ML20196B527
| ML20196B527 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/09/1988 |
| From: | Kosarek L SUSQUEHANNA VALLEY ALLIANCE, LANCASTER, PA |
| To: | |
| Shared Package | |
| ML20196B518 | List: |
| References | |
| OLA, NUDOCS 8806300287 | |
| Download: ML20196B527 (16) | |
Text
.
G Finally, I looked at the dose to the GIT from one year's consumption of Ru-106, Ce-144, co-60 and Pu-239. The values, respectively, are < 47 mrem,
< 27 mrem, 1.44 mrem and < 0.07 mrem.
Thus in all these cases the GIT is not the oigan of highest dose.
In Conclusic I believe that the studies made by GPU and by the NRC staff are woefully inadequate and much more data chould be provided before deciding the best way to be rid of this problem, i.e. before deciding to let go of the bear we have by the tail.
I-r1
. Morg u
8806300207 8006?.O PDR ADOCK 0500 0
G 9
S Appendix Dose Rate R(mram/ year) = q( Ci) 3.7 x 104 (dis /8 pCi) EQN (MeV/ dis X rem / rad)
X 1.602 x 10'0 (erg /MeV) 1/m (1/g) 10 (mrem / mrad) x 3,600 x 24 x 365 (S/y) x 1/100 (grad / erg) = 1.87 x 1 EQN q mrem /y (1)
Dose from a Single Intake D=
Re dt = R(1-e-Xt),1.87 x 10 EQN q (1-e"
)m 2)
-At o
Dose from Continuous Intake dq/dt + Aq = P q=f(1-e
~
)
P = A(cc/y) f x C(pCi/cc) = 2,200 (cc/d) 365 (d/y) f C g
g 5
= 8.03 x 10 fG g
1
.t 1.87 x 10 EQN x 8.03 x 10' f c p
D=
(1-e, g) de =
0 l
-At EQN f C (t + f 13 1.50 x 10 p
D=
mrem (3) l Dose from One Day's Intake after Exposure of t Years q1 = 2,200 f C g
7
-t
.t 1.87 x 10 EQN 2,200 f C e de g
D",o m
I A-1 l
l
4.11 X 10
.'EQN f G (1-e-t) g D=
mrem (4) 10 4.11 X 10 EQN f G g
d D=
mram for t=
(4)
Dose to Lower G.T. Tract (Colon) from One Year's Continuous Exposure at ICRP-2 MPC Level (MPC)
!"correspondstoR=15,000 mrem /ydoseratewhen exposure time, t, is >> 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> C x 1,5 mrem (5)
D1=
68
)LLI r
A-2
w mw
EXHIBIT C AFFADAVIT OF IDUIS KOSAREK'IN SUPPORT OF C0tVrENTIONS 3,4,AND 5 l
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I,CVIEW OF ORIGINAL AmYu..u.
.a-D i S.s O S A L CJ
% L... u r.
c.
. :4 u N PER DOCUMEN T NUREG-U /..:. (1; ib3Ld3
.N LEPTEMBE;e J. J t icA cY h e t_
~
o..
OF NUCLE.,, REACTOR REGUt.ATION CF THE NUCLEAR REOULA(Onv C W 'il S11 Gs, nZRE WERE FOUR DISPOSAL ALTERNATIVES WHICH THE NUdLEAR REGULATORY COMM1EGION (NRC) CONSIDERED VIABLE FOR THE DISPOSAL OF ACCIDENT GENERniED WATER AT c
UNIT 2 OF THE THREE MILE ISLAND FACILITY OPERATED BY GENERA-PUBLIC UTILITIES.
THE FOUR ALTERNATIVES CONSIDERED BY THE NRC ON ? AGE 13 OF NUREG-0732 TO BE VIABLE BY THE NRC IN 1980 ARE:
"1) HOLDING THE PROCESSED WATER IN TANKS AT TMI FOR APPROXIMATELY 60
- YEARS,
- 2) RELEASING THE PROCESSED UATER TO THE RIVER AT TMI,
- 3) RELEASING THE PROCESSED WATER VAPOR TO THE AIR BY FORCED EVAPORATION AND,
- 4) RELEASING THE PROCESSED WATER VAPOR TO THE AIR BY NATURAL EVAPORATION".
REVIEW OF ORIGINAL ALTERNATIVES FOR DECONTAMINATION OF RADIOACTIVE WATER THE ACCIDENT GENERATED WATER CONTAINS RADIOACTIVE MATERIA S WHICH MUST BE REMOVED FROM THE WATER TO MAINTAIN COMPLIANCE WITH 10 CFR PART 20, APPENDIX B (2) WHF.NCVER THE WATER IS DISCHARGED BY ANY OF YHESE METHODS.
THE METHODS WHICH HAVE BEEN EVALUATED BY THE NUCLEAR REGw AT0jY CCMMISSION FOR DECONTAMINATING RADIOACTIVE WATER ARE LISTED IN NUREG-0732 (1).
