ML19087A064: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2019 Mr. Phil Noss Licensing Manager Orano Federal Services LLC 505 S. 336th Street, Suite 400 Federal Way, WA 98003
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2019 Mr. Phil Noss Licensing Manager Orano Federal Services LLC 505 S. 336th Street, Suite 400 Federal Way, WA 98003  


==SUBJECT:==
==SUBJECT:==
CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE
CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE  


==Dear Mr. Noss:==
==Dear Mr. Noss:==
As requested by your application dated July 19, 2018 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML18215A182], as supplemented on January 14, 2019 (ADAMS No. ML19017A066), enclosed is Certificate of Compliance No. 9379, Revision No. 0, for the Model No. 1105-SD transportation package. The staff's safety evaluation report is also enclosed.
As requested by your application dated July 19, 2018 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML18215A182], as supplemented on January 14, 2019 (ADAMS No. ML19017A066), enclosed is Certificate of Compliance No. 9379, Revision No. 0, for the Model No. 1105-SD transportation package. The staff's safety evaluation report is also enclosed.
The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of Title 49 of the Code of Federal Regulations 173.471.
The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of Title 49 of the Code of Federal Regulations 173.471.
If you have any questions regarding this certificate, please contact me or Norma García Santos of my staff at (301) 415-6999.
If you have any questions regarding this certificate, please contact me or Norma García Santos of my staff at (301) 415-6999.
Sincerely,
Sincerely,  
                                                /RA/
/RA/
Ilka T. Berrios, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9379 EPID L-2018-NEW-0002
Ilka T. Berrios, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9379 EPID L-2018-NEW-0002  


==Enclosures:==
==Enclosures:==
Line 38: Line 37:


==SUBJECT:==
==SUBJECT:==
CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE, DOCUMENT DATE: March 26, 2019 DISTRIBUTION: SFST r/f This closes CAC\Docket No.\EPID combination 001029\719379\L-2018-NEW-002.
CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE, DOCUMENT DATE: March 26, 2019 DISTRIBUTION: SFST r/f This closes CAC\\Docket No.\\EPID combination 001029\\719379\\L-2018-NEW-002.
G:\SFST\PART 71 CASEWORK\9379.r0.docx G:\SFST\PART 71 CASEWORK\9379.r0.LTR&SER.doc ADAMS Package No.: ML19087A063 LTR : ML19087A064           CoC: ML19087A065 OFFICE:     NMSS/DSFM     NMSS/DSFM       NMSS/DSFM     NMSS/DSFM NMSS/DSFM NAME:       NGarcía Santos   SFigueroa       HLindsay        JPiotter      JIreland by email       by email       by email     by email DATE:         3/11/19       3/11/19         3/11/19       3/15/2019     3/11/19 OFFICE:     NMSS/DSFM     NMSS/DSFM       NMSS/DSFM     NMSS/DSFM   NMSS/DSFM NAME:         WAllen         TAhn           ELove       DMarcano     DTang for Y.
G:\\SFST\\PART 71 CASEWORK\\9379.r0.docx G:\\SFST\\PART 71 CASEWORK\\9379.r0.LTR&SER.doc ADAMS Package No.: ML19087A063 LTR : ML19087A064 CoC: ML19087A065 OFFICE:
by email      by email        by email                Díaz-Sanabria by email DATE:         3/14/19       3/14/19         3/19/19       3/20/19       3/21/19 OFFICE:     NMSS/DSFM     NMSS/DSFM       NMSS/DSFM NAME:           TTate         MRahimi        IBerrios by email       by email DATE:         3/25/19       3/22/19         3/26/19 OFFICIAL RECORD COPY
NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:
NGarcía Santos SFigueroa by email HLindsay by email JPiotter by email JIreland by email DATE:
3/11/19 3/11/19 3/11/19 3/15/2019 3/11/19 OFFICE:
NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:
WAllen by email TAhn by email ELove by email DMarcano DTang for Y.
Díaz-Sanabria by email DATE:
3/14/19 3/14/19 3/19/19 3/20/19 3/21/19 OFFICE:
NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:
TTate by email MRahimi by email IBerrios DATE:
3/25/19 3/22/19 3/26/19 OFFICIAL RECORD COPY


UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 71-9379 Model No. 1105-SD Transportation Package Certificate of Compliance No. 9379 Revision No. 0
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 71-9379 Model No. 1105-SD Transportation Package Certificate of Compliance No. 9379 Revision No. 0  


==SUMMARY==
==SUMMARY==
 
By {{letter dated|date=July 19, 2018|text=letter dated July 19, 2018}} (Orano, 2018), as supplemented on January 14, 2019 (Orano, 2019), Orano Federal Services LLC (thereafter, Orano or the applicant), requested that the U.S.
By letter dated July 19, 2018 (Orano, 2018), as supplemented on January 14, 2019 (Orano, 2019), Orano Federal Services LLC (thereafter, Orano or the applicant), requested that the U.S.
Nuclear Regulatory Commission (NRC, the staff) approve the Model No. 1105-SD package as a Type B(U)-96 package for the transport of radioactive sealed sources (gamma, beta, and small neutron sources) or shielded irradiation devices containing their gamma sources. Quantities of fissile materials [e.g., plutonium-239 (239Pu)] are less than 15 grams.
Nuclear Regulatory Commission (NRC, the staff) approve the Model No. 1105-SD package as a Type B(U)-96 package for the transport of radioactive sealed sources (gamma, beta, and small neutron sources) or shielded irradiation devices containing their gamma sources. Quantities of fissile materials [e.g., plutonium-239 (239Pu)] are less than 15 grams.
The design of the Model No. 1105-SD package is based on the design of the Model No. 435-B, certificate of compliance (CoC) No. 9355, Revision 2 (NRC, 2018a). The staff issued Revision 2 of the Model No. 435-B on January 26, 2018 (NRC, 2018a).
The design of the Model No. 1105-SD package is based on the design of the Model No. 435-B, certificate of compliance (CoC) No. 9355, Revision 2 (NRC, 2018a). The staff issued Revision 2 of the Model No. 435-B on January 26, 2018 (NRC, 2018a).
The staff reviewed the application for the Model No. 435-B, including relevant information in the supplements to the application, using the guidance in NUREG-1609, Standard Review Plan for Transportation Packages for Radioactive Material. This guidance also applies to the review of Model No. 1105-SD. Based on the statements and representations in the application, as supplemented, and the conditions listed below, the staff concludes that the Model No. 1105-SD meets the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71, Packaging and Transportation of Radioactive Material.
The staff reviewed the application for the Model No. 435-B, including relevant information in the supplements to the application, using the guidance in NUREG-1609, Standard Review Plan for Transportation Packages for Radioactive Material. This guidance also applies to the review of Model No. 1105-SD. Based on the statements and representations in the application, as supplemented, and the conditions listed below, the staff concludes that the Model No. 1105-SD meets the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71, Packaging and Transportation of Radioactive Material.
EVALUATION The Model No. 1105-SD package is based on the design of the Model No. 435-B, CoC No.
EVALUATION The Model No. 1105-SD package is based on the design of the Model No. 435-B, CoC No.
9355, Revision 2 (NRC, 2018a). In Attachment 2 to the letter dated July 19, 2018 (Orano, 2018), the applicant included a road map related to the changes corresponding to the safety analysis report corresponding to Revision 2 of the CoC for to the Model No. 435-B compared to the application for the Model No. 1105-SD. The staff reviewed the application for the Model No.
9355, Revision 2 (NRC, 2018a). In Attachment 2 to the {{letter dated|date=July 19, 2018|text=letter dated July 19, 2018}} (Orano, 2018), the applicant included a road map related to the changes corresponding to the safety analysis report corresponding to Revision 2 of the CoC for to the Model No. 435-B compared to the application for the Model No. 1105-SD. The staff reviewed the application for the Model No.
1105-SD, Revision 0, and compared it to the safety analysis report corresponding to Revision 2 of the CoC for the 435-B and found that the two package designs are essentially the same. The main changes to the safety analysis report corresponding to CoC, Revision 2, of the Model No.
1105-SD, Revision 0, and compared it to the safety analysis report corresponding to Revision 2 of the CoC for the 435-B and found that the two package designs are essentially the same. The main changes to the safety analysis report corresponding to CoC, Revision 2, of the Model No.
435-B were as follows:
435-B were as follows:
: 1)       editorial differences related to the change to Model No. 1105-SD from Model No. 435-B (e.g., drawing numbers);
: 1) editorial differences related to the change to Model No. 1105-SD from Model No. 435-B (e.g., drawing numbers);
: 2)       changes related to the change of the package model number, Enclosure 2
: 2) changes related to the change of the package model number,
: 3)     commitment to the use of the American National Standards Institute (ANSI) N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment (ANSI, 2014).
: 3) commitment to the use of the American National Standards Institute (ANSI) N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment (ANSI, 2014).
In the January 14, 2019, letter (Orano, 2019), the applicant supplemented its application by responding to a request for supplemental information (NRC. 2018c) as part of the acceptance review of the application (NRC, 2019). As part of the response to question RSI-1, the applicant included a list of documents that constitute the licensing basis for the Model No. 1105-SD.
