NUREG-1536, Responds to Re Transfer of Spent Fuel.Nrc Has Approved Applications for Sierra Nuclear VSC-24 Storage Sys. Description of Approved Sys & Acceptance Criteria Located in NUREG-1571 & NUREG-1536 Respectively.W/O NUREGs: Difference between revisions

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{{Adams
#REDIRECT [[NUREG-1536, Provides follow-up to Telcons That Followed Issuance of Directors Decision 97-18 Re Petition Filed by Prairie Island Indian Community Pursuant to 10CFR2.206.Addl Info Re Research Ref in Stated Passage of Directors Decision]]
| number = ML20203E310
| issue date = 12/04/1997
| title = Responds to Re Transfer of Spent Fuel.Nrc Has Approved Applications for Sierra Nuclear VSC-24 Storage Sys. Description of Approved Sys & Acceptance Criteria Located in NUREG-1571 & NUREG-1536 Respectively.W/O NUREGs
| author name = Raddatz M
| author affiliation = NRC
| addressee name = Chiou S
| addressee affiliation = TAIWAN (REPUBLIC OF CHINA), ATOMIC ENERGY COUNCIL
| docket =
| license number =
| contact person =
| case reference number = RTR-NUREG-1536, RTR-NUREG-1571, RTR-NUREG-CR-6407
| document report number = NUDOCS 9712170012
| title reference date = 10-14-1997
| package number = ML20203E315
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 2
| project =
| stage = Other
}}
 
=Text=
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^ Mr. Syh-Tsong Chiou,' Director Fuel Cycle and Materials Administration'
- Atomic Energy Council 4
SF, No; 27, San Min Road,- Soc. 2 Panchlao
; Taipei County, Taiwan 220 -
 
==SUBJECT:==
RESPONSE TO LETTER DATED OCTOBER 14,1997
 
==Dear Mr. Chiou:==
: In your {{letter dated|date=October 14, 1997|text=October 14,1997, letter}}, you requested information on the classification of venting :
l
; systern and sealing gasket components and on United States Nuclear Regulatory Commission
-t regulations and reviewing experience of transfer casks used for the transport of research reactor fuels from the storage pool to a transportation cask. The intent of this letter is to respond to your questions.
The transfer of spent fuel is generally licensed under the provisions of Title 10 of the Code of Federal _ Regulations (10 CFR), Part 50," Domestic Licensing of Production and Utilization Facilities." Generally,10 CFR Part 72, " Licensing Requirements for the Independent Storage of -
Spent Nuclear Fuel and High-Level Radioactive Waste," and 10 CFR Part 71,
* Packaging and Transportation of Rasonctive Material," certificates or licenses take precedence over 10 CFR -
- Part 50 licenses at the point where the spent fuel is moved outside of the building containing the spent fuel.1 Transfers of spent fuel from a storage pool to a storage cask are currently reviewed
_ under 10 CFR Part 72. To date, there are no 10 CPR Part 71 systems that utilize a transfer cask, if a transfer cask were to be approved for a transportation application, a careful review of
. the regulations, including 10 CFR Part 50, would be required to establish the acceptance E
. criteria.
l NRC has reviewed and approved license applications for the Sierra Nuclear VSC-24 storage L-system and several Vectra NUHOMS systems, including the NUHOMS-7P, NUHOMS-24P, Standardized NUHOMS-24P, and Standardized NUHOMS-528. A description of the approved l
systems can be found in NUREG-1571, "Information Handbook on independent Spent Fuel L
Storage Installations" (Enclosure 1), in the past, NRC staff reviewed these applications, which l
contained the design of a transfer cask, in accordance with 10 CFR 72. The acceptance criteria L
, for the dry cask storage systems can be found in NUREG-1536, " Standard Review Plan for Dry L
Cask Storage Systems," (Enclosure 2). These criteria were formulated from a review of the :
VSC-24 and NUHOMS systems.'
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Mr. S. T. Chiou.
In response to question 3 of your letter, the following components of dry spent fuel storage casks are classified as Category A components: inner and outer cask lid seats, pressure relief devices, vent and drain port plugs, and seals for vent and drain port plugs and pressure relief devices. Category A components are those components that are critical to the safe operation of the storage cask systems and whose failure could directly result in a condition adversely affecting public health and safety. A description of these components and a discussion of the safety categories can be found in Section 6 of NUREG/CR-6407, " Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to importance to Safety"(Enclosure 3). The quality control requirements for Category A components are specified in 10 CFR 72, Subpart G, and 10 CFR 72.174. Tne types of quality control records that are required to be maintained in accordance with these regulatory requirements also listed in NUREG/CR-6407.
If you have any further questions, please contact me at the above address.
Sincerely, o g g c g.yt s+~es
>s
/s/
Michael Raddatz
 
==Enclosures:==
: 1. NUREG-1571
: 2. NUREG-1536
: 3. NUREG/CR-6407 Distribution: w/ incoming PUBLIC NRC File Center KAGruss NMSS r/f SFPO r/f SFLS r/f CJHaughney WUpshaw. OIP KDBurke. OIP SFShankman OFC
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