THE FIVE DECONTAMINATION ALTERNATIVES WHICH THE NUCLEAR REGULATORY COMMISSION HAD EVALUATED IN 1980 ON PAGE 10 OF NUREG-07C2 ARE A3 FOLLOWS:
"A ZEOLITE AND RESIN SYSTEM, AN EVAPORATION AND RE;i.
u Y S i e.M,
DIRECT BITUMINIZATION, SOLIDIFICATION WITH PORTLAND CEMENT AND l
FILTRATION FOLLOWED BY STORAGE".
l FAGE 2 OF 15
t.
e.
CriDICC GF EVAPORA ; Ica ' FOR-DIS:'OSAL OF M _' ;. ) L:
J2N: :w :i J a:4. c b.ITHIN DOCUMEr0 4410-i-35 -L-OO12/ U330' Wi d Ch '0 166 Ut. s Jr.;
.. rnx 0 '.t G U.
c v.
OF GENERAL PUBLIC UTILITIES NUCLEV D.ATED FEBRUArlY 16, 1980 (3 ), G1E NRC DISPOSAL METHOD CHOSEN DY GENERAL PUBLIL. UTILITIES TO DISFUSE OF THE ACCIDCNT GENERATED WATER IS NRC ALTERNATIVE #3 AS SPECIFIED IN NUREd 0732 WHICH IS RELEASING THE PROCESSED WATER VAPOR TO THE AIR BY FORCED EVAPORATION.
PER DOCUMENT 4410-88-L-OO12/0335P WHICH WAS. ISSUED BY F R STANDERFER OF GENERAL PUBLIC UTILITIES NUCLEAR DATED FEBRUARY 16 1988 (3), THE NRC RECOMMENDED DECONTAMINATION METHOD CHOSEN BY GENERAL PUBLIC UTILITIES TO TREAT THE RADIOACTIVE ACCIDENT GENRATED WATER PRIOR TO DISPOSAL IS SIMILAR TO THE NRC ALTERNATIVE ON PAGE 10 OF AN EVAPORATUR AND RESIN SYSTEM.
IN DOCUMENT 4410-88-L-OO12/0335P WHICH WAS ISSUED BY F R STANDERFER OF GENERAL PUBLIC UTILITIES NUCLEAR DATED FEBRUARY 16, 1988 (3), THE DOCUMENT SPECIFIES ON PAGE 1 THAT AN EVAPORATION SYSTEM IS PROPOSED TO BE USED TO ACCOMPLISH THE CONTROLLED DISPOSAL OF APPROXIMATELY 2.3 MILLION GALLONS OF "ACCIDENT GENERATED WATER".
THE USE OF THE EVAPORATION SYSTEM FOR TREATING ACCIDENT GENERATED WATER IS SUBJECT TO APPROVAL BY THE NRC PER NUREG-06G3 AS SPECIFIED IN A POLICY STATEMENT
..;dCH 13 IN THE PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT OF 1981 (4).
THE EVAPORATION PROCESS IS DESCRIBED BY NRC ON PAGE 11 OF DOCUMENT NUREG 0732 (1) ISSUED IN SEPTEMBER OF 1980 BY THE OFFICE OF NUCLEAR REACTOR i
REGULATION OF THE NUCLEAR REGULATORY COMMISSION.
THE NRC DESCRIPTION OF EVAPORATION IN NUREG-0732 IS AS FOLLOWS:
"THE WATER WOULD BE REDUCED TO 1/30 OF ITS ORIGINAL VOLUME AND THE L
RADIOACTIVITY WOULD BE REDUCED TO 1/1000 ITS ORIGINAL CONCENTRATION (EXCEPT FOR TRITIUMi".
PAGE 3 OF 15
a d C uts T A 7.i N A T 1 O N F HC ! CR. Ci< c
' Jhi,.. o
.cr. FIT.D r.f..; ihL.1
,n.
J..---__-____..---.-_...--..-.
SINCE A DECONTAMINATION FALiuA (D,)
IG L i. ; i i c.;.D Ch PiL c C _
.JouL. L
-0142 ($) AS THE RATIO OF THE CONuENTRA110N OF A GIVEN COMPor.ilai In ind FEED AT ANY TIME TO THE CONCENTRn l # i-UR l HE SAME COMPONENT... THE IREAIED WATER AT THE SAME TIME, THE 1/1000 REDUCTION SPECIFIw IN NURCC 0732 (1) IN 1980 IS EQUAL TO A DECONTAMINATION FACTOR (Df) OF 1000.
IN DOCUMENT 4410-88-L-OO12/0335P WHICH WAS ISSUED BY F R 01ANDERFER OF GENERAL PUBLIC UTILITIES NUCLEAR DATED FEBRUARY 16, 1988 (3), THE DOCUMENT SPECIFIES ON PAGE 18 THAT THE DECONTAMINATION FACTOR FOR RADIOACTIVE PARTICULATE OF THE PROPOSED EVAPORATION SYSTEM IS 1000 (SEE TABLE 1).
