ML20148M536

Forwards Safety Evaluation of Nuclear Assurance Corp Rept, Rev 2, Topical SAR for Nuclear Assurance Corp Storage/ Transport Cask for Use at Isfsi. Cask Meets Requirements of 10CFR72

ML20148M536
Person / Time
Site:	07201000
Issue date:	03/29/1988
From:	Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Viebrock J NAC INTERNATIONAL INC. (FORMERLY NUCLEAR ASSURANCE
Shared Package
ML20148M540	List: ML20148M536 ML20148M542
References
REF-PROJ-M-40 NUDOCS 8804050431
Download: ML20148M536 (6)

Text

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W  ! 9 ;gg Project M-40 Nuclear Assurance Corporation ATTN: Mr. James M. Viebrock Senior Vice President 6251 Crooked Creek Road Suite 200 Norcross, Georgic 30092

SUBJECT:

ACCEPTANCE AS A REFERENCE OF "TOPICAL SAFETY ANALYSIS REPORT FOR THE NAC STORAGE / TRANSPORT CASK FOR USE AT AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION," REVISION 2 The Nuclear Regulatory Commission (NRC) staff has completed its review of c,evision 2 of the Nuclear Assurance Corporation (NAC), "Topical Safety Analysis Report for the NAC Storage / Transport Cask for use at an Independent Spent Fuel Storage Installation" (TSAR). Based on this review, NRC staff hds concluded 1

that the NAC Storage / Transport (S/T) cask design as described in the 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 rtaff'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 2), augmented by information i submitted after the filing of Revision 2 and in this letter with its enclosure.  ;

1 By letter dated December 13, 1984 Nuclear Assurance Corporation sutnitted for l review a topical report entitled, "Topical Report for the NAC Storage / Transport Cask for an Independent Spent Fuel Storage Installation" dated December 1984 l (docketed under Project No. M-40). In response to NRC staff comments, a first and then a second revision to the original NAC report were subsequently submitted and docketed. This last revision was Revision 2 entitled, "Topical Safety l Analysis Report for the NAC Stora(,e/ Transport Cask for use at Independent Spent l Fuel Storage Installation dated April 1987.

In this SER, the staff's review examined how the submitted NAC Storage / Transport dry cask design for an ISFSI meets specific reqisirements of 10 CFR Part 72 with respect to design, operation, and decomissioning. The staff's review addresses nornal 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 t. ave been reviewed for compliance with applicable requirements of Subparts E, F, and G of 10 CFR Part 72.

8804050431 080329 0 PDR

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Nuclear Assurance Corporation 2 MAR 3 p 1986 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.

Operating limits establish for the cask and its spent fuel content 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 specifics 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 technical specification and limitation will apply, depending on siting or other conditions associated with a specific license application.

As a result of its evaluation, the NRC staff firds that the Nuclear Assurance Corporation, "Topical Safety Analysis Report for the NAC Storage / Transport Cask for an Independent Spent Fuel Storage Installation, "Revision 2, as augmented by additional information received and docketsd after submittal of Revision 2, 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:

i Chapter 10, Developn'ent 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 wit 1 the LimitationsandOperatingConditionsListing(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 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 Reports Revision 2, which need to be clarified or corrected (seeenclosure3,TSARCorrections). 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 after the TSAR, i.e.,

Revision ?, and docketed under Project M-40. The report identification of the approved .eport is to have and "A" suffix.

The NRC staff does not intend to rtpeat the review of the features important to safety described in the TSAR and found acceptable when it appears as a

Nuclear Assurance Corporation 3 WAR I p g 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 subsequent to the filing of the TSAR (i.e., Revision 2).

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, Origiral 51#W' John P. Roberts, Section Leader Irradiated Fuel Section Fuel Cycle Safety Brsnch

Enclosure:

1. Limitations and Operating Conditions Listing

2. Safety Evaluation Report

3. TSAR Corrections DISTRIBUTION:TBrown M Mrat%O.E'W m+ r W-M f M b  ;

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POR~ lNRC File Center.

