IR 07200009/2020001

Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report 07200009/2020001

ML20297A461
Person / Time
Site:	07200009
Issue date:	10/23/2020
From:	Greg Warnick Division of Nuclear Materials Safety I
To:	Flohr C US Dept of Energy (DOE)
References
IR 2020001
Download: ML20297A461 (14)

Text

October 23, 2020

SUBJECT:

FORT SAINT VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) - NRC INSPECTION REPORT 07200009/2020001

Dear Ms. Flohr:

This letter refers to the U.S. Nuclear Regulatory Commissions (NRCs) announced routine inspection conducted on August 18-20, 2020, of the dry cask storage activities associated with your Independent Spent Fuel Storage Installation (ISFSI). The NRC inspectors discussed the results of this inspection with Mr. Steve Ahrendts, NRC Licensed Facility Director, and other members of your staff during a final telephonic exit meeting conducted on September 23, 2020.

The inspection results are documented in the enclosure to this letter.

The inspectors examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

Within these areas, the inspections consisted of selected examination of procedures and representative records, observations of dry cask storage surveillance operations, observations of site meetings, and interviews with personnel. Specifically, the inspection reviewed compliance with the requirements specified in the site-specific ISFSI License SNM-2504 and associated Technical Specifications, the Safety Analysis Report, and the regulations in Title 10 of the Code of Federal Regulations Part 72 and Part 20.

Based on the results of these inspections, the inspectors documented one violation of NRC requirements in this report. The violation was determined to be a Severity Level IV violation of low safety significance under the NRCs traditional enforcement process. The NRC is treating this violation as a non-cited violation consistent with Section 2.3.2.a of the NRC Enforcement Policy.

If you contest the violation or significance of the non-cited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to: (1) the Regional Administrator, Region IV, and (2) the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

In accordance with 10 CFR 2.390 of the NRCs Agency Rules of Practice and Procedure, a copy of this letter, its enclosure, and your response if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRCs Website at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy or proprietary information so that it can be made available to the Public without redaction.

If you have any questions regarding this inspection report, please contact Lee Brookhart at 817-200-1549, or the undersigned at 817-200-1249.

Sincerely, Gregory G. Warnick, Chief Reactor Inspection Branch Division of Nuclear Materials Safety

Docket Nos.: 72-009 License Nos.: SNM-2504

Enclosure:

Inspection Report 07200009/2020001

Gregory G. Warnick Digitally signed by Gregory G. Warnick Date: 2020.10.23 13:46:48 -05'00'

SUNSI Review By: LEB ADAMS:

X Yes No Sensitive X Non-Sensitive Non-Publicly Available X Publicly Available Keyword NRC-002 OFFICE DNMS:RxIB DNMS:RxIB DNMS:RxIB NAME LEBrookhart CSmith GGWarnick SIGNATURE

/RA/

/RA/

/RA/

DATE 10/22/2020 10/22/2020 10/23/2020

Enclosure

U.S. NUCLEAR REGULATORY COMMISSION REGION IV

Docket Nos.:

072-00009 License Nos.:

SNM-2504 Report No.:

07200009/2020001

Enterprise Identifier:

I-2020-001-095 Licensee:

U.S. Department of Energy Idaho Operations Office Facility:

Fort Saint Vrain Independent Spent Fuel Storage Installation

Location:

Platteville, CO 80651 Inspection Dates:

On-site: August 18-20, 2020 Exit Meeting Date:

September 23, 2020

Inspectors:

L. Brookhart, Senior ISFSI Inspector Reactor Inspection Branch Division of Nuclear Materials Safety, Region IV

C. Smith, Reactor/ISFSI Inspector Reactor Inspection Branch Division of Nuclear Materials Safety, Region IV

Approved By:

G. Warnick, Chief Reactor Inspection Branch Division of Nuclear Materials Safety, Region IV

EXECUTIVE SUMMARY NRC Inspection Report 07200009/2020001

On August 18-20, 2020, the U.S. Nuclear Regulatory Commission (NRC) performed a routine on-site inspection of the dry fuel storage activities of the Fort St. Vrain (FSV) Independent Spent Fuel Storage Installation (ISFSI) in Platteville, Colorado. The inspection included an evaluation of the current condition of the ISFSI and reviews of several topical areas to evaluate compliance with the applicable NRC regulations and the provisions of the site-specific license. The inspection included reviews of documentation relevant to ISFSI activities and operations that occurred at FSV since the last ISFSI inspection performed in May 2017. The documentation reviewed included quality assurance records, radiological surveys, corrective action reports, and records demonstrating compliance with Technical Specifications and Safety Analysis Report (SAR) requirements. One Severity Level IV violation of low safety significance was identified for the licensees failure to perform a surveillance requirement within the required time interval.

