IR 05000413/2020010

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000413/2020010 and 05000414/2020010

ML20070J968
Person / Time
Site:	Catawba
Issue date:	03/10/2020
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Simril R Duke Energy Carolinas
References
IR 2020010
Download: ML20070J968 (11)

Text

March 10, 2020

SUBJECT:

CATAWBA NUCLEAR STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000413/2020010 AND 05000414/2020010

Dear Mr. Simril:

On February 6, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba Nuclear Station and discussed the results of this inspection with you 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,

/RA/

James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000413 and 05000414

License Numbers:

NPF-35 and NPF-52

Report Numbers:

05000413/2020010 and 05000414/2020010

Licensee:

Duke Energy Carolinas, LLC

Facility:

Catawba Nuclear Station

Location:

York, SC

Inspection Dates:

February 03, 2020 to February 06, 2020

Inspectors:

N. Morgan, Reactor Inspector

M. Riley, Reactor Inspector

A. Ruh, Resident Inspector

Approved By:

James B. Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Catawba 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

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from February 3 - 6, 2020.

(1) Evaluation AR 02104045, Revised SG (Steam Generator) PORV (Power Operated Relief Valve) Flow Rates & Post-MSLB (Main Steam Line Break) Cool-down

(2) Evaluation AR 02236975, CNS (Catawba Nuclear Station) U1 (Unit 1) Turbine Trip and Feedwater System Pipe Break

(3) Evaluation AR 02245001, CNS UFSAR (Updated Final Safety Analysis Report)

Chapter 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly

(4) Evaluation AR 01962944, Revision to Methodology Report DPC-NE-2009-P-A

(5) Evaluation AR 02047559, Revision to Methodology Report DPC-NE-2009-P-A

(6) Evaluation AR 02085006, VIPRE Upgrade from Mod. 2r to Mod. 2.5adke

(7) Evaluation AR 02110981, Update to Catawba Nuclear Station UFSAR Table 15-14

(8) Evaluation AR 02213061, Addition of an External Constituent to the Control Room

(9) Screen EC 402534, Optional Hydraulic Accumulator to be installed on 1CF33, 1CF51, 1CF60, 2CF33, 2CF42, 2CF51, and 2CF60

(10) Screen EC 412812, Generate Test Acceptance Criteria for Reactor Vessel Vents Flow Rate

(11) Screen EC 411844, Degraded Bus Timer Setpoint

(12) Screen EC 108311, Replace Valves 2NV202B and 2NV203A to Gain Operating Margin

(13) Screen EC 94585, Replace D/G (Emergency Diesel Generator) 2A Voltage Regulator/Excitation System

(14) Screen EC 114179, UNIT 2: Removal of SPV (Single Point Vulnerability) at A518 Pin 24 In SSPS (Solid State Protection System) Logic Cabinets for Train A & B on Unit 2

(15) Screen EC 408742, NW (Containment Valve Injection Water) Group 2: Convert to Type C Leak Rate Testing

(16) Screen EC 408429, ESF (Engineered Safety Feature) Backleakage to FWST (Refueling Water Storage Tank) and Leakage in Aux. Bldg.

(17) Screen EC 415036, Changes to the VQ (Containment Air Release and Addition)

Containment Pressure Annunciator

(18) Screen EC 411492, Replacement of 2NW8A, 2NW20A, 2NW61B, 2NW69B Valve and Operator due to Solenoid Failures

(19) Screen EC 413660, Large NC (Reactor Coolant) System Vent - Remove 3 Pressurizer Safety Valves

(20) Applicability Determination AR 2287956, PT/1/A/4250/006 B - 0000215277 CA (Auxiliary Feedwater) System Flow Verification

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On February 6, 2020, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Robert T. Simril and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

CNC-1201.30-00-

27

Determination of NC System Cooldown Time Following a

Main Steam Line Break

Rev. 3

CNC-1223.03-00-

0038

Determination of Unit 2 Reactor Vessel Head Vent Flow

Rev. 0

CNC-1223.19-00-

0004

NW System Setpoint Calculation

Rev. 9

CNC-1223.21-00-

22

Post-Accident FWST In-Leakage Sources

Rev. 0

CNC-1223.43-01-

27

Main Steam Power Operated Relief Valve Flow Capacity

Rev. 0

CNC-1227.00-00-

0106

Radiological Consequences of a DB LOCA at Catawba

Nuclear Station

Rev. 16

CNC-1227.00-00-

0130

Radiological Consequences of a DB MSLB at Catawba

Nuclear Station

Rev. 11

CNC-1381.05-00-

0012

4160 Volt Essential Auxiliary Power Switchgear Relay

Settings (Type I Changed to Type III)

