Letter Sequence Acceptance Review |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, ... further results|Request]]
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, ... further results|Supplement]]
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, ... further results|Meeting]]
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, ... further results|Approval]]
Other: L-18-006, ISFSI - Site-Specific License Renewal Application, Revision 0, July 2018, L-23-005, Independent Spent Fuel Storage Installation License Renewal Application, Revision 1 (Cac/Epid No. 001028/L-2022-RNW-0007), ML17311A450, ML18018A018, ML18022A077, ML18022A078, ML18022A079, ML18087A056, ML18087A057, ML18087A058, ML18087A059, ML18087A060, ML18087A061, ML18087A062, ML18100A185, ML18100A188, ML18100A190, ML18100A191, ML18100A193, ML18101A024, ML18108A052, ML18131A047, ML18131A048, ML18141A561, ML18141A562, ML18141A563, ML18141A564, ML18141A565, ML18141A567, ML18179A258, ML18179A260, ML18179A266, ML18201A455, ML18205A179, ML18222A351, ML18228A530, ML18228A531, ML18228A532, ML18228A533, ML18234A012, ML18248A121, ML18255A093, ML18255A094, ML18255A096, ML18255A097, ML18255A098, ML18255A101, ML18255A102, ML18324A577, ML18324A594... further results
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MONTHYEARML19255E7911997-05-31031 May 1997
Enclosure 1 - Ecological Assessment of the Low Level Waste Depository, Andrews County, Tx
Project stage: Other
ML19255E7952004-10-25025 October 2004
Enclosure 2 - Habitat Characterization and Rare Species Survey for the Proposed Low Level Waste Repository, Andrews County, Tx
Project stage: Other
ML19337B5182007-03-16016 March 2007
Enclosure 10 - Applicable Sections of LLRW License
Project stage: Other
ML19255E7982007-03-16016 March 2007
Enclosure 3 - Supplemental Survey to Ecological Assessment of the Low Level Waste Depository, Andrews County, Texas
Project stage: Supplement
ML19217A2112007-04-30030 April 2007
Enclosure 1 - Report on Mapping of a Trench Through Pedogenic Calcrete (Caliche) Across a Drainage and Possible Lineament, Waste Control Specialists Disposal Site, Andrews County, Tx (Public)
Project stage: Other
ML19255E8002008-07-0303 July 2008
Enclosure 4 - Environmental Assessment Report Prepared for Application for Renewal of Radioactive Material License R04971 Waste Control Specialists LLC Andrews County, Texas
Project stage: Request
ML19217A2142008-07-28028 July 2008
Enclosure 4 - Report on Activities to Satisfy Byproduct RML Conditions 41A, 41C, and 43, July 2008 (Public)
Project stage: Other
ML19217A2132011-02-22022 February 2011
Enclosure 3 - Oag Water Levels: Empirical and Modeled Relationships Between Precipitation and Infiltration, 2011 (Public)
Project stage: Other
ML18100A1882013-04-11011 April 2013
Enclosure 7 - Procedure 12751-MNGP-QP-9.201, Revision 0, Visual Weld Examination
Project stage: Other
ML18100A1852013-04-11011 April 2013
Enclosure 6 - Procedure 12751-MNGP-OPS-01, Revision 0, Spent Fuel Cask Welding: 61BT/BTH NUHOMS Canisters
Project stage: Other
ML18100A1912014-01-30030 January 2014
Enclosure 9 - Structural Integrity Associates, Inc. Report 130415.402, Revision 0, Review of Trivis Inc. Welding Procedures Used for Field Welds on the Transnuclear NUHOMS 61BTH Type 1 & 2 Transportable Canister for BWR Fuel
Project stage: Other
ML18100A1902014-05-22022 May 2014
Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records
Project stage: Other
ML18011A1582017-12-22022 December 2017
International HI-STORE Cis (Consolidated Interim Storage Facility) License Application Responses to Safeguards Related Requests for Supplemental Information
Project stage: Supplement
ML17249A1572018-01-11011 January 2018, 16 January 2018
Package: Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years
Project stage: Request
ML18022A1512018-01-16016 January 2018
Memo to A. Hsia Summary of December 12, 2017, Meeting with Pacific Gas & Electric Company to Discuss the Upcoming Submittal of the Application for Renewal of the Humboldt Bay Independent Spent Fuel Storage Installation License
Project stage: Meeting
ML18022A1532018-01-16016 January 2018
Enclosure 2: Agenda (Memo to A. Hsia Summary of December 12, 2017, Meeting with Pacific Gas & Electric Company to Discuss the Upcoming Submittal of the Application for Renewal of the Humboldt Bay ISFSI License)
