ML19221A298
| ML19221A298 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/22/1979 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19221A296 | List: |
| References | |
| NUDOCS 7905210230 | |
| Download: ML19221A298 (4) | |
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1 TO:
Victor Stello, Jr.
FROM:
John T.
Collins
SUBJECT:
RADIOLOGICAL ASSESSMENT CF OPERATION OF OTSG-S IN SOLID MODE The radiological consequerices of coeration of CTSG-B in a solid mode have been identified and eval"ated as follows:
Radioactive Maierial Inventorv The water volume of the solid systen was calculated to be 28,000 8
gal or 1.1 2 10 cc.
Based on a steam generator water sample taken on 4/19/79, the inventory of the principal radionuclides in the system is:
1-131-59 Ci Cs-134:
0.57 Ci Cs-136:
0.52 Ci Cs-137:
2.6 Ci Princioal Leakace Paths The principal potential leakage path for escape of radioactive materials from the system to the environment is the release of gases evolved as the system s=ter flow passes through the main condenser, with the gases being removed from the system by the mechanical vacuum pumps.
Liquid leakage, such as may be expected from pump seals and valve stems, will be collected in the turbine building sumps.
I f the solid mode is used, all turbine building sumps will be aligned with the condensate polishing regeneration sump and then routed to the Miscellaneous Water Holdup Tank for processing, if required prior to discharge.
159 029 D
. Gaseou,f-fluents Non-condensible gases will be removed f rom the main condenser by the mechanical vacuum pumps.
Output from the pumps is ducted through a treatment sys tein cons ist ing, sequentially, of a HEPA filter, charcoal adsorber, and HEPA fil ter, before being vented to the atmosphere through the Unit 2 vent.
All Unit 2 vent releases are monitored by the plant vent monitor, HPR-219 for noble gases, radiciodine and particulates.
Potential releases via this pathway were calculated, based on the following assumptions:
1.
1-131 concentration in the solid system is 0.54 uci/cc (based or, h/19/79 inventory of 59 ci).
2.
Pa rt i t ion Factor in the steam generator is 1, since no steam generatio'n occurs, i.e.,
all activity present would carry-over to the condenser.
3 No platcout in the bypass lines to the condenser.
4 Although in the water-solid condition little evaporation would occur, evaporation in the main condenser is assumed to be of 1% of flow.
At the expected flow of 1,500 gpm; evaporation is 15 gpm.
159 030
e 5 Partitioning of iodine to the vapor phase during evaporation of 0.0001 (PF = 0.0001).
6.
Efficiency of charcoal adsorber of 99% for ra d i c i od i r.e.
7 Plant vent total flow of 87,000 cfm.
CAL CUL ATI ON Release = 15 cal x 3.8 x 103 10-4 x 0.c4 uCi/cc cc x min gal
- 3.1 uCi/ min Treatment DF of 100 3.1
= 0.031 uCi/ min 100 Stack fl ow 87,000 cfm:
Cmc
= 0.031 uCl/ min
= 1.3 x 10*II uCi/cc ft / min x 2.83 x 104 cc/ft) 3 8.7 x 104 This result, 13% of unrestricted MPC at the plant vent, assumes that a constant source of I leaks from the primary system to the secondary to replentish the I lost by radioactive decay and discharge.
Even if a 20 gallon / day leak were to occur in the steam gene rator wi th an initial primary I level of 3 x 103 uCi/ce, the contribution to the I release at the plant vent would not exceed 2 x MPC.
At off-site locations, the concentrations would be less than 0.2% of MPC.
Summary Operation with B steam generator in the solid mode, with cooling f l ow through bypass to the main condenser, would resul t in generation 159 03i
_4_
of additional iodine releases to the Unit 2 vent.
These releases, however, are calculated to be less than 2 x MPC at the release point, and less than 0.2% of MPC of f-site even for significant steam generator leakage from the primary system.
Liquid leakage is expected to occur; however, such leakage is expected to be of small volume and would be collected for processing within existing unit collection and processinc systems.
No envirnnmental impact would be expected from liquid leakage.
C W
John T. Collins 159 032