The violation was treated as a non-cited violation in accordance with the NRCs Enforcement Policy.

Away from Reactor ISFSI Inspection Guidance, Inspection Procedure 60858

• The licensee conducted quality assurance audits and surveillances of the ISFSI program.

The inspectors reviewed the quality assurance audits and surveillances performed by contractor and the Department of Energy Quality Assurance Department, since the last ISFSI inspection. Issues identified in the quality assurance audits and surveillances were entered into the sites corrective action program for resolution. No findings were identified related to the licensee quality assurance activities. (Section 1.2.a)

• Radiation levels around the ISFSI facility and within the facility were within the expected ranges and areas inside the facility with radiological dose rates were properly posted. The ISFSI facility was maintained in good physical condition. Based on documents reviewed and interviews with personnel, areas with observable degradation were repaired or remediated through the sites aging management program. At the time of the inspection there were no observable signs of degradation. (Section 1.2.b)

• Environmental data reviewed from the 2017, 2018, and 2019 site radiological environmental operating reports determined that radiation levels offsite were nominal and in accordance with the design basis and federal regulations. (Section 1.2.c)

• Revisions to the SAR and changes to other major programs since the last inspection were reviewed. There were no changes made to the Radiological Environmental Monitoring Program, the Training Program, the Quality Assurance Program, or Natural Gas and Oil Infrastructure near the site. Revision 15 to the SAR was reviewed and changes made were found to meet the requirements of the Title 10 Code of Federal Regulations (10 CFR)

Part 72.48 change process. (Section 1.2.d)

• Selected deficiency reports and corrective action requests were reviewed for the period of May 2017 through August 2020. A wide range of issues had been identified and resolved by the licensee. The issues identified did not have a significant impact on safety and resolution of those issues was appropriate. No adverse trends were identified during the review.

(Section 1.2.e)

• The Fort St. Vrain emergency response plan was being maintained and a revision to the plan was reviewed by the inspectors. The inspectors determined the changes did not reduce the effectiveness of the plan and did not require NRC approval pursuant to 10 CFR 72.44. Drills, exercises, and training were performed in accordance with requirements in the plan. Offsite support agencies were offered an opportunity to participate in the licensees latest biennial exercise. (Section 1.2.f)

• Fort St. Vrain implemented its Aging Management Program, which was required with the 20-year license renewal. The Aging Management Program is documented in the licensees Technical Specifications and SAR. At the time of the inspection, the licensee performed all required inspections, maintenance, and repairs to the ISFSI. (Section 1.2.g)

• The inspectors documented one Severity Level IV; non-cited violation related to Licensee Event Report 2019-001-0 (STI-NLF-RPT-129) (ADAMS Accession No. ML20276A243).

Specifically, the violation related to the licensees failure to perform License SNM-2504, Technical Specification Surveillance Requirement 3.1.1.1 to inspect the inlet and outlet screens of the modular vault dry store system for blockage within the required time frame of 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />. As documented in the Licensee Event Report, the licensee self-identified that the surveillance was completed at 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br />, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> later than the allowed time interval between November 20, 2019 and November 29, 2019. The inspectors determined that the finding was of low safety significance since the surveillance was late by 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, there was no adverse weather during the interval, and security forces (present 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-per-day) did not observe any screen blockage during their rounds. (Section 1.2.h)

Review of 10 CFR 72.48 Evaluations, Inspection Procedure 60857

• The inspectors reviewed a sample of 10 CFR 72.48 screenings and evaluations that had been performed within the inspection period. No findings were identified through the selected sample review. (Section 2.2)

REPORT DETAILS

Summary of Facility Status

The Fort St. Vrain (FSV) Independent Spent Fuel Storage Installation (ISFSI) is a modular vault dry store (MVDS) system developed by Foster Wheeler Energy Corporation. The facility provided storage for the spent fuel from the decommissioned FSV high temperature gas cooled reactor. There were 244 fuel storage containers (FSC) loaded with spent fuel at the FSV ISFSI.

