Text

Gamma Spectroscopy Analysis Rept
	ML20093N490
Person / Time
Site:	Fermi
Issue date:	03/03/1994
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20093M863	List: ML20093N044; ML20093N463; ML20093N478; ML20093N490;
References
	FOIA-IN95-349 NUDOCS 9510270257
	Download: ML20093N490 (153)
	v • d • e

_

o faxtm's********ww*******,.*******************************,************,******.,

DCTROIT EDISON FERMI-E POWER PLANT g-MAR-1994 17:49:07.^^

0000***************************************************w.******,,,******,*,***

l RADIATION PROTECTION DEPARTMENT l

GAMMA SPECTROSCOPY ANALYSIS REPORT Sample ID Number LLD2000 i

Aquistion Taee: 2-MAR-1994 17a15:40.85

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I Storace files LLD2000.cnf akh b k 1 b.sJ!-Rh REMARKS

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SIGt#tTURE REU EWE BY

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SIGN URE/DATE 9510270257 951023 PDR FOIA DEER IN95-349 PDR w, gg p,,

m g,g; g3,g

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I Page :

2

,Snaple ID : LLD2000 Acquisition date : 2-MAR-1994 17:15:40 oco**************************************************************************

Fermi 2 Radiation Protection Gamma Spectroscopy Report oco************************** Sample Parameters *****************************

Bacple ID Number: LLD2000 Scople collection start date: 2-MAR-1994 17:15:00.00 Sceple collection end date

2-MAR-1994 17:15:00.00 Type of sample 1 Liter Marine 11 Socple quantity :

1.00610E+03 al Saople geometry :

M1LL Operator BPB oco*********************** Acquisition Parameters ***************************

Detector number DET1 Acquire date :

2-MAR-1994 17:15:40.85 Proset live time 0 00:33:20.00 Elapsed live time :

0 00:33:20.00 Elcosed real time :

0 00:33:20.22 Percent dead time :

0.00 %

000***********************

Calibration Parameters *****++********************

Detector number :

DET1 Yearly cal date :

2-MAR-1994 13:47:45.33 Ksv/ channel 4.99924E-01 Zero offset:

3.26084E-01 Dcily cal date

2-MAR-1994 13: 47:45.33 oco+**********************

peak search parameters *****++******++************

Start channel :

100 End channel : 4096 Hai Dht consitivity 5.00000 Ghape sensitivity 10.00000 Msximum number of iterations to resolve multiplets : 5 occ****************** Nuclide Identification Parameters *********************

Ensegy tolcronce : 1.25000 Half life eatio a 10.00000 Abundance limit 75.00000 Library : deceaster.n1b Effioicney file : EFFD1_,m i l l Cfficiencies at Pw*k enwr gy oco*******************************+******************************************

No peaks were found 1

l e

1 rt?a Ac7tstc w 16 01

, PIG 311rN %Igid fgt,9,T_P66T-EO-RM

o Minimum Detectable Activity Report e

Bckgnd Energy MDA Nuclide Sun (kev)

(uCi/ml)

CE-7 3.

4//.59 1.6030E-07 F-18 12.

511.00 1.8086E-08 NA-C2 0.

1E74.54 1.0280E-08 NA-24 2.

1368.53 3.9984E-08

)

MG-27 W.

1814.44 8.4822E-08 CL-38 1.

1642.42 1.4582E-07 K-CD E.

1460.81 3.9424E-07 AR-41 1.

1293.64 3.1852E-08 CC-4b 4.

889.25 3.3734E-08 CR-51 4.

320.08 1.3737E-07 MN-bv' 4.

834.83 3.1193E-08 CO-56 2.

1238.25 5.1158E-08 MN-db O.

1810.69 5.5286E-08 NI-56 8.

158.38 1.0601E-08 CO-57 8.

122.06 1.2228E-08 CO-58' 3.

810.76 2.7617E-08 FE-59' 4.

1999.22 7.0800E-08 CO-60' 3.

1332.49 4.2641E-08 CU-64 2.

1345.90 3.5422E-06 NI-65 1.

1481.84 1.4694F-R7 ZN-6S" 3.

1115.52 7.1440E-08 ZN-69M 2.

438,63 1.44AAF-08 SE-75 6.

136.00 1.5968E-08 AS-76 5.

SM9.1R 5.4503E-OS BR-82 3.

776.49 3.1704E-08 BR-83 1

529.64 1.0439E-06 BR-84 6.

881.50 2.5595E-08 OR-AM 4

802.41 1.0864E-05 KR-83 3.

513.99 4.0513E-06 4

KR-05M 3.

151.18 9.7050E-09

'SR-G5 3.

513.99 1.75S1E-08 RB-06 1.

1976.63 8.7464E-07 HR-37 4.

402.58 3.6271E-08 ER-87M 3,

386.40 1.8289E-04 KR-C8 5.

196.32 4.0416E-08 RD 00 0.

1382.39 2.7901E-06 Y-B8 0.

1836.01 1.4183E-08 HR-09 2.

220.90 3.4788E-W/

RB-89 0.

1931.88 2.9351E-08 HR-93 3.

1118.69 1.W116E-05 RB-90 3.

831.69 8.6341E-07 i

RB-90M 9.

824.23 2.5027E-06 Y-90M-7.

202.51 1.2540E-08 SH-91 3.

1924.30 1.0644E-07 t

Y-91 2.

1e04.90 1.11'24E-05 Y-91M 4.

555.60 2.8921E-08 SR-92 9.

1383.94 1.3231E-08 Y-92 2.

934.46 2.0703E-07 SR-93 3.

590.28 1.0558E-07 Y-93 7.

266.90 2.0377E-07 NS-94 3.

702.63 2.2469E-08 NB-95 2.

765.79 2.0921E-08 ti'd 6SETSTS88L16 01 Sdo e NOSIG311mi=1 m v7 set w t-e '

e.

Mkndous Detectable Activity Heport (continued)

Page :

2 1SOcple ID : LLD2000 Acquisition date : 2-MAR-1994 17:15:40 Bekund Energy MDA Nuclide bus (kev)

(uCi/ml)

N3-95M 7.

235.69 5.2000E-08 ZR-95 1.

756.72 3.3124E-08 NB-97 e.

657.90 6.6749E-09 ZR-97 3.

743.36 2.5936E-08 MO-99' 4.

739.58 2.1847E-07 TC-99M 13.

140.50 1.4676E-08 IC-101 11.

306.81 4.5352E-08 RU-103 2.

497.08 1.6750E-08 TC-104 3.

357.99 2.6381E-08 RH-1C5 5.

318.90 7.3587E-08 RU-1G5 1.

724.50 3.5679E-08 RU-106 2.

621.84 1.8534E-07 CD-109 5.

88.03 3.1027E-07 AG-110M 2.

937.48 7.9751E-08 SN-113 3.

391.69 2.1542E-08 SN-117M 7.

158.56 1.1174E-08 SB-122 2.

563.93 2.3686E-08 0B-124 2.

602.71 1.6779F-RA SB-105 5.

427.89 6.2726E-08 TE-125M 11.

109. PA 4.6779E-06 TE-127 3.

417.90 1.4752E-06 TE-187M 15.

57.60 1.4055E-05 XE-127 6.

202.84 1.6086E-08 TF-1P9 5.

,459.60 3.3619E-07 TE-129M 2.

695.88 6.1272E-07 XE-129M 6.

196.56 C.14G5C 07 I-130 9.

536.09 4.7650E-09 BO-131 7.

ic3.00 3.4303E-08 I-131 7.

364.48 2.2381E-08 TE-131 3.

149.7e 1.DD65E-08 TE-131M 3.

773.67 6.8957E-08 XE-132M 8.

163.93 5.4331E-07 I-132 4

667.69 2.6633E-08 TE-13e 8.

228.16 1.5267E-WB l

BA-133 3.

302.84 6.2612E-08 CA-133M 6.

276.09

/.5820E-08 1-133 1.

529.87 1.4621E-08 TE-133M 2.

912.58 3.7846E-08 XE-133 7.

81.00 4.1586E-08 XE-133M 8.

233.22 1.3157E-07 CS-134v' 1.

604.70 1.4394E-08 I-134 0.

884.09 1.4417E-08 TE-134 6,

210.47 6.4945E-08 BA-135M 6.

268.24 8.5881E-08 I-135 1,

1260.41 9.9614E-08 XE-135 6.

249.79 1.4215E-08 XE-135M 2.

526.56 3.8615E-08 CS-136 3.

818.50 2.7496E-08 I-136 2.

1313.02 1.2286E-06 C8-137p 1.

661.65 1.7883E-08 XE-137 2.

455.49 3.0424E-07 ST'd 6SETSTS806T6 01_

Sd0 dB NOSIQ3 11N N WOW S2491 J 66] g Ut$1

4 9f *d ~10101 Minimu~ Detectable Activity Report (continued)

Page 3

'i S20ple ID : LLD2000 Acquisition date : 2-MAR-1994 17:15:4a Bekend Energy MDA Nuu11de bus (kev)

(uCi/s1)

CO-138 1.

1435.86 5.2750E-08 XE-138 3.

258.31 6.4639E-08 BA-139 0.

1420.50 4.6556E-06 CE-139 8.

165.85 1.3011E-08 C3-149 7.

1283.23 2.2773E-06 BA-140 1.

537.32 5.0645E-08 LH-140 2.

1596.49 4.1847E-08 BA-141 7.

190.22 4.0137E-08 UE-141/

5, 145.44 1.7825E-08 LA-141 1.

1354.52 1.1870E-06 BA-142 4.

255.12 1.5242E-07 LA-142 3.

641.17 4.4718E-08 CE-143 9.

293.26 3.9334E-08 CE-144' 6.

133.54 8.7563E-08 PR-144 0,

1489.15 7.3197E-06 ND-147 12.

91.10 5.6108E-MA PM-148M 3.

550.27 2.0817E-08 EU-152 9.

344.27 7.1554E-OS EU-154 2.

2004.76 1.6930E-07 EU-156 2.

64R.R9 2.6485E-07 HF-181 4

482.03 2.1913E-08 TA-182 4.

1221.42 1.6140E-07 W-137 2.

685.81 6.8759E-08 RE-188 9.

15'J. 03

7. 2546E- 00 HG-203 6.

279.19 1.7677E-08 BI-207 5.

569.67 c.4305E-08

)

TL-208 3.

583.14 2.0126E-07 DB-212 2.

238.63 1.84905-00 81-214 9.

609.31 1.1974E-07 PB-214 10.

351.9E S.2787E-08 RA-224 5,

240.98 2.9586E-07 RA-226 13.

186.21 4.2616E-07 AC-228 3.

338.32 1.0610E-07 TH C00 6.

84.37

1. 09 7 /f_--06 PA-234 8.

131.20 5.4043E-08 TH-234 23.

63.29 1.3445E-06 U-235 6.

143.76 8.6637E-08 NP-E39 7.

106.14 4.7001E-08 AM-241 9.

59.54 1.2871E-07 l

1

{

m.a mm-1, n,

w -m y==

~1 mmu 3

s C

O *** C

2 *GQO * * *O vf GO 50*0 * *

Q,.* *gspd *G* OGb*GuGG S

O*G*G*e#G

,+ 0 m n o e.a. 9 0 0

o 0 13-MAR-94 15:17:55 o**o**o******of;**

l3 o * :+ * *

m * * * * * * * *

m * *

m

m * *

m * *

n- * * * * #, * * * * * * * * * * * *

C 94-198 FERMI CST WATER SPECTRAL FILE NAME:

L941981.R3L SAMPLE DATE:

15-MAR-94 06: 40:00 SANPLE IDENTIFICATION:

L941901.R3L TYPE OF SAMPLE:

WATER DANPLE QUANTITY:

510.3v00 LNITS:

ERAN SAf1PLE GEOMETRY:

MAR 500 EFFICIENCY FILE NAME:

MAR 50093.EFF ococ**** m *************** m **+**w *+**+ m ********+********a

. ACQUIRE DATE: 13-MAR-94 14:16:55

FWr tM ( 1332 )

1.975 PRESET T1NE(LIVE):

3600. SEC

SIN 8ITIVITY:

b.000 ELAPGED REAL TIME:

3600. SEC

SHAPE PARAMETER : 10.O %

ELAPSED LIVE TIME:

3600. SEC

NBR I TEiMTICNS:

10.

% :t G k k

k

9 * * * * *

k * * * * * * * *

u * * * *

9 * + k * * * * > *

1e k 4t * + + * + * * * * * * * * +- *

DETECTOR: ADC Detector

+ LIBRARY:NUCL. LIB 2ALIB Df,TE:

02-FEB-94 11:04:12

ENERGY TOLERANCE:

1.500 KE.

KEV /CHNL:

.5012213

HALF LIFE RATIO:

8.00 OFFSET;

.7430013 KEV

ABUNDANCE LIMI?:

75. O )%

rs *

f n * * +

w * * + * * & W * + + * * *

Y k *

v-t

4

V * * * + +

e + + + + % *

4 +t + * * + + *- *

h- +

ENERG) WINDOW

.24 TO 4105.26 PK 1T ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC XER:;

FIT 1

0 244.E7 62.

313. 14.67 467.44 472 36 1.71E-02 96..

2 0

365.15 30.

65.

.72 733.00 722 13 8. CE-03 60.'

3 0

427.71 63.

73.

1.E6 664. 3';.

547 14.. :7 4 E -4.%

3 2...

4 5

600.53 63.

15.

4.20 1199.63 1192 33 2.31E-02 18.3 2,29E+00

.3 5

6C4.66 193.

20.

2.17 1207. E.5 1192 33 5.37E-02 9.5 6

0 661.55 131.

26.

1.39 1321.36 1314 15 3. 64E-C 2 1 '. 9 7

0 795.55 94.

30.

1.c2 1588.70 1383 12 2. 61E--01 14.9 S

O S10.24 50.

17.

1.36 1618.01 1614 12

1. 39E-02 25. C 9

0 034.53 59.

24.

1.T6 1666.47 1662 10 1.6OE-02 23.1 o

10 0 1114.39 35.

16.

1.09 2224.83 22:,3 13 9.69E-03 33.4

.1 0 11'72.40 287.

8.

1.65 2340.58 2331 16 7.M E-C2 6.0 12 0 1331.68 232.

O.

2.25 2658.34 2648 18 6.44E-02 6.E PEAK SEARCH COMPLETED (REV 15.2 - ND PC VERSION DEC 88/

j PULSE-PILE-UP CORRECTED DATA. CORRECTION =

1.000 UNCORR. LIVE TIME:

3600. CORRECTED LIVE TIME:

3eOO.

PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR 1

0 244.57 62.

315. 14.67 489.44 472 36 1.7$E-02 96.2 h

2 0

365.15 30.

65.

.72 730.00 722 13 8.45E-03 60.4 3

0 427.71 63.

73.

1.86 854.82 847 14 1.74E-02 32.2 g/

4 5

600.53 83.

15.

2.20 1199.63 1192 33 2.31E-02 18.3 V

5 5

604.66 193.

20.

2.17 1207.85 1192 33 5.37E-02 9.5 6

O 661.55'"

.131.

26.

1.39 1321.361314 15 3.64E-02 11.9 7

0 795.55 94.

30.

1.42 1588.70 1583 12 2.61E-02 14.9 n.

n n,n v mn 11 t

<tso s<

<t<n

<n

, nac n,

on e,

-... ~ ~

,,,, m _ _,,

2224.83 2218' ' 13 9. 69E-03 33. 4 10 0

1114.39 35.

16.

1.09 l'1 1172.40 287.

8.

1.85 2340.58 23'31 16 7.97E-02 6.3 9,12,' O 0 : 1331.68 232.

O.

2.25 2658.34 264S 10,6.44E-02

6. 8

.f*ILE-UP CORRECTION COMPLETED e

(

t 4

e d

8 1

g

~NV W "P

w ar m' -w -

r....

9 NUCL'IDE IDENTIFICATION SYSTEN (ND PC VERSION DEC'88)

QNUCLIDE'LINE HCTIVITY REPORT f; AGE 1

i ELAPEED LIVE TIME:

3600. (PILE-UP CORRECTED)

FISSION GAS UCI/

i-SIGMA NUCLIDE SDHR ENERGY AREA CKGND

%ABN

%EFF GRAM ERROR i<R-88 FG 196.32 0.

O.

26. 00*

O.OOGE+00

.OOOE O

834.83 59.

24.

13.00 7.946E-01 4.996E-11 1.152E-11 1529.77 O.

O.

10.90 0.000E+00

.OOOE O

.OOOE O 2195.84 0.

O.

13.20 0.OOOE500

.OOOE O

.OOCE O 2392.11 O.

O.

34.60 O.OOOE+00

.OOOE O

ACTIVATION PRODUCT UCI/

1-SIGMA NULLIDE SEHR ENERGY AREA BKGNL

%ABN Z FF GRAM ERROR MN-54 AP 834.83 59, 24.

99.98*

.846E-01 1.096E -7 2.528E -8 CD-58 AF 810.76 50.

17.

99.40*

8.063E-01 9.044E -8 2.263E -8 CO-60 AP 1173.22 287.

8.

100.00 5.736E-01 7.356E -7 4.635E -E 1332.49 232.

O.

100.00*

5.101E-01 6.687E -7 4.578E -8 NI-65 6P 366.27 30.

6G.

4.61 1.676E+00 9.929E-12 6.OO2E-12 1115.52 35.

i6.

14.80 6.011E-01 9.88'7E-12 3.300E-12 1451.34 0.

O.

23.DC+

v.000E+00

.OOGE O

.OOOE O

2N-65 sip J115.52 35.

16.

30.75*

6.011E-01 1.674E -7 5.587E -E HALO 6EN FISSION PREDUCT UCI/

1-SIGMA th)CLIDE SLHR ENERGY AREA BKOND

%ABN

%EFF GRAM ERROR I-131 HFP 284.30 0.

G.

6.05 0;OO0E+00

.GOGE O

.000E O

364.48 30.

65.

E1.20*

1.676E+00 2.849E -8 1.722E -8 636.97 0.

O.

7.26 O.OOOE+00

.OOOE O

722.89 0.

O.

1.20 O.OOGE+00

.OOOE O

FI3SION PRODUCT LICI/

1-5IGMA NilCLIDE 55HR ENER3/

AREA BF.GND

%ABN XEFF GRAM ERROR MD-95 FP 140.5)

O.

40.60 0.GOOE+0V

.OOOE O

181.06 O.

O.

6.20 0.00:>E+00

.OOOE O

.OOGE O

566.43 30.

65.

1.37 1.676E+00 1.282E -6 7.750E -7 739.38 O.

O.

12.80*

O.OOOE+00

.OOOE O

.OOOE D

77G.00 O.

O.

4.50 0.OOOE+00

.OOOE O

.OOGE O

LB-125 FE 176.33 O.

O.

6.89 O.GOOE+00

.OOOE O

.000E O

427.89 63.

73.

29.33*

1.451E+00 2.162E -7 6.955E -5 463.38 O.

O.

10.35 O.OOOE+00

.OOGE O

.OOOE 0

600.56 G3.

15.

17.80 1.06LE+00 6.456E -7 1.180E -7 635.90 O.

O.

11.32 O.OOUE+00

.OOOE O

CS-134 FP 563.23 O.

O.

8.38 O.OOOE+00

.OOOE O

569.32 0.

O.

15.43 O.00;iE+00

.OOOE O

604.70 193.

20.

97.60*

1.056E+00 2.736E -7 2.620E -8 795.85 94.

30.

85.40 8.2OOE-01 1.967E -7 2.937E -8 801.93 0.

O.

8.73 O.OOOE+00

.OOOE O

CS-137, FP 661.65 131.

26.

85.12*

9.718E-01 2.328E -7 2.763E -8 g,wwe

=-

x NUCL*IDE IDENTIFICATION SYSTEM (ND PC VERSION DEC 88)

Ur

,4KNOWN LINE REPORT

,PAGE 2

ELAPSED LIVE TIME 3600. (PILE-UP CORRECTED)

UNIDENTIFIED PEAKS PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC "<. EAR

%EFF 1

0 244.57 62.

315. 14.67 489.44 472 36 1.72E-02 96.2 2.39E+00 5

0 427.71 63.

73.

1.86 854.82 847 14 1.74E-02 32.2 1.45E-OO 4

5 600.53 83.

15.

2.20 1199.63 1192 33 2.31E-02 18.3 1.06E+00 LINES NOT MEETING

SUMMARY

CRITERIA PK NUCLIDE ENEROY HLFE DECAY UCI/ GRAM ABNDIFF FAILED 2 NI-65 366.27 2.52H 1.715E -5 9.929E-12 45.23%

ABN i

2 MD-99 366.4.3 66.02H 6.579E -1 1.282E -6 1.19%

ABN f

3 SB-125 427.89 2.77Y 9.989E -1 2.162E -7 62.27%

ADM 4 SB-125 600.56 2.77Y 9.989E -1 6.456E -7 62.27%

AB!x 9 KR-88 834.83 2.84H 5.906E -5 4.996E-11 13.31%

AEN 10 NI-65 1115.52 2.52H 1.715E -5 9.887E-12 45.23%

ABN i

9 t

9

lNUCt.*IDE' IDENTIFICATION SYSTEM

.(NC PC VERSION DEC 88)

St/t1 MARY OF NUCLIDE ACTIVITY RAGE 3

TOTAL LINES IN LPECTRUM 12 UNIDENTIFIED FEAKS 3

IDENTIFIED IN

SUMMARY

REPORT-9 75.00%

ACTIVATIGN PRODUCT 1-SIGMA NUCLIDE EBHR

.HuIFE DECAY UCI/ GRAM ERR 3R

% ERR MN-54 AP 312.7CD

.996 1.096E -7 2.52SE -8 23.06 CO-50 AF

70. BOD

.954 9.044E -8 2.263E -8 25.02 CD-60 AP 1923.OOD-

.999 6.687E -7

4. 578E

--B 6.85 ZN-65 6F 244.40D

.995 1.674E -7 5.557E -8 33.38 HALOGEN FISSION PRODUCT 1-SIGMA NUCLIDE ESHR HLIFE DECAY UCI/ GRAM ERROR

% ERR I-131 HFP 8.04D

.867 2.849E -8 1.722E -8 60.45 FISSION PRODUCT 1-SIGMA 4

NJCL1LE 3BHN HLIFE DECAY UCI/ GRAM EPRC'4

% ERR CS-154 T

7'J.3.10D

.998 2.756E -7 2.620E -O 9.51 C3-137 "F

30.1.'Y 1.000

.2.320E -?

