ML20128B076
| ML20128B076 | |
| Person / Time | |
|---|---|
| Issue date: | 05/14/1985 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Barnhart V GENERAL NUCLEAR SYSTEMS, INC. |
| Shared Package | |
| ML20128B081 | List: |
| References | |
| REF-PROJ-M-34 NUDOCS 8505240400 | |
| Download: ML20128B076 (4) | |
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Original concurrence copy to be Distribution: returned to FBrown
[froject M-34 SS 396 MAY 14 G85 NMSS R/F PDR FCAF R/F Project M-34 LCRouse JRoberts FSturz General Nuclear Systems, Inc.
JSchneider ATTN:
Mr. Victor J. Ba rnhart NDavison Progran Panager LA File 135 Darling Drive CEMacDonald Avon, Connecticut 06001 JKennedy
Dear Mr. Ba rnha rt:
SUBJECT:
ACCEPTANCE AS A REFERENCE OF " TOPICAL SAFETY ANALYSIS REPOPT FOR THE CASTOR Ic CASK INDEPENDENT SPENT FUEL STORAGE INSTALLATION (DRY STORAGE), REVISION 3 The Nuclear Regulation Commission (NRC) staff has completed its review of Revison 3 of the General Nuclear Systems, Inc., " Topical Safety Analysis Report for the CASTOR Ic Cask Independent Spent Fuel Storage Installation (Dry Storage)" (TSAR). Based on this review NRC staff has concluded that the CASTOR Ic cask design as described in the TSAR provides for an acceptable means to neet the requirenents of 10 CFR Part 72, as specified in this letter and its enclosures, 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 3), augumented by responses submitted after the filing of Revision 3 to NRC staff requests for additional information, and in this letter with its enclosures.
By letter dated April 30, 1982, Gesellschaft fiir Nuklear Service ebH (GNS),
a West Geman fim, submitted for review a topical report entitled, " Topical Safety Analysis Report for the CASTOR Ic Cask Independent Spent Fuel s
Storage Installation (Dry Storage)" (TSAR), dated April 1992 (docketed under Proj ect No. M-34).
By letter dated March 8,1985, GNS requested that the applicant of record for this review be changed to General Nuclear Systems, Inc. (GNSI), a United States (U.S.) company incorporated in the state of Delaware, which is a partnership between Chem-Muclear Systems, Inc.,
also a U.S. corporation, a nd GNS.
In response to NRC staff comments, revisions to the original GMS report were subsequently subnitted and docketed. These were:
Revision 1, dated November 1982; Pevision 2, dated July 1983; and Revision 3, dated Septenher 1984 8505240400 850514 PDR PROJ M-34 PDR
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General Nuclear Systems, Inc. The NRC staff has completed its review of the GNSI TSAR and additional infomation requested and docketed under Project No. H-34 These documents have provided sufficient infomation for the staff to complete its safety review. The staff evaluation and conclusions are detailed in an enclosed safety evaluation report (SER) (see enclosure 1).
In this SER the staff's review examined how the submitted CASTOR Ic 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 nomal and off-noval operating conditions and accidents.
Radiological, shielding, criticality, structural and themal aspects of the cask design and the vendor's Quality Assurance Progran have been reviewed for compliance with applicable requirenents 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 TSAR and were not addressed in the staff's review.
Operating limits established 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 2). This listing specifies the limitations under which the TSAR, with its described Cdsk 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 specifica-tions and limitations will apply, depending on siting or other conditions associated with a specific license application.
As a resulc of its evaluation, the NRC staff finds that the General Nuclear Systems, Inc., " Topical Safety Analysis Report for the CASTOR Ic Cask Independent Spent Fuel Storage Installation (Dry Storage)," Revision 3, as augmented by responses submitted after submittal of Revision 3 to NRC's requests for additional infomation, is acceptable as a reference, under the limitations delineated in the TSAR, as modified and expanded in the Limitations and Operating Conditions Listing (enclosure 2) and the SER (enclosure 1), with the following exception:
Chapter 10, Development of 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 speci fi cations. This does nnt preclude a license applicant's use of Chapter 10 of the TSAR as guidance along with the Limitations and Operating Conditions Listing (enclosure 2).
NRC FORM 318 t10180) NRCM O240 OFFICIAL. RECORD COW W u.s. apo 19:3_4oo.247
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~-+v w mi General Nuclear Systems, Inc. MAY 141985 It is requested that General Nuclear Systems, Inc. publish an approved version of this report, with proprietary information in a separate binder, as per Item 3. "Proprieta ry Information," of the Introduction to Pegulatory Guide 3.48, within three (3) months of the receipt of this letter and submit 25 copies to me for docketing.
In the approved version, the following items relating to the CASTOR Ic Topical Safety Analysis Report, Revision 3, need to be clarified or corrected. While they do not affect our assessment of safety and compliance with the requirements of 10 CFi cart 72 as reflected by the SER, they should be incorporated in the TSAR.
1.
Cask body activation summarized in Table 3.5-1 of the TSAR and the ORIGEN activation results provided as a supplement on November 29, 1984, do not agree. The differences should be reconciled.
(See Section 3.5.1.1, Cask Rody Activation, of the SER.)
2.
In Section 7.P.1 of the TSAR, activation of the cladding material should be included in the gamma source strength. Also sources for the discrete energy gamma rays emitted from the head and foot piece regions should be identified.
(See Section 5.3.1, Gamma Source, of the SER.)
3 Atom number densities for the shield materials should be provided.
Idaterial density differences between Section 3.2.5.3 and Section 7.3.2.1 should be corrected for the steel in the botton and lids. Atom number densities for the iron and boron in Source Region Nos. I through 4 should be provided. (See 5.3.2.2, Shield Regional Densities, of the SER.)
4 Section 8.2 of the TSAR lacks discussion of the dose consequences due to seal malfunction resulting from the accidents analyzed. A discussion of the dose consequences should be provided for each accident. Furthemore, since there are results of GNS crop tests for which no leakage occurs, this should be stated in the text with reference to the Rundesanstalt fur Materialprufung, (BAM) report, Gutachten Aktenzeichen 1.02/3023 (November 1982), which constitutes Appendix 12 of the superseded Revision 2 of the TSAR.
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NRC FORM 318 (10/80l NRCM O240 OFFICIAL RECORD COPY
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General Nuclea r Systems, Inc.
-4 MAY 141985 This revision is also to incorporate this letter with itsenclosures including our SER, following the title page and a listing identifying with submittal dates, supporting infonnation submitted in response (after submittal of the TSAR, i.e., Revision 3) to NRC's requests for additional infonnation and docketed under Project H-34. 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 decribed 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 responses submitte<1 subsequent to the filing of the TSAR (i.e., Revision 3).
Included in these supplemental responses is the declassified BAM report previously submitted as proprietary Appendix 12 of Revision 2 of the TSAR.
Should Nuclear Regulatory Commission criteria or regulations change, such that our cenclusions as to the acceptability of the report are invalidated, General Nuclear Systems 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 documentation.
Si ncerely, Ortatsmal sisood D7 W c.nouse Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety
Enclosures:
1.
Safety Evaluation Report 2.
Limitations and Operating Conditions Listing VA2@.
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