ML20135J083
| ML20135J083 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 08/31/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19273A537 | List:
|
| References | |
| NUDOCS 8509250203 | |
| Download: ML20135J083 (106) | |
Text
_ _ _________ - -__-______ -
)
i 11.0 RAD 10ACllVE WASTE MANAGEMENT 11.1 Source Terms O The source term is a realistic model used to predict expected long-term average concentrations of radionuclides in the primary and secondary fluid stream and an average plant's releases over its lifetime. This realistic model, based on available measured nuclide concentrations during~ normal operation, was formulated as a standard f or the American National Standard O Source Term Specifications, ANSI N237 0} , and is the source term model used in NUREG-0017(2) ,
11.1.1 Reactor Coolant Activity 11.1.1.1 Fission and Corrosion Products The parameters used to describe the source tenn model are given in lable l 11.1-1 together with the range of values utilized by ANSI N237-1976.
Corrections have been made according to the ANSI N237-1976 standard formulas.
Operation of the gaseous waste processing system (GWPS) is assumed. The Y parameter is interpreted as equal to the stripping f raction and is calculated using the f ormula in Table 11.1-1. These stripping f ractions apply to the gaseous waste management system. Stripping fractions (Y parameter) are listed in Table 11.1-1.
Specific activities in the primary coolant, based on the parameters of lable 11.1-1, are given in Table 11.1-2.
11.1.1.2 Tritium Production and Release to the Reactor Coolant There are two principal contributors to tritium production: the ternary fission source and the dissolved boron in the reactor coolant. Additional contributions are made by lithium-6, 11thium-7, and deuterium in the reactor water. Tritium production f rom the various sources is shown in Table 11.1-3.
WAPWR-WM 11.1-1 AUGUST, 1985 3133e:ld n509250203 850920 DR ADOCK 0 % 1 --- - _
i 4
Since tritium is found mainly as water, the concentration of' tritium in the primary coolant is controlled by discharging tritiated water f rom the plant.
The tritium concentration in the primary coolant is assumed to be controlled at 1.0 wei/g.
O Additional background information on tritium production is given in
- Reference 3.
11.1.1.3 Activation of Water Nitrogen-16 is produced by the 0-16 (r., p) N-16 reaction. The N-16 activity
]
in the primary coolant is the controlling radiation source in the design of the secondary shielding inside the containment. However, with a half-life of 4
7.11 sec., no N-16 is expected to be discharged to the environment through any j process pathway during normal, plant operation.
i j
The principal source of carbon-14 is the thermal neutrc.n reaction with oxygen-17 in the primary coolant: 0-17 (n, a) C-14. Based on NUREG-0017, the C-14 production rate is 8 ci/yr with I ci/yr released by way of containment venting and the remainder discharged by the gaseous waste processing system.
11.1.2 Secondary Coolant Activity !
l Nonnal plant operation is anticipated to result in a certain degree of l radioactivity within the secondary ecolant systems through primary to secondary steam generator tube leakage.
l The parameters used to describe the source term model are given in Table 11.1-1 together with the range of values utilized by ANSI N237-1976.
I O Corrections have been made according to the ANSI N237-1976 standard formulas.
i l Operation of the gaseous waste processing system is assumed. The Y parameter is interpreted as equal to the stripping f raction and is calculated using the lO i
, WAPWR-WM 11.1-2 AUGUS1, 1985 3133e:1d i
i
't i
i formula in Table 11.1-1. These stripping f ractions apply to the gaseous waste
- management system. Stripping fractions (Y parameter) are listed in Table
- 11.1-1. j Specific activities in the secondary coolant, based on the parameters of Table 11.1-1, are given in Table 11.1-2.
f 11.1.3 Argon-41 Production in the Containment Atmosphere
- O Argon-41 is formed by neutron activation of stable, naturally occurring Ar-40 in the containment air surrounding the reactor vessel. The Ar-41 is released to the environment when the containment is vented or purged.
l NUREG 0017 recommends an estimated annual release rate of 25 C1/ year for Ar-41 f based en reported release data f rom 10 operating PWRs during the period of ,
i 1972 to 1974.
t 11.1.4 Volume Control Tank Vapor Space Activity The vapor space in the chemical and volume control system's volume control
! tank (VCT) is nonnally purged to the gaseous waste processing system to remove
- fission gases f rom the reactor coolant. The activity in the VCT vapor space
( is based on the VC1 stripping f ractions given in Table 11.1-1 and the primary coolant source term given in Table 11.1-2. The VCT vapor space source term is given in Table 11.1-4.
I 11.1.5 Gaseous Releases to the Environment The argon-41 produced in the containment is released to the environment when
\
i the containment is purged or vented, and the VC1 purge flow is released to the environment by way of the gaseous waste processing system, in addition, j gaseous radioactivity is released to the environment due to primary or i secondary coolant leakage to the containment or other buildings, offgases from l
the main condenser evacuation system, and cover and vent gases f rom equipment r containing radioactive material. Modeling of these releases is discussed in Subsection 11.3.3 of this module.
WAPWR-WM 11.1-3 AUGUST, 1985 3133e:1d N - -_ -,_-_ -_ - .- - . - . . . _ - _ - - - _ _ - - - . - - _ - . _ - - - . . _ _ - _ - --
f I
i 11.1.6 Radioactive Releases to the Environment by the Liquid Pathway j
The activity level in the various liquids destired for discharge is generally defined as a fraction of primary or secondary coolant activity which are given in Table 11.1-2. The volumes and activity levels of liquids discharged to the environment are discussed in Subsection 11.2.
1
\
! 11.1.7 References i
O 1. American National Standard Source Tenn Specification, ANSI N237-1976/
j ANS-18.1, approved May 11, 1976.
1 l 2. U. S. Nuclear Regulatory Consnission, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized f Water Reactors," NUREG-0017, Of fice of Standard Development, April 1976.
) 3. " Source Term Data for Westinghouse Pressurized Water Reactors," WCAP-8253, Revision 1, February 1976.
1 i i 1
i O l i.
l l .
l l
O >
WAPWR-WM 11.1-4 AUGUST, 1985 3133e:ld
- o o o
~
o o o o TABLE 11.1-1 (SHEET 1 0F 2)
PARAMETERS USED TO DESCRIBE THE REACTOR SYSTEM-REALISTIC BASIS ANSI N237 Range Parameter Symbol Units i
Value Maximum Minimum Thermal power P MWt 4200 3000 3000 Steam flowrate FS lb/h 1.7 x 107 1.7 x 107 1.3 x 107 Weight of water in reactor coolant system WP lb 6.7 x 105 6.0 x 105 5.0 x 105 Weight of water in all steam generators WS lb 5.4 x 105 5.0 x 105 4.0 x 105 Reactor coolant letdown flow (purification) FD lb/h 5.a v 104 4.2 x 104 3.2 x 104 Reactor coolant letdown flow (yearly average for FB lb/h 8.7 x 102 1.0 x 103 j boron control) 25 x 10 Steam generator blowdown flow (total) F80 lb/h 5.4 x 104 (a) 1.0 x 105 5.0 x 104 Fraction of radioactivity in blowdown steam that NBD -
1.0(a) 1.0 is not returned to the secondary coolant system 0.9 Flow through the purification system cation FA lb/h 5.0 x 103 7.5 x 104 demineralizer 0.0 Ratio of condensate demineralizer flowrate to NC -
0.0(a) 0.01 0.0 l the total stream flowrate Ratio of the total amount of noble gases routed Y -
(b) 0.01 to gaseous radwaste from the purification system 0.0 to the total amount routed from the primary coolant system (not including the boron recycle system)
Primary-to-secondarylleak rate -
lb/ day 100 '
100
- a. Assumed value for the purpose of talculating a secondary coolanc source term. This parameter may change for any specific plant requiring a redetermination of the secondary coolant source term.
- b. Volume control tank noble gas stripping fractions (based on 0.7 SCFM purge to the gaseous waste processing system)
WAPWR-WM 11.1-5 3133e:ld AUGUST, 1985
\
TA8LE 11.1-1 (SHEET 2 0F 2).
PARAMETERS USED TO DESCRI8E THE REACTOR SYSTEM-REALISTIC BASIS Isotope Stripping Fraction O Kr-83m 0.81 Kr-85m 0.67 Kr-85 0.32 Kr-87 0.86 Kr-88 0.75 O Kr-89 Xe-131m 0.99 0.26 Xe-133m 0.30 Xe-133 0.27 Xe-135m 0.95 Xe-135 0.48 Xe-137 0.99 Xe-138 0.96 The nuclide stripping f ractions are calculated using the following co';ation:
K0
?=1 KQ + A (KL + V) + P where:
? = nuclide volum control tank stripping f raction.
K= .
R = gas constant (45.59 'g * .g).
T = nominal volume control tank temperature (590'R).
M = molecular weight of water (18.0 g/g mol).
4 H = Henry's Law constant equal to 3.32 x 10 atm/mol fraction for krypton and 2.39 x 10 atm/mol fraction for xenon, at'130'F O Q = letdown or purification flowrate'(6.3 x 103 g/sec).
A = nuclide decay constant (sec-I).
L = volume control tank liquid mass (6.8 x 106 ,,3)
V = volume control tank vapor volume (1.02 x 107 g)
P = volume control tank purge rate to the gaseous waste management system, 2 3 at volume control tank conditions (1.30 x 10 cm /sec).
WAPWR-WM 11.1-6 AUGUST, 1985 3133e:1d
- TABLE 11.1-2 (SHEET 1 0F 3)
SPECIFIC ACTIVITIES IN PRINCIPAL-FLUID STREAMS-REALISTIC BASIS 4
Normal Plant Operation Source Terms (based on ANSI N237)
Volume Control Tank Purge of 1.30 x 102 cm3/s Group I - Noble Gases
, Reactor Steam- Steam Coolant Gen. Liq. Gen. Steam Activity Activity Activity Nuclide (uti/a) (uCi/c) (uCi/a)
Kr-83m 1.8 x 10-2 Nil 4.5 x 10-9
- Kr-85m 2 Nil 2.1 x 10-8
] Kr-85 8.5 5.6 x x 10 10-3 Nil 1.4 x 10-9 5.5 x 10-2 Nil Kr-87 1.3 x 10-8
, Kr-88 1.7 x 10-l Nil 8 i
Kr-89 5.1 x 10-3 Nil 4.0 x 10 1.2 x 10-9 Xe-131m 1.6 x 10-2 Nil 4.0 x 10-9 Xe-133m 8.5 x 10-2 Nil 2.1 x 10-8 l Xe-133 4.3 x 100 Nil 1.1 x 10-6 l Xe-135m 1.3 x 10-2 Nil 3.1 x 10-9 Xe-135 2.4 x 10-1 Nil 5.9 x 10-8 Xe-137 9.1 x 10-3 Nil 2.2 x 10-9 Xe-138 4.4 x 10-2 Nil 1.0 x 10-8 Group II - Halogens
- Reactor Steam Steam t
Coolant Gen. Liq. Gen. Steam Activity Activity Activity l Nuclide (pCi/a) (uCi/a) (uci/a) 4 Br-83 4.8 x 10-3 9.9 x 10-8 g,9 x 10-10
- Br-84 2.6 x 10-3 1.6 x 10-8 1.6 x 10-10 l Br-85 3.1 x 10-4 1.7 x 10-10 1.7 x 10-12 i
1-130 2.0 x 10-3 9.7 x 10-8 9.7 x 10-10 l I-131 2.5 x 10-I 1.9 x 10-5 1.9 x 10-7 i 1-132 1.0 x 10-I 7.3 x 10-6 7.3 x 10-8 j I-133 3.6 x 10-1 2.0 x 10-5 2.0 x 10-7 I-134 4.7 x 10-2 4.4 x 10-8 4.4 x 10-9 I-135 1.9 x 10-I 6.9 x 10-6 6.9 x 10-8 O
WAPWR-WM 11.1-7 AUGUST, 1985 3133e:1d
l
[
l l
TABLE 11.1-2 (SHEET 2 0F 3)
SPECIFIC ACTIVITIES IN PRINCIPAL FLUID STREAMS-REALISTIC BASIS Group III - Rubidium and Cesium O Reactor Coolant Activity Steam Gen. Liq.
Activity Steam Gen. Steam Activity Nuclide (vCi/c) (vCi/a) (UCi/c)
Rb-86 7.8 x 10-5 6.5 x 10-9 6.5 x 10-12 O Rb-88 Cs-134 Cs-136 2.0 x 10-1 2.3 x 10-2 1.2 x 10-2 6.6 x 10-6 1.5 x 10-6 8.3 x 10-7 6.6 x 10-10 1.5 x 10-9 8.3 x 10-10 Cs-137 1.6 x 10-2 1.2 x 10-6 1.2 x 10-9 Ba-137m 1.6 x 10-2 1,1 x 10-6 1.1 x 10-9 Group IV - Nitrogen-16 Reactor Steam Steam Coolant Gen. Lig' . Gen. Steam Activity Activity Activity Nuclide (pCi/a) (yCi/c) (pCi/c)
N-16 4.0 x 101 8.3 x 10-7 8.3 x 10-8 Group V - Tritium Reactor Steam Steam Coolant Gen. Liq. Gen. Steam Activity Activity Activity Nuclide (UCi/c) (vCi/c) (uCi/c)
H -3 1.0 1.0 x 10-3 1.0 x 10-3 O
O s
k .
h!APWR-WM f 11.1-8 ', AUGUST, 1985 3133e:1d
- c s; -
s ,. .
\ **1p %
. m
TA8LE 11.1-2 (SHEET 3 0F 3)
SPECIFIC ACTIVITIES IN PRINCIPAL FLUID STREAMS-REALISTIC 8 ASIS Group VI - Miscellaneous Isotopes Reactor Steam Steam Coolant Gen. Liq. Gen. Steam Activity Activity Activity Nuclide (vCi/a) (vCi/a) (vCi/c)
C r-51 1.7 x 10-3 1.2 x 10-7 1.2 x 10-10 O Mn-54 Fe-55 2.8 x 10-4 1.4 x 10-3 3.0 x 10-8 1.0 x 10-7 3.0 x 10-11 1.0 x 10-10 Fe-59 9.0 x 10-4 7.7 x 10-8 7.7 x 10-11 Co-58 1.4 x 10-2 1.1 x 10-6 1.1 x 10-9 Co-60 1.8 x 10-3 1.3 x 10-7 1.3 x 10-10 Sr-89 3.2 x 10-4 3.1 x 10-8 3.1 x 10-11 Sr-90 9.0 x 10-6 7.5 x 10-10 7.5 x 10-13 Sr-91 6.3 x 10-4 2.6 x 10-8 2.6 x 10-11 Y-90 1.1 x 10-6 4.2 x 10-10 4.2 x 10-13 Y-91m 3.6 x 10-4 2.3 x 10-8 2.3 x 10-11 Y-91 5.8 x 10-5 4.6 x 10-9 4.6 x 10-12 Y-93 3.3 x 10-5 1,7 x 10-9 1.7 x 10-12 O Zr-95 Nb-95 Mo-99 5.4 x 10-5 4.5 x 10-5 7.7 x 10-2 4.6 x 10-9 4.6 x 10-9 6.3 x 10-6 4.6 x 10-12 4.6 x 10-12 6.3 x 10-9 Tc-99m 4.7 x 10-2 1.5 x 10-5 1.5 x 10-8 Ru-103 4.1 x 10-5 3.1 x 10-9 3.1 x 10-12 Ru-106 9.0 x 10-6 7.5 x 10-10 7.5 x 10-13 Rh-103m 4.5 x 10-5 1.5 x 10-8 1.5 x 10-11 Rh-106 1.0 x 10-5 4.2 x 10-9 4.2 x 10-12 Te-125m 2.6 x 10-5 1.4 x 10-9 1.4 x 10-12 Te-127m 2.5 x 10-4 1.4 x 10-8 1,4 x 10-11 Te-127 8.2 x 10-4 8.6 x 10-8 8.6 x 10-11 Te-129m 1.3 x 10-3 9.3 x 10-8 9.3 x 10-11 Te-129 1.6 x 10-3 4,4 x 10-7 4.4 x 10-10 C) Te-131m 2.3 x 10-3 1.4 x 10-7 1.4 x 10-10 Te-131 1.1 x 10-3 4.0 x 10-7 4.0 x 10-10 Te-132 2.5 x 10-2 1.6 x 10-6 1.6 x 10-9 Ba-140 2.0 x 10-4 1.5 x 10-8 1.5 x 10-11
) La-140 - 1.4 x 10-4 2.0 x 10-8 2.0 x 10-11 Ce-141 6.3 x 10-5 4.7 x 10-9 4.7 x 10-12 Ce-143 3.7 x 10-5 2.4 x 10-9 2.4 x 10-12 Ce-144 3.0 x .10-5 3.0 x 10-9 3.0 x 10-12 Pr-143 4.5 x 10-5 3.3 x 10-9 3.3 x 10-12 Pr-144 3.3 x 10-5 1.6 x 10-8 2.5 x 10-11 Np-239 1.1 x 10-3 6.6 x 10-8 6.6 x 10-11 MAPWR-WM 11.1-9 AUGUST, 1985 3133e:ld
TABLE 11.1-3 TRITIUM PRODUCTION a)
O Release Expected to Total Produced Reactor Coolant Tritium Source (Ci/ cycle) (Ci/ cycle)
Ternary fissions Initial cycle 23,520 2352 Equilibrium cycle 23,520 2352 Coolant (soluble boron)
Initial cycle 420 420 Equilibrium cycle 530 530 Coolant (lithium, deuterium)
Initial cycle 338 338 Equilibrium cycle 338 338 Total initial cycle 16,500 3110 Total equilibrium cycle 11,400 3220
- a. The following parameters were used:
Power level, 4200 MWt Release fraction from fuel,10 percent Lithium concentration (99.9 atom-percent lithium-7), 2.2 ppm Initial cycle operating time,13140 ef fective full-power h Equilibrium cycle operating time,13140 ef fective f ull-power h O
O WAPWR-WM 11.1-10 AUGUST, 1985 3133e:1d
_ _ . _ _ _ _ _ _ _ _ _ _ . ~ _ . . - . _ . _ _ _ _ . _ _ . _ . . - - _ _ _ . . _ _ _ . . . - _ _ _ _ _ _ . - _ . _ _ .
i )
i r 4
l (
TA8LE 11.1-4 VOLUME CONTROL TANK VAPOR SPACE ACTIVITIES I "}
!O ;
Activity (b) l Nuclide (pCi/cm }. l i Kr-83m 7.7 x 10 -2 t f Kr-85m 6.1 x-10 -I
-2
! Kr-85 8.5 x 10 ,
-I Kr-87 1.7 x 10 l
-I Kr-88 9.2 x 10 l
-4
. Kr-89 8.1 x 10 I
-I Xe-131m 1.9 x 10
-I l Xe-133m 9.5 x 10 Xe-133 5.0 x 10 Xe-135m 9.4 x 10 Xe-135 2.0
!^ Xe-137 1.8 x 10 -3
-2 Xe-138 3.0 x 10
- a. Based on parameters given in Table 11.1-1.
i b. At 130*F and 30 psig. i i
l O
i i
!O
, i i i r i O ,
WAPWR-WM ,
11.1-11 AUGUST, 1985 3133e:1d
11.2 Liquid Waste Management Systems The liquid waste management systems include all systems that may be used to process for disposal liquids containing radioactive material. These include:
A. Boron recycle system (BRS) (Subsection 9.3.4 of RESAR-SP/90 PDA Module
- 13. " Auxiliary Systems").