.:. < 03E -8 11.87 I

e g

M! nit 1UM DETECTABLE ACTIVITY REPORT (ND PC VERSION ' AUG 89)

PEAK WIDTH =

3.00 FWHM, CONFIDENCE LEVEL =

4.66.

MINIHUM NUCLIDE BKG ENERGY UCI/ GRAM D E-- 7 34.

477.59 2.7841E-07 ANIL-511 88.

511.00 HALF LIFE TOO SHORT NA-22 1.

1274.54 1.3015E-08 NA-24 3.

1368.53 3.8071E-09 CL-38 1.

2167.51 0.OOOOE+00 AR-41 4.

1293.64 HALF LIFE TOO SHORT K-40 11.

1460.81 4.5768E-07 SC-46 23.

1120.51 5.4922E-08 LR-51 S?.

320.08 2.7910E-07 MN-56 23.

846.75 HALF LIFE TOO SHORT FE-59 30.

1999.22 1.0784E-07 CO-57 92.

122.05 2.1657E-08 NI-65 1.

1481.84 HALF LIFE TOO SHORT CU-64 6.

1345.90

7. 7~545E-07 ZN-69M 47.

433.63 4.5705E-09 AS '76 22.

559.10 2.1557E-08 SE-75 77.

264.65 4.6142E-OB BR-82 40.

554.32 2.3831E-OS DR -54 25.

881.50 HALF LIFE TOO 5HOFT KR-85 45.

513.09 8.4410E-06 LR-adM 97.

151.16 HALF LIF E IUO SHOMT J.-L7 40.

402 58 H4LF LIFE 100 SHOR~i r;R-88 108.

196.32 HALF LIFE TOO SHOPT RE-88 2.

1836.01 HALC LIFE TCO GHORT RB-89 26.

1031.83 HALF LIFE TOO EHCJT LR-85 45.

313.99 3.5930E-08 f

SR-OSM 84.

231.69 HALF LIFE TOO SHORT SR-91 27.

1024.30 9.3396U-09 SF -9 2 1.

1383.94 HALF LIFE TOO bHORT Y-SS 2.

1836.01 2.5471E-08

(-91 9.

1204. %

1.2141E-OS Y-91 TID 39.

553.57

.2.0376E-0; Y 92 29.

934.46 HoLF LlFE 2.!O E -lORT Y-93 65.

266.90 2.418SE-03 ZR-95 21.

7D6.72 6.5083E-08 2R-97 28.

74 3. 36 0.7217E-On ND-74 25.

702.63

3. 7002E-OE NS-95 24.

765.79 3.9431E-Oa ND-- 5 7D 27.

1024.50 1.OO52E 0i MO-YO 74.

257. 4 2.6189E-;O MD-99 21.

739.58 1.8391E-07 TC-99MD 87.

140.51 1.2587E-08 RJ-103 30.

497.05 3.1421E-OB RU-105 22.

724.50 HALF LIFE TOO SHORT' RU-106 34.

621.84 3.8803E-07 RH-105 52.

318.90 6.3799E-08 AG-110M 35.

657.75 4.3132E-08 CD-109 91.

89.03 5.9348E-07 SN-113 46.

391.69 4 4385E-08 SB-122 29.

563.93 2.9499E-08 G

m.

m

1 a

PAGE' 2

.FEAK WIDTH =

3.00 FWHM, CONFIDENCE LEVEL =

4.66.

MINIt1UM NUCLIDE Db.G ENERGY UCI/ GRAM E?I: 124 232.

602.71 9.6837E-08 EB-125 115.

427.89 1.6857E-07 TE-123r:

94.

150.99 2.4117E-08 TE-- 132 98.

228.16 2.2475E-08 I 132 1~.

667.69 HALF LIFE TOO SHORT I-133 38.

529.57 1.0526E-08 I-134 23.

847.03 HALF LI.:E TOO SHORT I-135 5,

1260.41 1.5384E-09 XE-131M 1C 8.

163.93 1.0459E-06 XE-133 89.

80.99 5.3272E-08 XE -133'1 7E.

233.22 1.4636E-07 X E-13"5 101.

249.77 1.6313E-09 4

XE-135N 44.

526.56 HALF LIFE TOO SHURT XE 38 60.

253.31 HAiF LIFE TOO SHORT CE~134M 84.

127.42 HALF LIFE TOO SHORT CS-136 24.

818.50 3.9039E-08 C5-130 3.

1435.86 HALF LIFE TOO SHORT Bk13S 8.

356.00 4.1235E-08 Im-139 1.02.

165.85 HALF LIFE TOO 5HCRr Da 140 23 G37.32 1.0518E-07 IA-141

?G.

j90.22 HALF LIFE TOO 3 HURT Lii-1 E 1.

15%. W 8.4008E-09 CE-139 L02.

lob ES 2.7407E-08 CE-;41 G,5.

.t 4 5. 4 '1 3.5859E-OB C E- - 143 82.

207.26 3.2286E-Od:

i CE -144 90.

J33.54 1.6612E-07 hlD-147 86.

91.11 6.6835E-08 EU-152 54.

344.27 1.OB93E-07 EU-154 1.

1274.4D 3.6669E-05 i

HF-131 44.

432 05 3.9942E-08 W-187 41.

17:

'7 4.375;E-OC

.. 3 --- 2 0 3 6>.

..9

3. 2445E -08 h 20 61.

coc. 11 1.0816E-07 1 H-232 1:0.

236.63 6.9013E-08 4

u-23S 109.

18E.72 4.7140E-08 U -238 81.

131.20 8.3930E-08 W 239 89.

106.13 5.1706E-08 AN-:s41 53.

59.54 1.3560E-07 i

m e

9 9

0

o.

CALCULATES THE D0SE DUE T0 NUCLEAR POWER PLANT LIQUID RADIOACTIVE EFFLUENTS l

U.

S.

NUCLEAR REGULATORY COMMISSION PCD0SE AAAAAAAAAAA

. bi LIQUID DOSE CALCULATIONS from NUCLEAR POWER PLANT EFFLUENTS Rev. 34 08/20/91 16-Har-94 t

9 4

e e

e mm b"

h

FILENAME ????????.WK1 PLANT NAHE Har-94 16-Mar INDIVIDUAL MAXIHUM 06:59 AM Dilution Radioactive Release ENTER PLANT SPECIFIC DATA WHEN COMPLETED====>

Press ALT E FRESH WATER Flow Rate 4.00E+02 g/ min

=

Flow Rate 1.68E+04 g/ min Flow Time 2.30E+01 hr

=

Average Flow During Report Period Report Period e 1.20E+01 mth Individual Average Consumption (kg/y)

Transit Times (hrs)

Drinking Water 0.01

=

Pathways Adult Teen Child Fish / Invertebrates 0.01

=

Water 730 510 510 SportFish 21 16 6.9 Comments:

1 4

7 9

b FILENAME ????????.WK1 PLANT NAME Har-94 16-Har INDIVIDUAL HAIIHUM 06:59 AH ENTER RADIOACTIVITY RELEASED FOR EACH RADIONUCLIDE Nuclide uCi/ml WHEN COMPLETED====>

Press ALT J Hn-54 1.10E-07 Co-58 9.04E-08 Co-60 6.69E-07

)

Zn-65 1.67E-07 I-131 2.85E-08 Cs-134 2.76E-07 Cs-137 2.33E-07 H-3 3.30E-04 l

WHEN COMPLETED====>

Press ALT J ADDITIONAL DILUTION FACTORS Food Consumption Products:

1. Potable Water Near Field

====>

Dw 7.70E+01

=

2. Sport Fish

====>

Dsf 5.00E+00

=

3. Sport Invert

====>

Dsi 5.00E+00

=

4. Commercial Fish

====>

Dcf 5.00E+00

=

5. Commercial Invert

===J>

Dc1 5.00E+00

=

i FILENAME ????????.WK1 PLANT NAME Mar-94 16-Mar INDIVIDUAL MAXIHUH 06:59 AH ADULT TOTAL DOSE RECEIVED PER ORGAN 4

arem/

12.00 mth Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-L11 Hn-54 5.29E-05 1.01E-05 1.57E-05 1.62E-04 Co-58 9.25E-07 2.07E-06 1.87E-05 Co-60 1.96E-05 4.33E-05 3.69E-04 Zn-65 4.25E-04 1.35E-03 6.11E-04 9.05E-04 8.52E-04 I-131 5.37E-07 7.68E-07 4.40E-07 2.52E-04 1.32E-06 2.03E-07 Cs-134 9.02E-03 2.15E-02 1.75E-02 6.94E-03 2.30E-03 3.75E-04 1

Cs-137 9.76E-03 1.33E-02 8.74E-03 4.53E-03 1.51E-03 2.58E-04 H-3 2.87E-05 2.87E-05 2.87E-05 2.87E-05 2.87E-05 2.87E-05 4

J i

i a

TOTALS 1.92E-02 3.63E-02 2.70E-02 2.81E-04 1.24E-02 3.84E-03 2.06E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli e

s e

.-6

FILENAME ????????.WK1 PLANT NAME Har-94 16-Har TNDIVIDUAL HAXIHUH 06:59 AH TEEN TOTAL DOSE RECEIVED PEP. ORGAN mrem /

12.00 mth Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Hn-54 5.20E-05 1.03E-05 1.55E-05 1.07E-04 Co-58 9.16E-07 2.11E-06 1.26E-05 Co-60 1.96E-05 4.41E-05 2.55E-04

)

Zn-65 3.85E-04 1.34E-03 6.24E-04 8.56E-04 5.67E-04 I-131 5.69E-07 7.97E-07 4.28E-07 2.33E-04 1.37E-06 1.58E-07 Cs-134 9.24E-03 2.18E-02 1.01E-02 6.91E-03 2.64E-03 2.71E-04 Cs-137 1.04E-02 1.39E-02 4.84E-03 4.73E-03 1.84E-03 1.98E-04 H-3 2.08E-05 2.08E-05 2.08E-05 2.08E-05 2.08E-05 2.08E-05 TOTALS 2.01E-02 3.71E-02 1.56E-02 2.53E-04 1.25E-02'4.50E-03 1.43E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-L11 1

t i

j 1

,a w.

ma+ r. n

b FILENAME ????????.WK1 PLANT NAME Har-94 16-Har INDIVIDUAL MAXIHUH 06:59 AH CHILD TOTAL DOSE RECEIVED PER ORGAN mres/

12.00 mth-Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Hn-54 4.10E-05 1.09E-05 1.15E-05 3.44E-05 Co-58 7.70E-07 2.36E-06 4.49E-06 Co-60 1.67E-05 4.93E-05 9.27E-05 Zn-65 3.96E-04 1.05E-03 6.56E-04 6.65E-04 1.85E-04 I-131 8.37E-07 8.42E-07 4.79E-07 2.78E-04 1.38E-06 7.50E-08 Cs-134 1.12E-02 1.83E-02 3.86E-03 5.67E-03 2.04E-03 9.87E-05 Cs-137 1.32E-02 1.26E-02 1.86E-03 4.11E-03 1.48E-03 7.89E-05 H-3 3.30E-05 3.30E-05 3.30E-05 3.30E-05 3.30E-05 3.30E-05 o

TOTALS 2.47E-02 3.21E-02 6.48E-03 3.11E-04'1.05E-02 3.55E-03 5.27E-04 Bone Liver T. Body Thyroid Kidney Lung Gi-L11

u.

i FILENAME ????????.WK1 PLANT NAME Mar-94 16-Har INDIVIDUAL MAIIHUH 06:59 AH TOTAL DOSE

SUMMARY

REPORT 1.20E+01 ath Group Organ Total Adult Bone 1.92E-02 Adult Liver 3.63E-02 Adult Tot Body 2.70E-02 Adult Thyroid 2.81E-04 Adult Kidney 1.24E-02 Adult Lung 3.84E-03 Adult Gi-Lli 2.06E-03 Teen Bone 2.01E-02 Teen Liver 3.71E-02 Teen Tot Body 1.56E-02 Teen Thyroid 2.53E-04 Teen Kidney 1.25E-02 Teen Lung 4.50E-03 Teen Gi-Lli 1.43E-03 Child Bone 2.47E-02 Child Liver 3.21E-02 Child Tot Body 6.48E-03 Child Thyroid 3.11E-04 Child Kidney 1.05E-02 Child Lung 3.55E-03 Child Gi-Lli 5.27E-04 1.20E+01 ath ORGAN NITH HAXIHUM DOSE Group Organ Total Teen Liver 3.71E-02 a

t s

e

=

W

_....... ~

f ceca c oo oooooooo*om *-* * *o*o*o**m&*o *

ommmmm.mm *.

cp*oooconoccoccoo 17-MAR-94 14:52:56 co************t**

+

0c**********************************-************,********+.***

FERMI 2 CST LIQUID DURING 3/94 DISCHARGE SPECTRAL FILE NAME:

L942011.R3L SAMPLE DATE:

16-MAR-94 07:05:00 SAMPLE IDENTIFICATION:

L942011.R3L

. TYPE OF SAMPLE:

LIQUID SAMPLE QUANTITY:

506.1000 UNITS:

GRAMS SAMPLE GEOMETRY:

MAR 50093.EFF EFFICIENCY FILE NAME:

MAR 50093.EFF co*o********************** m **** m ***** m ***u**********v**

, ACQUIRE-DATE: 17-MAR--94 13: 44:10

FWHM(1332) 1.975 PRESET TIME (LIVE):

3600. SEC

SENSITIVITY:

5.OGv ELAFSED REAL TIME:

3600. SEC

SHAPE PARAMETER : 10.0 i'.

ELAPEED LIVE TIME:

3600. EEC

NBR ITERATIONS:

10.

okoot*********************4l&**********************************

DETECTOR: ADO Detectcr

LIBRARY:NJCL. LIB CALIB DATE:

02--FEB-94 11:04: 12

ENERGY TOLERMCE:

1.500 KEV KEV /CHNL:

.5012213

HALF L.IFE RATIO:

8.00 OFFSET:

.7430013 KEV

ALUNDANCE LIhIT:

75. 0 :',.

k % * * * *

k * * * + + 3R

t * * * * *

se 4 a + r

4t *

k + * * * * + *

Vr * *

t e> + * * * +

4 * % 9 4

4 f -+ v r

ENERGY WINDOW

-.24 TO 4105.26 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FI-1 2

16.55 F'.

12.

1.07 34.50 31 12 1. 37E-02 22. 5 4,77E- 01 2

2 18.29 24 63.

1.59 37.98 31 12 6.60E-0! 74.1 3

O 23.T2 26.

57.

1.32 49.20 47 6 7.2EE-03 54.5 4

0 175.89 41.

90.

1.46 352.41 349 10 1.1SE-02 47.;

5 0

351.89 13.

30.

1.26 703.55 699 8 3.55E-03 96.1 6

0 428.30 39.

93.

1.92 856.15 S47 18 1.64E-02 40.7 7-0 510.36 76.

29.

2.35 1019.72 1013 1e 2.11E-02 23.3 8

0 568.78 29.

15.

.94 1136.28 1132 10 8.1EE-03 31.8 9

0 604.47 174.

76.

1.74 1207.48 1199 15 4.LME-02 14.2 10 0

635.57 32.

32.

1.33 1269.53 1263 13 8.92E-03 40.5 11-O 661.47 97.

17.

1.29 1321.21 1316 11 2.70E-02 13.6 12 0

795.74 101.

33.

1.81 1589.OE 1552 17 2.32E-02 18.0 13 0

810.39 50.

18.

1.28 1618.32 1614 10 1.36E-02 23.6

14. O 834.37 64.

21.

.2.06 1666.15 1661 13 1.78E-02 23.3 15 0 1115.43 31.

21.

1.51 2226.91 2220 12 8.64E-03 39.T 16 0 1172.49 234.

17.

2.33 2340.74 2333 16 6.50E-O?

7.2 17 0 1331.60 230.

15.

2.05 2658.19 2651 13 6.40E-02 7.1 PEAK SEARCH COMPLETED (REV 15.8 - ND PC VERSION DEC 88)

, PULSE-PILE-UP CORRECTED DATA. CORRECTION =

1.000 UNCORR. LIVE TIME:

3600. CORRECTED LIVE TIME:

3600.

4 PK.IT ENERGY AREA BKGND

'FWHM= CHANNEL LEFT PW CTS /SEC % ERR 1J'2.

16.55 49.

12.

1.07.

34.50 31 12 1.37E-02 22.5,

h.

21 2-18.29-24.

65.

1.59 37.98 31 12 6.60E-03 74.1 1

m e,

.,1 m

em

,m 1,,___ m m WJmr:g 1

-. >~, - g a

~

,?

v --

l

-...a.

v s. + r us

.a. s l

5 0

331.89 13.

50.

1.26 703.55 699' 8 3.55E-03 96.1 6

0 428.38 59.

91.

1.92 856.15 847 18 1.64E-02 40.7

,7 0

510.36 76.

29.

2.33 1019.72 1013 16,2.11E-02 23.3

<3 0

525.70 29.

15.

.94 112a.28 1132 10 8.18E-03 31.8 l

9 0

604.47 174.

74.

1.74 1207.48 1199

.15 4.84E-02 14.2 1O O

+35.57 32.

32.

1.33 1269.53 1263 13 8.92E-03 40.5 j

!1 0

661.47 97, 17.

1.29 1321.21 1316 11 2.70E-02 13.6 12 0

95.74 101.

33, 1.81 1509.C8 1582 17 2.82E-02 18.O 13 O

G.O.39 5 0.,

18.

1.28 1618.32 1614 10 1.38E-02 23.6 14 O

G34.37 64.

21.

2.06 1666.15 1661 13 1.7EE-02 23.3

)

15 0

1115.4:'

31.

21.

1.51 2226.91 2220 12 8.64E-03 39.5 to 0

1172.49 234.

17.

2.33 2340.74 2333 16 6.50E-02 7.2 1

17 0

1331.60 230.

15.

2.05 2638.19 2651 13 6.40E-02 7,1 1

PILE-UP CL'FsREC I ION COMFLETED I

l 1

l I

i

)

4 n

h 9

a p

e,

NUCl IDE IDENTIFICATION SYSTEM (ND PC VERGION DEC 88)

NUCLIDE LINE ACTIVIT't REPORT ffGE 1

2 LAPSED LIVE TIME:

3600. (FILE-UP CORRECTED,

_FIGGION' GAS GCL/

.t-SIGNA NUCLIDE S'BHR ENERGY-AREA DI:GND

%ABN

%EFF GRANS ERROR KR-80 FG 196.32 0.

G.

26.00*

O.OOGE+00

.000E o

.000E O

834.83 64.

21.

13.00 7.846E-01 1.630E -3 4.336E -4 1529.77 O.

O.

10.7C O.OOOE+00

.00?E O

, 00 :)E O

2195.84 O.

O.

13.20 0.OOOE+00

.OOCE O

.OOOE O

2392.11 0.

O.

34.60 0.OOOE+0C

.000E 0

.OOCE 0

AC1IVATION PRUDUCT Ut:I /

cSIGMA NUCLIDE SBHR ENERGY AREA BKGND

%ABN 5.EFF GRANS ERROR ANIL-511 AP D11.OO 76.

29.

96.73*

1.234E+00 1.2t.4E -2 2.944E -O MN-54 AP 834.83 64 21.

99.98*

7.848E-01 1.215E ~7

2. 827 E -8 CO-38' AP 810.76 30.

18.

99.40+

8.061E-01 9.284E -8 2.193E -8 CO-60 AP 1173.22 234

'17.

100.00

5. 736E -01 6.054E -7 4.352E -8 1332.49 230.

15. 100.00*

5.101E-01, 6.704E -/

4 7462 -8 N1-63 A?

366.27 O,

4.6i O.SOOEv00

.GOOE O

.0001 0

1115.52-31.

li 14.8C 6.OOeE-01 2.720E -3 1.076E

.s 1481.34 O.

O.

22.SO*

O.OQUE400

.~.OuE O

.000E O

Z fs--65 AP 1115.52

~1.

21.

50.7b*

6.OO6E-01

. 020E -7 6.002E -;.

HALOGEN FIECION PRODUCT LCi/

1-32GMA NU3LIDE SBHR ENERGY AREA BKGND

%ABN

%EFF GRah3 ERROR I-131

.HFP 284.30 0.

O.

6.05 O.OOGE+00

.OOGE O

.OOOE O

364.48 O.

O.

81.20*

O.OOOE+00

.000E O

.OOOE O

636.97 31.

32.

7.26 1.00SE+00 7.261E -7

.952E -7 722'.89 C.

O.

1.80 O.000E+00

.000E O

.0005 O

FI5 SIGN FRO.%CT Ut -I /

1-9IGi1A NUCLIDE SBHR ENERGY aRCi 4 LKGND

%ABN

.EFF BRAN 6 ERROR GB-125 FF 176.33 21.

90.

6.87 3.10:>E+00

.E51E

~7 3D7E 7

427.89 b9.

91.

29.33*

1.44?E+00 2.0395

-7 8.382E -8 463.33 C.

O.

10.35 O.000E+00

.000E C

.UOOE O

600.So O.

O.

1 ~/. 80 O.OOOE+00

.'OvE 0

.000E 635,90 32.

32.

11.r2 1.005E+00 4.1: 9E

-7 1.694E

-7 i

CS-134 FP 563.23 O.

O.

