ML20153C424: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 2: Line 2:
| number = ML20153C424
| number = ML20153C424
| issue date = 09/21/1998
| issue date = 09/21/1998
| title = Responds to 980904 Ltr Requesting NRC Review Aspects of 980624 Application from Saxton Nuclear Experimental Corp & Gpu Nuclear,Inc for Regulatory Relief from DOT Shipping Requirements.Srvts Should Be Classified as LSA-III
| title = Responds to Requesting NRC Review Aspects of 980624 Application from Saxton Nuclear Experimental Corp & Gpu Nuclear,Inc for Regulatory Relief from DOT Shipping Requirements.Srvts Should Be Classified as LSA-III
| author name = Kane W
| author name = Kane W
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 9809240087
| document report number = NUDOCS 9809240087
| title reference date = 09-04-1998
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 2
| page count = 2
| project =
| stage = Other
}}
}}


Line 26: Line 29:
==Dear Mr. Boyle:==
==Dear Mr. Boyle:==


1 By letter dated September 4,1998, you requested that the Spent Fuel Project Office review              l aspects of the June 24,1998, application from the Saxton Nuclear Experimental Corporation and GPU Nuclear, Inc. (the applicants) for regulatory relief from U.S. Department of Transportation (DOT) shipping requirements. The application requested authorization to classify the reactor vessel from the Saxton Nuclear Experimental Facility (Saxton) as low specific activity (LSA) material and to transport it, under a specified transport plan, from Saxton to a disposal site in Barnwell, South Carolina. You requested our recommendation concerning issuance of an            ,
1 By {{letter dated|date=September 4, 1998|text=letter dated September 4,1998}}, you requested that the Spent Fuel Project Office review              l aspects of the June 24,1998, application from the Saxton Nuclear Experimental Corporation and GPU Nuclear, Inc. (the applicants) for regulatory relief from U.S. Department of Transportation (DOT) shipping requirements. The application requested authorization to classify the reactor vessel from the Saxton Nuclear Experimental Facility (Saxton) as low specific activity (LSA) material and to transport it, under a specified transport plan, from Saxton to a disposal site in Barnwell, South Carolina. You requested our recommendation concerning issuance of an            ,
exemption for the Saxton Reactor Vessel Transportation System (SRVTS) as LSA material.                  l We have reviewed the activation analysis method used by the applicants to determine the                '
exemption for the Saxton Reactor Vessel Transportation System (SRVTS) as LSA material.                  l We have reviewed the activation analysis method used by the applicants to determine the                '
amount and distribution of radioactive material within the reactor vessel and the applicants'
amount and distribution of radioactive material within the reactor vessel and the applicants'
Line 42: Line 45:


I 4
I 4
3                      SAXTON REACTOR VESSEL TRANSPORTATION SYSTEM Determination as Low Specific Activity Material As part of the decommissioning of the GPU Saxton Nuclear Experimental Facility, various facility components must be shipped to a radioactive waste disposal facility. By letter dated September 4,1998, the U.S. Department of Transportation (DOT) requested NRC's recommendation conceming DOT issuance of an exemption to transport the Saxton Reactor Vessel Transportation System (SRVTS) as Low Specific Activity (LSA). At issue is whether the vessel, as prepared for transport, satisfies the applicable definition for LSA as provided in US Nuclear Regulatory Commission (NRC) and DOT regulations.
3                      SAXTON REACTOR VESSEL TRANSPORTATION SYSTEM Determination as Low Specific Activity Material As part of the decommissioning of the GPU Saxton Nuclear Experimental Facility, various facility components must be shipped to a radioactive waste disposal facility. By {{letter dated|date=September 4, 1998|text=letter dated September 4,1998}}, the U.S. Department of Transportation (DOT) requested NRC's recommendation conceming DOT issuance of an exemption to transport the Saxton Reactor Vessel Transportation System (SRVTS) as Low Specific Activity (LSA). At issue is whether the vessel, as prepared for transport, satisfies the applicable definition for LSA as provided in US Nuclear Regulatory Commission (NRC) and DOT regulations.
By memorandum dated August 19,1998, NRC's Division of Waste Management (DWM) provided the results of its review of Saxton Nuclear Experimental Corporation's (SNEC's) waste classification of the reactor vessel and its components, to the Non-Power reactors and Decommissioning Project Directorate (NPRDPD). DWM concluded that it had no objection to SNEC's blending of components for waste classification purposes and agreed with the classification of the components as Class C waste. SNEC was advised of the staff's waste classification review by NPRDPD memorandum, dated August 24,1998. Although this determination concerned the suitability of the material for disposal, the analyses performed involved average activity concentration and are directly applicable to the determination of the specific activity of the components for transportation purposes.
By memorandum dated August 19,1998, NRC's Division of Waste Management (DWM) provided the results of its review of Saxton Nuclear Experimental Corporation's (SNEC's) waste classification of the reactor vessel and its components, to the Non-Power reactors and Decommissioning Project Directorate (NPRDPD). DWM concluded that it had no objection to SNEC's blending of components for waste classification purposes and agreed with the classification of the components as Class C waste. SNEC was advised of the staff's waste classification review by NPRDPD memorandum, dated August 24,1998. Although this determination concerned the suitability of the material for disposal, the analyses performed involved average activity concentration and are directly applicable to the determination of the specific activity of the components for transportation purposes.
SNEC estimated the total activity of the SRVTS at 1285 curies, with 1282 curies contained as activated metal, and 3 curies as surface contamination. The SNEC classification shows that on average, the vessel and internals have a specific activity of 1.7 x 104 A2/g (<0.1 percent of the LSA-Ill limit), and that the lower guide blocks have the greatest specific activity, at 4 percent of the applicable LSA limit. On this basis, the components qualify as low specific activity material.
SNEC estimated the total activity of the SRVTS at 1285 curies, with 1282 curies contained as activated metal, and 3 curies as surface contamination. The SNEC classification shows that on average, the vessel and internals have a specific activity of 1.7 x 104 A2/g (<0.1 percent of the LSA-Ill limit), and that the lower guide blocks have the greatest specific activity, at 4 percent of the applicable LSA limit. On this basis, the components qualify as low specific activity material.

Latest revision as of 17:22, 10 December 2021

Responds to Requesting NRC Review Aspects of 980624 Application from Saxton Nuclear Experimental Corp & Gpu Nuclear,Inc for Regulatory Relief from DOT Shipping Requirements.Srvts Should Be Classified as LSA-III
ML20153C424
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/21/1998
From: Kane W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Boyle R
TRANSPORTATION, DEPT. OF
References
NUDOCS 9809240087
Download: ML20153C424 (2)


Text

. .

6 September 21, 1998 Mr. Rich:rd W. Boyla, Chitf t

Radioactive Materials Branch l Office of Hazardous Materials Technology U.S. Department of Transportation '

l 400 7th Street, SW Washington, DC 20590

SUBJECT:

TRANSPORTATION OF THE SAXTON REACTOR VESSEL

Dear Mr. Boyle:

1 By letter dated September 4,1998, you requested that the Spent Fuel Project Office review l aspects of the June 24,1998, application from the Saxton Nuclear Experimental Corporation and GPU Nuclear, Inc. (the applicants) for regulatory relief from U.S. Department of Transportation (DOT) shipping requirements. The application requested authorization to classify the reactor vessel from the Saxton Nuclear Experimental Facility (Saxton) as low specific activity (LSA) material and to transport it, under a specified transport plan, from Saxton to a disposal site in Barnwell, South Carolina. You requested our recommendation concerning issuance of an ,

exemption for the Saxton Reactor Vessel Transportation System (SRVTS) as LSA material. l We have reviewed the activation analysis method used by the applicants to determine the '

amount and distribution of radioactive material within the reactor vessel and the applicants'

( LSA-Ill determination. The use of the ORIGEN code by the applicants to determine activation l levels in the reactor vessel is acceptable to the staff. The applicant treated the reactor vessel components as a collection of solid c5jects and determined that the worse case component (lower guide blocks)is less than 4 percent of the LSA-ill limit. The staff finds the applicants' method of determining the specific activity of the reactor vessel to be acceptable.