B. Steam generator blowdown processing system (Subsection 10.4.8 of RESAR-SP/90 PDA Modules 6 and 8 (combined) " Secondary Side Safeguards System / Steam and Power Conversion System").
C. Turbine building floor drain system (Subsection 9.3.3 of RESAR-SP/90 PDA Module 13 " Auxiliary Systems").
D. Liquid waste processing system (LWPS) (Section 11.2).
This section primarily addresses the LWPS. The other systerr.s are also addressed in Subsection 11.2.3 of this module, which discusses the expected releases from all liquid waste management systems.
l The LWPS is designed to control, collect, process, handle, store, and dispose of liquid radioactive waste generated as the result of normal operation, including anticipated operational occurrences.
11.2.1 Design Bases O
The conformance of the LWPS design with the criteria of applicable Regulatory Guides is discussed in Section 1.8 of this module.
O 11.2.1.1 Capacity The projected flows of various liquid waste streams to the LWPS are specified p in Table 11.2-1. The LWPS provides adequate capacity to meet the anticipated b processing requirements of the plant.
WAPWR-WM 11.2-1 AUGUST, 1985 3236e:1d
1 O The LWPS design can accept equipment malfunctions without affecting the
%Y capability of the system to handle both anticipated liquid waste flows and possible surge load due to excessive leakage. Surge capacity of individual tanks is discussed in Subsection 11.2.2.6.2.
O Portions of the LWPS may become unavailable as a result of the malfunctions listed in Subsection 11.2.1.1.1 through 11.2.1.1.3.
O Ample surge capacity of the system and the low load factor of the processing V equipment permits the system to accommodate waste until failures can be repaired and normal plant operation resumed. In addition, the LWPS is designed to accommodate the anticipated opt rational occurrences described in Subsections 11.2.1.1.4 through 11.2.1.1.6.
i 11.2.1.1.1 Pump Failure
- Where operation is . not essential and surge capacity is available, a single pump is provided. Two reactor coolant drain tank (RCOT) pumps are provided because the relative inaccessibility of the containment during plant operation would hinder maintenance. Pump repair and replacement is facilitated by using two standard pump designs for the eight applications in the LWPS. To protect the pumps .from damage due to loss of suction, each pump is interlocked to stop on a low level condition in the tank feeding the pump.
11.2.1.1.2 Filter, Strainer, or Demineralizer Plugging Instrumentation is provided to give local indication of the pressure drop across all filters, strainers, and demineralizers. Periodic rhecks of the
. pressure drops provide indication of the equipment fouling, thus permitting s corrective action to be taken before an excessive pressure drop is reached.
i ,
i 11.2.1.1.3 Waste Evaporator Failure The waste holdup tank normally provides the only feed to the waste evapora-tor. The tank has sufficient surge capacity to accomodate approximately 35
.WAPWR-WM 11.2-2 AUGUST, 1985 3236e:ld
. _ - - _ _ _ = - - _.
\ .
days of normal inflow without evaporator processing. This is based on an initial tank level of 40 percent and inflow according to Table 11.2-1.
The floor drain tank contents normally do not require processing by the waste evaporator. However, if processing by the evaporator is required and it is {
not available, the tank has suf ficient surge capacity to accommodate approxi-mately three days,of normal inflow. This is based on an initial tank level of 40% and inflow according to Table 11.2-1.
O The monitor tank demineralizer may also be used to process the floor drain tank contents to reduce the activity level and permit discharge. Thus, unavailability of the evaporator is unlikely to have any impact on the ability to process waste liquid directed to the floor drain tank.
11.2.1.1.4 High Leakage Rate The system is designed to handle a 1-gal / min primary coolant system leak in addition to the expected leakage during normal operation. Operation of the system is the same as for normal operation except that the load on the system is increased. A 1-gal / min leak into the RCDT is handled automatically but may increase the load factor of the recycle evaporator.
The extra leakage may be directed to the waste holdup tank or the floor drain tank. Each of these tanks has the capacity to accommodate over 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of l
1 the increased inflow without evaporator processing based on an initial tank level of 30 percent. The floor drain tank contents are not necessarily processed through the evaporator; they may be discharged without treatment if i sample analysis indicates that the waste quality is acceptable for discharge.
4 11.2.1.1.5 Refueling During refueling the load on the LWPS is expected to increase, but operation f .[' is the same as for normal plant operation, and there is no significant effect 4
on the performance capability of the LWPS.
WAPWR-WM 11.2-3 AUGUST, 1985 3236e:1d
11.2.1.2 Controlled Release of Radioactivity The LWPS provides the capability to reduce the amounts of radioactive nuclides released in the liquid wastes through the use of demineralization, evaporative separation with disposal of concentrates and recycling of clean tritiated water for re-use in the reactor plant when possible, and time de' lay for decay of short-lived nuclides.
The assumed equipment decontamination f actors are included in Table 11.2-2.
The radioactive source terms and annual average flowrates that will be processed in the LWPS or discharged to the environment during normal operation are estimated in Table 11.2-1.
Before any liquid radioactive waste is discharged, it is pumped to a monitor tank. A sample of the nonitor tank contents is analyzed and the results logged. In this way, a record is kept of all planned releases of radioactive liquid waste. The liquid waste is discharged from the monitor tank in a batch )
operation, and the discharge flowrate is restricted as necessary to maintain an acceptable concentration when diluted by the circulating water discharge flow. These provisions preclude uncontrolled releases of radioactivity. In addition, the discharge line contains a stop valve interlocked with radiation monitor on the system discharge line. The valve automatically closes and an alarm is actuated if the activity in the discharge stream reaches the monitor setpoint. The stop valve is also interlocked to isolate discharge flow if sufficient dilution flow is not available.
O To minimize leakage f rom the LWPS, the system is of all-welded construction except where flanged connections are required to facilitate component neintenance. The use of canned rotor design pumps for most applications minimizes system leakage and the release of radioactive gas that might be entrained in the leaking fluid to the building atmosphere.
Provisions are made to preclude uncontrolled spills of radioactive liquids due to tank overflows. These provisions include tank level indication, level annunciation, and overflow disposition.
WAPWR-WM 11.2-4 AUGUST, 1985 3236e:1d
f
(
11.2.1.2.1 Expected Releases THe LWPS design ensures that the annual average concentration limits established by 10 CFR 20 ( Appendix B, table II, column 2) for liquid releases
- are -not exceeded during plant operation with expected levels of fuel cladding defects. Subsection 11.2.3 of this module discusses the calculated releases i of radioactive materials f rom the LWPS and other portions of the liquid waste management systems resulting from normal plant operation.
O 11.2.1.2.2 Off-Normal Operation l Subsection 11.2.1.1 discusses the capability of the LWPS to accommodate i various equipment failures and anticipated operational occurrences. During these anticipated occurrences, the ef fectiveness of the LWPS in controlling releases of radioactivity remains essentially unaffected, so releases are limited to approximately the same as during nonnal operation.
The GALE codeIII, used to calculate the release concentration described in Subsection 11.2.1.2.1, contains an adjustment factor of 0.15 Ci/ year to
- account for abnormal occurrences resulting in unplanned releases.
i 11.2.1.3 Equipment Design l
l The LWPS equipment design parameters are provided in Table 11.2-2.
s The seismic design classification and safety classification for the LWPS components and structures are listed in Table 3. 2-1 of RESAR-SP/90 PDA Module 7 " Structural / Equipment Design". Safety class designations are also
- indicated on the LWPS piping and instrumentation diagram, Figure 11.2-1.
O 11.2.2 System Descriptions The LWPS collects and processes potentially radioactive wastes for recycling, solidification, or release to the environment. Provisions are made to sample Oi and analyze fluids before' discharge. Based on the laboratory analysis, these I
WAPWR-WM 11.2-5 AUGUST, 1985 3236e:ld i
wastes are either retained for further processing or released under controlled
{
4 conditions through the cooling water system, which dilutes the discharge flow. A permanent record of liquid releases is provided by analyses of known volumes of effluent.
4 i
O The bulk of the radioactive liquid discharged f rom the reactor coolant system (RCS) is processed and recycled by the boron recycle system (BRS). This limits input to the LWPS and results in the processing of relatively small quantities of what are generally low activity level wastes.
The LWPS is arranged to recycle as much reactor grade water entering the system as possible. This is implemented by the segregation of equipment i drains and waste streams to prevent intermixing of liquid wastes. The LWPS can be divided into the following subsystems:
- A. Reactor coolant drain tank (RCDT) . subsystem This portion of the LWPS collects nonaerated, reactor grade ef fluent
- from sources inside the containment for recycling.
j B. Drain Channel A This portion of the LWPS collects aerated, reactor grade ef fluent that f
i normally can be recycled.
i ,
C. Drain Channel B l
This portion of the LWPS processes all effluent that is normally to be
- discharged to the environment and is not suitable for recycling.
i i
In addition, the LWPS provides capability for handling and storage of spent .
ic i exchange resins.
O WAPWR-WM 11.2-6 AUGUST, 1985 3236e:1d
The LWPS does not include provisions for processing secondary system wastes.
Secondary system effluent is handled by the steam generator blowdown processing system (SGBPS) and by the turbine building drain system. Estimated releases from these systems are discussed in Subsection 11.2.3 of this module. The LWPS design, which segregates primary and secondary wastes, minimizes the amount of water that must be processed by the waste evaporator by discharging low activity wastes directly, where permissible, with no treatment.
p 4
Instrumentation and controls necessary for the operation of the LWPS are located on a control board in the auxiliary building. Any alarm on this control board is relayed to the main control board in the control room.
The piping and instrumentation diagram and process flow diagrams for the LWPS
' are shown on Figures 11.2-1 and 11.2-2, respectively. Table 11.2-1 lists the assumptions regarding flows and activity levels. Figure 11.2-2 also includes process flow diagrams for the letdown path in the chemical and volume control
. 3 i
(Q system, for the boron recycle system and for the steam generator blowdown processing system.
11.2.2.1 Reactor Coolant Drain Tank Subsystem Recyclable reactor grade ef fluents enter this subsystem from valve leakoffs, the reactor coolant pump No. 2 seal leakoffs, the reactor vessel flange leakof f, and other deaerated, tritiated water sources inside. the containment.
This deaerated, tritiated liquid is normally processed by the BRS for reuse, j but if desired, it can be sent to the LWPS drain channel A for processing.
- Connections are provided for draining the RCS loops and the safety injection system (SIS) accumulators and for cooling the pressurizer relief tank. In addition, refueling canal drains can be routed to the ref ueling water storage O tank using the RCDT pumps.
The RCDT contents are continuously recirculated through the RCDT heat exchanger to maintain the desired temperature. Level is prevented from f varying significantly from a control value which automatically opens a path ,
WAPWR-WM 11.2-7 AUGUST, 1985 3236e:ld
I f rom the recirculation line to the BRS when nonnal tink level is exceeded.
The RCDT is also connected to the gaseous waste processing system (GWPS) vent header. Hydrogen gas bottles connected to the RCD 1 ensure a hydrogen blanket. Maintaining a constant level minimizes the amount of gas sent to the GWPS and minimizes the amount of hydrogen used. Provisions for sampling the gas are provided. )
11.2.2.2 Drain Channel A Subsystem Ae rated , tritiated liquid enters drain channel A through lines connected to the waste holdup tank. Sources of this aerated liquid are as follows:
A. Accumulator drainage (via RCDT pump suction).
B. Sample room sink drains (excess primary sample volume only).
C. Ion exchangers, filter, pump, and other equipment drains.
If the quality of water in the containment sump or auxiliary building sump is acceptable for recycling, it may be directed to the waste holdup tank. If the water quality is not acceptable, it must be directed to the floor drain tank for disposal.
The collected aerated drainage is pumped or flows to the waste holdup tank, the initial collecting point for liquids processed through the waste evaporator before reuse.
The basic composition of the liquid collected in the waste holdup tank is boric acid and water with some radioactivity.
When there is sufficient liquid collected in the waste holdup tank, the waste evaporator feed pump delivers the contents of the waste holdup tank through a filter, to the waste evaporator package for removal of radioisotopes, boric O
WAPWR-WM 11.2-8 AUGUST, 1985 3236e:ld
/
(g} acid, and air prior to reuse in the RCS. The gases are stripped and sent to the plant vent. The condensate leaving the waste evaporator passes through a waste evaporator condensate demineralizer and a filter to the waste evaporator condensate tank. The condensate can bypass the demineralizer when waste holdup tank samples indicate low radioactivity levels. This bypassing reduces the amount of waste resin to be solidified. When a suf ficient quantity of water has been collected in the waste evaporator condensate tank, it is normally transferred to the reactor makeup water storage tank (RMWST) by the waste evaporator condensate pump for reuse. Samples are taken at sufficiently frequent intervals to ensure proper operation of the system and to minimize the need for reprocessing. If a sample indicates that further processing is required, the condensate can be passed through the waste condensat, demineralizer or, if necessary, returned to the waste holdup tank for additional evaporation. The evaporator bottoms are discharged to the solid waste processing system for solidification.
11.2.2.3 Drain Channel B Subsystem V)
Drain channel B is provided to collect and process nonreactor grade liquid wastes. These include:
o Wastes f rom floor drains.
o Equipment drains containing nonreactor grade water.
o Laundry and hot shower drains.
b(N o Other nonreactor grade sources.
Drain channel B is comprised of three drain subchannels, each associated with one of the following tanks.
G WAPWR-WM 11.2-9 AUGUST, 1985 3236e:ld
-- - - . _ - - - ~ . -. . . - . - _ . -
1 A. Laundry and Hot Shower Tank The laundry and hot shower tank is provided to collect and process ;
- waste ef fluents f rom the plant laundry and personnel decontamination .
! showers and hand sinks.
1 4
Laundry and hot shower drains nonnally need no treatment for removal of radioactivity. This water is transferred to a waste monitor tank through the laundry and hot shower tank filter for eventual discharge. If sample analysis indicates that dec'ontamination is l necessary, the water can be directed through the waste monitor tank i demineralizer for cleanup.
) B. Floor Drain Tank i
, Water may enter the floor drain tank f rom system leaks inside the
] containment through the containment sump, and from system leaks in the l auxiliary building through auxiliary building sumps and the floor
- d rains. Sources of water to the containment sump and auxiliary f building sumps and floor drains are the following
l 1. Fan cooler leaks.
! l i
{ 2. Secondary side steam and feedwater leaks.
1
- 3. Primary side process leaks.
j
! 4. Spent fuel pool liner leaks.
i .
. 5. Component cooling water leaks.
l
- 6. Decontamination water.
i
!O i
i i WAPWR-WM 11.2-10 AUGUS1, 1985
- 3236e
- 1d
_ __ - . _ . _. ~. - __ - - . .. -. .
1 If the quality of the water in the containment sump or auxiliary building sumps is acceptable for recycling, the water may be directed to the waste holdup tank. However, unl.ess a large primary side leak develops, this liquid would probably not be directed to the waste holdup tank because it would be diluted and contaminated by water from other nonreactor grade sources.
Another source of water to the floor drain tank is the chemical laboratory drains. Excess nonreactor grade samples that are not chemically contaminated and laboratory equipment rinse water are drained to the floor drain tank.
4 Generally, the contents of the floor drain tank are discharged without processing by the waste evaporator. Floor drain tank contents are pumped to a waste monitor tank for ultimate discharge.
l If the activity in the floor drain tank liquid is such that the discharge limits cannot be met without cleanup, the liquid can be
! processed by the waste monitor tank demineralizer or by the waste evaporator. The waste evaporator condensate is pumped to a waste moniter tank for ultimate discharge and the concentrates are transferred to the solid waste processing system.
C. Chemical Orain Tank i
Laboratory samples which contain reagent chemicals (and possibly
, tritiated liquid) are discarded through a sample room sink which drains to the chemical drain tank. Chemical drains requiring radwaste processing are sent to the solid waste management system.
1 i Any liquids released to the environment by the LWPS are first directed to a waste monitor tank. Before releasing the contents of a waste monitor tank, a sample is taken for analysis. The findings are logged, and, if the activity level is within acceptable limits, the tank contents are rcleased to the l
l l
WAPWR-WM 11.2-11 AUGUST, 1985 3236e:ld
discharge canal. The discharge valve is interlocked with a process radiation monitor and closes automatically when the radioactivity concentration in the liquid discharge exceeds a preset limit. The radiation element is located upstream of the discharge valve at a distance sufficient to close the valve before passing the fluid that activated the detector trip signal. The stop valve is also interlocked with the circulating water pump to block flow if sufficient dilution water is~ not available. The radiation monitor is described in Section 11.5 of this module. A permanent record of the radioactive releases is provided by a sample analysis of known values of waste effluent released. Liquid waste discharge flow and volume are also recorded.
