Calculations) Reviewed Name / Date / Time i ES-2 1372c
Nualear "" THI-i Operating Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 8 ATTACHMENT 6 Page 1 of 3 SOLIDIFICATION CALCULATION SHEET FOR WASTE OIL Liner type to be used I. PARAMETERS FOR FULL SCALE SOLIDIFICATION Emulsifier: (5) x 7.48 + (1) - ( ) x 7.48 + ( ) - gal / (9) ' ft3 Anti-foam 1 1 l (6) x 7.48 x (1) + (2) -( ) x 7.48 x ( )+ ( ) gal / (10) ft3 Cement: (7) x 62.43 x (1) (2) - h .43 x ( ) ( ) Ibs/ (11) . ft3 ASMS: 1 1 (8) x 62.43 x (1) + (2) - ( ) x 62.43 x ( ) +( ) lbs/ (12) ft3 1 II. ' QUANTITIES TO BE ADDED FOR FULL SCALE SOLIDIf! CATION - Volume of untreated waste to add to liner (Max Treated Waste Vol from Solidification Data Tables):3 (13) Concentrated Waste to be added: 60% x (13) x 7.48 - 0.60 x ( ) x 7.48 - gals (14) Waste 011 to be added: 40% x (13) - 0.40 x ( )- ft3 (15) f 40% x (13) x 7.48 - 0.40 x ( ) x 7.48 - _ gals > E6-1 137::
Nuslear ,,_, Numeer 4 Operatino Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 9 ATTACWENT 6 (Cont'd) Page 2 of 3 Emulsifier to be added: (15) x (9) - ( ) x( )- gals Anti-foam to be Added: (13) x (10) - ( ) x( )- gals ASMS to be added: (13) x (12) - ( ) x( ) - Ibs (46) (16) + 100 - ( ) + 100 - bagsl Volume of cement to add to liner: (13) x (11) - ( ) x( ) - lbs (17) ( l' 7 ) + 94 - ( ) + 94 - bagsl FOOTNOTES: TEN ! I Round rJf up to the nearest whole bag. 2 Reduce the quantity of total waste in the liner by I ft3 for every 10 gallons I of anti-foam added to the liner. No adjustment is necessary for the first 10 l gallons. 3 Use actual waste volume added to the liner in step / equations used in Section II I if waste Step volume
/ Equation 13. added to the liner is less than the value obtained in III. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT SOLIDIFICATION CALCULATION SHEETS REVIEWED Name / Date / Time i
E6-2 1372c 1 !
{ gggy Number Operating Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 7 ATTACHMENT 6 (Cont'd) Page 3 of 3 SOLIDIFICATION DATA TABLES FOR WASTE OIL HN-100 HN-100 Series 3 LVM Usable Liner Volume, (ft3 ) 141.1 157.5 Max. Haste Volume j (oil and conc. waste), ft3 93.7 104.6 Max. Solidified Volume, ft3 141.1 157.5 Maximum Rad Level R/hr Contact 12 12 (\ I i l s l E6-3 137:c I i
Nu: lear ""**" Ts!-i Operating Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 8 ATTACHHENT 7 Page 1 of 2 CLASS A STABLE, CLASS 3 AND C TEST SOLIDIFICATION DATA SHEET FOR USED PREC0AT Balance Cal. Info. Chemistry Parameters Liner No.: CMTE No, pH Sample No.: Serial No. Gamma Scan mC1/ml Date: Cal. Due Date % Oil % Waste Class I. SAMPLE PREPARATION Weight of Dewatered Powered Resin gms (1) Volume of Dewatered Powered Resin ml (2) 1 j Weight of Water Added to Powdered Resin: gms (3) Total of Volume of Powered Res, 4 Ih) ml (4) Quantity of Anti-foam Agent ded to Sample: gms (5) Quantity of oil in Sample *
. (fd 0;antity of Emulsifying Agent Added to Sample: gms (7) l Initial pH of Sample: (8)
II. SOLIDIFICATION Quantity of Ca(OH)2 necessary to raise pH > 11.5: gms (9) Final pH of Sample: (10) Quantity of Portland Cement Added to Sample gms (11) Final Sample Volume: mis (12) Test Solidification Performed By: l l Name Date Time , l E7-1 1372:
ENuslear 1M1 3 Operating Procedure
"*r 1104-28I Title Revision No.
Waste Solldtfication Process Control Program 9 ATTACHMENT 7 (Cont'd) Page 2 of 2 CLASS A STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET FOR USED PREC0AT III. SAMPLE INSPECTION Sample cured for: Hours Cured Temp. Cured Verified By Date Sample contains "No Free Liquid"* Verified By Date Sample " Resists Penetration"- Verified By Date 1 Acditional batches solidified based on this sample solidification: Liner Waste Liner Haste Liner Waste No. Vol, Date No. Vol. Date No. Vol. Date
- 2. 5. 8.
- 3. 6. 9. I
- 4. 7. 10.
