ML20030E056
| ML20030E056 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/15/1981 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20030E021 | List: |
| References | |
| NUDOCS 8109170356 | |
| Download: ML20030E056 (4) | |
Text
._
9/15/81 Ull!TED STATES OF CERICA l
fiUCLEAR REGULATORY CO:i'41SSION GEFORE THE ATOMIC SAFETY AND LICEriSillG BOARD In the Matter of
)
)
PEiniSYLVANIA POWER Att0 LIGHT COMPANY
)
Docket tio. 50-387 l
ALLEwiENY ELECTRIC COOPERATIVE, INC, 50-388 (Susquehanna Steam Electric Station.
)
Units 1 and 2)
)
TESTIMONY OF CHARLES LEE MILLER RELATING TO QUAtiTITIES OF RADI0fiUCLIDES IN LIOUID EFFt UFNTS (Contention 2)
Q.
By whom are you employed, and describe the work you perform?
A.
I am employed by the Effluent Treatment Systems Branch, Division of Syste.ns Integration, Office of Nuclear Reactor Regulation, U.S. riuclear Regulatory Connission. A copy of my professional qualifications is attached.
j Q.
Would you describe the scope of the subject matter addressed.in your testimony?
A.
I have been asked to discuss the methodology that was used by the Staff in calculating the source tenns that could be expected from the operation of the Susquehanna Steam Electric Station, and to discuss the results for Co-60 and Cs-137 in liquid effluents.
8109170356 810915 PDR ADOCK 05000387
_T PDR
2
'l
.I i
Q.
How does the NRC calculate source terms and what are they?
A.
The NRC staff uses the BWR-gal,E (3 oiling Water Reactor - Gaseous and Liquid Ef fluent (NUREG-0016)) computer code to calculate plant radioactive effluent source terms.
" Source terms" are the radionuclide species and j
their quantities that comprise the liquid and gaseous effluents from the
{
plant during normal operations incluoing anticipated operational occurren-l ces. The computer code identifies the effluent waste streams in ' boiling-4 water reactors and calculates the estimate of the quantities of radioactive
)
effluents that will be released.
Q.
Shat is the basis of the SUR-GALE computer code?
A.
The BWR-GALE computer code is used by the NRC. Staff to help determine con-formance to 10 CFR Part 50, Appendix I.
It is a mathematical model that calculates the release of radioactive materials in gaseous and liquid effluents and is based on the best available data.
This data is generated from operating reactors, field tests, labcratory tests, and plant specific i
design considerations incorporated to reduce quantitils of radioactive materials released to the environment.
The liquid effluent waste streams 1
identified by the GALE code are consistent..ith those identified in 4
ANSI N197-1976, "Anerican National Standard SWR Liquid Radioactive Waste Process System."
3
}
3 The source terms calculated in the GALE code are based on:
(a) standardized coolant activities derived from the AN3 18.1 Working Group; (b) release and transport mechanisms that result in radioactive matsrials appearing in liquid and gaseous waste stremns; (c) plant specific design features to reduce radioactive materials released; and (d) information received from operating ' plants on radioactive waste stream characteristics and waste treatment equipment performance.
Q.
What are the results of the NRC Staff liquid source term calculations for Co-60 and Cs-137 for the Susquehanna Steam Electric Station?
A.
Table 4.11, " Calculated Releases of Radioactive Materials in Liquid Effluents from Susquehanna" of UUREG-0564, " Final Environmental Statement celated to the Cperation of Susquehanna Steam Electric Station", shows the results obtained from the GALE code.
It shows that, on the average, 0.01 Ci/yr of Co-60 and 0.036 Ci/yr of Cs-137 are estimated to be released in the liquid effluent.
m m
. m...
.m m
. m
/
- /
CllARLES LEE MILLER PROFESS 10!!AL QUAL 2FICAT1014S DIVIS10ft 0F SYSTEMS IriTEGRATION Of flCE OF !;UCLEAR REACTOR REGULATION U.S. TiUCLEAR REGULATORY COMMISS10ft
/
I am currently employed by the U.S.1;uclear My name is Charles Lee Miller.
Regulatory Cor. mission 2s a f;uclear Eogineer, Effluent Treatment Sysicas Branch, Division of Systems Integration Office of fluclear Reactor As such, my duties include participation in safety and Regulation.
environ. ental reviews associated with licensing actions involving the cesign and operati)n of radioactive waste treatment systems of nuclear l
reactor power piants.
I recieved a PhD in Chemical Engineering from the University of fiaryland in August of 1974 and a fiasters Degree in Chemical Engineering from the In 14ay of 1968, I received a University of I4aryland in August of 1971.
B.S. in Engineering from t!idener College.
I am a registered Professional Engineer (District of Columbia).
In 1974, I joined Sechtel Power Corporation in the Gaithersburg, Maryland I was it.volved in office as a Chemical Engineer in their nuclear staff.
the review, design, evaluation and selection of systems and components -
I also was responsible for used for treatment of radioactive wastes.
performing thermal-hjdraulic ana!ysis for loss-of-coolant accidents.
In 1976, I Jcined Science Applications Inc. located in McLean, Va. as My respansibilities included evaluation of Nuclear a Senior Engineer.
1:aste Dispesal Alternatives, Nuclear Facility Safeguards, and Alternative Reprocessing schemes for fluclear Fuel.
I have held my position with the Cormission since April,1980.
e m.
.m m
.