If the monitor tank contents are not acceptable for discharge, the fluid can be held for a time to allow activity to decay to acceptable levels, or it can be further processed by the waste evaporator or waste monitor tank demineralizer.
11.2.2.4 Spent Resin Handling Subsystem This subsystem collects, handles, and processes spent resins f rom the primary fluid systems prior to their disposal.
Spent resin from the primary system demineralizers is transported to and stored in the spent resin storage tank prior to being d rumed . The spent resin sluice portion of the LWPS consists of a spent resin sluice filter, spent resin sluice pump, and the spent resin storage tank. The resin sluice water, af ter being directed to an ion exchange vessel by the sluice pump, O returns to the spent resin storage tank for reuse.
This sluicing of spent resin f rom primary plant demineralizers is accomplished without generating a large volume of liquid waste.
Resin slurry fran the spent resin s+.orage tank is sent to the solid waste processing system by pressurizing the tank with nitrogen.
O WAPWR-WM 11.2-12 AUGUST, 1985 3236e:1d
11.2.2.5 Liquids f rori Sources Other Than the Liquid Waste Processing System 11.2.2.5.1 Steam Generator Blowdown Processing System Blowdown from the steam generators of each unit is cooled, filtered, and demineralized. Normally it is then returned to the condensers for reuse as condensate makeup, but it may be discharged to the environment. The SGBPS is described in Subsection 10.4.B of RE iAR SP/90 PDA Modules 6 and 8 (combined),
" Secondary Side Safeguards System / Stear.: and Power Conversion Systems".
11.2.2.5.2 Boron Recycle System Water is processed by the BRS using an evaporator to concentrate boric acid solution to the concentration required in the boric acid tanks. Both evaporator condensate and concentrates are normally recycled; however, a fraction of the condensate is discharged for the purpose of avoiding excessive buildup of tritium in the reactor coolant water. The BRS is described in Subsection 9.3.4 of RESAR SP/90 PDA Module 13, " Auxiliary Systems".
11.2.2.5.3 Turbine Building Drain System The function of the turbine building drain system is to collect the floor drains and sampling wastes in the turbine t'vt k% g and other miscellaneous drains.
11.2.2.6 Equipment Description Principal design parameters for the LWPS equ'pment are given in Table 11.2-2.
All parts or components in contact with borated water are f abricated f rom or clad with austenitic stainless steel. Pumps are provided with vent and drain O connections.
Component safety classes, seismic design, and principal cc'J es are shown in Table 3.2-1 of RESAR SP/90 PDA Module 7, " Structural / Equipment Design".
O WAPWR-WM 11.2-13 AUGUST, 1985 3236e:ld
i i
11.2.2.6.1 Pumps i
Pumps in the LWPS have been standardized wherever possible. Where operation is not critical and surge capacity is available, a single pump has been i provided. Spare pumps can be kept onsite in case any pump should fail. Quick replacement is possible because:
f' !
o The pumps are flanged, not welded. !
o- The system has surge capacity.
i o Adequate vent, flush, and drain t;apabilities are provided. ;
i j o - The pumps are standardized.
! Two standard pump designs are utilized as described below.
j Pumps with identical head-flow characteristics are used for the following i applications:
a i
! o Spent resin sluice pumps.
l o RCDT pumps.
Another pump design is used for the following applications:
o Waste evaporator feed pumps.
o Waste evaporator condensate tank pumps.
lO o Chemical drain tank pump.
. o Waste monitor tank pumps.
i O
WAPWR-WM 11.2-14 AUGUST ,1985 3236e:1d.
- - . _ . . . _ - - _ - - . - _ _ - - . . _ _ _ - _ _ _ - _ _ - . _ _ _ _ . . . - . - . - . - = - . . , . _ -
, l s
o Floor drain tank pump.
o laundry and hot shower tank pump.
Globe valves are installed in pump discharge lines where necessary to prevent pump runout. Pump miniflow lines have locked-in-position globe valves to ensure that the minimum pump flow requirements are met.
A. RCDT Pump
- The design basis for this pump is that, in its function of. RCS drain,
- the coolant level reaches the midplane of the reactor vessel nozzles within an 8-hr period. Two pumps are furnished because of the relative inaccessibility of the containment during plant operation.
Both pumps are operated to meet the draining time requirement. One pump provides sufficient flow for normal operation of the RCDT portion of the LWPS. The liquid is sent to the recycle holdup tanks.
i O :
B. Waste Evaporator Feed Pump This pump supplies feed to the waste evaporator from the waste holdup i tank, and it can be used to transfer waste holdup tank ~ contents to the floor drain tank, if desired.
C. Waste Evaporator Condensate Pump The waste evaporator condensate tank pump is used to transfer the contents of the waste evaporator condensate . tank to the RMWS1 or the BRS holdup tank.
j O D. Chemical Drain Tank Pump This pump is used to transfer the liquid in the chemical drain tank to the solid waste processing system.
l l
l l WAPWR-WM 11.2-15 AUGUST, 1985 3236e:ld
E. Spent Resin Sluice Pump 4
One pump is provided to sluice resins from primary side demineralizers to the spent . resin storage tank. Its delivery flow is based on the velocity required to sluice resin in a 3-in. pipe.
F. Laundry and Hot Shower Tank Pump This pump is used to transfer the water from the laundry and hot shower tank to a waste monitor tank.
G. Floor Drain Tank Pump l
l This pump is used to transfer water f rom the floor drain tank to the j
waste monitor tank. The pump can also be used to supply the waste evaporator.
H. Waste Monitor Tank Pumps Two pumps are provided, one pump for each monitor tank to discharge wate= from the LWPS or for recycling if further processing is j required. The pump may also be used for circulating the water in the j waste monitor tank to obtain uniform tank contents, and therefore a representative sample, before discharge. These pumps can be throttled l to achieve the desired discharge rate.
! 11.2.2.6.2 Tanks A. Reactor Coolant Drain Tank One tank is provided to collect leakoff-type drains inside the containment at a central collection point for further disposition through a single penetration - via the RCD 1 pumps. The tank provides surge volume and net positive suction head (NPSH) to the pumps.
4
- WAPWR-WM 11.2-16 AUGUS1, 1985 l 3236e
- 1d l
/
Only water which can be directed to the boron recycle holdup tanks enters the RCDT. The water must be compatible with reactor coolant and must not contain dissolved air or nitrogen.
A constant level is maintained in the tank to minimize the amount of Os gas sent to the GWPS and also to minimize the amount of hydrogen cover gas required. The level is maintained by one continuously running pump and by a control valve in the discharge line. This valve operates on a signal from a level controller to limit the flow out of the system. The remainder of the flow is recirculated to the tank.
Continuous flow is maintained through the heat exchanger in order to prevent loss of pump NPSH resulting f rom a sudden inflow of hot liquid into the RCDT.
B. Waste Holdup Tank One atmospheric pressure tank is provided to collect:
- 1. Equipment drains.
- 2. Valve and pump seal leakoffs (o,utside the containment).
- 3. Boron recycle holdup tank overflows.
- 4. Other water f rom tritiated, aerated sources.
O I 1
The tank size is . adequate to accommodate approximately 35 days of expected influent during normal operation.
O C. Waste Evaporator Condensate Tank One- tank with a diaphragm to exclude air is provided to collect condensate from the waste evaporator. The tank has sufficient O capacity to allow a 25-gal / min evaporator to operate without interruption for a 3-hr period.
WAPWR-WM 11.2-17 AUGUST, 1985 3236e:ld
D. Chemical Drain Tank One tank is provided to collect chemically contaminated, tritiated water f rom the laboratories. This tank has sufficient capacity to accept more than a month's laboratory waste during normal opefat. ion.
E. Spent Resin Storage Tank-I The purpose of the spent resin storage tank is to provide a collection point for spent resin and to allow for decay of short-lived
- radionuclides before disposal. The tank also serves as a head tank for the spent resin sluice pump.
One vertical, cylindrical tank with suf ficient capacity to handle the spent resin storage needs is provided. A vertical, cylindrical tank is used because the symmetrical bottom facilitates the removal of i resin. The tank is designed so that sufficient pressure can be applied in the gas space of the tank to move the resin slurry to the solid waste processing system.
The spent resin storage tank and associated equipment which can contain radioactive material are shielded to limit the dose to
- personnel.
The level indicating system in the spent resin storage tank shows only total level and not the amount of resin and water separately.
O However, since the resin volumes flushed f rom demineralizers and the resin volumes transferred to the solid waste processing system are known, the resin volume in the tank is also known.
F. I.aundry and Hot Shower Tank This atmospheric pressure tank is provided to collect laundry and hot shower drains. The tank size is sufficient to furnish a 20-day capacity during normal operation and a 2-day capacity during refueling.
WAPWR-WM 11.2-18 AUGUS1, 1985 j 3236e:ld
.=. _ - - - . _ _ - - _ _ - . _ - - . - - __ - _ . ,
{ G. Floor Drain Tank This atmospheric pressure tank is used to collect floor drains f rom the controlled areas of the primary system. The tank provides sufficient surge capacity for the floor drains within the collection area and, in connection with the waste holdup tank, provides surge capacity for abnonnal primary system leaks. The tank size is adequate to accommodate almost 5 days of expected influent during normal operation or 2 days of expected influent during sh' utdown operation.
H. Waste Monitor Tanks ,
Two atmospheric pressure waste monitor tanks are provided to monitor liquid discharged f rcn the plant site. Each tank is sized to hold a f
volume large enough that sampling requirements are minimized, thereby minimizing laboratory effluent.
]
I. Waste Evaporator Reagent Tank ,
i This tank is provided to make it poss4le to add chemicals to the evaporator for cleaning the waste evapo% tor tubes and for similar activities, 11.2.2.6.3 Reactor Coolar.t Drain Tank Heat Exchanger i
This heat exchanger is located in the discharge line of the RCDT pumps and is O in constant service as part of the RCDT recirculation path. Continuous component cooling water flow is maintained to the heat exchanger to accomodate, without operator action, sudden flow of hot liquid to the RCDT.
The heat exchanger can also be used to cool the contents of the pressurizer
! relief tank in the RCS.
i i
1 O
l WAPWR-WM 11.2-19 AUGUST, 1985 3236e:ld l
The heat exchanger is sized for several modes of operation: ,
3 A. It can maintain the RCDT liquid below 170*F, assuming a 10-gal / min input of 600*F reactor coolant.
O B. It can cool the contents of the pressurizer relief tank from 200*F to 120*F in less than 8 hr.
I i
C. It can maintain the contents of the RCDT at less than 170*F, assuming i
a 25-gal / min input f rom the excess letdown heat exchanger (chemical and volume control system). ,
11.2.2.6.4 Demineralizers j
i As part of a program of pressurized water reactor operating plant followup,
} Westinghouse has obtained operational data on demineralizer decontamination j factors for selected isotopes. The measured range of decontamination factors f for these isotopes is given in Table 11.2-3.
! These values were observed across mixed bed demineralizers containing cation i
resin in the lithium-7 form and anion resin in the borated form.
i i
In considering the waste evaporator condensate demineralizer and the waste monitor tank demineralizer, it can be assumed that greater decontamination ;
i factors would be realized because the resin in both demineralizers is in the hydrogen-hydroxyl form. The minimum values in Table 11.2-3 were generally
, O observed just before resin flushing and recharging; during the operating life of the demineralizer, decontamination factors were consistently closer to the L
- maximum values.
t Although spec 1;ic operating decontamination factors were not measured for other isotopes, their behavior in a mixed bed demineralizer may be inferred from this data.
i O WAPWR-WM 11.2-20 AUGUSl, 1985 3236e:1d
)
a ~
The process decontamination factor used for the demineralizers in the analysis of system performance is taken from Reference 1. These decontamination factors are given in Table 11.2-2.
A. Waste Evaporator Condensate Demineralizer i One mixed bed demineralizer is provided to remove trace ionic i
contaminants from the waste evaporator condensate stream that is to be-recycled. Resin in the hydrogen-hydroxyl form is utilized in this demineralizer. The use of this demineralizer is optional, depending on the activity levels observed in the output from the waste t evaporator.
B. Waste Monitor Tank Demineralizer .
1 One mixed bed demineralizer is provided upstream of the waste monitor tanks to remove, if desired, trace ionic contaminants f rom waste evaporator condensates that are to be discharged. The demineralizer may also be used to clean up the monitor tank contents or floor drain I
tank contents without having the flow first go through the waste i
evaporator. The laundry and hot shower tank contents can also be f processed through the demineralizer if such processing is necessary.
Resin in the hydrogen-hydroxyl form is used in this demineralizer. '
11.2.2.6.5 Filters The following filters are provided in the LWPS:
o Waste evaporator feed filter.
o Laundry and hot shower tank filter.
I v o Floor drain tank filter.
o Spent resin sluice filter.
l o Waste ev aporator condensate filter.
! o Waste monitor tank filter.
J l
l WAPWR-WM 11.2-21 AUGUST, 1985 3236e:ld :
i
l l
l
!' 11.2.2.6.6 Strainers Basket-type strainers of mesh construction are provided to prevent clogging of filters and lines downstream because of large particles being sluiced through the lines during liquid transfer operations.
The following strainers are prov'ide'd in the LWPS:
o laundry and hot shower tank strainer.
o Floor drain tank strainer.
I 11.2.2.6.7 Waste Evaporator i
One forced circulation type waste evaporator is provided. Evaporator distillate is either recycled, reprocessed, or discharged, depending on its chemistry and activity and other plant operating factors. Evaporator bottoms ll are discharged to the solid waste management system.
O The process decontamination factors used for the waste evaporator in the analysis of system performance are taken from Reference 1 and are listed in Table 11.2-2.
11.2.2.7 Instrumentation Design The system instrumentation is shown on the LWPS piping and instrumentation f diagram (Figure 11.2-1).
T Instrumentation readout is located mainly on the waste processing system panel I l in the auxiliary building. Some instruments are read where the equipment is i located.
All alarms are shown separately on the waste processing system panel and are l
further relayed to one common waste processing system annunciator on the main control board in the control room.
j WAPWR-WM 11.2-22 AUGUS1, 1985
-3236e:ld
) All pumps are protected against loss of suction pressure by a control setpoint j
on the level instrumentation for the respective vessels feeding the pumps. In addition, the RCDT pumps and the spent resin sluice pump are interlocked with
! flowrate instrumentation to stop the pumps when the delivery flows reach
{
minimum setpoints.
I ,
)i Pressure indicators are provided to give local indication of pressure drops
! across demineralizers, filters, and strainers.
lO
}
All releases to the' environment are monitored for radioactivity. This instrumentation is described in Section 11.5 of this module.
i Each tank is provided with level indication instrumentation that actuates an ,
alarm on high liquid level in the tank, thus warning of potential tank overflow.
! L
? 11.2.2.8 Operating Procedures i
l O The LWPS is manually operated except for some functions of the RCDT circuit.
l The system includes adequate control equipment to protect components and adequate instrumentation and alarm functions to provide operator information
) to ensure proper system operation.
i Operation of the LWPS is essentially the same during all phases of normal and
} defined off-normal reactor plant operation; the only differences are in the a
! load on the system. The term " normal operation", as used here, means all
- phases of plant operation except operation under emergency or accident conditions. The LWPS is not regarded as an engineered safety features system.
i .
i 11.2.2.8.1 Reactor Coolant Drain Tank Subsystem Recirculation !
l l
- A. Reactor Coolant Drain Tank Recirculation i
Reactor coolant is continuously circulated through the RCDT heat
{
j exchanger to maintain $170'F in the event of a hot reactor coolant l
l WAPWR-WM 11.2-23 AUGUST, 1985 l 3236e:1d
I j
leak to the RCDT. Level is maintained by a control valve which automatically opens a path from the recirculation line to the recycle holdup tanks. Normal operation of this mode is automatic and requires no operator action. The system can be put into the manual mode, if desired.
Leakage into the RCDT can be estimated by putting the system in the manual mode, stopping the pump, and monitoring the level change.
A venting system is provided to prevent wide pressure variations in 4
the RCDT. A hydrogen blanket is automatically maintained between 2 and 6 psig. Hydrogen is supplied f rom bottles which must be replaced when the pressure drops to ~100 psig. During all other operations, the recirculation mode is stopped and the RCDT is isolated.
B. Pressurizer Relief Tank Cooling The pressurizer relief tank may be cooled by a feed-and-bleed method, by spraying cold makeup water and pumping the water to the recycle holdup tanks with an RCDT pump through the RCDT heat exchanger. This is a rapid cooldown and can be used even if the hcat cxchanger is out of service. However, to mirfbize the addition of water to the system when a rapid cooldown is not necessary, the pressurizer relief tank l
may be cooled f rom 200*F to 120*F in less than 8 hrs. by using the RCDT heat exchanger and one pump in a recirculation mode without adding water.
C. Loop Draining Four RCS loops may be drained simultaneously to the midpoint of the
]
.' reactor vessel nozzles in less than 8 hr when both RCDT pumps are running. The loops are vented to atmospheric pressure, then spool pieces are connected to the pumps' suction. The water is sent to the recycle holdup tanks in the BRS. Since the RCDT heat exchanger is no, O needed for cooling, it may be bypassed or used in parallel with the bypass.
WAPWR-WM 11.2-24 AUGUST, 1985 3236e:ld i
r
- w. .,< .
1 A .,
- s. -\p .
e O
D. Refueling Canal Draining and Uleanup N
. Refueling canal water is transf errea', using the RCD 1 pumps. .- to' the
, 's refueling water storage tank (draining), to the canal via, the spent m'y fuel pool cooling system (cleanup), or to the waste holdup ' tank (disposal). Since the RCDT heat exchangermis noi needed for cooling, s it may be bypassed or used in parallel with the bypass.
E. Accemulator Draining s
i This mode is available for accumulator maintenance. After the accumulator is vented to atmospheric pressure, the spool piece is connected to the RCDT pump suction for transfer of accumulator water to the wa,te holdup tank.
F. Excess Letdown Header O During normal plant heatup operations, excess letdown to the RCDT will permit faster heatup rate. Excess letdown flow is directed f rom the RCDT to the recycle holdup tanks.