6. U3 O.000E+00

.00CE O

.00CE 560.32 29.

15.

15.43 1.1175+00 2.3~9E -7 E.074E -E oO4.70 174.

76.

97.60*

1.052.E+00 2.SiUE -7

'. 576E -8 793.85 102.

33.

55.40 8.198E-01 2.152E -7 3.369E'-3 801.93 O.

O.

S.73 0.:f00E+00

.OOGE O

.OOOE O

C5-136' FF 176.55 41.

90.

13.56 3.100E+00 1.566E -7 7.375E -E 273.65 O.

O.

12.66 O.OOCE+00

.UOOE O

.GOOE O

340.57-O.

O.

48.50 0.OOOE+00

.OOOE O

818.50 O.

O.

99.70*

O.OOGE+00

.COOE O

.OOOE O

1048.07 O.

O.

79.60 0.OOOE+00

.000E O

.OOOE O

1235.34 O.

O.

19.70 0.OOOE+00

.OOOE O

CS-137 FP 661.65 97.

17.

85.12*

9.719E-01 1.745E -7 2.369E -8

~

NUCLIDE IDENTIFICATION SYSTEM UJD PC VERSION DEC 88)

Ni/CLIDE L INE ACTIVITY REPORT

,P, AGE 2

ELAP3ED LIVE TIME:

3600. (PILE-UP CORRECTED)

NATUR1L FRUDUCT UCI/

1-8IGMA NUCL1DE SEHR ENERGY AREA BKGND "ABN

%EFF GRAMS ERROR RA-22o NP 186.21 0.

O.

3.23 O.OOGE+00

.OOOE O

241.93 0.,

O.

7.49 O.OOOE+00

.OOOE O

275.21 C.

O.

19.20 0 OOOE+00

.OOOE O

.COOE O

351.92 13.

50.

37.20 1.733E+00 2.942E -8 2.828E -8 609.31 0.

O.

46.30*

O.COOE+00

.OOOE O

1120.29 0.

O.

15.1O O.000E+00

.OOGE O

.OOOE O

1238.11 0.

O.

D.94 O.OOOE+00

.OOOE O

1764.4?

O.

1S.SO O.OOOE+00

.OOOE O

2204.22 O.

O.

4.98 O. 000E-OO

.OOoE O

.OOGE 0

U-238 tlF-131.20 0.

O.

20.40*

O.OOGE+00

.OOOE O

152.70 O.

O.

6.80 0.OOOE+00

.000E O

.OOOE C

569.50 29.

15.

11.00 1,117E+00 3.557E -7 1.131E -7 880.51 0.

O.

12.24 0.OOGE+00

.OOOE O

.OOOE C

883.24 0.

O.

12.00 O.OOOE+00

.OOOE O

.OOGE O

926.00 O.

O.

11.20 0.OOOE+00

.OOOE O

946.O')

O.

12.GO O.OOOE400

.COOE O

,OOOE O

I

~

o e

e a.

.NUCLIDE IDENTIFICATION SYSTEM (ND PC VERSION DEC 653)

UNKNOWN LINE REPORT RAGE 3

,' ELAPSED LIVE TIME 3600. (PILE-UP CORRECTED)

UNIDENTIFIED PEAKS PK IT ENERGY AREA EKiSND FWHM CHAMEL LEFT FA CTS /SEC % ERR

%EFF 1

2 16.55 49.

12.

1.07 34.50 31 12 1.37E-02 22.5 2.43E-02 2

2 18.29 24.

65.

1.59 37.98 31 12 c.60E-03 74.1 3.36E-02 3

0 23.92 26.

57.

1.32 4.20 4-7 6 7.23E-03 54.5 8.01E-02 4

0 175.89 41.

90.

1.46 352.41 349 10 1.15E-02 47.1 3.10E+00 5

0 351.89 13.

50.

1.26

'703.35 699 8 3.53E-03 96.1 1.73E+00 6

0.428.38 59.

91.

1.92 CSc.15 847 18 1.64E-02 40.7 1.45E+00 7

0 510.36 76.

I'9.

2.33 1019.72 1013 16 2.11E-02 23,3 1.23E+00 10 0

635.57 32.

32.

1.33 1269.53 1263 13 S.9.?E-03 40.5 1.01E+00 LINES NOT MEETIN3

SUMMARY

CRITERIA PK NUCL'DE ENERGY HLFE DECAY UCI/GRAN5 ABNDIFF FAILED l

4 S9-125 176.33 2.77Y 1.001E O

2.861E

-7 62.81%

AEN 4 CS-136 176.55 13.16D 1.071E Q

1.Sc6E -7 4.?5%

ABN 5 Ris-226 351.92 1600.00Y 1.000E O

2.94.iE -8 23.96%

ADN 6'GD-125 427.89 2.'7Y 1.OO1E O

2. OUiE -7

62. ' 1%

ABN 8

7 ANIL-511 5 J.1. 00 IO9.70M 1.339E S

1.264E -2 100.00%

DCY E U-23G 569.50 1.voE+10Y 1.OOOE O

3. 537E -- 7 12.54%

Abt !

1O ES-125 632.90

2. 77;'

1.OO1E O

4. 3 7 '-/E

--7 67.31%

ABN 10 1-13.1 636.97 8.04D 1.11aC O

7.21;E -7

.54%

ALN 14 KR-88 G34.83 2.84H

2. 00 M 3

1.3S3E -3 13.31%

DCY.NN 15 NI-65 1115.52 2.51H 5.243L 3

1.725E -3 34.49%

DCY,AB1 l

4 l

i s

e f

g ag 9

9 w

=

<5h p e

F

n NUCL.IDE IDENTIFICATION SYSTEM (ND PC VERSION DEC'88)

SyMMARY OF NUCLIDE ACTIVITY

,PAGE 4

TOTAL LINES IN SPECTRUM 17

-UNIDENTIFIED PEAKS 8

IDENTIFIED IN

SUMMARY

REPORT 9

52.94%

ACTIVATION PRODUCT 1-SIGt1A NUCLIDE SBHR HLIFE DECAY

'UCI/ GRAMS ERROR

% ERR Mil-54 AP 312.70D 1.003 1.215E -7 2.827E -8 23.27 CO-58 AP 70.80D-1.013 9.284E -8 2.193E -8 23.62 CD-60 AP 1925.00D 1.000 6.704E -7

4. 746E

-8 7.08 ZN-65 AP 244.40D 1.004 1.520E -7 6.002E -8 39.49 FISSION PRODUCT 1-SIGMA NUCLIDE SEHR HLIFE DECAY UCI/ GRAMS ERROR

". ERR CS-134 FP 753.10D 1.001 2.513E -7 3.576E -8 14.23 CS-137 FP 30.17Y 1.000 1.745E -7 2.369E -8 13.58 4

a U

N

MAR-15-1994 16:01 FRON DECO FERM12 DOSitETRY 917085151259 P.01 1

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t1AR-13-1994 26:02 8: ROM DECO FERfil3 70SitETRY

'TO 9. J5852259 P.03 o

g CALCULA ).10N OF MFC FRACTION e

Melease Perust No.

94 CST 2 Type of Sample:

CST 2

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,4 MAR-23-1994,16802 FROM DECO FERM12 D031 METRY

.TO 927085151259 P.04

. p CIRCUt.ATING WATER DECANT MONITOR SETPOINT COMPARISON Re. pe,m o.

0. car 2

1. Estimated Circulating Water Decant Monitor alarm (fugh hgh) setpoint based on nuoWe mk of batch to be released =

(Cr 51 cono (at 2) n 0.096 x 2.7E+8) + (Total conc except Cr 51 x 2.7E+6)

Circ Water.

+ DecantMonitor

=

MPCF(Ali2) A 2 reading (At:1) t J

.g

)

(.

0 uCiks x 0498 x 2.70E+08) + (. 1.99E-06 uCi/mi x 2.70E+06) i 160 cpm

+

8.25E-02 x 2 4

3.43E+03 opm

- =

' 2. Installed Circulatin0 Water Decent Monitor alarm (hi h high) setpoint 0

1700 cpm

=

3.Setpoint change required?

YES X

NO Performed by:

7-/[

LaL ms R. _

\\;

~

Sr. nature / Date Reviewed by:

~5 //SIfN (Csr only) I : NA

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't1AR-15-1994 16803 FROM DECO FERM12 DOS 1t1ETRY TO

'917085151259 P.05 i

CALCULATION OF DISCHARGE MONITOR RELEASE RATE AND GETPOINT -

I CIRCULATING WATER NOT CONTAMINATED e

1 Release Permit No.

94 CST 2 BF = 0.1 H3MPCF = 0.13 H3F = 0.99

1. Maximum CWD now rate (Att 1) x U.b 1.56e04 gpm x 0.5 Allowable

=

3.80E+04 gpm

=

M*===

[(MPCF(Att 2) x (1 + SF)) + H3MPCF) [( 8.2SE-02 x (1 + 0.1)) + 1.3E 1J Rate

2. Detemunation of

Estimated release rate" (for use h Part 3 and 4 below):

a)If maudmum allowable release rate is greater than or equal to maximum release tank discharge flow rate, estimolod reioaso rate equals maxhman selv4w tak diaderge fkm rate (from Att 1 Part 4),

b) If maximum allowable release rate is less than rnaxsnum release tank (tischarge flow rate, cettmated release rate equais maximum allowable release rate.

Et,timated reloooo roto x lMPCF x (1 + BF) + H3MFCF)

3. TotalMPC fraction =

at discharge point CWD flow mte 4.00E+02 gpm x { 8.25E-02 x (1 + 0.1) + 1.3E-1 ]

=

5.26E-03

=

1.88E+04 gym l

I Monitor Tntal enrr, SensitMiy CWD flow rate Discharge 4.

Discharge (Att 2) x (Att 1) x (Att 1 Part 3) x H3F Monlior MonitorSetpoint a

+

Backgrcund MPCF Estimated release rate Reading (Att2) x

- (Atte Part>)

(1 + BF)

(Att 1 Parti) com 1.99E-06 uCl/oc x 1.60E+07 /(uCikc) % 1.86E+04 gpm x 0.99 l.

+

120 com 8.25E 02 x

4.00E+02 spm x

(1+0.1) 5 t

j,4%+Q(

Cpgj 2

Por*,m eo [ d / s d M o aie F/P7Y se..w..y &M L '

Daie bs44 Reviewed Dy Dele

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g I

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. m gelertetapasse J.,.i.. S :.;, M iH M ~t:.:- q-uteimge idU ;gg.ta-tych;ppet? - * ~v n _ m.qt;. Im: :dhp on;p;p;qt:.... -....8 'ff-M-

--t o~~s f

3esnme esgeneosg {eRorag 9.0E43 1.73E42 1838 44 5.6eE-Of'~ ~~~

t.89E43 Nre buen ossa dose $rAsn$

6.0SE-04 2.8AE44 1.7tE44 LO2E44 102E-04 t.94E44 2.44E-04 0

retal eenn dose drrdher:)

9.SSE43 f.MIE:02 1.54E42 6.e6E-c4 5 70E 03 2 08E 03 e.ME 44 21ssessmusm 1 _ _ may=W Ww.;m r";3osesfeg4Wegurspac e

.ue w. w e m agsse_dessiocygeg.34. q,.- mt.:.o r R 3errene orgendoes $nRom) 2 88E-02 565E42 3.83E-02 6.83E-04 1.eeE42 1.5 tE40 t9 N Pure tots orgsrieoes(reftese) 1.8eE-03 8.4eE44 3.9eE44 2.12E-04 112E-04 4 54E-C4 5.8E44 rates caen dame (ndbrug 2.8SE-02 5.1SE42 38242 T.95E44 1RE-02 5 98E 03 2 SK43 Outtt@eWHtergelttfo rutseamm:: :im:t; = -'; ne m W 5 F9

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Puse bate esgen q$oes97Geru) 806E-04 2 GE44 17E44 1.02E-04 10E-04 1.94E44 2.4E-04 4

Teesiogne close(trdisrve 9.05E-03 1.7eES2 134E42 8.85E44 5.ME43 208E C3 EPE44 8

FC" 7.esY -

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Tegelegen done enRem) 2.85E42 5.11E42 18E-02 E95E44 /\\

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t1AR-15-1994 16:05 FROM DECO FERM12 DOSIMETRY TO 917085151259 P.07 s

o *.oc ocooooooo o w oooo o' ce **co **.**** *. a * * * ** ** e a o + o *

o...o ao ** o o

DETROIT EDISON FERMI-2 POWER PLANT 15-MAR-1994 09:57:15.43 4

e....................................................*....

l RADIATION PROTECTION DEPARTMENT GAMMA SPECTROSCOPY ANALYSIS REPCRT Sample ID Number: CST 31594-1 Aquistion Times 15-MAR-1994 FI8 : 23 : 4.a. 84 Storage file CST 31594-1.cnf REMARKG__

)

PERFO 9PT.lJ &

(

SIGNATERE REVIE Y

A i

f/ M hN y

sIeN y e DAre 4

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' 94MI 0 0900

..=,s=

m

t1AR-15-1994 16:06 -FRON DECO FERM12 DOSINETRY TO 917085151259 P. 08 j

PaDe :

2 Cocplo ID s CST 31594-1 Mcquisition date : 15-MAR-1994 08:23:46 4o***************************************************************************

Fermi E Hediation Protection Gamma Spectroscopy Report eco************************** Sample Parameters **+**************************

Socple ID Number CST 31594-1 Sacple collection start date: 15-MAR-1994 07:40:00.00 Sotple collection end date

15-MAR-1994 07:40:00.00 Type of sample 1 Liter Marine 11 Sorple quantity's 1.00210E+03 GM SSeple geometry :

M1LL Operator BPB coc*********************** Acquisition Parameters ***************************

Detector number DET1 Acquire data :

15-MAR-1994 08:23:48.84 Proset live time 0 00:33:20.00 Elapsed live time :

0 00:33:20.00 Elopsed real time :

0 00:33:20.43 Percent ri a ad e i m e :

e.00 %

- c* *** ** * ** * * * **** * * * * * ** Ca l i brat i o n Pa ra m e t e r s *+++++***********+****nxxxx Datector number :

DET1 Yearly cal date :

2-MAR-1994 13:47:45.33 Kev / channel 4.99915E-01 Zero offsets S.38667E-01 Daily cal date

15-MAR-1994 08:08:18.41 000*********************** peak Search Parameters **************************+

Stcet channal 100 End channel 4096 Height sensitivity a 5.00000 Shape sensitivity

10.00000 Mawimum number of iterations to resolve multip1wt* a C con ***************** Nuclide Identificatiuss Parameters *********************

Energy tolerance : 1.25000 Half-life ratio : 10.00000 Abundance limit e 75.00000 Lilar wr y a dacmaster.n1b Efficiency file : EFFD1 Efficiencies at : Peak ener l

ease *************zumum* e111'*****************************************gy Pk It Energy Area Bkgnd FWHM Channel Left Pw Cts /See % Err Fit 1

0 437.84 81 36 1.60 854.75 849 14 4.03E-02 20.1 e

e 604.39 149 48 1.78 1208.31 1203 13 6.94E-02 16.0 3

0 661.47 93 28 1.73 1322.10 1313 19 4.65E-02 17.2 4

e 795.91 79 19 1.70 1591.02 1586 14 3.94E-02 17.7 5 0 810.14 49 27 2.24 1619.49 1608 19 2.45E-02 34.0 6

e 835.01 62 20 1,79 1669.24 1661 16 3.11E-02 22.4 7 0 1172.85 239 9

3.05 2345.05 2337 15 1.19E-01 6.6 8

e 1322,.21 204 9

2.06 2663.83 2655 16 1.02E-01

7. 4

, og...

m+v.6tme --^_^ ~ ~ ~

~~

'd'"~~'

MAR-15-1994 16:07 FROM DECO FERf112 DOSIMETRY TO 917085151259 P.09

- occoceococconoc*ooono**eosooooooo****co*o***cc****csooon******o a'

Dw t ro'i t Edicen Foral EP Generated 15-MAR-199'4 08 : 57 coco ***************************eak Report,***************************************:21.08

'c.S.saple ID : CST 31594-1 h Jidled O D2eay Time =

0 00:43:48.84 Deposition Time 17 NGV-r5 i6 00:00:00.e*'

=

Post-NID Peak Search Report l

It Energy Area Bkgnd FWHM Channel Left Pw 'AErr Fit Nuclides O

427.84 81 36 1.60 ~854.75 849 14 20.1 5ts DS O

604.69 139 48 1.78 1208.31 1803 13 16.0 CS-134 0

661.47 93 28 1.73 1322.10 1313 19 17.2 CG-1.~ 7 i

O

/95.91 79 19 1.70 1591.02 1586 14 17,7 CS-134 r

O 610.14 49 27 2.24 1619.49 1608 19 34.0 CO-58

)

0 835.01 62 20

1. 79 1669.24 1661 16 22.4 MN-34

~

0 1172.85 239 9

3.05 2345.05 2337 15 G.6 co-Ge 0

1332.21 204 9

2.06 2663.83 2655 16

7. 4 CO-63 4

I 4

1 i

+~----~~~.^----^=~~~'

\\

-NAR-15-1994 :16:09 FROM DECO FERM12 DOSIPETRY

. TO.

917085151259 P.10 Sub0 cry of Nuclido Activity Page :

2 Btrplo ID : COT 31594-1:

Acquisition date : 15-MAR-1994 08:23:48 Tetel-number: of L11nes in spectrum 8

' Nu3b;r of unident ified lines 0

Nu;bsr of lines tentatively identified by NID 8-100.00%

Muc11'e Type d

activation-Uncorrected Decay Core Decay Corr 1-Sigma

-Nuclide:

H11fe-Decay

-uC1/GM uCi/GM 1-Sigma Error % Error Flaas 1N-54 312.70D' 1.000

1. 6 4 f.E-07 1.641E-07 0.368E-07 22.42 CO-58 70.800 1.000 1.264E-07 1.264E-07 0.430E-07 34.05

' CD-60 :

5.27Y-1.000 8.110E-07 6.110E-07 0.602E-07 7.43

-A CE-134' 2.06Y-1.000 2.729E-07 2.729E-07 0.436E-07 15.99 Tot al Act i vi t y :

1.374E-06 1.374E-GG Nsalige Type a fission Uncorrected. Decay Corr Decay Corr 1-Sigma

.Nuclide

'H11 f e.

Decay uC1/GM uC1/GM 1-Sigma Error 5 Error Flags CS-137 30.17Y 1.000 2.27eE-07 2.270E-07 0.391E 07 17.CC Total Activity c.C7eC 07 C.07ec 07 Gecnd Total Activity :

1.601E-06 1.601E-06 Flcgos "K" = Heyline not found "M" = Manually accepted "k" = Manually edited "H" = Nue11de specific abn. 11mit Sb-!2f 3.ErPE-7 4=

/,77E-4

. +,, -,

.w..-..

1994 16:10- FROM DECO FERN 12 LOSlf1ETRY

. TO 917085151259 P.11 Unid:ntiflod' Energy Lines Page s 3

~

Bhtp3o ID : CST 31594-1 Acquis 2 tion dat e : 15-MAR-1994 08:23:48 I t'.-

Energy Area-Bkgnd FWHM Channel Left Pw Cts /See */ Err 4Eff Flags G

427.84 81 36 1.60 854.75 849 14 4.03E-02 20.1 9.57E-01 T

'F1 cgs:

"T"'= Tentatively associated 4

t M M4 4 W.@ ^ ^ ^ ^ ^

~

$M-~

4_'__

_2'

'N MDID"

^

t1AR-15-1994 16:11 FROt1 DECO FERtil2 DOSlf1ETRY

'TO 917085151259 P.12 R$Jocted Report Page :

4 b5cple 10 : L'S 131694-1 Acquisition date : 15-MAR-1994 08:23:48 4

Half-Life 1-Sigma Nuclide Half-life Ratio Energy %Abund Activity

% Error Rejected by BR-84 31.80M 1.90 604.80 1.80 5.410E-05 15.99 Abun.

736.50 1.31 --- Not found ---

802.20 6.10 --- Not found ---

881.50+ 42.00 --- Not found ---

1015.90

6. 20 --- Not found ---

1213.30 2.60 --- Not found ---

1463.80 2.00 --- Not found ---

1741.20 1.60 --- Not found ---

1877.50 1.14 --- Not found ---

1897.30 14.90 --- Not found ---

2029.60 2.10 --- Not found ---

% Abundances Fnund =

P. Pa KR-08 P.84H 0.35 165.98 3.10 --- Not found 1

Abun.

196.32* 26.00 --- Not found ---

362.23 2.25 --- Not found 834.83 13.00 1.613E-06 22.42 985.78 1.31 --- Not found 1141.33 1.28 --- Not found ---

1179.51 1.00 Not found 1250.67 1.12 --- Not found ---

1309.50 1.48 --- Not ruund ---

1518.39 2.15 --- Not found ---

10c1. 77 10.90 --- Not found ---

2029.84 4.53 --- Not found ---

2033.41 3.74 Not found ---

% Abundances Found =

18.09 SB-125 2.77Y 0.00 d 76.33 6.89 --- Not found --- Abun.

1 380.44 1.50 --- Not found ---

p27.89* 29.33 3.877E-07 20.15 463.38 10.35 --- Not found ---

d600.56 17.80 --- Not found ---

9606.64 5.02 --- Not found ---

d635.90 11.32 --- Not found ---

671.41 1.81 --- Not found ---

% Abundances Found =

34.91 AC-228 6.13Y 0.00 129.08 2.80 --- Not found --- Abun.

209.28 4.40 --- Not found ---

270.23 3.60 Not found ---

327.64 3.20 --- Not found ---

338.32* 11.40 --- Not found ---

409.51 2.13 --- Not found ---

463.00 4.40 --- Not found ---

794.70 4.60 4.312E-06 17.74 911.07 27.70 --- Not found ---

964.60 5.20 --- Not found ---

969.11 16.60 --- Nnt found 1588.00 3.50 --- Not found ---

% Abundances Found =

5.14 i

i

~

_ N % 6dk *" N O *O

l.

