ML19317E939
| ML19317E939 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/23/1972 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19317E930 | List: |
| References | |
| NUDOCS 8001070735 | |
| Download: ML19317E939 (6) | |
Text
L YA &
Y Cm 3.9 RADI0 ACTIVE EFFLUENTS Applicability Applies to disposal of radioactive liquid, and gaseous wastes from the station.
Objective To define the conditions for release of radioactive liquid waste to the Keovee liydro dam ca11 race and radioactive gases to the unit vent to assure that any radioactive material released is kept as low as practicable and, in any event, in within the limits of 10 CFR 20.
Specification 1.9.1 General Equipment installed in the radioactive wasta systems shall be main-tained and used to assure that except under unusual conditions, releases of radioactive materials in effluents will be kept at small fractions of the limits specified in 20.106 of 10 CFR 20.
The Licensee is per-zitted the flexibility of operation, compatibic with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 20.106 of 10 CFR 20.
It is expected that using this operational flexibility under unusual operating conditions the y
Licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.
1.9.2 Liquid Wastes 3.9.2.1 Operating procedures shall be developed and used, and equipment which has been installed to maintain control over radioactive materials in liquid effluents produced during normal reactor operations, including expected occurrences, shall be maintained and used to keep levels of radioactive material in effluents released to unrestricted areas as low as practicable.
Inputs to the low activity waste tank may be released directly to the Keowee tailrace without further processing than the filtration system so long as the affluents &tw ain only trace quantities of radioactive material.
3.9.2.2 Prior to release to the Keowee Hydn a 31 race, two independent samples of liquid wastes shall be aN 1yz d te determine gross beta-gamma and/or isotopic activity concentratiom.
3.9.2.3 Radioactive liquid waste shall be continuously monitored for flow and gross radioactivity concentration during release.
3.9.2.4
'4herein practicable, radioactive waste releases shall be coordi -
nated with normal operation of the Keowe.e Hydro S ution.
\\
3.9-1 8001070 ns
.s-3.9.2.5.
The ralease of radioactive liquid effluents shall be such that the concentration of radionuclides during discharge to tne Kaowee Hydro ta11 race (based on a minimum dilution flow of s,s/
30 CFS or the available flow from the Keowse Hydro Station if operating) does not exceed the limits of 20.106 of 10 CFR 20, Appendix 3. for unrestricted areas.
3.9.2.6.
Under unuadal conditions when waste treatment equipment is inoperable, liquid waste shall be held up for decay for the maximum period practicable prior to release and every reasonable effort shall be made to return any such disabled equipment to its operable conditions before releases are made.
3.9.2.7.
If the limits of Specification 3.9.2.5 cannot be met, radioactive liquid effluents shall not be released.
3.9.2.8.
The continuous water sampler in the Keowee River near the site boundary shall be operable during discharge of liquid waste to the Keowee Hydro dam ca11 race.
If it is inoperable and the waste cannot be held up any longer, grab samples shall be taken in the Keowee River where the continuous sampler is located in order to determine the concentrations of radioactivity in the river during the tacch discharge operation. Refer to Table 4.11-1 for sample frequency and analysis requirements.
3.9.3 Gaseous Wastes 3.9.3.1.
The annual average release rates of gaseous and airborne particulate w.s/
wastes shell be limited in accordance with the following equation:
(4.61 x 10-6 sec/m3 x {Q1/(MPC)i] I 1.0 where Qi is the annual release rate in Ci/see of any radio-nuclide in the gaseous wastes mixtures; (MPC)1 is the permissible concentration for unrestricted areas in units of C1/m3 (pC1/cc=
3 Ci/m ) for any radionuclida taken from Appendix 3, Column 1, 1
Table II of 10 CFR 20; and 4.61 x 10-6 sec/m3 is the long term atmospheric dispersion factor (X/Q), at the exclusion area boundary of 1609 meters for a ground level release.
3.9.3.2.