THIS DECONTAMINATION FACTOR OF 1000 IS DEMONSRATED UTILIZING THE DATA LISTED IN TABLE 3-2 (P 18)
WHEN YOU COMPARE THE RATIO OF THE CONCENTRATION OF RADIOACTIVE PARTICULATE OF A GIVEN COMPONENT IN THE INFLUENT TO THE CONCENTRATION FOR THE SAME COMPONENT IN THE EFFLUENT, THIS RATIO WHICH IS THE DECONTAMINATION FsLTCa LCUALS 1000 IN ALL CASES OF RADIOACTIVE PARTICULATE.
THE DECONTAMINATION FACTORS FOR 'nE VOALTILE GASSES TRITIUM AND IODINE-129 ARE 1.
THE EVAPORATION PHOCEbS AS DESCRIBED BY NKU UN PHGE 11 OF DCuuMENI NUREG-0732 (1) ISSUED IN SEPiEMBER OF 1980 BY THE OFFICE OF NcLLEAR REACTOR REGULATION OF THE NUCLEAR REGULATORY COMMISSION HAS A DECONTAMINATION FACTOR OF 1000.
THE PROPOSED EVAPORATION PHLiidS DESCRIBED IN DOCUMENT 4410-88-L-OO12/0335P WHlCH WAS ISSUED Br FR STANDERFER OF GPUN DATED FEBRUARY 16, 1908 (3),
INCOPQRATES A DECONTAMINATION FACTOR OF 10v0.
THE DECONTAMINATION FACTOR O.2 1000 FOR AN EVAPORATOR IS FURTHER UTILIZED IN THE GPUN RESPONCE ON PAGE 22 TO INTERROGATORIES DATED FEBRUnkY 19, 1908(6) IN ANSWER 320. THE 520 ANSWER SiATCL iHAT:
PAGE 4 OF 1$
4 JABLE;1. A JutHAMINHfluN FACiOR CALLutaTcw
. i: th u s s
W,9 5 w m/;e/e5 s3)
INFLUENT EF FLuius IreLudN r/EFFLu NT
' CONSTITUENT CONCENTRATION CONCENTRAiIGN DEUUNTAMINATION uCi/ml uCi/ml FACT 0A TRITIUM 0.130000000000-0.130000000000 1
CESIUM-137 0.000037000000 0.000000037000' 1000 CESIUM-134 0.000000880000 0.000000000880 1000-STRONTIUM-90 0.000110000000 0.000000110000 1000 ANTIMONY-125/
TELLURIUM-125m 0.000002300000 0.000000002300 1000 CARBON-14 0.000100000000 0.00000010s000 1000 TECHNETIUM-99
.0.000001000000 0.000000001000 1000 IRON-55 0.000000480000 0.000000000480 1000 COBALT-60 0.000000480000 0.000000000480 1000-IODINE-129 0.000000600000 0.000000600000 1
. CERIUM-144 0.000001800000 0.000000001800 1000
' MANGANESE-54 0.000000040000 0.000000000040 1000 COBALT-58 0.000000040000 0.000000000040 1000 NICKEL-63 0.000000600000.
0.000000000600 1000 ZINC-65 0.000000098000 0.000000000098 1000 RUTHENIUM-106/
RHODIUM-106 0.000000330000 0.0000000.vc50 1000 SILVER-110m 0.000000056000 0.000000000056 1000 PROMETHIUM-147 0.000004800000 0.000000004800 1000 EUROPIUM-152 0.000000000380 0.000000000000 1000 EUROPIUM-154 0.000000044000 0.000000000044 1000
- EUROPIUM-155 0.000000110000 0.000000000110 1000 URANIUM-234 0.000000010000 0.000000000010 1000 URANIUM-235 0.000000012000 0.000000000012 1000 URANIUM-238 0.000000012000 0.000000000012 1000 PLUTONIUM-238 0.000000012000 0.000000000012 1000
. PLUTONIUM-239 0.000000014000 0.000000000014 1000 PLUTONIUM-240 0.000000014000 0.000000000014 1000 PLUTONIUS a..
0.000000650000 0.000000000650 1000
~ AMERICIUM-241 0.000000012000 0.000000000012 1000 CURIUM-242 0.000000100000 0.000000000100 1000 y
TOTAL PER REPORT 0.130261494380 0.000000260894 ACTUAL 0.130261494380 0.1300003609 1
PAGE 5 OF 15
i "its MElv-x u a.i R Y U Y._ a inndiIUs F ur-. n i s D. o; u
- r... e v-T O BE C. ' ).
ii/1000).
THE CARRY OVER OF 1 EFFLUENT TO AN INFLUENT OF 10<.0 IJUAuS A DECONTAMINATION FACTOR OF 1000.
FURTHER, THE S28 ANSWER IN THE INTERROGATORIES DATED FEBRUARY 19, 1988 SPECIFIES THAf:
"TH E V_;JMhD FRACTION (O.1%) IS BASED UPON ROUTINE PERFORMANCE EX'PERIENCE WITH TYPICAL EVAPORATOR SYSTEMS, AND IS ALSO UTILIZED BY THE NRC STAFF IN PEIS, SUPPLIMENT No.2(7)FOR RELEASE CALCULATIONS".
HENCE, A DECONTAMINATION FACTOR OF 1000 WAS USED FOR EVAPORATION BY THE NRC STAFF IN PEIS, SUPPLIMENT No.2 (7) FOR RELEASE CALCULATIONS.
