ML19289F875
| ML19289F875 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/04/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| OSP-790604, NUDOCS 7906210004 | |
| Download: ML19289F875 (36) | |
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Volume and Activity of the k'ater to be Processed by the EPICOR-II System Table A contains a listing of all water volumes stored in TMI Unit No.
- 2. which will be processed by the EPICOR-II system.
The liquid sources are categorized by Cesium-137 activity 1cvel, since this will be the predominant and controlling isotope at the time th e s e liquid volumes are processed.
The liquid volumes are established frca tank level measurements taken by plant personnel. The levels are read frca instrumentatica panels located in the Unit 2 auxiliary building and the Unit 2 control room.
The levels which are obtained are then converted to gallcas by utilizing the utility supplied document 2104-4.1, Revisica 0 which converts a specific tank level to a specific volume based on tank geometry.
Activity levels are established frem liquid samples analyzed by in-plant staff as well as by various contractors, thus providing duplicate sample anal sis in all cases. All liquids which will be processed through j
the EPICOR-II system will be at activity levels of less than 40 uCi/ml.
241 073 5
TABLE A Radioactive water volumes and activites for Unit 2 which will be processed by EPICCR-II:
Activity Level
- i Volume uCi)
Source (gal.)
al' Reactor Coolant Bleed Tanks A, B & C 198,540
~30 Miscellaneous Waste Holdup Tank, Auxiliary Building Sump, Auxiliary Building Sump Tank 20,9S2
~10 "eutralizer Tanks A & B 17,520 0.5 1.5 Waste Evaporator Condensate Tanks A & B, Contaminated Drain Tanks A & B, g
Miscellaneous Su=ps 15,700 u 0.1 l
Activity levels of Cs-137 (the controlling nuclide at time of processing) kT. CST activity levels: M 0-5 to 10'b; CDT levels:
~2 x 10-3 All activity levels conf!rmed 27 May 79 by Radwaste Management Group.
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241 {,)4
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As a result of the design features provided to minimize gaseous releases, releases of radioactive material in airborne effluents will be very small.
We have estimated gaseous releas as as a result of operation of the EPICOR II system.
The bases used in this estimate are as follows:
(1)
Data obtained from operation of EPICOR-I system;
)
(2) Data obtained on nuclide activity levels in the reactor coolant and the reactor coolant bleed tanks; (3)
Data en EPICOR-II system ficw rate and chemical cleaning building ventilation rate; (4)
Design of charcoal absorbers en the Off Spec Receiving Tank and in the chemical cleaning building ventilation exhaust vent filtration system.
Based on these calculations, we estimate that as a result of the operation of the EPICCR-II system, the release of Xe-133 will be less than 1 Ci and the release of I-131 vill be less than 1 x 10-4 Ci.
241 075
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GPU is considering processes for cleaning the contaminated water produced in March 28 accident at TMI.
One of the feasible processes involves ion exchange and phys 4. cal absorption processes for which considerable experience and information is available at SRP and ORNI..
cpu is arranging for contractors in the private sector to propose and conduct activities to clean up the water.
Fo rma tion o f a small advisory group of carefully selected technical and operational sta f f from SR P, and possibly CPSL would be of major value.
The group would be used on a or.e t ime ba si s t o review and evaluate the proposals developed by contractors. Suggestions for improvements to the original proposals would be carefully considered by GPU.
It would be valuable to retain access to the group should unforeseen circumstances develop.
In this case GPU would expect to call on the advisory group for special assistance.
Types needed include an operational manager, a radio chemist, and a separations chemist.
241 076
. - ~ ~ - - - - -
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lab In order to convert the chemical cleaning building to use for the housing fo the EPICOR II system, several modifications were made to the building. These codifications included the following:
l.
Additien of the EPICOR II system itse1# to the building.
Specifically the addition in the building of the prefilters, demineralizer, preccat and chemical addition tanks and associated pumps, pipes, valves and instrumentation of the EPICOR II system was installed in the building; 2.
Addition of shield walls around new EPICCR II equipment. These shield walls were added for the protection of plant persennel involved in operation of this system (a complete descriptien of the shielding is contained in the section on minimizing occupational
-xposures);
3.
Addition of an overhead conorail hoist system. This hoist system was provided for removal and replacement of the demineralizers and prefilters. The monorail system extends from the north side of the building above the prefilter througi the south end of the building extending 18 feet outside the building over a cask loading area at which point the shielded prefilter and decineralizer casks can be loaded onto a truck; The chemical ekeaning building was made into a low leakage confinment 4.
building by spraying the interior of the structural steel portion of the building with a chemical sealant. This sealant was added to prevent air and radioactive material outicakage from the Luilding; s
241 077 a
2a 5.
