IR 05000483/2022013

Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2022013

ML22319A087
Person / Time
Site:	Callaway
Issue date:	11/15/2022
From:	Vincent Gaddy NRC/RGN-IV/DORS/EB1
To:	Diya F Ameren Missouri
Sifre W
References
IR 2022013
Download: ML22319A087 (9)

Text

November 15, 2022

SUBJECT:

CALLAWAY PLANT - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000483/2022013

Dear Mr. Diya:

On November 3, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Callaway Plant and discussed the results of this inspection with Mr. Barry L. 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, Signed by Gaddy, Vincent on 11/15/22 Vincent G. Gaddy, Chief Engineering Branch 1 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: 05000483/2022013 Enterprise Identifier: I-2022-013-0003 Licensee: Ameren Missouri Facility: Callaway Plant Location: Steedman, MO Inspection Dates: October 17, 2022 to November 3, 2022 Inspectors: J. Braisted, Senior Reactor Inspector D. Reinert, Reactor Inspector W. Sifre, Senior Reactor Inspector Approved By: Vincent G. Gaddy, Chief Engineering Branch 1 Division of Operating Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.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.

Specific Guidance 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) Component Cooling Water to Residual Heat Removal Heat Exchanger A Isolation Valve EGHV0101

(2) Residual Heat Removal Pump A Suction Isolation Valve EJHV8701A

(3) Turbine Driven Auxiliary Feedwater Pump to Steam Generator B Valve ALHV0010

(4) Turbine Driven Auxiliary Feedwater Pump to Steam Generator C Valve ALHV0012

(5) Pressurizer Power Operated Relief Valve BBPCV0456A

(6) Residual Heat Removal Loop 1 Inlet Isolation Valve BBPV8702A

(7) Safety Injection Pump A Discharge to Hot Leg Injection Isolation Valve EMHV8802A

(8) Chemical and Volume Control System Component Cooling Pump to Reactor Coolant Pump Seals Throttle Valve BGHV8357B

(9) Steam Generator C Atmospheric Steam Dump Valve ABPV0003

(10) Motor Driven Auxiliary Feedwater Pump B to Steam Generator D Valve ALHV0005

(11) Reactor Coolant System Pressurizer Outlet Power Operated Relief Valve BBHV8000B

(12) Service Water to Essential Service Water Train B Upstream Isolation Valve EFHV0024

INSPECTION RESULTS

No findings 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) inspection results to Mr. Barry L. Cox, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations AB-42 ABPV0001-4 Capability and Margin Calculation 3

AL-07 Failure Analysis Calculation of the Valve Stem on 0

ALHV0005/7/9/11

AL-38 ALHV0006 Capability and Margin Calculation 2

M-BB-18 Pressurizer Safety and Relief Valves Maximum Reaction 0

Forces

ZZ-214 MOV Voltage Drop Calculation 12

ZZ-443 Small Break LOCA Containment Pressure-Temperature 1

Analysis

ZZ-467 MOV High Torque-High Voltage Conditions 0

ZZ-525 LOCA and MSLB Containment Pressure and Temperature 3

Response

ZZ-534 Quarter-Turn MOV Capability and Margin Calculation 1

ZZ-536 Rising-Stem MOV Capability and Margin Calculation 2

Corrective Action Condition Report 202204485, 201900092, 202101555, 202105068,

Documents 202201038, 201303382, 201806463, 201900180,

2004200, 202004239, 201902392, 201705979,

201801857, 201907109, 202103637, 202201372,

2103140, 202203930, 202005727, 202104467,

2203142, 201408399, 201800513, 201800813,

201800316, 202101876, 202203588, 201707095,

2204499, 202204501, 202204669, 201600100,

201705611, 201801820, 201801836, 201901444,

201902545, 201905928, 202100006, 202102952,

2103313, 202103313, 202200020, 202200740,

2202780, 202203930, 202203978, 202204499,

201606533

Corrective Action Condition Report 202206849, 202206881, 202206943, 202206944,

Documents 202206946

Resulting from

Inspection

Drawings E-23EG07(Q) Schematic Diagram, Component Cooling Water Supply to 16

Inspection Type Designation Description or Title Revision or

Procedure Date

RHR Heat Exchanger

M-22AL01(Q) Piping & Instrumentation Diagram, Auxiliary Feedwater 51

System

M-22EG02(Q) Piping & Instrumentation Diagram, Component Cooling 26

Water System

Engineering MP 19-0103 RFR 180203 - Hot Leg Recirculation Valve Position 0

Changes Change and Mission Time Basis Documentation

MP 94-1006 Change Limitorque Operator Gear Ratio for RHR Suction A

Isolation Valves

Engineering Request for 20224A, 15502A, 2930A, 200604991, 5353B, 8746I,

Evaluations Resolution 5353S, 5353Y, 5353X, 18112D, 8746R, 5353H

Miscellaneous Inservice Testing Program 37

5710-99-H 049 Westinghouse Instruction Book for Motor Operated Gate 1

Valves, Manually Operated Gate Valves & Swing Check

Valves for SNUPPS Project

AOV.BID Preventive Maintenance Background Information 6

Document, Air Operated Valves (AOV)

EDP-ZZ-01114 Motor Operate Valve Program Guide 41

EDP-ZZ-01133 Air Operated Valve Program Guide 25

Procedures ISL-BB-0P403 RCS Pressure (WR) Loop Calibration 026

ITM-ZZ-VT001 Diagnostic Calibration and Testing of Modulating Air 25

Operated Valves

MTE-ZZ-QA013 Movats UDS Testing of Torque Controlled Limitorque Motor 5

Operated Rising Stem Valves

MTE-ZZ-QA035 MOVATS Votes Testing of Torque Controlled Limitorque 8

Motor Operated Rising Stem Valves

MTE-ZZ-QA037 MOVATS Votes Testing of Limitorque Motor Operated 9

Butterfly Valves

MTM-BB-QV002 Pressurizer Power Operated Relief Valves 017

Disassembly/Inspection/Reassembly

OSP-BB-V0001 Reactor Coolant System Valve Inservice Test 031

OSP-BB-V002A Power Operated Relief Valve Inservice Test 016

OSP-BG-V001B Chemical and Volume Control Train B Valve Inservice Test 042

Work Orders Job 10511183.600, 10511184.600, 13506020.600,

Inspection Type Designation Description or Title Revision or

Procedure Date

19511393.500, 19511394.500, P724301.500,

15512230.500, 10507456.500, 7507046.500,

13505927.500, 21002431.500, 20512247.655,

20513601.500, 22508953.500, 17512947.500,

20511322.500, 20511372.500, 20511724.500,

20509560.565, 18500160.500, 19003553.500,

21500227.500, 14005755.901, 16000928.500,

11513514.580, 5109335.550, 12000070.550,

13505384.500, 21002429.500, 07506261.500,

13505468.500

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