;NAR-15-1994.:16322 -FROM DECO FERM12 DOSIMETRY-

-TO ~

917085151259

.P.13

'I 4

l

.'Rh 0StOd R0 pert: (continusd)

- Page

-5

. 80;plo ? ID 's s-CST 31594-1 Acquisition-date : 15-MAR-1994.08:23:48-l 4-,-

j

_lcgs'"*":= Keyline' f

1 I

I 1

I I

')

Y i

i, e

4 e

I

g e

o

L M...

??O.- = -

r*

4

~~

NAR-15-1994 16:12 FRott DECO FERP112 DOS 1tETRY TO 917085151259 P.14

*5e ooa n oc e * *

o e **

o * * *

oo oooo ** cocoa no n e** *** * *

m e o*

o*

o c a * * * ****

9.

Datroit Edison Foroi 2 MDA R3 port, Generated 15-MAR-1994 09219:34.48

,o**eo******************************************************m********.***.********.

o Sacple ID : CST 31594-1 Pa of oc*oc************************************ge

- - - - m*****************************

Minicus Detectable Activity Report Bckgnd Energy MDA Nuclide Sun (kev)

(uci/GM) i CE-7 19.

477.59 3.4362E-07 F-18 58.

511.00 4.7661E-08 NA-22 0.

1274.54 1.0321E-08 NA-24 2.

1368.53 3.9023E-08 MG-27 12.

1014.44 1.3915E-05 CL-38 2.

164?.4P 4.1261E-07 K-40 5.

1460.81 5.2864E-07 AR-41 3.

1293.64 6.2703E-08 SC-46 16.

889.25 5.9751E-08 CR-51 37.

320.OS 3.4549E-07 a

CO-56 5,

1238.25 7.2715C-08 MN-56 1.

1810.69 1.8319E-07 NI-56 32, 158.38 1.9543E-08 4

CD-07 33.

122.06 C.3CGGC 00 FE-59/

15.

1999.22 1.2272E-07 CU-64 3.

1345.00 1.4720E-05 NI-65 e.

1481.84 6.6084E-08 ZN 6D' 37.

1110.02 2.0677E-07 ZN-69M 28.

438.63 4.3380E-08 CE-75 32.

136 ee 3.1796E-08 i

AS-76 21.

559.10 9,8030E-08 4

OR-le 17.

776.49 6.6137E-08

g CR-23 18, 529.64 3.9246E-06

~ 4, CR-84 19.

881.50 5.6519E-07 CR.~5 0,

802.41 Half-Life too short MR-05

' M2.

513.99 9.3752E-06 KR-55M 32, 151.18 2.9621E-08 SM-s5 ee.

513.99 4.0626E-08 RB *6 18.

1976.63 8.4553E-07 KH-87 30.

402.58 1.3069E-07 SR-87M 30.

388.40 5.7244E-08 KR-88 37.

196.32 1.1296E-07 RB-88 1.

1382.39 3.8478E-05 t

Y-88 0.

1836.01 1.4243E-08 KR-39 9.

220.90 Half-Life too short RB-89 9.

1931.88 1.2455E-06 KR-90 9.

1118.69 Half-Life too short RB-90 0.

831.69 Half-Life too short RB-9:M 0.

824.23 Half-Life too short Y-9;M 38, 202.51 3.0873E-06 BR-91 16.

1924.30 2.2424E-07 Y-91 3.

1204.90 1.2951E-05 Y-91M 15.

555.60 9.0199F-08 SR-92 1.

1383.94 4.3433E-08 Y-92 17.

934.46 5.5933E-e7 BR-93 22.

598.28 1.4657E-05 Y-93 36.

266.9m 4.4752E-e7

- _ t % p.m. +.se.

^

%t

" ^ '

-9 h W4

- ^^ ~ ~ -

4

f1AR-15-1994 16:14 FROM DECO FEPJ112 DOSIMETRY TO 917085151259 P.15 Manlcuo Detectcblo Activity Report (continued)

Page :

2

'E2Cple ID : CST 31594-1 Acquisition date 15LhAR-1994 08:23:46

^

Bekgnd Energy MDA Nuclide Sua (kev)

(uCi/GM)

NR-9 4 7.

70?.63 3.3749E-08 NB-95 17.

765.79 5.3015E-08 N3-C5M 41.

P35. A9 1.133RF-07 ZR-95 10.

756.72 7.3705E-08 N3-97 16.

657.90 7.957AE-RA ZR-97 17.

743.36 5.4698E-08 MD-99M G.

739.Sa 2.8761E-07 TC-99M 37.

140.50 2.5581E-08 TC-101 33.

304.91 6.0159E-07 RU-103 17.

497.08 3.9781E-08 TC-104 22.

357.99 3.1283E-07 RH-105 31.

318.90 1.6464E-07 RU-105 10, 724.50 9.6359E-08 RU-1C6 10, 621.84 3.4183E-07 CD-109 EU.

88.03 6.6228E-07 AG-110M 18.

937.48

1. 9489 E-07 CN-113 32.

391.69 5.8690E-08 SN-117M 32.

158.56 2.2359E-08 C3-122 32.

363.93 7.5040E-08 CB-124 130.

602.71 1.0876E-07 CB-125 90.

427.89 2.ED53E-07 TE-125M 42.

109.28 8.3931E-06 TE-127 18, 417.90 3.3793E-06 TE-127M 27.

57.60 2.3631E-05 XE-127 42.

202.84 3.6574E-08 TE-129 35.

459.60 1.1562E-06 TE-129M 12.

695.88 1.2291E-06

) XE-129M 37.

196.56 4.8425E-07 I-130 19.

536.09 4.1934E-08 2A-131 31.

123.80 6.6210E-08 1-131 41.

364.48 4.9536E-08 TE-131 38.

149.72 1.5397E-07 TE-131M 18.

773.67 1.4723E-07 XE-131M 45.

163.93 1.1516E-06 I-132 12.

667.69 5.3369E-08 TE-132 40.

PPA.1A 3.1014E-08 BA-133 38, 302.84 1.8284E-07 RA-133M 32.

276.09 1.5757E-07 I-133 18.

529.87 4.6083E-08 TE-133M Pt.

912.58 1.6711E-07 XE-133 29.

81.00 7.7981E-08 XE-133M 37.

233.22 2.6113E-07 I-134 21.

884.09 2.2512E-07 TF-134 42.

210.47 3.1751E-07 BA-135M 37.

268.24 1.8746E-07 I-135 2.

1260.41 1.3609E-07 XE-135 31.

249.79 3.1091E-08 XE-135M 21.

526.56 6.9574c 07 CG-136 14.

818.50 5.2740E-08 I-126 0.

1313.0c Italf-Life too misur4 XE-137 0.

455.49 Half-Life too short e

i ewA b. w

- ' ~ * * * ' '

MAR-15-1994 16:15 FRON DECO FERM12 DOSitETRY TO 917085151259 P.16 Minicua Datsctablo Activity Report (continuzd)

Page :

3 3:cplo ID : CST 31594-1 Acquisition date : 15-MAR-2994 08:23:48 i

1 Bckgnd Energy MDA Nuclide Sum (kev)

(uC1/GM)

C3-133 2.

1435.86 1.9703E-07 XE-133 33.

258.31 1.5070E-06 BA-139 5.

1420.50 3.2466E-05 CE-139 26.

165.85 2.2218E-08 CS-139 3.

1283.23 4.2496E-05 BA-140 23.

537.32 1.7259E-07 LA-140 2.

1596.49 4.5931E-08 BA-141 33.

190.22 4.0244E-07 CE-141/

38.

145.44 4.2528E-08 LA-141 3.

1354.52 1.9785E-06 RA-142 31.

255.12 6.0611E-06 LA-142 17.

641.17 1.2943E-07 CE-163 28.

293.26 6.6927E-08 CE-14 /

35.

133.54 1.8378E-07 PR-144 2.

1489.15 1.4234E-04 ND-147 22.

91.10 7.4169E-08 PM-148M 16.

550.07 3.9041C 00 EU-152 20.

344.27 1.0251E-07 EU 154 9.

1004.76 2.8957E-07 EU-156 14.

646.29 5.6816E-07 14F 101 22.

482.03 4.6440E-08 TA-182 7.

1221.42 2.0251E-07 W-107 11.

6 e5. 81 1.3933E-07 RE-188 44.

155.03 1.5291E-07 HS.233 33.

279.19

3. 7200ti-06 BI-207 32.

569.67 5.4367E-08 IL-208 0.

583.14 Half-Life too short PB-212 46.

238.63 7.1546E-08 CI-214 28.

609.31 8.8643E-07 PB-214 4P.

351.92 4.8753E-07 RA-224 44.

240.98 7.5772E-07 RA-226 47.

186.21 7.5167E-07 AC-223 26.

338.32 2.6516E-07 TH-228 26.

84.37 2.0706E-06 PA-234 35.

131.20 1.0912E-07 TH-234 49.

63.29 1.9097E-06 U-235 41.

143.76 2.0224E-07 NP-239 25.

106.13 8.4008E-08 AM-241 31.

59.54 2.1796E-07

.g I

o TOTAL P.16

{

)3

oco*eneocooooo*****oe**eo*e**no******************************

ct00****o000***o*

16-MAR-94 07:40:43

- - - - o******

p y o o c u

w *- * * * * * *

o

o * * *, * *

w * * * *

n n * * * * * * ** * * * * * * * * * * * * *

DLANK DEMIN WATER 500t1L MARINELLI TO DETERMINE MDA'S SPECTRAL. FILE'NAME:

BKG9410. LAD SAMPLE DATE:

15-MAR-94 17:00:00 SAMPLE IDENTIFICATION:

BKG9410. LAB

-TYPE OF SAMPLE:

WATER SAMPLE QUANTITY:

500.0000 UNITG:

GRAM SAMPLE GEOMETRY:

MAR 500 EFFICIENCY FILE NAME:

MAR 50093.EFF

.********u****nu********u**o******on*w*nn*****+******

. ACQUIRE DATE: 15-MAR-94 17:14:32

FWHM(1332) 1.975 PRES 5ET TIME (LIVEi:

3600. SEC

5FNSITIVITY:

5.000 ELAPSED-REAL. TIME:

3600. SEC

SHAPE PARAMETER : 10.O %

ELAPSED LIVE TIME:

3600. SEC

NBR ITERATIONS:

10.

it

H * * > H + * * *

it * * *

k + * *

f * *

k

H *

u * *

H

M H

r e k t - +i k + * * *

k *

4 * *

+

DETECTOR: ADC Detector

LIBRARY: NJCL. LID CA_IB.DATE:

02-FEB-94 11:04:12 ENERCY TOLERANCE:

1.500 KEV

+

KEV / chill

.5012.713

HALF c.IFE RATIC:

5.00 UFFSCT:

.,74300t; <EV

/dsLNDANCE LINIT:

75.00%

+

+- H sr t * *

v * + k W

4 < % %- e + w

& e * + v k * +4 % + k w w ~

H +

9 + r + v t k + * + + it * * * + +- + %

ENERGY WINDOW

.24 TO 4105.26 PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT FW CTS /SEC % ERR FIT 1

0 238.SG 40.

22.

1.17 475.05 474 11 1.11E-02 26.E 2

0-371.14 9.

4.

1.02 741.96 740 5 2.51E-03 54,1 FEAK SEARCH CW1PLETED (REV 15 6 - ND FC VER5 Giv DE: SE)

PULSE-PILE-UP CORRECTED DATA. CORFECTION =

1.000 UNCORR. LIVE Tire:

3600. CDRREC TED LIVE tit"E:

3600.

Pi: IT ENERGY AREA BKGND FWHM LHANNEL LE.TT PW CTS /SEC XER;.

1 0

238,88 40.

22.

1.17 478.08 474 11 1.11E-02 26.6 2

0 371.14 9.

4.

1.02 741.96 74C 5 2.51E-03 54.1 T'ILE-UP CORRECTION COMPLETED 1

1

\\

7 I

l

!t NUCLIDE IDENTIFICATION SYSTEM AND PC VERSION DEC 88)

, NL'CLIDE LINE OCTIViT ( iiEPOR T

,FAGE 1

y ELAPSiID LIVE TIM ~:

'3 00.

(P!LE-UP CORRECTED) e l

' NATURAL PRODUCT UCI/

1-SIEMA NUCLIDE SDH9 ENERby-ARE:i BKGND 1.ABN

%5FF GRAM ERROR

.TH-232 NP 237,.03 4v.

22.

44 60+-

2.142E--OO 5.514E -8 1.'47EE -E 33:;.32 C.

O.

11.40 O.O)OE+00

.OOOE O

i 7;:7.17 O.

O.

11.50

_S.OOOE+00

.OOOE O

DE3,14 O.

O.

30.23 O.OOOE+00

.OOOE O

i 911.07 O.

O.

27.70 0.OOOE+00

.OOOE O

.000E O

V69.. I 1 0.

O.

16.60 0.OOOE+00

.OOOE O

.000E O

l 26L4.66 O.

O.

35.86 O.OOOE+00

.COCE O

.OOOE O

k.

i l

a 0

i a

4 5

i 4

1 l

4 4

4 e

e

s NUCLIDE IDENTIFICATION SYSTEM (ND PC VERSION.

DEC' 80)

-UNKNOWN LIFE REPORT PAGE 2

l h

ELAPSED LIVE TIME 3600. (PILE-LP CORRECTED)

UNIDENTIFIED PEAKS FK IT ENERGY A ~< E A Bef.GND FWHM CHANNEL LEFT FW CT5/5EC % ERR

%EFi' 1

0 238.88 40.

22.

1.17 47E.08 474 11 1.I1E-02 2.h.8 2.44E+04.'-

2-0 371.14 9.

4.

1.02 741.96

~74C 5 2.51E-03 G4.1 1.65E+>.0 LINES NOT MEETING

SUMMARY

CRITERIA PI: NUCL1DE ENERGY HLFE DECki

'JCI/ GRAM ABNDI F FAILED 1 TH-232-238.63 1.OOE+10Y

". 0GOE O

3.!!14E -8

25. ':>3%

4hd I

i 4

I I

I

-)

g,

NUCLIDE IDENTIFICATION SYSTEM (ND PC VERSION DEC 88) 1

SUMMARY

.0F'NUCLIDE ACTIVITY P. AGE. 3

]

., o

?

2 1

s TOTAL' LILIES IN SPECTRUM l

UNIDENTIFIED PEAKS 2'

IDENTIFIED IN

SUMMARY

REFORT O

.00%

i 4

i.

e i

i i

i e

1 I

i i

4 4

W 5

9 y

w

I%

MINIMUM DETECTABLE ACTIVITY. REPORT.

(ND PC VERbIO J AUG 89)

PEAK WIDTH =-

3.00 FWHM. CONFIDENCE LE /EL =

,.06.

MINIMUM NUCLIDE BMG ENERGY UCI/ GRAM BE-7

~7.

477.59

1. 3179E:-07 HNIL-511 33.

511.00 4.3240E-08 NA-22 1.

1274.54 1.33OUE-08 NA-24 1.

1368.53 1.4o63E-OL CL-38 4.

2167.51 O.OOOOE+00 AR-41 1.

1293.64

.8003E-C8 3

K-40 10.

1460.81 4.4537E-07 SC-46 8.

1120.51 3.3524E-05 CR-51 23, 320.C8 1.8554E-07 l'.N-34 7.

834.83 2.3911E-08 MN-56 8.

G46.'/5 3.2021E-OL FE-59 1.

1099.;2 2.0630E-08 CO-57 32.

122.06 1.3092E-OE CO -58 6.

610.76 2.1602E-OB CO-60 2.

1332.49

1. 9562E--08 NI-65 2.

1481.84 1.1235E-07 CU-64 1.

1345.90 1.9661E-oo

~N -oS 7.

1115.52 6.1533E--08 ZN-69M 7.

43ti. 63 1.3442E-05 AE-76 6.

559.10

3. 3494E-OE ad-7' 264.65

2. 7 0 78E--Of 19R-82 7.

554.32 2.2593E-t5 BR-84 2.

E81.50 8.5035Ew.8 KR-E,5 19.

513.99

5. 55 95E- 06 KR-BSM 38.

151.18 1.E837E-08 KR-87 17.

402.56 5.5823E-08 KR-88 29.

196.32 6.4667E-08 RB-88 1.

1836.02.

4.857EE-07 RD -89 5.

1031.Sa 3.1362E-07 SR-85 19.

513.99 2.4263E-Od SR-05M 33.

231.69 3.1400E-Xa SR-91 6.

1024.30 8.7054E-08 SR-92 4.

1383.94 3.8455E-06 Y-88 1.

1836.01 1.8586E-03 Y-91 2.

1204.90 5.9593E-06 N-91HD 8.

555.57 1.8701E-08

(-92 5.

734.46 1.8SOGE-07 Y-93 21.

266.90 2.2801E-07 ZR-95 8.

756.72 4.1756E-OE 2R-97 9.

743,36 2.6'09E-OD ND-94 3.

702.63 1.3082E-OE ND-95 7.

765.79 2.192SE-Ob NB-97D 6.

1C24,50 2.5596E-06 MD-90 26.

257.34 2.2740E-03 MO-99 6.

739.58 1.5370E-07 TC-99MD 33.

140.51 1.2120E-08 RU-103 9.

497.08 1.8096E-OS RU-105 8.

724.50 5.0555E-08 RU-106 11.

621.84 2.2597E-07 s

RH-105 16.

318.90 8.OO94E-08

_L,,

t PAGE 2

FEAK WIDTH =

3.00 FWHM. CONFfDENCE LEVEL =

4.66.

MINIMUM NUCLIDE DKG ENERGY UCI/ GRAM AG-110M 657.75 1.4952E-08 CD-109 4v.

88.03 4.0260E-07 SN-113 10.

391.69 2.1337E-08 55-122 4.

36~s. 92

1. '7267E-08 5B 124 7.

602.71 1.7505E-OE 58-125 15.

427.89 6.2205E-08 TE-123M 33.

158.99 1.4727E-08 TE-132 24.

228.16 1.6272E-08 I-131 17.

364.48 2.1215E-08 I-132 c.

6o7.69 2.2236E-03 1-133 7.

529.87 1.7855E-08 I-134 8.

847.03 4.8910E-08 I-135 5.

1260.41 1.1121E-07 XE-131M 43.

163.93 7.4371E-07 XE-133 43.

80.99 4.7264E-08 XE-133M 32.

233.22

1. 634'7E-07 XE-135 26.

249,,7?

1.8586E-08 XE-135M 7.

526.56 1.3764E-07 XE-138 20.

258.31 4.OO98E-07 C3-134 7.

604.70 1.7606E-OS CS-13411 32.

127.42 1.0232F '37 CS-136 2.

818.50 1.2575E-08 CG-137 8.

661.e5 2.3587E-08 C5-138 3.

1435.86 8.7601E-08 D4-133 13.

356.00 2.4552E-08 BA-139 36.

165.85 1.1483E-07 BA-140 6.

537.32 5.6523E-OU BA-141 20.

190.22 1.2553E-07 LA-140 O.

1 :~96. 4"/

O.^OOE+00 CE-139 36.

165.b5 1.o760E-08 CE-141 24.

145.44 2.01622-38 CE-143 181 293.2d 3.6241E-C8 CE-144 32.

133.54 1.0152E-u7 ND-147 50.

92.1.

5.7877E-OS EU-152 18.

344.27 6.4203E-08 EU-154 1.

1274.45

3. 7438E--OS HF-181 12.

482.03 2.1886E-08 W-187 8.

4 7 9. CJ 6.4299E-OE HG-203 17.

279.19 1.8075E-08 R(&-226 13.

609.31 3.0959E-08 TH-232 59, 238.63 5.1584E-08 U-235 39.

185.7'.

2.8778E-08 U-238 42.

131.20 6.1682E-08 NP-239 32.

106. 3 5.2079E-08 AN-241 41.

59.54 9.5008E-08 e

4 m

p ar lb Table 1 Fermi 2 Nuclear Station Confirmatory Measurements SAMPLE NUCLIDE NRC VAL.8 NRC ERR.* LIC. VAL.* LIC. ERR.8 RATIO

RES*

RESULT

CST HN-54 5.63E-07 4.00E-08 6.57E-07 4.70E-07 1.17 14.1 Agreement TANK C0-58 9.37E-08 2.26E-08 9.19E-08 2.29E-08 0.98 4.2 Agreement 4/15/94 CO-60 4.15E-07 4.14E-08 5.71E-07 5.03E-08 1.38 10.0 Agreement ZN-65 1.69E-07 4.18E-08

< MDA*

4.0 No Comparison Sb-125 2.02E-07 6.33E-08 2.14E-07 7.49E-08 1.06 3.2 Agreement CS-134 1.54E-07 3.17E-08 1.62E-07 3.84E-08 1.05 4.9 Agreement CS-137 1.80E-07 3.16E-08 1.93E-07 3.23E-08 1.07 5.7 Agreement 8

These quantities are in the units of microcurie per milliliter.

