ML20091S491
ML20091S491 | |
Person / Time | |
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Site: | Byron |
Issue date: | 04/16/1984 |
From: | Brown S, Kathy Weaver COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20091S488 | List: |
References | |
NUDOCS 8406180298 | |
Download: ML20091S491 (10) | |
Text
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Environmental Water Sampling Program Special Analyses Byron Station
/
Preparedby_c/ LLL/y1 [ /) f, salth Physicist e Reviewed by Md Y4/ff Station Health Physicist Approved by Q 86 1 c. . f/ /6 !VV Radiation-Chemistry Supervisor l
e40425 84061902p05000454 -
4 In June of 1983, an NRC auditor observed that Byron Station had a higher quantity of gross beta detected at the discharge p'oint (BY-11) as compared to the intake point (BY-10) of the plant cooling water from the Rock River.
The average gross beta concentrations for the sampling period of June 28 through December 27,1982 was 3.9 pC1/1 at the intake point and 21.7 pCi/l at the discharge point.
Byron Station began an environmental water rampling program to determine the reason for this observation. Several sample points were selected.
Sarples were collected and analyzed for gross alpha and beta concentrations and ganna/ isotopic concentrations. The data from this study, lasting four months, was sporadic and inconclusive due to differing laboratory techniques, short count times, and system testing that delayed sampl'ing.
A second sampling program was initiated in December of 1983. This program concentrated on the actual flowpath of the water flowing out the discharge.
Except during the hot functional testing of Byron Unit 1, discharge to the Rock River consisted solely of sewage treatment discharge. The origin of this water is the onsite deep well, not the intake point BY-10. (See Attachment A) The average gross beta concentration for the sampling period of July 2 through December 6, 1982 was 6.3 pC1/1 for the onsite deep well. l Figure 3.3-1 of the Environmental Report, the Water Usage Flow Diagram l (See Attachment 3), shows the flowpath as it will occur in the operating license stage. During 1982 and 1983, there was no steam generator blowdown, radwaste, or natural draft cooling tower blowdown except during the hot functional testing, as previously mentioned.
To eliminate error in the second sampling program, the same technician collected and analyzed the sampl'es, the sample volume for gross alpha and beta was increased from 10 to 50 m1, and isotopic analysis duration was set at 90 minutes.
The results from this study showed only naturally occu[ing radionuclides (including K-40) were present in the water samples. Isolating the reason for the increase along the flowpath was not possiple but this study did show that no cmatamination of the water was occu nng. (See Attachments C and D)
For the third study, we cencentrated on accurate gross beta counts to see if there was a significant increase in one particular section of the water l flowpath. Counting times were increased froa 10 minutes to 60 minutes to give a 225% counting er'ror for the gross alpha and beta analysis. Followup isotopic analyses were conducted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The results from this study showed a definite _ increase af gross beta at ?
the sewage treatment plant. (See Attachment E) The isotopic analyses could not isolate the isotope due to background fluctuation and such low levels of activities. (See Attachment F)
Page 2 .
For our fourth and final study, we sent samples to Teledyne Isotopes Midwest Laboratories for in-depth analysis. Teledyne's analyses included overnight gamma spectroscopy, gross beta, and atomic absorption. The laboratory had to use atomic absorption since activity levels were too -
low to be detected accurately with gamma spectroscopy.
Teledyne's results showed a nearly perfect correlation between K-40 and elevated gross beta concentrations. (See Attachment G) These data are 4 reported in 1983 Final Report for Byron Nuclear Power Station Environmental Radiological Monitoring Program. The study showed K-40 accounting for approximately 70-90% of the beta activity at the sewage treatment plant
> and the discharge point. When the discharge had a high gross beta con- L centration, the K-40 concentration was also elevated.
In summary, Byron Station concludes that:
- 1. No contamination of the plant discharge water is occurring. Only naturally occurring isotopes were revealed. l
- 2. Elevated gross beta concentrations were noticed in the sewage treat-ment plant.
- 3. When gross beta concentrations at the discharge point were elevated, an elevated concentration of K-40 was noticed.
In conclusion, the reason for the increase in gross beta concentrations at the discharge point BY-11 is due to the addition of potassium-40 through human excretion to the water flowpath originating from the onsite deep well.
