IR 05000220/2022010

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Design Basis Assurance Inspection (Programs) Inspection Report 05000220/2022010 and 05000410/2022010
ML22326A053
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 11/22/2022
From: Mel Gray
NRC/RGN-I/DORS
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:

DPR-63 and NPF-69

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

2EQDP-MOV004

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