In the {{letter dated|date=January 14, 2019|text=January 14, 2019, letter}} (Orano, 2019), the applicant supplemented its application by responding to a request for supplemental information (NRC. 2018c) as part of the acceptance review of the application (NRC, 2019). As part of the response to question RSI-1, the applicant included a list of documents that constitute the licensing basis for the Model No. 1105-SD.
(Appendix A of this Safety Evaluation Report includes the list of documents provided by the applicant in its January 2019 letter.) The staff considers the information provided in the January 14, 2019, letter part of the application for Revision 0 for the Model No. 1105-SD package.
(Appendix A of this Safety Evaluation Report includes the list of documents provided by the applicant in its January 2019 letter.) The staff considers the information provided in the {{letter dated|date=January 14, 2019|text=January 14, 2019, letter}} part of the application for Revision 0 for the Model No. 1105-SD package.
In observation OBS-Co-1 (NRC. 2018c), the staff requested clarification about the applicants requirements to develop and approve procedures to perform leak tests to verify the applicants commitment to follow the 2014 Edition of ANSI N14.5 (ANSI, 2014). Moreover, the staff wanted to ensure the following:
In observation OBS-Co-1 (NRC. 2018c), the staff requested clarification about the applicants requirements to develop and approve procedures to perform leak tests to verify the applicants commitment to follow the 2014 Edition of ANSI N14.5 (ANSI, 2014). Moreover, the staff wanted to ensure the following:
: 1)     personnel developing and approving leakage rate testing procedures is certified as an American Society for Nondestructive Testing (ASNT) nondestructive testing (NDT)
: 1) personnel developing and approving leakage rate testing procedures is certified as an American Society for Nondestructive Testing (ASNT) nondestructive testing (NDT)
Level III, and
Level III, and
: 2)     personnel performing leakage rate testing is qualified and certified in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT), in accordance with Sections 8.5, Leakage rate testing, and 8.8, Quality assurance, of ANSI N14.5-2014 (ANSI, 2014).
: 2) personnel performing leakage rate testing is qualified and certified in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT), in accordance with Sections 8.5, Leakage rate testing, and 8.8, Quality assurance, of ANSI N14.5-2014 (ANSI, 2014).
The applicant noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing procedures must be approved by personnel certified as an ASNT NDT Level III. The staff finds the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014). The applicant also noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing must be performed by personal qualified and certified personnel in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT). The staff also finds this part of the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014).
The applicant noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing procedures must be approved by personnel certified as an ASNT NDT Level III. The staff finds the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014). The applicant also noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing must be performed by personal qualified and certified personnel in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT). The staff also finds this part of the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014).
The applicant summarized in the response to OBS-Co-1 (Orano, 2019) that written leakage rate testing procedures for the 1105-SD package are developed, approved, and performed by qualified and certified NDT personnel for leakage testing in accordance with industry standards.
The applicant summarized in the response to OBS-Co-1 (Orano, 2019) that written leakage rate testing procedures for the 1105-SD package are developed, approved, and performed by qualified and certified NDT personnel for leakage testing in accordance with industry standards.
The staff confirmed that ANSI N14.5-2014 is referenced in Chapters 7 and 8 of the application and that Chapters 7 and 8 are also referenced in the CoC. The applicant will use the NRC-approved quality assurance program under Docket No. 71-0938 (NRC, 2018b) for this package (Orano, 2019).
The staff confirmed that ANSI N14.5-2014 is referenced in Chapters 7 and 8 of the application and that Chapters 7 and 8 are also referenced in the CoC. The applicant will use the NRC-approved quality assurance program under Docket No. 71-0938 (NRC, 2018b) for this package (Orano, 2019).
EVALUATION FINDINGS The staff concludes that besides the above described differences and other minor editorial differences (e.g., replace 435-B with 1105-SD), the two applications are essentially the same, with the exceptions noted in Attachment 2 to the application submitted in July 2018). As the package design has already been approved as part of the 435-B technical review, the staff concludes that the same safety evaluation findings can be made for the 1105-SD.
EVALUATION FINDINGS The staff concludes that besides the above described differences and other minor editorial differences (e.g., replace 435-B with 1105-SD), the two applications are essentially the same, with the exceptions noted in Attachment 2 to the application submitted in July 2018). As the package design has already been approved as part of the 435-B technical review, the staff concludes that the same safety evaluation findings can be made for the 1105-SD.  