The addition of an exhaust ventilation systen to maintain the chemical clesning building at a negative pressure. This also minimizes air outleakage and directs air flow through the ventilation system. This new ventilation system includes filtration of the air through a prefilter, a high efficiency particulate air (RE PA) filter, charcoal absorber, beds and a final HEPA filter on the ventilation system exhaust. The purpose of these filter units is to remove any radioactive materials present in th~e air before it is released to the environment. A new building was constructed, directly adjacent east of the existing chemical cleaning building, to house this new air filtration equipment; 6.
Addition of a TV Monitor Control Building directly adjacent north-
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west of the existing chemical cleaning building.
Since operation of the EPICOR II system is by remote means, the purpose of this building is to provide a room where re=ote system operations of the EP'CCR II system can be controlled.
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241 078 t
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VIII. Occupational Exposure A design criterion for the facility was that occupational exposure should be maintained as low as is reasonably achievable.
Therefore, the design was made consistent with the guidance of Regulatory Guide 8.8.
The sections below describe the design and operational I
features included to minimize occupatienal exposure. The anticipated dose rates and occupational exposures are also described.
Conc. rete shield wati.s, 12 inches thick and 14 feet high surround the EPICOR II processing are a.
The prefilter is installed inside a cylindrical concrete cask, 12 inches thick. The cask is then surrounded by a rectangular leak brick wall, 5 inches thick. The top of the
'l steel liner which houses the prefilter is filled with 3 inches of lead shot.
The prefilter is also covered by a steel lid, 5 inches thick.
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___ J The lid has cutouts for the hose connections.
The cesium removal demineralizer is installed inside a cylindrical concrete cask, 12 inches thick. The cask is surrounded by a rectangular lead brick wall, 5 inches thick. The cesies removal demineralizer is covered by
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a steel lid, 5 inches thick with cuouts for ho se connections. The mixed bed demineralizer is also surrounded by a rectangular lead brick wall, 3 inches thick. The strainer is shielded with 8 inches
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o' concrete bicek.
The post-filter la shielded with 3 inches of lead 2
brick. The feed line from the Unit II auxiliary. building is shielded
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by lead bricxs, 4 inches thick. The shield bell used to transfer the prefilter and the cesium removal demineralizer onto the truck provides 3i inches of lead shielding.
Concrete walls, 24 inches thick, separate 241 079
s the rooms through which the building is accessed from the room containing the filter and demineralizers. A water box windcw, 18 inches thick, is included in this wall to allow direct viewing of the system from a shielded area.
The EPICCR-II facility has radiation monitors mounted inside the lead brick walls around the prefilter and the de=ineralizers. The design criteria call for the prefilter to be changed if the prefilter reaches a dose rate at contact of 2500 rem per hour.
The cesium removal demineralizer, polishing demineral izer, strainer, and post filter will be changed when dose rates at centact reach 400, 20, 3, and 3 rem n3 l
per hour, respectively.
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The truck which is used to transfer the spent filters and demineralizers on to the on-site staging area has a cylindrical reinforced concrete shell 15 inches thick. The transfer bell holdong the spent filter or cesium removal demineralizer will be placed inside this shell for additional shielding in route to the staging area. The polishing demineralizer will be lifted into this shell without a transfer bell.
The control room for EPICCR II is located outside of the chemical cleaning building. The operations can centrol the system in the f acility from this centrol room by means of remote cameras, control and readouts from instru=entation.
Using the crane and transfer bell 1
241 080
l the spent filters and demineraliners can be removed from the facility without entering the EPICOR II room.
Since the connections and dis-connections of the filters and demineralizers will require direct handling by personnel, quick connect / disconnect i
hoses and caps will E
be used.
,, j Ladders will be provided to facilitate access to the tops
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of the filter and demineralizers to make connections.
Features are included to allow flushing of piping and hoses and to allow sanpling to be perferned from the outside of the EPICOR II room.
The operators for EPICOR II will be trained in'the operations of the This training will include several trial operations of the system.
various systems before radioactive water is processed.
The EPICOR II
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system uses the same type of equipment being used in EPICCR I.
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.here-fore, operators trained in the use of the EPICOR I are already experienced
_,j in many of the operational aspects of EPICCR II.
Coverage by health physics personnel will be provided whenever the EPICOR II building is accessed.
=
241 08i L
The estimated radiation dose rates outside of the lead brick walls surrounding and demineralizers are 15 millirem per hour.
The estimated the filters 100 millirem per hour with dose rates on top of the steel cover plates are 1 rem per hcar above the cut-outs due to streaming.
The estimated dose The estimated rate above the polishing demineralizer is 20 rem per hour.
._ i dose rates at centact with the strainer and post filter are 3 rem per hour.
The estimated maximum dose rate outside of the f acility is 2.5 millirem per hour The estimated dose except during filter or demineralizer removal by crane.
rate outside of the transfer bell with a cesium removal demineralizer in it is 100 millirem ; er hour.
