IR 05000321/2020011
| ML21197A000 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/15/2021 |
| From: | Shawn Smith NRC/RGN-II |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2020011 | |
| Download: ML21197A000 (8) | |
Text
July 15, 2021
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANTS, UNITS 1 AND 2 - TEMPORARY INSTRUCTION 2515/193 INSPECTION REPORT 05000321/2020011 AND 05000366/2020011
Dear Ms. Gayheart:
On June 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plants, Units 1 and 2 and discussed the results of this inspection with Mr. Sonny Dean, Site VP, 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/
Steven P. Smith, Chief Reactor Projects Branch #6 Division of Reactor Projects
Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000321 and 05000366
License Numbers:
Report Numbers:
05000321/2020011 and 05000366/2020011
Enterprise Identifier: I-2020-011-0038
Licensee:
Southern Nuclear Operating CO. INC
Facility:
Edwin I. Hatch Nuclear Plants, Units 1 and 2
Location:
Baxley, GA
Inspection Dates:
October 26, 2020 to June 29, 2021
Inspectors:
B. Bishop, Sr. Project Engineer
R. Rodriguez, Reliability and Risk Analyst
Approved By:
Steven P. Smith, Chief
Reactor Projects Branch #6
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction 2515/193 Inspection at Edwin I. Hatch Nuclear Plants, Units 1 and 2, 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
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
2515/193 - Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions
Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions (1 Sample)
- (1) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the reliable hardened containment wetwell vent as described in the plant specific submittals and the associated safety evaluations (ADAMS Accession No. ML19044A555), and determined that the licensee was in compliance with NRC Order EA-13-109 Phase 1, Reliable, Severe Accident Capable Wetwell Venting System (ADAMS Accession No. ML13143A321).
The inspectors evaluated licensee implementation of the appropriate elements of the reliable hardened containment wetwell vent as described in the plant specific submittals and the associated NRC safety evaluation (ADAMS Accession No.
ML19044A555). Specifically, the inspectors evaluated licensee implementation of the Hardened Containment Vent System (HCVS) functional requirements, design features, maintenance and testing, quality standards, and programmatic requirements as described in Appendix A of TI 2515/193 Revision 1.
The inspectors verified that the licensee satisfactorily:
- Developed and implemented adequate maintenance and testing of HCVS equipment to ensure their availability and capability;
- Developed and issued procedures to safely operate the HCVS using normal power supplies, during Extended Loss of All AC Power (ELAP), and a postulated severe accident scenario, and integrated the procedures into existing plant procedures; and
- Trained their staff to assure personnel can proficiently operate the HCVS.
Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the reliable wetwell venting strategy as described in the plant specific submittals and the associated safety evaluation (ADAMS Accession No. ML19044A555) and determined that the licensee was in compliance with NRC Order EA-13-109 Phase 2, Reliable, Severe Accident Capable Drywell (or alternative strategy) Venting System (ADAMS Accession No.
The inspectors also evaluated licensee implementation of the appropriate elements of the reliable wetwell venting strategy as described in the plant specific submittal(s) and the associated NRC safety evaluation (ADAMS Accession No. ML19044A555).
Specifically, the inspectors evaluated licensee implementation of Severe Accident Water Addition / Severe Accident Water Management (SAWA/SAWM) functional requirements, installed instrumentation, maintenance and testing, and programmatic requirements as described in Appendix B of TI 2515/193 Revision 1.
The inspectors verified that the licensee satisfactorily developed a strategy making it unlikely that venting from the containment drywell would be necessary. As part of that strategy, the licensee:
- Implemented the Severe Accident Water Addition (SAWA)/Severe Accident Water Management (SAWM) systems as defined and fulfilled functional requirements for installed and portable equipment.
- Installed and/or identified the previously-installed instrumentation necessary to implement SAWM;
- Developed and implemented adequate maintenance and testing of SAWA/SAWM equipment to ensure availability and capability;
- Developed and issued procedures to safely operate the SAWA/SAWM during an ELAP and during postulated severe accident scenario, and integrated their procedures into their existing plant procedures such that entry into and exiting from the procedures are clear when using existing plant procedures; and
- Trained their staff to assure personnel can proficiently operate the HCVS during ELAP and accident scenarios.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 29, 2021, the inspectors presented the Temporary Instruction 2515/193 Inspection results to Mr. Sonny Dean, Site VP, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2515/193
Corrective Action
Documents
10583367, 10667796, 10675195, 10714850, 10749713
Miscellaneous
Flex Verification and Validation Report, Version 3, with HCVS
Addendum
Final Integrated Plan HCVS Order EA-13-109
Procedures
FSG - ELAP (Extended Loss of AC Power)
2.2
Station Blackout
11.2
NMP-GM-038
Diverse and Flexible Coping Strategies (FLEX) Program
3.0
Work Orders
SNC915259, SNC1022034, SNC964621, SNC972716,
SNC962586, SNC962594, SNC984309, SNC984309,
SNC1078029, SNC984199, SNC1016103, SNC943695,
SNC1102718, SNC101444