ML20107A268
Text
_.
v.J6' y_s
. ~. ~. ;,.
.lersey Central Power & Light Company MA:,' SON AVENUE AT PUNCH BOWL RO AD
- i.:JRRISTOWN,N. J. 07960
- 201 539-6111 aa.. u m
,] Public Utahties Corporahon Generei u,u, December 13, 1973 r
/
{
n A
.i
% gCl'i
'..,' t h.
SJ f.,i Robert J. Schemel, Chief
[
'-l P'O
-I Operating Reactors Branch til r; '
e y c, Directorate of Licensing J.'. /
i Office of Regulation V\\ L,'
-/
United States Atomic Energy Commission-
'dA
., O/
J ' ' ' 3 ',,
'?(,'[6,., \\ i ' ' yO' Washington, D. C. 20545 s
.~
[
Dear Mr. Schemel:
SUBJECT:
' OYSTER CREEK NUCLEAR GENERATING STATION RADIOACTIVE WAST", TREA'DIENT I
SYSTDI MODIFICATION In reply to your letter dated October 10, 1973 in which you, requested I
. additional information in connection with our September 20, 1973 sub:nittal entitled " Preliminary Description and Analysis of Proposed Modifications to i
the Caseous, Liquid and Solid Radioactive Waste Trcctment Systems'for the i
Oyster Creek Nuclear Generating Station", we are enclosing our responsen l
to the questions that were included as Attach:nent A to your letter.
If you have any questions regarding these responses, uc would be l
pleased to meet with your representatives at your convenience.
Very truly yours, h//
.I
\\ {. ' ) ['. l.'
l
^
.,.,/
4 Ivan R. Finfrock, Jr.
Vice President pk Enclosure 1
8931 1
D 9604120215 960213
/
r
()
t',
QUESTION 1 It is proposed to design and construct the liquid waste system and the gaseous waste system to Quality Group D and non seicnic classification.
In this regard, discuss how the guidelines in Regulatory Guides 1.26 and 1.29 would be met for the accident conditions.
RESPONSE
A.
Classification of Radvaste System as Group D and Seisnic Category II Regulatory Guide 1.26 requires radwaste treatment system components to be class-ified as Group C unless the failure of any system component wou]d result in a calculated exposure less than 170 mrom whole body dose or its equivalent to parts of the body at the offsite location of highest exposure.
The analysis presented herein demonstrctes that the liquid and gaseous radwaste system inten-dcd for installation at Oyster Creek 1:uclear Station, Unit 1, acets the aforc-mentioned guidelines.
s Rego]ntory Guide 1.29, E.v.
- 1. requires those portions of radwaste treatment systems to be Scismic Category I unicss simultaneous failure of these portions result in calculated off site exposures less than the 500 nrem to the whole 1
body or its equivalent to any part of the body.
It is shown horcin that simul-taneous failure of all components in the Augmented Offgas System and Liquid Radwaste System riect the aforcucationed guidelines.
B.
Aufecnted Offras System Summary The highest offsite whole body exposure due to the failure'of a singic cocpon-ent in the Augmented Offgas System is 60 urem.
The offsite whole body dose due to the failure of all components in the Augmented Oficas System is 110 uren, which is Icss than the 500 mrem guideline of Regula-tory Guide 1.29.
e 1-3
1
)
The highest offsite thyroid expor.ure from lodine released as a resul,t of the failure of all Augmented Offgas System Components is 342 mrem assuming 100% of the system iodine inventory escapes.
This doce is-within the 1500 mrem guide-lines.
these conservatively calculated exposures are within the guidelines presented in Regulatory Guides 1.26 and 1.29 and therefore, the systems are Class D and Scismic Category II.
C.
Assur.:ptions and Cciculational Procedures Tabic 11.1.1 of Reference 1 lists the source terms used as a basis for estab-liching inputs, releases and inventories of each system ccmponent.
Table 11.3.3A of Reference 1 lists node point activities derived for the system.
1 Component inventories were deternitied by activity balances for cach component.
For parent i otopes,.an4nming steady stete operation, the follouing relatien var utilized:
in j,in - Iout j,out ~' AjUj=0 (Equation 1)
F C
C where, in consistent units:
i F
= V lumetric flow rate into component.
in e
F
= V lu tric fl w rate fr m component.
out Gj.in = Specific activity of isotope j catering component.
1 G
= Specific activity of isotope j leaving component.
j.out A
= Decay constant for isotope j.
3 l
N
= Total activity of isotope j within component.
j For daughter isotopes, again assur.ilns steady state operation, the following rcIntiun holds:
+ Ialj-1j_1-ljNj=0 (Equation 2)
Fin j.in " F C
out Cj.out N
B j
3-2
~
( >
,)
)
P w
where A _7 = decay constant for isotope j-1.
j Nj_1 = total activity of isotope j-1 within component.
E _7 = fraction of isotope j-1 which decays to isotope j.
j Eqaations I and 2 were used to calculate ccmponent isotopic inventories (Nj).
Values for C) were calculated using a computer code entitled " CORN" which was developed by Burns and Roe, Inc.