The FSV ISFSI license was transferred from Public Service Company of Colorado to the Department of Energy Idaho Operations Office (DOE-ID) on June 4, 1999. Currently the facility is being maintained by Spectra Tech, Incorporated (STI) as the management and operations contractor for the DOE-ID. At the time of the inspection, the ISFSI was being maintained under site-specific License SNM-2504 Amendment 11 and Safety Analysis Report (SAR) Revision 15.

1.

Away From Reactor ISFSI Inspection Guidance (IP 60858)

1.1 Inspection Scope

The inspectors performed a review of the licensees ISFSI activities to verify compliance with requirements of the site-specific License SNM-2504, Amendment 11 and SAR Revision 15. The inspectors reviewed selected procedures, corrective action reports, and records to verify ISFSI operations were compliant with the license Technical Specifications, requirements in the SAR, and NRC rules and regulations.

1.2 Observations and Findings

a. Quality Assurance Audits and Surveillances

Both DOE-ID and the contractor, STI, had performed numerous Quality Assurance (QA)

audits and QA surveillances of operations at the FSV ISFSI since the last NRC inspection in May 2017. A total of six audit reports and 42 surveillance records were sampled for review during the inspection.

The licensees audit and surveillance program encompassed many topical areas and provided in-depth reviews of the licensees ISFSI programs, operations, training, and record keeping. All identified issues were placed into either the licensees corrective action program (CAP) or STIs CAP as deficiency reports (DRs) or Corrective Action Requests (CARs). Each DR or CAR required a formal response from the impacted program department. The inspectors reviewed the problem statements for all DRs and CARs that resulted from the ISFSI audits. The DRs/CARs were evaluated to ensure that the problems being identified were properly categorized based on their safety significance and were properly resolved by the licensee. The inspectors determined corrective actions identified or taken for the issues were appropriate for the significance of the problems being identified. The inspectors did not identify any concerns related to the findings of the sites QA auditing and surveillance program. The audits and surveillances performed met the requirements of 10 CFR 72, Subpart G and the licensees QA program requirements.

b. Radiological Conditions and Tour of the ISFSI

A tour of the FSV ISFSI facility was performed during the inspection. A recent radiological survey of the ISFSI was provided to the inspectors prior to their arrival at the facility. The Facility Director, ISFSI Manager, and others accompanied the inspectors during the facility tour. During the tour the inspectors determined that the charge face area of the MVDS system was in good condition. The security tamper seals on the 244 loaded storage positions, each of which contained an FSC, were all intact. No flammable or combustible materials were observed anywhere inside or near the ISFSI facility. Radiation readings were taken on approach to the ISFSI facility and remained at nominal levels. Areas within the facility that required postings and/or boundaries were properly roped off and properly posted in accordance with 10 CFR Part 20 requirements.

Areas external to the ISFSI facility were also inspected. On the outside, the inlet and outlet screens were clear of debris and the ISFSI concrete structure was in good physical condition with no significant observable degradation. The licensee utilized its Aging Management Program to inspect, repair, and assess the ISFSI structures per the license renewal requirements (see Section 1.2.g).

c. Radiological Environmental Monitoring Reports

Annual Radiological Environmental Operating Reports for FSV were reviewed for 2017, 2018, and 2019. The sites environmental monitoring program is responsible for measuring the direct radiation impacts of plant operations at 20 thermoluminescent dosimeters (TLD) monitoring stations. All TLD monitoring stations at FSV, including those in close proximity to the ISFSI at the site boundary, documented the dose equivalent to any real individual located outside of the owner controlled area were below the 10 CFR 72.104(a)(2) requirement of less than 25 mrem per year due to the direct radiation influence from the ISFSI. No findings were identified related to the radiological review.