11.2.2.8.2 Drain Channel A Subsystem Operation Water ii accumulated in the waste holdup tank until sufficient quantity exists to warrant an evaporator startup. The water volume for an evaporator startup is approximately 30.to 40 percent of tank capacity, which leaves the remainder as surge capacity available for abnormal situations. The waste evaporator feed pump is started and samples are taken from the miniflow line.
If it is not desired to recycle . the water in the waste holdup tank and analysis indicates that decontamination by the waste evaporator is not
~necessary, the water may be sent to the floor drain tank for eventual discharge.
m, WAPWR-WM. 11.2-25 AUGUS1, 1985 3236e:ld
The waste holdup tank contents are processed by the waste evaporator.
Evaporator feed is concentrated to 12-weight percent boric acid, 20-weight percent solids, or 40. pCi/cm3 , whichever is achieved first. Concentrates are discharged to the solid waste processing system for solidification.
Gases stripped from the water by the evaporator are released to the plant vent.
Af ter evaporation, the distillate in the waste evaporator condensate tank is checked for boron and activity concentration; if the analysis shows compati-bility with reactor makeup grade water, it may be transferred directly to the RMWST. If the distillate is high -in boron concentration or activity, it may be recirculated through the waste evaporator condensate demineralizer before being transferred to the RMWST. If reevaporation is required, the distillate can be transferred back to the waste holdup tank or to the boron recycle holdup tanks for processing by the boron recycle evaporator. If an overload forces some discharge, distillate may be directed to a waste monitor tank.
11.2.2.8.3 Drain Channel B Subsystem Operation Drain channel B of the LWPS consists of the laundry and hot shower system, the floor drain tank system, and the chemical drain tank system.
Laundry and hot shower water enters the laundry and hot shower tank for holdup; it is sampled, filtered, and transferred to the monitor tank for discharge. This water is not processed by the waste evaporator because of the resultant soap fouling. If demineralization is required, the resin must be s replaced with clean resin thereafter.
The floor drain tank contents are recirculated, and then samples are taken and analyzed. If the floor drain tank is overloaded or the water .is recyclable, the water can be transferred to the waste holdup tank. If' evaporation is necessary, the distillate is returned to a waste monitor tank directly or via the waste monitor tank demineralizer and filter. To prolong resin life, the O demineralizer is normally used only after evaporation and if distillate V sampling demands it. The evaporator concentrate is recycled or sent to the drumming station as determined by sample analysis.
WAPWR-WM 11.2-26 AUGUST, 1985 3236e:1d
L
\
One waste monitor tank is used only for floor drain tank contents and one for laundry water. This ensures segregated reprocessing methods. Before being discharged, .w ater. in the waste monitor tank is again sampled; it can be recirculated through the waste monitor tank demineralizer or returned to the floor drain . tank for processing by the evaporator if further processing is required. Normally, sampling will ~ indicate that waste monitor tank contents can be discharged into the plant discharge pipe. The' rate of discharge flow is determined by the effluent activity concentration and .the dilution flowrate. It is discharged into the cooling water system at a rate so as not to exceeded a small f raction of maximum permissible concentration for liquid releases.
Water leaving this system to the discharge canal is monitored for radiation.
This radiation monitor is described in Section 11.5 of this module. If the radiation monitor closes the discharge valve, it must be cleared before the valve can be reopened. The monitor element can be cleared by flushing it with demineralized water f rom the temporary connection- back to the waste monitor O tank. During refueling, the load on this portion of the LWPS is increased, but there is no change in operation.
Spent samples with high chemical concentrations are held ~up in the chemical drain tank, then sampled. The contents are transferred to -the solid waste processing system for solidification.
11.2.2.8.4 Spent Resin Handling Subsystem O A. Resin Fluffing The demineralizer .is valved out of service, and the flow path is aligned from the spent resin sluice pump through the process line of the demineralizer, through the .lohnson ' screen at the top of the demineralizer and back to the spent resin storage tank. The resin bed is backflushed for about 10 min. to loosen it for sluiting. This operation may also be used to recover pressure drop caused by bed WAPWR-WM 11.2-27 AUGUST, 1985 3236e:1d
i 1
l fouling by backwashing particulates from the top layer of the resin into the spent resin storage tank. Such a recovery is useful when the resin is not ionica11y depleted.
B. Resin Sluicing i
The sluice pump is shut off after fluffing. The valves in the backflush circuit are closed, the sluice line to the bed screen is opened, and the sluice pump is started. The resin flows to the spent 1 resin storage tank, initially at a slow rate; it continues for about 10 min. ~until sluicing is completed. Finally, the pump is stopped, and the sluice inlet and outlet valves are closed. If the pump i suction line screen in the tank becomes resin plugged at any time, it j can be cleared with a blast of nitrogen.
When resin activity in a demineralizer is low, the spent resin can be sluiced to a bulk disposal unit for low-level or nonradioactive waste O. instead of to the spent resin storage tank. Reactor makeup water is added to the spent resin storage tank to replace any sluice water lost to the bulk disposal facility.
l Resin Fill C.
Af ter sluicing is completed, f resh resin must be added. The path to the drain header from the demineralizer is opened to allow overflow.
The resin fill line is opened and resin added. Af ter f resh resin is added, the fill line valve is closed and the flow path is realigned for normal demineralizer operation.
D. Resin Disposal The resin in the spent resin storage tank is loosened before disposal by sending pressurized nitrogen or sluice water through the six sparging nozzles in the tank. The valves in the resin transfer line Ov are opened to direct the spent resin to the solid waste processing
. system.
WAPWR-WM 11.2-28 AUGUST, 1985 3236e:ld
O h The tank is then pressurized with nitrogen to force the resin up through the resin transfer line to the disposal area. A single nozzle in the spent resin storage tank is provided to allow local fluidiza-tion with sluice water at the opening of the discharge pipe. During resin transfer, this nozzle is used to ease the flow of the resin slurry. Af ter resin transfer is complete, the tank is vented to the plant vent and returned to atmospheric pressure. The resin transfer line is then backflushed to the spent resin storage tank to clear it of resin.
Since a certain amount .of resin remains in tl.e tank af ter a disposal operation, it may hinder the backflush operation. Therefore, the fluidizing nozzle is again used to facilitate the backwash operation.
11.2.3 Radioactive Releases 11.2.3.1 Criteria for Discharge, Recycle, or Further Treatment of Liquid Waste Processed liquids are recycled for reuse within the plant whenever possible, provided that the following criteria are satisfied:
o The plant water inventory requires makeup, o The water to be reused satisfies system water quality requirements, o Tritium buildup is less than plant operating limits.
Processed liquids are discharged under the following conditions:
o The processed water does not satisfy plant operating requirements for water quality and tritium buildup.
o The ef fluent concentrations are within the ' limits specified by 10 CFR 20, Appendix B, Table II, column 2.
!!APWR-WM 11.2-29 AUGUS1, 1985 3236e:ld
o The discharge does not cause the limits of 10 CFR 50, Append'ix 1, to be exceeded.
Processed liquids are recycled within their respective treatment systems for-additional processing when system wa'ter quality requirements are not satisfied and reuse within the plant is desirable, or when discharge of the processed liquid is planned but the discharge would result in exceeding either the concentration limits of 10 CFR 20, Appendix B, Table II, column 2, or the
, limits of 10 CFP. 50, Appendix I.
11.2.3.2 Estimated Releases 1
The equipment utilized during liquid waste processing is at the discretion of the operator; therefore, the calculated releases conservatively do not address
, all possible treatment processes but only the expected process. Liquid releases are calculated using the PWR-GALE computer code UI and parameters listed in Table 11.2-4, which are discussed in nere detail below. Releases d calculated assuming operation with expected levels of fuel cladding defects of j 0.12 percent are presented in Table 11.2-5. Primary and secondary coolant i activity levels are given in Section 11.1 for the realistic case. In agreement with Reference 1, the total releases include an adjustment f actor of 0.15 C1/ year, using the same isotopic distribution as the calculated release, to account for anticipated operational occurrences.
4 i Table 11.2-5 lists the calculated annual release f rom each of the process paths discussed below as well as the total annual release. Based on the annual average releases given in Table 11.2-5, the discharge of liquid wastes
! would require a dilution flow of greater than 40 gpm to achieve annual average i ef fluent concentrations within the limits of 10 CFR 20 Appendix B, Table II, column 2. While the actual dilution flow is site dependent, it would be many times greater than the 40 gpm required to meet concentration limits. ,
1 A survey has been performed of liquid discharges f rom dif ferent Westinghouse pressurized water reactor plants, with results presented in Table 11.2-6. The I
WAPWR-WM 11.2-30 AUGUS1, 1985 3236e:1d
(a data includes radionuclides released on an unidentified basis and are all within the permissible concentration for release of liquid containing an unidentified radionuclide mixture. The data' in Table 11.2-6 clearly indicate that actual releases are highly dependent upon the actual operation of the plant and can vary significantly f rom year to year for a given plant as well as from plant to plant.
i 11.2.3.2.1 Baron Recycle System (BRS) b d Primary coolant is withdrawn from the reactor coolant system (RCS) and processed through the chemical and volume control system (CVCS). A portion of the letdown stream is assumed to be diverted to the BRS as shim bleed. The shim bleed is combined with other reactor grade wastes that are collected by the reactor coolant drain tank (equipment drain wastes).
The combined shim bleed and equipment drain waste streams are processed through one of the recycle evaporator feed demineralizers and routed to one of the recycle holdup tanks. The contents of the recycle holdup tank are then processed through the recycle evaporator and recycle evaporator condensate demineralizer. The condensate is either pumped to the reactor nakeup water storage tank for reuse in the plant or to a waste monitor tank for monitoring and discharge. The BRS has sufficient capacity to allow total reuse of the combined shim bleed and equipment drain wastes. However, in the release calculations, a discharge f raction of 0.214 is used because up to one and half RCS volumes of treated primary coolant per year may be discharged for tritium control.
v Figure 11.2-2, sheets 1 & 2, shows a process flow diagram of this path, 11.2.3.2.2 Liquid Waste Processing System (LWPS)
A. Clean Wastes (Drain Channel A - Miscellaneous Wastes)
O Clean wastes are collected in the waste holdup tank for eventual V processing by the waste evaporator. The evaporator condensate is
(
WAPWR-WM 11.2-31 AUGUST, 1985 j 3236c:ld
E pumped to the waste evaporator condensate tank if the water is to be reused or to a waste monitor tank if the water is to be discharged.
Based on sample analysis, the water in the monitor tank would either be discharged or processed further by recirculation through the waste ,
monitor tank demineralizer until sample analysis indicated that it was acceptable for discharge. The LWPS has suf ficient capacity to allow total reuse of the processed clean wastes. However, in the release calculations, a discharge f raction of 1.0 is used since reuse of this water is not expected.
Figure 11.2-2, sheet 3, shows a process flow diagram of this path.
B. Dirty Wastes (Drain Channel B - Miscellaneous Wastes)
Dirty wastes are collected in the floor drain tank. A sample is analyzed to determine whether the water can be discharged without processing, if cleanup is required, the liquid is processed either by O the waste monitor tank demineralizer while it is pumped to the waste monitor tank, or by the waste evaporator with the condensate directed to the waste monitor tank. The processing method used is determined based on the amount of cleanup required. Based on sample analysis, the monitor tank contents are either discharged or processed further by recirculation through the monitor tank demineralizer until sample analysis indicates that the water is acceptable for discharge. Since all of the dirty wastes are normally discharged, a discharge fraction of 1.0 is used in the release calculations.
Figure 11.2-2, sheet 4, shows a process flow diagram of this flow path.
C. Detergent Wastes (Laundry and Hot Shower Tank)
Detergent wastes are normally released without treatment. The releases through this path are assumed to be the same as listed in Reference 1 Table 2-20. ,
WAPWR-WM 11.2-32 AUGUS1, 1985 ,
3236c:1d
Figure-11.2-2, sheet 5, shows a process flow diagram of this flow path.
j 11.2.3.2.3 Steam Generator Blowdown Processing System (SGBPS)
The SGBPS is not part of the nuclear power block. However, operation of a typical Westinghouse design SGBPS is assumed in order to estimate secondary side source terms and releases. Blowdown from the steam generators is I
normally processed by the two steam generator blowdown demineralizers (in series) and recycled back to the main condenser. If discharge of blowdown is desired, the demineralizers can be bypassed, however, in the event of a primary to secondary side leak, the demineraliters would be in use. For the release calculation, a 100 lb/ day primary to secondary side leakage is I
assumed. Also, a total blowdown rate of 54,000 lb/hr is assumed with 10 percent of the flow being discharged. This blowdown rate is 30 percent of system capacity, which is the expected average blowdown flow.
]
No credit is taken for radioactive decay of the isotopes in the blowdown stream since the SGBPS design utilizes a through-flow process with no significant decay. ,
[
Figure 11.2-2, sheet 6, shows a process flow diagram of this flow path.
] 11.2.3.2.4 Condensate Cleanup System i ;
j
- The condensate cleanup system is not part of the nuclear power block. For the purpose of estimating secondary side source terms and releases, it is assumed
! that the characteristics of this system are identical to those used in the sample GALE run included in Reference 1.
'T 11.2.3.2.5 Turbine Building Floor Drains 1 The processing of turbine building drains is not in the scope of the nuclear power block. The drain water volume, activity level, and decontamination l factors are assumed within the body of the GALE code (Reference 1). ;
1 hfAPWR-WM 11.2-33 AUGUS1, 1985 3236c:ld i
_ - _ _ _ = _ = _ _ = -
REFERENCES
-1. U.S. Nuclear Regulatory Commission, " Calculation of Releases from Pressurized Water Reactors," PWR-GALE Computer Code, NUREG-0017 April-O 1976. l O
i f
i O
i e
l 9 i O ,
WAPWR-WM 11.2-34 AUGUST, 1985 3236e:1d ;
I
4
\ 5 i
I 5
TAGLE 11.2-1 (SNEET 10F 3) l PARANETERS USED IN THE CALCULAil0N OF ESTINATES ACTIVITY IN LIOUIB WASTES
. Collection Tack Espected
- and Seerces Inset RatesI *I Activitv(b) gg,,,sg 9,n
- 1. Seector coolant 300 gel /dey 1.0 m (RCS) RC peup No. 2 seel leakeff Strected to BR$ recycle holde, '
drain tank tritium; of 0.05 gal /trin per peup tanks for recycle j
i 0.1 m (RCS)
~
other nec11 des l -
! Recycled to reacter makeup water 1 2. Weste holder tank 160 get/ day 0.423 m (RCS) storage tank after processing i i I
O. Egetyment drat.s 110 gel / day 0.55 m (RCS) ANSI /ANS-55.6-1979
}
- b. Samele room drains 50 gal / day 0.143 x (RCS) (d)
] '
2620 gal / day (normal) 0.029 m (RCS) Discharged to environment !
j 3. Fleer drals tank
! after samp11pg
- t 570 gel / day 0.01 m (RCS) ANSI /ANS-55.6-1979
- c. Aeu111ary be11 ding 3 sump ICI i
i
- b. Containment sgI *I AN51/ANS-55.6-1979
' 570 gal / day 0.106 m (RCS) i l c. tat egetament rinse 140 gal / day C.M u (RCS) (d) water l l ,
11.2-35 AUGUST. 1985 i
{ unswe-6st !
j 3236e:1d
o
~
O O O O O O TA8tt 11.2-1 (SNEET 2 0F 3)
Cs11ection Tank Espected Activitv(b) te_111 Dissositten and Seerces _ Intet Rates (a) 40 gel / day (neenst) 0.01 m (DCS) AN51/ANS-55.6-1979
- d. Area decontaminetten 3000 gel / day (shetdown) 0.01 m (RCS) 700 gel / day 0.001 m (ats) ANSI /ANS-55.6-1979
- o. Spent feel pool liner teakage (d) Transferred to se11d weste 10 gal / day 0.148 m (DCS)
- 4. Cheetcal drain tant processing system.
Discharged to environment after 530 gel / day (porael) (e)
- 5. Laundry and het showr tank sagling 3900 gel / day (shetesun) (e)
(e) AN51/ANS-55.6-1979
- c. Laundry weste 300 gel / day (neenst) 2000 gel / day (shetdown) (e) ANSI /ANS-55.6-1979 meglitible (perus1) (e) ANSI /ANS-55.6-1979
- h. leet shoser weste (e) ANSI /ANS-55.6-1979 400 gel / day (shetdown)
(e) AW51/ANS-55.6-1979
- c. need washes 200 set / day (perust)
(e) ANSI /ANS-55.6-1979 1500 gel / day (shutdown) 1.5 BCS volumes purged per Bischerged to environment after Deren recycle systee 600 gel / day (f) 6.
year for tritium centrol. samp11ng AUGUST, 1995 11.2-36 WAPWR-tet 3236e:Id
TA0tt 11.2-1 ($NEET 3 0F 3) i O. These rates de not represent system capacity, i ity as given in Section 11.1 unless stated b.
Activity of the 11 geld westes entering the LWPS is given in terms of a fractlen of primary coolant act v otherwise.
- c. Eac*a sono soy be directed to ettner the weste heldup er fleer drain tent, depending upon water gestity.
Reacter Systems Samo1 1mg. The total rate is
- d. Espected 1ppet rates are based on a total rate of 200 gal / day in accordence with ANSI /AN5-55.6-1979, ,
dielded among sample room drains. lab rinse water, and cheetcally contaminated sesele:.
9.
Laundry and het shouer weste activity is taken from NUREG-0017. April 1916.
The activity of the water is primary coolant f.
The 500 gel /dey coming free the beren recycle systee is a fraction of the 11 geld processed by that system.
activity in accordance with Section 11.1 but redeced by the processtag performed by the beren recycle system.