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Attachment A
. i DEEP SAND FILTERED WATER <
VELLS Y FILTERS h STORAcE r TANK i
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POTABLE VATER SYSTEM l i
Zeolite S o f t e ne r. --- ----- - 3 Pn euma t i c Receiving ,
Tank f fl beine ank NapO3/Na.SO4 (
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Hypochlorite t I
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RAW SEVAGE PLANT FUNCTIONS % - -.
- i SEVAGE TREATMENT l i
activated sludges C ommuni t o r-) Su r g e Ta nic..) C o n t a c t Chamber..) Clarifier..q p..-_- ---------------J i Pres ttling Chamb e r-) Sand F i l t e r sy C l e a rwe l l-} L i f t Station #2 i-l l
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- Attachment B AMENDMENT NO.3 :
4 ROCK RIVER (MEAN AP$NUAL FLOW - 4580 CFS) MARCH 1982
% / % f N MAKEUP 76 9 CFS
> BLOWDOWN MAKEUP 4 CFS 301 CFS lf BLOWDOWN ]f EVAPOR ATION 46 7 CFS+ 4 STEAM NATURAL DRAFT 2 CFS MECHANICAL DRAFT GE" ^ COOLING TOWERS
- COOLING TOWERS O DOWN DRIFT 0 06 CFS +
Ak h Ak EVAPORATION y PLANT 2 CFS WASTE DRIFT 0 01 CFS If lf CONDENSER NONESSENTIAL ESSENTIAL ADWASTE 4 S S EM COOLING SERVICE SERVICE C WATER 2815 CFS WATER 156 CFS WATER 107 CFS lf II If SOLIDS TO h RECYCLE APPAOVED OFFSITE DISPOSAL BACKWASH 2.2 CFS.
If 5-10 MIN EACH jf DAY j
) 0 33 0 33 CONDENSATE CFS MAKEUP CFS FILTERED INLETS INLETS SAND DEEP STORAGE h WATER h WATER & FILTERS WELLS TANK TREATMENT STORAGE
^ ^
INTERMI ENTLY tNTERMITTENTLY qy NONRADIOACTIVE SEWAGE 0 22 CFS POTABLE WASTE 1 TREATMENT 4 WATER WATER PLANT IN TERMITTENTLY SYSTEM TREATMENT BUILDINGS ITION MOCLEAR GENERAilut STATilt BRITS 1 &2 ENVIRONMENT AL REPOef -OPERATING LICENSE STAGE h
FIGURE 3.3-1 WATER USAGE FLOW DIAGRAM
Attachment C .
Isotopic Data Summary.- 2nd Study Filtered Water Potable Lift Discharge Discharge Energy (kev) Nuclide Deep Well Storage Tank Water Station 2 Pipe Bay Pb-212 Thorium Series * *
- 238 352 Pb-214 Uranium Series * *
- 511 T1-208 Thoriu:n Series * * * * *
- 609 Bi-214 Uranium Series * * *
- Co-60 * *
- 1332 1460 K-40 * * * * *
- 1764 Bi-214 Uranium Series
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NOTE: Due to variable background, these data are to be used for qualitative analyses only. Samples were collected once a day for 5 days.
- - This nuclide detected more than one time at the specified sample point.
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i Attachment D Gross Alpha / Beta Counts - 2nd Study ,
Filtered Water Potable Lift Discharge . Discharge Deep Well Storage Tank Water Station 2 Pipe Bay 1-13 alpha- 5.05 6.06 4.04 0 0 1.01 1-13 beta 4.65 7.75 2.33 3.49 6.29 9.30 1-16 alpha 2.02 6.06 7.07 0 0 0 l 1-16 beta 4.65 1.93 4.65 1.93 2.32 1.93 1-17 alpha 4.04 12.12 4.04 0 0 0 1-17 beta 3.87 7.36 8.91 5.42 5.81 7.36 l 1-18 alpha 4.04 8.08 7.07 2.02 0 0 1-18 beta 2.32 6.20 4.26 3.10 5.81 5.81 1-19 alpha 6.06 6.06 7.07 1.01 1.01 0 1-19 beta 3.87 6.58 3.48 7.75 6.58 4/26 NOTE: The units for the above are dpm/50ml.
Multiply the above numbers by 9.0 to convert to pCi/1.