For purpose of calculating permissible releases by the formula l
in 3.9.3.1, MPC for halogens and particulates with half-lives longer i
than eight days shall be reduced by a factor of 700 from their listed values in 10 CFR 20, Appendix 3, Column 1, Table II.
l
% sl 3.9-2
x-.
3.9.3.3.
During release of radioactive gaseous wastes from the gaseous waste disposal system to the unit vent, the following conditions shall be mat y
a.
The gaseous radioactivity monitor, iodine monitor, and the particulate monitor in the unit vent shall be operable.
b.
The waste gases and particulates shall be passed through the high efficiency particulate filters and charcoal filters provided (except as noted in 3.9.3.9) 3.9.3.4 Purging of the reactor building shall be governed by the following conditions:
Reactor building purge shall be through the high efficiency a.
particulate filters and charcoal filters until the activity concentration is below the occupational limit inside the re-actor building, at which tima bypass may be initiated.
b.
Reactor building purge shall be through the high efficiency particulate filters and charcoal filters whenever irradiated fuel is being handled or any objects are being handled over irradiated fuel in the Reactor Su11 ding.
The limits of 3.9.3.4a and 3.9.3.4.b shall be met or the c.
containment shall not be purged.
3.9.3.5 During power operation, whenever the air ejector off-gas monitor
\\_,
is inoperable, grab samples shall be taken from the air ejector discharge and analyzed for gross radioactivity daily.
3.9.3.6 Potentially highly radioactive gaseous waste from the gaseous waste disposal system and vent headers of unit components shall be provided a minimum holdup of thirty days (except as noted in 3.9.3.7) when the release of the gaseous waste would exceed 1% of 10CTR20 limits as determined by the following equation:
-6
[4.61 x 10 sec/m3 Qi/(MPC)i] 10.01 x
3.9.3.7. Under unusual conditions, gaseous waste may be discharged from the waste gas header directly to the unit vent for a period not to exceed seven days if the holdup system equipment is not available and the releases = set Specification 3.9.3.1 and 3.9.3.3. Every reason-able effort shall be made to re-establish the availability of the holdup system equipment.
3.9.3.8. Under unusual conditions, gaseous radioactive waste from the gaseous disposal system can be released to the unit vent without vaseg passing through the EEPA and charcoal filters if the filter system in inoperable.
This mode of release may not exceed a seven-day period, and the release rate must be within the limits of Specification 3.9.3.1 and 3.9.3.34.
s.
3.9-3 Rev. 19. 5/5/7.*
s, 3,i.3.9. Under unusual conditions, when the filter system is inoperable,
,,,/
gaseous wastes shall be held up for the maximum period practicable prior to release.
Every reasonable effort shall be made to return inoperabis 'ilears en the operabia condition before releases to the envir: 24nt are made.
3.9.3.10 The maximum activity to be co_ntained in one gas holdup tank shall be 1i_mited to 17,200 C1/E.
E will be assumed to be the same as the E of the noble gases in the reactor coolant system as determined in accordance with Table 4,J-3 pf Specification 4.1.2.
3.9.3.11 Gaseous waste releases shall be restricted so as to yield con-centrations in the area of the temporary construction workers' quarters in the east-southeast section of the exclusion area that are no greater than that which could exist at the normal 1609 meter exclusion area boundary.
Bases Waste processing equipment shall be maintained and used in accordance with 10CFR50.36a and administrative procedures developed in accordance with 10CFR50.34a to assure that releases of radioactivity will be maintained as low as practicable with the intent to be less than 1* of the limits of 10CTR20 Appendix 3 Table 2 Column II after dilution,with the total hydro flow occurring during discharge of liquid radioactive waste. Provision is made for flexibility of operation compatible with hesith and safety to be sure that the public is provided a dependable source of power.
Even under s s/
unusual operating conditions, which may temporarily result.in releases higher than usual, the limits of 10CFR20 will still be maintained.
It is not intended that this waste be continually reprocessed.
Such reprocessing would be the prerogative of the licenses.
Unusual operations, as used in these specifications, are those conditions existing when not all processing equipment is operable.
