IR 05000317/2023011
| ML23130A003 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/10/2023 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2023011 | |
| Download: ML23130A003 (1) | |
Text
May 10, 2023
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - TITLE 10 OF THE CODE OF FEDERAL REGULATIONS 50.69 RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS INSPECTION REPORT 05000317/2023011 AND 05000318/2023011
Dear David Rhoades:
On April 27, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 and discussed the results of this inspection with Patrick Navin, Site Vice President, 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 (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety
Docket Nos. 05000317 and 05000318 License Nos. DPR-53 and DPR-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000317 and 05000318
License Numbers:
Report Numbers:
05000317/2023011 and 05000318/2023011
Enterprise Identifier: I-2023-011-0017
Licensee:
Constellation Energy Generation, LLC
Facility:
Calvert Cliffs Nuclear Power Plant
Location:
Lusby, MD
Inspection Dates:
April 10, 2023 to April 27, 2023
Inspectors:
J. Bozga, Senior Reactor Inspector
C. Hobbs, Reactor Inspector
M. Patel, Senior Reactor Inspector
D. Werkheiser, Senior Reactor Analyst
Approved By:
Glenn T. Dentel, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a special inspection at Calvert Cliffs Nuclear Power Plant, 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.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
37060 - 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components Inspection
The inspectors reviewed the licensees program and implementation of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, in accordance with the following procedure sections. Section 02.04 was not completed during this inspection because the feedback and process adjustment required by 10 CFR 50.69(e) was not implemented by the licensee. As of the date of this inspection, two refueling outages have not occurred since system categorization was completed on at least three systems.
Review of the Licensees Programs and Procedures (IP Section 02.01) (1 Partial)
(1)
(Partial)
The inspectors reviewed the licensees program and procedures associated with 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components (SSCs) for Nuclear Power Reactors, license amendment described in the plant safety evaluation and Updated Final Safety Analysis Report and documented in the staffs Safety Evaluation Report (ADAMS Accession Nos.
Review of the Licensees 10 CFR 50.69 Program Implementation (IP Section 02.02) (1 Partial)
(1)
(Partial)
The inspectors reviewed the licensees 10 CFR 50.69 categorization process and alternate treatment requirements completed on the following systems.
- Saltwater
- Component Cooling Water
- Emergency Core Cooling
- Chemical and Volume Control Problem Identification and Resolution (IP Section 02.03) (1 Partial)
(1)
(Partial)
For the systems listed above, the inspectors reviewed the licensees corrective action program to verify that conditions that would prevent RISC-3 SSCs from performing their safety-related function have been corrected. Additionally, the inspector verified that, as appropriate, the licensee performed common cause reviews for RISC-3 SSC deficiencies to ensure that the licensees SSC categorization process remains valid.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 27, 2023, the inspectors presented the special inspection results to Patrick Navin, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
37060
Corrective Action
Documents
04354107
04382129
04382133
04382136
04415947
04421707
04440416
04501647
04503419
04505413
04517507
04529372
04529524
04546790
04548940
Corrective Action
Documents
Resulting from
Inspection
04669728
04670772
04671594
Engineering
Changes
ECP-22-000095
Technical Evaluation for Alternative Treatment for EQ
components categorized RISC-3 per 10CFR50.69
Revision 0
Engineering
Evaluations
AT-21-0050
ECCS Relief Valves Alternative Treatment Plan
AT-21-0066
ECCS AOV IST Position Indication Testing Alternative
Treatment Plan
AT-21-0067
ECCS Manual Valves IST Alternative Treatment Plan
AT-21-0068
ECCS AOVs Inservice Test Alternative Treatment Plan
AT-21-0070
Shutdown Cooling Heat Exchanger CC Inlet Thermal Relief
Valves AT Plan
AT-21-0071
Emergency Diesel Generator Relief Valves AT Plan
AT-21-0073
Component Cooling Relief Valves AT Plan
AT-22-0082
CVCS Relief Valve Alternative Treatment
AT-22-0085
CVCS AOVs Alternative Treatment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AT-22-0088
50.69 White Paper for Alternative Treatment Plan
AT-22-0089
Alternative Treatment for RISC-3 components of system 15
(Component Cooling)
AT-22-0091
Alternative Treatment for system 52 (ECCS) RISC-3
components
AT-22-0094
CVCS Pumps & Check Valves IST Alternative Treatment
CA-5069-007
Estimates of Surveillance Limits for 10 CFR 50.69
Categorized Systems of ECCS, EDG, and EDG Oil
Revision 0
CA-5069-012-003
CFR 50.69 SCD - Saltwater System
Revision 0
CA-5069-015-003
CFR 50.69 SCD - Component Cooling System
Revision 0
CA-5069-024-003
CFR 50.69 SCD - Emergency Diesel Generator System
Revision 2
CA-5069-041-002
CVCS Passive Consequence Development in Support of
50.69 Passive Support Categorization
Revision 0
CA-5069-041-003
CFR 50.69 SCD - Chemical and Volume Control System
Revision 0
CA-5069-052-
061-002
ECCS Passive Consequence Development in Support of
50.69 Passive Categorization
Revision 0
CA-5069-052-
061-003
CFR 50.69 SCD - Emergency Core Cooling System
Revision 1
Miscellaneous
CA-PRA-005.012
Saltwater Cooling System Notebook
Revision 1
CA-PRA-005.015
Component Cooling System Notebook
Revision 3
CA-PRA-005.023-
24
DO and EDG System Notebook
Revision 3
CA-PRA-005.041
Chemical and Volume Control System Notebook
Revision 3
CA-PRA-005.052
Safety Injection System Notebook
Revision 3
CA-PRA-005.061
Containment Spray System Notebook
Revision 2
CA-PRA-012
Internal Flood Notebook
Revision 8
ER-CA-330-1004
Calvert Cliffs Nuclear Power Plant Fifth Interval Risk
Informed Inservice Inspection Report
Revision 0
LOI-024A
Operations Training - Fairbanks Morse Diesel Engine and
Generator Controls
Revision 8
LOI-024C
Operations Training - SACM Emergency Diesel Generators
Revision 9
LOI-041-1
Operations Training - CVCS: Letdown
Revision 8
LOI-041-2
Operations Training - CVCS: Charging
Revision 7
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CFR 50.69 Program
Revision 6
CFR 50.69 Active Component Risk Significance Insights
Revision 6
CFR 50.69 Passive Component Categorization
Revision 4
CFR 50.69 Risk Informed Categorization for Structures,
Systems, and Components
Revision 8
CFR 50.69 Alternative Treatment Implementation Process Revision 8
Integrated Decision-Making Panel for Risk Informed SSC
Categorization Duties and Responsibilities
Revision 8
Requirements for Immediate and Periodic Performance
Monitoring Reviews
Revision 5
Job Familiarization of 50.69 Project Team and Site
Personnel
Revision 6
STP O-8A-2
Test of 2A DG and 4 kV Bus 21 UV
2/13/2023
STP O-8B-2
Test of 2B DG and 4 kV Bus 24 UV
2/14/2023