Ratio - Licensee Value / NRC Value Resolution - NRC Value / NRC Error (one standard deviation)

Result : The result of the comparison is based on the criteria in Attachment I and is expressed by the following Agreement

- Criteria Relaxed Disagreement No Comparison MDA - Minimum Detectable Activity 0

b

M

-_ d 4,-

S t uMS

" - - - ^

- -^

.? ~

Table 2

(

Fermi 2 CST Discharge Activity Calculation (April 15-17, 1994, Discharge)

Date of analysis:

April 15, 1994 Volume (gallons) -

558360 (liters)= 2.114E+06 Flow Rates:

(gallons per minute)

Dilution-15600 CST dchg=

400 Isotope EC' Result' Conc./EC*

Activity i

uCi/ml uCi/ml (mC1) i Mn-54 3.000E-05 5.635E-07 4.696E-04 1.191E+00 Co-58 2.000E-05 9.372E-08 1.171E-04 1.981E-01 Co-60 3.000E-06 4.146E-07 3.455E-03 8.763E-01 Zn-65 5.000E-06 1.687E-07 8.435E-04 3.566E-01 Sb-125 3.000E-05 2.020E-07 1.683E-04 4.270E-01

(

Cs-134 9.000E-07 1.541E-07 4.281E-03 3.257E-01 1

Cs-137 1.000E-06 1.795E-07 4.488E-03 3.794E-01

~-

H-3 1.000E-03 3.260E-04 8.150E-03 6.890E+02 Totals' 3.278E-04 6.928E+02 (w/ Dilution)'

8.194E-06 2.197E-02 1

8 Effluent concentrations for release to unrestricted areas as listed in 10 CFR 20, Appendix B, Table 2, Column 2.

Result of gamma isotopic and tritium analyses of Condensate Storage Tank performed in NRC Region III Laboratory.

' Fraction of 10 CFR 20 effluent concentrations. This fraction is calculated as the concentration of effluent as it enters the lake, including the dilution flow.

1

Total, undiluted activity from condensate storage tank.

l

Totals with dilution credit from recirculation water.

_--a_

4 --

4

T 3

d' ANNUAL ADULT TOTAL DOSE RECEIVED PER ORGAN (mrem)

,.(

Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Mn-54 3.06E-04 5.83E-05 9.10E-05 9.37E-04 Co-58 1.08E-06 2.41E-06 2.18E-05 Co-60 1.37E-05 3.02E-05 2.57E-04 Zn-65 4.83E-04 1.54E-03 6.94E-04 1.03E-03 9.67E-04 Cs-134 5.66E-03 1.35E-02 1.10E-02 4.36E-03 1.45E-03 2.36E-04 Cs-137 8.45E-03 1.16E-02 7.57E-03 3.93E-03 1.30E-03 2.24E-04 l

H-3 3.19E-05 3.19E-05 3.19E-05 3.19E-05 3.19E-05 3.19E-05 TOTALS 1.46E-02 2.69E-02 1.94E-02 3.19E-05 9.44E-03 2.78E-03 2.67E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli l

ANNUAL TEEN TOTAL DOSE RECEIVED PER ORGAN (mrem)

Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli l

Mn-54 3.01E-04 5.96E-05 8.97E-05 6.17E-04 Co-58 1.07E-06 2.46E-06 1.47E-05 Co-60 1.36E-05 3.07E-05 1.78E-04 Zn-65 4.38E-04 1.52E-03 7.09E-04 9.72E-04 6.43E-04 4

Cs-134 5.81E-03 1.37E-02 6.34E-03 4.34E-03 1.66E-03 1.70E-04 Cs-137 9.05E-03 1.20E-02 4.19E-03 4.10E-03 1.59E-03 1.71E-04 s

H-3 2.31E-05 2.31E-05 2.31E-05 2.31E-05 2.31E-05 2.31E-05 TOTALS 1.53E-02 2.76E-02 1.14E-02 2.31E-05 9.53E-03 3.27E-03 1.82E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli o

l

o,

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j ANNUAL CHILD TOTAL DOSE RECEIVED PER ORGAN

(

(mrem)

Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Mn-54 2.37E-04 6.30E-05 6.64E-05 1.99E-04

.Co-58 8.97E-07 2.74E-06 5.23E-06 i

Co-60 1.17E-05 3.44E-05 6.46E-05 Zn-65 4.49E-04 1.20E-03 7.45E-04 7.54E-04 2.10E-04 Cs-134 7.01E-03 1.15E-02 2.43E-03 3.57E-03 1.28E-03 6.20E-05 I-Cs-137 1.14E-02 1.09E-02 1.61E-03 3.56E-03 1.28E-03 6.84E-05 H-3 3.66E-05 3.66E-05 3.66E-05 3.66E-05 3.66E-05 3.66E-05 4

i TOTALS 1.89E-02 2.39E-02 4.92E-03 3.66E-05 7.98E-03 2.60E-03 6.46E-04 j

Bone Liver T. Body Thyroid Kidney Lung Gi-Lli i

l TOTAL DOSE

SUMMARY

REPORT j

(mrem)

Group Organ Total

_______==.

j j

Adult Bone 1.46E-02 i

Adult Liver 2.69E-02 l

Adult Tot Body 1.94E-02 i

G' Adult Thyroid 3.19E-05 Adult Kidney 9.44E-03 i

Adult Lung 2.78E-03 Adult Gi-Lli 2.67E-03 Teen Bone 1.53E-02 Teen Liver 2.76E-02 Teen Tot Body 1.14E-02 Teen Thyroid 2.31E-05 Teen Kidney 9.53E-03 i:

Teen Lung 3.27E-03 Teen Gi-Lli 1.82E-03 l

Child Bone 1.89E-02 Child Liver 2.39E-02 Child Tot Body 4.92E-03 1

Child Thyroid 3.66E-05 i

Child Kidney 7.98E-03 Child Lung 2.60E-03 Child Gi-Lli 6.46E-04 ORGAN WITH MAXIMUM DOSE Group Organ Total Teen Liver 2.76E-02

(

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CALCULATES THE D0SE DUE TO NUCLEAR POWER PLANT LIQUID RADIOACTIVE EFFLUENTS (s...

1 U.

S.

NUCLEAR REGULATORY COHHISSION PCD0SE AAAAAAAAAAA LIQUID DOSE CALCULATIONS from NUCLEAR POWER PLANT EFFLUENTS 1

Rev. 34 08/20/91 18-Apr-94 4

\\

J FILENAME ????????.WK1 PLANT NAME Apr-94

(

18-Apr INDIVIDUAL MAXIHUH 09:56 AM Dilution Radioactive Release ENTER PLANT SPECIFIC DATA WHEN COMPLETED====>

Press ALT E FRESH WATER Flow Rate

= 4.00E+02 g/ min Flow Rate 1.56E+04 g/ min Flow Time

= 2.40E+01 hr

=

Average Flow During Report Period Report Period = 1.20E+01 mth Individual Average Consumption (kg/y)

Transit Times (hrs)

Drinking Water 0.01

=

Pathways Adult Teen Child Fish / Invertebrates 0.01

=

Water 730 510 510 SportFish 21 16 6.9 Comments:

i J

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FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL MAXIHUH 09:56 AM i

ENTER RADIOACTIVITY RELEASED FOR BACH RADIONUCLIDE Nuclide uci/ml WHEN COMPLETED====>

Press ALT J Hn-54 5.63E-07 Co-58 9.37E-08 Co-60 4.15E-07 Zn-65 1.69E-07 Cs-134 1.54E-07 Cs-137 1.80E-07 H-3 3.26E-04

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WHEN COMPLETED====>

Press ALT J ADDITIONAL DILUTION FACTORS Food Consumption Products:

1. Potable Water Near Field

====>

Dw 7.70E+01

=

2.

Sport Fish

====>

Dsf 5.00E+00

=

3.

Sport Invert

====>

Dai 5.00E+00

=

4. Commercial Fish

====>

Def 5.00E+00

=

5.

Commercial Invert

====>

Dci 5.00E+00

=

v en - -

1 FILENAHE ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL HAXIHUH 09:56 AH ADULT TOTAL DOSE RECEIVED PER ORGAN mrem /

12.00 mth Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Hn-54 3.06E-04 5.83E-05 9.10E-05 9.37E-04 Co-58 1.08E-06 2.41E-06 2.18E-05 Co-60 1.37E-05 3.02E-05 2.57E-04 Zn-65 4.83E-04 1.54E-03 6.94E-04 1.03E-03 9.67E-04 Cs-134 5.66E-03 1.35E-02 1.10E-02 4.36E-03 1.45E-03 2.36E-04 Cs-137 8.45E-03 1.16E-02 7.57E-03 3.93E-03 1.30E-03 2.24E-04 H-3 3.19E-05 3.19E-05 3.19E-05 3.19E-05 3.19E-05 3.19E-05 TOTALS 1.46E-02 2.69E-02 1.94E-02 3.19E-05 9.44E-03 2.78E-03 2.67E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli e

l FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL MAXIHUH 09:56 AH i

l TEEN TOTAL DOSE RECEIVED PER ORGAN l

mrem /

12.00 mth l

Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli l

Hn-54 3.01E-04 5.96E-05 8.97E-05 6.17E-04 I

Co-58 1.07E-06 2.46E-06 1.47E-05 Co-60 1.36E-05 3.07E-05 1.78E-04 Zn-65 4.38E-04 1.52E-03 7.09E-04 9.72E-04 6.43E-04 Cs-134 5.81E-03 1.37E-02 6.34E-03 4.34E-03 1.66E-03 1.70E-04 Cs-137 9.05E-03 1.20E-02 4.19E-03 4.10E-03 1.59E-03 1.71E-04 H-3 2.31E-05 2.31E-05 2.31E-05 2.31E-05 2.31E-05 2.31E-05 l

l l

2e l

l l

I l

l l

l TOTALS 1.53E-02 2.76E-02 1.14E-02 2.31E-05 9.53E-03 3.27E-03 1.82E-03 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli l

l 1

l l

l g

0 4

FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL HAXIHUH 09:56 AH CHILD TOTAL DOSE RECEIVED PER ORGAN mrem /

12.00 mth Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Hn-54 2.37E-04 6.308-05 6.64E-05 1.99E-04 Co-58 8.97E-07 2.74E-06 5.23E-06 Co-60 1.17E-05 3.44E-05 6.46E-05 Zn-65 4.49E-04 1.20E-03 7.45E-04 7.54E-04 2.10E-04 Cs-134 7.01E-03 1.15E-02 2.43E-03 3.57E-03 1.28E-03 6.20E-05 Cs-137 1.14E-02 1.09E-02 1.61E-03 3.56E-03 1.28E-03 6.84E-05 H-3 3.66E-05 3.66E-05 3.66E-05 3.66E-05 3.66E-05 3.665-05 TOTALS 1.89E-02 2.39E-02 4.923-03 3.66E-05 7.98E-03 2.60E-03 6.46E-04 Bone Liver T. Body Thyroid Kidney Lung Gi-Lli w

9

r._

FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL HAXIHUH 09:56 AH TOTAL DOSE

SUMMARY

REPORT 1.20E+01 ath Group Organ Total Adult Bone 1.46E-02 Adult Liver 2.69E-02 Adult Tot Body 1.94E-02 Adult Thyroid 3.19E-05 Adult Kidney 9.44E-03 Adult Lung 2.78E-03 Adult Gi-L11 2.67E-03 Teen Bone 1.53E-02 Teen Liver 2.76E-02 Teen Tot Body 1.14E-02 Teen Thyroid 2.31E-05 Teen Kidney 9.53E-03 Teen Lung 3.27E-03 Teen Gi-Lli 1.82E-03 child Bone 1.89E-02 child Liver 2.39E-02 Child Tot Body 4.92E-03 Child Thyroid 3.66E-05 Child Kidney 7.98E-03 Child Lung 2.60E-03 child Gi-Lli 6.46E-04 n.

1.20E+01 mth ORGAN WITH MAXIHUM DOSE Group Organ Total Teen Liver 2.76E-02 w

O

A FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL HAXIHUH 09:56 AH 6.00E+03 Bioaccumulation Bioaccumulation Bioaccumulation Half Life---SALT WATER---

---FRESH WATER--- ---FRESH WATER---

(hrs)

Fish Invert Fish Invert Fish Invert Nuclide 7.49E+03 5.50E+02 4.00E+02 4.00E+02 9.00E+04 4.00E+02 9.00E+04 Hn-54 1.70E+03 1.00E+02 1.00E+03 5.00E+01 2.00E+02 5.00E+01 2.00E+02 Co-58 4.62E+04 1.00E+02 1.00E+03 5.00E+01 2.00E+02 5.00E+01 2.00E+02 Co-60 5.85E+03 2.00E+03 5.00E+04 2.00E+03 1.00E+04 2.00E+03 1.00E+04 Zn-65 1.81E+04 4.00E+01 2.50E+01 2.00E+03 1.00E+03 2.00E+03 1.00E+03 Cs-134 2.64E+05 4.00E+01 2.50E+01 2.00E+03 1.00E+03 2.00E+03 1.00E+03 Cs-137 1.08E+05 9.00E-01 9.30E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 H-3 1

1 1

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1 1

1 We

FILENAME ????????.WK1 PLANT NAME Apr-94 18-Apr INDIVIDUAL HAXIHUH 09:56 AH

(

Adult Dose Factors (arem/pC1)

Select Position and Press ENTER Nuclide Bone Liver T. Body Thyroid Kidney Lung Gi-Lli' Hn-54 4.57E-06 8.72E-07 1.36E-06 1.40E-05 Co-58 7.45E-07 1.67E-06 1.51E-05 Co-60 2.14E-06 4.72E-06 4.02E-05 Zn-65 4.84E-06 1.54E-05 6.96E-06 1.03E-05 9.70E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 4.79E-05 1.59E-05 2.59E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 3.70E-05 1.23E-05 2.11E-06 H-3 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07

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SUMf1ARY OF NUCLIDE ACTIVITY l'ACC 3

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765.79 3.70662-b ND-97D 18.

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257.34 5.6129E-37 9 9 23, 739.5E 3.781cE-07 TC-99hD 86.

140.51

2. 4 587E -03 RU-103 34.

497.06 3.6041E-06 RU-105 29.

724.50 2.5354E-06 RU-106 44.'

621.84 4.5680E-U7 4

4 1.05 56.

318.90 2.2775E-07 110M 30.

657.75 4.1418E-08 C -109 90.

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s

15 Aor 94 18:48 Pace #1 Protocol #:12 H-3 DPH User : ANDRE /GLINSKI I

Tite:

10.00 Data Hode: DPH Nuclide: 3H-UGXR Quench Set: 3H-UGXR tma Coincidence On

\\.

akground Subtract: 1st Vial LL UL LCR 2S%

BKG Region A:

0.0 - 18.6 0

0.5 11.10 Region B:

2.0 - 18.6 0

0.5 10.80 Region C:

0.0 -

0.0 0

0.5 0.00 1

Qucnch Indicator: tSIE/AEC Ext Std Terminator: Count EPA.INTERCOMPARISON SAMPLE 94-200 Luminescence Correction On S#

T1HE CPHA A:2S%

CPMB B:2S%

DPH1 tSIE 1

10.00 11.10 18.98 10.80 19.16 282.18 2

10.00 2016.50 1.43 1974.70

1. 44 7113. 89 252.46 SA - L4 3 3

10.00 2002.50 1.44 1961.70

1. 4 5 7008. 57 254. 51 %4- ;D f'/

4 2.64 61799.5 0.50 60312.7 0.50 205679 268.26 i

d i

4 S

f l

l

TD.-

917005151259 P.01 APR-15-1994 04135PM FROM RP tGT* ENGR *Eff.IR*SP

,%g.

l9 4

j CA1A:UA.ntuMWilIM*dAICflun 5esq-9 cBr3

)

Type of Sample:

CST 5

n wm?!.se,.,yri:i.eiEih=.-~.s.m,=r ~..:w.=~e-- --5-4 c.m=. =.,-.we.:=m=Lx::iiii.

u~...

a_=m

~_.:n~

nn~,,.a,wa,,...;.

gyc_-

_ _=_.~_, r_7- - w

-::=.:_~::::::

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w., a

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.=;,

~

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mc _ = ~--

m-----~-~-~

re:= -:---

1.

Ma54 6.97B 07 3.005 04 2.32E43 i

2.

Co-58 5.47E46 2.00E 04 2.74E44 3,

ca.do 5.28B47 3.00E-05 1.76E42 4.

Co 134 2.62547 9.00E-06 2.91E42 5.

Co137 7 12 & o7 1.00505 2.12B42 6.

1.

5.

9.

10.

11.

12.

13.

14.

3 15.

16.

17.

18.

19.

20.

21.

22.

23.

24, 25.

26, 27, 28.

29.

30.

31.

32.

33.

34.

35.

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t.,

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A Bquivalentto62.000.120 Am2 F1/1 U10394 DCT: V88URV Files 1202 e

4 e

m

APR-15-1994 04:36PM FROM RP MGT* ENGR 4ENVR*SP TO 917085151259 P.03 T

CAI.4ULATION OF MFC FRAC 110N Relesso Permit No.

94 cst 3

(.6N pg y

(

Type of Sample.

CST

,..,....c.w ::=:c_:r=_r,,3w.:=:::::=e _rf=_=..=r :t:::n-m rz:==w~~.r==_:::=:r_h==t:r rn=:=w.:h sE3p=a:::w.:=c E4

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r ~

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M

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s.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18, 19, 20.

21.

22.

23.

24.

25.

26.

27, 28.

29.

30.

31.

32.

33.

34.

35.

rtrauni::

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~

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T'O 917085151259

.P.04 LAPR-15-1994 04:37PM.' FROM RP NGT* ENGR *ENVR*SP CIRCULATING WATER DECANT MONITOR SETPOINT COMPARI8(Mi ReimasePamt A 94C873

' i.

1. Esemated Circuleung Water Decant Monllor elarm (high high) setpoint beoed on nucikle inix of botch b be seisesed =

(cr.5t cone (au ?) x o.098 x 2.7E+6) + (Total cono emospt Cr-61 x 2.7Ed)

CareWater

--- + DecantMonnor

=

MPCF(Att2)x2 reading (Att 1)

l.

'i.

~(

UCl/cc x 0.098 x 2.70E+08) + (

1.7WE 06 uCtrni x 2.70e+0e) +

170 cpm 7.06EM X 2 4

= 3.63E+03 cpm 4

2. Instelled Cligvisung Waler Decant Monlior alunn (high high) setpoint a

1(00 cpm i

}

3.Setpointchange required?

YES X

NO h4 Perbrmed by: Y YO

/ signature / OW L

W %. -A A d i h t/

n *wed e Signature T Dets '

[

(CSTonly) [ ] NA Reviewed by:

I DsAs /

j 4

l s

I

]

Equivalentt62.000.120 AltsPiti 010394 DCT:VSSURV pte:1202 j

i i

4..

-~

APR-15-1994 04:37Pri FROM RP t1GTcEM3R:ENVR*SP TO 917085151259 P.05 CALCULATION OF DISCHAR'IE MONITOR RELEASE RATE AND SETP:OINT.

CIRCULATING WATER NOT CONTAMINATED Release Permit No.

94 CST 3 BF = 0.1 H3MPCF = 0.13 H3F - 0.00

1. Maximum CWD flow rate (Att 1) x 0.5 1.SoE+04 gpm x 0.5 l

= 3.76E+04 gpm

=

Anowable

=

Release

((MPCF(A112)x (1 + BF)) + H3MPCF) (( 7.05E-02 x (1 + 0.1)) + 1.3E-1]

Rate

2. Determine 00n of " Estimated release rate" (for use in Part 3 and 4 below):

a)If rnaximum allowable release rate is greater than or equal to maximum release tank discharge fbw rate, estimated release roto equals rnaximum release tank discharge low rate (from Att t.

Part4),

b)If maximum allowable release rate is less than maximum release tank discharge flow rate, ewmoted release rate equalc maximum allowable release rate.

Estimeled release rate x [MPCF x (1 + BF) + H3MPCF) at discherpe point CWDilow rate j

4.00E+02 gprn x ( 7.06E-02 x (1 + 0.1) + 1.3E-1 ]

=

5.32E-03

=

1.56E+04 gpm M

Totalconc SensitMty CWD flow rate Discharge 4.

Discharge (A212) x (Att 1) x (An 1 Part 3) x H3F Monitor

+

Background

Monitor Setpoint = -

MPCF Esthneted release rate Reading (Att 2) x (Att4 Part2) x (1 + BF)

(Att 1 Parti) cpm 1.75E-06 uCt/co x 1.60E+07 /(ucitoc) x 1.50E+04 gpm x 0.99 7.05E-02 x

4.00E+02 gpm x

(1+0.1) 1.43E+04 cpm

=

b / N Y Performed Date Reviewed by h&

Date W(NQ

/h

__ (CST only) [ ] NA l

Date Raylewed by a

1 J

Equivalent tu 02.000.120 AS4 P1/1 010304 DCT:VSSt1RV File:1202 g.

'""'N' M

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e

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44 ReE*e.