Project stage: Meeting
ML17249A1592018-01-16016 January 2018
Letter to C. C. Chappell Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years
Project stage: Approval
ML18022A1542018-01-16016 January 2018
Enclosure 3: Handout-PG&E Presentation on Humboldt Bay ISFSI LRA (Memo to A. Hsia Summary of December 12, 2017, Meeting)
Project stage: Meeting
ML18022A1522018-01-16016 January 2018
Enclosure 1: Meeting Attendees (Memo to A. Hsia Summary of December 12, 2017, Meeting with Pacific Gas & Electric Company to Discuss the Upcoming Submittal of the Application for Renewal of the Humboldt Bay ISFSI License)
Project stage: Meeting
ML18018A0182018-01-17017 January 2018
Letter to K. Manzione Application for Holtec International HI-STORM Umax Multipurpose Canister Storage System License Amendment Request No. 3 to Certificate of Compliance No. 1040 - Accepted for Review
Project stage: Other
ML18018A0192018-01-17017 January 2018
Enclosurequest for Additional Information (Ltr to K. Manzione Application for Holtec International HI-STORM Umax Multipurpose Canister Storage System License Amendment Request No. 3 to Certificate of Compliance No. 1040-Accepted for Review)
Project stage: RAI
ML18018B2972018-01-19019 January 2018
Federal Registered Notice: Correction of Certificate of Compliance No. 1004, Renewed Amendments No. 11, Revision 1 and No. 13, Revision 1
Project stage: Request
ML18022A6122018-01-19019 January 2018
Letter to K. Manzione Amendment No. 4 to Certificate of Compliance No. 1032 for the HI-STORM Flood/Wind Multipurpose Canister Storage System-Request for Additional Information
Project stage: RAI
ML18022A0782018-01-22022 January 2018
Enclosure 1: Revised Title for Figure 1-5 Corrected Technical Specifications for Certificate of Compliance No. 1004 Renewed Amendment No. 11, Revision 1 Enclosure 1
Project stage: Other
ML18022A0792018-01-22022 January 2018
Enclosure 2: Revised Title for Figure 1-5 Corrected Technical Specifications for Certificate of Compliance No. 1004 Renewed Amendment No. 13, Revision 1
Project stage: Other
ML18022A0772018-01-22022 January 2018
Letter to J. Bondre Correction to Tn Americas LLC Technical Specifications for Renewed Amendments No. 11, Revision 1 and No. 13, Revision 1 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks
Project stage: Other
ML18022A0762018-01-22022 January 2018
Package: Correction to Title of Figure 1-15 in Technical Specifications for Certificate of Compliance 1004 Renewed Amendments No. 11, Revision 1 and No. 13, Revision 1
Project stage: Request
ML18024A2732018-01-24024 January 2018
Letter to D. G. Stoddard U.S. NRC Approval of Virginia Electric and Power Company Request for Withholding Information from Public Disclosure for North Anna Power Station ISFSI (Cac/Epid Nos. 001028/L-2017-RNW-0010 and 000993/L-2017-LNE-0008
Project stage: Withholding Request Acceptance
ML18031A4572018-01-31031 January 2018
Submittal Date for Response to NRCs Requests for Additional Information (Rais) for License Amendment Request 1032-4 to HI-STORM FW CoC No. 1032 (CAC No. 001028)
Project stage: Request
ML17311A4502018-01-31031 January 2018
ISFSI License Renewal Final Environmental Assessment
Project stage: Other
ML18036A2222018-02-0101 February 2018
International - Transmittal of HI-STORM Umax License Amendment Request No. 3 - Administrative RAI Response
Project stage: Request
ML17298A1342018-02-0202 February 2018
Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005)
Project stage: Approval
ML17298A1352018-02-0202 February 2018
Safety Evaluation Report (Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005)
Project stage: Approval
ML18031A2282018-02-0606 February 2018
Enclosure 2: Safety Evaluation Report (Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station ISFSI)
Project stage: Approval
ML18031A2252018-02-0606 February 2018
Enclosurenewed License SNM-2507 (Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station Independent Spent Fuel Storage Installation)
Project stage: Approval
ML18031A2272018-02-0606 February 2018
Enclosurenewed License SNM-2507 Technical Specifications (Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station ISFSI)
Project stage: Approval
ML18031A2222018-02-0606 February 2018
Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2017-RNW-0010 and 000993/L-2017-LNE-0008)
Project stage: Approval
ML18031A2242018-02-0606 February 2018
