IR 05000348/2019004

Integrated Inspection Report 05000348/2019004 and 05000364/2019004 and Independent Spent Fuel Storage Installation Report 07200042/2019003 and 07200042/2019002

ML20044E628
Person / Time
Site:	Farley, 07200042
Issue date:	02/13/2020
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2019002, IR 2019003, IR 2019004
Download: ML20044E628 (15)

Text

ary 13, 2020

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000348/2019004 AND 05000364/2019004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200042/2019003 AND 07200042/2019002

Dear Ms. Gayheart:

On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On January 21, 2020, the NRC inspectors discussed the results of this inspection with Keith Brown 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/

Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000348, 05000364 and 07200042 License Nos. NPF-2 and NPF-8

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000348, 05000364, and 07200042 License Numbers: NPF-2 and NPF-8 Report Numbers: 05000348/2019004, 05000364/2019004, 07200042/2019002 and 07200042/2019003 Enterprise Identifier: I-2019-004-0027 and I-2019-003-0081 and I-2019-002-0096 Licensee: Southern Nuclear Operating Co., Inc.

Facility: Joseph M. Farley Nuclear Plant Location: Columbia, AL Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: B. Caballero, Senior Operations Engineer R. Carrion, Senior Reactor Inspector B. Collins, Senior Reactor Inspector P. Meier, Senior Resident Inspector K. Miller, Resident Inspector Approved By: Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Joseph M. Farley Nuclear 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 Type Issue Number Title Report Section Status LER 05000364/2019-003-00 LER 2019-003-00 for Joseph 71153 Closed M. Farley Nuclear Plant, Unit 2, Manual Reactor Trip due to 2C Reactor Coolant Pump High Vibration Indication

PLANT STATUS

Unit 1 began the report period in mode 5 for a refueling outage. Following the refueling outage, mode 1 was achieved on October 24 and the unit was synchronized to the grid on October 25.

100 percent rated thermal power (RTP) was achieved on October 29. The unit remained at or near 100 percent RTP level through the end of the report period.

Unit 2 began the report period at approximately 100 percent rated thermal RTP and remained at or near 100 percent RTP through the end of the report period.

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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 'A' train A/C distribution and 'A' train emergency diesel generator during the unit 1 refueling outage 'B' train maintenance window on October 7, 2019 (FNP-1-STP-27.1)

(2) Unit 2 'A' train containment spray system alignment during the 'B' train containment spray pump surveillance on November 4, 2019 (FNP-2-SOP-9.0A)

(3) #1 diesel driven fire pump and motor driven fire pump alignment during a #2 diesel driven fire pump planned maintenance outage on December 9, 2019 (Dwg D170366; WO SNC994937)

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) U1 service water system on October 10 to 13, 2019 (Dwg D170119)

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 1 containment (FZ 1-CTMT) on October 20, 2019 (FNP-1-FPP-3)

(2) Unit 1 '1A' 125 VDC switchgear room (FZ 224) on December 11, 2019 (FNP-1-FPP-1.0)

(3) Unit 1 '1B' 125 VDC switchgear room (FZ 226) on December 11, 2019 (FNP-1-FPP-1.0)

(4) Unit 1 '1C' 125 VDC battery charger room (FZ 224) on December 11, 2019 (FNP-1-FPP-1.0)

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from October 7 - 11, 2019:

(1) Ultrasonic Examination (UT)a. Examination of ALA2-4507-1-OE-UT, Tee to Pipe Weld on 10" diameter Residual Heat Removal (RHR) Piping; ASME Class 2 (observed)b. Examination of ALA2-4507-2-OE-UT, Pipe to Elbow Weld on 10" diameter RHR Piping; ASME Class 2 (observed)c. Examination of ALA2-4507-3-OE-UT, Elbow to Pipe Weld on 10" diameter RHR Piping; ASME Class 2 (observed)

(2) Penetrant Testing (PT)a. Examination of ALA1-4304-7-RB, Pipe to Valve Weld on 6" diameter Safety Injection Piping; ASME Class 1 (observed)

(3) Visual Examination (VE)a. Examination of ALA1-4304-7-RB, Pipe to Valve Weld on 6" diameter Safety Injection Piping; ASME Class 1 (observed)

(4) Eddy Current Testing (ET)a. SG 2A - ET for tubes R1C41 & R3C4, ASME Class 1 (observed)b. SG 2B - ET for tubes R1C76 & R2C77, ASME Class 1 (observed)c. SG 2C - ET for tubes R38C59 & R1C45, ASME Class 1 (observed)

The Inspectors evaluated the licensees boric acid corrosion control program performance.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)

The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. During the week of November 25, 2019, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP

===71111.11.

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam, which the facility licensee completed administering on September 18, 2019.

==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during unit 1 reactor coolant system drain down to the reactor flange in preparation for refueling on October 2, 2019 and during unit 1 reactor startup on October 23, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)==

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Unit 1 'C' service water pump failure due to maintenance errors during the unit 1 outage in October 2019 and the associated repair in November 2019 (WO SNC1055920).

Quality Control (IP Section 02.02) ===

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Unit 1 main steam isolation valve overhauls during the refueling outage in October 2019 (WO SNC966900, SNC966902, SNC771090, SNC771103).

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Unit 1 risk associated with the time the 1C service water pump was out of service for replacement from October 21, 2019 to November 8, 2019 (NMP-DP-001).

(2) Risk while the unit '1C' emergency diesel generator was out of service from November 17, 2019 to November 20, 2019 (NMP-DP-001).

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Portion of debris interceptor inside unit 1 containment removed during mode 3 walk down on September 29, 2019 (CR10650505).

