IR 05000348/2019010

NRC Evaluation of Changes, Tests, and Experiments Report No. 05000348/2019010 and 05000364/2019010

ML19031C813
Person / Time
Site:	Farley
Issue date:	01/31/2019
From:	Robert Williams NRC/RGN-II/DRS/EB1
To:	Madison D Southern Nuclear Operating Co
References
IR 2019010
Download: ML19031C813 (9)

Text

UNITED STATES January 31, 2019

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT NUMBER 05000348/2019010 AND 05000364/2019010

Dear Mr. Madison:

On January 17, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2, and discussed the results of this inspection with Mr. Daniel Komm and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Robert E. Williams, Jr., Acting Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000348 and 05000364 License Nos.: NPF-2 and NPF-8 Enclosure:

Inspection Report 05000348/2019010 and 05000364/2019010

_ML19031C813 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII/DRS/EB1 RII/DRS/EB1 RII/DRS/EB1 RII/DRS/EB1 SIGNATURE BJD4 PXB3 CAF4 REW1 NAME B. Davis P. Braxton C. Franklin R. Williams DATE 1/ 29 /2019 1/ 30 /2019 1/ 29 /2019 1/ 31 /2019 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers: 05000348 and 05000364 License Numbers: NPF-2 and NPF-8 Report Numbers: 05000348/2019010 and 05000364/2019010 Enterprise Identifier: I-2019-010-0022 Licensee: Southern Nuclear Operating Co., Inc.

Facility: Joseph M. Farley Nuclear Plant, Units 1 and 2 Location: Columbia, AL 36319 Inspection Dates: January 14, 2019 to January 17, 2019 Inspectors: P. Braxton, Reactor Inspector B. Davis, Sr. Reactor Inspector C. Franklin, Reactor Inspector Approved By: Robert E. Williams, Jr., Acting 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 10 CFR 50.59 inspection at Joseph M. Farley Nuclear Plant, Units and 2, 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.

No finding or violation was identified.

TABLE OF CONTENTS

INSPECTION SCOPES

REACTOR SAFETY

..................................................................................................................

EXIT MEETINGS AND DEBRIEFS

.............................................................................................. 5 LIST OF

DOCUMENTS REVIEWED

............................................................................................ 6

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

The inspectors evaluated the following samples for compliance with Title 10, Code of

Federal Regulations (CFR) 50.59, Changes, Tests, and Experiments, from January 14,

2019 to January 17, 2019:

Changes, Tests, and Experiments (22 Samples)

(1) SNC655485 - Reactor Vessel Head Vent Restraints, Unit 1

(2) SNC785885 - Replace Cable 2VAJ2J10A, Unit 2

(3) SNC50287 - Emergency Diesel Generator (1A, 2A, 1B, 1C, 2C) Fuel Oil Day Tank Level

Setpoint and Instrument Changes, Units 1 & 2

(4) SNC782338 - Main Steam Valve Room "B" Bay Cracked Support Box Beam 2B9, Unit 2

(5) SNC540332 - Residual Heat Removal Low Flow Alarm Setpoint Change Version 1.0,

Unit 2

(6) SNC368758 - Residual Heat Removal Auto-Closure Interlock Removal, Unit 1

(7) SNC730101 - Main and Bypass Feed Regulator Valve Digital Positioner Upgrade, Unit 1

(8) SNC612802 - Replace the Turbine Driven Auxiliary Feed Water Warm up Line Check

Valve From the B Steam Generator, Unit 2

(9) SNC632333 - 2A Steam Generator Feed Pump Radial Bearing Vibration Point

Adjustment, Unit 2

(10) SNC814800 - Turbine Driven Auxiliary Feed Water Pump: Make Temporary Modification

SNC731742 Permanent, Unit 1

(11) SNC875794 - Install Jumper on the Turbine Driven Auxiliary Feed Water Governor

Valve, Unit 1

(12) SNC386541 - Minor Design Change Will Clear temporary Modification TM343204 on

Incore Thimble R-8, Unit 2

(13) SNC594819 - Design Change Proposal for Design for Addition of Automatic Isolation

Valves for the Refueling Water Storage Tank to the Refueling Water Purification Pump

Adjacent to Q2G31V010, Unit 2

(14) SNC582588 - Reactor Coolant Pump Shutdown Seal Replacement GEN III Minor

Design Change, Unit 2

(15) SNC50734 - Replace 1B Emergency Diesel Generator Governor, Unit 1

(16) SNC73454 - Replace R2, R7, R27A/B Radiation Monitors (Group 4BB/10B), Unit 2

(17) SNC459694 - Incipient Fire Detection Modifications, Unit 1

(18) SNC459687 - Cable and Raceway Fire Protection, Unit 1

(19) SNC459699 - 125 VDC Switchgear Breaker Coordination, Unit 2

(20) SNC808954 - Replace 4KV Breakers - Train A, Unit 1

(21) SNC902732 - Replace 4KV Switchgear Bus 2K Lightning Arrestor Power Cable -

2VADF02 Q, Unit 2

(22) SNC561820 - Yokogawa Main Control Board Paperless Recorder Replacements, Unit 1

EXIT MEETINGS AND DEBRIEFS

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

• On January 17, 2019, the inspectors presented the 10 CFR 50.59 inspection results to

Mr. Daniel Komm and other members of the licensee staff.