d. Biennial Update Reports and SAR Revisions

The 2019 biennial report was reviewed. The report provided information related to revisions made during the reporting period to the SAR and certain programs required by the Technical Specifications. The June 2019, biennial report (for period of June 2017 through June 2019) included Revision 15 of the FSAR. The changes to the SAR were editorial corrections, clarifications, changes to contractor and DOE-ID organization, adoption of Amendment 11 of the license, and other minor facility changes that had taken place over the last couple of years. The 2019 biennial report continued by describing that no other changes were made to the following areas: Technical Specifications, Radiological Environmental Monitoring Program, the Training Program, Quality Assurance Program, or Natural Gas and Oil Infrastructure. The licensee further stated that no additional changes were made to those programs between June 2019 and the date of the inspection. The inspectors identified no concerns with the changes made by the licensee.

e. Corrective Action Program

The inspectors performed a review of FSVs CAP associated with ISFSI operations.

A list of ISFSI related DRs and CARs issued since the last routine NRC inspection in May 2017 was provided by the licensee during the current inspection. Several DRs and CARs were selected by the inspectors for further review.

The adverse to quality conditions discussed in the DRs and CARs reviewed by the inspectors covered a broad range of paperwork and maintenance issues that were identified during routine ISFSI storage operations. Based on the types of problems identified, the licensee continued to demonstrate a reasonably low threshold for placing ISFSI and maintenance issues into the CAP. The actions taken for the resolution of the issues were appropriate to the low safety significance of the issues that were identified.

No significant or adverse trends were identified during the review of the CAP at FSV.

f. Emergency Planning

Revisions to the licensees Emergency Response Plan since the last NRC inspection in May 2017 were reviewed. The FSV Emergency Response Plan, STI-NLF-RPT, Revision 0 had been issued in January 2018. The changes to the FSV Emergency Response Plan resulted from the updated formatting requirements and procedure implementation of a new DOE-ID contractor (STI) operating the FSV ISFSI. The inspectors reviewed the changes, which were mostly editorial in nature. The inspectors determined the changes did not result in a decrease in the effectiveness of the plan and pursuant to 10 CR 72.44, the changes did not requirement NRC approval.

Required emergency drills/exercises were listed in Section 4.6.1 of the plan. Required semiannually drills included radiological/health physics drills, medical drills, and fire drills. Biennial exercises were larger drills that tested the adequacy of the implementing procedures, emergency equipment, and communications networks and ensured the emergency response personnel were familiar with their duties. Offsite response organizations were invited to participate in the biennial exercises. The licensee had successfully conducted the required exercises and drills since the last ISFSI inspection.

A sample of drill packages and the most recent biennial exercise were selected for review. The inspectors determined that the selected drills and the exercise met the objectives of the site Emergency Response Plan. No concerns were identified with the licensees implementation of their emergency response plan.

g. Aging Management Program

As a condition of the FSV license renewal, DOE-ID was required to establish an aging management program to ensure that all ISFSI structures, systems, and components (SSCs) considered important to safety remain functional through the duration of the extended licensing period. The FSV ISFSI license was renewed on July 18, 2011 and included Technical Specification 5.5.5 which required that an Aging Management Program be established as a means for monitoring and mitigating potential aging effects of the modular vault system. The FSV Aging Management Program, STI-NLF-PM-034, Revision 0, specified the specific SSCs that are inspected, which included the fuel storage containers, fuel storage container support stools, standby storage wells, container handling machine raise/lower mechanism, container handling machine fuel storage container grapple, charge face structural steel, cask load/unload port, structural concrete of the MVDS building, and concrete fill inside the charge face structure.

The inspection and maintenance of these SSCs were implemented through Technical Procedures (TPRs) and Operational Procedures (OPS). Inspection or maintenance periodicity varied from monthly, for some active components, to every 10 years for passive systems. The inspectors reviewed several of the aging management related TPRs/OPSs that were completed during the years since the last inspection. None of the TPR/OPSs reviewed observed any significant deficiencies. At the time of the inspection, the licensee had performed all required inspections, maintenance, and repairs associated with their aging management program.

h. Licensee Event Report

The licensee submitted Licensee Event Report (LER) 2019-001-1, STI-NLF-RPT-129, on April 6, 2020, (ADAMS Accession No. ML20276A243) for their failure to perform a visual inspection of the cooling inlet and outlet screens every seven (7) days. The inspectors reviewed the LER and identified that a violation of Surveillance Requirement (SR) 3.1.1.1 occurred.