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' Mdessendage $sResr$

HHiHUimib1H!Wii

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58:88 13eE44 7.2tE44 4.EE44 j

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r

APR-15-1994 04I39PN FROM RP NGT* ENGR *ENVR*SP ic 917005151259 P.07 Pago :

2 82plo ID : OMO

-k.94 Acquicition deco a 15-ADR-1994 09s19:33 o

QUQN**************M***********e***********M**N=xxxxN***M*********************

Fermi 2 Radiation Protection Damma Speretroscopy Report c*o************************** Sample parameters

- - - - =xxxxx***********

Senple ID Numbers nuo --E94 Sanple collection start date: 15-APR-1994 07:37:00.00 ff Sc ple collection end date

15-APR-1994 07:37:00.00 Type of sample 1 Liter Nartnell I

Scaple quantity :

1.00000E+03 ml Staple geometry :

M1LL Uperator: TLR con *********************** Acquisition Parameters *************************xx Dstector number DET1 Acquire date :

15-APR-1994 09:19:33.32 Proset live time 0 00:30:00.00 Elapsed live time :

O 00:38:28.00 Elopsed real time :

0 00:33:00.36 percent dead time :

0.00 %

ocu**********4************

Calibration Parameters ***************************

Datector number :

DET1 Yearly cal date :

2-NAR-1994 13:47:46.JJ Kev / channel 5.00200E-01 Zero offset:

2.18052E-02 Dcily cal date

15-APR-1994 08:14:24.90 occ*********************** Peak Search Parameters ***************************

Start channat 100 End channel : 4096 Hsight sensitivity :

5.00000 Shape sensitivity : 10.00000 Maximum number of itarations to resolve multiplets : 5 on#******************

Nuclide identification Parameters *********************

Enargy tolerance : 1.25000 Half-life ratio : 10.00000 4

Abundance limit e 75.00000 LihvAry a dacmaster.n1b Efficiency file : EFFD1_ mill Efficiencies at : Peak energy

-one*****xxxxx*n**************************************************************

j Pk It Energy Area Bkgnd FWHM Channel Left Pw Cts /See WErr Fit 1

0 428.28 40 35 0.99 856.18 850 15 2.22E-02 35.5 2

0 665.43 74 49 1.70 1210.38 1282 14 4.10E-02 23.8 3

0 661.82 71 17 1.83 1323.08 1314 13 3.94E-02 16.7 4

W 796.06 61 16 1.00 1501.46 1584 13 4.47E-02 15.2 5

0 810.29 32 7

0.99 1619.91 1613 14 1.78E-02 24.9 6

0 834.74 2e3 8

2.39 1668.79 1GGi 14 1.24C-01

7. 2 7

0 1172.85 144 4

2.85 2344.75 2336 17 7.99E-02 9.0 8

0 1331.89 129 0

3.36 E66e.71 e60s is 7.17c 02 4

A p

..[.

iZ r

APR-15-1994 04:39PN FROM RP MGT* ENGR *ENUR*SP TO 917085151259 P.00 CCCCCOCD2CCCCGCOCCDCOCOMQ3CCCMOc32CMGM2COMMM9804400CCQQhMOc#OOOMOO##HAuceCHuuendu O

D3trcit Edicon Foral E Pock Raporta, Genovated 15-ADR-3494 09:49 48.19 j

c o m u n

w w * * * *

w w u n * * *

w a *

w m * *

n o m *

w n * * *

w w * * *

w u n *

w w w * *

w w w w'* *

w w w * * * *

w

I oSScmple 10 : 0330 -E94 o D: cay Time =

0 81:42:33.32 Deposition Tirne = 00:00:00.00 l

Psot-HID Peak Search Report It Energy Area Bkgnd FWHM Channel Left Pw WErr Fit Nuclides O

428.28 40 35 0.99 856.18 850 15 35.5

.fI-/7J~

O 605.45 74 49 1./6 181a.38 12ee 14 e3.0 CE-134 0

661.82 71 17 1.83 1323.08 1314 13 16.7 CS-137 0

796.06 81 16 1.82 10'91.46 1584 13 10.2 CD -134 0

810.29 32 7

0.99 1619.91 1613 14 24.9 CO-58 0

834.74 223 8

2.39 1668.79 1661 14 7.a MH-54 O

1172.85 144 4

2.85 2344.75 2336 17

9. 0 CD-60 0

1331.89 129 0

3.30 2662.71 2655 1d

.B. 8 CO-60

)-.

J 1

e 5

t e

0 4

I 4

1

'O APR-15-1994 04:40PM FROM RP MGT* ENGR *O W SP T

917085131259 P.09 p

Curocry of Huelido Activity Pago a E

15-QDR-1994 C9319:33 SCOplo ip : DM7_-E34 Acquioition dato Total number of lines in spwetrur 8

Hunt;er of unidentified lines 0

Humber of lines tentatively identirAwd by HID o

les. sex Huclide Type : activation Uncorrected Decay Curi-Decer Corr 1-91gma Hualide H11fe Decay uCi/ml uti/ml 1-Sigma Error

% Error Flags NN-54 312.70D 1.00 6.568L-u/

6.565E-07 0.470E-07 7.16 CD-58 70.80D 1.00 9.178E-08 9.185E-08 2.287E-08 24.90 CD-60 5.27Y 1.00 5.714E-07 b.714E-87 0.593E-07 0.80 A

CS-134 2.96Y 1.00 1.615E-97 1.615E-87 9.384E-07 23.76 Tobal Activity :

1.481E-06 1.4SEE-06 Nuclide Type fission Uncorrected Decay Corr Decay Cerv 1-Sigma Nuclide Hlife Decay uCi/ml uC1/ml 1-Sigma Error XError Flagw CS-137 3A.17Y 1.90 1.928E-07 1.928E-07 0.323E-07 16.73 Total Antivity a 1.928E-07 1.928E-07 Grand Total Activity 1.674E-06 1.675E-06 Flogs:

"K" = Keyline not found "M" = Nanually accepted "E" - Manually edited "A" = Nuclide specific abn. limit 56-I25~

2. I% E-7 Qd 1,29124 9

E t

t t

+

s

+ - - -

APR-15-1994 04340PM FROM RP t0T* ENGR *ENUR*SP TO 917085151259 P.10 yage a n

$fE[

[33o.gg4 Acquisition data 8 15-APR-1994 09819833 p

p Nalf-Life 1-Sigma Nuclide Half-life Ratio Energy %Abund Activity

% Error Rejected by Abun.

BR-82 35.30N 0.06 221.45 2.26 --- Not Found 554.32 70.60 --- Not Found ---

606.30 1.17 1.400E-05 23.76 619.07 43.10 --- Not Found ---

698.33 28.20 --- Not Found ---

776.49* 83.31 --- Hot Found ---

827.81 24.20 --- Not Found 1007.57 1.27 --- Not Found ---

1043.97 27.30 --- Not Found ---

1317.47 26.90 --- Not Found ---

1474.82 16.58 --- Not Found ---

% Abundances Found =

0.36 BR-84 31.80M 3.70 604.80 1.80 1.116E-04 23.76 Abun.

736.50 1.31 --- Not Found ---

802.20 6.10 --- Hot Found ---

881.50* 42.00 --- Not Found 1915.90 6.20 --- Not Found 1213.30 2.60 --- Not Found ---

1463.80 2.00 --- Hot Found 1741.20 1.60 --- Not Found ---

1877.50 1.14 --- Not Found ---

1897.30 14.90 --- Not Found ---

2029.60 2.10 --- Not Found ---

% Abundances Found =

2.20 Abun.

KR-88 2.84H 0.69 165.98 3.10 --- Not Found 196.32* 26.00 --- Not Found ---

ll 362.23 2.25 --- Not Found ---

834.83 13.00 8.144E-06 7.16 985.78 1.31 --- Not Found 1141.33 1.28 --- Not Found ---

1179.51 1.00 --- Not Found ---

1250.67 1.12 --- Not Found ---

1369.50 1.48 --- Not Found ---

1518.39 2.15 --- Not Found ---

1529.77 10.90 --- Not Found ---

4 2029.84 4.53 --- Not Found ---

2035.41 3.74 --- Not Found ---

% Abundances Found =

18.09 Abun.

SB-125 2.77Y 0.00 176.33 6.89 --- Not Found 380.44 1.50 --- Not Found ---

427.89* 29.33 2.143E-07 35.49 463.38 10.35 2--

Not Found ---

600.56 17.80 --- Not Found ---

606.64 5.02 3.140E-06 23.76

--er

.~.

u.x r....a Abundance limit 75.00000 Library : dacmaster. nib Efficioney file : EFFD1_m111 Efficiencies at : Peak energy

.s oc***************************************************************************

s Pk It Energy Area Bkgnd FWHM Channel Left Pw Cts / Soc KErr Fit 1

0 605.05 119 22 2.27 1209.58 1204 12 6.64E-02 12.2 2

0 661.44 78 14 1.51 1322.33 1317 le 4.34E-02 14.6 3

8 795.67 103 4

2.30 1590.69 1582 16 5.74E-02 10.7 4

R 411.96 19 20 1.04 1623.25 1614 14 1.06E-02 55.7

'4w.4 E**? ?d *

P***

e 4.

W c11. w n

uw A.o*

4.co. w 5 0 034.66 237 14 2.25 1668.63 1659 *19 1.32E-01

7. *,;

4 0

1173.24 102 22 1.96 2345.52 2339 13 6.79E-02 12.1 7

0 1332.01 119 5

3.14 2662.97 2653 18 6.6EE-02 10.1

,u i.

i 4

9 4

I 9

=

6 1

i 4

4 f

.; g------

-'o APR-15-1994 04:41PM-FROM RP MGT* ENGR *ENUR*SP TO, 917085151259 P.12 anE*= coma nnuocom u na n a n oacun o *

a nnoaa m ounn anscue *u *nnana mun wonones cun n un maa nnenna O

Detroit Edisen Ferai E Padh Report, Donsvated 15-APR-19,9,4 19:42:59.6G e

1 000************************************************p****************************

O 9 ample ID : 03Ju-94 O Decay Time =

0 08:28:14.98 Deposition Time = 00:00:00.00 Pact-HID Peak Search Report It Energy Area Bkgnd FWHM Channel Left Pw XErr Fit Nuclides 0

605.05 119 22 2.27 1209.58 1204

.a 12.2 CS-134 0

661.44 78 14 1.51 132E.33 1317 10 14.6 C8-137 0

795.67 103 4

2.30 1590.69 1582 16 10.7 CS-134 9.

811.96 19 20 1.04 1623.25 1614 14 bd. /

co-56 0

834.66 237 14 2.25 1668.63 1659 19 7.5 MN-54 0

1173.24 122 22 1.96 2345.52 2339 13 12.1 U0-60 0

1332.01 119 5

3.14 2662.97 2653 18 10.1 CO-60 I

4 4

9 i

g d

6 a

4 6

a 9

'~~~*m m

APR-15-1994 '04:42PM FROM RP NGT* ENGR *ENVR*SP TO 917005151259

.P.13 Pogo 3

o.

Sumecry of Huelido Activity Acquieition dato a 15-APR-1994 10:08:14 C Ople ID r t!JJO-94 1-7 Tcrtal number ot lines in spect,vum B

Nunber of unidentified' lines Hunber of lines tentatsvely identified by HID 7

ise. sex Nuclide Type : activation Uncorrected Decay Curr Decay Coff 1-Sigma.

Huclide Hlife Decay (uCi) tuCi) 1-Sigma Error XError Flags MH-54 312.7BD 1.00 6.97eh-u7 6.373E-e7 e.525c 07 7.53 CO-58 70.80D 1.00 5.46&E-08 5.470E-08 3.049E-08 55.75 CD-60 5.27Y 1.00 5.277E-07 b.277E-07 e.33EE-e7 10.98 A

CS-134 2.06Y 1.00 2.616E-07 2.616E-07 0.320E-07 12.21 Total Activity :

1.541E-06 1.541E-06

. Huelide Type s fission Uncorrected Decay Corr Decay Corv 1-Sigma Huclide Hlife Decay (uCi)

(uC1) 1-Sigma' Error MError Flags CS-137 3R.17Y l'.00 2.123E-07 2.123E-07 0.309E-07 14.57 Total Activity a 2.123E-07 2.123E-07

' Grand Total Activity :

1.754E-06 1.754E-06 Fisgs:

"K" = Keyline not found "N" = Nanually accepted "E" - Manually editwel "A" = Nuclide specific abn. Limit 4

S 9

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TOTAL P.13

z-

= =

l

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3.

ig 4

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TABLE 2 f

U.S. NUCLEAR REGULATORY COMMISSION REGION III CONFIRMATORY MEASUREMENTS PROGRAM FACILITY:

FERMI 2 i

FOR THE 1ST QUARTER OF 1994 4

i SAMPLE NUCLID NRC VA NRC ERR. LIC. VAL. LIC. ERR. RATIO RESOL RESU f

4 CST-CR-51 8.26E-96 6.73E-87 1.21E-85 1.26E-86 1.46 12.3 A

TANK MN-54 6.52E-87 6.38E-88 6.74E-87 1.20E-67 1.83 18.2 A

DET 1 CO-66 6.37E-87 5.96E-08 8.42E-87 1.96E-87 1.32 10.7 A

1/11/94 I-131 1.55 E-86 9.50E-98 2.66E-06 1.91E-67 1.33 16.3 D

CS-134 7.85E-86 1.59E-87 9.43E-06 2.83E-87 1.28 52.4 A

CS-136 2.49E-07 5.52E-98 0.00E+60 '8.00E+88 4.5 D

1' CS-137 7.22E-06 1.49E-87 7.47E-66 2.72E-87 1.e4 48.4 A

CST CR-51 8.26E-86 6.73E-87 9.58E-86 7.52E-87 1.16 ' 12.3 A

}

TANE MN-54 6.52E-87 6.38E-88 7.20E-07 6.69E-88 1.10 10.2 A

DET 2 CO-66 6.37E-07 5.96E-88 6.61E-07 7.11E-88 1.94 10.7 A

i 1/11/94 I-131 1.55E-86 9.50E-88 1.64E-66 1.12E-07 1.86 16.3 A

CS-134 7.85E-96 1.58E-87 8.47E-86 1.86E-87 1.08 52.4 A

CS-136 2.49E-87 5.52E-08 3.81E-07 6.61E-68 1.53 4.5 A

CS-137 7.22E-96 1.49E-87 7.10E-06 1.88E-87 8.98 48.4 A

CST CR-51 3.39E-67 1.52E-07 1.18E-06 2.97E-07 3.25 2.2 D

j TANK MN-54 2.96E-87 3.5 4E-88 1.85E-87 4.52E-68 8.90 5.8 A

l DET 2 CO-58 1.68E-67 2.22E-88 1.43E-97 3.23E-98 8.89 7.2 A

]

2/17/94 CO-66 7.52E-07 5.16E-88 9.11E-87 8.29E-68 1.21 14.6 A

I-131 7.78E,08 2.58E-88 9.00E-08 3.46E-88 1.17 3.0 A

CS-134 7.08E-97 5.97E-88 7.95E-87 7.11E-98 1.12 14.0 A

,~

CS-137 6.37E-87 4.35E-88 5.04E-07 6.33E-98 8.79 14.6 A

CST CR-51 3.08E-97 1.28E-97 6.18E-87 1.88E-07 1.98 2.4 A

i TANK SB-125 9.13E-98 2.85E-88 1.20E-87 4.70E-88 1.31 3.2 A

1 CO-58 8.74E-98 1.93E-88 1.96E-87 2.28E-08 1.14 4.5 A

1 2/21/94 CO-66 5.06E-97 3.73E-98 5.20E-87 5.00E-98 1.03 13.6 A

I-131 6.65E 2.16E-88 6.00E-08 1.40E-88 0.96 3.1 A

CS-134 1.30E-87 2.49E-98 1.5SE-97 3.20E-98 1.15 5.2 A

CS-137 1.90E-97 2.33E-88 6.79E-98 3.28E-88 0.67 4.3 A

L CST CR-51 2'.76E-97 9.24E-98 2.89E-97 1.20E-97 1.05 3.8 A'

\\

TANK SB-125 0.00E+44 0.00E+0S 8.00E+00 0.00E440

/

l PRE-CO-58 6.47E-88 1.29E-48 S.00E+98 0.00E+0S 5.0 D

l DISCH._ CO-68 4.26E-97 2.36E-98 -5.06E-97 4.45E-88 1.19 18.8 A

1

-2/24/94 I-131' 3.02E 1.08E-08 7.30E-88 2.81E-98 2.42 2.8 A

CS-134 1.47E-97 1.69E-98 1.64E-97, 3.53E-97 1.12 8.7 A

+

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b CS-137 1.68E-87 1.69E-88 1.11E-07 3.00E-88 0.66 10.0 A

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Fermi 2 Condensate Storage Tank Discharge 1

1 Regulations:

'10 CFR 20.1302 (b) (2) (i)

Effluent releases to unrestricted area must be maintained as an annual' average _ concentration less than the concentrations in Table 2 of Appendix B to 10 CFR 20.

Design-objectives for equipment to

-10 CFR 50.34(a) 1 control releases of radioactive material in effluents.

This section refers only to applications for construction permits.

"These numerical guides (i.e.

Appendix I) for design objectives and limiting conditions for operations are not'to be construed as radiation protection standards."

Requirement for Technical specifications 10 CFR 50.36(a) on effluents from nuclear power reactors during operation.

TS to maintain releases'ALARA, including the requirement for procedures developed pursuant to 50.34(a).

Appendix I provides numerical' guidance to ensure

)

releases are maintained ALARA.

This section also sets the requirement for the annual effluent. report.

i 10 CFR 50 APP I --

" Numerical Guides for design objectives and limiting conditions for operation to meet the criterion "As Low AS Reasonably Achievable."

Section II Guides:

Liquids --

Whole Body 3 MREM /yr and Organ 10 MREM /yr (Calculated). (Section II.A.)

Gases 10 mrad gamma and 20 mrad beta' per year.

(section II.B.1) or, the Commission may specify lower quantities if an I

i estimated annual dose of 5 MREM Whole Body.

j (B.2.a.) or must meet 5 MREM Whole Body and 15 MREM skin (B.2.b.).-

1

~Particulates -- Annual total of radioiodines and particulate radioactivity released to l

atmosphere will not results in an annual-dose j

cnr dose. commitment from all pathways of exposure-in excess of 15 mREN to any organ-of

\\

. >s 4

y IMW' - - -

e mwd w

um+44

i y-s

' i any person in an unrestricted area.

Section III Implementation:

Land use Census -- A.1.

Section IV Technical Specifications:

Quarterly dose calculations -- If exceed one-half of annual limits, a report must be made to the Commission describing a causal investigation and program of corrective actions. (A (1-3))

l Environmental Monitoring Program -- B.2'.

Land Use Census -- B.3.

Regulatory Staff Position:

7 Liquid Effluents:

Total dose from all pathways less that 5 MREM per year whole body (A.1.)

Total quantity

< 5 Curies (excluding H-3 and dissolved gases) 4 l

i e

i n

e I

m

.i EPA Drinking Water Standards (i.e. Maximum contamination in

~

community water) 40 CFR 141.15(a)

Ra-226 + Ra-228 < 5 picocuries/ liter 40 CFR 141.15(b)_

Gross alpha (including Ra-226, but excluding radon and

- uranium) '< 15 picoeuries/ liter 40 CFR 141.16(a)

Annual concentration:' Beta and Gamma annual dose equiv to the total body or internal organ cannot exceed 4 mrem /yr.

40 CFR 141.16(b)

Isotope Limit H-3 20,000 picocuries/ liter Sr-90 8 picocuries/ liter I

I.

t 1

1 N64' 4'unks ! - -

i Licensee's Technical Specifications:

Offsite Dose Calculation Manual:

3.11.1.1 The concentration of radioactive material in liquid effluents is not to exceed ten times the conc.

values specified in 10 CFR 20.1001-20.2401.

The limits for dissolved or entrained noble gases will be limited to 2E-4 microcuries/ml total activity.

I 3.11.1.2 The dose or dose commitments to a member of the public for radioactivity in liquid effluents, from each reactor, shall be limited:

Quarterly -- 1.5 mrems to the total body and 5 rems to any organ.

Annual -- 3 mrems to the total body or 10 mrems to any organ.

3.11.1.3 -- Appropriate portions of the.radwaste treatment system shall be operable and used to reduce rad materials in liquid effluents when projected doses are greater than 0.06 whole body and 0.2 rem to any organ in a 31-day period.

l 1

I

(

Condensate Storace Tank Activitv/NRC Analyses Jan 11, 1994 - Split CST samples were analyzed by the NRC and the licencee.

The results of these analyses were in good agreement and were documented in the Augmented Inspection Team report.

SAMPLE NUCLIDE NRC VAL. NRC ERR.

LIC. VAL.

LIC. ERR.

RATIO RESO*. R'ESLT CST CR-51 8.26E-06 6.73E-07 1.20E-05 1.26E-06 1.46 12.3 A

TANK MN-54 6.52E-07 6.38E-08 6.74E-07 1.20E-07 1.03 10.2 A

DET 1 CO-60 6.37E-07 5.96E-08 8.42E-07 1.06E-07 1.32 10.7 A

1/11/94 I-131 1.55E-06 9.50E-08 2.06E-06 1.91E-07 1.33 16.3 A

CS-134 7.85E-06 1.50E-07 9.43E-06 2.83E-07 1.20 52.4 A

CS-136 2.49E-07 5.52E-08 0.00E+00 0.00E+00 4.5 D

CS-137 7.22E-06 1.49E-07 7.47E-06 2.72E-07 1.04 48.4 A

CST CR-51 8.26E-06 6.73E-07 9.58E-06 7.52E-07 1.16 12.3 A

TANK MN-54 6.52E-07 6.38E-08 7.20E-07 6.69E-08 1.10 10.2 A

DET 2 CO-60 6.37E-07 5.96E-08 6.61E-07 7.11E-08 1.04 10.7 A

1/11/94 I-131 1.55E-06 9.50E-08 1.64E-06 1.12E-07 1.06 16.3 A

CS-134 7.85E-06 1.50E-07 8.47E-06 1.86E-07 1.08 52.4 A

CS-136 2.49E-07 5.52E-08 3.81E-07 6.61E-08 1.53 4.5 A

CS-137 7.22E-06 1.49E-07 7.10E-06 1.80E-07 0.98 48.4 A

Feb. 17, 1994 - The NRC and licensee analyzed a licensee collected CST sample (during recirculation).

The results were in good agreement:

SAMPLE NUCLIDE NRC VAL. NRC ERR.

LIC. VAL.

LIC. ERR.

RATIO RESOL. RESLT CST CR-51 3.39E-07 1.52E-07 1.10E-06 2.97E-07 3.25 2.2 D

TANK MN-54 2.06E-07 3.54E-08 1.85E-07 4.52E-08 0.90 5.8 A

DET 2 CO-58 1.60E-07 2.22E-08 1.43E-07 3.23E-08 0.89 7.2 A

2/17/94,CO-60 7.52E-07 5.16E-08 9.11E-07 8.29E-08 1.21 14.6 A

l I-131 7.70E-08 2.58E-08 9.00E-08 3.46E-08 1.17 3.0 A

CS-134 7.08E-07 5.07E-08 7.95E-07 7.11E-08 1.12 14.0 A

CS-137 6.37E-07 4.35E-08 5.04E-07 6.33E-08 0.79 14.6 A

^

5

~

Feb. 21, 1994 - A sample was collected by the licensee and was split between the licensee, NRC, and State of Michigan for analyses.

. SAMPLE NUCLIDE NRC VAL. NRC ERR.

