IR 05000277/2020012
| ML20253A254 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/09/2020 |
| From: | Josephine Ambrosini Division Reactor Projects I |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Ambrosini J | |
| References | |
| IR 2020012 | |
| Download: ML20253A254 (7) | |
Text
September 9, 2020
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - TEMPORARY INSTRUCTION 2515/193 INSPECTION REPORT 05000277/2020012 AND 05000278/2020012
Dear Mr. Hanson:
On August 20, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Peach Bottom Atomic Power Station, Units 2 and 3 and discussed the results of this inspection with Mr. Dave Henry, Plant Manager 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, X /RA/
Signed by: Josephine A. Ambrosini
Josephine A. Ambrosini, Team Leader Technical Support and Administrative Team Division of Reactor Projects
Docket Nos. 05000277 and 05000278 License Nos. DPR-44 and DPR-56
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000277 and 05000278
License Numbers:
Report Numbers:
05000277/2020012 and 05000278/2020012
Enterprise Identifier: I-2020-012-0007
Licensee:
Exelon Nuclear
Facility:
Peach Bottom Atomic Power Station, Units 2 and 3
Location:
Delta, PA 17314
Inspection Dates:
August 17, 2020 to August 20, 2020
Inspectors:
F. Arner, Senior Reactor Analyst
P. Boguszewski, Resident Inspector
Approved By:
Josephine A. Ambrosini, Team Leader
Technical Support and Administrative Team
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting Temporary Instruction (TI) 2515/193 inspection at Peach Bottom Atomic Power Station, Units 2 and 3, 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), regional inspectors were directed to begin telework. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely as well as on site and all the objectives and requirements for completion of the IP were met.
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) PHASE 1 The inspectors evaluated licensee implementation of the appropriate elements of the reliable hardened containment wetwell vent as described in the plant specific submittal(s) and the associated NRC safety evaluation (ADAMS Accession No.
ML19015A422). 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.
PHASE 2 The inspectors 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. ML19015A422).
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
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 20, 2020, the inspectors presented the Temporary Instruction 2515/193 inspection results to Mr. Dave Henry, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2515/193
Calculations
HCVS Compressed Nitrogen Sizing Calculation
Revision 2
Corrective Action
Documents
04339435
Corrective Action
Documents
Resulting from
Inspection
04363915
04364296
Drawings
M-367
P and I Diagram Containment Atmospheric Control System
Revision 92
Miscellaneous
Peach Bottom Atomic Power Station, Units 2 and 3 - Safety
Evaluation Regarding Implementation of Hardened
Containment Vent Capable of Operation Under Severe
Accident Conditions Related to Order EA-13-109 (CAC Nos.
MF4416 And MF4417)
03/11/2019
Procedures
CC-PB-118-1004
Final Integrated Plan
Revision 1
FSG-040-2
Aligning the FLEX Pump From the ECT to RHR
Revision 2
T-200-2
Primary Containment Venting
Revision 14
T-200-3
Primary Containment Venting
Revision 17
T-200J-2
Containment Venting via the Torus Hardened Vent
Revision 6
T-200J-3
Containment Venting via the Torus Hardened Vent
Revision 5