Based on the statements and representation in the application, as supplemented, and the conditions listed below, the staff concludes that the package design meets the requirements of 10 CFR Part 71 and is described in sufficient detail to provide an adequate basis for its evaluation.
Based on the statements and representation in the application, as supplemented, and the conditions listed below, the staff concludes that the package design meets the requirements of 10 CFR Part 71 and is described in sufficient detail to provide an adequate basis for its evaluation.
REFERENCES (ANSI, 2014)             American National Standards Institute, ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, ANSI, New York, NY.
REFERENCES (ANSI, 2014)
(ASNT)                   American Society for Nondestructive Testing (ASNT) Recommended Practice No. SNT-TC-1A, Personnel Qualification and Certification in Nondestructive Testing, ASNT, Columbus, OH.
American National Standards Institute, ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, ANSI, New York, NY.
(NRC, 2018a)             Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Al-Daouk, Ahmad M., National Nuclear Security Administration (NNSA),
(ASNT)
American Society for Nondestructive Testing (ASNT) Recommended Practice No. SNT-TC-1A, Personnel Qualification and Certification in Nondestructive Testing, ASNT, Columbus, OH.
(NRC, 2018a)
Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Al-Daouk, Ahmad M., National Nuclear Security Administration (NNSA),
January 26, 2018, Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML18026A874.
January 26, 2018, Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML18026A874.
(NRC, 2018b)             Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Lloyd, Christopher, Orano Federal Services (Orano), June 4, 2018, ADAMS Package Accession No. ML18155A238.
(NRC, 2018b)
(NRC, 2018c)             García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),
Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Lloyd, Christopher, Orano Federal Services (Orano), June 4, 2018, ADAMS Package Accession No. ML18155A238.
(NRC, 2018c)
García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),
letter to Noss, Phillip, Orano Federal Services LLC (ORANO), December 21, 2018, ADAMS Package Accession No. ML18360A572.
letter to Noss, Phillip, Orano Federal Services LLC (ORANO), December 21, 2018, ADAMS Package Accession No. ML18360A572.
(NRC, 2019)             García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),
(NRC, 2019)
García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),
letter to Noss, Phillip, Orano Federal Services LLC (ORANO), February 6, 2019, ADAMS Package Accession No. ML19036A911.
letter to Noss, Phillip, Orano Federal Services LLC (ORANO), February 6, 2019, ADAMS Package Accession No. ML19036A911.
(Orano, 2018)           Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.
(Orano, 2018)
Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.
Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),
Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),
July 19, 2018, ADAMS Package Accession No. ML18215A243.
July 19, 2018, ADAMS Package Accession No. ML18215A243.
(Orano, 2019)           Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.
(Orano, 2019)
Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.
Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),
Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),
January 14, 2019, ADAMS Package Accession No. ML19017A066.
January 14, 2019, ADAMS Package Accession No. ML19017A066.
CONDITIONS The conditions for the CoC for the 1105-SD are the same as CoC, Revision 2, for the Model No.
CONDITIONS The conditions for the CoC for the 1105-SD are the same as CoC, Revision 2, for the Model No.
435-B, with the following main exceptions:
435-B, with the following main exceptions:
: 1)     CoC holders information,
: 1)
: 2)     applications title,
CoC holders information,
: 3)     references to the Model No. 1105-SD instead of the Model No. 435-B, and
: 2) applications title,
: 4)     changes in drawing names.
: 3) references to the Model No. 1105-SD instead of the Model No. 435-B, and
: 4) changes in drawing names.
The expiration date for this CoC is March 31, 2024.
The expiration date for this CoC is March 31, 2024.
CONCLUSION Based on the statements and representations contained in the application, as supplemented, and the conditions listed above, the staff concludes that the applicant adequately described and evaluated the design of the Model No. 1105-SD transportation package and that the package meets the requirements of 10 CFR Part 71.
CONCLUSION Based on the statements and representations contained in the application, as supplemented, and the conditions listed above, the staff concludes that the applicant adequately described and evaluated the design of the Model No. 1105-SD transportation package and that the package meets the requirements of 10 CFR Part 71.
