ML20154Q961
| ML20154Q961 | |
| Person / Time | |
|---|---|
| Issue date: | 09/29/1988 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Viebrock J NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE |
| Shared Package | |
| ML20154Q964 | List: |
| References | |
| REF-PROJ-M-51 NUDOCS 8810040117 | |
| Download: ML20154Q961 (6) | |
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Project M-51 SEP 2 91988 Nuclear Assurance Corporation ATTH:
Mr. James M. Viebrock Senior Vice President 6251 Crooked Creek Road Suite 200 Norcross, Georgia 30092
Dear Mr. Viebrock:
SUBJECT:
ACCEPTANCE AS A REFERENCE OF "TOPICAL SAFETY ANALYSIS REPORT FOR THE NAC STORAGE / TRANSPORT CASK CONTAINING CONSOLIDATED FUEL FOR USE AT AN INDEPENDE,iT SPENT FUEL STORAGE INSTALLATION " REVISION 1 The Nuclear Regulatory Commission (NRC) staff has completed its review of Revision 1 of the Nuclear Assurance Corporation (NAC), "Topical Safety Analysis Report for the NAC Storage / Transport Cask Containing Consolidated Fuel for Use at an Independent Spent fuel Storage Installation" (TSAR).
Based on this review, NRC staff has concluded that the NAC Storage / Transport (S/T) cask design as described in the TSAR 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 at an independent spent fuel storage installation to be located at a nuclear power plant site.
This acceptability is limited to conditions and the spent fuel detailed in the TSAR (i.e., Revision 1),
augmented by information in conjunction with the filing of Revision 1 and in this letter with its enclosure.
By letter dated February 17, 1988, Nuclear Assurance Corporation submitted for review a topical report entitled, "Topical Report for the NAC Storage / Transport Cask Containing Consolidated Fuel for Use at an Independent Spent Fuel Storage Installation" dated January 1988 (docketed under Project No. H-51).
In response to NRC staff comments, a revision to the original NAC report was subsequently submitted and docketed.
This was Revision 1 entitled, "Topical Safety Analysis Report for the NAC Storage / Transport Cask Containing Consolidated fuel for Use at Independent Spent Fuel Storage Installation dated July 1988.
In its SER, the staff's review examined how the submitted NAC Storage / Transport 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 goo f7 33ay2y
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M-51 pp;
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ggp g g )ggg compliance with applicable requirements of Subparts E, F, and G of 10 CFR Part 72.
Review 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 TSAR and were not addressed in the staff's review.
However, we understand that NAC will seek a 10 CFR Part 71 certification of a packaging design with the standard cask body used in this and in previous and succeeding TSAR dry storage cask designs (docketed under Project Nos. M-40 and M-52, respectively) submitted to NRC for letters of approval pursuant to 10 CFR Part 72.
Therefore, we recommend that NAC remain cognizant of 10 CFR Section 72.18. "Evaluation of repetition,"
regarding re/erencing of previous reviews, since review by NRC staff pursuant to a certification under 10 CFR Part 71 may be referenced where requirements meet or exceed those of 10 CFR Part 72.
Thus, should any design changes be required under 10 CFR Part 71, in the interest of regulatory efficiency, we hope that a further review of such changes under 10 CFR Part 72 could be limited.
Operating limits established for the cask and its spent fuel contents have been reviewed, and a Limitations and Operating Conditions listing applicable to fuel loading, onsite transfer, emplacement of a cask, cask storage operations, and cask decommissioning is enclosed (see enclosure 1).
This listing specifies the limitations under which the TSAR, 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 te hnical 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 Nuclear Assurance Corporation, "Topical Safety Analysis Report for the NAC Storage / Transport Cask Containing Consolidated Fuel for Use at an Independent Spent Fuel Storage Installation," Revision 1, as augmented by additional information received and docketed in conjunction with the submittal of Revision 1, is acceptable as a reference, under the limitations delineated in the TSAR, as modified and expanded in the Limitations and Operating Conditions listing (enclosure 1) and the SER (enclosure 2), with the following exception:
Chapter 10. Development and Operating Controls and Limits of the TSAR 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 TSAR as guidance along with the Limitations and Operating Conditions Listing (enclosure 1).
It is requested that Nuclear Assurance Corporation publish an approved version of this report, with proprietary information in a separate binder, as per
o Nuclear Assuranco Corporation 3
SEP 2 91988 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 retained by NAC for further reference.
In the approved version, there are items relating to the NAC S/T cask Topical Safety Analysis Report, Revision 1, which need to be clarified or corrected (see enclosure 3, TSAR Corrections).
While they do not affect our assessment of safety and compliance with the requirements of 10 CFR Part 72 as reflected by the SER, they should be incorporated in the TSAR.
This revision is also 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 in conjunction with the TSAR, i.e., Revision 1, and docketed under Project H-51.
