ML25006A189

ISFSI Inspection (Request for Information)

ML25006A189
Person / Time
Site:	Sequoyah
Issue date:	01/06/2025
From:	NRC/RGN-II/DORS
To:	Medina R Tennessee Valley Authority
References
Download: ML25006A189 (1)

Text

SEQUOYAH NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION Ricardo Medina:

From February 3 - 7, 2025, the Nuclear Regulatory Commission (NRC) will perform an inspection of the Independent Spent Fuel Storage Installation at the Sequoyah Nuclear Plant, in accordance with NRC inspection procedure IP 60855, Operation of An Independent Spent Fuel Storage Installation.

Experience has shown that this inspection is resource intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we are requesting in advance documents needed for this activity.

Section A of the enclosure identifies information to be provided prior to the inspection. The NRC requests that these documents be provided to the lead inspector no later than January 28, 2025. Section B of the enclosure identifies additional information the inspectors will need during the onsite week to complete the review of inspection. The inspection staff will appreciate if all the documents requested are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.

Please note that our inspection dates are subject to change based on your schedule of activities. If there are any questions about this inspection, changes to the schedule of activities, or the material requested, please contact the lead inspector, Darrell Neal, at (404) 997-4639 or Darrell.Neal@nrc.gov or the Engineering Branch 3 Chief, Nicole Coovert at (404) 997-4510.

In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.

PAPERWORK REDUCTION ACT STATEMENT This letter contains voluntary information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB) approved these information collections (approval number 3150-0011). The burden to the public for these information collections is estimated to average 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> per response. Send comments regarding this information collection to the FOIA, Library and Information Collection Branch, Office of the Chief Information Officer, Mail Stop: T6-A10M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) OMB, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.

Enclosure ISFSI INSPECTION DOCUMENT REQUEST Site:

Sequoyah Nuclear Plant Docket No.:

07200034 Inspection Dates:

February 3 - 7, 2025 Inspection Procedure:

IP 60855, Operation of An Independent Spent Fuel Storage Installation, Dated January 1, 2021 IP 60856, Review of 10 CFR 72.212(b) Evaluations Dated January 1, 2021 (if applicable)

IP 60857, Review of 10 CFR 72.48 Evaluations Dated January 1, 2021 (if applicable)

Inspector(s):

Darrell Neal, Health Physicist (Lead Inspector)

Anthony Ponko, Senior Construction Project Inspector Jose Vasquez, Construction Project Inspector A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office in care of the lead inspector by January 28, 2025. The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (e.g. compact disk), or web-based document management system.

If requested documents are large and only hardcopies are available, please inform the inspector(s) and provide the subject documentation during the first day of the onsite inspection.

Additionally, some of the information requested may not apply to the site depending on the scope of the loading campaign or other plant-specific conditions. If there are any questions regarding this information request, please contact the lead inspector as soon as possible.

A.1 General Information

1. Provide a copy of the latest applicable amendment and cask FSAR.

2. Provide a copy of the ISFSI specific sections for the site specific FSAR.

3. Please provide a detailed schedule of the loading campaign.

4. Please provide NRC inspectors with the receipt inspection records and the Certificate of Conformance documentation for casks that were accepted for the up-coming campaign.

5. A copy of the most recent program self-assessment.

6. A copy of the sites response to recent NRC generic communications and other industry operating experience notifications associated with ISFSI cask loading activities or cask design.

A.2 Changes, Tests, and Experiments and 72.212 Evaluations.

1. Provide a copy of your 72.48/50.59 screening/evaluation procedure.

2. Provide a copy of the current 10 CFR 72.212 report.

3. List of the 72.48 screenings performed for any revisions of your 72.212 report since the original placement of the current cask design.

2 Enclosure

4. List of ISFSI related modifications/72.48 screenings and/or applicability since the original placement of the current cask design.

5. List of all ISFSI 72.48 safety evaluations performed since the original placement of the current cask design.

A.3 Loading and Unloading Activities Specific Heavy Loads

1. Provide a copy of your operation and maintenance procedures for the cranes associated with the loading campaign.

2. List of condition reports for the past 3 years related to the cranes associated with the loading campaign.

3. List modifications (ECs) and 50.59 screenings for the cranes associated with the loading campaign since the original placement of the current cask design.

4. List of any 50.59 safety evaluations performed for the cranes associated with the loading campaign since the original placement of the current cask design.

5. Copy of the most recent annual crane maintenance for the cranes associated with the loading campaign.

6. Copy of the most recent ANSI N14.6 maintenance on special lift devices (MPC cleats, Lift yoke, lift yoke extension, lift brackets, etc.)

