ML20141C267
| ML20141C267 | |
| Person / Time | |
|---|---|
| Site: | 07200003 |
| Issue date: | 03/28/1986 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Massey J NUTECH ENGINEERS, INC. |
| Shared Package | |
| ML20141C270 | List: |
| References | |
| REF-PROJ-M-39 NUDOCS 8604070218 | |
| Download: ML20141C267 (4) | |
Text
g-3 MAR 2 s 1985 Project M-39 NUTECH, Inc.
ATTN: John V. Massey, Ph.D NUH0MS Project Manager 145 Martinvale Lane San Jose, California 95119
Dear Dr. Massey:
SUBJECT:
ACCEPTANCE AS A REFERENCE OF " TOPICAL REPORT FOR THE NUTECH H0RIZONTAL MODULAR STORAGE SYSTEM FOR IRRADIATED NUCLEAR FUEL," (NUH-001), REVISION 1 The Nuclear Regulatory Commission (NRC) staff has completed its review of NUTECH, Inc., " Topical Report for the NUTECH Horizontal Modular Storage System for Irradiated Nuclear Fuel," (NUH-001), Revision 1.
Based on this
-review, NRC staff has concluded that NUTECH Horizontal Modular System (NUHOMS) 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, 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 (ISFSI) to be located at a nuclear power plant site. This 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 enclosures.
By letter dated November 11, 1985, NUTECH, Inc., submitted for review a topical report entitled " Topical Report for the NUTECH Horizontal Modular Storage System for Irradiated Nuclear Fuel," (NUH-001), Revision 0, dated November 1984 (docketed under Project No. M-39).
In response to NRC staff comments, a revision to the original NUTECH report was subsequently submitted and docketed. This was Revision 1 entitled, " Topical Report for the NUTECH Horizontal Modular Storage System for Irradiated Nuclear Fuel," (NUH-001),
Revision 1, dated November 1985.
In the SER, the staff's review examined how the submitted NUHOMS concrete horizontal storage module (HSM) and steel dry shielded canister (DSC) 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. Radiological, shielding, criticality, structural and thermal aspects of the storage module 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.
8604070218 860328 PDR PROJ M-39 PDR e
NOTECH, Inc.
2 MAR 2 81986 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.
Operating limits established for the module and its spent fuel content have been reviewed, and limitations and operating conditions applicable to fuel loading, onsite transfer, insertion of a canister into a module, storage operations, and surveillance are detailed in Chapter 12 of the SER (see enclosure 1). These specify the limitations under which the TR, with its described HSM, DSC 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, these are 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 NUTECH, Inc.,
" Topical Report for the NUTECH Horizontal Modular Storage System for Irradiated Nuclear Fuel," (NUH-001), Revision 1, as augmented by additional informaticn received ar.d docketed after submittal of Revision 1, is acceptable as a reference, under the limitations delineated in the TR, as modified and expanded in the SER (enclosure 1), with the following exception:
Chapter 10, Development and Operating Controls and Limits, 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 information contained in the SER (enclosure 1).
It is requested that NUTECH, 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 25 copies for docketing.
This revision is also to incorporate this letter with its enclosure, 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-39.
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).
NUTECH, Inc.
3 MAR 2 8 1986 Should NRC criteria or regulations change, such that our conclusions as to the acceptability of the report are invalidated, NUTECH, Inc., 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 documentati.on, i
Sincerely, Originsi aignon by Leland C. Rouse j
.j j '--
g 'L' eland C. Rouse, Chief Advanced Fuel and Spent Fuel Licens'ing Branch 4
Division'of Fuel Cycle and Material Safety i
Enclosure:
l.
Safety Evaluation Report DISTRIBUTION:.Please retdrn original concurrence copy to FBrown SS 396
- Project.M-39 ' Docket 72-3
~J'~Stokley, SAIC
'NMSS R/F PDR&LPDR bcc:
FCAF R/F J. Kozyra, CP&L LCRouse JRoberts FSturz Glode Requa NDavison JSchneider R8achmann CGaskin JKennedy LA Fila DWeiss GBennington WBrown LCobb, IE
- sl OFC: F.
________s._f._-___________......__.______._____.____......._____
- FCAF/ #:
NAME:J erts :LCR6i$
DATE:03/19/86 :03/{ 86 :
-E P
u NMSSr ep;a Material FCUF FCAF I
[A$et # M-3 Project # (h-54 (Mu Other 9R-3 (N-Ak()
Pra
- :it
=,4 10 s< v J
4
._._ _. _. - _.._,_._.. _ _--.. _,....,_.. _, _ _ _ _.,