THE DECONTAMINATION FACTOR OF 1000 FOR AN EVAPORATOR IS FURTHER UTILIZED IN THE NRC RESPONSE TO INTERROGATORIES PAGE 20 DATED FEBRUARY 22, 1986 (8)
ANSWER TO INTERROGATORY 22.
THE SECTION B ANSWER TO INTERROGATORY 22 STATES THAT:
"NUREG-0017 REV.1 (MARCH 1995) PROVIDE (D) NRC STAFF RESULTS OF DECONTAMINATION FACTORS MEASURED AT SEVERAL NUCLEAR POWER PLANTS AND BASED ON A GENERIC REVIEW OF NUCLEAR INDUSTRY DATA.
NUREG-0017 LlSTS A DECONTAMINATION FACTOR OF 1000 (i. e.
O.1%) AS fHE BESf REFEhm..u
'M ESTIMATION EVAPORATOR OPERATING PERFORMANCE".
THE DECONTAMINATION FACTOR OF 1000 FOR AN EVAPORATOR HAS BEEN OSED BY NRC AND GPUN SINCE 1980.
A REVIEW OF NUREG-0017 (9) AS CITED BY NRC STAFF IN THE RESPOrjSE TO INTERROGATORIES DATED FEBRUARY 22, 1988 (8) IN ANSWER TO INTERROGATORY 22, NUREG-0017 STATES THE FOLLOWING ON RAGE 2-42.
PAGE 6 OF 15 l
{
"2.2.21.2 'dASES i
THE: Ut:. CON TAN N A s ION FAC TORS f-OR EVAP wha 70riS arc. Us M i ; E c.. i ' ;.
3 FIl4 DINGS OF A GE:dR [C REVIEW Ln ORNL (Oss Hil;Ot;. mi ton.% LmDL:A;uRY.
OF EVAPORAiORS USEi.;-IN THE NULLEAR INDiJSTM (REF. 32, Cium.% 7 5.,,
,,c PRINCIPAL CONCLUSIONS RECHED IN THE REPORT ARE:
1.
DECONTAMINATION FACTOR 5 t,c 10000 CAN BE EXPECTED FOR NONVOLATIL2 RADIOACTIVE NUCLIDES IN A SINGLE STEP EVAPORATOR.
2.
DECONTAMINATION FACTORS FOR IODIDE ARE A FACTOR QF 10 LE65'THAN friE Df FOR NONVOLATILE NUCLIDES.
3.
DECONTAMINATION FACTORS FOR WASTES CONTAINING DETERGENTS THAT TEND TO FOAM ARE A FACTOR OF 10 TO 100 LOWER THAN Df 's EXPEC FED FOR NOt#0AMING WASTES.
THESE CONCLUSIONS HAVE BEEN EXTENDED TO TAKE INTO ACCOUNT THE FOLLOWING FACTORS:
- . FOR NONVOLATILE NUCLIDES IN THE NONFOAMING SOLUTION, A Df OF 10000 IS USED.
2.
THIS~VALUE IS REDUCED TO 1000 FOR BORIC ACID WASTES BECAUSE THE TENDENCY FOR FOAMING IN THESE SOLUTIONS c3EE 5 ADOVE).
3.
IF AN EVAPORATOR IS USED FOR DETERGENT WASTES, THE Df FOR THE EVAPORATOR IS REDUCED TO 100 TO REFLECT CARRYOVER DUE TO FOAMING THAT REDUCES THE Df."
PER THE ANSWER BY THE NRC STAFF IN THE RESPONSE TO INTERROGA*/ChiEG OF FEBRUARY 22, 1988 (B) IN ANSWER TO INTERROGATORY 22 THE NRC STAFF Si4TES THAT NUREG-OO17 PROVIDED NRC STAFF WITH A DECONTAMINA TION FACiva OF 1000 AND NUREG-OO17 SPECIFIES A DECONTAMINATION FACTOR OF 1000 IN fr>E BASE:
"2.
THIS VALUE Id REDUCED TO 1000 FOR BORIC ACID WASTES BECAUSE THE 2
TENDENCY FOR FOAh1NG IN THESE SOLUTIONS."
THEREFORE,THE ACCIDENT GENERATED WATER IS CONSIDERED A BORIC ACID WASTE.
PAGE 7 OF 16 l
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$ i A C C l a d N i U c.r. d s i L U WAIEn HAu c.Le h LON0iudRcu :O c.s,
'A DdCONTAMINATION FACI 06 OF w0o Fors CLT1c:AT IGW OF hvneOMiLa UFEusi1HG PERFORMANCE AS A BORIC ACID.WA0TE IN:
NUREG-0732, 1980 (1):
'NUREG-0683, 1981 (4)
NUREG-0683 SUPPLIMENT No.2, 1987(7)
DOCUMENT 4410-88-L-0012/33SP, 1988 (3)
INTERROGATORIES RESPONSE BY GPUN, 2/19/88 (6)
INTERROGATCRIES RESPONSE BY NRC STAFF, 2/22/88 (8)
APPLICATION OF GENERIC EVAPORATION DATA TO PARTICULAR TMI-2 CHEMISTRY SINCE THE EVAPORATOR OPERATING PERFORMANCE IN NUREG-0017 IS BASED ON GENERIC DATA, TMI-2 WATER CHEMISTRY IS A SIGNIFICANT PARAMETER IN EVALUATING THE ACHIE.HrLE DECONTAMINATION FACTOR.