IV. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT l Test Sample Meets Acceptance Criteria (Section 10) Name
/ Date / Time Test Solidification Data Sheets (Calculations) Reviewed a Name / Date / Time i E7-2 1372:
l
8 Nuslear TsI_i Operating Procedure 4 1104-28I i Title Revision No. 4 Waste Solidification Process Control Program 8 ATTACHMENT P Page 1 of 3 SOLIDIFICATION CALCULATION SHEET FOR USED PREC0AT Liner Type to be used I. PARAMETERS FOR FULL SCALE SOLIDIFICATION. f Quantity of Water: [ p (3) x 7.48 - ( ) x 7.48 gal / (13) (2) ( ) ft3 of waste ' Quantity of Anti-Foam Agent: ' (5) x 7.48 - ( ) x 7.48 gal / (14) -l (2) ( ) N ft3 of waste Quantity of Emeisifier: j (7) x 7.48 - ( ) x 7.48 gal / (15) (2) ( ) ft3 of waste Quantity of Ca(OH)p: (9) x 62.43 - _( ) x 62.43 ,, Ibs/ (16) l (2) ( ) ft3 of waste Quantity of Portland Type 1 Cement: l (11) x 62.43 = ( ) x 62.43 Ibs/ (17) I (2) ( ) ft3 of waste II. QUANTITIES TO BE ADDED FOR FULL SCALE SOLIDIFICATION - Volume of Dewatered Powdered Resin to be Solidified: ft3 (18) Quantity of Water: 'I (18) x (13) = ( )x( )= gal (19) Quantity of Anti-Foam Agent: ! (18) x (14) = ( ) x( )- gal (20) l i Quantity of Emulsifier: (l (18) x (15) -( ) x( ) - gal (21) i E8-1 1372: ! i
lb lJ[3 l0kOII" Number THI-1 Operatino Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 9 ATTACHMENT 8 (Cont'd) Page 2 of 3 SOLIDIFICATION CALCULATION SHEET FOR USED PREC0AT Quantity of Ca(OH)2: (18) x (16) - ( ) x( )= lbs (22) (22) + (100) - ( ) +( ) - bags 2 Quantity of Portland Type Cement: (181 x (17) = ( ) x( ) = lbs (23) (23) + (94) -( ) +( ) - bags 2 I The volume of waste, to be solidified in a liner cannot exceed the maximum settledfor Table and treated used waste volume listed on the Class B Waste Solidification Data precoat. 2 Round up to the nearest whole bag. III. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT SOLIDIFICATION CALCULATION SHEETS REVIEWED ,se@h lWRVbe / Date / Time E8-2 1372:
Nuslear TMI-i Operatino Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 8 ATTACHMENT 8 (Cont'd) Page 3 of 3 SOLIDIFICATION DATA TABLE FOR USED PREC0AT . HN-600 MUS HN-200 MU Usable Liner Volume, ft3 59.3 59.4 Max. Solidified Waste Vol. ft3 59.3 59.4 Max. Dewatered Waste Vol., ft3 33.3 33.3
- Min. Haste Vol. ft3 32.9 32.0 Min. Solidified Waste Vol, ft3 58.6 57.0 Max. Radiation Level R/hr Contact of Liner 100 800 1
E8-3 1372c
Nuslear TsI-i Operatino Procedure 1104-28I Title Revision No. Waste Solidification Process Control Program 8 ATTACHMENT 9 Page 1 of 2 CLASS A STABLE, CLASS B AND C TEST SOLIDIFICATION DATA SHEET FOR BEAD RESIN Balance Cal. Info. Chemistry Parameters Liner No.: CMTE No. pH Sample No.: Serial No. Gamma Scan mC1/ml Date: l Cal. Due Date % Oil % Waste Class: I. SAMPLE PREPARATION I Sample Height: gms (1) Sample Volume: ml (2) Height of EC-3: , gms (3) Height of water: gms (4) l Height of Anti-foaming agent added to sample: gms (5) Quantity of oil in sample: % (6) Height of Emulsifier added t gms (7) Initial pH of sample: (8) II. SAMPLE SOLIDIFICATION Height of Ca(OH)2 added to sample to raise the pH > 11.S:
, gms (9)
Final pH of sample: (10) Height of Portland Type 1 cement added to sample: gms (11) Final Sample Volume: (12) _ ml Test Solidification Performed By: I Name Date Time E9-1 1372 1
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l l
Nu21 ear 1sI_i
""*b'r Operating Procedure 1104-28I Title Revision No.
Haste Solidification Process Control Program 9 ATTACHMENT 9 (Cont'd) Page 2 of 2 CLASS A STABLE, CLASS 8 AND C TEST SOLIDIFICATION DATA SHEET FOR BEAD RESIN III. SAMPLE INSPECTION Sample cured for: Hours Cured Temp. Cured Verified By Date Sample contains "No Free Liquid": Verified By , Date Sample " Resists Penetration": Verified By Date Additional batches solidified based h\ Kple solidification: Liner Waste L Waste Liner Haste No. Vol. Date No. Vol. Date No. Vol. Date 1 l 2. 5. 8.