Cask Processing

1. Copies of your cask processing procedures including;

a. Pre-operational Inspections

b. MPC Loading

c. MPC Sealing

d. MPC Transfer/Transport

2. Copies of procedures referenced within cask processing procedures (if applicable) including;

a. Cask Welding

b. Non-Destructive Examinations

c. Leak rate testing Welding Operations

1. Copies of the following documentation for the cask welds:

a. Applicable ASME BPVC Edition and Addenda

b. weld data sheet (traveler)

c. weld configuration and supporting drawings

d. Weld Procedure Specification (WPS) used to fabricate the welds

e. Procedure Qualification Records (PQRs) supporting the WPS

f.

mechanical test reports supporting the applicable PQRs

2. Welder performance qualifications records, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS

3. Personnel qualification records for all applicable NDE techniques

3 Enclosure Radiological

1. Copy of the most recently performed radiological survey of the ISFSI pad/fence area.

2. Provide any TLD monitoring data for the past 3 years that reflects the dose coming from the ISFSI. Specifically, data that may reflect the ISFSI dose that is not tracked or reported in the Annual Radiological Environmental Operating Reports by the REMP program.

3. A copy of the Person-Rem dose per cask evaluations or list that shows the Person-Rem per cask.

4. Provide the ALARA plan for the ISFSI campaign or document that establishes the expected cumulative dose for the campaign.

A.4 DSS Fuel Selection

1. Documentation of the canister fuel contents including;

a. initial enrichment,

b. burnup,

c. decay heat load,

d. cooling time,

e. physical assembly type and parameters,

f.

non-fuel hardware inserts, and

g. intact/damaged classification.

2. Provide a copy of the visual examination procedure for spent fuel.

3. Provide copies of the examination records that support the classification for undamaged or damaged fuel.

A.5 ISFSI Storage Monitoring and Surveillance.

1. Provide a copy of the monitoring and surveillance procedures.

2. Documentation of the cask and ISFSI pad yearly maintenance (work order or completed procedure) for the past 3 years (if available).

A.6 Quality Assurance Program

1. List of ISFSI QA related audits performed since the original placement of the current cask design.

2. List of ISFSI related condition reports for the past 3 years.

3. Provide a copy of your current corrective action program procedure

4. List of ISFSI QA surveillances performed since the original placement of the current cask design, including any vendor audits conducted by the CP QA personnel.

B. Information Requested for the On-Site Inspection Week Please provide the information requested below in hard copy or electronic (preferred) format to the lead inspector during the onsite inspection week. Prior to the onsite inspection, the inspector(s) will select inspection samples from the information provided in response to Section A of this enclosure.

B.1 General Information

1. Updated schedule of the loading campaign.

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2. Names and contact information for the following program leads:

a. ISFSI Program

b. Radiological Program

c. Licensing

d. Site Welding

e. Overhead and Mobile Cranes

f.

Quality Assurance Program B.2 Changes, Tests, and Experiments and 72.212 Evaluations.

1. Copies of the 72.48 screenings performed for revisions of your 72.212 report selected for review.

2. Copies of ISFSI related modifications/72.48 screenings and/or applicability that were selected for review.

3. Copies of ISFSI 72.48 safety evaluations that were selected for review.

B.3 Loading and Unloading Activities Specific Heavy Loads

1. Copies of condition reports related to the cranes associated with the loading campaign selected for review.

2. Copies of modifications (ECs) and 50.59 screenings for the cranes associated with the loading campaign selected for review.

3. Copies of the 50.59 safety evaluations performed for the cranes associated with the loading campaign selected for review.

Welding Operations

1. Copies of the following documentation for the cask welds:

a. Weld record for all cask welds (alternatively the weld package for the previously processed cask in the same ISFSI Campaign)

b. examination records for the NDEs performed Radiological

1. Copies of the Radiation Work Permits (RWPs) and surveys for the current loading campaign.

B.4 DSS Fuel Selection

1. Video recording of the fuel loaded into the current cask.

B.5 Quality Assurance Program

1. Copies of ISFSI QA related audits selected for review.

2. Copies of ISFSI related condition reports selected for review.

3. Copies of ISFSI QA surveillances selected for review.

Enclosure Inspector(s) Contact Information:

Darrell Neal Health Physicist Radiological Safety Branch Div. of Fuels, Radiological Safety, & Security 404-997-4639 Mailing Address:

US NRC Region II Attn: Darrell Neal 245 Peachtree Center Avenue, Suite 1200 Atlanta, GA 30303