The estimated dose rate outside of the shield shell on the truck with the polisher de=ineralizer in it is 100 millirem per houm. For a very short time before being lowered cnto the truck, the polisher m
- I demineralizer will have an estimated dose rate of 20 rem per hour.
l 0
The estimated maximum dose at the site boundary is less than 1 millirem; m.J this dose includes all of the handling operation.
Thic dose is less than 47.
of the 25 millirem annual limit in 40 CFR Part 190.
Disconnections of hoses and capping of spent filters and demineralizers will be the highest occupational dose activity associated with EPICOR-II operation.
These activities require direct handling by persennel in radiation streaming 7
fields of 1 rem per hour. EPICOR-I which is similar in size to and has the
. N.
same quick connect / disconnect fittings as EPICOR-11.
Experience from operation of EPICOR-I shows that a filter or demineralizer can be disconnected and capped by a trained operator in an average ti=e of about h'1f of one minute.
241 082
that these activities Based on the licensee's estimate of the number of times will be necessary, we estimate that operation of EPICOR-II will cause 1-5 manrem of occupational dose. This estimate includes other lesser dose causing activities involved in the oper ion of EPICOR-II, and this estimate is a very a nuclear small percentage ( <17.) of the annual average occupatienal dose at power plant.
Based on our review, we conclude that the licensee's design and operational considerations to minimize occupational exposure are censistent with the guidance of Regulatory Guide 8.8 and, therefore, acceptable.
Based on our estimate of the occupational dose associated with EPICOR-II operation and based on our estimate of the direct radiation dose rates off-site, we conclude that this change to the plant design does not constitute a significant
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environmental impact.
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'O see ti o n o The EPICOR II system is housed in an existing on site structure called the Chemical Cleaning Butiding. This building was originally intended to be used in the chemical cleaning of the steam generators for Units 1 and 2.
This chemical cleaning was to occur at such times as deemed advisable in the course of unit operations. As a result of
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recent secondary coolant system design modifications by Babcock and Wilcox, the need for this building for its original purpose has been lessened.
ccnstructed during the construction The chemical cleaning building wa r of Unit No. 2.
It is a box shaped building with dimensions of 48 f t. by 60 ft, by 52 ft. high. The foundation of the building and the walls up to a height of 13.5 feet above the basement floor are concrete and the upper walls and roof are of structural steel.
The foundation of the building is designed to Seismic Cat; gory I ccnditions as are the primary concrete wr.11s and structural steel frame, in the building. The secondary concrete walls are designed for all seismic dead and live loads to which they are subjected. The building is watertight up to e height of 13.5 feet above the basement floor so as to contain the release of water in the building in the event of rupture of the ta r.'<s in the building.
As originally designed, the chemical cleaning building contains two large water storage tarks, the chemical cleaning solution tank with a capacity of 95,000 gallons and the rinse hold tank with a capacity of 133,000 gallons. The butiding also contains a stainless steel lined sump.
In additien, there is an undergrovad pipe trench to the building.
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241 08 tr
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In order to ccnvert the chemical cleaning building to use for the E
housing Ec the EPICOR II system, several modifications were made to the building. These modifications included the following:
1.
Addition of the EPICCR II system itself to tra building.
Specifically7 s
-the--nddii. ;u ue a u.l L..,
- f the prefilterf, demineralizer, precoat and chemical addition tanks and associated pumps, pipes, valves and instrumentation of the EPICOR II system m installed in the building; 2.
Addition of shield walls around new EPICOR II equipment. These shield. walls were added for the protection of plant personnel involved in operation of this system (a complete description of the shielding is contained in the section on minimizing occupational exposures);
3.
Addition of an overhead manerail hoist system. This hoist system was provided for removal.and replacement of the demineralizers and prefilterc. The monors system extends from the north side of the building above the prefilter through the south end of the building extending 18 feet outside the building ovet a cask loading area at which point the shielded prefilter and demineralizer casks can be loaded onto a truck;
{
4 The chemical cleaning building was made into a low leakage confiE.ent g
building by spraying the interior of the structural steel portion of the building with a chemical sealant. This sealant was added to prevent air and radioactive material outleakage frca the building; 241 085
5.
The addition of an exhaust ventilation system to maintain the chemical cleaning building at a negative pressure. This also minimizes air outleakage and directs air ficw through the E
ventilation system. This new ventilation system includes filtration of the air thrcugh a prefilter, a high efficiency particulate air (IEPA) filter, charcoal absorbergebeds and a fina!
liEPA filter, en.'. u. c.n il a thn p r= 2xMe.
The purpose of g o M '.w Au/
40 j
filter units is to remove any radicactive-eaterials present these 7
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in the air before it is released to the environment. A new building Zo A AldD was constructed, directly adjacent east ot the existiur chemical 4
p cleaning building, to house this new air filtration equipment; 6.