PER THE GPUN RESPONSE l
ON PAGE 31 TO INTERROGATORIES DATED CEBRUARY 19, 1986 (6) IN ANSWER S43 IT IS STATED THAT:
"WATER WITH THIS PARTICULAR CHEMISTRY IS UNIQUE TO TMI-2.
NO TWO BODIES OF WATER HAVE EXACTLY THE SAME CHEMISTRY".
IN APPLY 1NG THE GENERIC DATA OF NUREG-0017, THE DECONTAMINATION FACTOR OF AN EVAPCRA10R WILL BE EVALUATED FROM THE PERSPECrIVE OF WHAT THE lNFLUENT WATER CONTAINS BE IT: NONVCLATILE NUCLIDES IN A NONFOAMING SOLUTION, IODINE, DETERGENT WASTES, OR BORIC ACID WASTES THE UNIQUNESS OF THE ACCIDENT GENERATED WATER AT TMI-2 IS FURTiHER CONFIRMED IN THE CHEMICAL FORMULATIONS AND VARIOUS PROCESS CHEMICALS WHICH WERE ADDED SUBSEQUENT TO THE NUREG'-0732 ANALYSIS BY NRC 1N 1980.
ON PAGES 36 AND 37 UF INTERROGATORIES DATED FEBRUARY IV,
,cJio; IN G'uNr ANSWER No. 552, CHEMICALS USED IN 1986 DURING THE CLEANUP INCLUDE:
COAGULANTS SUCH AS 30.6 GAL OF BETZ 1182, 0.75 GAL OF BETZ 1192 AND 2.4 GAL OF CALGON 289, DIATOMACEOUS EARTH SUCH AS 880 POUNDS OF STANDARD SUPER CEL PLUS 20 POUNDS JF CELITE 503, AND ADDITIONS OF 350 GALLONS TRITON-X-100 TO THE AGW INVENThAGE8OF 15
FCCUSSiNG ON THE WATEk-IHdhrhEfC M ui
.#_e W,-iiUn
- ._; a.
. :_, r.
c..u u,
.PERSFECTIVE TO NUREG-0017 (9), THE CnAhaGTERISTICS OF lHL
.L R:.d l C A L %Ccc g
- TO THE ACCIDENT _ GENERATED WATER IN THE GREATEST VOLUME SHOULD BE
! UNDERSTOOD TO'SPECIFY THE CORRECT NUREG-OO17 EVAPORATOR DECONTAMINATION FACTOR.
Oi,. uts 6 UF INTERROGATORIES DATED MARCH 30, 1963 (10) IN GPUN ANSWER No.
6, THE ADDITIVE TRITON-X-100 IS DESCRIBED AS FOLLOMS:
"TRITON-X-100 IS A NONIONIC SURFACTANT WITH THE CHEMICAL NAME
- ISOOCTYLPHENOXYPOLY THOXYETHANOL ETHYLENE OXIDE.
IT IS USED AS A A DEGREASER AND A DECONTAMINATION AGENT FOR FLOORS, WALLS, PIPING AND MECHANICAL EQUIPMENT".
THE'NONIONIC SURFACTANT TRITON-X-100 IS MANUFACTURED BY THE ROHM & HAAS COMPANY LOCATED AT INDEPENDENCE MALL WEST IN PHILADELPHIA, pet 4NSYLV ANI A (11) WITH THE PHONE NUMBER OF 2155923000.
WITHIN THE 'ROHM AND HAAS SPECIALTY CHEMICALS DETERGENT FORMULATION MANUAL'(12), ON PAGE 126, A A NONIONIC SURFACTANT IS DESCRIBED'AS:
"SURFACTANT THAT CONTAINS NEITHER POSITIVELY NOR NEGATIVELY CHARGED (IONIC) FUNCTIONAL GROUPS AND LCES N_G IONIZE IN SOLUTION. SUCH SURFACTANTS (eg ALKYLPHENOL ETHOXYLATES) HAVE BEEN FOUND f0 BE a
PARTICULARLY EFFECTIVE IN REMOVING OILY SOIL."
THE.NALCO HANDBOOK (13), A PROFESSIONA' REFERENCE IN THE WATER TREATMENT INDUSTRY DEFINES A SURFACTANT ON PAGE 6-8 AS A SURFACE ACTIVE AGENT; i
"USUALLY AN ORGANIC COMPOUND WHOSE MOLECULES CONTAIN A HYDROHPYLIC GROUP
[
AT ONE END AND A LIPOPHILIC GROUP AT THE OTHER."
PAGE 9 OF 15 t
e
_m..,__,.__
- W11 din.THE 'ROHM AND r.AAS SPECI ALTY Cr!EMICALS ' Ud EHJi/..
