IR 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, 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:
Report Number:
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
AB-42
ABPV0001-4 Capability and Margin Calculation
AL-07
Failure Analysis Calculation of the Valve Stem on
ALHV0005/7/9/11
AL-38
ALHV0006 Capability and Margin Calculation
M-BB-18
Pressurizer Safety and Relief Valves Maximum Reaction
Forces
ZZ-214
MOV Voltage Drop Calculation
ZZ-443
Small Break LOCA Containment Pressure-Temperature
Analysis
ZZ-467
MOV High Torque-High Voltage Conditions
ZZ-525
LOCA and MSLB Containment Pressure and Temperature
Response
ZZ-534
Quarter-Turn MOV Capability and Margin Calculation
Calculations
ZZ-536
Rising-Stem MOV Capability and Margin Calculation
Corrective Action
Documents
Condition Report
2204485, 201900092, 202101555, 202105068,
2201038, 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
Documents
Resulting from
Inspection
Condition Report
2206849, 202206881, 202206943, 202206944,
2206946
71111.21N.02
Drawings
E-23EG07(Q)
Schematic Diagram, Component Cooling Water Supply to
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RHR Heat Exchanger
M-22AL01(Q)
Piping & Instrumentation Diagram, Auxiliary Feedwater
System
M-22EG02(Q)
Piping & Instrumentation Diagram, Component Cooling
Water System
MP 19-0103
RFR 180203 - Hot Leg Recirculation Valve Position
Change and Mission Time Basis Documentation
Engineering
Changes
MP 94-1006
Change Limitorque Operator Gear Ratio for RHR Suction
Isolation Valves
A
Engineering
Evaluations
Request for
Resolution
224A, 15502A, 2930A, 200604991, 5353B, 8746I,
5353S, 5353Y, 5353X, 18112D, 8746R, 5353H
Inservice Testing Program
5710-99-H 049
Westinghouse Instruction Book for Motor Operated Gate
Valves, Manually Operated Gate Valves & Swing Check
Valves for SNUPPS Project
AOV.BID
Preventive Maintenance Background Information
Document, Air Operated Valves (AOV)
EDP-ZZ-01114
Motor Operate Valve Program Guide
Miscellaneous
EDP-ZZ-01133
Air Operated Valve Program Guide
ISL-BB-0P403
RCS Pressure (WR) Loop Calibration
26
ITM-ZZ-VT001
Diagnostic Calibration and Testing of Modulating Air
Operated Valves
MTE-ZZ-QA013
Movats UDS Testing of Torque Controlled Limitorque Motor
Operated Rising Stem Valves
MTE-ZZ-QA035
MOVATS Votes Testing of Torque Controlled Limitorque
Motor Operated Rising Stem Valves
MTE-ZZ-QA037
MOVATS Votes Testing of Limitorque Motor Operated
Butterfly Valves
MTM-BB-QV002
Pressurizer Power Operated Relief Valves
Disassembly/Inspection/Reassembly
017
Reactor Coolant System Valve Inservice Test
031
Power Operated Relief Valve Inservice Test
016
Procedures
Chemical and Volume Control Train B Valve Inservice Test
2
Work Orders
Job
10511183.600, 10511184.600, 13506020.600,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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