IR 05000220/2021010

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Triennial Fire Protection Inspection Report 05000220/2021010 and 05000410/2021010
ML21235A048
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 08/24/2021
From: Glenn Dentel
Division of Operating Reactors
To: Rhoades D
Exelon Generation Co, Exelon Nuclear
References
IR 2021010
Download: ML21235A048 (8)


Text

August 24, 2021

SUBJECT:

NINE MILE POINT NUCLEAR STATION - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000220/2021010 AND 05000410/2021010

Dear Mr. Rhoades:

On August 12, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station and discussed the results of this inspection with Mr. Adam Schuerman 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, Glenn T. Dentel, Chief Engineering Branch 2 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:

05000220/2021010 and 05000410/2021010

Enterprise Identifier: I-2021-010-0016

Licensee:

Exelon Generation Company, LLC

Facility:

Nine Mile Point Nuclear Station

Location:

Oswego, NY

Inspection Dates:

July 26, 2021 to August 12, 2021

Inspectors:

C. Bickett, Senior Reactor Inspector

L. Dumont, Reactor Inspector

C. Hobbs, Reactor Inspector

D. Kern, Senior Reactor Inspector

M. Patel, Senior Reactor Inspector

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 triennial fire protection inspection 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.

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.

However, all the inspection activities were performed onsite.

REACTOR SAFETY

===71111.21N.05 - Fire Protection Team Inspection (FPTI)

Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)===

The inspectors verified that the following systems credited in the approved fire protection program could perform their licensing basis function:

(1) Unit 1 Emergency Cooling System
(2) Unit 1 Core Spray System
(3) Unit 1 Fire Protection Water Supply System
(4) Unit 1 Fire Barriers
(5) Unit 2 Safety Relief Valves
(6) Unit 2 Residual Heat Removal System
(7) Unit 2 Fire Protection Water Supply System
(8) Unit 2 Fire Barriers

Fire Protection Program Administrative Controls (IP Section 03.02) (4 Samples)

The inspectors verified that the selected administrative control or process was implemented in accordance with the current licensing basis. The inspectors ensured that the fire protection program contained adequate procedures to implement the selected administrative control and that the selected administrative control met the requirements of all committed industry standards.

(1) Unit 1 Fire Protection System Impairment Control
(2) Unit 1 National Fire Protection Association (NFPA) 805 Monitoring Program
(3) Unit 2 Fire Protection System Impairment Control
(4) Unit 2 Combustible Control Program

Fire Protection Program Changes/Modifications (IP Section 03.03) (4 Samples)

The inspectors reviewed the following changes to ensure that they did not constitute an adverse effect on the ability to safely shutdown post-fire and did not degrade assumptions and performance capability stated in the safe shutdown analysis. The inspectors verified that fire protection program documents and procedures affected by the changes were updated.

(1) Unit 1 ECP-20-000210, Upgrade Diesel Fire Pump Alternate Supply Fuse
(2) Unit 1 ECP-21-000074, Extend Surveillance Testing Interval of the Electric Fire Pump
(3) Unit 2 FPEE2-19-001, Use of Non-IEEE-383 Rated Cabling on the Refueling Floor
(4) Unit 2 FPEE2-20-001, Review of Fire Damper Testing

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 12, 2021, the inspectors presented the triennial fire protection inspection results to Mr. Adam Schuerman and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.05 Calculations

S13.1-100F002

Fire Protection Water Supply

Corrective Action

Documents

03992068

04177783

208724

263696

268283

288697

04328835

04337624

04359366

04368005

04374440

04388247

04415668

04424579

04425591

04425598

04426317

Corrective Action

Documents

Resulting from

Inspection

04434317

04437318

04437336

04437464

04437709

04439263

04440093

04440187

04440250

04440254

Engineering

Changes

ECP-21-000074

Extend the Testing Frequency of the Unit 1 Electric Fire

Pump, Unit 2 Electric Fire Pump, and Unit 2 Diesel Fire

Pump from Monthly to Quarterly

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Evaluations

FPEE2-19-001

Use of Non IEEE-383 Rated Cabling on the Refuel Floor

FPEE2-20-001

Review of Fire Damper Testing

Miscellaneous

DCD-805

Nine Mile Point Unit 1 NFPA 805 Design Criteria

E208

Nine Mile Point Unit 1 Nuclear Safety Capability

Assessment

N1-PRA-005.20

Nine Mile Point Unit 1 Probabilistic Risk Assessment Fire

Protection Water Injection System Notebook

Procedures

N1-FRE-F001

Fire Risk Evaluation Report

N1-PM-C3

Electric and Diesel Fire Pump Performance Tests

05/05/2021

N1-SOP-21.1

Fire in Plant

N1-SOP-21.2

Control Room Evacuation

N2-FSP-FPP-

R001

Fire Rated Assemblies and Watertight Penetration Visual

Inspection

00500

N2-FSP-FPP-

R002

Fire Damper Operation and Inspection

013T1

N2-OP-52

Reactor Building Ventilation

N2-OP-78

Remote Shutdown System

N2-SOP-34

Stuck Open Safety Relief Valve

N2-SOP-78

Control Room Evacuation

NMP2-P306C

Cable and Mechanical Penetration Stops and Seals

OP-AA-201-007

Fire Protection System Impairment Control

OP-AA-201-009

Control of Transient Combustible Material

OP-NM-102-106

Operator Response Time Program at Nine Mile Point

OP-NM-201-105

Compensatory Measures for Inoperable Fire Protection

Systems and Components

Work Orders

C92692919

C92757601

C93175479

C93636525

C93672489

C93710683