IR 05000327/2020402

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Regulatory Commission Security Baseline Inspection Report 05000327/2020402 and 05000328/2020402
ML20262H080
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/18/2020
From: Scott Shaeffer
NRC/RGN-II/DRS/EB2
To: Rasmussen M
Tennessee Valley Authority
References
IR 2020402
Download: ML20262H080 (7)


Text

September 18, 2020

SUBJECT:

SEQUOYAH NUCLEAR PLANT - NUCLEAR REGULATORY COMMISSION SECURITY BASELINE INSPECTION REPORT 05000327/2020402 AND 05000328/2020402

Dear Mr. Rasmussen:

On August 7, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah Nuclear Plant. On August 6, 2020, the NRC inspectors discussed the results of this inspection with Mr. Brian Brigman and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79

Enclosure:

As stated

REGION II==

Docket Numbers: 05000327 and 05000328 License Numbers: DPR-77 and DPR-79 Report Numbers: 05000327/2020402 and 05000328/2020402 Enterprise Identifier: I-2020-402-0035 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant Location: Soddy Daisy, TN Inspection Dates: August 03, 2020 to August 06, 2020 Inspectors: D. Strickland, Reactor Inspector Approved By: Scott M. Shaeffer, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a security baseline inspection at Sequoyah Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Unless otherwise noted, baseline security inspections were conducted in accordance with the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2201, Security Inspection Program for Commercial Nuclear Power Reactors. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. Publicly available IPs are located at:

http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

SAFEGUARDS

71130.14 - Review of Power Reactor Target Sets

The inspectors evaluated the Security Target Set Program. The following elements were evaluated:

===Review of Power Reactor Target Sets (1 Sample)

(1) Power Reactor Target Sets===

Section 02.01 Review of Events and Logs The inspector reviewed any licensee event reports, safeguards log entries, and corrective action program entries since the last Target Set inspection that concern the target set identification, development, and maintenance program.

Section 02.02 Target Set Identification and Development Process Review The inspector assessed the licensee's documentation and maintenance of the process used to develop and identify complete and accurate target sets as required by 10 CFR Part 73 by reviewing applicable portions of procedures and samples of records and conducting interviews with responsible personnel and plant employees.

Section 02.03 Verification of Target Sets Changes The inspector reviewed changes to the licensees documented target sets since the last Target Set inspection. The inspector verified that any design modifications and procedure or configuration changes that have occurred were appropriately documented in the site's target sets.

Section 02.04 Verification of Complete and Accurate Target Sets The inspector interviewed licensee personnel and reviewed a sample of target sets for reactor operation and for all modes of operation. The inspector reviewed assumptions used in the licensees development of its target sets.

Section 02.05 Physical Protection Program Review The inspector verified that the licensee performed a review of target sets for accuracy, completeness, and applicability at least every 24 months and as otherwise required, documented the results and recommendations, and entered findings in the sites corrective action program (CAP).

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On August 6, 2020, the inspectors presented the security baseline inspection results to Mr. Brian Brigman and other members of the licensee staff.

THIRD PARTY REVIEWS The NRC did not review any third party reports or documents during the inspection period.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71130.14 Corrective Action CR 1348458 10/16/2017

Documents CR 1348463 10/16/2017

CR 1348790 10/17/2017

CR 1348821 10/17/2017

CR 1548285 09/11/2019

CR 1618357 06/23/2020

CR 1618360 06/23/2020

CR 1618370 06/23/2020

CR 1618372 06/23/2020

CR 1618373 06/23/2020

CR 1622781 07/14/2020

Corrective Action CR 1627751 08/03/2020

Documents CR 1627753 08/03/2020

Resulting from CR 1627943 08/04/2020

Inspection CR 1627947 08/04/2020

CR 1627951 08/04/2020

Procedures NPG-SPP-14.2 Rev. 9

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