Issued with Certificate of Compliance No. 9379, Revision No. 0, on 3/26/19.
Issued with Certificate of Compliance No. 9379, Revision No. 0, on 3/26/19.
Appendix A. Licensing Basis Documents Applicable to the Model No. 1105-SD (Orano, 2019)
Appendix A. Licensing Basis Documents Applicable to the Model No. 1105-SD (Orano, 2019)
Revision Discipline           Title       Document Number     Documentum                 Date              Description No.
Discipline Title Document Number Documentum Revision No.
This calculation forms the basis "435-B Drop 01916.01.C004.01-07 CALC-3006972-000     0     5/14/12 for Section 2.12.4 SAR. This Analysis" analysis includes computer files.
Date Description Structural "435-B Drop Analysis" 01916.01.C004.01-07 CALC-3006972-000 0
This calculation forms a partial Structural  "435-B Weight                                                               basis for the structural analysis in 01916.01.C004.01-01 CALC-3003541-000     0       3/1/12 Calculation"                                                                the SAR. This analysis includes computer files.
5/14/12 This calculation forms the basis for Section 2.12.4 SAR. This analysis includes computer files.  
              "Buckling Analysis                                                           This calculation forms a partial for the Model No.                                                           basis for the structural analysis in 01916.01.C004.01-02 CALC-3003967-000     0       2/7/11 LANL-B" (i.e.,                                                              the SAR. This analysis includes Model No. 435-B)                                                            computer files.
"435-B Weight Calculation" 01916.01.C004.01-01 CALC-3003541-000 0
              "Thermal and Gas                                                             This calculation forms the basis Generation                                                                   for the thermal evaluation in the Thermal                        01916.01.C004.01-08 CALC-3007066-005     5     1/25/17 Analysis for the                                                             SAR. This analysis includes 435-B Package"                                                              computer files.
3/1/12 This calculation forms a partial basis for the structural analysis in the SAR. This analysis includes computer files.  
This calculation forms the basis "LANL-B Device 01916.01.C004.01-05 CALC-3006640-001     1     4/11/12 for Section 5.5.3 of the SAR. This Shielding Analysis" analysis includes computer files.
"Buckling Analysis for the Model No.
Shielding                                                                                This calculation forms the basis "435-B LTSS                                                                 for the shielding analysis in the 01916.01.C004.01-06 CALC-3006972-001     1     9/10/15 Shielding Analysis"                                                          SAR. This analysis includes computer files.
LANL-B" (i.e.,
Includes the description of the "435-B Package                                                               requirements of the certification Certification Test   PKG-TP-SPC-008   SPC-3004633-002     2     11/2/11 tests to be performed on the 435-Procedure"                                                                  B with a LTSS and Shielded Certification Device.
Model No. 435-B) 01916.01.C004.01-02 CALC-3003967-000 0
Test This calculation forms the basis "435-B Package for Section 2.12.3 of the SAR.
2/7/11 This calculation forms a partial basis for the structural analysis in the SAR. This analysis includes computer files.
Certification Test   PKG-TR-SPC-011   SPC-3006329-001     1     4/17/12 This analysis includes computer Report" files.}}
Thermal "Thermal and Gas Generation Analysis for the 435-B Package" 01916.01.C004.01-08 CALC-3007066-005 5
1/25/17 This calculation forms the basis for the thermal evaluation in the SAR. This analysis includes computer files.
Shielding "LANL-B Device Shielding Analysis" 01916.01.C004.01-05 CALC-3006640-001 1
4/11/12 This calculation forms the basis for Section 5.5.3 of the SAR. This analysis includes computer files.  
"435-B LTSS Shielding Analysis" 01916.01.C004.01-06 CALC-3006972-001 1
9/10/15 This calculation forms the basis for the shielding analysis in the SAR. This analysis includes computer files.
Certification Test "435-B Package Certification Test Procedure" PKG-TP-SPC-008 SPC-3004633-002 2
11/2/11 Includes the description of the requirements of the certification tests to be performed on the 435-B with a LTSS and Shielded Device.  
"435-B Package Certification Test Report" PKG-TR-SPC-011 SPC-3006329-001 1
4/17/12 This calculation forms the basis for Section 2.12.3 of the SAR.
This analysis includes computer files.}}