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NAME:Jpoberts/lg:  :  :  : i DATE:3/M/88 -

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l LIMITATIONS AND OPERATING CONDITIONS '

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i The following limitations and operating conditions are to be considered in i i

developing site-specific technical specifications for the use of the NAC S/T  !

cask for receipt, handling, and storage of spent fuel at an ISFSI located t j at a reactor site. Additional technical specifications and limitations, as  ;

} appropriate, will be necessary with respect to the issuance of any site-specific j i 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). l Limitations 1 1. Basic Components

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The Basic Components of the Model NAC S/T cask that are important to safety i are listed on pages 3.4-2 and 3.4-3 of the TSAR.  !

2. Fill gas: Helium l

!] 3. Fuel Stored i i i

a. The type of Pressurized Water Reactor (PWR) fuel found acceptable is ,

Westinghouse 15 x 15 assemblies with Zircaloy fuel rod cladding. On j a site-specific basis other fuel assembly types wh hh are no more reactive

than this type and which meet the other limiting conditions of this review -

are also acceptable.

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j b. Maximum number of PWR fuel assemblies stored per cask shall be 126.

I c. Assemblies to be contained in the NAC S/T fuel basket shown in Figures  !

4.2-10, 4.8-1, and 4.8-4.

l d. Initial fuel enrichment shall not exceed 3.3 percent U-235 by weight.

) e. Fuel Assembly Surnup shall not exceed 35,000 MWD /MTV.

j 8 Neutrons emitted per assembly shall not exceed 1.452x10 n/s.15 j Gamma photons emitt g per/ assembly shall not exceed 5.720x10

photons /s (3.540x10 MeV/s).

1 i f. Spent fuel assemblies known or suspected either to have gross j 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, j assemblies from which fuel pins are missing must not be stored l unless dummy fuel pins are 'twed to displace an amount of water

equal to that displaced by the original pins.

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Cask Operating Conditions Operatina Limit '

j 1. Max. Lifting Height i 6 feet l

2. Dose Rate: i

a. from top or side surface of the cask i at 2 m distance < 10 rem /h .

! b. at top and side surfaces of the cask 7 200 mrem /h (These limits conform to transportation i cask dose rate limits, Actual dose rates  !

at these surfaces for the NAC S/T will be less.)  ;

j 3. Cask Tightness (at closure):  !

(Standard He-Leak Rate) i

a. Primary Cover Seal < 10-6 ,g, c,373,e All Pentration (Vent, Drain, Fill,

b.  !

' and Pressure Transducer Lines) -6 3 Seals (Primary and Secondary) 110 atm em /sec

4. Max. Specific Power of One Fuel < 1.0 kW

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Assembly As Calculated with i ORIGEN-2 (For spent fuel with the  !

maximum specified burnup, this specific i power value assures that fuel must '

4 have decayed 5 years after discharge 1

from the reactor core and that the l total heat generation load of the cask ,

j does not exceed 26 kW). j

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5. Max. Calculated Cladding Temperature 380'C l

6. Initial Helium Pressure Limit (Cavity) $ 32 psia l

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1 7. Siting Limitations

a. 10 CFR Part 72.67 (a) j b. 10 CFR Part 72.68 l 8. Cask Emplacement

Cask empiccement on a storage pad shall be in an upright position, j Horizontal cask positioning for storage is prohibited.

Technical Specifications Listina l

Cask Monitorino Pressure Sensing Element: A f: :tional check during preparation of cask for  !

1 plact hht in storage shall be performed to ensure l l the - . ment is functioning. i l

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Cask Related Activities Not Covered:

{ Activities associated with the receipt, stor6ge, and unloading of the cask for  !

which limitations and operating conditions have not been identified include, j but are not necessarily limiting to the following items. These have not been l included either because they are site specific or because they would be j covered under a 10 CFR Part 50 Operating License of a reactor, t 4

1. Cask handling and loading operations. (

2. Cask Decontamination, j

! 3. Cask sealing and drying (See also Cask Operating Conditions, items 3 and

, 5-6).

4. Cask transfer to ISFSI. f

5. Cask emplacement at ISFSI (See also Cask Operating Conditions, items 1 and  !

8).

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6. ISFSI siting (See also Cask Operating Conditions, item 7). l t

7. Cask return to reactor. l i

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8. Cask handling and unloading operations including cavity sampling and cask l cooling. i;

9. Siting and radiological evaluation for a cask array.  ;

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