Addition of a TV Monitor Control Building directly adjacent north-west of the existing chemical cleaning building.
Since operation of the EPICOR II system is by renote means, the purpcse of this building is to provide a roca wher remote system operatiens of M
the EPICOR II system can be, controlled.
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e 241 086
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The EPICOR II system consists of a vendor supplied liquid radwaste processing system which is located in the previously constructed chemical The EPICOR II system is designed to decontaminate by cleaning building.
filtration and ion exchange radioactive waste water contained in the No. 2 and to transfer this decontaminated water auxiliary building of Unit
& $ $ cl &retci-AW
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%.,12-I reedim...v. cr L to Unit No.
g The EPICOR 11 system is designed to function in such a pr ;-; m
- dag.
to of radioactive material to the environ =ent manner as to limit releases
/
In additicn it is designed levels which are as low as reascnably achievabic.
to be operated, maintained and dismantled in such a manner to =aintain exposures to plant personnel to levels which are "as low as reasonably achievable."
A.
Sources of Radioactive Water As indicated above, the EPICOR II system will process apprcxi=ately gallons of intermediate level radioactive vaste water currently 200,000 Waste that is acceptable in the Unit No. 2 auxiliary building.
for processing in the EPICOR 11 system is that which has,z# odine-131 i
A.
and cesium 137 concentrations of less than 40 uCi/cc Specifically, y
i f
the tanks in the Unit No. 2 auxiliary building which are to be processed using the EPICOR II system are the following:
i l
1.
reactor coolant bleed tanks l
l 2.
miscellaneous waste holdup tank f
3.
auxiliary building sump I
4.
auxiliary building su=p tank 5.
neutralizer tanks 241 087
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2 6.
garte evaporator condensate tanks 7.
contaminated drain tanks 8.
miscellaneous sumps E
A complete discusiten of the quantities of water frem these tanks and the associated radioactivity levels is centained in the section on activity levels cf water.
3.
Descriotion of the EPICOR II System 5
The EPICCR II system consist, of the following components all of which are located in the chemical cleaning building except as noted:
1.
Cap-Gun Pu=ps (5) 2.
Transfer pump 3.
Prefilter - containing silver impregnated charcoal 4.
Demineralizers - one cation bed followed by a mixed bed 5.
Miscellaneous waste holdup tank.- located in the auxiliary building i
6.
Clean wastes receiver tank (formerly named the rinse hold tank when it was part of the chemical cleaning system)
Off-spec water receiving / batch tank (formerly kacen d na me 7.
aa the l
chemical cleaaing solution tank when it was part of the chemical i
cleaning system) i 241 088 t
3 8.
Chemical cleaning building sump pump 9.
Monorail hoist system 10.
Ventilation system A flow diagram of the system is attached as Figure 1.
The system operates in the following manner. The miscellaneous vaste holdup tank (MJET) is located in the auxiliary building of Unit No. 2 and receives water frem the specific auxiliary building tank to be n
proceered. The first Cap-Gum pump is used to pump water frem the FMHI to the prefilter. Water is pu= ped from the MWHT in the auxiliary building to the prefilter in the chemical cleaning building, c; --- -
iv c oiry g A p see through the yard. This piping located in the yard is enclosed in a guard pipe, the open end of ' tch term-inate{insidethechemicalcleaningbuilding. The prefilter contains a precoat =aterial which enables it to remove particulate 2
radioactive vastes of greater than 5-
=icrons and other suspended solids. The prefilter also contains )( silver impregnated charcoal which makes it highly efficient for the removal of iodine from the waste stream. After passing through the preffiter, the water is circulated through the two demineralizers arranged in l
series by the Cap-GdE pumps. The first demineralizer contains cation I
bed resins which makes it highly efficient f or removal of cesium frem the waste stream. The second demineralizer contains mixed bed resins which makes it efficient for removal of various radionuclides
-241 089 t
4 including cesium and iodine. After processing, the water is collected in the clean water receiving tank (CWRT) which has a capacity of 133,000 gal.
In the CJRT the water is sampled 5
and analyzed.
If the analysis shows that the processed waste contains concentrations of radioactivity below release limits )
the water is then transferred to UnitNo. 1 Liquid Waste Disposal system for ultimate disposition.
Processed waste which is not A
suitable for<Al 5lisuf Alo1 m/kfW rc.,. M c : -- ; _ _. _.
_11 m e-c ' v%-i to the O f f Spec Water Receiving / Batch Tank (04RT) which has a capacity of 95,000 gallons. Water in this tank can be recycled through the EPICOR II system for additional processing. Water is pumped from the CJRT to the (MRT by the transfer pump.