Rev. 17

CNC-2206.02-83-

2011

Chemical and Volume Control System Rigorous Stress

Analysis Problem NVI

Rev. 9

DPC-1552.08-00-

0134

RSG FSAR Analyses - 15.2.3 - Turbine Trip

Rev. 8

DPC-1552.08-00-

0140

RSG FSAR Analyses - 15.2.8 - Feedwater System Pipe

Break

Rev. 4

Corrective Action

Documents

AR 01962944

Revision to Methodology Report DPC-NE-2009-P-A

11/03/2015

AR 02047559

Revision to Methodology Report DPC-NE-2009-P-A

04/20/2017

AR 02085006

VIPRE upgrade from mod 2r to mod 2.5adke

03/06/2017

AR 02104045

Revised SG PORV Flow Rates & Post-MSLB Cool-down

05/31/2017

AR 02110981

Update to Catawba Nuclear Station UFSAR Table 15-14

01/23/2018

AR 02213061

Addition of an External Constituent to the Control Room

07/18/2018

AR 02236975

CNS U1 Turbine Trip and Feedwater System Pipe Break

01/31/2019

AR 02245001

CNS UFSAR Chapter 15.4.7 Inadvertent Loading and

Operation of a Fuel Assembly

11/27/2018

AR 2287956

PT/1/A/4250/006 B - 0000215277 CA System Flow

08/21/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Verification Applicability Determination

ARs

1897290

1901154

1949424

1956237

1962944

2047559

2096392

2152427

2159141

25766

25774

251416

287953

287956

2085003

Corrective Action

Documents

Resulting from

Inspection

AR 2314794

20 50.59 EC 408742 UFSAR Update

2/06/2020

Drawings

CN-1578-01.00

Flow Diagram of Control Room Area Ventilation System

(VC)

Rev. 31

CN-1602-01.00

Flow Diagram of Nitrogen System (GN)

Rev. 30

CN-2569-01.00

Flow Diagram of Containment Valve Injection Water

System (NW)

Rev. 30

CN-2605-01.00

Flow Diagram of Instrument Air System (VI)

Rev. 11

CNM 1205.06-

0492.001

Outline Drawing for CMV-868, 1" FO Fisher Air Oper

Globe Valve

Rev. 0

CNM 1205.06-

0493.001

Valve and Actuator Instruction Manual for CMV-868 and

CMV-869, 1" and 2" FO Fisher Globe Valve

Rev. 0

Engineering

Changes

108311

Replace Valves 2NV202B and 2NV203A to Gain

Operating Margin

Rev. 2

114179

Unit 2 Removal of SPV at A518 Pin 24 in SSPS Logic

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Cabinets for Train A&B

2534

Optional Hydraulic Accumulator to be Installed on 1CF33,

1CF51, 1CF60, 2CF33, 2CF42, 2CF51, and 2CF60

Rev. 0

408429

ESF Backleakage to FWST and Leakage in Aux Bldg.

Revise FW, NV, NI, ND, NS DBD, TS Basis, UFSAR

Rev. 0

408429

ESF Backleakage to FWST and Leakage in Aux Building;

Revise FW, NV, NI, ND, NS DBD, TS Basis, UFSAR

Rev. 0

408742

Convert the Group 2 containment isolation valves (CIVs)

from NW Testing

to C-Leak Rate Testing (C-LRT)

