ML19270G913
| ML19270G913 | |
| Person / Time | |
|---|---|
| Site: | 07002623 |
| Issue date: | 05/07/1979 |
| From: | Hoefling R, Spitalny B NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS), NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | |
| Shared Package | |
| ML19270G911 | List: |
| References | |
| NUDOCS 7906210120 | |
| Download: ML19270G913 (5) | |
Text
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UNITLD STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
DUKE POWER COMPANY Docket No. 70-2623 (Amendment to Materials License
)
SNM-1773 for Oconee Nuclear Station
)
Spent fuel Transportation and Storage )
at McGuire Nuclear Station)
)
NRC STAFF RESPONSE TO CAROLINA ENVIRONMENTAL STUDY GROUP INTERR0GATORY NO. 120 Intprrogatory 120 Assume a fuel assembly with normal burn and 270 days storage.
Assume an NFS-4 cask.
The cask has been normally filled with the assembly and fuel pool water, closed, and 25 gallons of water drained.
It is properly placed on the trailer.
Assume the drain valve for the internal water is opened and left open for an indefinite period of time. Assume that due to the combination of 80 psi air pressure, vapor pressure, and boiloff that all liquid water leaves the assembly chamber.
Provide the time temperature function until steady state is reached of the fuel pellets ir, the hottest fuel rod, the coolest fuel rod, the average fuel rod.
Provide the corresponding fuel rod sheath temperatures.
Provide the number of sheaths which will have failed by the time steady state is reached.
Will fuel melt have occurred at initial steady state?
Steady state in this context means the maximum average temperature attained by the fuel elements.
Catalog, in both mass and curies, the radionuclides which will be released.
Answer:
The request by CESG fails to recognize that each cask design is limited to a specific quantity of internal decay' heat.
In the case of the NFS-4, this limit is 11.5 kw per package.
This maximum heat load limit results in maximum fuel clad temperatures well below the melting point of the stainless steel and zironiun alloys (Zircaloy-2 and Zircaloy-4) 2240.530 7 906 210/Rd -
which are used for cladding.
It should also be noted that the scenario suggested in this interrogatory would not result in a loss of coolant, due to redundant safety features incorporated in the design of the package.
A quick-disconnect valve which is downstream of the drain valve closes automatically.
0 For conditions of a 130 F day with solar heating of the cask and 11.5 kw 0
internal heat, the maximum fuel pin temperature will be about 360 F.
If the coolant water is lost, this maximum fuel pin temperature could be U
exp,ected to reach 810 F.
If'both the coolant water and shield water were lost, the thermal resistance of the cask would increase resulting 0
in approximately a 142 F increase in the cavity wall temperature.
This U
would result in a maximum fuel pin temperature of 982 F.
These temperatures are all well below those which would cause the fuel to melt or significant creep rupture of the fuel rods to occur.
The Staff has not performed all calculations requested in that the bounding temperatures do not warrant such consideration.
2240 331
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
DUKE POWER COMPANY
)
Docket No. 70-2623 (Amendment to Materials License SNM-1773 for Oconee Nuclear Station
)
Spent Fuel Transportation and Storage )
at McGuire Nuclear Station)
)
AFFIDAVIT OF BRETT S. SPITALNY I, Brett S. Spitalny, am employed by the Nuclear Regulatory Commission in the Office of Nuclear Material Safety and Safeguards, Fuel Reprocessing and Recycle Branch, as the project manager for the amendment to materials license SNM-1773.
I have prepared, or assisted in the preparation of, the response to Carolina Environmental Study Group Interrogatory No.120.
These. answers are true and correct to the best of my knowledge.
S At W. T n Y ~,,
Bret't ~S. Spitalny
/
Subscribed and sworn to before me this 7 78 day of MAf
,1979.
O Notary Feblic My Coi;nissim Expires: I-
~,. f jj!fc?,
O V
UNITED STATES OF AMERICA NUCLEAR PEGULATORY COMMISSION BEFORE THE ATOMIC SAFETY aND LICENSING BOARD In the Matter of DUKE POWER COMPANY Docket No. 70-2623
)
(Amendment to Materials License
)
SNM-1773 for Oconee Nuclear Station
)
Spent Fuel Transportation and Storage )
at McGuire Nuclear Station)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF RESPONSE TO CAROLINA ENVIRON-MENTAL STUDY GROUP INTERROGATORY NO.120" and " AFFIDAVIT OF BRETT S.
SPITALNY" dated May 7, 1979 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, through deposit in the Nuclear Regulatory Commission's internal mail system, this 7th day of May,1979.
- Marshall E. Miller, Chairman Ms. Brenda Best Atomic Safety and Licensing Board Carolina Action U.S. Nuclear Regulatory Commission 1740 E. Independence Blvd.
Washington, D. C.
20555 Charlotte, North Carolina 28205 Dr. Cadet H. Hand, Jr., Director Anthony Z. Roisman, Esq.
Bodega Marine Laboratory Natural Resources Defense Council University of California 917 - 15th Street, N.W.
P.O. Box 247 Washington, D. C.
20555 Bodega Bay, California 94923 Shelley Blum, Esq.
- Dr. Emmeth A. Luebke 418 Law Building Atomic Safety and Licen,ing Board 730 East Trade Street U.S. Nuclear Regulatory Commission Charlotte, North Carolina 28202 Washington, D. C. 20555 J. Michael McGarry, III, Esq.
W. L. Porter, Esq.
Debevoise & Liberman Associate General Counsel 1200 Seventeenth Street, N.W.
Legal Department Washington, D. C.
20036 Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 2240
.333
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- Atomic Safety and Licensing Appeal Board Mr. Geoffrey Owen Little U.S. fluclear Regulctory Connission P. O. Box 2501 Washington, D.C.
20555 Davidson College Davidson, fl.C.
28036
- Atomic Safety and Licensing Board Panel U.S. lluclear Regulatory Conmission Washington, D. C.
20555
- Docketing and Service Section U.S. iluclear Regulatory Commission Washington, D. C.
20555 Mr. Jesse L. Riley, President Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Richard P. Wilson, Esq.
Assi,stant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 d Y Ricfiard K. Hoefling '
()
G~
Counsel for flRC Staff 2240
.334
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