The sonorail hoist system consists of a 20 ton hoist mounted on a monorail which extends from above the prefilter, across the top of the demineralizers, and extends approximately 18 feet outside of the chemical building over the cask loading area.
The purpose of the hoist system is to provide for removal and replace =ent of the demineralizer and prefilters when thev have reached the cavi=um
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The radioac ivity loading is radios.ctivity loading per=ittedg limited by contact radiation dose rate readings on the vessel to meet DE requirecents. The operation of the monorail hoist system A
is done re=otely by use of a closed circuit TV system located in the control shed located adjacent to the chemical cleaning building.
241 090
6 The building ventilation system consists of an exhaust ventilation The system which maintains a negative pressure in the building.
exhaust ventilation system consists of a 4-
'-: = heating unit a u nti' n._-c and moisture separator, a xm.mi-__ w filter unit, and a w.... _ t i c f an assembly, a e.;_.% radiation monitor, weather proof enclosure. Building exhaust air is passed through the moi $;;re separator and a 80 )?J heater to ruove acisture frca
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ShK Q P9 the at:4to improve the filter unit iodine removal c ap abilities.
The J
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air is then passed through the c:11__u unit which consists of a ventilation prefilter, a high efficiency air particulate (EEPA) filter, b
charcoal absorber cads and a final hTPA filter.
The HEPA filters are used to remove radioactive material in particulate form. The charcoal filters are used to rc=ove radiciodine in the air.
The f an assembly draws air frem the building and exhausts it through ducting and to a local stack at the roof line of the chemical cleaning building. The radiation monitor samples air in the fan discharge line.
Indication of ventilatien system exhaust cctivity The is provided both locally and remotely in the control shed.
that monitor will provide an alarm in the central shed in the event level.
radiatica levels in the effluent stream exceed a preset The chemical cleaning building sump is a stainless steel lined pit located in the northwest corner of the building.
All leakage frca A
cask overflows and from equipment leakage is collected in the su=p.
sump pump transfers water from the sump to tne of f Spec Water Receiving /
The sump pump starts automatically en a level indicarica Batch Tank.
in the sump.
2M 00
Volume and Activity of the Water to be Processed by the EPICOR-II System Table A contains a listing of all water volumes stored in TMI Unit The liquid sources No. 2. which will be processed by the EPICOR-II system.
this will be the are categorized by Cesium-137 activity level, since pred ominant and controlling isotope at the time these liquid volu=es are processed.
The liquid volumes are established from tank level measure =ents taken by plant personnel. The levels are read from instrumentation panels located in the Unit 2 auxiliary building and the Unit 2 control room.
The levels which are obtained are then converted to gallcas by utilizing the utility supplied document 2104 4.1, Revisica 0 which converts a specific tank level to a specific volume based en tank geccetry.
Activity levels are established from liquid samples analyzed by in-plant staf f as well as by various contractors, thus providing duplicate sample analysis in all cases. All liquids which will be processed through lavels of less than 40 uCi/=1 # b 4
the EPICOR-II system will be at activitf f
M C: - / 3 2
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TABLE A Radioactive water volumes and activites for Unit 2 which will be processed by EPICOR-II:
Activity Level
- Volume (uCi 5
Source (gal.)
ml Reactor Coolant Bleed Tanks A, B & C 198,540
~GO Miscellaneous Was te Ecidup Tank, Auxiliary Building Sump, Auxiliary Building Sump Tank 20,982
~10 Neutralizer Tanks A & B 17,520 0.5 1.5 Waste Evaporator Condensate Tanks A & B, Contaminated Drain Tanks A & B,
<< 0.1,
Mi-seellaneous sumps 15,700 Activity levels of Cs-137 (the controlling nuclide at ti=e of processing)
++ WECST activity levels:
+40-5 to 10-6; CDT levels:
s2 x 10-e All activity 1Avels confirmed 27 May 79 by Radwaste Management Group.
241 093
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2 5.
Level instrumentation in the demineralizers is similiar to that for prefilter. High level alarm for the decineralizer will &Lacs W in the centrol shed.
6.
For the clean water receiving tank and the off-spec water i
receiving / batch tank, an overflow line with a loop seal is provided near the top of the tank.
Tank level indication is provided on the centrol panel in the gentrol shed.
W Wh-All system cceponents which asafeyn hose connections are provided 7.
with drip trays to collect leakage. Tubing frca these drip trays is routed to the nearest floor or equipment drain.
8.
All system liquid piping is welded stainless steel to prevent syste= leakage. All fittings and hoses installed have pressure P
ratings that exceed p maximum discharge pressure of the pumps used. All discharge hoses have a pressure rating of 600 psig All hoses and fittings are hydrostatically tested or greater.
prior to use.
Pu=p diaphragms are designed to rupture at pressures greater than 125 psig. The maxi =um available air l
pressure to drive the pu=ps is 100 psig, (thus protecting All hose connections are tape.2 _uu wrapped i
l diaphragm integrity).