'Ihc atmospheric dispersion coefficient (X/Q) for ground release was determined using site wind direction data and site plan dota.
The X/Q was evaluated to be 2.26 x 10' seconds per cubic meter using equations 3.141 and 3.142 from Reference
?., a wind speed of 1 meter per second and Pasquill Type F conditions.
Dace conversion factors, used to evaluate the whole body exposure and iodine exposures were obtained from Reference 3 The doses were calculated using the methods described in Section 7-5.2 of Reference 2 for the dose fron a finite cloud.
1 Release f actors for Xe end 1 r gases from the charcoal adsorbers for a charcoal i
upset failure are based on the assumption that the charcoal bed ;ceperature instantaneously increases from 400F, its operating temperature, to 1000F, the highest expected ambient temperature.
The dif ference between the equilibrium isotopic inventories for bed temperaturca of 40 F and 100 F is the conservatively assumed basis for establishing relenced activity.
This approach leads to released fractions of 0.5 to 0.67 of the 40 F bed inventory depending on the isotope and the source of the dynamic adsorption i
coefficients (10 ).
j 9
If concentration gradients and comparative gradients vere infinite, the.5 to
.67 fractica would be instantaneously released.
Since these gradients are not
t
! s)
)
infinite, it would bb realistic to choose a much smal'icr fraction than theuc
-4 for-estimating releases during the first two hours ' following the postulated failure.
Itowever, in the interest of conservatism, the exposure calculation is cased on a released fraction of 0.5.
The whole body dose due to releases from the first carbon bed adsorber it calculated to bc 60 mrem.
This.was the highest dose calculated in thc.singic component failure analysis.
The dose due to the failure of all components in the Augmented Offgas System is 110 mrem.
The whole body exposure due to the relcane of activity from the end of the delay pipe at the anticipated operational occurrence activity release rate of 260,000 nicrocuries per second'was calculated to be 15 area, if the reactor is postulated to operate for 20 minutes af ter the accident.
If 100% of the Augmented Offgas System iodine inventory is assumed to be re-leased, the resultant thyroid exposure was calculated to be 342 mrem.
This calculation is very conservetive, since a very sicall fraction of the iodine will actually be released.
D.
Liquid Radwaste System The nobic gas inventory in the liquid radwaste system is several orders of magnitude less than that of the Augmented Offgas System.
The resultant whole body' exposure due to the release of the entire nobic gas inventory will thus be negligibic with respect to the guidelines of Regulatory Guides i
1.26 and 1.29.
The lower' floor of the Liquid Radwaste Duilding will be watertight with retaining wal]n sufficiently high to contain the entire liquid inventory of the building.
The Leuer floor and the. portion of the surrounding wall that is required to retain the building's liquid inventory will bc designed to i
Scismic Cater,ory I requirements.
Therefore, all Jiquid wastes within the 1
()
.)
' Liquid' Raduaste Building will be contained following a postulated SSE.*
In addition, the new tanks located outside of thic building will be Scismic Cctegory I'to ensure containnent of radioactive liquids.
- Safe.Shutdoun Earthquake.
REFER):NCES Reference 1
" Preliminary Description and Analysis of Proposed Modifi-cations to the Gcccous Liquid and Solid Radioactive Waste Treatment Systens for Oyster Creek Nuc1 car Generating Station." submitted 9/20/73.
Reference 2 "Mateor$1ogy and Atomic Energy 1969" by D.11. Slade.
Reference 3
" Final Environnental Statenent - ALAP - LUR Effluents, Volu::e 1 - The Statetent," July 1973.
i l
l 9
i s
1-5
- i.
I.).
)..
OA
'QUESTIOS 2J L Provido 'the. weight ' of. charcoal in.each adsorber bed of the proposed gaseous waste system,'the operating pressure of the beds, and the t dyn?n':Ladsorption: coefficient for the operating co ritions of the '
Lbeds..
RESPO.' SE :
The total estimated weight of the charcoal in adsorber beds of the proposed gaseous udste system is approximately 20 tons as' computed from the'following formula for the proposed operating conditions listed below:
KM t = D where t = recidence time (cinutes).
~y-~
K = Dynamic Adsorption Coef ficient.
D
. (cubic 'centicetars/gra:a)
J1 = Mass of Charcoal (grams)
F = Volueetric hlow.-(cubic centimeters / minute)~ ~
' Charcoal' Ecd Temperature
= 40 F r
MJninum Bed Operating
= 1 Atn. (14.7 psia)
-Pressure Xenon delay (residence
= 20 days (28,800 minutes) tice)
^
Total volunetric flow rate = 20 SCFM* (566,400 cubic centimeters / minute)
Relative humidity of
= 30%
entering gas The dynnmic adsorption coefficient at the above referenced conditions for xenon is approximately B50 cc/gm.
The weight of charcoal is therefore:
l tF = (28,800 minutes)
(566,400 cc/ min)
M " Ep
,850 cc/gm
=.19.19 x 106 gns = 21.2~ tons
?* Reference conditions are 600F and 14.7 psia.
