ML20024C755
| ML20024C755 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/08/1983 |
| From: | Snow A DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20024C741 | List: |
| References | |
| NUDOCS 8307130224 | |
| Download: ML20024C755 (7) | |
Text
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C UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION e--
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
DUKE POWER COMPANY, et al.-
)
Docket Nos.
50-413
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50-414 (Catawba Nuclear Station,
)
Units 1 and 2)
)
l AFFIDAVIT OF A. L. SNOW REGARDING PALMETTO ALLIANCE /
CAROLINA ENVIRONMENTAL' STUDY GROUP ALLIANCE CONTENTION 19 1.
My name is A. L.
Snow.
I am employed by Duke Power Company as Design Engineer II.
I have been employed in thi_s position since 1979 and with the Company since 1968 in various engineering assignments.
2.
The purpose of this affidavit is to address DES Contention 19, as it raises questions as to routine releases during normal operations at Catawba.-
My familiarity with this. area stems from experience with system-wide radwaste design review activities including radioactive effluent analysis for normal and accident conditions.
3.
Both liquid and gaseous source terms from spent fuel pool operations are evaluated in the Catawba FSAR (Chapter 11) and in the Catawba ER (Sections 3.5 and 5.2).
The liquid source term results from postulated leaks in the spent fuel cooling system which are collected in the Auxiliary Building floor drain portion of the Liquid Radwaste System.
The gaseous source term (predominantly Tritium) results from evaporation at the spent fuel pool surface which is discharged via the Spent Fuel Pool Ventilation System.
4.
Using the accepted regulatory models suggested in NUREG 0017, ANSI
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v N237-1976, Regulatory Guides 1.109, 1.112 and 1.113 as outlined in
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8307130224 830708 PDR ADOCK 05000413 g
PDR I
C NUREG 0800, Standard Review Plan Sections 11.1, 11.2 and 11.3 and in Regulatory Guide 4.2 Sections 3.5 and 5.2, it has been demonstrated in the FSAR and ER Sections cited in paragraph 3 that the Catawba Station is designed to comply with 10 CFR 20 and 10 CFR 50 Appendix I limits for liquid and gaseous radioactive effluents.
5.~
Section I of 10 CFR 50 Appendix I states.in part that " Design objectives and limiting conditions for operation coriforming to the guidelines of this appendix shall be deemed a conclusive showing of compliance with 'as low as is reasonably achievable' [ALARA) requirements of 10 CFR 50.34a and 50.36a."
The Catawba FES concludes that doses are "well below the Appendix I design ol..yctive values....."
FES Section 5.9.3.2 6.
The referenced evaluations include consideration of Catawba and non-Catawba (i.e., Oconee and McGuire) spent fuel.
These evaluations reveal that spent fuel operations do not contribute significantly to Catawba station releases.
7.
Both Applicants and the NRC staff's evaluations bound the Oconee and i
McGuire spent fuel contributions to Catawba Station effluents.
This is because Oconee or McGuire spent fuel which has been allowed to decay prior to postulated transshipment to the Catawba pool does not contribute significantly to either liquid or gaseous releases.
This is due to the decay reduction in fuel gap inventory and the low temperature condition l
V of the fu el.'
Therefore, the environmental costs of storage of non-Catawba spent fuel at Catawba have been evaluated in the referenced evaluation reports and found in compliance with applicable regulations.
_. 8.
In_... conclusion, since (1) regulatory compliance with ALARA is demonstrated with respect to station releases, and (2) spent fuel pool operations are an insignificant contritIutor to these station releases and f-
C (3) McGuire and Oconee contributions to the Catawba spent fuel pool
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releases are insignificant, it can be stated that the environmental impact of McGuire and Oconee spent fuel at Catawba is likewise insignificant.
I, A. L.
Snow, of lawful age, being first duly sworn, state that I have reviewed the foregoing affidavit, and that the statements contained therein.are 4
true and correct to the best of my knowledge and belief.
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A. L. Snow STATE OF NORTH CAROLINA County of Mecklenburg Subscribed and sworn to before me this Pth day of July,1983.
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, DUKE POWER COMPANY 4
ARTHUR LOWELL SNOW
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EDUCATION:
B.S., Nuclear Engineering, University of Tennessee M.E., Mechanical Engineering, University of South Carolina Additional Courses:
Graduate Course Work in Mechanical Engineering toward PhD 1
CERTIFICATIONS / PROFESSIONAL AFFILIATIONS b
Professional Engineer - North Carolina 7397
- South Car 611na 6145 Menber of the American' Nuclear Soc'iety YEARS EXPERIENCE:
15 i
SUMMARY
OF PERTINENT EXPERIENCE Supervisor, Mechanical and Nuclear Division, Nuclear Activities - All Duke Nuclear Power Stations:
System-wide radwaste design review activities, licensing activities, probabilistic risk assessment and safety reviews, evaluation of ' nuclear accident scenario and corrective actions, radioactive
= ffluents analysis, and nuclear fuel criticality analysis for spent fuel e
storage designs.
d5 l
- Supervisor, Ploe Support / Restraint Design - Design, engineering and construct-ability of ASME lit and B31.1.0 piping support / restraints for Catawba Nuclear Station.