Latest revision as of 04:02, 5 January 2025

Letter to P. Noss Certificate of Compliance No. 9379, Rev No. 0, for the Model No. 1105-SD Transportation Package (W/Enclosure 2)
ML19087A064
Person / Time
Site: 07109379
Issue date: 03/26/2019
From: Ilka Berrios
Spent Fuel Licensing Branch
To: Noss P
Orano Federal Services
Santos N
Shared Package
ML19087A063 List:
References
EPID L-2018-NEW-0002
Download: ML19087A064 (6)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2019 Mr. Phil Noss Licensing Manager Orano Federal Services LLC 505 S. 336th Street, Suite 400 Federal Way, WA 98003

SUBJECT:

CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE

Dear Mr. Noss:

As requested by your application dated July 19, 2018 [Agencywide Documents Access and Management System (ADAMS) Accession No. ML18215A182], as supplemented on January 14, 2019 (ADAMS No. ML19017A066), enclosed is Certificate of Compliance No. 9379, Revision No. 0, for the Model No. 1105-SD transportation package. The staff's safety evaluation report is also enclosed.

The approval constitutes authority to use the package for shipment of radioactive material and for the package to be shipped in accordance with the provisions of Title 49 of the Code of Federal Regulations 173.471.

If you have any questions regarding this certificate, please contact me or Norma García Santos of my staff at (301) 415-6999.

Sincerely,

/RA/

Ilka T. Berrios, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No. 71-9379 EPID L-2018-NEW-0002

Enclosures:

1. Certificate of Compliance No. 9379, Rev. No. 0
2. Safety Evaluation Report cc w/encls: R. Boyle, U.S. DOT J. Shuler, U.S. DOE, c/o L. F. Gelder

SUBJECT:

CERTIFICATE OF COMPLIANCE NO. 9379, REVISION NO. 0, FOR THE MODEL NO. 1105-SD TRANSPORTATION PACKAGE, DOCUMENT DATE: March 26, 2019 DISTRIBUTION: SFST r/f This closes CAC\\Docket No.\\EPID combination 001029\\719379\\L-2018-NEW-002.

G:\\SFST\\PART 71 CASEWORK\\9379.r0.docx G:\\SFST\\PART 71 CASEWORK\\9379.r0.LTR&SER.doc ADAMS Package No.: ML19087A063 LTR : ML19087A064 CoC: ML19087A065 OFFICE:

NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:

NGarcía Santos SFigueroa by email HLindsay by email JPiotter by email JIreland by email DATE:

3/11/19 3/11/19 3/11/19 3/15/2019 3/11/19 OFFICE:

NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:

WAllen by email TAhn by email ELove by email DMarcano DTang for Y.

Díaz-Sanabria by email DATE:

3/14/19 3/14/19 3/19/19 3/20/19 3/21/19 OFFICE:

NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME:

TTate by email MRahimi by email IBerrios DATE:

3/25/19 3/22/19 3/26/19 OFFICIAL RECORD COPY

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 71-9379 Model No. 1105-SD Transportation Package Certificate of Compliance No. 9379 Revision No. 0

SUMMARY

By letter dated July 19, 2018 (Orano, 2018), as supplemented on January 14, 2019 (Orano, 2019), Orano Federal Services LLC (thereafter, Orano or the applicant), requested that the U.S.

Nuclear Regulatory Commission (NRC, the staff) approve the Model No. 1105-SD package as a Type B(U)-96 package for the transport of radioactive sealed sources (gamma, beta, and small neutron sources) or shielded irradiation devices containing their gamma sources. Quantities of fissile materials [e.g., plutonium-239 (239Pu)] are less than 15 grams.

