ML18012A623
| ML18012A623 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/18/1997 |
| From: | Le N NRC (Affiliation Not Assigned) |
| To: | Robinson W CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-M98207, NUDOCS 9704240135 | |
| Download: ML18012A623 (6) | |
Text
April 18, 1997 Hr.
W.
R. Robinson, Vice President Shearon Harris Nuclear Power Plant Carolina Power
& Light Company Post Office Box 165 - Hail Code:
Zone 1
New Hill, North Carolina 27562-0165
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON SPENT FUEL CASK DROP DESIGN AND LICENSING BASIS ISSUES AT THE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. H98207)
E
Dear Hr. Robinson:
By letter dated March 14,
- 1997, you submitted for NRC review and approval an unreviewed safety question regarding the spent fuel cask drop design and its related licensing basis issues along with your proposed Final Safety Analysis Report revisions that would incorporate the results of the cask drop analysis and dose assessment.
During the staff review of the above
- request, we have identified the need for additional information as indicated in the enclosed request for additional information (RAI).
Your written response to the RAI is expected within 30 days of the receipt of this letter.
Should you have any questions, do not hesitate to contact me at (301) 415-1458.
Sincerely, (Original Signed By)
Ngoc B. Le, ProjectManager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc w/enclosure:
See next page Distribution
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Mr. W.
R. Robinson Carolina Power
& Light Company Shearon Harris Nuclear Power Plant Unit 1
CC:
Mr. William D. Johnson Vice President and Senior Counsel Carol,ina Power
& Light Company Poqt Office Box 1551
- Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, North Carolina 27562-9998 Ms. Karen E.
Long Assistant Attorney General State of North Carolina Post Office Box 629
- Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer 11649
- Columbia, South Carolina 29211 Regional Administrator, Reg'ion II U.S. Nuclear Regulatory Commission 101 Marietta St.,
N.W. Suite 2900 Atlanta, Georgia 30323 Mr. Mel Fry, Acting Director Division of Radiation Protection N.C. Department of Environment, Health and Natural Resources 3825 Barrett Dr.
- Raleigh, North Carolina 27609-7721 Mr. T. D. Walt Director Operations
& Environmental Support Department Carolina Power
& Light Company 412 S. Wilmington Street
- Raleigh, North Carolina 27601 Mr. Bo Clark Plant General Manag'er Harris Plant Carolina Power
& Light Company Shearon Harris Nuclear Power Plant P.O.
Box 165 New Hill, North Carolina 27562-0165 Mr. J.
W. Donahue Director of Site Operations Carolina Power
& Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, MC: Zone 1
New Hill, Nor th Carolina 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC Post Office Box 29520
- Raleigh, North Carolina 27626 Chairman of the North Carolina Utilities Commi ss ion Post Office Box 29510 Raleigh, North Carolina 27626-0510 Ms.
D.
B. Alexander, Supervisor Licensing/Regulatory Programs Carolina Power
& Light Company
'hearon Harris Nuclear Power Plant P. 0.
Box 165, Mail Zone 1
New Hi 1 1, North Carol ina 27562-0165 Mr. Stewart Adcock, Chairman Board of County Commissioners of Wake County P. 0.
Box 550 Raleigh; North Carolina 27602 Margaret Bryant Pollard, Chairman Board of County Commissioners of Chatham County P. 0.
Box 87 Pittsboro, North Carolina 27312 Mr. Milton, Shymlock U.S. Nuclear Regulatory Comm.
101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia
,30323-0199
RE VEST FOR ADDITIONAL INFORMATION ON SPENT FUEL CASK DROP UNREVIEWED SAFETY UESTION FOR THE SHEARON HARRIS NUCLEAR PLANT UNIT NO.
1 Justify that your fuel handling operation, as described in the March 14, 1997, request (specifically, the removal of valve box covers outside of the emergency ventilation envelope) meets the requirements for "appropriate containment, confinement, and filter systems" in 10 CFR Part 50 Appendix A, GDC 61.
Provide a-full description of the radiological consequence
- analysis, including; 1.
What was the maximum number of bundles assumed in the casks
'as the dispersal of the crud inside the cask assumed'.
What was the power history and decay time assumed for the fuel bundles'as fresh spent fuel (e.g.,
minimum decay allowed by Tech.
Specs.
prior to loading into cask) assumed'f not, what decay time(s) were assumed'rovide justification that th'is is a conservative and bounding assumption.
Was a radial peaking factor of 1.65 applied to the reactor power
- assumed, as specified in Position C. l.e of Regulatory Guide 1.257 If not, what peaking factor(s) were appliedf Provide justification that this -is a conservative
.and bounding assumption.
3.
The March 14, 1997, request states that "fuel rod damage occurs and maximum available gap activity is released."
Were lOOX of the fuel rods in the core assumed damaged by the dropt If not, what X damage was assumed'rovide justification that this is a conservative and bounding assumption.
Mere the assumptions in Reg.
Guide 1.25, Position C. l.d 5 f, used to determine the assumed fuel gap inventory? If not, specify the gap inventory used and describe the assumptions use to determine it.
Provide justification that the assumed inventory was determined with conservative and bounding assumptions.
- 4. Describe the dose calculational model used.
What release rate and release duration were assumed'hat breathing rate(s) were assumed for individuals at the locations of interest7
The March 14, 1997, request states that X/g "values used for other FSAR I'Final Safety Analysis Report]
Ch.
15 analysis are applied."
Give the specific X/g values used and the applicable FSAR reference: