ML20012C999
| ML20012C999 | |
| Person / Time | |
|---|---|
| Site: | 07109238 |
| Issue date: | 03/14/1990 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Parker T NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9003260272 | |
| Download: ML20012C999 (3) | |
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SGTB:NLO 71-9238 Northern States Power Company
' ATTN: Mr. Thomas M. Parker
.414-Nicollet Mall:
Minneapolis, MN 55401-1927:
Dear Mr. Parker:
A This refers to your application dated October 26, 1989,-requesting approval for the Pathfinder Vessel as a radioactive material transportation package.
In connection'with'our review,-we need:the information identified in the enclosure to this-letter.
Please advise us within 30 days from the date of this letter when this
-1'nformation will be provided.. Additional information requested by this letter should be submitted in the form of revised pages.
If you have any questions
.regarding this matter, we would be pleased to meet with you and your_ staff.
Sincerely i
Charles E. MacDonald, Chief l
' Transportation Branch Division of Safeguards and Transportation, NMSS
Enclosure:
As stated listribution:
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/. t p* 71 9238 Encl to Ltr datedleAR 14 M DRAWINGS Provide detailed engineering drawings of the package, including: vessel dimensions, wall thickness, and materials of construction' size and number of vessel head bolts; reactor internals dimensions, masses, materials of construction, and arrangement within the reactor vessel. WELDING The application should describe the procedures, standards, types, sizes, locations, and i inspection procedures that will be used for the welds on the nozzle cover plates I (approximately 32 locations). Note that NUREG/CR 3019, " Recommended Welding Criteria For Use in the Fabrication of Shipping Containers for Radioactive Materials," provides welding criteria for Category III containers which are acceptable to the staff. STRUCTURAL EVALUATION 1. Provide additional narration and a sketch to clarify the calculations of package weight and center-of-gravity in Appendix 2.10.1. i 2. Show that the six substitute head bolts which are used to lift the vessel meet the requirements of 10 CFR 571.45(a). 3. Provide a drawing which shows how the package will be tied down and supported j for transport. Show that the portions of the tie dowm system which are a structural part of the package meet the requirements of 10 CFR 571.45(b). 4. Provide a sketch which shows locations for which maximum stresses were calculated for the one-foot free drop test. Provide a table which summarizes stress intensities at these locations. 5. Note that the reference (p.2-12) to the location of the load-deflection calculations should be Appendix 2.10.5 rather than 2.10.1. L SHIELDING EVALUATION 1. Clarify whether the specific activities in Table 7.1 (page 19 of Appendix 5.5.1) cre maximum or average values. If the values are averages, describe the areas and l l
2 ) masses over which the averages were derived. For any component or region where the maximum specific activity is greater than 0.3 mci /g, provide the numerical ) calculations used to derive the average value. Regarding the Pathfinder Curie Estimate Spreadsheet, Figure B-1 (pp. 52-57 of 2. ~ Appendix 5.5.1) address the following: The spreadsheet indicates that the total weight of the reactor vessel and the a. internals is 186,936.50 lbs. The sum of the calculated weights for the vessel and internals given in Figure 1.1, page 1-9, is 198,000 lbs. Clarify this apparent difference. The axial profile of the neutron activation model (Figure 5.3, page 13 of b.. Appendix 5.5.1) indicates that the major portion of the boiler boxes lies in the core region (layer 4, cylinder 0). However, the spreadsheet shows a larger inventory of radioactivity for the portion of the boiler boxes located in the first level above the core region (layer 3, cylinder 0), than for the core region. Explain this apparent inconsistency. Explain why the portion of the boiler boxes located in the first level below-c. the core region (layer 5, cylinder 0) shows no radioactivity. 3. Clarify whether or not the dose rates listed in Section 5.1.2, page 5-1, and Table 5.1 have been increased by 15%, as explained in Section 9.1 of Appendix 5.5.1, to account for the contribution of the regions above and below the core. Justify the conclusion that the_ dose rates at the ends of the package meet the ' 4. external radiation standards of 10 CFR 571.47. ACCEPTANCE TESTS The acceptance tests should include acceptance criteria for contamination surveys. 1. Clarify the acceptance criterion for surface radiation surveys. Unless the package 2. is shipped in a closed vehicle, dose rates on all accessible external surfaces of the package must not exceed 200 mrem /hr. The acceptance tests should address the package marking requirements of 10 CFR 3. S71.85(c). 1 1 .-}}