- ':T<MULHTI ON MAmjAL ' (12 /,' UN PAGE 124, A DEGREhSER IS DEFINc. 45:
" A SPECI ALTY PRODUCT THAT REMOVES GREASE AND GREASY / OIL't 5 OILS FROM HARD SURFACES.
THEIR BASIC INGREDIENTS ARE SURFACTANTS THAT PENETRATE AND EMULSIFY.
TriEY MAi ALSO CONfeiN ALCOHOL OR A GLYCOL DEfs.VATIVE TO BOOST CLEANING AND AID SOLVENCY."
THE MATERIA'. SAFETY DATA SHEET (MSDS) ISSUED BY ROHM Arw HAAS ON 1RITON
-X-100 (14) SPECIFIES THE COMMON NAME OF TRITON-X-100 AE OCTYLPHENOXY-
- POLYETHOXYETHANOL NONIONIC SURFACTANT.
THE BOILING POINT OF TRITON-X 100 IS SPECIFIED IN THE MSDS TO BE 520 F. WITH A BOILING POINT OF 520 F.
WHENEVER TRITON-X-100 ENTERS THE EVAPORATOR, IT WILL NOT BOIL BUT WILL CONCENTRATE IN THE EVAPORATOR AND ULTIMATELY BE CONTAINED IN THE EVAPORATOR BOTTOMS TO BE SOLIDIFIED.
THE TRITON-X-100 SPECIFICATION a
SHEET ISSUED BY ROHM AND HAAS (11) DESIGNATES THAT:
"TRITON-X-100 SURFACTANT IMPROVES THE DETERGENCY AND WETTING PROPERTIES OF_ LAUNDRY, METAL CLEANING AND SPECIALTY FORMULA 1IONL FLc.. iuML AND INDUSTRY."
THE TRITON-X-100 SPECIFICATION SHEET (11) STATES THAT TRITON-X-100 IS A "HIGHLY EFFECTIVE HARD-SURFACE DETERGENT."
PAGE 10 OF 15 b
O J
5
CHEMICAC MODIFICATkC" OF ACW AT TMI-2 "O BE DE ERGENT U^7'c '0 C"
'c25 a----_-----------..------------..--------_------------
THE NRC (C) HAS SPECIFIED THAT THEY RELY ON NUREG-OO17 Y 7" T C REVIEW OF NUCLEAR INDUSTRY DATA FOR ESTIMATING EVAPORATOR ~7~ RATING PERFORMANCE.
PER THE MANUFACTURER, TRITON-X-100 IS A DETEF.3ENT (11).
GPUN HAS CTATED THAT TRITON-X-100 IS CONTAINED IN THE ACC!rINT CENERATED WcTER (6).
NUREG-OO17 STATES THAT:
"3.
IF AN EVAPORATOR IS USED FOR DETERGENT WASTES, THE Df FOR THE EVAPORATOR IS REDUCED TO 100 TO REFLECT CARRYOVER DUE TO FOAMIlG THAT
. REDUCES THE Df."
(9)
BASED ON THE ADDITION OF THE DETERGENT TRITON-X-100 BEFORE 1986 TO THE AGW,. CITING NUREG-OO17, THE ACCIDENT GENERATED WATER SHOULD BE CLASSIFIED AS DETERGENT WAGTE AND THUS THE EVAPORATOR DECONTAMINATION FACTOR USED FOR THE ACCIDENT GENERATED WATER AT TMI-2 IN 19?S SHOULD BE 100 NOT 1000.
THE KNOWLEDGE THAT CHEMICALS SUCH AS DETERGENTS WILL AFFECT THE OPERATING EFFICIENCY OF AN EVAPORATOR HAS BEEN DEMCNSTRATE0 BY GPUN.
IN THE AFFIDAVIT OF DAVID R.
BUCHANAN, MANAGER, "<ECOVERY EN7INEERING FOR CPUN (15) IN CTATEMENT 11, MR. BUCHANAN STATES THE FOLLOWIN2:
"FUAPORATORD HAVE BEEN USED EXTENSIVELY AND FOR MANY YEARC. AND THE FACTORS THAT AFFECT THEIR EFFICIENCY, ARE WELL KNOWN.... THE FRESENCE OF "DETERGENTS" WHICH CAN REDUCE HEAT TRANSFER RATES AND PPODUCE VAPOR WITH A HIGHER MOISTURE CONTENT."
IN THIS CASE "HIGHER MOISTURE CONTENT" REFERS TO A HIGHER LEVEL OF CONTAMINATION IN THE VAPOR.
THE I9ONY OF ADDING THE DETERGENT TRITON-X-100 IN 1955 IN PERSPECTIVE TO THE OPERATION OF AN EVAPORATOR WITH AN EFFICIENT DECONTAMINATION FACTOR IS THAT WHEN TRITON-X-100 WAS ADDED TO THE A G W THERE WAG NOT ANY CONSIDERATION FOR THE AFFECT ON EVAPORATOR EFFICIENCY EST THE PAGE 11 OF 15
DONSIDERATION FOCUSSED CN THE ADLERSE AFFECT OF TRITON ~x
- G Q rHE SDS AND EPICOR II SYSTEMS.
THE USE OF THE DETERGENT TRITON-X..O B'-
GPUN AND ITS ADVERSE AFFECT IN PEPSPECTIVE TO THE SDS AND EPICCP SYSTEMS
.IS STATED IN STATEMENT 16 IN.THE AFFIDAVIT OF KERRY L HARNER (16):
' TRITON-X-100....CAN ADVERSELY AFFECT THE SDS AND EPICOR II SYSTEMS...
.AND HAS NOT BEEN USED SINCE 1985."
'THERE IS NO CONSIDERATION FOR THE UNDESIRABLE USE OF A DETERGENT IN AN EVAPORATOR APPLICATION.
THE USE OF NUREG-OO17 DATA IN 1980 WHICH WAS APPLIED TO THE AGW PRIOR TO CHEMICAL ADDITIONS IN 1985 TO GENERATE A DECONTAMINATION FACTOR FOR AN EVAPORATOR OF 1000 IS UNFOUNDED ESPECIALLY WHEN THE FACTDRS FOR A DECONTAMINATION FACTOR ARE: NONVOLATILE RADIOACTIVE NUCLIDES, IODIDE,
' BORIC ACID AND DETERGENTS.
THE CHOICE OF THE DECONTAMINATION' FACTOR uF 1000 FOR AN EVAPORATOR IS A CHOICE FOR GPUN BECAUSE PER THE ANSWERS TO INTERROGATORIES DATED MARCH 30, 1988 (10) IN GPUN ANSWER No.22(1st)
"THE CARRY OVER O.1% IS BASED ON ROUTINE PERFORMANCE EXPERIENCE.....AND NOT UPON TESTS OR RESEARCH."
THE CHOICE OF A DECONTAMINATION FACTOR OF 1000 IS ONLY A CHOSEN VALUE WITHOUT TESTING OR RESEARCH.
NUREG/CR 1992 (17) SPECIFIES THAT THE i
DECONTAMINATION FACTORS ACHIEVED IN EVAPORATORS FOR RADIOACTIVE PARTICULATE CAN VARY WITH THE SAME INFLUENT SOLUTION BY A FACTOR OF 72 FROM 1667 TO 23 OVER TIME.
THE CRITICAL PARAMXFFRS INCLUDE: FEED RATE.
RADIONUCLIDE CONCENTRATION IN THE BOTTOMS, MOISTURE CARRYOVER (FOAMING, i
.ENTRAINMENT, SPLASHOVER).
THE PARAMETERS WHICH CAUSE VARIATION OF THE t
DECONTAMINATION FACTOR FOR AN EVAPORATOR HAVE NOT BEEN ADDRESSED IN l
f WRITING BY GPUN INCLUSIVE OF THE PROPOSAL OF 1986 (18).
THERE IS NO DEMONSTRATED BASIS TO OPERATE AN EVAPORATOR WITH A Df OF 1000.
PAGE 12 OF 15 J'
...- - -, -. -. - _ =.,, _ -
t t,
SUMMARY
THIS' AFFIDAVIT SPECIES THA'T IN THE INTERIM CF 1980 AND '981, A GENERIC REVIEW OF EVAPORATOR DESIGN CRITERIA SPECIFIED A DECONTAMINATION FACTOR OF 1000.
THIS DECONTAMINATION FACTOR OF 1000 WAS CITED IN A VARIETY OF DOCUMENTS INCLUDING:.NUREG-0732 (1),NUREG-0683/PEIS OF 1951 AND 1987 AND GPUN STATEMENTS (3,6) AND NRC STATEMENTS (8).
SUBSEQUENT TO THE ORIGINAL-CITATION, A DTERGENT WAS ADDED TO THE ACCIDENT GENERATED WATER 1
AND MODIFIED THE GENERIC CRITERIA UNDER WHICH THE ORIGINAL DECONTAMIN-ATION FACTOR WAS DERIVE'D.
THE ACCIDENT GENERATED WATER SHOULD BE CONSIDERED AS A DETERGENT WASTE AFTER 1985.
THE DISPOSAL ALTERNATIVES AND-THE PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT MADE SEFORE 1984 ARE NO LONGER VALID AND ALL CALCULATIONS REQUIRE REEVALUA.' ION.
THE REEVALUATION IS IN PERSPECTIVE TO~THE QUANTITY OF RADIONUCLIDES RELEASED AND THE ASSOCIATED PROCESS MODIFICATIONS SUCH AS BOTTOMS CONCENTRATION.
THIS AFFIDAVIT DEMONSTRATES WHAT CAN OCCUR WHEN A GENERIC DATA BASE IS UTILIZED AS A DESIGN BASIS AND THE WATER QUALITY IS CONSIDERED TO BC A CONSTANT AND FURTHER SCRUTINY OF THE WATER IS NOT CONDUCTED TO UPDATE THE DESIGN BASIS.
THE USE OF THIS GENERIC DATA BASE SHOULD BE CONFIRMED IN TESTS OR RESEARCH TO DETERMINE THAT THE UNIQUE. WATER CAN BE PROCESSED AS THEORIZED.
b s
'i l
PAGE 1 3 Dir 15
I:EFEDENCES 1F NUREG-0732.