The report identification of the approved report is to have and "A" suffix.
The NRC staff does not intend to repeat the review of the features important to safety described in the TSAR 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 TSAR, as augmented by the supplemental information submitted in conjunction with the TSAR (i.e., Revision 1).
Should NRC criteria or regulations change, such that our conclusions as to the acceptability of the report are invalidated, Nuclear Assurance Corporation and/or the applicants referencing the Topical Report will be expected to 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, p s,t.stG w n 911)
John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Branch
Enclosure:
- 1. Limitations and Operating Conditions Listing
- 2. Safety Evaluation Report
- 3. TSAR Corrections DISTRIBUTION:
Please return original concurrence copy to FBrown SS 6-H-3 Project H-51 FBrown POR NRC File Center NM55 R/F IMSB R/F IMIF R/F CN5mith, SGLB JPRoberts FSturz JSchneider KCleu J5praul, NRR GJackson LCRouse 5Ruffin Q..........Q J[/f)Q y.................................
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- D IBrown
- J/ Roberts NAME:JF5ch ider:Ig k........../........................................
D ATE: 9/2 7/88
- 9Mf/88
- 9/Jf/88 OFFICIAL RECORD COPY
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LIMITATIONS AND OPERATING CONDITIONS i
The following limitations and operating conditions are to be considered in i
developing site-specific technical specifications for the use of the NAC $/T cask for receipt, handling, and storage 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.
I The Basic Components of the Model NAC S/T cask that are important to safety are listed on pages 3.4-1 and 3.4-2 of the TSAR.
i 2.
Fill gas:
Helium 3.
Fuel Stored l
a.
Fuel rods from Pressurized Water Reactor (PWR) Westinghouse W-STD 15 x 15 assemblies with Zircaloy fuel rod cladding are acceptable.
On a site-specific basis fuel rods from other fuel assembly types which l
are no more reactive than this type and which meet the other Ilmiting conditions of this review are also acceptable.
b.
Fuel rods shall be stored in stainless steel canisters, j
c.
Canister cross section shall be square with inside dimensions of i
8.4 inches x 8.4 inches, d.
No canister shall contain fewer than 361 fuel rods nor more than 408 fuel rods, i
e.
Maximum number of fuel rod canisters stored per cask shall be i 28.
f f.
Assemblies are to be contained in the NAC S/T fuel basket shown in I
Figures 4.2-10 and, 4.8-1.
g.
Initial fuel enrichment shall not exceed 3.5 percent U-235 by weight, h.
Fue'
%)y Burnup shall not exceed 35,000 MWD /MTU.
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Cask Operatina conditions Operatina Limit 1.
Max. Lifting Height:
- a. with impact limiters
< 4 feet 11 inches
- b. without impact limiters 515 inches 2.
Dose Rate:
a.
from top or side surface of the cask at 2 m distance
< 10 ares /h b.
at top and side surfaces of the cask I 200 mren/h (These limits conform to transportation cask dose rate Ifmits. Actual dose rates at these surfaces for the NAC S/T will be less.)
3.
Cask Tightness (at closure):
(Standard He-Leak Rate) a.
Primary Cover Seal 10-6,g,g,3,,e 1
7 b.
All Penetrations (Vent, Orain, Fill, and Pressure Transducer Lines)
Seals (Primary and Secondary) 110 6,g,c,3,,,
j 4.
Max Specific Power of each Fuel Rod
< 0.714 kW
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Canister As Calculated with ORIGEN-2 (For spent fuel with the maximum specified burnup, this specific power value assures that fuel must have decayed 10 years after discharge from the reactor core and that the total heat generation load of the cask does not exceed 20 kW).
5.
Max. Calculated Cladding Temperature 300'C 6.
Initial Helium Pressure Limit (Cavity) 5, 32.4 psia 7.
Siting Limitations a.
Cask Transfer and Emplacement.
Cask transfer to and emplacement on a storage pad shall be in an upright position. Horizontal cask positioning for storage is prohibited.
Technical Specifications Listina Cask Monitoring Pressure Sensing Element: A functional check during preparation of cask for placement in storage shall be performed to ensure the element is functioning.
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Cask Related Activities Not Covered:
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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 a 10 CFR Part 50 Operating License of a reactor.
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1.
Cask handling and loading operations.
2.
Cask Decontamination.
4 3.
Cask sealing and drying (See also Cask Operating Conditions, items 3 and 5 6).
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4.
Cask transfer to ISFSI.
5.
Cask emplacement at ISFSI (See also Cask Operating Conditions, items 1 and l
l 8).
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6.
ISFSI siting (See also Cask Operating Conditions, item 7).
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7.
Cask return to reactor.
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8.
Cask handling and unloading operations including cavity sampling and cask J
cooling.
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Siting and radiological evaluation for a cask array.
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