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 Enterprise Identifier: I-2020-010-0037 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations CNC-1201.30-00- Determination of NC System Cooldown Time Following a Rev. 3

27 Main Steam Line Break

CNC-1223.03-00- Determination of Unit 2 Reactor Vessel Head Vent Flow Rev. 0

0038

CNC-1223.19-00- NW System Setpoint Calculation Rev. 9

0004

CNC-1223.21-00- Post-Accident FWST In-Leakage Sources Rev. 0

22

CNC-1223.43-01- Main Steam Power Operated Relief Valve Flow Capacity Rev. 0

27

CNC-1227.00-00- Radiological Consequences of a DB LOCA at Catawba Rev. 16

0106 Nuclear Station

CNC-1227.00-00- Radiological Consequences of a DB MSLB at Catawba Rev. 11

0130 Nuclear Station

CNC-1381.05-00- 4160 Volt Essential Auxiliary Power Switchgear Relay Rev. 17

0012 Settings (Type I Changed to Type III)

CNC-2206.02-83- Chemical and Volume Control System Rigorous Stress Rev. 9

2011 Analysis Problem NVI

DPC-1552.08-00- RSG FSAR Analyses - 15.2.3 - Turbine Trip Rev. 8

0134

DPC-1552.08-00- RSG FSAR Analyses - 15.2.8 - Feedwater System Pipe Rev. 4

0140 Break

Corrective Action AR 01962944 Revision to Methodology Report DPC-NE-2009-P-A 11/03/2015

Documents 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 11/27/2018

Operation of a Fuel Assembly

AR 2287956 PT/1/A/4250/006 B - 0000215277 CA System Flow 08/21/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Verification Applicability Determination

ARs

1897290

1901154

1949424

1956237

1962944

2047559

2096392

2152427

2159141

25766

25774

251416

287953

287956

2085003

Corrective Action AR 2314794 2020 50.59 EC 408742 UFSAR Update 02/06/2020

Documents

Resulting from

Inspection

Drawings CN-1578-01.00 Flow Diagram of Control Room Area Ventilation System Rev. 31

(VC)

CN-1602-01.00 Flow Diagram of Nitrogen System (GN) Rev. 30

CN-2569-01.00 Flow Diagram of Containment Valve Injection Water Rev. 30

System (NW)

CN-2605-01.00 Flow Diagram of Instrument Air System (VI) Rev. 11

CNM 1205.06- Outline Drawing for CMV-868, 1" FO Fisher Air Oper Rev. 0

0492.001 Globe Valve

CNM 1205.06- Valve and Actuator Instruction Manual for CMV-868 and Rev. 0

0493.001 CMV-869, 1" and 2" FO Fisher Globe Valve

Engineering 108311 Replace Valves 2NV202B and 2NV203A to Gain Rev. 2

Changes Operating Margin

114179 Unit 2 Removal of SPV at A518 Pin 24 in SSPS Logic Rev. 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Cabinets for Train A&B

2534 Optional Hydraulic Accumulator to be Installed on 1CF33, Rev. 0

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

408429 ESF Backleakage to FWST and Leakage in Aux Bldg. Rev. 0

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

408429 ESF Backleakage to FWST and Leakage in Aux Building; Rev. 0

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

408742 Convert the Group 2 containment isolation valves (CIVs) Rev. 0

from NW Testing

to C-Leak Rate Testing (C-LRT)

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 Rev. 0

Vents Flow Rate

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- Weak Link Analysis for CMV-868 & CMV-869, 1" & 2" FO 12/02/2019

0498.001 Fisher Air Oper Globe Valve

CNM 1205.06- Valve Actuator Sizing for CMV-868. 1" FO Fisher Air Oper 12/02/2019

0499.001 Globe Valve

CNM 1301.00- Failure Mode & Effects Analysis of Voltage Regulator Rev. 1

0449.001 System/Chassis P/N: 72-10800-100-ESI

CNR-1205.06-00- Technical Requirements for Containment Valve Injection Rev. 1

0011 Water (NW) System Surge Tank RN Supply Valves and

Surge Tank Outlet Valves

CNS-1553.NC-00- Reactor Coolant System (NC) Design Basis Specification Rev. 46

0001

CNS-1569.NW-00- Containment Valve Injection Water System (NW) Design Rev. 22

0001 Basis Document

CNS-1578-VC.00- Control Room Ventilation Design Basis Specification Rev. 39

0001

CNTC-1571- Primary Coolant Leakage Sources Outside Containment Rev. 0

Inspection Type Designation Description or Title Revision or

Procedure Date

FW.S001-01

CNTC-2571- Primary Coolant Leakage Sources Outside Containment Rev. 0

FW.S001-01

DPC-NE-2009-PA Duke Power Company Westinghouse Fuel Transition Rev. 3a, b, c

Report

DPC-NE-3002-A UFSAR Chapter 15 System Transient Analysis Rev. 4C

Methodology

DPND-DPC-NE- Thermal-Hydraulic Statistical Core Design Methodology - 10/27/2016

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

Initial Issue

UFSAR Section Inadvertent Loading and Operation of a Fuel Assembly Rev. 20

15.4.7

WCAP-12610-P-A & Optimized ZIRLO(tm) 07/2006

CENPD-404-P-A

Addendum 1-A

WCAP-8963-P-A Safety Analysis for the Revised Fuel Rod Internal Rev. 1-A

Addendum 1-A Pressure Design Basis (Departure from Nucleate Boiling

Mechanistic Propagation Methodology)

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 Rev. 8

Procedure

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 Rev. 76

Performance Test

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 Type Designation Description or Title Revision or

Procedure 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 09/27/2019

Test

PT/2/A/4350/015A Diesel Generator 2A Periodic Test 09/27/2019

Pump and Valve Pump and Valve Inservice Testing Program Manual Rev. 33

Inservice

TN/2/A/EC94585/01E Implementation of Diesel Generator 2A Voltage Regulator Rev. 3

Replacement

TT/2/A/9300/081 NV Pump Miniflow Line Verification Rev. 0

TT/2/A/EC94585/01E Test Procedure for Diesel Generator 2A Voltage Rev. 2

Regulatory Replacement

Work Orders 02198745

20189558-01

2560010

290927-01

290968-01

292012-01

294822-01, 02

20311516-01

20329544-01

20344519

9