ML20010F379
| ML20010F379 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/02/1981 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010F375 | List: |
| References | |
| NUDOCS 8109100112 | |
| Download: ML20010F379 (7) | |
Text
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7 bHITED STATES OF AMERICA HUCLEAR REGULATORY CUNMISSION BEFORE THE ATOMIC SAFETY AND LICEUSING BOARD In the Matter of
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PEldSYLVANIA POWER AliD LIGHT COMPANY
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Docket No. 50-387 ALLEGtiEHY ELECTRIC COOPERATIVE INC.
50-388 (Susqu hanna Steam Electric Station.
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Units 1 and 2)
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AFFIDAVIT OF CHARLES LEE MILLER I, Charles Lee Miller, being duly sworn, depose and state:
Q.
By whom are you employed, and describe the work you perform?
A.
I am employed by the Effluent Treatment Systems Branch, Division of Systems Integration, Office of Nuclear Reactor Regulation, U.S. Nuc. lear 9,egulatory Commission. A copy of my professional qualifications is attached to this affidavit.
O.
Have you read " Applicants' Motion for Summary Disposition of Contention 2 (Het'th Effects of Low-Level Radiation and Other Discharges frorc the Facility)", filed August 13, 1981, and the documents attached theretc, including the affidavit of John C. Dodds?
A.
Yes.
Q.
Would you describe the scope of the subject matter addressed in your affidavit?
A.
I have been asked to determine if the information presented in the
" Applicants' Motion for Summary Disposition of Contention 2" Lad the documents attached thereto, are correct, and if the NRC supports the applicants position.
I have also been asked to discuss the methodology that was used by NRC in calculating the source terms 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.
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Are the aforementioned documents submitted by the applicant correct and q.
do you support the applicant's position?
A.
The applicant has stated on the first page of the " Applicants' Statement Of Material Facts As To Which There Is fio Genuine Issue To Be Heard (Contention 2)(Source Term)" that the " GALE" computer code was developed for the fiRC by Battelle Pacific florthwest Laboratcries. This statement is in error. The code was developed by fiRC staff. The other information presented by the applicant is correct and,the liRC staff supports their position.
Q.
How does the fiRC calculate source terms and what are they?
A.
The fiRC staff uses the BWR-GALE (Boiling Wr;1r Reactor _ Gaseous and Liquid Effluent (iiUREG-0016)) computer code to calculate plant radioactive effluent source terms. " Source terms" are the radionuclide species and their gaantities that comprise the liquid and gaseous effluents from the plant during normal operations including anticipated operational occurren-The computer code identifies the effluent waste streams in boiling ces.
water reactors and calculates the estimate of the quantities of radioactive effluents that will be released.
7 Q.
What is the basis of the Bl!R-G LE computer code?
A.
The BWR-GALE computer code is used by the flRC Staff to help determine con-l fermance to 10 CFR Part 50, Appendix 1.
It is a mathematical model that l
calculates the release of radioattive materials in gaseous and liquid l
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effluents and is Sased on the best available data. This data is generated from'* operating reactors, field tests, laboratory tests, and plant specific design considerations incorporated to reduce quantities of radioactive materials released to the environment. The liquid effluent waste streams identified by the GALE code are consistent with those identified in ANSI N197-1976, "American National Standard BWR Liquid Radioactive Waste Process System."
The source terms calculoted in the GALE code are based on:
(a) standardized coolant activities derived from the ANS 18.1 Working Group; 1
(b) release and transport mechanisms that result in radioactive materials appearing in liquid and gaseous waste streams; I
(c) plant specific design features to reduce radioactive materials released; and (d) information received from operating plants on radioactive wasta stream characteristics and waste treatment equipment performance.
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Q.
What are the results of the NRC Staff liquid source term calculations
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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 NUREC-0564, " final Environmental Statement related to the Operation of Susquehanna Steam Electric Station", shows the results obtained from the GALE code.
It shows that, on the average,
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0.01 Ci/yr of Co-60 and 0.036 Ci/yr of Cs-137 are estimated to be released in the liquid effluent. These values are slightly higher than 0
those reported by the applicants, but are of the same order of magnitude.
I I hereby certify that the above statements are true and correct to the best of my knowledge and be. lief.
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l)r. Charles Lee Miller Subscribed and sworn to before me this Ond day of September, 1981.
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Notary Public-()
My Ccnaission expires: C
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Cl{ARLES LEE Milt.ER PR0 FESS 10!!AL QUALIFICAT10f45 OIVIS10l10F SYSlEMS I!iTEGRATION OFFICE OF I;UCLEAR REACTOR REGULATION U.S.1lUCLEAR RLGULATORY C0:*.!ilSS10ft_
I am currently employed by the U.S. Huclear 1:y name is Charles Lee l'illcr.