A.
Liquid Wastes Radioactive liquid wastes will be collected in waste storage tanks.
Treatment of liquid wastas for recovery of the water by evaporation and/or ion exchange and disposal of concentrated evaporator bottoma and spent resin as solid wastes will be performed to maintain quantities of radioactive materials released as low as practicable. Contents of the low activity waste tank and the condensate test tank will be mixed and sampled for analysis to determine the resulting concentration upon dilution.
The minimum dilution flow without Kaowee Hydro Station operation is 30 cfs and will be periodically verified.
It is intended where practicable, to coordinate radioactive liquid waste releases with the operation of the Keovee Hydro Station to provide dilution flows greater than 30 efs. However, calculations to determine batch 4
discharge races will be made on the basis of a 30 cfs dilution flow s,/ l or the available flow from the Kaowse Hydro Station if operating.
3.9-4 Rev. 19 5/5/72 (Carry over)
% mar i
Inputs to the low activity waste tank are expected to contain only
- ~'
trace quantities of radioactivity and consequently may be released directly to the Keowse tailrace without further processing than the filters associated with the car.k.
In the event that significant activity, on the order of 2 x 10-8 uCi/ml, is found in the low activity waste tank, the contents will be processed either by evaporators and/or demineralizers. High activity wastes drain to either the miscellaneous waste holdup tank or the high activity waste tank.
j i
The specification regarding returning inoperable equipment to the operable condition is intended to preclude unnecessary delays in recovering from unusual operating conditions in conformance with 10 CFR 50.36a.
j 3.
Gaseous Wastes
?.adioactive gases will be those resulting from the fission process and neutron activation. These gases will be collected in the waste gas tanks from the various liquid storage tanks associated with the reactor, Ganeous wastes in the reactor building atmosphere are released by purging to the unit vent. Any gaseous wastes in the Auxiliary 3uilding atmosphere will be released through the ventilation system to the unit vent which is monitored.
N Temporary construction quarters are located inside the exclusion area. During the period of time that these quarters are in use, administrative procedures will limit releases of gaseous waste in this sector of the exclusion area in accordance w1:h appropriate meteorological restrictions.
In addition to this, these quarters will be monitored to assure that the administrative procedures are effective and that the dose limits prescribed by regulations are not exceedsd.
i The long term atmospheric dilution f actor (X/Q) at the exclusion area boundary of 1609 meters for a ground release as used in this i
specification incorporates results from SF6 (sulfur hexafluoride) gas tracer experiments (see Oconee FSAR Appendix 2A) and includes a 0.53 dilution factor for inversion occurrences at low wind speeds.
The (X/Q) value to be used under Gaseous Wastes in Specification 3.9, is 4.61 x 10-6.
High concentrations of airborne radioac:ivity are not expected in :he containment unless the reactor has significant failed fuel and/or there is significant uncollected primary coolant leakage in the con:ainment.
In order to reduce the amount of radioactivi:y'which l
would be purged to the atmosphere, the containment air will be exhaus:ed I
s.-
\\
3.9-5 Rev. 19 5/5/72 (Carry over)
i-J
~
through h'igh efficiency particulate and charcoal filters until con-tinuous occupancy occupational exposura limits are attained in the containment. After these limits are attained, the maximum concentration of radioactivity at the site boundary would be approximately 0.12% of 10 CFR 20 Limits for unrestricted areas assuming the restrictive at-mosphere diffusion factor applied to the accident analysis (1.16 x 10-4 sec/m). However, containment purging would normally be timed to coin-cide with better atmospheric dispersion conditions.
It is considered reasonable to allow by-passing of the purge filters under these con-ditions since with small concentrations of radioactivity little, if any, discernable health benefit would be achieved by using the filters while the useful life of the filters would be consumed.
In addition, it is anticipated that the containment will be purged only on a periodic basis when personnel are required in the containment.
j
'I 1
3.9-6 Rev. 19 5/5/72 (Carry over)
__