AUGUST, 1995 11.2-37 W M WE-488 sz3se:14
1ABLE 11.2-2 (SHEET 1 0F 10) l 1 .
j EQUIPMENT DESIGN PARAMETERS j Pumps RCOT Pumps j Number 2 l Type Horizontal, centrifugal f Design pressure (psig) 150 l Design temperature (*F) 200 l Design flow (gal / min) 100/150(*)
Design head (ft) 260/250(*)
Material Stainless steel (55) I l
c Waste evaporator feed pump j Number 1 l Type Horizontal, centrifugal !
j Design pressure (psig) 150 l l Design temperature (*F) 200 l l' Design flow (gal / min) 35/100(a) ,
Oesign head (ft) 250/200(a) {
Material SS Waste evaporator condensate pump ;
! Number 1 Type Horizontal, centrifugal j 8
Design pressure (psig) 150 i j
Design temperature (*F) 200 l Design flow (gal / min) 35/100(a) {
{ Design head (ft) 250/200(a) l
! Material
- SS !
j l l !
lO i
i WAPWR-WM 11,2-38 AUGUS1, 1985 ;
3236eild !
, g t
l
] TABLE 11.2-2 (SHEE1 2 0F 10) t 1 Chemical drain tank pump (
Number 1 I Type Horizontal, centrifugal Design pressure (psig) 150 :
- Design temperature (*F) 200 35/100(a) j I Design flow (gal / min) !
Design head (ft) 250/200(a) j Material SS Spent resin sluice pump ;
i Number 1 Type Horizontal, centrifugal i I
Design pressure (psig) 150
- Design temperature (*F) 200 i l Design flow (gal / min) 100/150(a) {
l Design head (ft) 260/250(a) i
! Material 55 i
Laundry and hot shower tank pump i j Number 1 l
! Type Horizontal, Centrifugal l 3
Design pressure (psig) 150 (
l Design temperature (*F) 200 !
Design flow (gal / min) 35/100(a) l O Design head (ft) 250/200(a) ;
Material $$ j i
!O l
1 i !
l WAPWR-WM 11.2-39 AUGUS1, 1985 f
, 3236e:Id
TABLE 11.2-2 (SHEET 3 0F 10)
' Floor drain tank pump Number 1 Type Horizontal, centrifugal Design pressure (psig) 150 Design temperature (*F) 200 O Design flow (gal / min)
Design head (ft) 35/100(a) 250/200(a)
Material SS i Waste monitor tank pumps Number 2 Type Horizontal, centrifugal Design pressure (psig) 150 Design temperature (*F) 200 O Design flow (gal / min) 35/100(a)
Design head (ft) 250/200(*)
Material SS i i
Filters Waste evaporator feed filter Number 1 Disposable cartridge O Type Design pressure (psig) 300 Design temperature (*F) 250 Design flow (gal / min) 250 Ap at design flow (psi) 5 Size of particles, 98% re- 100 tention (um) (nominal)
Materials SS O
WAPWR-WM 11,2-40 AUGUS1, 1985 3236e:1d
s TA8LE 11.2-2 (SHEET 4 0F 10) l Waste evaporator condensate filter Number 1 Type Disposable cartridge Design pressure (psig) 200 Design temperature (*F) 250 Design flow (gal / min) 35 Ap at design flow (psi) 5 ,
Size of particles, 98% re- 25 I tention (pm) (nominal)
Material SS Spent resin sluice filter Number 1 Type Disposable cartridge O Design pressure (psig) 300 Design temperature (*F) 250 Design flow (gal / min) 250 Ap at design flow (psi) (unfouled) 5 Size of particles, 98% re- 25 tention (um) (nominal)
Material SS O Laundry and hot shower tank filter Number 1 Type Disposable cartridge Design pressure (psig) 200 Design temperature (*F) 250 Design flow (gal / min) 35 6p at design flow (psi) (unfouled) 5 Size of particles, 98% re- 25 O tention (um) (nominal)
Material SS WAPWR-WM 11.2-41 AUGUS1, 1985 3236e:ld
3 l 1
$ 8 TABLE 11.2-2 (SHEET 5 0F 10)
Floor drain tank filter Number 1
}
l Type Disposable cartridge 1 Design pressure (psig). 300 l Design temperature (*F) 250 Design flow (gal / min) 250
- op at design flow (psi) (unfouled) 5 1 Size of particles, 98% re- 100 tention (um) (nominal) j Material SS , l' l
l Waste monitor tank filter Number 1 f Type Disposable cartridge :
Design pressure (psig) 200 I Design temperature (*F) 250
[ Design flow (gal / min) 35 op at design flow (psi) (unfouled) 5 j Size of particles, 98% re- 25 j tention (um) (nominal)
Material SS l
Strainers j Laundry and hot shower tank strainer i Number 1 Type Basket l Design pressure (psig) 150 ,
Design temperatura (*F) 200 '
Design flow (gal / min) 35
]
i Ap at design flow (psi) Negligible
? Strainer mesh number 40 Material SS +
! WAPWR-WM 11.2-42 AUGUS1, 1985 3236e:ld i u . ~_ , _._ .. _ _ _ _ . _ _ _ . . _ , _ _ . . __ _ _ . . _ . _ _ _ _ . _ _ _ _ _ _ . _ . . . . , _ . . _ _
i t
1 TABLE 11.2-2 (SHEE1 6 0F 10) ;
l Floor drain tank strainer Number 1 Type Basket Design pressure (psig) 150 Design temperature (*F) 200
. Design flow (gal / min) 35
} 8p at design flow (psi) Negligible f Strainer mesh number 40 Material SS i'
Evaporator Waste evaporator Number 1 Type Forced circulation j Design flow (gal / min) 25 j Feed concentration (ppm' boron) 10-2,500 I Bottoms concentration (ppm boron) 7000-21,000 Process decontamination 1000 for iodine; 10,000 f or factors ID) cesium and all other nuclides Heat Exchanger 1
j RCDT heat exchanger Number I
- Type U-tube i Estimated UA (Btu /hr/'F) 70,000 Shell Side Tube Side Design pressure (psig) 150 240 j Design temperature (*F) 250 200 i Design flow (1b/hr) 112,000 44,600 Temperature inlet (*F) 105 180 1 Temperature outlet (*F) 125 130 i
! WAPWR-WM 11.2-43 AUGUST, 1985 i RERidl61
a 1
I ~ .
TABLE 11.2-2 (SHEET 7 0F 10) 1
. Demineralizers i
i O Waste evaporator condensate demineralizer Number 1 Type Flushable l Design pressure (psig) 300 Design temperature (*F) 250 l
Design flow (gal / min) 120 1
Resin v.olume (ft ) 30 Material SS Resin type IRN-150(c)
!- Process decontamination factors IDI 10 for iodine; 10 for cesium; 10 for all other nuclides( l l
Waste monitor tank demineralizer
! Number 1 i Type Flushable
- i j Design pressure (psig) 300
! Design temperature (*F) 250 i f t
! Design flow (gal / min) 120 Resin volume (ft ) 30 -
Material SS i l Resin type IRN-150 ICI Process decontamination factors (b) 100 for iodine; 2 for cesium; 100 for all other nuclides j
!O ,
!O i
l l
~
WAPWR-WM 11.2-44 AUGUST, 1985 L 3236e:1d
TABLE 11.2-2 (SHEET 8 0F 10)
Tanks Reactor Coolant Drain Tank Number 1 Usable volume (gal) 350 Type Horizontal Internal design pressure (psig) 100 External design pressure (psig) 60 Design temperature (*F) 250 Material SS Waste holdup tank Number 1 Usable volume (gal) 10,000 O Type Vertical Design pressure (psig) Atmospheric Design temperature (*F) 200 Material SS Waste evaporator condensate tank Number 1 Usable volume (gal) 5000 Type Vertical with diaphragm Design pressure (psig) Atmospheric Design temperature (*F) 200 Material SS O
O WAPWR-WM 11.2-45 AUGUS1, 1985 3236e:1d
- I I
i 's 1
TABLE 11.2-2 (SHEET 9 0F 10) ;
I l
Chemical drain tank Number 1
{ Usable volume (gal) 600 Type Vertical I Design pressure (psig) Atmospheric Design temperature (*F) 200 l 3 Material SS I i
! Spent resin storage tank !
! Number 1 Resin / total volume (ft ) 250/550 l a .
l Type Vertical !
Design pressure (psig) 150 l Design temperature (*F) 200 O
i Material SS !
1 i laundry and hot shower tank [
Number 1 i j Usable volume (gal) 10,000 Type Vertical ;
i Design pressure (psig) Atmospheric
! Design temperature (*F) 200 !
4 Material SS 1
1 Floor drain tank l j Number 1 Usable volume (gal) 10,000 !
f
! lype Vertical i Design pressure (psig) Atmospheric !
Design temperature (*F) 200 i Material SS l
l
! FPWR-WM 11.2-46 AUGUST, 1985 l- 3236e:Id i
, -- _. _ ._ _ __._. _ _ _. __ ._--._. _.~. _ _ . _ . - . _ _ _ . . _ _ _ , _ _ _ _ . _ _
1 4
TABLE 11.2-2 (SHEET 10 0F 10) i .
Waste monitor tank Number 2 1
Usable volume (gal) 5000 j Type Vertical
! Design pressure (psig) Atmospheric Design temperature (*F) 200 i Material SS i
(
l Waste evaporator reagent tank Number 1 ,
Usable volume (gal) 5 Type Vertical l
Design pressure (psig) 150
! Design temperature (*F) 200
{ Material SS i
2 i I
l a. Denotes two design conditions. :
9
) b. Decontamination factors are taken from ' Calculation of Releases of !
{ Radioactive Materials in Gaseous and Liquid Ef fluents f rom Pressurized l j Water Reactors (PWR-GALE Code)." Of fice of Standards Development, U.S.
j Nuclear Regulatory Commission NUREG-0017. April 1976. i l c. Rohm and Haas Amber 11te or equivalent (H+ OH- form). i
- d. The process decontamination factor is 10 for iodine, cesium, and all other i nuclides when used as a second demineralizer in a series. !
i l i
!O l
i l WAPWR-WM 11.2-47 AUGUS7, 1985 3236e:1d
l i
i l
TA8LE 11.2-3 i
RANGE OF MEASURED DECONTAMINA110N FACTORS FOR SELECTED ISOTOPES S !
Isotope Minimum Maximum
! i 1.1 x 10 I 1.6 x 10 4 I-131 l
I-133 1.1 x 10 I 1.8 x 10 4 !
s 1-135 1.4 x 10 I 2.0 x 10 4 Cs-137 2.4 1.3 x 10 3 l l 1.73 x 10 I 1.5 x 10 3 F-18 Co-58 3.2 x 10 I 8.2 x 10 3 Mn-54
>2.5 x 10 I >1.3 x 10 2 l l
l These values were observed across mixed bed demineralizers containing cation !
O resin in the lithium-7 form and anion resin in the borated form. !
l i
O l
l FNR-WM 11.2-48 AUGUS1, 1985 3236e:1d
I
] TABLE 11.2-4 (SHEET 1 0F 4) i i
1 PARAMETERS SPECIFIED BY REGULA10RY GUIDE 1.112 APPENDIX B I
(INPUT PARAMETERS FOR THE GALE COMPUTER CODE)
!O i
i l Description value !
i l
Thermal power level (MWt) 4200 5
I Mass of primary coolant (1b) 6.7 x 10 Primary system letdown rate (gal / min) 100
! 1.etdown cation demineralizer flowrate (gal / min) 10
, Number of steam generators 4 7
l Total steam flow (Ib/hr) 1.708 x 10 Mass of steam in each steam generator (1b) 1.05 x 10 4 !
5
! Mass of liquid in each steam generator (1b) 1.245 x 10 2.16 x 10 6 Total mass of secondary coolant :
4 Total blowdown rate (1b/hr) 5.4 x 10 l Condensate demineralizer regeneration time, days 28 l i
Condensate demineralizer flow f raction 0.65 ,
i Radwaste dilution flow (gal / min) Later ;
I, -
I Shim Bleed i 1
1 i 3
! Shim bleed flowrate (gal / day) 2.5 x 10 l 5
Decontamination factor for I 10 Decontamination f actor for Cs and Rb 4 x 10 4 6
I Decontamination f actor for others 10 ;
l i Collection time (day) 28.7 {
Process and discharge time (day) 1.9 l l} Fraction discharged 0.214 l
lo r
WAPWR-WM 11.2-49 AUGUS1, 1985 [
3236e:Id '
--,_. ~ . _ _ _ . ~ ...__ _ -. .,.__ _ _ _ _.._ -. _ ..,,_._ _ _ _ _ ,__ _ _ .__ .__- _ ._ _ .._ ..__, _ -
l 4 l i !
t t
t TABLE 11.2-4 (SHEET 2 0F 4)
Description Value l j
O Equipment Orains l
Equipment drains flowrate (gal / day) 300 l Fraction of reactor coolant activity 1.0 1 5
! Decontamination factor for I 10 l l Decontamination factor for Cs and Rb 4 x 10 4 l I 6 j Decontamination factor for others 10 t
Collection time (day) 28.7 l Process and discharge time (day) 1.9 l Fraction discharged 0.214 f i
Clean Waste i j P
Clean waste input flowrate (gal / day) 160 l Fraction of reactor coolant activity 0.423 I 3
Decontamination factor for 1 10 f 4
Decontamination factor for Cs and Rb 10 !
Decontamination factor for others 10* i l
Collection time (day) 25 !
l Process and discharge time (day) 0.11 i I I Fraction discharged 1.0 l l
)
i O i O
WAPWR-WM 11.2-50 AUGU51, 1985 3236e:1d
9 TABLE 11.2-4 (SHEET 3 0F 4) .
} Description Value O Dirty Waste i
Dirty waste input flowrate (gal / day) 2.62 x 10 3
- Fraction of reactor coolant activity 0.028 3
i Decontamination factor for I 10 ,
4 Decontamination f actor for Cs and Rb 10 4 ~
Decontamination factor for others 10 <
1 n,
l
! Collection time (day) 1.5 1 Process and discharge time (day) 0.11 Fraction discharged 1.0 I i Blowdown Waste I
4 Blowdown fraction processed 1.0 3
Decontamination factor for I 10 2 .
Decontamination f actor for Cs and Rb 10 3
Decontamination f actor for others 10 4
- Collection time (day) 0.0 j
Process and discharge time (day) 0.0 l Fraction discharged 0.1 1
1 Condensate Demineralizer Regenerant Solution i
Regenerant Flowrate (gal / day) i
' 4 Decontamination factor for I .. 10 5
- j. Decontamination factor for Cs and Rb 10 5 .
! Decontamination factor for others 10 1 1
! FAPWR-WM 11.2-51 AUGUS1, 1985 l 3236e:1d 1
. - , _ - - , . . ._,-._.__,.m.m.. ,.m..,_m -,--,_.---...--,e,,.,.,,_,_,.__.-.,,m___._m,-, - , - . , - _ . . . . , _ , , , , , - , ,
.I j !
\
i TABLE 11.2-4 (SHEET *4 0F 4) >
. r Description Value !
Collection time (day) 4.8 l Process and discharge time (day) 0.44 I Fraction discharged 0.1 l I
Gaseous Waste System -
} ,
L l Holdup time for xenon (day) 60 l Holdup time for krypton (day) 3 Fill time of decay tanks for gas stripper 0.0 Gas waste system: HEPA? No
! Auxiliary building: charcoal? No ;
- 4
! Auxiliary building: HEPA? Yes Containment volume (ft )
3 3.1 x 10 6 ,
l 3 !
Containment atmosphere cleanup rate (ft / min) 25 x 10 Containment shutdown purge: charcoal?, HEPA? No, yes Number purge per year 24 I
! Containment normal purge rate (ft 3/ min); 0.0, NA, NA j charcoal?, HEPA?
j Fraction of iodine released from blowdown tank 0 ,
l vent l Fraction of iodine released from main condenser 1.0 air ejector l'
Detergent waste decontamination factor 1.0 O
l WAPWR-WM 11.2-52 AUGUST, 1985 3236e:1d
______.-___.._._.__,_.._.0b__._.___._.._.-,.__._:
P i
O O
<l' O' -
O ,
O O O
, TABLE 11.2-5 (SHEE1 1 0F 3) ,
/
CALCULATED RELEASES OF RADIDACTIVE MATERIALS IN LIQUID EFFLUENTS ASSUMING EXPECTED FUEL LEAKAGE ANNUAL RELEASES TO DISCHARGE CANAL 8eron Adjusted Detergent Recycle Misc. Wastes Secondary Turb Bids Total LWS- Total Wastes Total Nuclide (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) !
CR 51 1.92E-07 2.93E-05 2.71E-09 1.06E-06 3.05E-05 1.00E-04 a 1.00E-04 MN 54 4.43E-08 5.43E-06 9.15E-10 2.38E-07 5.71E-06 1.88E-05 1.00E-03 1.00E-03 FE 55 2.35E-07 2.83E-05 3.77E-09 9.51E-07 2.95E-05 9.69E-05 a 9.70E-05 '
FE 59 1.17E-07 1.62E-05 2.15E-09 7.10E-07 1.70E-05 5.59E-05 a 5.60E-05 ,
! CO 58 2.03E-06 2.68E-04 3.18E-08 9.49E-06 2.80E-04 9.18E-04 4.00E-03 4.90E-03 :
CO 60 2.95E-07 3.55E-05 4.27E-09 1.07E-06 3.68E-05 1.21E-04 8.70E-03 8.80E-03 8R 83 7.90E-14 2.31E-05 b 1.20E-06 2.43E-05 7.97E-05 a 8.00E-05 BR 84 'b 1.89E-07 b 5. 50E-10 1.89E-07 6.22E-07 a 6.22E-07 i RB 86 5.10E-07 1.23E-06 6.41E-11 5.32E-08 1.80E-06 5.90E-06 a 5.90E-06
- RB 88 b 5.40E-08 b 5.63E-12 5.40E-08 1.77E-07 a 1.77E-07 SR 89 4.21E-08 5.74E-06 7.44E-10 2.37E-07 6.02E-06 1.98E-05 a 2.00E-05 SR 90 1.48E-09 1.78E-07 1.91E-11 4.76E-09 1.84E-07 6.04E-07 a 6.04E-07 Y 90 1.50E-09 1.01E-07 1.92E-11 1.~18E-09 1.04E-07 3.41E-07 a 3.41E-07 SR 91 7.86E-11 2.00E-06 2.27E-15 1.45E-07 2.14E-06 7.03E-06 a 7.03E-06 Y 91M 5.07E-11 1.29E-06 1.47 E-15 9.35E-08 1.38E-06 4.54E-06 a 4.54E-06 !