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Attachment E Gross Alpha / Beta Counts - 3rd Study Filtered Water Potable Lift Discharge Discharge Deep Well Storage Tank Water Station 2 Pipe Bay 1-30 alpha 4.04 1.21 1.82 0.81 0 0.71 1-30 beta 3.80 2.71 1.94 4.85 0 0.89 1-31 alpha 5.96 2.53 0.51 0 0.20 0.51 1-31 beta 3.06 0.62 0 0 0 0 2-01 alpha 0 0 0.16 0.84 3.53 0 2-01 beta 0.50 4.90 0.62 2.18 1.15 0 2-02 alpha 1.82 2.53 1.31 1.01 0.50 0.61 2-02 beta 2.02 0.19 0.78 4.84 0.58 0.08' 2-03 alpha 0 3.33 2.83 0 0.20 1.31 2-03 beta 0 2.64 2.02 5.81 0 0.27 NOTE: The above units are in dpm/50ml. To convert to pC1/1, multiply the above numbers by 9.0.
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Attcchment G T ab le 1. Acalyses for K-40 (by atomic absorption), gross beta, and gamma-emitting isotopes in special sampl:: tallected at Byron Nuclear Power Station.
i Units: pCl/l BYSW-835 BYSW-836 BYSW-837 BYSW-838 8YSW-839 BTWW-840 BYWW-841 BYWW-842 8YWW 843 Lab Code 8YSW-834 Date Collected 3-13-84 3-14-84 3 84 3-13-84 3-14-84 3-15-84 (Dup of 839) 3-13-84 3 14-84 3-15-84 Discharge Discharge Discharge Sewage Sewage Sewage Sewage Deep Well Deep Well Deep kell Location Treat ment Treatment Treatment freat ment 25.910.2' 4.220.1 4.210.1 30.0t 0. 2 31.110.2 31.210.2 31.5to.2 3.4t9.1 3.5t0.1 3. 6t 0.1 K-40 ( AA)
Gross Beta 30.St2.2 6.Itl.2 5.6tl.2 33.212.3 33.5t2.3 34.412.4 32.5t2.3 9.6t1.3 9.111.3 10.4tl.4 Be-1 <21.8 (26.4 <29.4 <30.5 <40.3 <33.5 (45.6 <21.1 (36.5 (11.0 Mn-54 <3.3 (2.0 <3.2 <3.4 <3.9 <3.3 <4.9 <2.5 <3.7 <2.6 00-58 <3.4 <3.1 <3.5 <3.6 (4.2 <3.4 (4.4 <2.5 <3.8 <2.8 Co-60 <3.6 <2.3 <3.2 <3.6 <4.1 <3.6 <4.7 <2.6 (3.7 <1.?
Fe-59 <6.6 <4.0 (6.8 <7.6 <6.6 *
(6.0 (8.8 <5.0 (7.4 <4.0 Zn-65 <6.6 <3.4 (6.9 <1.6 (8.5 <7.6 (8.9 (4.8 (8.5 (4.2 Ir 95 (6.2 <4.2 (6.5 (6.7 < 7. 3 (5.8 (8.6 <4.5 (6.6 < 3.1 -
Nb-95 '5 <2.8 <3.6 <3.9 (4.2 <3.4 <4.9 <3.1 <4.0 (2.8 Ru-103 .4 <3.0 <3.6 <3.6 (4.2 <3.5 (4.8 <2.2 <3.8 <2.2 Ru-106 <31.5 (17.0 <30.4 <31.6 <36.7 <31.1 (45.3 (17.0 <32.9 (17.0 1-131 <4.5 <3.0 (4.5 <5.1 <5.8 <4.2 (5.8 (5.0 (5.7 <3.0 Cs-134 <3.4 <2.5 <3.6 <3.7 (4.0 <3.3 (4.7 <2.5 <3.1 <l.1
<3.8 <2.2 <4.0 <3.9 (4.2 <4.1 <4.8 <3.4 <3.9 <2.8 Cs-131 <8.2 Ba-140 <14.6 <10.4 (15.0 <!6.3 <l6.5 <l2.7 (18.5 <ll.9 (15.6 La-140 (4.2 <2.5 (4.6 <4.8 <4.1 <3.1 <4.4 <3.1 <3.7 <l.9
<6.8 <6.1 (6.4 <8.5 (6.8 (9.4 (4.6 <1.8 <3.6
] Ce-141 <5.9 Ce-144 (26.5 <29.4 <26.8 (27.6 <38.8 <33.3 <44.4 <29.5 <35.9 <l5.5
) ine error given is the probable counting error at the 95% confidence level. Less than (<) values are based on 4.66 sigma counting error for background ,
samples.
All results are decay corrected to the time of collection. -
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