- 3. 6. 9.
- 4. 7. 10.
l IV. INDEPENDENT VERIFICATION BY GPUN MANAGEMENT Test Sample Meets Acceptance Criteria (Section 10) Name / Date / Time ( Test Solidification Data ' Sheets (Calculations) Reviewed Name / Date / Time < E9-2 1372c
Nualear ""**" TsI-i Operatino Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 8 ATTACHMENT 10 Page 1 of 3 i SOLIDIFICATION CALCULATION SHEET FOR BEAD RESIN Liner Type to be used: II. PARAMETERS FOR FULL SCALE SOLIDIFICATION Quantity of EC-3: j (3) x 6.3 - ( ) x 6.3 o gal / (13) (2) ( ) ft3 of waste 1 Quantity of Water: (4) x 7.48 - ( ) x 7.48 gal / (14) (2) ( ) ft3 of waste Quantity of Anti-Foam Agent: q L (5) x 7.48 = ( ) x 7.48 gall (15) (2) ( ) ft3 of waste Quantity of Emulsifier: 1 (7) x 7.48 - ( ) x 7.48 gal / (16) (2) ( ) ft3 of waste 3 Quantity of Calcium Hydroxide Ca(OH)2: (9) x 62.43 - ( ) x 62.43 Ibs/ (17) (2) ( ) ft3 of waste Quantity of Portland Type 1 Cement: (11) x 62.43 - ( ) x 62.43 lbs/ (18) (2) ( ) ft3 of waste II. QUANTITIES TO BE ADDED FOR FULL SCALE SOLIDIFICATION Waste Volume of to be Solidifiedl .3: ft3 (19) Quantity of EC-3: j (19) x (13) =( ) x( )- gal -(20) E10-1 1372:
Nualear. Nu m e THI-l Operattna Procedure 1104-28I Title Revision No. Haste Solidification Process Control Program 9 ATTACHMENT 10 (Cont'd) Page 2 of 3 i SOLIDIFICATION CALCULATION SHEET FOR BEAD RESIN Quantity of Water: l (19) x (14) - ( )x( )- gal (21) l l Quantity of Anti-Foam Agent: (19) x (15) - ( ) x( )- gal (22) Quantity of Emulsifier: (19) x (16) - ( ) x( )- gal (23) Quantity of Calcium Hydroxide Ca(OH)2 (19) x (17) - ( ) x( ) - lbs (24) (24) + (100) =( )+ 100 '- bags 2 Quantity of Portland Type Ce (19) x (18) - ( ) x( )- Ibs (25) (25) + (94) =( ) + 94 = bags 2 i I l The volume of dewatered bead resin to be solidified cannot exceed the maximum treated waste volume listed on the Class A Stable, Class B and C Test Solidification Data Sheet for Bead Resin. 2 Round up to the nearest whole bag. 3 Reduce the quantity of waste in liner by 1 ft3 for every 10 gallons of anti-foam agent plus emulsifier added to liner. III. INDEPENDENT VERIFICATION Bf GPUN MANAGEMENT SOLIDIFICATION j CALCULATION SHEETS REVIEWED Name / Date / Time ll l, E10-2 1372: { 1 l
4 4 , . Nuslear ""***' THI-i
. Operating Procedure 1104-28I Title Revision No.
Haste Solidification Process Control Program 8 ATTACHMENT 10 (Cont'd) Page 3 of 3 SOLIDIFICATION DATA TABLES FOR BEAD RESIN HN-100 HN-600 HN-600 LVMU HN-200 HU LVMVGS Usable Liner 148.8 59.4 64.0 61.7 Volume (cu. ft.) Max. Dewatered 120.0 47.9 51.6 49.8 Waste Volume (cu. ft.) l Max. Solidified 148.8 59.4 64.1 61.7
- Waste Volume (cu. ft.)
1 ! Max. Rad. Level 12 800 100 100 R/hr Contact Min. Recommended (l) Haste Vol (ft3 ) 106.9 N'- 47.3 Min Solidified (I) 132.6 0 - 58.6 (1) Grout will have to be added to the HN600 HU to increase the solidified waste volume to meet the 15% maximum void space criteria for shipment to Barnwell. l l I l ~ I E10-3 1372: ! l .)
r 1 1 e J A Nuslear TWI-i Operating Procedure
""*'r 1104-28I Title Revision No.
Waste Solidification Process Control Program 7 ATTACHMENT 11 Page 1 of I r TEST SOLIDIFICATION USING WESTINGHOUSE - HITTMAN PROCEDURE Waste to be Processed: Westinghouse - Hittman Procedure No. Procedure - Title l Current Revision Justification to use this alternate test procedure: , A Liner Type Waste Class Balance Cal Info. 1 I l CMTE No. Serial No. Cal. Due Date Approved By l Eng. Review By NOTE: Form should be attached to valid Westinghouse - Hittman Procedure used for the Test Solidification I E11-1 1372c j
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