- Y 91 8.50E-09 1.13E-06 1.20E-10 3.61 E-08 1.17E-06 3.85E-06 a 3.85E-06 Y 93 5.13E-12 1.10E-07 1.92 E-16 7.46E-09 1.17E-07 3.85E-07 a 3.85E-07 4
ZR 95 7.52E-09 9.99E-07 1.56E-10 4.74E-08 1.05E-06 3.46E-06 1.4E-03 1.40E-3 N8 95 7.56E-09 8.99E-07 1.84 E-10 4.75E-08 9.55E-07 3.13E-06 2.0E-03 2.00E-3 MO 99 1.11E-06 7.54E-04 7.42E-09 4.43E-05 8.00E-04 2.63E-03 a 2.60E-03 l TC 99M 1.06E-06 6.69E-04 7.09E-09 3.61 E-05 7.07E-04 2.32E-03 a 2.30E-03 '
RU103 5.08E-09 7.21E-07 6.89E-11 2.37E-08 7.50E-07 2.46E-06 1.40E-04 1.40E-04
, RH103M 5.09E-09 7.24E-07 6.90E-11 2.36E-08 7.53E-07 2.47E-06 a 2.47E-06 1.84E-11 4.75E-09 1.82E-07 5.97E-07 2.40E-03 '
RU106 1.44E-09 1.76E-07 2.40E-03 RH106 1.44E-09 1.76E-07 1.84E-11 4.75E-09 1.82E-07 5.97E-07 a 5.97E-07 ,
AG110M b b b b b b 4.40E-04 4.40E-04 j WAPWR-WM 11.2-53 AUGUST, 1985
- 3236e
- 1d
O O O' .
O O O O TA8LE 11.2-5 (SHEET 2 0F 3)
CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID EFFLUENTS ASSUMING EXPECTED FUEL LEAKAGE ANNUAL RELEASES TO DISCHARGE CANAL Boron Adjusted Detergent Recycle Misc. Wastes Secondary Turb Bldg Total LWS Total Wastes. Total Nuclide (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies)
TE125M 3.56E-09 4.79E-07 3.81E-11 1.19E-08 4.95E-07 1.62E-06 a 1.62E-06 TE127M 3.75E-08 4.78E-06 4.23E-10 1.19E-07 4.94E-06 1.62E-05 a 1.60E-05 TE127 3.72E-08 6.53E-06 4.19E-10 2.57E-07 6.82E-06 2.24E-05 a 2.20E-05 TE129M 1.51E-07 2.21E-05 1.96E-09 7.09E-07 2.30E-05 7.54E-05 a 7.50E-05 TE129 9.71E-08 1.43E-05 1.26E-09 4.58E-07 1.49E-05 4.88E-05 a 4.90E-05 1130 6.65E-09 8.06E-05 4.28E-12 3.24E-06 8.39E-05 2.75E-04 a 2.80E-04 TE131M 8.36E-09 1.67E-05 1.65E-11 1.01E-06 1.77E-05 5.81E-05 a 5.80E-05 TE131 1.53E-09 3.05E-06 3.01E-12 1.85E-07 3.23E-06 1.06E-05 a 1.10E-05 1131 1.27E-04 3.28E-02 6.31E-06 6.42E-04 3.36E-02 1.10E-01 6.20E-05 1.10E-01 TE132 4.41E-07 2.54E-04 2.59E-09 1.12E-05 2.66E-04 8.72E-04 a 8.70E-04 1132 4.54E-07 1.76E-03 3.77E-09 3.98E-05 1.80E-03 5.90E-03 a 5.90E-03 1133 5.71E-06 2.11E-02 2.48E-08 7.17E-04 2.18E-02 7.16E-02 a 7.20E-02 1134 b 2.23E-05 b 3.19E-07 2.26E-05 7.43E-05 a 7.40E-05 CS134 2.57E-04 4.41E-04 3.63E-08 1.59E-05 7.13E-04 2.34E-03 1.30E-02 1.50E-02 1135 3.77E-08 3.95E-03 4.83E-13 2.02E-04 4.15E-03 1.36E-02 a 1.40E-02 CS136 6.31E-05 1.76E-04 7.48E-09 8.06E-06 2.47E-04 8.12E-04 a 8.10E-04 CS137 1.87E-04 3.19E-04 2.67E-08 1.15E-05 5.18E-04 1.70E-03 2.40E-02 2.60E-02 8A137M 1.75E-04 2.98E-04 2.50E-08 1.07E-05 4.84E-04 1.59E-03 a 1.60E-03 8A140 1.50E-08 2.98E-06 1.85E-10 1.17E-07 3.11E-06 1.02E-05 a 1.00E-05 LA140 1.70E-08 2.73E-06 2.12E-10 8.55E-08 2.84E-06 9.31E-06 a 9.31E-06 CE141 7.46E-09 1.10E-06 1. 28E-10 4.73E-08 1.15E-06 3.79E-06 a 3.79E-06 CE143 1.62E-10 2.78E-07 2.37E-13 1.03E-08 2.89E-07 9.48E-07 a 9.48E-07 PR143 3.88E-09. 7.18E-07. 4.13E-11. 2.36E-08 7.46E-07 2.45E-06 a 2.45E-06 CE144 4.71E-09 5.78E-07 9.12E-11 2.38E-08 6.06E-07 1.99E-06 5.20E-03 5.20E-03 PR144 4.71E-09 5.76E-07 9.12E-11 2.38E-08 6.06E-07 1.99E-06 a 1.99E-06 WAPWR-WM 11.2-54 AUGUST, 1985
! 3236e:1d
O O O' -
O O O O TABLE 11.2-5 (SHEET 3 0F 3)
CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID l EFFLUENTS ASSUMING EXPECTED FUEL LEAKAGE ANNUAL RELEASES TO DISCHARGE CANAL i
8oron Adjusted Detergent Recycle Misc. Wastes Secondary Turb 81dg Total LWS Total Wastes Total Nuclide (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) (Curies) .
! NP239 1.22E-08 1.02E-05 7.33E-11 6.56E-07 1.09E-05 3.57E-05 a 3.57E-05
! All j others 1.36E-10 8.87E-09 3.03E-12 4.30E-11 9.05E-09 2.97E-08 a 2.97E-08 l TOTAL 8.22E-04 6.31E-02 6.50E-06 1.76E-03 6.57E-02 2.16E-01 6.23E-02 2.80E-01 '
I (Except tritium) i Tritium Release 840 curies per year
- a. No value provided in the source term utilized in the GALE code.
- b. Value is less than 10-15, i
I 4
j i a
i WAPWR-WM 11.2-55 AUGUST, 1985
) 3236e:1d
.~. _ __ ___ _ ____
- . - . .- . .. _ -_ = _ _. . =_ . .-.
- TABLE 11.2-6 (SHEET 1 0F 2)
RADIDACTIVE LIQUID RELEASES FROM WESTINGHOUSE-DESIGNED PRESSURIZED WATER REACTOR PLANTS-(ZIRCALOY FUEL CLADDING) ,
e Primary Coolant (a) Total Average Discharge Activity, Fraction Annual Concentration Plant Year of Desian Basis Release (C1) (vCi/mi)
R. E. Ginna 1972 0.126 0.375 5.18 x 10~
1973 0.023 0.074 9.74 x 10 1974 0.025 0.138 2.15 x 10 -10 1975 0.013 0.420 6.09 x 10~
~
$ 1976 0.064 0.689 1.09 x 10 ' ;
1977 0.033 0.065 9.01 x 10~
~
H. B. Robinson 2 1972 0.006 0.371 3.4 x 10 '
1973 0.003 0.306 2.1 x 10
1974 0.003 2.9 5.2 x 10 -9 i 1975 0.002 0.44 6.79 x 10
-10 l 1976 <0.001 0.375 6.07 x 10 1977 <0.001 0.329 4.7 x 10 -10 Point Beach 1972 0.062 0.934 1.9 x 10 -9
-0 l 1 and 2 1973 0.015 0.746- 7.39 x 10 1974 0.101 0.196 3.29 x 10 -10
~
! 1975 0.049 3.35 6.03 x 10 '
1976 0.012 3.24 6.17 x 10 -9 1977 0.009 1.5 2.6 x 10' Surry 1 and 2 1972 <0.001 0.083 6.04 x 10 -10
-10 .
1973 0.001 0.145 2 . t..i x 10
-8 1974 <0.001 :29.2 2.32 x 10
-8
( 1975 0.002 27.5 1.12 x 10
-8 1976 0.011 33.7 1.45 x 10
-8 1977 '0.005 65.5 2.58 x 10 NAPWR-WM 11.2-56 AUGUST, 1985 3236e:1d
l i
TABLE 11.2-6 (SHEET 2 0F 2)
Primary Coolant (a) Total Average Discharge O Plant Year Activity, Fraction of Design Basis Annual Release (Ci)
Concentration (vCi/mi) 1.97 x 10 -10
- Turkey Point 1973 <0.001 0.037 3 and 4 1974 0.010 1.69 3.21 x 10
1975 0.012 3.07 2.31 x 10
- 1976 0.006 8.65 2.92 x 10
-9 1977 0.005 8.9 5.06 x 10 i Zion 1 and 2 1973 <0'. 001 <0.001 2.77 x 10 -I 3
-12 1974 <0.001 0.005 8.03'x 10 1 1575 0.003 0.0087 1.18 x 10 -II ,
1976 0.013 0.16 1.58 x 10'II f 1977 0.009 0.95 8.33 x 10 -10 2
'O Prairie Island 1974 0.002 <0.001 2.29 x 10 -12 4
1 and 2 1975 0.006 0.45 1.18 x 10~
~
1976 0.008 <0.012 <3.59 x 10 "
-II 1977 0.008 0.013 1.41 x 10 Kewaunee 1974 0.012 0.422 3.49 x 10 -9 1975 0.005 0.447 2.68 x 10 -9
-8 1976 0.002 2.85 2.32 x 10 1977 <0.001 1.26 8.69 x 10 -9 Donald C. Cook 1 1975 <0.001 0.26 3.19 x 10 ~9
-8 '
1976 0.003 1.87 2.69 x 10
-8
$ s 1977 0.005. 1.52 2.09 x 10 i
- a. Inferred by radioiodine in reactor coolant - includes dif fusion and recoil i sources. ,
WAPWR-WM 11.2-57 AUGUST, 1985 3236e:1d
. - - - - . . = - . . . - - - . . . -
O .
l O
l O
I i
FIGURE 11.2-1 SHEET 1 (FOLDOUT)
PROPRIETARY O
O -
O WAPWR-WM AUGUST, 1985
lO .
O 1 l
O I
I FIGURE 11.2-1 SHEET 2 (FOLDOUT) '
PROPRIETARY O
O -
O WAPWR-WM AUGUST, 1985
r_ _ .
i i
O I
l lO O
FIGURE 11.2-1 SHEET 3 (FOLDOUT)
PROPRIETARY O
O -
O WAPWR-WM AUGUST, 1985
1 O .
O O l FIGURE 11.2-1 SHEET 4 (FOLDOUT)
PROPRIETARY O
O '
~
O pyg,g AUGUST, 1985
i Q, . .
i i IE !
1 3 ac !
s t m.
i j l l ,,,,
-(a,c) .
l i . t
. \
l 4 ,
-! l I
1 1
i
, i I
i 1
)
- t i.
4 ;
i l
~
l i
I 1
I i ; I _o r
! C !
l E
- Chemical and Volisne Control System
) s Figure 11.2 2 !'
j g - (Sheet 1)
- v. ,
- . Lfquid Waste Management Systems Process Flow Diagram l
. - . - , . . . - - - - .., - , , , -~w - , , , - - - - .---- ,.. . - - ---
_ _ _ . - _ - - . _ _ _ _ _ _ . . _ _ . . - . - - - - - . .. - - - .. - - _ . - . ~ . - . . _ - -
's i
l i fit i
- E I m e
i 5 =
. (a,c) .
i 4
1 1
1 t
t t
'ii e
I I
I Boron Recycle Systes I e i Figure 11.2-2 .
~'~
(Sheet 2) .
l ,
L1qu1d Waste Managenent Systems
! E' C
( Process Flow Diagram v'e j
40 I i i i
I i p I 6 t
i l I I
7 1 t i '
.s t
l i tr, !
o E i n.
b i 1
\ -
f - (a,C) l i
4 , .
I' I l i i
I l
l i 1 .
l -r i !
I l I !
! I l
\
c i i I
i i w
i t
j j >
i C.,
c -
I c Liquid Waste Processing System U
- Train "A" - Clean Waste l
I I
, Figure 11.2-2 e
on.
(Sket 3) v Liquid Waste Management Systems t l _ Process Flow Diagram ,
i i i i I
l
~ -
. A u.
m v
I I E E t.
mO m e EE ~ t5 7
- ,k a5 g-' 21 g C o.
. 'm "4 . .
c
%* C %C RS 9y fb er 3'
3 O
O O .
f .I O
MAPWR-WM AUGUST, 1985
e
=
U G w 8
I I
.E. . .E A
m2 e g 9 E' U I ~4 E5 4* 4
- ( .2 b
g "t E ue t2 2 C
. , B>C = .
"5C E O 5t 37
==
SU 3"
=
d) a a O
9 O
G ;
i I O
AUGUS1, 1985 WAPWR-WM
l, i
tr 2
m.
1 1
l (a,c)
F r
i i ;
I I l
i
,i ,
i i t i
i I
t i
l
. I 5
i > -
4 c c3 Steam Generator [
5 u
Blowdown Processing System I F1 i .
e
- hre11.2-2 heet 6) !
j $ Liquid Waste Management System !
Process Flow Diagram l [
i i
1 y ,- 9,,-3--. & . --m-e--m- - , . -- yq --- - - --------e -e w-- 4 ----w--- w- - - --aM--N-- m- - - PWw' " '-' - -w F------ '-- ?*---eww - - - Tn ' - - ' * * - - - - - - - - - -
.l 11.3 GASE0US WASTE PROCESSING SYSTEM (GWPS)
During reactor operation, radioactive isotopes of xenon, krypton and iodine are created as fission products. A portion of these radionuclides are released to the reactor coolant due to a small number of fuel cladding defects. Any leakage of reactor coolant thus results in a release to the atmosphere of the noble gases and a portion of the iodines contained.
Therefore, to limit airborne releases it is necessary not only to restrict reactor coolant leakage but to restrict the concentrations of radioactive noble gases and iodines. Iodine removal is accomplished by ion exchange process in the chemical and waste processing system (CVCS) as indicated on Figure 11.2-2. Sheet 1. The noble gases are removed f rom the reactor coolant by a continuous purge of the CVCS volume control tank (VCT) vapor space. The
- purge flow is directed to the GWPS for processing to minimize the releases of radioactive noble gases to the environment. The GWPS performs this f unction by using temporary adsorption of xenon and krypton on charcoal to permit most 4
of the radioactivity to decay away before it is released to the atmosphere.
11.3.1 Design Bases 11.3.1.1 Source Terms Virtually all the radioactive gas flowing into the GWPS enters as trace
- . contamination in a stream of hydrogen. 1 The primary source of radioactive gas is the volume control tank (VCT) purge.
Hydrogen gas enters the VCT, stripping the fission gases f rom the vapor phase as it is vented to the GWPS.
The source term model is a realistic one and is used to determine expected l O GWPS inventory and releases. This model is based on the American National Standard Source Specification, N-237. Table 11.1-4 lists the activities in the VCT vapor space that are associated with this model and Table 11.1-2 lists the primary and secondary coolant activities.
WAPWR-WM 11.3-1 AUGUST, 1985 3433e:Id
1 N l 11.3.1.2 Expected Releases and Doses i l
The GWPS is designed to collect, process, and delay release of radioactive gaseous wastes generated due to plant operations including anticipated operational . occurrences. The system is designed to assure that during normal j operation the release of gaseous effluent f rom the plant and the expected offsite doses are as low as reasonably achievable (ALARA) as defined in Appendix I of 10CFR50. An evaluation of plant conformance to Appendix I is given .in. Section 11.3.3.
l The GWPS is designed to continuously discharge gaseous waste to the environment with activity levels reduced by radioactive decay. A decay period of 60 days is provided for xenon isotopes and 3 days for krypton isotopes through the temporary adsorption of these gases on the charcoal beds in the process path. In this way, the GWPS conforms to the requirements of General Design Criterion 60.
11.3.1.3 Accommodation of Surges
, The design of the GWPS is based on a continuous inflow of 0.7 scfm f rom the
, VCT purge. Venting of other equipment to the GWPS does not create surges in the VCT purge processing since these vent gases are handled separately, event-ually being transferred to the VCT.
The GWPS is designed to be f ree f rom surges in the process flow path leading through the charcoal adsorption beds. This flow path does not experience flow surges as a result of plant startups, plant shutdowns, or equipment downtime.
The purge flow from the VCT can be administratively increased above the normal 0.7 scfm. The delay times for krypton and xenon would be reduced propor-O tionately to the increase in total flow through the charcoal. The maximum VCT purge flow to the GWPS would be.l.2 scfm.
i O
i I
WAPWR-WM 11.3-2 AUGUST, 1985 3433e:ld
l 11.3.1.4 System Leakage l The GWPS operates at pressures not f ar above atmospheric thus limiting the potential for leakage. leakage f rom the GWPS is further limited through the use of welded conne'.tions wherever not restricted due to maintenance requirements. All control valves are provided with bellows seals to minimize leakage through the valve topworks. Wherever possible, manual valves are of the diaphragm type to prevent leakage.
O 11.3.1.5 Monitoring Releases b Releases f rom the GWPS are continuously monitored by a radiation monitor in the plant vent. In addition, the system design includes provisions for taking grab samples of the discharge flow stream for analysis. In this manner, the requirements of General Design Criterion 64 are responded to.
11.3.1.6 Control of Releases Due to Operator Error or Equipment Malfunction In order to control the release of radioactive gases resulting f rom equipment failure or operator error, the discharge line from the GWPS is automatically isolated on a high plant vent radiation signal. The GWPS design is such that an equipment failure might require that the system be isolated for maintenance but no significant inadvertent release would occur.
