ML20246E107
| ML20246E107 | |
| Person / Time | |
|---|---|
| Issue date: | 07/05/1989 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Hanson A TRANSNUCLEAR, INC. |
| Shared Package | |
| ML20246E112 | List: |
| References | |
| REF-PROJ-M-42 NUDOCS 8907120108 | |
| Download: ML20246E107 (7) | |
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UNITED STATES.
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NUCLEAR REGULATORY COMMISSION o-
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WASHINGTON, D. C. 20555 I%... + /j o,
c July 5,_1989 L
lProjectM-42 Transnuclear, Inc.
ATTN:
Dr.. Allen Hanson President Two Skyline Drive Hawthorne, New York 10532-2120
Dear Dr. Hanson:
SUBJECT:
ACCEPTANCE AS A REFERENCE OF "TN-24 DRY STORAGE CASK TOPICAL REPORT,"
REVISION I The Nuclear Regulatory Commission (NRC) staff has completed its review of Revision 1 of the Transnuclear, Inc., "TN-24 Dry Storage Cask Topical Report."
Based on this review, NRC staff has concluded that the TN-24 cask design'as described in the Topical Report (TR) provides for an acceptable means to meet the requirements of 10 CFR Part 72, as defined in this letter, and subject to appropriate specifications expressed in enclosure 1, Limitations and Operating-Conditions, and enclosure 2, the NRC staff's safety evaluation report (SER),
for the safe receipt, handling, and storage of. spent fuel in an independent spent fuel storage installation to be located at a nuclear power plant site.
-Thisl acceptability is limited to conditions and the spent fuel detailed in the TR (i.e., Revision 1), augmented by information submitted after the filing of Revision 1 and in this letter with its enclosure.
By letter dated August 30, 1985, Transnuclear, Inc. (TN), submitted for review a topical report entitled, "TN-24 Dry Storage Cask Topical Report (docketed under Project No. M-42).
In response to NRC staff comments, a revision to the original TN report was subsequently submitted and docketed.
This was Revision 1 entitled, "TN-24 Dry Storage Cask Topical Report" dated July 1988.
In the SER, the staff's review examined how the submitted Transnuclear TN-24 dry cask design for an ISFSI meets specific requirements of 10 CFR Part 72 with respect to design, operation, and decommissioning.
The staff's review addresses normal and off normal operating conditions and accidents.
Shielding, criticality, structural, thermal, and radiological aspects of the cask design and the vendor's Quality Assurance Program have been reviewed for compliance with applicable requirements of Subparts E, F, and G of 10 CFR Part 72.
Requirements for physical protection in 10 CFR Part 73 and for offsite.
-transport of radioactive materials in 10 CFR Part 71 were not within the scope of the TR and were not addressed in the staff's review.
8907120108 890705 PDR PROJ TFo3 t
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Transnuclear, Inc. July 5, 1989 l-Operating limits established for the cask and its spent fuel content have been reviewed, and Limitations and Operating Conditions applicable to fuel loading, onsite transfer, emplacement of a cask, cask storage operations, and cask de-commissioning is enclosed (see enclosure 1).
This listing specifies the limita-tions under which the TR, with its described cask and spent fuel, is accepted as a reference in a Safety Analysis Report in a 10 CFR Part 72 site-specific spent fuel storage license application.
However, this listing is not complete; other appropriate technical specifications and limitations will apply, depending on siting or other conditions associated with a specific license application.
As a result of its evaluation, the NRC staff finds that the Transnuclear, Inc.,
"TN-24 Dry Storage Cask Topical Report," Revision 1, as augmented by additional information received and docketed after submittal of Revision 1, is acceptable as a reference, under the limitations delineated in the TR, as modified and expanded in the Limitations and Operating Conditions listing (enclosure.1) and the SER (enclosure 2), with the following exception:
Chapter 10, Operating Limits Summary, of the TR is not to be cited as a reference.
A site-specific license application should explicitly list its proposed technical specifications.
This does not preclude a license applicant's use of Chapter 10 of the TR as guidance along with the Limita-tions and Operating Conditions (enclosure 1).
It is requested that Transnuclear, Inc., publish an approved version of this report, with proprietary information in a separate binder, as per Item 3,
" Proprietary Information," of the Introduction of Regulatory Guide 3.48, within three (3) months of the receipt of this letter and submit 5 copies for docketing with 20 copies to be retained by TN for future reference.
This revision is to incorporate this letter with its enclosures including the SER, following the title page, and a listing identifying with submittal dates, supporting supplemental information submitted after the TR, i.e., Revision 1, and docketed under project M-42.
The report identification of the approved report is to have an "A" suffix.
The NRC staff does not intend to repeat the review of the features important to safety described in the TR and found acceptable when it appears as a reference in a' license application except to assure that the material presented is applicable to the application involved.
The NRC staff's acceptance applies only to the features described in the TR, as augmented by the supplemental information submitted subsequent to the filing of the TR (i.e.,
Revision 1).
Should NRC criteria or regulations change, such that our conclusions as to the acceptability of the report are invalidated, Transnuclear Inc.,
and/or the, applicants referencing the topical report will be expected to
Transnuclear, Inc. July 5, 1989 i-revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the topical report without revision of their respective documentation.