Enclosure 1: Preamble-SNM-2507 License Renewal Order (Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station Independent Spent Fuel Storage Installation)
Project stage: Approval
ML18031A2312018-02-0808 February 2018
Federal Register Notice - Notice of Issuance for License Renewal (Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station ISFSI)
Project stage: Approval
ML18053A2222018-02-15015 February 2018
Application for Amendment 1 to the NUHOMS Eos System, Revision O (Docket No. 72-1042)
Project stage: Request
ML18053A2332018-02-15015 February 2018
Enclosure 4: CoC 1042 Amendment 1 Proposed Technical Specifications, Revision 0
Project stage: Request
ML18053A2342018-02-15015 February 2018
Enclosure 6: Proposed Amendment 1, Revision 0 Changes to the NUHOMS Eos System Updated Final Safety Analysis Report, Chapters 1 to 14
Project stage: Request
ML18057A2172018-02-23023 February 2018
Letter to A. Zaremba Request for Additional Information for Review of Duke Energys Decommissioning Funding Plan Update
Project stage: RAI
ML18058A0572018-02-23023 February 2018
Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.S Decommissioning Funding Plan Update)
Project stage: RAI
ML18058A0242018-02-23023 February 2018
Enclosurequest for Additional Information (Letter to G. Van Noordennen Request for Additional Information Regarding Zionsolutions, LLCs Decommissioning Funding Plan Update for Zion Independent Spent Fuel Storage Installation)
Project stage: RAI
ML18058A6082018-02-23023 February 2018
HI-2177593, Rev 0, Holtec International & Eddy Lea Energy Alliance (Elea) Underground CISF - Financial Assurance & Project Life Cycle Cost Estimates
Project stage: Request
ML18058A6072018-02-23023 February 2018
HI-2177565, Rev 0, Holtec International & Eddy Lea Energy Alliance (Elea) Cis Facility - Decommissioning Cost Estimate and Funding Plan
Project stage: Request
ML18058A0562018-02-23023 February 2018
Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.S Decommissioning Funding Plan Update
Project stage: RAI
ML18058A0232018-02-23023 February 2018
Letter to G. Van Noordennen Request for Additional Information Regarding Zionsolutions, LLCs Decommissioning Funding Plan Update for Zion Independent Spent Fuel Storage Installation
Project stage: RAI
ML18057A2182018-02-23023 February 2018
Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energys Decommissioning Funding Plan Update)
Project stage: RAI
2018-01-11
[Table View] |
Text
March 1, 2021 Robert D. Quinn, Director Nuclear Material Management Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, PA 16066
SUBJECT:
ACCEPTANCE REVIEW OF THE RENEWAL APPLICATION TO CERTIFICATE OF COMPLIANCE NO. 1026 FOR THE FUELSOLUTIONS' SPENT FUEL MANAGEMENT SYSTEM (DOCKET NO. 72-1026, CAC NO. 001028, EPID:
L-2020-RNW-0035) - REQUEST FOR SUPPLEMENTAL INFORMATION
Dear Mr. Quinn:
By letter dated November 6, 2020 [Agencywide Document Access and Management System (ADAMS) Accession No. ML20315A012], Westinghouse Electric Company (Westinghouse) submitted to the U.S. Nuclear Regulatory Commission (NRC) a request to renew the Certificate of Compliance (CoC) No. 1026 for the FuelSolutions' Spent Fuel Management System.
The staff has performed an acceptance review of your application to determine if the application contains sufficient technical information to begin a detailed technical review. The staff has determined that the application does not provide sufficient technical information to begin a detailed review and that supplemental information is needed. The information needed to continue our review is described in the enclosed request for supplemental information (RSI).
In order to schedule our technical review, responses to the enclosed RSI should be provided within 30 days from the date of this letter. If Westinghouse is unable to meet this response date, please notify us, at least one week prior to the due date, of your new submittal date and the reasons for the delay. If Westinghouse is not able to respond within this timeframe or the RSI responses do not provide sufficient information, the application may not be accepted for review.
R. Quinn Please reference Docket No. 72-1026, CAC No. 001028, and EPID No. L-2020-RNW-0035 in future correspondence related to this licensing action. If you have any questions, please contact me at 301-415-1018.