Few operator actions are required during GWPS operation since, once aligned for operation, the GWPS operates automatically in response to the control C/ signals f rom the instrumentation supplied. The potential for operator error is therefore small.
11.3.1.7 Frotection From Explosion Since the GWPS process stream consists mainly of hydrogen, there is the potential for an explosion should a significant amount of oxygen enter the system. Instead of designing the GWPS to withstand an explosion, the system s is provided with redundant oxygen analyzers at two locations in the system.
WAPWR-WM 11.3-3 AUGUST, 1985 3433e:ld
One set of analyzers monitors the incoming VCT purge gas stream while the other set monitors the combined vent gases coming f rom all other equipment.
Each analyzer has a high alarm and a high-high alarm. Coincident with the high-high alarm, corrective actions are automatically taken to avoid continued buildup of oxygen concentration. Connections are provided to the nitrogen supply header to allow the gas stream to be diluted with pitrogen if desired.
i 11.3.1.8 Component Design Parameters O The GWPS component design parameters are listed in Table 11.3-1.
11.3.1.9 Seismic and Safety Classification The GWPS components and piping are not designed to withstand a seismic event and are classified as Non-Nuclear Safety Class. The GWPS design is consistent with the guidelines of NRC Regulatory Guide 1.143, Revision 1, in these rega rds.
11.3.2 System Description
- The GWPS receives and delays release of fission gases that have been stripped from the reactor coolant in the VCT by a hydrogen gas purge flow. The flow to i the GWPS thus consists of hydrogen with trace amounts of fission gases. The constant removal of the fission gases by the hydrogen purge of the VCT main- ,
tains the fission gas concentration in the reactor coolant at a low residual level. This minimizes the escape of radioactive gases during maintenance d operations on the reactor coolant system (RCS) or resulting f rom leakage of reactor coolant liquid.
The GWPS uses charcoal at ambient temperature to slow the passage of radioat-tive gases through the system. When operating at design conditions the mass of charcoal provided in the GWPS is sufficient to provide a minimum of 60 days delay f rom xenon and a minimum of 3 days delay for krypton. The carrier gases (hydrogen or nitrogen) are not delayed by the charcoal.
v WAPWR-WM 11.3-4 AUGUST, 1985 l
3433e:ld
Y t
Sampling capability is provided downstream of the charcoal adsorption tanks.
Analyses of these samples provides indication of the GWPS performance when they are compared with VCT vapor space sample analyses.
With the GWPS normally - containing a hydrogen flow stream, care is taken to assure that oxygen is excluded f rom the system. The GWPS is operated at positive pressure at all times to prevent any possibility of oxygen inleakage. Gases entering the GWPS are continuously monitored by redundant oxygen analyzers. The analyzers provide alarms and automatic actuation of equipment if oxygen levels above preset limits are detected,- thus preventing the gas stream f rom reaching a potentially flammable hydrogen-oxygen mixture.
The operator may inject nitrogen into the GWPS to obtain dilution. Nitrogen i purge is also used to clear a portion of the system of hydrogen before performing maintenance or of oxygen af ter maintenance is complete. Thus, the possibility of hydrogen ignition is very remote and the GWPS is not designed j to withstand one.
The dilution of the hydrogen stream, when it is discharged into the plant vent, is so great that the 4 percent flammability limit for hydrogen in air will never be reached. Discharge from the GWPS is automatically terminated'on low dilution flow.
Besides processing the VCT purge flow, the GWPS collects non-oxygen bearing 4
vent gases and injects them into the VCT. In this nenner, these gases are 4 eventually returned to the GWPS via the VCT purge path where any fission gases will be subjected to the charcoal adsorption process thus delaying their release. By treating the vent gases in this manner there is the additional advantage that the flow through the charcoal beds is not subjected to flow surges. ,
In addition, the GWPS contains the nitrogen and hydrogen distribution headers.
i The GWPS design is shown in detail in the piping and instrumentation diagram, I
Figure 11.3-1.
WAPWR-WM 11.3-5 AUGUST, 1985 3433e:ld
11.3.2.1 System Operation 11.3.2.1.1 Norna.1 VCl Purge Flow Processing During normal power operation, hydrogen is continuously purged through the VCT and to the GWPS to strip fission gases from the reactor coolant. After entering the GWPS, the gas stream passes through two redundant oxygen analyzers that continuously monitor the gas stream oxygen content. If the r\
Q concentration of oxygen in the hydrogen stream approaches explosive limits, the inflow of gas to the GWPS is automatically terminated. Alarms are provided to annunciate high oxygen levels.
After leaving the oxygen analyzers, the gas stream is processed by the ref rigerated waste gas dryer to remove water vapor. Removing moisture f rom the gas stream is necessary for proper operation of the GWPS since adsorption of water on the charcoal in the charcoal adsorption tanks would diminish the capability of the charcoal to adsorb fission gases. An analyzer monitors the gas stream leaving the gas dryer for humidity and automatically closes a downstream valve and actuates an alarm if a high humidity level is detected.
Af ter treatment by .the gas dryer, the gas stream flows through one of two charcoal guard beds which are installed in parallel. The charcoal guard bed is provided to protect the downstream charcoal adsorption tanks f rom being exposed to the high' humidity gas stream that would result from a failure of the refrigerated waste gas dryer and of the humidity analyzer. During normal operation the charcoal guard bed removes iodines and any residual moisture in (s
\
the gas stream. A humidity analyzer downstream of the guard beds actuates an alarm if the guard bed in service becomes ineffective due to saturation. If this occurs, the flow path is realigned to pass through what had been the standby charcoal guard bed and to isolate the guard bed that . had been in service.
Following the guard bed, the gas stream flows through a series of charcoal adsorption tanks which delay the passage of xenon and krypton isotopes. At p design flow through the charcoal adsorption tanks, xenon is delayed by 60 days and krypton is delayed- by 3 days while the hydrogen passes through without WAPWR-WM 11.3-6 AUGUST, 1985 3433e:ld
l I
delay. These delay times allow all of the isotopes of concern, except krypton-85, to decay to very small f ractions of the concentrations entering the GWPS. Because of its long half-lif e, the concentration of krypton-85 in the gas stream remains essentially unchanged by the.3 day delay.
Provisions are made to take a grab sample of the gas stream leaving the charcoal adsorption tanks.
The flow stream leaving the charcoal adsorption tanks next passes through the charcoal fines filter and then is directed either to the plant vent or to the I
gas surge tank and recycle line compressors for reuse as hydrogen purge flow [
to the VCT.
I If the gas stream is being discharged to the plant vent, the discharge line
- will be automatically isolated on either a high plant vent radiation signal or a high plant vent hydrogen concentration signal.
j Operation of the GWPS with the discharge hydrogen stream being recycled
] conserves hydrogen gas. With the exception of krypton-85, all gaseous
- isotopes in the hydrogen stream have decayed suf ficiently during the transit i of the GWPS to have no significant ef fect on the reactor coolant concentra-tions when the gas stream is recycled to the VCT. However, due to the long i i half-life of krypton-85, its concentration in the GWPS outlet stream is essentially the same as in ttie inlet stream with the result that, when the I
hydrogen stream is recycled, the concentration of krypton-85 in the reactor
{
coolant will rise. To avoid excessive krypton-85 buildup in the reactor coolant, the GWPS must be operated _in the release mode at least part of the time. Reactor coolant sample analysis would detect any excessive buildup of x
, krypton-85 so that corrective action could be taken.
In the recycle mode, the hydrogen stream is directed to the inlet of the
- recycle line compressors. One or both of the compressors may be utilized 4 depending on gas surge tank pressure. The gas surge tank provides a large volume to prevent rapid changes in pressure upstream of the compressor.
O WAPWR-WM 11.3-7 AUGUST, 1985 3433e:ld
N 11.3.2.1.2 Equipment Veni Gas Processing Besides processing the VCT purge flow, the GWPS receives vent gases f rom a number of components in the boron recycle system (BRS), the. liquid waste processing system (LWPS), and the RCS.
Vent gases from the following components can be directed to the GWPS:
- 1. BRS recycle evaporator package
- 2. BRS recycle holdup tanks
- 3. LWPS reactor coolant drain tank
- 4. RCS pressurizer relief tank The vent lines f rom the recycle evaporator package and the reactor coolant drain tank are normally open to the GWPS.
! Venting of the recycle holdup tanks is performed administratively af ter a 1
0 t recycle holdup tank has accumulated a specified amount of gas under its
! diaphragm. The gas is pumped to the GWPS by the recycle holdup tank vent compressor. Provisiens are included to permit taking a grab sample of the recycle holdup tank vent gas.
The pressurizer relief tank is vented to the GWPS only during maintenance operations.
The vent gases are all collected in the gas surge tank. Periodically, as controlled by gas surge tank pressure, the gas surge tank contents are pumped to the VCT by a recycle line compressor. In this way, the vent gases are not released directly but eventually are returned to the GWPS via the VCT purge path where they are subjected to the charcoal adsorption process thus delaying l
their release and reducing their activity by radioactive decay.
Before going to the compressors, the gas stream passes through two redundant j oxygen analyzers that continuously monitor the gas stream. If the concentra-tion of oxygen approaches its specified limit the compressors are automati-cally stopped. Alarms are provided to annunciate high oxygen levels.
WAPWR-WM 11.3-8 AUGUST, 1985 i j 3433e:ld
I
(
11.3.2.1.3 Startup Initial startup comences with the GWPS flushed f ree of air using nitrogen.
This can be accomplished by either repeated pressurization of the system using nitrogen, each time venting to the plant vent, or by a feed and bleed ,
. process. Both nitrogen 'and oxygen pass through the charcoal beds without delay.
Initially during plant startup, the VCT purge flow is aligned to discharge directly to the. plant vent. Upon removal of the air f rom the reactor coolant l
! using nitrogen purge of the VCT, a hydrogen purge to the VCT is initiated to strip the nitrogen from the reactor coolant. When the reactor coolant I hydrogen concentration reaches the required level, the VCT purge flow is i directed to the charcoal beds and operation of the GWPS is resumed as described in Subsection 11.3.2.1.1.
i t
i 11.3.2.1.4 Shutdown and Degassing of the RCS i .
If the unit is shutdown and it is necessary to remove the residual fission a
t gases and hydrogen f rom the reactor coolant, operation of the GWPS remains unchanged until af ter the reactor coolant fission gas concentration is reduced to the required level. Then the VCT hydrogen supply is isolated, the VCT purge flow is directed to the plant vent, and a nitrogen purge of 5 scfm is initiated through the VCT to strip the hydrogen f rom the reactor coolant. The nitrogen purge is continued until the desired low hydrogen concentration in i the reactor coolant is reached. Degassing is then complete and the RCS may be opened for maintenance or refueling. The charcoal beds are not in use and that portion of the system is isolated, maintaining a hydrogen atmosphere.
11.3.2.2 Component Description Component parameters are given in Table 11.3-1. In keeping with the guidance
[ of Regulatory Guide 1.143, Revision 1, the GWPS equipment is classified as Non-Nuclear Safety class and is not designed to withstand a seismic event, O
i i WAPWR-WM 11.3-9 AUGUST, 1985 3433e:ld
- . . - - . - _ - - . . - . . - - - - - _ _ - . . - = _ _ - - ~ . .
o i
11.3.2.2.1 Ref rigerated Waste Gas Dryer The ref rigerated waste gas dryer cools the hydrogen purge stream f rom the VCT i and condenses and removes water vapor to a dew point of 40*F before the gas j enters the charcoal adsorption beds. Removal of the water vapor from the gas i stream prolongs the life of the charcoal adsorption beds. The ref rigerated i
waste gas dryer consists of a refrigerated chiller unit to cool the gas j
$ l stream, and a separator to remove the condensed water vapor. [
O A humidity analyzer downstream of the gas dryer is provided to detect 1
inadequate moisture removal.
l
.11.3.2.2.2 Charcoal Guard Beds II
- Two charcoal guard beds are provided in parallel between the refrigerated waste gas dryer and the charcoal adsorption tanks. One guard bed is in l service to protect the downstream charcoal adsorption tanks from being f contaminated by water if f ailure occurs in both the ref rigerated waste gas
! dryer and in the automatic process isolation on high humidity. During normal
- operation, the guard bed removes iodines and any residual moisture in the gas i stream. The second guard bed is held in reserve to be brought into service if j the first guard bed becomes inef fective in removing water vapor. A humidity l analyzer dcanstream of the guard beds actuates an alarm if the gas stream I water content exceeds desired limits. '
i I
. The charcoal guard beds have provisions to allow replacement of the charcoal i
should it prove necessary, i
Although the guard bed does provide fission gas adsorption capacity, no credit is assumed in designing the GWPS process delay for krypton and xenon since i
water adsorption on the guard bed results -in declining ef fectiveness in noble gas adsorption.
l 4
WAPWR-M 11.3-10 AUGUST, 1985 3433e:ld
3 t
i 11.3.2.2.3 Charcoal Adsorption Tanks
]
The charcoal adsorption tanks are vertical tanks connected in series to l i provide a long charcoal filled flow path for the' waste gas stream. At design .
flow and temperature the total delay time provided by the charcoal adsorption ,
tanks is 60 days for xenon and 3 days for krypton.
i
! Although it is highly unlikely that charcoal would need to be replaced, each tank has provisions to facilitate charcoal replacement.
11.3.2.2.4 Charcoal Fines Filter 9
The charcoal fines filter is a disposable cartridge type filter placed down-i stream of the charcoal adsorption tanks. Its ' purpose is to filter out any j charcoal particles that might be entrained in the hydrogen gas stream as the l gas stream leaves the adsorption tanks. Filter cartridge change-outs are i <
expected to be very infrequent. !
!O f 11.3.2.2.5 Gas Surge Tank i
i j Surge capacity in the recycle line compressor suction line is provided by the :
gas surge tank. The tank is provided to stabilize the pressure in the. suction j line to the compressors so the compressors will not be spuriously started or l stopped by pressure surges. Gas surges from any of the various equipment vent lines will be dampened by the gas surge tank volume. The surge tank volume l
j O also compressorstabilizes is running. the pressure at the recycle line compressor suction while a .
8 11.3.2.2.6 Recycle Holdup Tank Vent Compressor O The recycle holdup tank vent compressor is provided to pump the gases th have accumulated under a BRS recycle holdup tank diaphragm into the gas surge I tank. The vent compressor is designed to accommodate any water that will condense out of the vent gas under compression. Operation of the vent O
WAPWR-WM 11.3-11 AUGUST, 1985 3433e:Id
--r --- -e - ww--~~,.,-r en -
1--twww-e,--~e--ame-ve-,-ve=ee-n---- :w-----2w.m- -t--,---. w w w --,- we - z-- -e-.,-w. --r*--w-ev=<
A compressor is initiated administratively and can be stopped manually or operated until a low suction pressure signal stops it automatically. The vent '
compressor is also stopped automatically on a high discharge pressure signal.
11.3.2.2.7 Recycle Line Compressors Two recycle line compressors are provided to transfer gases from the GWPS to the VCT. The compressors are designed to accommodate any water that will
[ condense out of the process gas under compression.
In the " discharge" mode of operation, normally only one compressor is required to operate. Either compressor can be used. The operator initially chooses
- one compressor to act as the intermittently run compressor, and the second I compressor acts as the backup. The intermittent-running compressor starts on high suction pressure. Both compressors start on high-high suction tank pressure or manually. The intermittent-running compressor stops on low suction pressure.
O In the " recycle" mode, one compressor is running continuously and one is used intermittently to relieve the gas surge tank pressure as necessary. The compressor chosen to run intennittently can be started manually or by high suction pressure. It is stopped manually or by low suction pressure.
Each compressor automatically stops on high discharge pressure, low suction pressure, or high-high suction oxygen concentration.
11.3.2.3 Instrumentation and Control The GWPS instrumentation is shown on the piping and instrumentation diagram, Figure 11.3-1.
Instrumentation having remote readouts have the readouts on the GWPS panel.
All alarms are shown separately on the GWPS panel and, in addition, any alann on the GWPS panel also actuates one common GWPS annunciator on the main i
control board.
WAPWR-WM 11.3-12 AUGUST, 1985 3433e:ld
l I
11.3.2.3.1 Flow Instrumentation VCT Purge Flow (1-FT-1094)
This instrument monitors normal purge flow entering the GWPS from the VCT. Indication and high ' alarm function are provided on the GWPS panel.
Instrument calibration is based on a hydrogen process stream.
VCT Purae Flow to Plant Vent (FT-1057)
This instrument provides local indication of purge flow bypassing the charcoal beds to the plant vent. Instrument calibration is based on a nitrogen process stream.
Recycle Holdup Tank Vent Flow (FT-1089)
This instrument provides local indication of the ficw rate of recycle holdup tank vent line when vent _ gases are being pumped to the gas surge tank.
11.3.2.3.2 Pressure Instrumentation Pressure instruments located in portions of the system that may contain radioactive gases are. provided with diaphragm seals to prevent outleak-age through the instrument.
Hydrogen Supply Header Pressure (PT-1065)
This instrument provides indication of the hydrogen supply header pres-sure locally and on the GWPS panel.
O A low alarm is provided on the GWPS panel.
O WAPWR-WM 11.3-13 AUGUST, 1985 3433e:ld
4 Nitrogen Supply Header Pressure (PT-1066)
This instrument provides indication of the nitrogen supply header pres-sure locally and on the GWPS panel. A low alarm is provided on the GWPS panel.
J Nitrogen Purge Pressure (PI-1047)
This instrument provides local indication of pressure in the GWPS nitro-gen purge line downstream of the pressure control valve.
VCT Purge Pressure (1-PI-1095)
This instrument locally indicates the pressure in the VCT purge line at a point downstream of the pressure control valve. l Charcoal Fines Filter Pressure (PI-1038. PI-1039) a Local pressure indicators are located on_the upstream and downstream sides of the charcoal fines filter to indicate the pressure drop across the filter.
Recycle Holdup Tank Vent Compressor Suction Pressure (PT-1029)
This instrument indicates locally the pressure on the suction side of the compressor. If the suction pressure should fall below 7-inches water column vacuum, the compressor is automatically switched off and an alarm on the GWPS panel is sounded.