Based on our review, we recommend that the SRVTS be classified as LSA-Ill (see enclosure).

If you have any questions concerning our review, please contact Mr. Earl Easton of my staff at 301-415-8520.

Sincerely,

[ Charles J. Haughney for:]

William F. Kane, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards ,

Docket No. 50-146 I

Enclosure:

As stated of91 09 NRC F/C NMSS r/f SFPO r/f AAdams, NRR hh PUBLIC ESchultz OFC SFPO* SFPO* SFPO -

SFPO d NAME JCook/lg/dd EEaston SSh an h b Kane k DATE 09/21 /98 09/21/98 /98 /%//98 C = COVEP E = COVER & ENCLOSURE N = NO COPY FILE NAME- A:\SAXTON.WPD (DIRK INCLUDED) OFFICIAL RECORD COPY 9809240087 980921 PDR ADOCK 05000146 P PDR

I 4

3 SAXTON REACTOR VESSEL TRANSPORTATION SYSTEM Determination as Low Specific Activity Material As part of the decommissioning of the GPU Saxton Nuclear Experimental Facility, various facility components must be shipped to a radioactive waste disposal facility. By letter dated September 4,1998, the U.S. Department of Transportation (DOT) requested NRC's recommendation conceming DOT issuance of an exemption to transport the Saxton Reactor Vessel Transportation System (SRVTS) as Low Specific Activity (LSA). At issue is whether the vessel, as prepared for transport, satisfies the applicable definition for LSA as provided in US Nuclear Regulatory Commission (NRC) and DOT regulations.

By memorandum dated August 19,1998, NRC's Division of Waste Management (DWM) provided the results of its review of Saxton Nuclear Experimental Corporation's (SNEC's) waste classification of the reactor vessel and its components, to the Non-Power reactors and Decommissioning Project Directorate (NPRDPD). DWM concluded that it had no objection to SNEC's blending of components for waste classification purposes and agreed with the classification of the components as Class C waste. SNEC was advised of the staff's waste classification review by NPRDPD memorandum, dated August 24,1998. Although this determination concerned the suitability of the material for disposal, the analyses performed involved average activity concentration and are directly applicable to the determination of the specific activity of the components for transportation purposes.

SNEC estimated the total activity of the SRVTS at 1285 curies, with 1282 curies contained as activated metal, and 3 curies as surface contamination. The SNEC classification shows that on average, the vessel and internals have a specific activity of 1.7 x 104 A2/g (<0.1 percent of the LSA-Ill limit), and that the lower guide blocks have the greatest specific activity, at 4 percent of the applicable LSA limit. On this basis, the components qualify as low specific activity material.

The regulations also require that the radioactive material be distributed throughout a collection of solid objects, such as the vessel components. This requirement was intended to prohibit the situation in which a small component with very high activity could be packaged with very low specific activity materials such that the package contents would still meet the overall LSA limit.

In an accident, if the high activity item were released, the public health hazard could be considerable. While there is variability in the radioactive material distribution in the vessel components, two factors provide reasonable assurance that components will not become separated in an accident: the components are permanently attached and all the components are grouted inside the vessel. Even if such an accident and separation were to occur, a scenario the staff believes to be non-creditable, the fact that each component meets the LSA definition by a wide margin tends to minimize the potential for impact on public health.

Accordingly, the staff believes an exemption from the " distributed throughout" requirement is warranted.

Staff concludes the SRVTS may be classified as LSA-Ill and has no objection to the issuance of an exemption for its transport as LSA material.

Enclosure