LIC. VAL.

LIC. ERR.

RATIO RESOL. RESLT I

i l

CST CR-51 3.08E-07 1.28E-07 3.00E-07 2.00E-07 0.97 2.4 A

TANK SB-125 9.13E-08 2.85E-08 1.50E-07 7.00E-08 1.64 3.2 A

NRC VS CO-58 8.74E-08 1.93E-08 8.00E-08 3.00E-08 0.92 4.5 A

MICHIGAN CO-60 5.06E-07 3.73E-08 4.50E-07 7.00E-08 0.89 13.6 A

2/21/94 I-131 6.65E-08 2.16E-08 7.00E-08 3.00E-08 1.05 3.1 A

CS-134 1.30E-07 2.49E-08 1.10E-07 4.00E-08 0.85 5.2 A

CS-137 1.00E-07 2.33E-08 8.00E-08 3.00E-08 0.80 4.3 A

CST CR-51 3.08E-07 1.28E-07 6.10E-07 1.80E-07 1.98 2.4 A

TANK SB-125 9.13E-08 2.85E-08 1.20E-07 4.70E-08 1.31 3.2 A

NRC VS CO-58 8.74E-08 1.93E-08 1.00E-07 2.20E-03 1.14 4.5 A

FERMI 2 CO-60 5.06E-07 3.73E-08 5.20E-07 5.00E-08 1.03 13.6 A

2/21/94 I-131 6.65E-08 2.16E-08 6.00E-08 1.40E-08 0.90 3.1 A

CS-134 1.30E-07 2.49E-08 1.50E-07 3.20E-08 1.15 5.2 A

CS-137 1.00E-07 2.33E-08 6.70E-08 3.20E-08 0.67 4.3 A

4 l

Prior to Discharge - Sample to be collected by the licensee and split between the licensee and NRC (2 samples).

One sample will be analyzed onsite in the NRC mobile laboratory, and an additional sample will be split for analyses in the Region III office.

Offsite dose calculations will be performed based on the results of these analyses.

During discharge - Sample to be taken at CST levels of 2/3 2and 1/3 and analyzed in RIII mobile lab.

One sample will 1

also be taken prior to end of discharge for future analysis, i

I t

==

i et.as=Me -*Me - __

i s

i 6

CST non-Radioloaical Chemistry Prior to the Turbine-Generator Failure:

System CSI Hotwell Date 12/21/93 12/25/93 Cond (uS/cm) 0.78 0.060 TOC (ppb) 73 C1 (ppb)

<1 NO3 (ppb)

<1 SO4 (ppb)

<1 SiO2 (ppb)

<S Isotopic (uCi/gm)

<MDA*

MDA:

Approximately 1E-6 to 1E-7 uCi/gm per isotope.

After the event:

System CEI Hotwell Date 12/27/93 12/30/93 Cond (uS/cm) 240 147 TOC (ppb) 33180 3100 C1 (ppb) 18400 NO3 (ppb) 2500 SO4 (ppb) 25700 SiO2 (ppb) 1126 Isotopic (uci/gm) 7.27E-5 I

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s CST Demineralization Results Isotope Before(1/11/94)

After (2/21/94) uCi/ml uCi/ml Cr-51 8.26E-6 3.08E-7 Mn-54 6.52E-7 0

Co-60 6.37E-7 5.06E-7 I-131 1.55E-6 6.65E-8 Cs-134 7.85E-6 1.3E-7 Cs-137 7.22E-6 1E-7 Sr-89 8E-6 Not analyzed.

H-3 1E-3 Not analyzed.

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Tvolcal RIII Plant Liauld Discharces Plant 1991 1992 1993 Davis Besse1 37.7 mci w/o H-3 23.65 mci w/o H-3 325Ci w/

H-3 381Ci w/

H-3 s

Fermi 21 0.02 Ci w/o H-3 0.000066C1 w/o H-3 2.24 Ci w/

H-3 0.352 Ci w/

H-3 Perry 0.105 Ci w/o H-3 0.0598 Ci w/o H-3 IIsotopes reported:

Co-60, Cs-134, Cs-137 J

2 1

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1 1

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Interactions with Canada

- Sandra Weston, Head-

' Commercial Chemicals and Nuclear Programs

' Environmental Contaminants and Nuclear Programs Division Environmental Protection

, Ontario Region Conservation and Protection Ms.Weston arrived onsite at 1400 hrs on February 17, 1994.

She observed the'NRC counting a CST-sample obtained by the licensee earlier that morning.

She observed the NRC comparing the licensee.and NRC result, in accordance with the acceptance criteria contained within Inspection Procedure 84750.

Ms Weston was also shown an NRC dose projection calculated via PC DOSE with licensee data from 2/16/94..All data and dose parameters were discussed by S.

Orth, and copies of the PC DOSE projection and IP 84750 were given to S. Weston.

Ms Weston toured the NRC mobile laboratory and walked down the licensee's modification for tne CST discharge.

S. Orth described the modification, including the new radiation monitor, monitoring and communications by operators, and conditions which would cause a termination of discharge.

4 Ms Weston left the Fermi 2 site at about 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months when the assistant to the plant manager announced that the discharge had been postponed.- S. Orth asked if she wished to wait for any further, unofficial analyses.

She responded that she will probably be'back for the official discharge analysis, so she saw no point in waiting for another split sample that

. day.

i I

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l NRC FORM 303(Rill)

U. S. NUCLEAR REGULATORY COMMISSION LABORATORY USE ONLY m

REQUEST FOR ANALYSIS CONTROL NUMBER f --[h RE040N 111 LABORATORY swtE LocAnON 4mSEE)

LICENSE NO.

DOCKET NO.

VW}

f SAMPLE SUBMITTED

TOTAL TYPE DATE SAMPLES SUBMffTED PRIORITY

[

Y G NT

SAMPL5 COLLEC'rldkl INTERVAL MONT DAY YEAR TIME START INSPECTOR RESPONSIBLE TELEPHONE NUMBER 8

ANALYSIS TO BE PERFORMED OTHER TYPE OF ANALYSIS (Spec #)r)

GROSS ALPHA (GA)

GROSS BETA (GB)

GAMMA SPEC (GS)

TRITIUM (H3)

CARBON-14 (C14)

IODINE.125 (1125)

REMARKS fu ils/?e sawfA<

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NOTE: SAMPLES WILLBE DISCARDED AFTER ANALYSIS UNLESS REASONS ARE NOTED IN REMARKS ABOVE.

~ FOR URGENT USE ONLY - Signature blocks below must be compieled by the inspectors appropriate Section Chief and by the a'

F Chief. Effluents Radiation Protection Section BEFORE e@mtlirig this form to the Region 111 Laboratory I

}

90 NATURE-Arv,survuATE NUCLEAR MATEMALS SAFETY eECnON C>EEF DATE -

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' WQNA

-FUEL FAcafnES AND CONTAhetATWh. SECGN/

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23 Frb 94 13:13 Pace #1 Protocol #:16 H-3/C-14 DPH User : GLINSKI/ ANDRE Time:

10.00 Data Mode: Dual DPH Nuclides: 3H14C-UGXR Quench Sets Sigma Coincidence On Low Energy:

3H-UGXR Background Subtract: 1st Vial High Energy: 14C-UGX R

LL UL LCR 2S%

BKG Region A:

0.0 - 12.0 0

0.5 4.60 Region B:

4.0 -

156 0

0.5 19.30 Region C:

0.0 -

0.0 0

0.5 0.00 Quench Indicator: tSIE/AEC Ext Std Terminator: Count WATER SAMPLES FROM FERMI Luminescence Correction On S#

TIME CPHA A:2S%

CPHB B:2S%

DPH1 DPH2 tSIE 1

10.00 4.60 29.49 19.30 14.36 247.85 2300'

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COUNTs c'

Ke v 50' 2

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10.00 2657.70 1.24 2572.70 1.26 10724.6 90.84 246.64 4

3.62 44497.6 0.50 43994.0 0.50 208403 547.55 216.24 tucas SoitYM

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Sample Id: blank SampTe Type: smear Thu Feb 24 15:06:48 1994 Counting Time:

30 min 0 see Alpha Counts Beta Counts Gross 1

25 Net CPM 0.033 0.833 Std Deviation

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200.000 40.000 Concentration (DPM/swp) 0.0971817 (DPM/swp) 2.05255 Sample Number 5

Sample Id: NO. 1 Sample Type: SMEAR Thu Feb 24 15:37:00 1994 Counting Time:

30 min 0 see Alpha Counts Beta Counts Gross 6

1844 Net CPM 0.167 60.633 Std Deviation

(%)

81.650 4.657 Concentration (DPM/swp) 0.485909 (DPM/swp) 149.343 Sample Number 6

Sample Id: NO. 2 Sample Type: SMEAR Thu Feb 24 16:07:12 1994 Counting Time:

30 min 0 see Alpha Counts Beta Counts Gross 6

1514 Net CPM 0.167 49.633 Std Deviation

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81.650 5.140 Concentration (DPM/swp) 0.485909 (DPM/swp) 122.25 l

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Sample Id: PB-210 SOURCE Sample' ' Type : CHECK Thu Feb 24 16:08:24 1994 Counting Time:

1 min 0 see Alpha Counts Beta Count s Gross 1357 307.)

Nat CPM 1357.000 3079.000 Std Deviation

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5.429 3.604 Concentration (DPM/gro) 1357 (DPM/gro) 3079 l

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LABORATORY

15 Mar 94

-13:16 Pace #1 Protocol #212-H-3 DPM User : ANDRE /GLINSKI Time:

30.00 Data Mode: DPM Nuclide': 3H-UGXR Oaench Set: 3H-UGXR Sigma Coincidence On Beckground Subtract: 1st Vial LL-UL LCR 2S%

BKG Ragion A:

0.0 - 18.6 O

O.5 9.53 R gion 9:

2.0 - 18.6 0

0.5 9.63 Ragion C:

0.0 -

O.0 O

O.5 0.00 Ou:nch Indicator: tSIE/AEC Ext Std Terminator: Count MONROE INTAKE WATER FERMI ORTH Luminescence Correction On S0-TIME CPMA A:2S%

CPMB B:2S%

DPM1 tSIE 1

3'.00 9.53 11.83 9.63 11.76 249.68 O

2 30.00 0.00 0.00 0.00 0.00 0.00 247.98-944V8 3

30.00 0.40 492.7 0.40 484.5

1. 43 249. 59 -f'/ -6Y9 4'

30.00 0.00 0.00 0.00 *****

O.00 249.85 99-440 5

3.98 40019.6 0.51 39841.4 0.51 206932 177.84 dmd Ek/

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2 1S.29 24.

65.

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0 23.92 26.

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0 6C4.47 174 76.

1.74 1207.48 1199 15 4.HE-02 14.2 10 0

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32.

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661.47 97.

17.

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795.74 101.

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834.37 64.

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2.33 2340.74 2333 w 6.SCE-02 7.2 17 0 1331.60 230.

15.

2.05 2655.19 2651 13 6.40E-02 7.1 PEAK SEARCH COMPLETED (REV 15.8 - ND PC VERSION DEC 88)

PULSE-PILE-UP CORRECTED DATA. CORRECT 1CN 'e 1.:10 0 JNCORR. LIVE TIME:

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3H-O'i 7 Dackground Subtract: 1st Vial High Energy: 14C-Uus R

LL UL LCR 2 S */.

DKG Region A:

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4.0 -

156 0

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0.0 0

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. Ext Std Terminator: Count FERMI CST SECOND DISCHARGE ORTH Luminescence Correction On SO TIME CPMA A:25%

CPMB B:25%

DPM1 DPM2 tSIE 252.96[dzs4; 1

30.00 5.20 16.01 21.20 7.94 2

30.00 1878.57 0.85 1872.80 0.86 7475.04 141. 39 248.89 '78/ 4C'l 4

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.LCR 2S%

BKG R gion'At 0.0 - 18.6 0

0.5 9.53 R;gion B:

2.0 - 18.6 0

0.5 9.63 R gion C:

0.0 -

0.0 0

0.5 0.00 Ouxnch Indicator: tSIE/AEC Ext Std Terminator: Count MONROE INTAKE WATER FERMI ORTH Luminescence Correction On S#

TIME CPMA A:2S%

CPMB B:2S%

DPM1 tSIE 1

30.00 9.53 11.83 9.63 11.76 249.68 2

30.00 0.00 0.00 0.00 0.00

0. 00 247. 98 -9'/"dN 3

30.00 0.40 492.7 0.40 484.5 1.43 249. 59 -ff-dYf 4

30.00 0.00 0.00 0.00 *****

O.00 249.85 99-o40 5

3.98 40019.6 0.51 39841.4 0.51 206932 177.84 QM Ek/,

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3H-UGXR Bcckground Subtracts ist Vial High Energy: 14C-UGX R

LL UL LCR 2S%

BKG Rsgion As O.0 - 12.0 0

0.5 4.00 Ragion B:

4.0 -

156 O

O.5 20.00 Ragion C:

0.0 -

0.0 O

O.5 0.00 Ousnch Indicator: tSIE/AEC i

Ext Std Terminator: Count FERMI 2,

CST SAMPLE, FOR H-3.

(Andre / Orth)

)

Luminescence Correction On 1

S#

TIME CPMA A:2S%

CPMB B 2S%

DPM1 DPM2 tSIE k 1

10.00 4.00 31.62 20.00 14.14 258.20-/d*

2 10.00 1849.20 1.49 1832.10 1.50 7320.98 127.65 250.23 74-19&*

3 10.00 1873.50 1.48 1851.80 1.49 7373.90 127.24 251. 65 94 -I4IS 4

10.00 1886.70 1.47 1887.90 1.48 7437.54 156.36 250.899tl-ITT" 5

10.00 1891.60 1.47 1878.40 1.49 7465.92 137.82 250.86 14 -1996 6

2.54 73944.4 0.46 63130.4 0.50 207246 1484.22 371.16 dae.*24 Sb/

I

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20.

1.28 1508.Ga 10.65 11

2. ".9E --02 1'.

)

810.! O 50.

M.

.36 1613.52 le11 16 1.37E-02 :

.3 40 0

G: S. 41 35 tB.

1.05 1660.J 1.3 6 1 la 2.36E-02. E. ~.

11 0 117T.De 237.

LU.

1.00 2-~40.90 2:30 15 7. 9 ?E --02

.7. 2 12 0 13!:. 77 262.

7.

1.60 2 659. 5'.:.

.h 51 16 7.27E-02 a. c.

FEAK EEnRCH COMLETED (REV 15.E - ND DC VERSION DEC d8; Pl!LSE-FILE-UP CORRECTED DATA. CORRECTION =.

1.000 JNCORR. LIVE TIME:

3600. CORRECTED LIVE TIME:

3600.

PK IT ENERGY AREA BKGND FWHM CHANNEL.LEFT PW CTS /SEC % ERR 1

O' 176.72 76.

73.

1.02 354.05 35d 9 2.10E-02 26.4 2

0 295.46 70.

47.

.90 590.96 587 9 1.95E-02 22.1 3

0 351.80 93.

60.

1.70 703.37 697 12 2.59E-02 20.9 4

0 428.34 97.

96.

1.92 856.07 847 19 2.70E-02 28.7 5

2 604.67 111.

56, 1.57 1207.87 1203 23 3.08E-02 15.5 6

2 609.29' 79.

43.

1.87 '1217.10 1203 23 2.19E-02 22.3 7

0 661.47 111.

24.

1.96 1321.20 1314 18 3.08E-02 14.5

.n

&~

ron u cu on 4.

,o 4 coo oc 4cae 4 4

, -. o c _ a,

<_7

"'*"* "I a.

~#

..... -. 4 em. r e as.

-.*.-ne

- +

-, + - i

.w..

v o, v..sv

,, v.

,g_,

._._,,N

',, !, z 2I

,,0 0

8:3,41 e =, -

13.

1.93 1 6 6 8 ' ~? ?

a p

13*4 4

- ~~ * * " g

3 g

, v ', '?

~

^

y' 3

"^

11 0

117 56

- c17.

" 5.

1.Go 2340.9n 2

7.?

.f

+ 1.77 6.

7.

1.68 2638.57, 2651 16.'.27E-02 6.6 PILE-UP COR.iECTICi' CCi1F LETZD l

l i

1 0

I s

i i

4 i

I i

i r

b

s NUCLIDE IDENTIFICATION SYSTEM (ND PC VERSION DEC 88)

NJCLIDE LINE AUTIVITY REPORT J; AGE 1

ELAPSED LIVE 1Il1E:

3600. (PILE-UP CORF ECTED)

F13GIO1 GAS UCI/

1-LIGM6 11 JCul D1 EBH'N ENEROY AREA BKGND

%ADN

%EFF GRAh ERRO3 MF-UB FG l , 6..~ 2 0.

(..

2a.00+

0.000Z+00

.000E O

. Q.. G E 834.83 Ei5.

1G.

13.00

7. 837E- 01 3.239E

-Q 5.961E- 0 1529.77 0.

O.

1O.90 O.000E+00

.000E O

.000E 2195.84 0.

O.

13.20 0.OOOE+00

.000E O

.0002 2392.11 0.

0.

34.60 O.000E+00

.000E a

.OGOE J

XE-123 FG 249.79 0.

O.

C9.70*

0.000E+00

.000E O

.000E 608.18 79.

43.

2.89 1.04EEiOO

5. W5E

-7 1.337E 7

DCT VJiTIOls FRODUCT UCle 1 - 31 E Mis iiUCLIDE S3HR ENEF;GY AREA DKGND

%(;BN

%EFF GRAM ERROR MN-b4 AP 834.53 85.

13.

79.985

7. C3 C O-01 a. 536 E --

2.9202 -3 CO-58

('iP 510.76 50.

c. 6.

99.40+

8.060E-01 9.05DE -G 2.650E

-6 v:)- 60 AP 1177. 22 287

25. 100 00 5.736E-Oi 7.332E -7 5.264E 1332.49 262.

7.

10Ja. OO*

5 101E-01

7. '315E

-7 4.9952 6

r.i-L.n E! ! l' i SE,101 i UEDDUCT 001 4'

lucic

. i Di. _.E;iR IMF.3Y

.,REA Bt.3NI 4SN

.E Fi-GRAE E RF< C i -1 51

-;F F 546.56 C.

O.

.21

0. OOoE -W

.OO0E O

.000E O

936.8:

85.

1.

6.67

.67DE-01 i. 663E

--7 3.42VE -4 1036.76 0.

J

'1.90 0.0:.4 2"00

.000E 0

.'00E O

1131.51 O.

22.50 0.000E+00

.00JE O

.OOGE O

1260.41 C.

O.

28.60+

0.000E+00

.000E O

.000E 0

14S7.56 0.

O.

3.60 C.100E+00

.OuGE J

.000E O

1376.03 0.

O.

'.:O

v. O JO2,00

.:>OOE 0

.000L 0

1791.20 0.

v.

ev d +00

. 00.>E C

.0GOE Pl'JEiON PFODoC1 LCIi 1 -E f GM LICCL : I'E 5BHR ENERGY AREA EKGND iALN

%EFF 3RAN ERRJF RO 1v2 FO i 9 7. 0<.

0 O.

80.00*

O.000E+00

.000E

(-

.000E 010.2.3 79.

43.

S.a0 1.04Sa+00

.932E

-6 4.3OoE

., e_

F-i f o... e.

,,,c.

o. Lm s

a a, 7 + A~

c.e. t o..,

m

1. - / 1 E -

ve v.

427.89 97.

46.

29.33*

1. L 4 7 E + 0'.-

3.351E

-7

9. o2; E J

463.38 0.

O.

10.36 O.OO:#E400

.UGOE O

.000E O

600.Sa 0.

O.

17.E0 O.C00E+00

.000E O

.uGOE 635.90 0.

O.

11.32 0.OOOE-00

.000E O

,00CE.

25 - 1 ~. 4 FP 563.23 0.

O.

8.38

0. :00E+ 00

.OOOE O

.OODE O

DS9.32 0.

O.

11 43 o.C:.UE+0v

.000E O

.000E e04.70 111.

56.

97.60*

1.056E+00 1.578E

-7 2.444E -ti 795.85 86.

20.

85.40 8.199E-01 1.801E -7 3.099E -6 801.93 0.

O.

8.73 O.000E+00

.000E O

l l

~... =

w +.. _

.u...

.a.

2

9

NUCLIDE IDENT1~ICATIGN SYSTEM (ND PC VERSION DEd A8)

NUCLIDE LINE ACTIVITY REPOf<T

. EASE 2

ELAFSED LIVE TINEt, 360v. (F ILE-UP CORRECTED)

FISSION FRODUCT

LCI, 1-5IGMA NUCLIDE SDHF ENERGY AREA ES:GND

%AEN

%EFF GFiAM ERROR LE -136 iT 176.5L 7:3.

73.

13.06 J.. O'/ OE + 00 1.597E

-T o.609E -8 273.6S

~.

O.

12,66 0 OOOE+00

.OOOE O

343.57

<i.

O.

4G.Su O.OODE+00

.OOGE O

.OOOE O

1 O '. D. 5 0 0.

O.

99./O*

O.GOGE+00

.OOOE O

104G, C '

Q.

O.

79,60 O.COOE+00

.OOOE O

.OODE O

1;35.34 O.

O.

19.70 O.OCOE+00

.GOOE O

.OOGE O

C5-13 FF 661.6~.i 111.

24.

GS.12+-

0.710E-Oi

1. 9 5 2 E

--7 2.8. IGE -G NATURAL PRODUCT UCI/

l-SICMA NUCLIDE 35HR ENERGY AREA BKGniD

%ABN

%EFF GRAM ERRCR RA-226 NF 1G6.21 o.

O.

3.28 O.COOE+0u

.OOOE O

,OOOE O

241. %

0.

O.

7.49 O.GOOE+00

.(OGL G

.OOCE O

l 2VD.11 70.

4 '/.

19.20 2.0;82400

.a.26E -7 S.814E -8 351. E 90.