Sincerely, John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety
Enclosure:
1.
Limitations and Operating Conditions Listing l
2.
Safety Evaluation Report
'Transnuclear, Inc. July 5, 1989 revise and resubmit their respective documentation, or submit justification for i
the continued effective applicability of the topical report without revision of their respective documentation.
Sincerely, Original Signed By John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety
Enclosure:
1.
Limitations and Operating Conditions Listing i
2.
Safety Evaluation Report
[SR/TRANSNUCLEAR ACCEPT LTR]
DISTk18UTION: w/ enclosure Project M-42 RGramann, SG SRuffin bec: WLloyd, LLNL NRC File Center JPRoberts JSpraul, NRR PDR DWeiss FBrown IMSB.R/F FSturz IMIF R/F.
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DATE:7/f/89
- 7/ 3 /89 :7 ( 89
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OFFICIAL RECORD COPY
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.is LIMITATIONS AND OPERATING CONDITIONS The following limitations and operating conditions are to be considered in
-developing site-specific technical specifications for the use of the TN-24 cask for receipt, handling, and stor, age of spent fuel at an ISFSI located at a reactor site.
Additional technical specifications and limitations, as appropriate, will' be necessary with respect to the issuance of any site-specific license under 10 CFR Part 72, but these are not addressed in this review.
(However, some areas requiring consideration are listed for information under Cask Related Activities and are cross-referenced to corresponding items under Cask Operating Conditions).
Limitations 1.
The Basic Components of the Model TN-24 cask that are important to safety are listed on page 3.4-2 of the TN-24 TR.
Also included are the cask fuel basket and the cask trunnions and associated bolts.
.2.
Fill gas:
Helium 3.
Fuel Stored a.
The types of Pressurized Water Reactor (PWR) fuel found acceptable are 14 x 14, 15 x 15, and 17 x 17 assemblies with Zircaloy fuel rod cladding.
b.
Maximum number PWR fuel assemblies stored per cask shall be < 24.
c.
Assemblies are to be contained in the TN-24 fuel basket shown in Figures 971-005, Rev. O, and 971-006, Rev. 1.
d.
Initial fuel enrichment shall not exceed 3.5 percent U-235 by weight.
e.
' Fuel Assembly Burnup shall not exceed 35,000 MWD /MTU at not more than 37.5 MW/MTU specific power.
f.
Spent fuel assemblies known or suspected either to have gross cladding defects or to have structural defects sufficiently severe to adversely affect fuel handling and transfer capability shall not be loaded into the cask for storage.
Partial assemblies, that is, assemblies from which fuel pins are missing must not be stored unless dummy fuel pins are used to displace an amount of water equal to that displaced by the original pins.
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. Cask Operating Conditions Operating Limit 1.
Max Lifting Height without bottom
< 18 inches impact limiter 1.'
D6se Rate:
la, at 2 m Distance from the cask surface
< 10 mrem /h b;
at Surface of the cask
~< 200 mrem /h (These limits conform to transportation cask dose rate limits.
Actual dose rates for the TN-24 wil' be significantly less).
3.
Cask Tightness (at' closure):
(Standard He-Leak Rate)
-6 a.
Primary Cover Seal
-<10 atm-cc/sec b..
Primary Cover, Vent, Drain and Overpressure Port
-6 o
<10 atm-cc/sec
-6 c.
Optional Seal Cover Weld 510 atm-cc/sec 4.
Max.'_ Specific Power of One Fuel
-< 1.0 kW Assembly As Calculated with ORIGEN-2 (For spent fuel with the maximum specified burnup, this specific power value assures that fuel must have decayed a minimum of 5 years after discharge from the reactor core and that the total heat generation load of the cask does not exceed 24 kW).
5.
Max. Calculated Cladding Temperature a.- During cask drying 380 C b.
During storage _
339 C 6.
Initial Helium Pressure Limit (Cavity) 2.2 atm 7.
Siting' Limitations a.
Top Impact Limiter During cask transfer from (or return to) the reactor and after cask emplacement on a storage pad, the impact limiter at the top of the cask shall remain affixed to the cask.
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Technical Specifications Listing
' Cask Monitoring l
Pressure Transducer System: A functional check during preparation of cask for placement in storage shall be performed to ensure the. system is functioning.
Cask Related Activities Not Covered:
Activities associated with the receipt, storage, and unloading of the cask for which limitations and operating conditions have not been identified include, but are not necessarily limiting to the following items.
These have not been included either because they.are site specific or because they would be covered under 10 CFR Part 50 Operating License of a reactor.
1.
Cask handling and loading operations.
2.
Cask Decontamination.
3.
Cask sealing and drying (See also Cask Operating Conditions, items 3, 5, and 6).
4.
Cask transfer to ISFSI.
5.
Cask emplacement at ISFSI (See also Cask Operating Conditions, item 1).
6.
ISFSI siting (See also Cask Operating Conditions, item 7).
7.
Cask return to reactor.
8.
Cask handling and unloading operations including cavity sampling and cask cooling 9.
Siting and radiological evaluation for a cask array.
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