Specifically, per the NRC License SNM-2504 Technical Specifications, in order to maintain adequate air flow cooling for the spent fuel contained within the FSV MVDS system, the cooling inlet and outlet screens must be free of blockage. Blockage that exceeds 50 percent but is less than 95 percent must be cleared within 7 days of discovery. Additionally, per Limiting Condition for Operation (LCO) 3.1.1, any blockage equal to 95 percent or more must be cleared within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The SR 3.1.1.1 requires a visual inspection of the cooling inlet and outlet screens every seven days. If the allowances of SR 3.0.2 are invoked, which provide a 25 percent extension to the surveillance frequency interval, the maximum interval to perform SR 3.1.1.1 would be 8.75 days, or 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />.

Contrary to SR 3.1.1.1, between November 20, 2019 and November 29, 2019, approximately 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> passed between performance of the SR 3.1.1.1 inlet and outlet screen visual inspections.

The security force, although not trained to perform Technical Specification actions or Surveillances, was present at the site during this time period from November 20 - 29, 2019 and periodically checked the MVDS as part of their security duties. The security personnel are trained to notify their management if any inlet or outlet screen blockage is observed. The security personnel did not report any screen blockage during the time period.

This violation was dispositioned per the traditional enforcement process using Section 2.3 of the NRCs Enforcement Policy. The inspectors determined that the finding was of low safety significance.

Consistent with the guidance in Section 1.2.6.D of the NRC Enforcement Manual, if a violation does not fit an example in the Enforcement Policy Violation Examples, it should be assigned a severity level: (1) commensurate with its safety significance; and (2) informed by similar violations addressed in the Violation Examples. The violation was evaluated to be similar to a Severity Level IV violation in Enforcement Policy Section 6.1.d.1. The inspectors determined that the SR 3.1.1.1 LCO did not occur within the LCO interval as required. However, because SR 3.1.1.1 was late by 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, out of

an interval requirement of 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />; there was no adverse weather during the interval; and that security forces (present 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-per-day) did not observe any screen blockage, the inspectors concluded that the late performance of the SR did not represent a significant failure.

The licensee entered the self-identified finding into the sites CAP. The licensee restored compliance, conducted a causal analysis, and initiated corrective actions to preclude reoccurrence. Because the licensee entered the issue into the CAP, the safety significance of the issue was low, and the issue was not repetitive or willful, this Severity Level IV violation was treated as an non-cited violation (NCV), consistent with Section 2.3.2.a of the Enforcement Policy (NCV 07200009/2020-001-01; Failure to Perform SR 3.1.1.1 to Visually Inspection Inlet and Outlet Screens).

The inspectors reviewed the LER and the associated causal analysis. The inspectors did not identify any issues with the LER or the licensees causal analysis. Inspectors found that the LER contained adequate content to be closed out in this inspection report.

This LER 2019-001-0, STI-NLF-RPT-129, is closed.

1.2 Conclusions

The licensee conducted quality assurance audits and surveillances of the ISFSI program. The inspectors reviewed quality assurance audits and surveillances performed by contractor and the DOE Quality Assurance Department, since the last ISFSI inspection. Issues identified in the quality assurance audits and surveillances were entered into the sites corrective action program for resolution. No findings were identified related to the licensee quality assurance activities.

Radiation levels around the ISFSI facility and within the facility were within the expected ranges and areas inside the facility with radiological dose rates were properly posted.

The ISFSI facility was maintained in good physical condition. Based on documents reviewed and interviews with personnel, areas with observable degradation were repaired or remediated through the sites aging management program. At the time of the inspection there were no observable signs of degradation.

Environmental data reviewed from the 2017, 2018, and 2019 site radiological environmental operating reports determined that radiation levels offsite were nominal and in accordance with the design basis and federal regulations.

Revisions to the SAR and changes to other major programs since the last inspection were reviewed. There were no changes made to the Radiological Environmental Monitoring Program, the Training Program, the Quality Assurance Program, or Natural Gas and Oil Infrastructure near the site. Revision 15 to the SAR was reviewed and changes made were found to meet the requirements of the 10 CFR Part 72.48 change process.

