ML14183A859
| ML14183A859 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/12/1998 |
| From: | James Shea NRC (Affiliation Not Assigned) |
| To: | Keenan J CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-MA0652, TAC-MA652, NUDOCS 9805190339 | |
| Download: ML14183A859 (4) | |
Text
M. i..
Keenan, Vice Prident Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI); REQUEST FOR STAFF REVIEW OF SPENT FUEL CASK DROP, H. B. ROBINSON, UNIT 2 (TAC NO.
MA0652)
Dear Mr. Keenan:
By letter dated August 27, 1997, Carolina Power and Light Company requested that the staff review an unreviewed safety question regarding a potential spent fuel shipping cask drop at H. B. Robinson Steam Electric Plant, Unit No. 2. We have conducted a preliminary review of your application and determined that additional information is needed to complete the review.
The staff's RAI is enclosed.
You are requested to provide the information within 30 days from receipt of this letter.
If you have any questions regarding this request, please do not hesitate to contact me at (301) 415-1428.
Sincerely, (Original Signed By)
Joseph W. Shea, Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
ock~t]Eile.
REmch, PERB LPlisco, RII MShymlock, RII PUBLIC PDII-1 Reading RPedersen, PERB OGC JZwolinski ACRS FILENAME -,G:\\ROBINSON\\ROB652.RAI OFFICE PM:PDI 1 LA:PDIl-1 (A)PD:PDII-1 NAME JSheP I,
Dunnington PTKuo DATE
(/(9 5///198
.(
8 COPY Yes/No e No Yes/No OFFICIAL RECORD COPY 9805190339 980512 PDR ADOCK 05000261
[
I P
Mr. J. S. Keenan H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr. William D. Johnson Mr. Mel Fry, Director Vice President and Senior Counsel N.C. Department of Environment Carolina Power & Light Company and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721 Ms. Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Max Batavia, Chief H. B. Robinson Steam Electric Plant South Carolina Department of Health 2112 Old Camden Road Bureau of Radiological Health Hartsville, South Carolina 29550 and Environmental Control 2600 Bull Street Regional Administrator, Region II Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Ms. D. B. Alexander Atlanta, Georgia 30303 Manager Performance Evaluation and Mr. J. W. Moyer Regulatory Affairs CPB 9 Plant General Manager Carolina Power & Light Company Carolina Power & Light Company Post Office Box 1551 H. B. Robinson Steam Electric Plant Raleigh, North Carolina 27602-1551 Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550 Mr. Milton Shymlock U. S. Nuclear Regulatory Commission Public Service Commission Atlanta Federal Center State of South Carolina 61 Forsyth St., SW, Suite 23T85 Post Office Drawer 11649 Atlanta, Georgia 30303 Columbia, South Carolina 29211 Mr. T. M. Wilkerson Manager - Regulatory Affairs Mr. H. K. Chernoff Carolina Power & Light Company Supervisor, Licensing/Regulatory Programs H. B. Robinson Steam Electric Plant, Carolina Power & Light Company Unit No. 2 H. B. Robinson Steam Electric Plant, 3581 West Entrance Road Unit No. 2 Hartsville, South Carolina 29550-0790 3581 West Entrance Road Hartsville, South Carolina 29550
0 0
REQUEST FOR ADDITIONAL INFORMATION H. B. ROBINSON SPENT FUEL CASK DROP UNREVIEWED SAFETY QUESTION.
TAC MA0652 Provide a full description of the radiological consequence analysis, including:
1 What was the maximum number of bundles assumed in the cask?
- 2.
What was the power history and decay time assumed for the fuel bundles?
What decay time was assumed prior to loading into the cask? Provide justification that this 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.1.e of Regulatory Guide 1.25? If not, what peaking factor(s) were applied? Provide justification that this is a conservative and bounding assumption.
- 3.
The August 28, 1997, request states that "fuel rod damage occurs and maximum available gap activity is released."
Were 100% of the fuel rods in the cask assumed damaged by the drop? If not, what % damage was assumed? Provide justification that this is a conservative and bounding assumption.
Were the assumptions in Reg. Guide 1.25, Position C.1.d & f, used to determine the assumed fuel gap inventory? If not, specify the gap inventory used and describe the assumptions used 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?
What breathing rate(s) were assumed for individuals at the locations of interest?
- 5. The August 28, 1997, request states that "The evaluation demonstrates that the release would not be sufficient to initiate the Control Room radiation alarm or pressurization mode of the Control Room ventilation system." This implies that the doses in the control room are acceptable. However, no results for the control room are provided. Provide the dose consequences to the control room operators during the postulated cask drop accident and compare these results to GDC 19.
-2
- 6.
The consequence table on page 3 of the submittal indicates that the 8-hour integrated dose at the low population zone is numerically the same as the 2-hour integrated dose at the site boundary. Explain why this is the case.