I with plastic to contain drips frem fittings.
Desien Featwes to Minimize Cascous Releases i
There are a number of design features built inot the EPICOR II system i
T e following is a to mini =1:e gaseous releases to the environment.
h i
listing of these features and a discussion of each:
241 094
3 1.
The che:ical cleaning building has been sealed with a chemical sealant to minimize both inleakage and outleakage of air.
2.
A buildhg exhaust ventilation system has been added to the i
building to maintain the chemical cleaning building at a negative This prevents outleakage of air from the building and pressure.
also routes any radioactivity in the air in the building to the exhaust ventilatien syst, filtration units.
3.
Filtration um.ce consisting of REPA filters and charcoal absorber beds provide re= oval of radioactive particulates and radiciodine, respectively, from the building air before it is released to the environ =ent.
4.
A radiation monitor in the ventilation system ductwork provides an indication of radiation levels both locally and in the control shed.
In addition the radiation monitor will provide an alarm if the radioactivity in the release exceeds a preset level.
In this =anner releases of radioactivity qq3/ be carefully controlled 3
to be within required limits.
&m Qs, MM jb, are provided with in lineJpWA f the cystem tank vents 5.
Within the plant
/
heaters, 4(_..stcr filtert,awi charocal absorbers to absorb evolved JA iodine.
- he Vengs from the prefilter and demineralizers are vented Yto the g tank (.
j 6.
The building sump will be a covered sump.
Iodine fixing chemicals can be added to the sump to =inimize iodine releases.
I 241 095
7.
Iodine fixing chemical :r.ay also be added to the of f spec receiving A&
P batchtankand.inthecleanwafte$receivertank.
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20--096
g As a result of the design features provided to tainimize g aseous releases, releases of radioactive =aterial in airborne ef fluents will be very sna11.
We have estimated gaseous releases as a result af o},eration of the EPICOR-II system.
E The bases used in this estimate are as follows:
(1)
Data obtained from operation of EPICOR-1 system; (2) Data obtained en nuclide activitf Icvels in the reactor coolant and the reactor coolant bleed tanks; (3) Data ca EPICOR-II system flow rate and chemical cleaning building ventilation rare; (4) Design of charcoal abs irbers en the Off Spec Receiving Tank vent and in the chemical c1 caning building ventilation exhaust filtration system.
Based on these calculations, we esti= ate that as a rasult of operation of the EPICOR-II system, the release of Xc-133 wi7 l
than 1 Ci and the release of I-131 will be less than 1 x 10-4 C1.
e
~241 097-6 w
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w VIII. Occupational Exnosure A design criterion for the facility was that occupational exposure Therefore, should be maintained as low as is reasonably achievable.
the design was =ade consistent with the guidance of Regulatory belew describe the design and operational Guide 8.8.
The section:
The anticipated f eatures included to minimize occupational exposure.
rates and occupational exposures are also described.
Concrete shield walle, 12 inches thick and 14 feet high, surround the The prefilter is installed inside a EPICOR II processing ares.
The cask is then surrounded cylind-ical concrete cask,12 inches thick.
inches thick. The top of the by a rectangular leak brick wall, 5 steel liner which houses the prefilter is filled with 3 inches of lead The prefilter is also covered by a steel lid, 5 inches thick.
f shot.
The cesium re= oval The lid has cutouts for the hose connections.
demineralizer is installed inside a cylindrical concrete cask, 12 The cask is surrounded by a rectangular lead brick inches thick.
The cesium removal demineralizer is covered by wall, 5\\ inches thick.
a steel lid, 5 inches thick with cuouts for hofse connections.
The mixed bed demineralizer is also surrounded by a rectangular lead I
The strainer l's shielded with 8 inches f
brick wall, 3 inches thick.
of concrete block. The post-filcer is shielded with 3 inches of lead brick. The feed line frem the Unit II auxiliary building is shielded by lead bricks, 4 inches thick. The shield bell used to transfer the prefilter and the cesium removal demineraliser onto the truck provides 3 inchem of lead shielding. Concrete walls, 24 inches thick, separate
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241 098 6"
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the rooms through which rnt building is accessed from the room containing the filter and domineralizers. A vater box window, 18 inches thL is included in this wall to allow direct viewing of the systen from a shielded area.
The EPICOR-II f acility has radiation monitors mounted inside the lead briek walls around the prefilter and the demineralizers.
The design iriteria call for the prefilter to be changed if the prefilter reaches a dose rate at contact of 2500 res per hour. The cesium removal demineralizer, polishing demineralizer, strainer, and post filter will be changed when dose rates at contact reach 400, 20, 3, and 3 rem per hour, respectively.
The truck which is used to transfer the spent filters and demineralizers mne to the on-site staging area has a cylindrical reinforced concrete shell 15 inches thick. The transfer bell hold $ng the spent filter or cesium removal demineralizer will be placed inside this shell for additional shielding in route to the staging area.
The polishing I
demineralizer will be lif ted into this shell without a transfer bell.
The control room for EPICOR II is located outside of the chemical cleaning building. The operations can control the system in the f acility from this control room by =eans of remote cameras, control and readouts from instrumentation. Using the crane and transfer bell 241 099 M
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the spent filters and demineralizers can be removed from the facility without entering the EPICOR II room.
Since the connections and dis-connections of the filters and decineralizers will require direct handling by personnel, quick connect / disconnect hoses and caps will be used. Ladders will be provided to facilitate access to the tcps of the filter and decineralizers to make connections. Features are included to allow flushing of piping and hoses and to allow sampling to be performed frca the outside of the EPICOR II roca.
The operators for EPICOR II will be trained itJ the operations of the This training will include several trial operations of the system.
various syste=s before radicactive water is processed. The EPICOR II system uses the sa=e type of equipment being used in EPICOR I.
There-fore, operators trained in the use of the EPICOR I are aircady experienced in many of the operational aspects of EPICCR II.
Coverage by health physics personnel will be provided whenever the EFTCOR II building is accessed.
24i 100 e
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A The estimated radiation dose rates outside of the lead brick walls surrounding The estimated the filters and decinerali=ers are 15 millirem per hour.
100 =1111 rem per hour with dose rates on top of the steel cover plates are The estimated dose 1 rem per hour above the cut-outs due to streaming.
The estimated rate above the polishing demineralizer is 20 rem per hour,
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dose rates at contact with the strainer and post filter are 3 rem per hour.
The estimated maxi =um dose rate outside of the f acility is 2.5 millirem per hour The estimated dose except durtag filter or demineralizer removal by crane.
rate outside of the transfer bell with a cesium removal demineralizer in it is 100 millirem per hour.
The estimated dose rate outside of the shield shell on the truck with the polisher demineralizer in it is 100 millirem per For a very short time before being icwered ento the truck, the polisher ho ux.
demineralizer will have an estimated dose rate of 20 rem per hour.
The estimated maxicum dose at the site boundary is less than 1 millirem; this dose includes all of the handling operation.
This dose is less than 47.
of the 25 millirem annual limit in 40 CFR Part 190.
i Disconnections of hoses and capping of spent filters and demineralizers will be 1
the highest occupational dose activity associated with EPICOR-II operation.
These activities require direct handling by perronnel in radiation streaming fields of 1 rem per hour. EPICOR-I which is similar in size ta and has the l
sa=e quick connect / disconnect fittings as EPICOR-II.
Experience from operatica of EPICOR-I shows that a filter or demineralizer can be disconnected and capped by a trained operatcr in an average time of about half of one minute.
241 101
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a Based on the licensee's estimate of the number of times that these activities 1-5 will be necessary, we estimate that operation of EPICCR-II will cause manrem of occupational dose. This estimate includes other lesser dose causing activities involved in the operation of EPICOR-II, and this estimate is a very a nuclear small percentage ( <17.) of the annual average occupational dose at power plant.
Based on our review, we conclude that the licensee's design and operational censiderations to =ini=L:e occupational exposure are consistent with the guidance of Regulatory Guide 8.8 and, therefere, acceptable.
Based on our esticate of the occupational dose associated with EPICOR-II operation and based on our estimate of the direct radiation dose rates off-site, we cencluce that this change to the plant design does not constitute a significant environmental impac t.
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Design Features for Soill Prevention There are a number of design features built into the EPICCR II system to prevent spills of radioactive water. The following is a listing of these features and a discussica of each:
1.
The piping carrying radioactive water from the miscellaneous waste holdup tank in the auxiliary building through the yard to the EPICOR II system in the chemical cleaning building is enclosed M% #
Within a 4"_Catek guard pipe.
Radiation shielding has been provided around the guar d pipe to minimize personnel exposure.
2.
The chemical cleaning building is constructed cf watertight seismic category I concrete construction to a height sufficient to contain the water in the large holdup tanks in the event of rupture of these tanks; 3.
All system overflev lines run to the chemical cleaning building sump.
The su=p pump routes all collected leakage to the off spec Water Receiving / Batch Tank. The sump pump is started either =anually i
i or aute=atically from.ne control panel.
If pump start is auto-
=atic, it occurs when the sump level reaches a preset height. A l
high su=p level alarm is also provided on the control panel in the control shed.
4.
Water level in the prefilter is maintained by a level probe and
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a solenoid valve. On a high level alarm an alarm will sound at t
the pu=p centrol panel in the control shed.