DOCUMENTS REVIEWED

Calculations

DOEJ-FDSNC50734-E001, Evaluation of Relay and Switches in Diesel Local Control Panel

Q1H21E527, Ver. 2

DOEJ-FDSNC50734-J001, Evaluation of the Emergency Diesel Generator 1B 2301A Analog

Governor Control Systems Electromagnetic Capability, Ver. 1

FMEA-FDSNC50734-E001, Analysis of EDG Governor Replacement Components, Ver. 2

Drawings

D205038, P&ID Safety Injection System, Ver. 38

D205043, P&ID Spent Fuel Pool Cooling System, Ver. 30

U611509, ESI - Turbine Control Wiring Diagram, Ver. 1

U611719, Model 93AS RCP Seal, Ver. 3

U732529, ESI - Turbine Control Schematic, Ver. 3

U732533, ESI - Turbine Control Schematic, Ver. 2

Procedures

IP-ENG-001, Standard Design Process, Ver. 0

NMP-AD-008, Applicability Determinations, Ver. 20

NMP-AD-009, Licensing Document Change Requests, Ver. 15

NMP-AD-010, 10 CFR 50.59 Screening and Evaluations, Ver. 15.1

NMP-ES-041, Minor Design Change Packages, Ver. 11.1

NMP-ES-044, Preparation of Design Change Packages, Ver. 13.1

NMP-ES-084, Design Control/Configuration Management Processes, Ver. 5.1

NMP-ES-095, Interface Procedure for IP-ENG-001, Standard Design Process, Ver. 5

Plant Modifications

SNC386541, Disposition of TM SNC343204, Ver. 1

SNC582588, Unit 2 RCP Shutdown Seal Generation III Installation, Ver. 1

SNC594819, U2 Addition of Auto Isolation Valves between RWST and RWPP Loop, Ver. 4

SNC612802, Replacement Valve for Q2N12V0004A, Ver. 1

SNC632333, 2A SGFP Radial Bearing Vibration Point Adjustment, Ver. 1

SNC814800, Reduce TDAFW Low-idle Setpoint to 800 RPM, Ver. 1

SNC875794, Disable Unit 1 Thermal Overload Switch for the Turbine Driven Auxiliary

Feedwater Pump Governor Valve Positioner, Ver. 2

SNC875795, Disable Unit 2 Thermal Overload Switch for the Turbine Driven Auxiliary

Feedwater Pump Governor Valve Positioner, Ver. 2

SNC368758, Residual Heat Removal Auto Closure Interlock Elimination, Ver. 2

SNC730101, Unit 1 Main and Bypass Feedwater Reg Valve Positioner Replacement, Ver. 5

SNC655485, Reactor Vessel Head Vent Restraint, Ver. 1

SNC785885, 2VAJ2J10A Cable Replacement, Ver. 1

SNC50287, Emergency Diesel Generator (1-2A, 1B, 1C, 2C) Fuel Oil Day Tank Level Setpoint

and Instrument Changes, Ver. 1

SNC782338, Unit 2 Main Steam Valve Room "B" Bay Cracked Support Box Beam 2B9, Ver. 2

SNC540332, Unit 2 Residual Heat Removal Low Flow Alarm Setpoint Change, Ver. 1

SNC561820, Unit 1 Yokogawa Main Control Board Paperless Recorder Replacement, Ver. 1

SNC902732, Unit 2 Replace 4KV Switch Gear Bus 2K Lightning Arrestor Power Cable -

2VADF02, Ver. 1

SNC808954, Unit 1 Replace 4KV Breakers - Train A, Ver. 1

SNC459699, Unit 2 125 VDC Switch Gear Breaker Coordination, Ver. 1

SNC459687, Unit 1 Cable and Raceway Fire Protection, Ver. 1

SNC459694, Unit 1 Incipient Fire Detection Modifications, Ver. 1

SNC50734, Unit 1 Replace 1B Emergency Diesel Generator Governor, Ver. 1

SNC73454, Unit 2 Replace R2, R7, R27A/B Radiation Monitors (Group 4BB/10B), Ver. 1

Miscellaneous Documents

25411-000-30R-M10G-00001, Addition of Automatic Isolation Valves for Refueling Water

Storage Tank Supply to Refueling Water Purification Pump, Ver. 1

DOEJ-FXNSC632333-J001, Report for the Farley 2A SGFP 2R23 Startup Vibration Analysis,

Ver. 1

FMEA-FMSNC582588-M001, FMEA for the Unit 2 RCP Shutdown Seal Generation III, Ver. 1

FM-S-13-002, Specification for RWST Air Operated Isolation 2-inch Ball Valves for Nuclear

Service, Ver. 2

PWROG-14001-P, PRA Model for the Generation III Westinghouse Shutdown Seal, Ver. 1

TR-FSE-14-1-P, Use of Westinghouse SHIELD Passive Shutdown Seal for FLEX Strategies,

Ver. 1

U262093, Auxiliary Feedwater Pump Turbine Drive Manual, Ver. 14

U277859, TDAFWP Turbine Instruction Manual, Ver. 11

U735869, Design and Seismic Stress Analysis per ASME B&PV Code Section III, Subsection

NC, Class 2 for 2 ANSI 150# Ball Valve, Ver. 1

U-733472, Fairbanks Morse Report No. R-5.00-4417(3) - Failure Modes and Effects

Analysis/Governor System Upgrade (Emergency Diesel Generator 1-2

A. 1B, 2B, 1C& 2C),

Ver. 5

U-733473, Fairbanks Morse Report No. R-5.00-4417(4) - Failure Modes and Effects

Analysis/Failures While Powered (Emergency Diesel Generator 1-2

A. 1B, 2B, 1C& 2C), Ver. 5

Condition Reports

368275

10571598

10572554

Work Orders

SNC343223

SNC758181

SNC73454

7