Sincerely, Yen-Ju Chen, Sr. Project Manager Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Docket No.: 72-1026 CAC No.: 001028 EPID: L-2020-RNW-0035
Enclosure:
RSI Yen-Ju Chen Digitally signed by Yen-Ju Chen Date: 2021.03.01 11:23:47 -05'00'
R. Quinn
SUBJECT:
ACCEPTANCE REVIEW OF THE RENEWAL APPLICATION TO CERTIFICATE OF COMPLIANCE NO. 1026 FOR THE FUELSOLUTIONS' SPENT FUEL MANAGEMENT SYSTEM (DOCKET NO. 72-1026, CAC NO. 001028, EPID: L-2020-RNW-0035) - REQUEST FOR SUPPLEMENTAL INFORMATION DOCUMENT DATE: March 1, 2021 ADAMS Accession Number: ML21060B312
DFM DFM*
DFM*
DFM*
NAME:
YChen WWheatley ASotomayor-Rivera JWise DATE:
2/26/2021 2/03/2021 2/9/2021 2/9/2021 OFFICE:
DFM*
DFM*
DFM*
NAME:
RChang TBoyce JMcKirgan DATE:
2/16/2021 2/16/2021 2/26/2021 OFFICIAL RECORD
Enclosure Request for Supplemental Information Docket No. 72-1026 Westinghouse Electric Company FuelSolutions' Spent Fuel Management System Certificate of Compliance No. 1026 Renewal Application By letter dated November 6, 2020 [Agencywide Document Access and Management System (ADAMS) Accession No. ML20315A012], Westinghouse Electric Company (Westinghouse) submitted to the U.S. Nuclear Regulatory Commission (NRC) a request to renew the Certificate of Compliance (CoC) No. 1026 for the FuelSolutions' Spent Fuel Management System.
The staff has performed an acceptance review of the application and determined that the application does not provide sufficient technical information to begin a detailed review and that supplemental information is needed. The information needed to continue the staffs review is described in the request for supplemental information (RSI) below.
Scoping Evaluation RSI 2-1 Revise the renewal application to clarify the subcomponents of the FuelSolutions' Spent Fuel Management System (including the SENTRY' addenda) that were determined to be within and outside of the scope of renewal.
The combined scoping and aging management review tables in Chapter 2 of the renewal application include all subcomponents listed in the drawings for the in-scope structure, system, and components, including those categorized as not important to safety (NITS). It is unclear to the staff which of the NITS subcomponents were determined to be within and outside of the scope of renewal.
The staff notes that some of the tables specifically identify the NITS subcomponents that were determined to be outside the scope of the renewal because their failure would not prevent the fulfillment of an important-to-safety (ITS) function, such as Table 2-6 for the transfer cask.
However, other tables do not address the scoping of NITS subcomponents, such as Tables 2-4a and 2-4b for the canisters. NUREG-1927, Revision 1, Section 2.4.2, provides guidance that the staffs review of the renewal application includes a verification that all NITS components whose failure could affect an ITS function are appropriately scoped into the aging management review.
Revise the renewal application to clearly identify the scoping determination for each of the NITS subcomponents. In addition, if any ITS subcomponents were determined to be outside the scope of renewal (i.e., they no longer have that ITS function during the period of extended operation), clarify that scoping determination in the application as well.
This information is needed to confirm compliance with 10 CFR 72.240(c).
RSI 2-2 Provide a drawing for the SENTRY' W110 Transfer Cask Neutron Shielding Shell that identifies the materials, applicable codes, safety classification, and configuration of the transfer cask subcomponents.
The combined scoping and aging management review table in Chapter 2 of the SENTRY' renewal application references drawing WDD-DW-00126-GEN for the W110 transfer cask neutron shielding shell. The staff notes that the referenced drawing does not appear to be included in the SENTRY' Dry Storage System Safety Analysis Report (Revision 0).
To support the staffs review of the scoping evaluation, provide the subject drawing.
This information is needed to confirm compliance with 10 CFR 72.236(d) and 72.240(d).
Aging Management Review RSI 3-1 In the FuelSoutions' W100 Transfer Cask Aging Management Program (AMP),
describe the activities that will be performed to manage the identified aging effects for the solid neutron shielding material.
The aging management review (AMR) for the FuelSolutions' system concluded that loss of shielding due to boron depletion was a credible aging effect for the neutron shield material in the top and bottom covers of the W100 transfer cask. The AMR table states that the W100 Transfer Cask AMP will be used to manage the aging effect. However, the W100 Transfer Cask AMP does not describe any activities for how that aging effect will be managed. Although the AMP includes dose rate acceptance criteria for the RX-277 solid neutron shield material, the AMP does not include any description of dose monitoring parameters, methodology, or frequency of activities that will be performed to verify that the acceptance criteria are met. In addition, the AMP does not address the NS-3 shielding material that is also managed by the Transfer Cask AMP.