Selected DRs and CARs were reviewed for the period of May 2017 through August 2020. A wide range of issues had been identified and resolved by the licensee. The issues identified did not have a significant impact on safety and resolution of those issues was appropriate. No adverse trends were identified during the review.

The FSV emergency response plan was being maintained and a revision to the plan was reviewed by the inspectors. The inspectors determined the changes did not reduce the

effectiveness of the plan and did not require NRC approval pursuant to 10 CFR 72.44.

Drills, exercises, and training were performed in accordance with requirements in the emergency plan. Offsite support agencies were offered an opportunity to participate in the licensees latest biennial exercise.

Fort St. Vrain implemented its Aging Management Program, which was required with the 20-year license renewal. The Aging Management Program is documented in the licensees Technical Specifications and SAR. At the time of the inspection, the licensee performed all required inspections, maintenance, and repairs to the ISFSI.

The inspectors documented one Severity Level IV, non-cited violation related to LER 2019-001-0 (STI-NLF-RPT-129). Specifically, the violation related to the licensees failure to perform License SNM-2504, Technical Specification SR 3.1.1.1 to inspect the inlet and outlet screens of the modular vault dry store system for blockage within the required time frame of 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />. As documented in the LER, the licensee self-identified that the surveillance was completed at 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br />, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> later than the allowed time interval between November 20, 2019 and November 29, 2019. The NRC determined that the finding was of low safety significance since the surveillance was late by 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, there was no adverse weather during the interval, and security forces (present 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-per-day) did not observe any screen blockage during their rounds.

Review of 10 CFR 72.48 Evaluations (IP 60857)

2.1 Inspection Scope

The licensees 10 CFR 72.48 screenings and evaluations performed since the NRCs last ISFSI inspection were reviewed to determine compliance with regulatory requirements.

2.2 Observations and Findings

The licensee performed several procedure revisions, one SAR revision, and some equipment or process changes under the 10 CFR 72.48 process since the last inspection. The inspectors reviewed the 10 CFR 72.48 screenings for those changes made within the ISFSI program. One of the screenings led to a 10 CFR 72.48 full evaluation. All screenings and the one evaluation were determined to be adequately performed.

2.3 Conclusions

The inspectors reviewed a sample of the licensees required safety screenings and evaluations that had been performed within the inspection period. No findings were identified during the selected sample review.

Exit Meeting Summary

On September 23, 2020, the inspectors presented the final inspection results to Mr. Steve Ahrendts, NRC Licensed Facility Director, DOE-ID, and other members of the licensees staff.

Attachment

SUPPLEMENTAL INSPECTION INFORMATION PARTIAL LIST OF PERSONS CONTACTED

Licensee Personnel S. Ahrendts, NRC License Facility Director D. Bland, ISFSI Program Manager, STI J. Newkirk, FSV ISFSI Manager, STI

INSPECTION PROCEDURES USED

IP 60858 Away from Reactor ISFSI Inspection Guidance IP 60857 Review of 10 CFR 72.48 Evaluations

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened and Closed 07200009/2020-001-01 NCV Failure to Perform SR 3.1.1.1 to Visually Inspection

Inlet and Outlet Screens

Closed 2019-001-0 LER Failure to Perform a Visual Inspection of the Inlet and Outlet Screens

LIST OF ACRONYMS USED

ADAMS Agencywide Documents Access and Management System CAP Corrective Action Program CAR Corrective Action Request CFR Code of Federal Regulations DOE-ID Department of Energy Idaho Operations Office DNMS Division of Nuclear Material Safety DR Deficiency Report FSC Fuel Storage Container FSV Fort Saint Vrain IP Inspection Procedure ISFSI Independent Spent Fuel Storage Installation LER Licensee Event Report LCO Limiting Condition for Operation MVDS Modular Vault Dry Store system NCV non-cited violation NRC U.S. Nuclear Regulatory Commission OPS Operating Procedures QA Quality Assurance SAR Safety Analysis Report SR Surveillance Requirement SSC structures, systems, and components STI Spectra Tech, Incorporated TPR Technical Procedures TLD thermoluminescent dosimeters