The design of the Model No. 1105-SD package is based on the design of the Model No. 435-B, certificate of compliance (CoC) No. 9355, Revision 2 (NRC, 2018a). The staff issued Revision 2 of the Model No. 435-B on January 26, 2018 (NRC, 2018a).

The staff reviewed the application for the Model No. 435-B, including relevant information in the supplements to the application, using the guidance in NUREG-1609, Standard Review Plan for Transportation Packages for Radioactive Material. This guidance also applies to the review of Model No. 1105-SD. Based on the statements and representations in the application, as supplemented, and the conditions listed below, the staff concludes that the Model No. 1105-SD meets the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 71, Packaging and Transportation of Radioactive Material.

EVALUATION The Model No. 1105-SD package is based on the design of the Model No. 435-B, CoC No.

9355, Revision 2 (NRC, 2018a). In Attachment 2 to the letter dated July 19, 2018 (Orano, 2018), the applicant included a road map related to the changes corresponding to the safety analysis report corresponding to Revision 2 of the CoC for to the Model No. 435-B compared to the application for the Model No. 1105-SD. The staff reviewed the application for the Model No.

1105-SD, Revision 0, and compared it to the safety analysis report corresponding to Revision 2 of the CoC for the 435-B and found that the two package designs are essentially the same. The main changes to the safety analysis report corresponding to CoC, Revision 2, of the Model No.

435-B were as follows:

1) editorial differences related to the change to Model No. 1105-SD from Model No. 435-B (e.g., drawing numbers);
2) changes related to the change of the package model number,
3) commitment to the use of the American National Standards Institute (ANSI) N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment (ANSI, 2014).

In the January 14, 2019, letter (Orano, 2019), the applicant supplemented its application by responding to a request for supplemental information (NRC. 2018c) as part of the acceptance review of the application (NRC, 2019). As part of the response to question RSI-1, the applicant included a list of documents that constitute the licensing basis for the Model No. 1105-SD.

(Appendix A of this Safety Evaluation Report includes the list of documents provided by the applicant in its January 2019 letter.) The staff considers the information provided in the January 14, 2019, letter part of the application for Revision 0 for the Model No. 1105-SD package.

In observation OBS-Co-1 (NRC. 2018c), the staff requested clarification about the applicants requirements to develop and approve procedures to perform leak tests to verify the applicants commitment to follow the 2014 Edition of ANSI N14.5 (ANSI, 2014). Moreover, the staff wanted to ensure the following:

1) personnel developing and approving leakage rate testing procedures is certified as an American Society for Nondestructive Testing (ASNT) nondestructive testing (NDT)

Level III, and

2) personnel performing leakage rate testing is qualified and certified in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT), in accordance with Sections 8.5, Leakage rate testing, and 8.8, Quality assurance, of ANSI N14.5-2014 (ANSI, 2014).

The applicant noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing procedures must be approved by personnel certified as an ASNT NDT Level III. The staff finds the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014). The applicant also noted in its response to OBS-Co-1 (Orano, 2019) that leakage rate testing must be performed by personal qualified and certified personnel in accordance with ASNT Recommended Practice No. SNT-TC-1A (ASNT). The staff also finds this part of the applicants response acceptable based on the staffs review of Sections 8.5 and 8.8 of ANSI N14.5-2014 (ANSI, 2014).

The applicant summarized in the response to OBS-Co-1 (Orano, 2019) that written leakage rate testing procedures for the 1105-SD package are developed, approved, and performed by qualified and certified NDT personnel for leakage testing in accordance with industry standards.

The staff confirmed that ANSI N14.5-2014 is referenced in Chapters 7 and 8 of the application and that Chapters 7 and 8 are also referenced in the CoC. The applicant will use the NRC-approved quality assurance program under Docket No. 71-0938 (NRC, 2018b) for this package (Orano, 2019).

EVALUATION FINDINGS The staff concludes that besides the above described differences and other minor editorial differences (e.g., replace 435-B with 1105-SD), the two applications are essentially the same, with the exceptions noted in Attachment 2 to the application submitted in July 2018). As the package design has already been approved as part of the 435-B technical review, the staff concludes that the same safety evaluation findings can be made for the 1105-SD.

Based on the statements and representation in the application, as supplemented, and the conditions listed below, the staff concludes that the package design meets the requirements of 10 CFR Part 71 and is described in sufficient detail to provide an adequate basis for its evaluation.