Rev. 0

408742

NW Group 2: Convert to Type C Leak Rate Testing

Rev. 0

411844

Degraded Bus Timer Setpoint Change

Rev. 0

2812

Generate Test Acceptance Criteria for Reactor Vessel

Vents Flow Rate

Rev. 0

413660

Large NC System Vent - Remove 3 PZR Safety Valves

Rev. 0

94585

Replace D/G 2A Voltage Regulator/Excitation System

Rev. 7

Miscellaneous

CNEI-0400-341

Catawba 1 Cycle 25 Core Operating Limits Report

Rev. 1

CNEI-0400-355

Catawba 2 Cycle 24 Core Operating Limits Report

Rev. 0

CNM 1205.06-

0498.001

Weak Link Analysis for CMV-868 & CMV-869, 1" & 2" FO

Fisher Air Oper Globe Valve

2/02/2019

CNM 1205.06-

0499.001

Valve Actuator Sizing for CMV-868. 1" FO Fisher Air Oper

Globe Valve

2/02/2019

CNM 1301.00-

0449.001

Failure Mode & Effects Analysis of Voltage Regulator

System/Chassis P/N: 72-10800-100-ESI

Rev. 1

CNR-1205.06-00-

0011

Technical Requirements for Containment Valve Injection

Water (NW) System Surge Tank RN Supply Valves and

Surge Tank Outlet Valves

Rev. 1

CNS-1553.NC-00-

0001

Reactor Coolant System (NC) Design Basis Specification

Rev. 46

CNS-1569.NW-00-

0001

Containment Valve Injection Water System (NW) Design

Basis Document

Rev. 22

CNS-1578-VC.00-

0001

Control Room Ventilation Design Basis Specification

Rev. 39

CNTC-1571-

Primary Coolant Leakage Sources Outside Containment

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FW.S001-01

CNTC-2571-

FW.S001-01

Primary Coolant Leakage Sources Outside Containment

Rev. 0

DPC-NE-2009-PA

Duke Power Company Westinghouse Fuel Transition

Report

Rev. 3a, b, c

DPC-NE-3002-A

UFSAR Chapter 15 System Transient Analysis

Methodology

Rev. 4C

DPND-DPC-NE-

2005-A

Thermal-Hydraulic Statistical Core Design Methodology -

Non-Proprietary - Replaces DPND-DPC-NE-2005-PA -

Initial Issue

10/27/2016

UFSAR Section

15.4.7

Inadvertent Loading and Operation of a Fuel Assembly

Rev. 20

WCAP-12610-P-A &

CENPD-404-P-A

Addendum 1-A

Optimized ZIRLO(tm)

07/2006

WCAP-8963-P-A

Addendum 1-A

Safety Analysis for the Revised Fuel Rod Internal

Pressure Design Basis (Departure from Nucleate Boiling

Mechanistic Propagation Methodology)

Rev. 1-A

Procedures

AD-LS-ALL-0007

Applicability Determination Process

Rev. 6

EP/1/A/5000/E-0

Reactor Trip or Safety Injection

Rev. 44

IP/0/A/4971/005

Degraded Bus Voltage Trip and Alarm Timers Calibration

Procedure

Rev. 8

OP/1/A/6200/014

Refueling Water System

Rev. 91

OP/2/A/6200/019

Containment Valve Injection Water System

Rev. 40

PT/0/A/4150/022

Total Core Reloading

Rev. 59

PT/0/A/4550/003 C

Core Verification

Rev. 20

PT/1/A/4200/001 C

As Left Containment Isolation Valve Leak Rate Test

Rev. 132

PT/1/A/4200/001 K

Summation of Recirculation Backleakage to FWST

Rev. 0

PT/1/A/4200/001 L

Controlling Procedure For Type B & C Leak Rate Tests

Rev. 33

PT/1/A/4200/001 T

Containment Penetration Valve Injection Water System

Performance Test

Rev. 76

PT/1/A/4200/018 B

CF Valve Inservice Test (CS)

Rev. 41

PT/1/A/4200/027

NW Valve Inservice Test (QU)

Rev. 53

PT/1/A/4250/006 B

CA System Flow Verification Test

Rev. 24, 25

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

PT/2/A/4200/013

NV Valve Inservice Test (UNK)

Rev. 31

PT/2/A/4350/002A

Diesel Generator 2A Operability Test

08/27/2019

PT/2/A/4350/012A

Diesel Generator 2A Governor and Voltage Regulator

Test

09/27/2019

PT/2/A/4350/015A

Diesel Generator 2A Periodic Test

09/27/2019

Pump and Valve

Inservice

Pump and Valve Inservice Testing Program Manual

Rev. 33

TN/2/A/EC94585/01E Implementation of Diesel Generator 2A Voltage Regulator

Replacement

Rev. 3

TT/2/A/9300/081

NV Pump Miniflow Line Verification

Rev. 0

TT/2/A/EC94585/01E

Test Procedure for Diesel Generator 2A Voltage

Regulatory Replacement

Rev. 2

Work Orders

2198745

20189558-01

2560010

290927-01

290968-01

292012-01

294822-01, 02

20311516-01

20329544-01

20344519