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Triennial Fire Protection Inspection Report 05000483/2022011
	ML22213A058
Person / Time
Site:	Callaway
Issue date:	08/02/2022
From:	James Drake; NRC/RGN-IV/DORS/EB2
To:	Diya F; Ameren Missouri
References
	IR 2022011
	Download: ML22213A058 (10)
	v • d • e

August 02, 2022

SUBJECT:

CALLAWAY PLANT TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000483 022011

Dear Mr. Diya:

On July 14, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Callaway Plant. On July 14, 2022, the NRC inspectors discussed the results of this inspection with Mr. B. Cox, 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 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, James F. Drake, Acting Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000483 License No. NPF-30

Enclosure:

As stated

Inspection Report

Docket Number:

05000483

License Number:

NPF-30

Report Number:

05000483/2022011

Enterprise Identifier:

I-2022-011-0002

Licensee:

Ameren Missouri

Facility:

Callaway Plant

Location:

Steedman, MO

Inspection Dates:

June 27, to July 14, 2022

Inspectors:

G. Pick, Senior Reactor Inspector, Team Leader

R. Deese, Senior Reactor Analyst

J. Drake, Senior Reactor Inspector

J. Lee, Reactor Inspector

B. Pinson, Reactor Inspector

Approved By:

James F. Drake, Acting 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 Callaway Plant, 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.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)

Main article: IP 71111.21

The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).

(1) Operator actions could be accomplished as assumed in the licensees fire probabilistic risk assessment analysis and safe shutdown analysis for fire area C-27 for a control room evacuation.

(2) Ensured that post maintenance tests and/or surveillance activities were performed as scheduled for the underground fire loop, fire pumps, sprinkler system in the cable spreading room, and halon gas system for engineered safety features switchgear room B.

(3) Walked down the sprinkler system and fire pumps to identify equipment alignment discrepancies. Inspected for deficient conditions such as corrosion, missing fasteners, cracks, and degraded insulation.

(4) Ensured that fire protection components were being managed for aging (e.g., loss of material, cracking, reduction of heat transfer) in accordance with appropriate aging management programs. Verified that the aging management program activities associated with fire protection equipment were being implemented.

Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)

The inspectors verified that the selected controls or processes were implemented in accordance with the licensees current licensing basis. If applicable, ensured that the fire protection program contains adequate procedures to implement the selected administrative controls. Verified that the selected administrative controls meet the requirements of all committed industry standards.

(1)hot work, fire impairment, and combustible control programs (2)fire probabilistic safety assessment monitoring for classic fire protection activities and comparing actual equipment unavailability to unavailability assumed in the probabilistic risk assessment

Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)

The inspectors verified the following:

a)

Changes to the approved fire protection program did not constitute an adverse effect on the ability to safely shutdown.

b)

If applicable, the adequacy of the design modification was appropriate c)

Assumptions and performance capability stated in the safe shutdown analyses had not been degraded through changes or modifications.

d)

The fire protection program documents, such as the updated final safety analysis report, fire protection report, fire hazards analysis, and safe shutdown analysis were updated consistent with the fire protection program or design change.

e)

Post-fire safe shutdown operating procedures, such as abnormal operating procedures, affected by the modification were updated.

(1) The inspectors reviewed the following as one sample:

FPR00000217, Detailed Fire Modeling Report for Fire Compartment A-27

FPR00000253, RFR 180096 - Ultimate Heat Sink Cooling Tower Return to Ultimate Heat Sink Pond

FPR00000256, Code Compliance Evaluation NFPA 805, Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants - Fire Safety Analysis for Fire Area YD-1

FPR00000269, Eliminate the Main Feedwater Regulating Valve Single Point Vulnerability and Improve Reliability

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On July 14, 2022, the inspectors presented the triennial fire protection inspection results to Mr. B. Cox, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

v t e Inspection Report - Callaway - 2022011
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
2022 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 10(0) 11(0) 13(0) 40(0) Security 401(0) 402(0) 403(0) 404(0) Operator Exams 301(0) Emergency Planning Other

IR 05000483/2022011