2-3
(: )
_)
lience, the weight of charcoal adsorbers to be inctalled at Cyster Creek tiuclear Station will be on the order of 20 tons.
The number of beds pro-vided is dependent on the vendor selected and is not known at this time.
J 4 -:2@
,. -r S
.3 s,
e en d *
.y-F,
% ream,
i e
l t
4 2-2
-. ~..
.. -. - ~ - -
)
.iQUESTIO" 3 i
-It istproposed to insta111the recombiners downstream of the delay linc.'
-State the reasons for.the proposed installation location-sinc ~eLit appears that installation of theLrecombincts ahead of the delay line cay be ad-
. vantageous because it would provide for longer _ deJ ir of the noble gases end eliminate the possibility of hydrogen explosions in-the' delay line.
4 RESP 0NSE:
Installation.of the reconbiner subsystem ahead of,the delay pipe would holdup.
)G:non and Krypton isotopes approximately' S hours longer than if installed downstream of khe delay pipe assuming a design basis. air in leakage rate of l
a -
i 20 SC111. Tnis additional delay, however,-has a negligibic effect on the de-J contamination factor achieved by the proposed system.
e i
l The consequences of a hydrogen explosion in the delay'line will not be increased
- due to the installation of the recombiner after the delay line.
Since the delay line is designed to withstand the effects of-a hydrogen explosion, installation of.the recorbiner vpatrean en eliminate the paaaibility of a bydrocon explonion-is not required.
Furthermore, recombiners operating at Tsuruga and KRB.for 4
g several years have not initiated any hydrogen explosion.
t The reasons for installing the-recombiner subsystem downstream of the delay line are as follows :
1.
Roduce the number of interconnectiens with the existing syster.l.
If the recombiner subsystem were located in f ront of the existing delay.line and charcoal subsystem downntream of the delay line, two 2
tie-ins to the existing system would be required. With the proposed arrangement only one tie-in is required.
Reducing the number of tie-ir.s will reduce-the interconnection time and will reduce the radiation exposures to the personnel making the tie-ins.
3-1
~
... ~. -...
i educed r.hielding~requiressnts
._ 2._
R The existing-delay lino _ holds' noble. gases _up to one h'our.
Locating'the recombiner subsysten downstream of,the delay
-line will reduce the slifelding requirement for the recombiner subsysteci. -
~
3.
Simplification of Preoperational Testing By installing.the recorbiner subsystem ' downstream of the delay pipe, it may be tested no a unit.with the charcoal adsorber
~
subsystem prior.to startup.
4'.
Economic and Space Considerations Locatir.g the recombiner in front of the delay ifne would require tuo new buildings,.onc with the recombiner subsystem
'and ' the othch with the charcoal subsystem The proposed
~
arrangement recuires only onc new building.
There is a minimal. amount of availabic space within the Turbine Eu11 ding. A recombiner subuyatem with adequate redundancy could not be installed in the Turbine Building without moving oxisting equipment and changing the flow ochema of the air ejectors.
Furtlier, there is no convenient location adjacent to the Turbine Building in the vicinity of the SJAE room on which a building can be erected to house the recombiner subsystem.
4 4
4 g,
3-2
-.,,... *,., ~
y
+
a 1;
igpEST7&l'4
+
- X
. ['
The Detergent and Laundry k*aste. Subsystem'wil11 utilize a detergent evaporator. -
.For;this evaporator, providcEthe. capacity,Ldesign temperature and design
- precsure..
RESPONSE
It'is anticipated that the' detergent-waste evaporator to be' installed at.
Oyster Crt:ek will be of a nomir'ial 4320_GFD capacit,y.
The "nornal' operation"fand " anticipated operational' occurrence" flow rates =
sssigned to detergent' waste in thei source term calculation was 4,000 GFD.
'this is a conservativo estiu: ate and was used only to establish a prudent i leve1Jof conservatism in'the annual activity rele'ase estimate.
To date, the production.of detergent and laundry waste at Oyster Creek has averaged
'800 CPD.
The schedulo, for the redesign 'of-the liquid radwaste system requires.that tho' new high. purity and chemical / floor drain weste subsystem be' constructed
. and. operational before the detergent and laundry waste subsystem can be 4
installed.
Detailed design of this subsystem has not progressed to.the point where it is possible to specify the design pressure and temperaturc
' of.the detergent waste evaporator at'this time. However, from the pre-liminaiy design information' which is avaflabic at present, it can bc assumed that the' steam side of the evaporator will operate at a pressuto e
< 75 ps'ig and the saturated steam temperaturh associated with that prensure-(320'T).. The procecs fluid side will operate at atmospheric.
- or sub-atmospheric: pressure and'.a temperature:of 212*F or less.
This is t
.r based entirely on preliminary estirnates. and is subject to' modification as
~
the;. design pro;;resses. ' Changes made in the liniting conditions specified
[
Twi31.ho pronpt.ly? reported.
.s 4-1 t
i v-
- -,. - +
.,.rn m,
-.-.y-m
. - ~
.r.-
-