6 f..

37.2C 1.733E+00

..I17E -1

4. 420E - 8 l

6 0 9. '.i 79.

t. a.

46.3O+

1.04EE+v0 L. Tc G E ~7 S.302E -E

.120.2?

0.

O.

15.10

..OO:E+00

. 0 0 '-

. M)OE O

1236.1i O.

O.

5.94 0.OU0E+00

.301E

.000E O

l'/64 si

).

i c.. 8. >

0.OO.:fv00

. D O ^ E.

u

.UODE O

j 2201.22 0.

O 4.96 O.X A400

.360E O

.OOoE v

i

'i e

9 e

l m

,d v

NLiCL I DE IDENTIFICATION SYSTEt1 (ND PC VERSION DEC 99)

UNMNOWN LINE REPORT fAGE 3

ELAPEED LIVE tit 12 3600. (PILE-UP CORRECTED)

UNIDENTIFIED PEAKS FK IT ENERGY AREA BKGND FWHM CHANtJEL EFT PW CiS/EEC %iRR

%2FF 1

0-176.72 76.

73.

1.02 354.03 35v 9 '2.10E-02

e. 4 3. 09E-UO 2

0 295.46 70.

47.

.90 590.96 507

- 1.75E-02 22.i 2.03E WO 3

0 351.80 93.

60.

1.70 703.37 6"7 12 2. 59E- 02 20. 7 3.73E+00 4

0 428.34 97.

96.

1.92 056.07 847 19 2.70E-02 28.? 1.4rE-OU 6

2 609.29 79.

'43.

1.67 1217.10 1203 23 2.19E-02 22.3 1.03E+03 4

LINE5 NCT NEETING SJbtARY CRITERI A Pr ?.

NL'CL1DE ENERGY HLFE CECAY UCI/ GRAM ABNDIi:F FAILEb e

i SD-125 176.33 2.77Y 9.993E -1 3.2OOE -7 47.85%

ABN 1 CS-136 176.55 13.16D 9.451E -1 2.507E -7 4.95%

AIJN 2 RA-226 295.21 1600.OOY 10.OOOE -1

.'. 636E -7 66.23%

ABN 3 f:A-226 351.92 1600.OOY 1O.OOOE -1

.i.IL7E -.

60.13%

ABN 4 SD-125 427.89 2.77Y 9.993E -1

~~.351E

?

47.85%

ADN 6 HU-103 610.33 39.35D (7.023E -1 1.931C -:>

0. 9 2 '<.

Abd 6 XE-135 608.18 9.11H i.073E -1 5.99CE -7 3.12%

6JN 6 (

226 60'.7.1 2e00.OOY 19.oOOE ~1 4.378E

~7 e ca.13%

.,LN 10 KR-85 8 34. a.>

a.84H 2.649E -3 3.239E ci I I. 51 %

ABu lis 0<L 6.5 9. 6 '. '

6. sin

/.317E

-z 1.. G e 3 ~i - 7 o. 7 J.

at.

1 e

t b

p "a$e,e,g.-

,,p

l i

j-NUCLIDE IDENTIFICATION S'r5 TEM (ND FC VERSION DEC'88)

BUNMARV 0F NUCLIDE ACTIVITY EAGE

_4 i

TOTAL LINES IN SPECTRJM 12 UNIbENTIF1ED PEAKS 5

4 liENTIFIED lli E>UMMARY REPORT 7

58.33%

' ACT P ' AT I Dc4 F i10DUC T 1-SIGMA NUCL2DE EBhR H IFE DECAY UCI/ GRAM ERROR

% ERR 2

MH-54 AP 312.7CD-

.990 1.3E6E -7 2.920E -8 18.41 1'

CO-59 AP

70. SOD

.990

9. OSSE -8 2.650E -3 29.27 CC-LO fiP 192S.Osb 1.000 7.015E -7 4.965E -O 6.63 i

FISSIGN PRODL:CT 1-SIGNA i

NUCLIDE SDHR hLIFE DECAY UCI/ GRAM ERROR

% ERR CU-134 FP 753.10L

.999 1.578E -7 2.444E -Q 15.49 CS-137 FP.

30.17Y 1.000 1.962E ~7 2.838E -8 14.46 l

ll 5

4 J

t f

i l

j o

i 1

4 J

I I

I P

d i

i J

4 9

f

/

4 eia

+*

a

~ --- ~

~-

~

- ~ ' ^ ~

., h NRC FORM 304(RIII) L.

U. S. NUCLEAR REGULATORY COMMISSION NTORY cWM N w g g

l g.;

g pg. t ~ ~ ^ :1. a u.f.

(, g

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.s-SAMPLE RECORD SHEET 1

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5

ROUTINE DATs I'm

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?.,h hh-1' REGION III LABORATORY

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Random uncertain 0es reported are 2 standard deviations, results s 2 o are kiterpreted as including *zero" or as not

...sf g "'*- 5 _.a {,} directed. ir approixiste, estrnates of poseable syenemeno emxo are reported in pareree y m;ANSPE .. A.(r '.y - n:x., ,y m.

.m/.d )cy , s. ~e x .... A . vg*......,... ..m -..y.o ..,y .a p -. ;,-..,.. ~.. - ~, e, p..g .s, NRC FORM 303(Rill) U. S. NUCLEAR REGULATORY COMMISSION LABORATORY USE ONLY ' m REQUEST FOR ANALYSIS CONTROL NUMBER -h REGION lit LABORATORY ~ m mim omLO LICENSE NO. DOCKET NO. g } SAMPLE SUBMITTED

TOTAL TYPE DATE SAMPLES SUBurfTED PRIORITY M/

/ RG ' AP/PLE COLLECfidW INTERVAL S MONT DAY YEAR TIME START HSPECTOR RESPONSIBLE TELEPHONE NUMBER STOP i ANALYSIS TO'BE PERFORMED DESIRED ST DESE OTHER TYPE OF ANALYSIS (Specify) LLD (Op60nal) LLD (Op60nal) GROSS ALPHA (GA) GROSS DETA (GB) GAMMA SPEC (GS) ) TRITIUM (H3) CARBON-14 (C14) l IODINE 125 (1125) nEuAaxa l esp 1.g4*sso*M.G*t.ksk}<,. :ph 2. y' ...&: 6:n :-y..a. d b d* Gi.m$i ),{ y r l 4 l l i i l 1 l r 6 L h l l E. M s NOTEijsAMPLESWILLBE.DISCARDEDDFTER' ANALYSIS;UNLESS REASONSk. s, ..r. t s.. I.9. ; "iya ff L NOTED E REMARKS ABOVE. a.. w s w m s

M s a.:. w.. - -.e>a z- ;. ---

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g. y u u

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l s j Ill s W 4

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= L 0 l le b kld a-g

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b-ll y3 3 w e a m Q g W h ~ k Y 6. t q Q (2 l' ! x g, b d N3.A ] 11 l s( v a wd 1 m,w ua m wR n. u..c.m a u w a p.mg-p p , +..*s p^p ;w pte p: nr ,e y gpw I?hf f Ik s h ki h Ihfh g Q g y. w E y i.gg 3%. c f u t c n n h h k h k ! %,Jg g t4m p.,3 g[g

l 19 Aor 94 13:44 Pace #1 Protocol #:12 H-3 DPH User ANDRE /GLINSKI Time: 10.00. Data Hode: DPH Nuclide: 3H-UGXR Quench Set: 3H-UGXR Sigma Coincidence On Background Subtract: 1st Vial LL UL LCR 2S% BKG Rzgion A: 0.0 - 18.6 0 0.5 7.40 Region B: 2.0 - 18.6 0 0.5 7.50 Rcgion C: 0.0 - 0.0 0 0.5 0.00 Quanch Indicator: tSIE/AEC Ext Std Terminator: Count FERMI CONDENSATE STORAGE TANK SAMPLE, 4/16/94. Luminescence Correction On S# TIME CPHA A:2S% CPMB B:2S% DPH1 tSIE 257.52 [/*j< 1 10.00 7.40 23.25 7.50 23.09 1.46 6967.03 253.15 9d/-ffI 2 10.00 1980.30 1,44 1939.30 3 10.00 1967.10 1.45 1926.70 1.46 6900.61 253.90 b 6 'l O de n guAo +- ( =,00D3,)Y,l n} t 4 5 F 6,C /n / b' p/t"lc - ooo3,Ilp 6h} / ~ IOel ^ p 4 3.I'l2^4

U E4,X /n}

@ 3,II E-9 * 't.SV6sM/wl e . r,,...-- r

ecan***n******n+++*****n******n***********************n* u.o*** u********* O2-MAY-94 10:17:34

n o********,*****.#**k***************************************

FERH1 2 CGT WATER DLRING DISCHARGE SPECTRAL FILE NAME: L942951.R3L SAMPLE DATE: 16-APh-94 09:05:00 GA11PLE IDENTIFICAT]DW. L942951.R3L 1/PIL OF SAMPLE: W41 EN SAr1PLE QUANTITY: 514.0000 UNITS: GRAM SAMPLE GEOMETRY: MAR 3OO EFFICILNCY - FILE NAME.: MHR50093.EFF

- - - - w****,**#*nt**** m
u*******u********** m m
n n ACQUIRE DATE: OZ-MF-94 08:09:30
FWHM(13!2) 1.975 PRESET TIME (LIVE):

57600. SEC

SENSITIVITY:

5.000 ELAPSED REAL TIME: 7657. SEC

SHAPE PARAMETER : 10.O %

ELAPSED LIVE TIME: 7657. SEC

NDR ITERATIONS:

10.

ei**e M****+*********w********************#*******************

DETECTOR: AOC Detector

LIBRARY NUCL. LID CALIb DATE:

JO-nW.-94 12: 53:53

ENERGY TOLERANCE:

1.500 KEV LEV /CHNL: .50M9EO

HALF LIFE RATIO:

8.00 OFFSEr: - 1. 311 W/ KEU

ADUNDANCE LIMIT:

75.00% 9 9***t********f***$*++*****************************9-**********#f ENERGY WINDOW .81 TO 4120.06 PK IT CNERG( AREA SKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR FIT 1 0 2Yb.21 104.

132, 1.67 589.+>

SSL 11 1.36E-02 2b.1 e O 3bl.a4 leo. 182. 1.27 701.96 695 *14 2.09E-02 19.1 3 0 428.1L L5. 132. .93 803.64 648 11 7.57E-03 40.8 4 0 566.00 104. 182. 10.79 1128.63 1114 27 1.76E-02 32.1 L 0 604.71 313.

118, 1.55 1204.59 1199 11 4.15E-02 9.1

'6 0 609.44 112. 76. 1.81 1214.00 1211 8 1.47E-02 16.7 O 661.83 250. 79. 1.80 1318.14 1310 16 3.65E-02 9.3 8 0 731.20 25. 71. 7.39 1456.17 1443 26 4.93E-03 74.2 9 0 795.02 24.. 44. 2.07 1584.46 1576 17 3.14E-02 10.6 10 0 810.07 cO. 46. 1.66 1614.37 1608 13 7.77E-03 28.9 11 0 834.91 615. 41. 1.78 1662.16 1655 13 8.03E-02 4.7 12 0 1173.46 402. 19. 1.95 2335.10 2328 15 5.26E-02 5.7 13 0 1332.83 339. 20. 1.92 2651.85 2640 14 4.42E-02 6.1 14 0 1461.50 16. 7. 1.97 2907.63 2905 7 2.09E-03 35.5 PEAK SEARCH COMPLETED (REV 15.8 - ND PC VERSION DEC 88) PULSE-PILE-UP CORRECTED DATA. CORRECTION = 1.000 UNCORR. LIVE TIME: 7657. CORRECTED LIVE TIME: 7657.' c PK IT-ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTG /SEC % ERR 1 0 295.21 104. 132. 1.67 ~589.40 585 11 1.36E-02 25.1 2-O- 351.84 160. 182. 1.27 701.96 - 695 14 2.09E-02 19.1 3 .O 428.15

58.

132. .93 853.64-848 11 7.57E-03 40.8 O O. 566.50 134. 1182. 10.79 1128.63 1114 27 1.76E-02 32.1 .ov,.,. ..om ii -m,- I

6.. O 609.44 112. 76. 1.81 1214.00 1211. 8 1.47E-02 16.7 7 0 661.83 280. 79. 1.EJ 1318.14 1310 16 3.65E-02 9.3 '8 ' O' -731.28 38. 71. 7._' 14D6.17 1443 26 4.93E-03 74. ,9 0 795.82 240. 44. 2.07 1D84.46 1576 17 -3.14E-02 10.6 10 0 810.87' 60. 46, 1.66 1614.37 1608 13 7.77E-O! 28.0 11 0 634.91

615, 41.

1.78 1662.16 1655 13 8.03E-02 4.7 12 0 1173.46 403. 19. 1.95 233D 10 2328 13 5.26E-02

3. 7 13

.0-1332.83 339. 20. 1.92 26D1.85 2640 14 4.42E-02 6.1 14 0 1461.50 16. 7. 1.97 2?O7.63 2903 7 2.O?E-03 35.3 FILE-UP CORRECTION COMPLETED l 4 -.c w w .a i. s s e.

NUCLIDE IDENTIFICATION SYSTEM (ND PC VERSION DEC 88) NUCLIDE LINE ACTIVITY RFPORT PAGE 1 EL6PSED LIVE TIME: 7657. (PILE-UP CORRECTED) F1SSION GAo UCI/ 1-SIGMA NUCLIDE SBHR ENERG) AREA BKOND %ABN %EFF GRAM ERROR KR-88 FG 196.32 O. O. 26.00* O.OOOE+00 .OOOE O .OOGE O 834.83 615. 41. 13.00 7.843E-01 2.133E 35 9.968E 33 1529.77 O. O. 1O.90 0.OOOE+00 .OOOE O .OOOE O 2195.84 O. O. 13.20 O.OOOE+00 .OOOE O .OOOE O 2392.11 0. O. 34.60 O.OOOE+00 .OOOE O .OOOE O XE-135 FG 249.79 0. O. 89.90* O.OOOE+00 .OOOE O .OOGE O 600.15 112. 76. 2.89 1.048E+00

1. 253E' 7

2.096E 6 ACTIVATION PRODUCT UCI/ 1-SIGMA NUCLIDE SBHR ENERGY AREA DKGND %ABN %EFF GRAM ERROR MN-54 AP G34.63 615. 41. 99.98* 7.843E-01 5.572E -7 2.604E -8 CO-58 AP 810.'76 60. 46. 99.40* 8.057E-01 5.962E --8 1.721E -8 EU-60 AP 1173.22 400.

19. 100.00 5.732E-01 4.8J2E

-7 2.783E -6 1332.49 339.

20. 100.00*

5.097E-01 4.5U4E -7 2.315E -8 FISSIOia Ph0 DUCT UCI/ 1-51GMA NUCLIDE SSHR ENERGr AREA DKGND %ABN %EFF URAL 1 ERROR RU-103 FP 197. OE O. O. 89.00* O.OOOE400 .OOOE O .OOOE O 610.33

112, 76.

5.60 1.045E+00 1.739E -6 2.905E -7 SB-125 FP 176.33 0. O. 6.89 0.OOOE+00 .OOCE O .OOOE O 427.89 58. 132. 29.33* 1.449E+00 9.464E -8 3.863E -8 463.36 0. O. 1O.35 O.OOOE+00 .OOOE G .OOOE O 600.So O. O. 17.80 O.OOOE+00 .OOGE O .OOOE O 635.90 O. O. 11,32 O.OOGE+00 .OOOE O .OOGE O CS-134 FP 563.20 O. O. 8.38 O.OOOE+00 .OOOE .000E O G59.22 O. O. 15.43 O.OOOE+00 .OOOE O .OOOE O 604.70 318. 118. 97.60+ 1.056E+00 2.14vE -7 1.546E -6 795.E5 240. 44. 85.40 8.197E-01 2.3E8E -7 2.526E -a 001.93 D. O. B.73 O.OOOE+00 .OOOE O .OOOE O CS-137 FP 661.6's 280. 79 85.12+ 9.714E-01 2.323E -7 2.164E -E i NATURAL PRODUCT ) UCI/ 1-SIGMA NUCLIDE SBHR ENERGY AREA DKGND %ABN %EFF GRAt1 ERROR K-40 NP 1460.81 16. 7. 10.67* 4.682E-01 2.197E '7 7.791E -8 RA-226 NP 186.21 O. O. 3.28 O.000E+00 .GOOE O .OOOE O 241.98 O. O. 7.49 0.OOGE+00 .OOOE O .OOOE O 295.21 104.

132, 19.20 2.030E+00 1.831E -7 4.598E -8 351.92 160.

182. 37.20 1.733E+00 1.700E -7 3.245E -8 609.31 112. 76. 46.30* 1.048E+00 1.587E -7 2.653E -8 1120.29 O. O. 15.10 0.OOOE+00 .OOOE O .OOOE O ~ 1238.11 0. O. 5.94 0.OOOE+00 .OOOE O .OOOE O 1764.49 0. O. 15.80 0.OOOE+00 .OOOE O .OOOE O 2204.22 0. O. 4.98 0.OOOE+00 .OOOE O .OOOE O /5 A.e. "A E ' e4Jm>M .. m h W J

NUCLIDE IDENT IFICATION GYSTEM (ND PC VERSILi4 DEC 88) UNKNOWN LINE REPORT PAGE 2 ELAPSED LIVE TIME 7657. (FILE-UP CURRECTED) UNIDENTIFIED PEAKE PK IT CNERGY AREA BKGND FWHM CHANNEL LEFT PW CT5/SEC % ERR %EFF 1 0 295.2) 104. 132. 1.67 S89.40 585 11 1.36E-02 25.1 2.03E+00 2 0 301.Gt 160. 182. 1.27 701.96 695 14 2.09E-02 19.1 1.73E+00 3 0 428,15 38. 132. .93 853.64 848 11 7.G7E-03 40.8 1.45E+00 4 0 566.50

134, 182, 10.79 1120.63 1114 27 1.76E-02 32.1 1.12E+00-6 0

609.44 112. 76. 1.81 1214.00 1211 8 1.47E-02 16.'7 1.05E+00' O O 731.28 38. 71. 7.39 1456.17 1443 26 4.93E-03 74.2 L2.8e~.-01 LINES NOT MECTING

SUMMARY

CRI'iERIA PK NUCLIDE ENERGY HLFE DECAY UC1/ GRAM ABNDIFF FAILED 1 RA-226 295.21 1600.OOY 1.OOOE O 1.831E -7 66.13% ADN 2 RA-226 351.92 1600.OOY 1.OOGE O 1.700E -7 66.13% ABN 3 SG-125 427.G9 2.77Y 1.011E 0 9.464E -8 38.75% ADN 6 RU-103 61O.33 39.35D 1.326E O 1.739E -6 5.92% AmJ 6 XE 13S 608.18 9.11H

4. '731E 12 1.25?E 7

3.11% DCY,AEN 6 RA-22L 609.31 16CO.00Y 1.OOGE O 1.G87E / 66.13% 'A % 11 1R-G8 G34.C3 2.84H G.15SE 40 .I.133E 35 13,31% DCi.A BI: I 4 m. h-i...-

..- - th

.w i NUCLIDE. IDENTIFICATION SYSTEM (ND PC VERSION DEC 88) l

SUMMARY

OF NUCLIDE ACTIVITY PAGE 3 TOTAL' LINES IN SPECTRUM 14 UNIDENTIFIED ~ PEAKS 6 IDENTIFIED IN

SUMMARY

REPORT G 57.14% ACTIVATION PRODUCT 1-SIGMA NUCLIDE SBHR' HLIFE DECAY UCI/ GRAM ERROR % ERR - MN AP 312.70D 1.036 5.572E -7 2.604E -8 4.67 CO-58 AP 70.80D 1.170 5.962E -8 1.721E -8 28.87 CD-60 AP-1925.OOD 1.006 4.584E -7 2.81GE -G 6.14 FISSION PRODUCT. 1-SIGMA NUCLIDE.SBHR HLIFE DECAY UCI/ GRAM ERROR % ERR CS-134 FP 753.10D 1.015 2.149E -7 1.946E -8 9.06 CS-137 FP 30.17Y 1.001 2.323E -7 2.164E -8 9.32 NATURAL PRODUCT 1 -Sli3f iA NUCLIDE SBHR HLIFE DECAY UCI/ GRAM ERROR % ERR K-40 NP 1.2GE+09Y 1.000 2.197E -7 7.791E -6 35.46 4 4 -I 9 ( 6 M' MU" M'M*msma MM

g. m q

NRC FORM 303 (Rlli) U. S. NUCLEAR REGULATORY COMMISSION LABORATORY USE ONLY m REQUEST FOR ANALYSIS CONTROL NUMBER -h REGION lil LABORATORY $MPLE LOCAM (LICENSE 1J LICENSE NO. DOCKET NO. SAMPLE SUBMITTED

TOTAL TYPE DATE SAMPLES SUBMITTED PRIORITY M7 /

d / Y RG NT "* ' SAMPLE COLLEC'fidte INTERVAL 1 MONT DAY YEAR TIME START cesPECTOR RESPONSIBLE TELEPHONE NUMBER ANALYSIS TO BE PERFORMED OTHER TYPE OF ANALYSIS (Specify) (O GROSS ALPHA (GA) GROSS BETA (GB) GAMMA SPEC (GS) TRITIUM (H3) CARBON-14 (C14) IODINE-125 (1125) a uARKs NOTE: SAMPLES WK1BE DISCARDED AFTER ANALYSIS UNLESS REASONS ARE NOTED IN REMARKS ABOVE. "* FOR URGENT USE ONLY -S4pneture blocks below must be completed by the inspector's appropriate Section CNef and by the f CNef, Effluents Redution Protection Section BEFORE submRting this form to the Reg 6on lil Laboratory -e + t f SIONATURE-APPROPRETE NUCLEAR MATERIALS SAFETY SECTION CHEF DATE

1. 4,- ---

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