IR 05000220/2022010
| ML22326A053 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/22/2022 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022010 | |
| Download: ML22326A053 (1) | |
Text
November 22, 2022
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000220/2022010 AND 05000410/2022010
Dear David Rhoades:
On November 3, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station and discussed the results of this inspection with Alex D. Sterio, 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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000220 and 05000410
License Numbers:
Report Numbers:
05000220/2022010 and 05000410/2022010
Enterprise Identifier: I-2022-010-0046
Licensee:
Constellation Energy Generation, LLC
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
October 17, 2022 to November 3, 2022
Inspectors:
J. Brand, Reactor Inspector
P. Cataldo, Senior Reactor Inspector
E. Miller, Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) at Nine Mile Point Nuclear Station, 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.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a) Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b) Determined whether the sampled POVs are capable of performing their design-basis functions.
c) Determined whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d) Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) IV-01-01, Main Steam System Inboard Isolation Valve, NMP1
- (2) IV-39-09R, Emergency Cooling System Outboard Isolation Valve, NMP1
- (3) IV-40-01, Core Spray Inboard Isolation Valve, NMP1
- (4) IV-44.2-17, Control Rod Drive System Shutdown Volume Drain Outboard Isolation Valve, NMP1
- (5) IV-80-21, Containment Spray Suction Isolation Valve, NMP1
- (6) PSV-01-102A, Automatic Depressurization System, Electromatic Relief Valve ERV-111 Solenoid Valve, NMP1 (7)2MSS*AOV6D, Main Steam Inboard Isolation Valve, NMP2 (8)2RHS*MOV15A, Residual Heat Removal - Containment Spray to Drywell; Outboard Isolation Valve, NMP2 (9)2SWP*MOV66A, Service Water System Return Isolation Valve from Diesel Generator Cooler, EG1, NMP2 (10)2CSH*MOV107, High Pressure Core Spray Injection Valve, NMP2 (11)2CPS*AOV109, Suppression Pool Purge Nitrogen Supply Inboard Outlet Isolation Valve, NMP2 (12)2ICS*MOV121, Reactor Core Isolation Cooling Turbine Steam Supply Outboard Isolation Valve. NMP2
INSPECTION RESULTS
No findings of more than minor safety significance were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 3, 2022, the inspectors presented the design basis assurance inspection (programs) results to Alex D. Sterio, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Corrective Action
Documents
Resulting from
Inspection
04529418
04530317
04530863
04530909
04530925
04530930
04532374
04532396
04532758
04534256
Miscellaneous
Environmental Qualification Document Package
Revision 6
N2-SURV-009
Missed Surveillance Risk Assessment for SR 3.3.3.1.2-8
and SR 3.6.1.3.5
Revision 0
Procedures
S-EPM-GEN-066
MOV Gear Case Lube Inspection and Stem Lubrication
Revision 12