Regulatory Connission as a f;uclear Engineer, Ef fluent Treatment Systc Cranch, Division of Systems Integration, Office c,f fluclear Reactor As such, my duties include participation in safety and cnvirona. ental reviews associated with licensing actions involving the Regulation.
design and operation of radioactive waste treatment systems of nuclear reactor por;er plants.
I recieved a T9D in Chemical Engineering from the University of Maryl in August of 1974 and a !! asters Degree in Chemical Engineerir.g from Ur.iversity of Maryland in August of 1971.
I am a registered Professional B.S. in Engineering from Widener College.
Engineer (District of Columbia).
In 1974, I joined Bechtel Power Corpcration in the Gaithersburg, Mar I was involved in office as a Chemical Engineer in their nuclear staff.the re ts used for treatment of radioactive wastes.
perfoiming thermal-hydraulic analysis for loss-of-coolant accidents.
In 1976, I jcined Science Applications Inc. located in McL tive 1:aste Disposal Alternatives, fluclear facility Safcguards, and Alterna a Senior Engineer.
Reprocessing schemes f or fluclear Fuel.
I have held my position <th the Conraission since April,1980.
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UNITED STATES OF At! ERICA NUCLEAR REGULATORY COMllISSION BEFORE THE AT0rflC SAFETY LICENSING BOARD In the Matter of PENNSYLVANIA POWER AND LIGHT CO.
Docket Nos. CO-387 50-388 ALLEGMENY ELECTRIC COOPERATIVE, INC.
(Susquehanna Steam Electric Station, Units 1and2)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF RESPONSE SUPPORTING APPLICANTS' MOTION FOR SU'CiARY DISPOSITION OF CONTE l;f!ON 2 (SOURCE TERM)" and
" AFFIDAVIT OF CHARLES LEE MILLER" in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class or, as indicated by an asterisk, by deposit in the Nuclear Regulatory Commission's internal mail system, this 8th day of September,1981:
James P. Gleason, Chairman Dr. Judith H. Johnsrud Administrative Judge Co-Director 513 Gilnoure Drive Environmental Coalition on Silver Sprir.g MD 20901 Nuclear Power 433 Orlando Avenue
- Mr. Glenn 0. Bright State College, PA 16801 Administrative Judge Atomic Safety and Licensing Board fir. Thomas M. Gerusky, Director U.S. Nuclear Regulatory Cannission Bureau of Radiation Protection 8
Washington, DC 20555 Department of Environmental Resources Commonwealth of Pennsylvania Dr. Paul W. Purdom P.O. Box 2063 Administrative Judge Harrisburg, PA 17120 245 Gulph Hills Road Radnor, PA 19087 Ms. Colleen Parsh Box 538A, RD#4 Jay Silberg, Esq.
Mountain Top, PA 17120 Shaw, Pittman, Potts and Trowbridge 1800 ft Street, N.W.
Mr. Thomas J. Halligan Washington, DC 20036 Correspondent: CAND P.O. Box 5 Bryan A. Snapp, Esq.
Scranton, PA 18501 Pennsylvania Power & Light Company o
Two North Ninth Street Allentown, PA 18101
- Richard S. Salzman, Esq., Chairman, Susquehanna Environmental Administrative Judge Advocates Atomic Safety and Licensing Appeal Board c/o Gerald Schultz, Esq.
U.S. fluclear Regulatory Commission P.O. Box 1560 Washington, DC 20555 Wilkes-Barre, PA 18703
- Dr. Jolin H. Buck, Administrative Judge Mr. Robert M. Gallo Atomic Safety and Licensing Appeal Board Resident Inspector U.S, fluclear Regulatory Commission P.O. Box 52 Wasaington, DC 20555 Shickshinny, PA 18655
- Mr. Thomas S. Moore, Administrative Judge Robert W. Adler Atomic Safety and Licensing Appeal Board Dept. of Environmental Resources U.S. Nuclear Regulatory Commission 505 Executive House Washington, DC 20555 P.O. Box 2357 Harrisburg, PA 17120
- Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Mr. DeWitt C. Smith, Director Washington, DC 20555 Pennsylvania Emergency Management Agency
- Atomic Sa.ety & Licensing Appeal Board Transportation and Safety Building Panel Harrisburg, PA 17120 U.S. Nuclear Regulatory Commission Washington, DC 20555
- Secretary U.S. Nuclear Regulatory Commission ATTN: Chief, Docketing & Service Branch Washington, DC 20555 GC Offd i
h Lacinda low Swartz Cour:3el for NRC Staff
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