I
Ef M' 4f-W CONFORMANCE OF NRC REGULATORY GUIDES EPICOR II System Design with NRC Regulatory Guides J ~ 'l C.
N$h The EPICOR II liquid waste processing system and the building 1.
h the design criteria of Regulat ory Guide p
housing the syr, tem meet w;
1.143, " Design Guidance for Radioactive Waste Managen nt Systems, h.
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Structures and Coeponents Installed in light-Water. Cooled Nuclear
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The building ventilation system for the building housing EPICOR II
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hpd is designed in conformance with Regulatory Guide 1.140, " Design, v.pi d5dk[
Testing, and Maintenance Criteria for Normal Ventilatian Exhaust
- .-e System Air Filtration and Adsorption Units of dight-Water-4 7,-
} n& M Cooled Nuclear Power Plants."
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L*h 1b*. 3 for EPICOR II is in confomnce with the requirements of
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Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting 4~, UT vb
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Radioactivity in Solid Wastes and Rulease of Radioactivity in Liquid and Gaseous Ef fluents from.' light-Water. Cooled Nuc1 car Yi}m CA w
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the chemical M5 4.
The radiation protection design of the feite0R II system, MC f
cleaning facility hnd the spent filter and resin handling systems gnm[q,g gg m
mn IO is consistent with the guidance of Regulatory Guide 8.8, "Infor=ation
%u (i;h tb u&a;. [A to Insuring that Occupational Radiation Exposure at Nuclear EWhg Relevant s.k'.iMk.@..
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)d rat j Power Systems will be as 14w as is Reasonably Achievable."
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system is acceptabic becaucc XZWh$1
"<5tj (1) The design of the EPICOR II system =ects the intent of NRC 4
C' Regulatcry Cuides 1.143, 1.140, 1.21 and 8.8:,
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(2) The system design will such as to prevent spills of radioactive
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(3) The system design will be such as assure that releases of radio-
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[$ml?+I, MM'l We have concluded, based on the considerations discussed above, that:
N(g[i fhy (1) theIAiMset61r_xisspyancmebat the health and saf ety of the gs g45g public will not be endangered by operation in the proposed manner, and
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- gygig (2) such activities will be conducted in co=pliance with the Co==ission's T5;*h b p, d regulations and the issuance of this amend =ent will not be inimical to the NL;M'M kihh coc=
- en defense and security or' to the health and safety of the public.-
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v The staff is directed to prepare an Environmental Assessment regarding C tz
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t d waste I. t.n
, proposals to decontaminate and dispose of radioactively.contam na e The Assessment will be divided water from the Three Mile Island facility.
The first portion of the Assessment will deal with the into several portions.
h EPICOR-II prcposed decontamination of intermediate-level waste water using t e The Assessment should include discussion of potential risks to
. system at TMI.
exposures and the risk of
.the public health and saf ety, including occupational PICOR-II system.
accidental releases, and a discussion of alternatives to the E Pending ccepletion of this portion of the Assessment and opportunity for the staff should direct the licensee not to operate the public coment, Testinc cf the EP]COR-II system without usinc contaminated EPICOR-II system.
Except for discharge of waste water decontaminated by the waste may proceed.
existing EPICOR-I decontamination sysic..1/ and discharge of industr'ial waste
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water / as consistent with the facility operating licenses, no disct.arge of 2
waste water shall be. permitted until completion of a second portion of the This tortion shall in- '
Assessment dealing with any such proposed discharSes.
clude a discussion of alternatives to discharce into the Susquehanc.a River.
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decontamination and disposal of high-level waste water will be the subject Tht the Director of the Of fice of Nuclea'r' of a subse:;uent Assessment.
- However, Reactor Regulation may authorize measures dee;ned necessary to cope with an Primarily pre-accident weste water from Unit 1 which has been partially 1/
contaminated by water f rcm Unit 2, with an activity level of less than 1 raicrocurie per cc. prior to treatment and with an activity level approxi-mately 10-7 microcuries per cc. in the discharge canal after treatment.
N
'raste voter slightly contamina ted (approxinately 10-7 aicrocuries per'cc.)
The discharge cue to leakage frcm secondary piant scrvice support systens.
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of this industrial waste water is necessary to maintain TH1 Unit 2 in a safe condition.
241 106
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2 energency.
If the Director of. the Office of Nuclear Reactor Reculation be-lieves tha public hesi th and satety requires the use of the EPICOF.-II system, prior to completion of the first portion of the Assessment, he shall so report
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to the Conrnission and the Comnission may then perTnit use of the systs..
The
. staff should inform the Comaission promptly recarding its estimated schedule
.for cogleting each portion of the Ass tent and fdr completing the entire Assessment.
For the Cc.miss ion l
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SAMUEL J.
HJLK Secretary of the Commission Ib t ed a t.',,' :h i ny tu si, DC,
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