Revise the Parameters Monitored/Inspected and Detection of Aging Effects program elements of the W100 Transfer Cask AMP to describe the activities that will be performed to ensure that the shielding performance of the RX-277 and NS-3 solid neutron shielding materials will be maintained.
This information is needed to determine compliance with 10 CFR 72.236(d), 72.240(c)(3) and 72.240(d).
RSI 3-2 Revise the Reinforced Concrete Structures AMPs for the FuelSolutions' and SENTRY' systems to define the sample size of the exterior inspections of the concrete storage casks.
The Reinforced Concrete Structures AMPs include visual inspections of exterior concrete surfaces; however, the AMPs are not clear on whether the exterior inspections will be performed on all casks or some smaller sample size.
Revise the AMPs to define the number of casks inspected and, if not all casks will be inspected, provide the technical basis for using a smaller sample size for the exterior inspections.
This information is needed to determine compliance with 10 CFR 72.240(c)(3).
RSI 3-3 Provide the test report(s) that demonstrate that the W110 transfer cask neutron shielding epoxy resin material is not subject to radiation-induced aging effects.
Appendix B of the SENTRY' renewal application summarizes the basis for why the W110 transfer cask epoxy resin neutron absorber material is not subject to radiation-induced aging (e.g., embrittlement, loss of hydrogen).
Provide the test reports that support the technical basis for concluding that aging effects for the epoxy resin are not credible.
This information is needed to determine compliance with 10 CFR 72.236(d) and 72.240(d).
OBSERVATIONS Observation 3-1 In the Reinforced Concrete Structures AMPs for the FuelSolutions' and SENTRY' systems, clarify the activities that will be used to verify the shielding performance of the concrete storage casks.
The Reinforced Concrete Structures AMPs include visual inspections and radiation surveys; however, it is unclear to the staff which activities are credited for managing the shielding performance of the concrete.
The AMPs Detection of Aging Effects program elements state that radiation surveys are performed to verify compliance with 10 CFR 72.104 and the Technical Specifications. However, the staff is unable to identify any radiation survey activities that occur in the period of extended operation. In addition, there are no details in the other program elements that describe the surveys, such as the measurement techniques, frequency, locations where radiation is measured, and acceptance criteria, that demonstrate that the surveys are capable of managing the aging of each of the concrete casks.
The AMPs also include visual inspections of the concrete; however, the AMPs are not clear on whether visual inspections are credited for managing shielding effectiveness. NUREG-2214, Managing Aging Processes in Storage (MAPS) Report, recognizes that visual inspection may be an effective means to monitor shielding effectiveness, provided that the visual inspection acceptance criteria (e.g., depth of spalling, width of cracks) are demonstrated to be sufficiently conservative to ensure that degradation will be identified and corrected prior to a loss of shielding. The AMPs do not provide such a demonstration.
Revise the renewal application to clarify which activities are credited to managing the concrete shielding and, as appropriate, provide the additional details described above that demonstrate the activities are capable of managing the aging of each of the concrete casks.
This information is needed to determine compliance with 10 CFR 72.236(d), 72.240(c)(3), and 72.240(d).
Observation 3-2 In the Reinforced Concrete Structures AMPs for the FuelSolutions' and SENTRY' systems, clarify the use of the ACI 349.3R concrete code criteria for the inspection of the internal and external surfaces of the storage cask.
The Reinforced Concrete Structures AMPs include visual inspections to monitor the condition of the concrete. The staff noted potential discrepancies or information gaps as follows:
- 1. For the cask annular space and interior areas of the vents, the visual inspection acceptance criteria are stated to conform to ACI 349.3R. The application also states that the cask interior surfaces that are covered by a metal liner are addressed by the Metallic Surfaces AMP.
It appears that the entire annular spaces of the FuelSolutions' and SENTRY' storage casks are metallic. In addition, the interior vent areas for the SENTRY' cask are also metallic. As a result, it is unclear which portions of those areas would be subject to the ACI 349.3R concrete code criteria.
- 2. For the cask exterior, the Detection of Aging Effects program element does not specifically state a code or standard for the visual inspections of the exposed concrete (unlike the annular space criteria described above). Clarify whether the inspections for the cask exterior will conform to ACI 349.3R or some other criteria.
- 3. The Detection of Aging Effects program element states that inspectors are qualified to ACI 349. It is unclear to the staff if this reference was intended to be ACI 349.3R, which is referenced in the acceptance criteria and defines the qualification requirements in Chapter 7 of that code.
Revise the Reinforced Concrete Structures AMPs, as appropriate, to clarify these details for the annular space and exterior inspections.
This information is needed to determine compliance with 10 CFR 72.240(c)(3).