REFERENCES (ANSI, 2014)

American National Standards Institute, ANSI N14.5-2014, American National Standard for Radioactive Materials - Leakage Tests on Packages for Shipment, ANSI, New York, NY.

(ASNT)

American Society for Nondestructive Testing (ASNT) Recommended Practice No. SNT-TC-1A, Personnel Qualification and Certification in Nondestructive Testing, ASNT, Columbus, OH.

(NRC, 2018a)

Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Al-Daouk, Ahmad M., National Nuclear Security Administration (NNSA),

January 26, 2018, Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML18026A874.

(NRC, 2018b)

Rahimi, Meraj, U. S. Nuclear Regulatory Commission (NRC), letter to Lloyd, Christopher, Orano Federal Services (Orano), June 4, 2018, ADAMS Package Accession No. ML18155A238.

(NRC, 2018c)

García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),

letter to Noss, Phillip, Orano Federal Services LLC (ORANO), December 21, 2018, ADAMS Package Accession No. ML18360A572.

(NRC, 2019)

García Santos, Norma, U.S. Nuclear Regulatory Commission (NRC),

letter to Noss, Phillip, Orano Federal Services LLC (ORANO), February 6, 2019, ADAMS Package Accession No. ML19036A911.

(Orano, 2018)

Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.

Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),

July 19, 2018, ADAMS Package Accession No. ML18215A243.

(Orano, 2019)

Noss, Phillip, Orano Federal Services LLC (ORANO), letter to U. S.

Nuclear Regulatory Commission (NRC) (Attn: Document Control Desk),

January 14, 2019, ADAMS Package Accession No. ML19017A066.

CONDITIONS The conditions for the CoC for the 1105-SD are the same as CoC, Revision 2, for the Model No.

435-B, with the following main exceptions:

1)

CoC holders information,

2) applications title,
3) references to the Model No. 1105-SD instead of the Model No. 435-B, and
4) changes in drawing names.

The expiration date for this CoC is March 31, 2024.

CONCLUSION Based on the statements and representations contained in the application, as supplemented, and the conditions listed above, the staff concludes that the applicant adequately described and evaluated the design of the Model No. 1105-SD transportation package and that the package meets the requirements of 10 CFR Part 71.

Issued with Certificate of Compliance No. 9379, Revision No. 0, on 3/26/19.

Appendix A. Licensing Basis Documents Applicable to the Model No. 1105-SD (Orano, 2019)

Discipline Title Document Number Documentum Revision No.

Date Description Structural "435-B Drop Analysis" 01916.01.C004.01-07 CALC-3006972-000 0

5/14/12 This calculation forms the basis for Section 2.12.4 SAR. This analysis includes computer files.

"435-B Weight Calculation" 01916.01.C004.01-01 CALC-3003541-000 0

3/1/12 This calculation forms a partial basis for the structural analysis in the SAR. This analysis includes computer files.

"Buckling Analysis for the Model No.

LANL-B" (i.e.,

Model No. 435-B) 01916.01.C004.01-02 CALC-3003967-000 0

2/7/11 This calculation forms a partial basis for the structural analysis in the SAR. This analysis includes computer files.

Thermal "Thermal and Gas Generation Analysis for the 435-B Package" 01916.01.C004.01-08 CALC-3007066-005 5

1/25/17 This calculation forms the basis for the thermal evaluation in the SAR. This analysis includes computer files.

Shielding "LANL-B Device Shielding Analysis" 01916.01.C004.01-05 CALC-3006640-001 1

4/11/12 This calculation forms the basis for Section 5.5.3 of the SAR. This analysis includes computer files.

"435-B LTSS Shielding Analysis" 01916.01.C004.01-06 CALC-3006972-001 1

9/10/15 This calculation forms the basis for the shielding analysis in the SAR. This analysis includes computer files.

Certification Test "435-B Package Certification Test Procedure" PKG-TP-SPC-008 SPC-3004633-002 2

11/2/11 Includes the description of the requirements of the certification tests to be performed on the 435-B with a LTSS and Shielded Device.

"435-B Package Certification Test Report" PKG-TR-SPC-011 SPC-3006329-001 1

4/17/12 This calculation forms the basis for Section 2.12.3 of the SAR.

This analysis includes computer files.

Retrieved from "https://kanterella.com/w/index.php?title=ML19087A064&oldid=4934366"