1980.
ANSWERS TO FREQUENTLY ASKED CUESTiONP M CLEANUP ACTIVITIES AT THREE MILE ISLAND, UNIT 2.
ISSUED BY TPE OFFICE OF NUCLEAR REACTOR REGULAT!ON 0F THE U S NUCLEAR REGULATORY CC""IErION
- 2) CODE OF FEDERAL REGULATIONS.
1978.
TITLE 10, PART 20, APPENDIX B.
3)-DOCUMENT 4410-88-L-OO12/0335P.
1988.
ACCIDENT GENERATED WATER DISPOSAL SYSTEM DESCRIPTION BY F R STANDERFER OF GPUN DATED FEBRUARY 16, 1988.
- 4) NUREG-0683. 1981. FINAL PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT
-ISSUED BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE U S NUCLEAR REGULATORY COMMISSION.
ALSO SEE U S NUCLEAR REGULATORY COMMISSION POLICY STATEMENT 46 FEDERAL P"GISTER 24, 764.
- 5) NUREG/CR-0142.
1978.
THE USE OF EVAPORATION TO TREAT FADIDACTIVE LIQUIDS IN LIGHT-WATER-COOLED NUCLEAR REACTOR POWER PLANTS.
CO-AUTHORED BY HW GOODBEE AND AH KIBBEY OF OAK RIDGE NATIONAL LABORATORY FOR THE OFFICE OF NUCLEAR REGULATORY RESEARCH OF THE U S NUCLEAP REGULATORY COMMISSION.
- 6) INTERROGATORIES RESPONSE BY GPUN. 1988.
LICENCEE'S ANSWERS. TO SVA/
TMIA'S INTERROGATORIES TO GPU NUCLEAR CORPORATION BY F R STANDERFER OF GENERAL PUBLIC UTILITIES NUCLEAR DATED FEBRUARY 19, 1988.
- 7) NUREG-0683, SUPPLIMENT No.
2.
1987. PROGRAMMATIC ENVIRONMENTAL IMPACT STATEMENT, FINAL SUPPLIMENT DEALING WITH DISPOSAL OF ACCIDENT GENERATED WATER BY THE TMI CLEANUP PROJECT DIRECTORATE OF THE U S REGULATO^Y COMMISSION.
- 8) INTERROGATORIES RESPONSE BY NRC STAFF.
1988.
NRC STAFF RESPONSE TO INTERROGATORIES FROM TMIA/SVA BY C P WOODGEAD, COUNSEL FOR NPC STAFF DATE FEBRUARY 22, 1988.
- 9) NUREG-OO17.
1985. CALCULATION OF RELEA3ES OF RADIOACTIVE MA'ERIALS IN GASEOUS AND LIQUID EFFLUENTS FROM PRESSURIZED WATER REACTORS.
ISSUED BY THE OFFICE OF STANDARDS DEVLOPMENT OF THE U S NUCLEAR REGULATORY COMMISSION.
- 10) INTERROGATORIES RESPONSE BY GPUN. 1988. LICENCEE'S ANSWERS ?C SVA/
TMIA'S SECOND SET OF INTERROGATORIES TO GPU NUCLEAR CORPORATION BY FR STANDERFER OF GENERAL PUBLIC UTILITIES NUCLEAR DATED MARCH 30, 1988.
- 11) ROHM ^ND HAAS CO. 1986.
TRITON-X-ido NONIONIC SURFACTANT DOCUMENT CS-427a.
PHILADELPHIA, PA.
- 12) ROHM AND HAAS CO. 1986.
SPECIALTY CHEMICALS DETERGENT FORMULATION MANUAL CS-480a.
PHILADELPHIA, PA.
- 13) NALCO CHEMICAL CO.
1979.
THE NALCO WATER HANDBOOK EDITED BY F N KEMMER AND PUBLISM*D BY McGRAW HILL DOOK CO.,
NEW YORK, NY.
I
- 14) TRITON-X-100 MATERIAL SAFETY DATA SHEET.
1987.
DATA PROVIDED BY l
RCHM AND HAAS Co.,
PHILADELPHIA, PA.
l PAGE 14 OF 15 l
C
- 15) AFFIDAVIT OF DAVID R.
BUCHANAN.
1988.
CONTENTIONS 4b IN PART AND 6 ON CHEMICALS DATED MAY 13, 1988.
- 16) AFFIDAVIT OF KERRY L.
HARNER.
1988.
CONTENTIONS 4b IN PART AND 6 ON CHEMICALS DATED MAY 13, 1988.
- 17) NUREG/CR1992.
19S1.
IN PLANT SOURCE MEASUREMENTS AT FOUR PWRs.
CO-AUTHORED BY JW MANDLER et al. AND ISSUED BY-THE OFFICE OF NUCLEAR REGULATORY RESEARCH OF THE NUCLEAR REGULATORY COMMISSION.
- 18) GPUN PROPOSAL. 1986.
PROPOSAL OF GENERAL PUBLIC UTILITIES NUCLEAR TO DISPOSE OF ACCIDENT GENERATED WATER.
PAGE 15 OF 15
,