Development of design criteria and specifications, technical i
contract administration, scheduling and coordination of design activities.
i Assistant Design Engineer - Design and engineering of nuclear fluid process systems for Catawba. Nuclear Station, review of operating procedures, testing l
procedures, start up assistance, operating parameters and cost evaluations, i
Assistant Design Engineer - Devel6pment of computer codes for radiation shielding, radioactive liquid and gaseous discharge.
Preparation of Safety An'alysis Reports / Environmental Reports. Radiation shielding designs.
t All this work for Oconee, McGuire and Catawba Nuclear Stations, y
EXPERIENCE:
DUKE POWER COMPANY since 1968 1979 to Design Engineer 11 - In charge of Nuclear Sub-Group Present responsible for: system-wide radwaste design review activities; technical interface for Mechanical / Nuclear Division with licensing, probabilistic risk assessment an'd safety review groups; radioa'ctive effluent analysis
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for normal and accident conditions; nuclear fuel crit-Icality and generic engineering activities.
Generic
. engineering activitieg, include steam generator. chemical cleaning, technical review of responses to TMI concerns, other regulatory and quality assurance matters.
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ARTHUR LOWELL SNOW (Cont'd) m 1977-1979 Design Engineer / Assistant Design Engineer - In responsible charge of Pipe Support / Restraint Group for Catawba. Multi-discipline group of Duke and contract personnel included clerks, draf tsmen, designers, Mechanical and Civil Engineers (B.S., M.S., and PhD's). Activities included setting up Initial organization, design criteria and specification preparation, contract administration, scheduling, interface with Construction Department, and other Design groups.
Group produced in excess.of 30,000 designs for ASME Section til, Class 2 and 3, and ANSI B31.1.0 piping systems and supports for HVAC seismically designed ducting.
1972-1977 Assistant Design Engineer - Responsible charge of fluid systems design for all Catawba nuclear process systems.
Supervised preparation of Flow Diagrams, Design Criteria, System Descriptions, Data Sheets fer Mechanical Equipment, Safety Analysis Report preparation for Mechanical / Nuclear systems. Developed operating parameters, costs, review of testing / operating procedures, piping system start up assistance.
1968-1972 Assistant Design Engineer / Associate Engineer /Jr. Engineer -
Responsible charge of Radiation Analysis Group. Activities
. included direct effott and supervisory responsibility for:
' development of radia't' ion shielding computer codes, develop-ment of radioactive liquid and gaseous discharge computer I
codes, cost. evaluation of Turbine-Generator bids using part load heat rates, Sa'fety Analysis Report and Environmental Report preparation, response to NRC'(then AEC) questions, and appearances before ACRS and NRC Staff for Oconee, McGuire and Catawba Nuclear Stations, design radiation shielding for McGuire and Catawba.
PUBLICATIONS:
" Criteria For Evaluation of Interim R da waste Solidification Systems" '83 Waste Management Symposium, Tuscon, Arizona 2/28/83.
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,,g c,o;mEWOWES3 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD J
-.0;I f
In the Matter of
)
)
.2 DUKE POWER COMPANY, et al.
)
Docket Nos. 50-413 '
)
50-414 (Catawba Nuclear Station,
)
Units 1 and 2)
)
CERTIFICATE OF SERVICE I hereby certify that copies of " Applicants' Motion for Summary Disposition" in the above-captioned matter have been served upon the following by deposit in the United States mail this 8th day of July, 1983:
James L.
Kelley, Chairman Richard P. Wilson, Esq.
Atomic Safety and Licensing Board Assistant Attorney General Panel State of South Carolina U.
S. Nuclear Regulatory Commission P. O. Box 11549 Washington, D. C.
20555 Columbia, South Carolina 29211 Dr. A. Dixon Callihan Robert Guild, Esq.
Union Carbide Corporation Attorney-at-Law s
P. O. Box Y 4
P. O.
Box 12097 Oak Ridge, Tennessee 37830 Charleston, South Carolina 29412 Dr. Richard F. Foster Palmetto Alliance P. O. Box 4263 2135 Devine Street I
Sunriver, Oregon 97702 Columbia, South Carolina 29205 Chairman Jesse L.
Riley Atomic Safety and Licensing 854 Henley Place Board Panel Charlotte, North Carolina 28207 U '.
S. Nuclear Regulatory Commission Washington, D. C.
20555 Henry A.
Presler 945 Henley Place Chairman Charlotte, North Carolina 28207 Atomic Safety and Licensing
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Appeal Board Carole F.
Kagan, Attorney U.
S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D. C.
20555 Board Panel U.
S. Nuclear Regulatory George E.
Johnson, Esq.
Commission Office of'the Executive Legal Director Washington, D.
C.
20555
..U.
S._. Nuclear Regulatory Commission Washington, D. C.
20555 e
n..
J. Michael McGarry, III, Esq.
Anne W.
Cottingham, Esq.
Debevoise & Liberman 1200 Seventeenth Street, N.W.
Washington, D. C.
20036 Scott Stucky Docketing and Service Section U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 h
Albert V.
Car. Jr.
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