Recycle Holdup Tank Vent Compressor Discharge Pressure (PT-1055)
This instrument indicates on the GWPS panel the pressure on.the discharge side of the compressor. If the pressure in the compressor discharge line rises above the maximum discharge pressure of the compressor, the WAPWR-WM 11.3-14 AUGUST, 1985
'3433e:1d
. compressor is automatically switched of f and an alarm is sounded on the J
GWPS panel. Indication is provided locally and on the GWPS panel.
Recycle Line Compressors Suction Pressure (PT-1052)
O This instrument provides indications of compressor suction pressure on the GWPS panel. When the pressure in the suction line rises to the high setpoint, one of the recycle line compressors is automatically started.
If the pressure drops to the low setpoint, the compressor is automatically v
stopped.
A high-high pressure switch is also pr0vided. On reaching the high-high setpoint, the backup recycle line compressor is automatically started, the VCT purge line isolation valve is automatically closed and an alarm is actuated to alert the operator that the pressure in the gas surge tank is approaching the upper limit for proper operation of the BRS recycle evaporator.
Recycle Line Compressor Suction Pressure (PT-1053. PT-1054)
These instruments indicate, on the GWPS panel, the pressure on the suction side of each compressor. If the pressure in .the suction line should approach atmospheric pressure, the compressor automatically is switched off and an alarm is sounded on the GWPS panel. This protects the compressors from being operated with the suction line. valved closed.
O V Recycle Line Compressor Discharge Pressure (PT-1079. PT-1088)
These instruments measure the pressurs on the discharge side of each .
compressor. If the pressure in the discharge line should rise to the N maximum discharge pressure of the compressor, the compressor is switched of f and an alarm is sounded. Indication is provided both locally and on the GWPS panel.
v i
WAPWR-WM 11.3-15 AUGUST, 1985 3433e:ld
11.3.2.3.3 Gas Analysis Instrumentation VCT Purae Line Oxygen Analyzers ( AE-1074. AE-1075)
These redundant' analyzers are provided upstream of the ref rigerated waste gas dryer to detect the presence of oxygen. Indication is provided both locally and on. the GWPS panel for each of the analyzers. The high alarm setpoint is well below the flammability limit for oxygen in hydrogen. If the oxygen concentration does approach the explosive limit, a high-high alarm is actuated and the VCT purge flow is automatically terminated.
't There is normally no oxygen in the flow stream.
Recycle Line Compressor Oxygen Analyzers ( AE-1077. AE-1078)
These redundant analyzers are provided upstream of the recycle line compressors to detect the presence of oxygen. Indication is provided both locally and on the GWPS panel for each of the analyzers. The high alarm setpoint is well below the flammability limit for oxygen in hydrogen. If the oxygen concentration does approach the explosive limit, a high-high alarm is actuated and the recycle line compressors are stopped. There is normally no oxygen in the flow stream.
Ref rigerated Waste Gas Dryer Outlet Humidity Analyzer-( AE-1036)
This instrument ~ monitors the humidity level of _ the waste gas stream leaving the ref rigerated gas dryer. If the high setpoint is reached a O- valve downstream of the analyzer is automatically closed and a high alarm I is actuated. Indication is provided both locally and on the GWPS panel.
. Guard Bed Outlet Humidity Analyzer ( AE-1037)
~
This instrument monitors the humidity level of the waste gas stream leaving the guard bed. A high alarm is provided to alert the operator that the guard bed is allowing moisture to pass through and that the gas l %)
i WAPWR-WM 11.3-16 AUGUST, 1985 3433e:ld
k stream should be diverted to pass through the standby guard bed. Indica-1 tion is provided locally. l l
Plant Vent Hydrogen Analyzer ( AE-1073)
O This instrument monitors the hydrogen concentration within the plant vent to assure enough ventilation flow exists for proper hydrogen dilution.
The discharge line to the plant . vent is isolated and a high alarm is sounded on high hydrogen concentration in the plant vent. Indication is provided on the GWPS panel.
11.3.2.3.4 Radiation Instrumentation i
Plant Vent Radiation (RE-014) l A radiation monitor is provided in the plant vent. Readout and high l alarms f rom this monitor are provided on the GWPS and radiation monitor-ing systems panels. The discharge line to plant vent is isolated on high radiation.
a i 11.3.3 Radioactive Releases 11.3.3.1 Discharge Requirements Radioactive gaseous effluents and particulates discharged from the plant may not exceed the concentration limits specified in 10 CFR 20, Appendix B Table
- ( II, column 1, or the dose limits specified in 10 CFR 50, Appendix 1.
11.3.3.2 Estimated Releases i
Radioactive effluent releases from the plant for normal operation are given in Table 11.3-2. These release rates were calculated using the PWR-GALE code l (Reference 1) and plant operating parameters listed in Table 11.2-4.
!, O i
WAPWR-WM 11.3-17 AUGUS1, 1985
! 3433e:ld
, .. _, . ., . . . ~ _ _ . _ _ _ . _ . . _ _ , . . _ - . . _ . _ _ . _ . _ _ - - _ . . . _ . . _ , _ . _ _ _ . _ _ . ~ _ _ _ _
I 9
J j.
( :
?
Table 11.3-2 lists the calculated total annual release as well as the annual release from each of the following pathways- !
i I
- 1. GWPS
- 2. ' Containment ventilation
[ 3. Aux bldg i 4. Turbine bldg ventilation i S. Air ejector exhaust LO 9 11.3.3.3 Release Points for Determination of Dilution Factors l
l 1
I i
j Gaseous and particulate radioactive ef fluents may be normally released through the plant vent and the turbine building vent.
i 1
l 11.3.3.4 Effluent Concentration and Dilution Factors A comparison of offsite (at site boundary) airborne gaseous and particulate effluent concentrations with 10 CFR 20 limits is given in Table 11.3-3. These l concentrations are based on the total annual releases given in Table 11.3-2
! and on an assumed dilution factor of 2.75 x 10~ sec/m which is
! conservative for the large majority of nuclear plant sites.
11.3.3.5 Estimated Doses from Atmospheric Releases i
i
{ Estimated annual average doses from continuous exposure at the site boundary l 1
L .
to noble' gases released to the atmosphere from the plant during normal ,
j operation are given in Table 11.3-4. These . calculated doses are well within the guidelines of Appendix I to 10 CFR 50. Doses due to the release of i iodines and particulates are not estimated since there is no site information
}
providing. definition of the various exposure pathways, i i ,
i WAPWR-WM 11.3-18 . AUGUST, 1985 ,
3433e:1d r '
I __-. _ _ _..,.-..,. . _ ._... . m. __ . . . . , _ , _ . . , - , . , _ , . . . _ , - - , - . . , _.m..._.~._,_,_m-,-
4 REFERENCES
- 1. U.S. Nuclear Regulatory Comission, " Calculation of Releases from Pressurized Water Reactors," PWR-GALE Computer Code, NUREG-0017 April 1976.
O O
O O
O WAPWR-WM 11.3-19 AUGUST, 1985 3433e:1d
TABLE 11.3-1 (Sheet 1 of 3)
GWPS COMPONENT DESIGN PARAMETERS REFRIGERATED WASTE GAS DRYER Quantity 1 Design Temperature, 'F 200 Design Pressure, psig 150 Design Flow, SCFM H 0*7 2
Material SS Operating Temperature (Inlet), 'F 115 Operating Pressure, psig 2-15 Dew Point (Outlet), 'F 40 CHARC0AL GUARD BEDS Quantity 2 Design Temperature, *F 200 Design Pressure, psig 150 Design Flow, SCFM H 0.7 2
Material SS Operating Temperature *F 100 Operating Pressure, psig 2 Bed Life, years 40 Charcoal / Bed, lbs. 2140 l O
O WAPWR-WM 11.3-20 AUGUST, 1985 3433e:1d
i TABLE 11.3-1 (Sheet 2 of 3)
GWPS COMPONENT DESIGN PARAMETERS CHARC0AL ADSORPTION TANKS Quantity 6 Design Temperature, 'F 200 Design Pressure, psig 150 Design Flow, SCFM H 0.7 2
Material CS
= Operating Temperature *F 100 Operating Pressure, psig 2 Bed Life, years 40 l Charcoal / Bed, lbs. 4300 CHARC0AL FINES FILTER O Quantity 1 lype Disposable cartridge Design Temperature *F 200 Design Pressure, psig 150 Design Flow, SCFM H I'4 2
AP at Design Flow, psi 0.1 AP Fouled, psi 0.5 Retention of 0.39 particles, % 99.7 O Material SS Operating Temperature *F 100 Operating Pressure, psig 2 O
O WAPWR-WM 11.3-21 AUGUST, 1985 3433e:ld
TABLE 11.3-1 (Sheet 3 of 3)
GWPS COMPONENT DESIGN PARAMETERS RECYCLE LINE COMPRESSORS Quantity 2 Type Diaphragm Design Temperature *F .200 O Design Pressure, psig Design Flow, SCFM Hg Material 150 1.4 SS Operating Temperature 'F 100 Operating Pressure, psig 2 Operating D.ischarge Pressure, psig 15-40 Operating Flow, SCFM H2 0.7 GAS SURGE TANK Q'antity 1 O Type Design Temperature, 'F Design Pressure, psig Vertical, cylindrical 200 150 Volume, ft3 300 Material SS Operating Temperature 'F 100 Operating Pressure, psig 1. 5 - 2 BRS RHT VENT COMPRESSOR Quantity 1 Type Diaphragm O. Design Temperature, 'F Design Pressure, psig 200 150 Design Flow, SCFM Hg 1.0 Material SS Operating Temperature 'F 115 Operating Suction Pressure, psig O Operating Discharge Pressure, psig Operating Flow, SCFM H2 0
2 1.0 0
WAPWR-WM 11.3-22 AUGUST, 1985 3433e:1d
i
, TABLE 11.3-2 j EXPECTED ANNUAL-AVERAGE RELEASE OF AIRBORNE RADIONUCLIDES i
h Gaseous Release Rate (Ci/ year) l Building Ventilation Air Ejector Nuclide GWPS Containment Auxiliary Turbine Exhaust Total Kr-83m 6.9E-10 1.5E-01 3.9E-01 2.5E-05 2.5E-01 7.9E-01 Kr-85m 3.6E-02 1.6E+00 1.8E+00 1.1E-04 1.1E+00 4.5E+00 Kr-85 3.5E+02 5.0E+00 1.2E-01 7.7E-06 7.8E-02 3.6E+02 Kr-87 a. 3.1E-01 1.1E+00 7.0E-05 7.0E-01 2.1E+00 Kr-88 8.2E-05 2.0E+00 3.6E+00 2.2E-04 2.2E+00 7.8E+00 Kr-89 a. 1.2E-03 1.1E-01 6.7E-06 6.8E-02 1.8E-01 Xe-131m 2.4E+01 1.0E+01 3.4E-01 2.2E-05 2.2E-01 3.5E+01 Xe-133m 3.1E-05 2.0E+01 1.8E+00 1.2E-04 1.2E+00 2.3E+01 Xe-133 7.9E+01 2.0E+03 9.1E+01 6.1E-03 6.1E+01 2.3E+03 1 Xe-135m a. 1.5E-02 2.8E-01 1.6E-05 1.6E-01 4.6E-01 i Xe-135 a. 1.0E+01 5.2E+00 3.2E-04 3.3E+00 1.9E+01
} , Xe-137 a. 2.5E-03 1.9E-01 1.2E-05 1.2E-01 3.2E-01 i Xe-138 a. 5.5E-02 9.4E-01 5.2E-05 5.3E-01 1.5E+00 I-131 a. 3.6E-03 3.9E-02 1.0E-03 7.0E-02 1.1E-01 1-133 a. 3.4E-03 5.7E-02 1.1E-03 8.0E-02 1.4E-01 Tritium gaseous release = 840 Ci/yr C-14 gaseous release = 8 Ci/yr Ar-41 gaseous release = 25 Ci/yr Airborne Particulate Release Rate (Ci/ year)
Buildino Ventilation Waste Gas Nuclide System Containment Auxiliary Total Mn-54 4.5E-03 3.3E-06 1.8E-04 4.7E-03 i
Fe-59 1.5E-03 1.1E-06 6.0E-05 1.6E-03 Co-58 1.5E-02 1.1E-05 6.0E-04 1.6E-02 1 Co-60 7.0E-03 5.0E-06 2.7E-04 7.3E-03
, Sr-89 3.3E-04 2.5E-07 1.3E-05 3.4E-04 Sr-90 6.0E-05 4.4E-08 2.4E-06 6.2E-05 Cs-134 4.5E-03 3.3E-06 1.8E-04 4.7E-03 i Cs-137 7.5E-03 5.6E-06 3.0E-04 7.8E-03
- a. Less than 10-10 Ci/yr.
WAPWR-WM 11.3-23 AUGUST, 1985 3433e:1d
l I i 4 ;
I ,
(
TABLE 11.3-3 COMPARIS0N OF CALCULATED MAXIMUM OFFSITE AIRBORNE CONCENTRATION WITH 10 CFR 20 1 ASSUMING EXPECTED FUEL LEAKAGE Maximum Site Maximum Per-4 Total Annual Boundary missible Concen-Release Concentration (a) tration (MPC)(b) . Fraction IsotoDe (Ci/vear) (vCi/ml) (vCi/ml) of MPC H-3 8.4E+2 7. 3 E-10 2.0E-07 3.6E-03 C-14 8.0E+0 7.0E-12 1.0E-07 7.0E-05 Ar-41 2.5E+1 2.2E-11 4.0E-08 5.5E-08 ;
Kr-83m 7.9E-01 6.9E-13 1. 0E-10 6.9E-03 L Kr-85m 4.5E+00 3.9E-12 1.0E-07 3.9E-05 Kr-85 3.6E+02 3.1 E-10 3.0E-07 1.0E-03 j Kr-87 2.1E+00 1.8E-12 2.0E-08 9.0E-05 4 Kr-88 7.8E+00 6.8E-12 2.0E-08 3.4E-04 Xe-131m 3.5E+01 3.1E-11 4.0E-07 7.8E-05 Xe-133m 2.3E+01 2.0E-11 3.0E-07 6.7E-05 Xe-133 2.3E+03 2.0E-09 3.0E-07 6.7E-03 j
O Xe-135 I-131 I-133 1.9E+01 1.1E-01 1.4E-01 1.7E-11 9.6E-14 1.2E-13 1.0E-07 1.0E-10 4.0E-10 1.7E-04 9.6E-04 3.0E-04 i Mn-54 4.7E-03 4.1 E-15 1.0E-09 4.1E-06 i Fe-59 1.6E-03 - 1.4 E-15 2.0E-09 7.0E-07
, Co-58 1.6E-02 1.4E-14 2.0E-09 7.0E-07 Co-60 7.3E-03 6.4E-15 3.0E-10 2.1E-05 l Sr-89 3.4E-04 3.0E-16 3.0E-10 1.0E-06 Sr-90 6.2E-05 5.4E-17 3.0E-11 1.8E-06 Cs-134 4.7E-03 4.1 E-15 4.0E-10 1.0E-05 1 Cs-137 7.8E-03 6.8E-15 5.0E-10 1.4E-05 Total 2.0E-02 i
l 1
i
! a. Based on the annual releases f rom Table 11.3-2 and an assumed X/Q of l 2.75 x 10 -5 sec/m ,
3 l
- b. From 10 CFR 20, Appendix B, Table 11, column 1. I J
WAPWR-WM 11.3-24 AUGUST, 1985 3433e:1d
i 8
, i t
t i
TABLE 11.3-4 ;
a i ESTIMATED ANNUAL DOSES 10 AN j INDIVIDUAL FROM GASEOUS EFFLUENTS [
ASSUMING CONTINUOUS PRESENCE AT THE SITE BOUNDARY l
Calculated 10 CFR 50, Appendix I
! Dose (mrem /vr)(a) Dose Limit (mrem /vr) [
i Whole body dose 1.0 5.0 !
l l l Skin Dose 2.4 15.0 l i
i
.l I
l O
i I
j .
I t 4
i 1
l l
O ,
I l
!O a. Based on the annual releases f rom Table 11.3-2 and an assumed X/Q of 2.75 x 10 -5 sec/m3 . Doses are calculated utilizing the. method i described in Reg. Guide 1.109, Appendix B.
O WAPWR-WM 11.3-25 AUGUST, 1985
- . 3433e
- 1d i
l
'O .
O O
1 FIGURE 11.3-1 SHEET 1 (FOLDOUT)
PROPRIETARY O
O O
MAPWR-WM AUGUST, 1985
i l
lO
- l l
O O
5, .
FIGURE 11.3-1 SHEET 2 (FOLDOUT)
PROPRIETARY O
O O
WAPWR-WM AUGUST, 1985
i 4
l l
11.4 SOLID WASTE PROCESSING SYSTEM ,
1 l
J j The solid waste processing system serves to collect, process, and package l
) radioactive wastes generated as a result of normal plant operation, including l anticipated operational occurrences. The packaged waste is stored until it is j shipped offsite to a licensed burial site.
i The design of the solid waste processing system is the responsibility of the plant specific applicant.
i 11.4.1 Design Bases j The solid waste processing system shall be designed to meet the following i
objectives: ,
A. Provide remote' transfer and holdup capability for spent radioactive i resins from the liquid waste processing and steam generator blowdown i processing systems.
B. Solidify and package spent resins f rom the liquid waste . processing i system and the steam generator blowdown processing system.
l
- C. Solidify, and package liquid waste solutions f rom the chemical drain
! tank, liquid waste evaporator, and boron recycle evaporator.
l l D. Provide a means to semiremotely remove and transfer the spent filter f cartridges from filter vessels to shielded drums in the manner which
! minimizes radiation exposure to operating personnel and the spread of
! contamination.
E. Provide a means for compacting and packaging miscellaneous dry radioactive materials, such as paper, rags, and contaminated clothing.
O '
WAPWR-WM 11.4-1 AUGUST, 1985 3514e:1d
- _ - _ - . _ , - - . _ - - . - - - . _ , - . - - _ - . . - - - - . - . - _ - - - . - - -