(2) 1E service water pump breaker did not open during the load shed surveillance while in mode 5 on September 30, 2019 (FNP-1-STP-80.15; CR10650998).

(3) Unpinned snubber identified near the regenerative heat exchanger potentially affecting the operability of the residual heat removal system on October 23, 2019 during the unit 1 refueling outage (CR 10658165).

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Unit 1 'B' train residual heat removal pump motor replacement during the unit 1 outage in October 2019 (WO SNC550842)

(2) Unit 1 'A' steam generator outboard MSIV (Q1N11V002A) overhaul during the unit 1 outage in October 2019 (WO SNC966900)

(3) Unit 1 'C' service water pump replacement in November 2019 (WO SNC1055920).

(4) Unit 1 containment tendon (H15AB) field end anchor replacement on November 2019 (WO SNC1020164)

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) Unit 1 refueling outage 29 from September 29, 2019 - October 25, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) Unit 2 'B' emergency diesel generator operability test done on October 30, 2019, (FNP-2-STP-80.1)

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Local leak rate testing on the unit 1 containment instrument air inside containment isolation check valve on October 17, 2019, during a refueling outage (WO SNC993450)

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05) ===

(1) Unit 1 (October 1, 2018 - September 30, 2019)

(2) Unit 2 (October 1, 2018 - September 30, 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (October 1, 2018 - September 30, 2019)

(2) Unit 2 (October 1, 2018 - September 30, 2019)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (October 1, 2018 - September 30, 2019)

(2) Unit 2 (October 1, 2018 - September 30, 2019)

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends regarding fire pump issues that might be indicative of a more significant safety issue (CR 10666490).

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Unit 1 aggregated operator issues before the October 2019 refueling outage and after the outage to ensure timely resolution based on the safety and risk significance (NMP-OS-006-002).

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000364/2019-003-00, Manual Reactor Trip due to 2C Reactor Coolant Pump High Vibration Indication (ADAMS accession: ML191316C570). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60853 - On-Site Fabrication of Components and Construction on an ISFSI On-Site Fabrication of Components and Construction on an ISFSI

(1) The inspectors conducted a review of licensee and vendor activities in preparation for the concrete placement for the center section of the Independent Spent Fuel Storage Installation (ISFSI) Pads F and G. The licensee will use the HI-STORM (Holtec International Storage Module) 100 System on the pad. The inspectors walked down the construction area of the ISFSI pad and examined the rebar installation, for compliance to licensee-approved drawings, specifications, procedures, and applicable codes, the certificate of compliance and technical specifications. The inspectors also evaluated the concrete formwork installation for compliance to the licensee-approved drawings. The inspectors interviewed licensee and contract personnel to verify knowledge of the planned work. The inspectors also observed the actual concrete placements for the center section of the ISFSI slabs and observed testing and sample collection by the independent testing laboratory to verify that the work was implemented according to approved specifications and procedures. Later, when the 7-and 28-day compression tests were completed by the independent laboratory, the inspectors reviewed the results to verify that the acceptance criteria were met.

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

(1) Verified that routine activities are performed in accordance with approved procedures and surveillance activities have been conducted at the specified periods on December 10, 2019 (FNP-0-STP-63.7).

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 21, 2020, the inspectors presented the integrated inspection results to Keith Brown and other members of the licensee staff.

• On October 10, 2019, the inspectors presented the ISI and SGISI inspection results to Chuck Kharrl, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Corrective Action CR 10491728 Missed NDE on welds

Documents CR 10517412 CR is written to I&R a boric acid leak in the U1 121' PPR

CR 10539379 U1 CTMT BA Walkdown: Boric Acid Found on

Q1B13V094B

CR 10539398 U1 CTMT BA Walkdown: Boric Acid Found on valve near

Q1E21V536A

CR 10551009 ISI Plan revision needed

CR 10591502 Weld Procedure Specification Change

CR 10599595 ISI Inspections

CR 10600957 Unapproved chemical used for purge damns in welding

process

CR 10602704 Performance Analysis request on ASME Code

CR 10608492 CR is written as a tracking item for ISI engineer to ensure

a relief request is submitted to the NRC

CR 10609029 BACCP Corrosion Assessment Procedure Revision

Needed

CR 10609031 Boric Acid Corrosion Assessment WELL sheet is needed

CR 10628228 Boric Acid Leak on Q1E21MOV8803A

CR 10633358 Request re-evaluation of Q1E21V134A Leakage

CR 10643619 Boric Acid Found on Q1E21V350

CR 10646814 Service Water Piping Through Wall Leak

CR 10647009 Boric Acid found on Q1E21P002A

Engineering Corrosion 4/24/2018

Evaluations Assessment 1B13-

2018-001

Corrosion 04/17/2019

Assessment 1B31-

2019-001

Corrosion 10/02/2019

Assessment 1E13-

2019-001

Corrosion 04/16/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Assessment 1E21-

2019-001

Corrosion 04/21/2019

Assessment 1E21-

2019-003

Miscellaneous Krautkramer Transducer Certification for Transducer S/N dated

00X125 1/17/03

Framatome Certificate of Personnel Qualification: ET III- January 30,

QDA (Greene) 2019

Framatome Certificate of Vision Examination (Greene) January 30,

2019

Framatome Certificate of Personnel Qualification: ET III- February 23,

QDA (LaReau) 2015

Framatome Certificate of Vision Examination (LaReau) July 11,

2019

NDE Personnel Certification Records for D. Brown and S.

Overly

Magnaflux Sonotrace 30 Certificate of Certification, Batch 01/18/2019

1. 19A061

Magnaflux Spotcheck Developer SKD-S2 Certificate of 06/16/2015

Certification, Batch #15F11K

Magnaflux Spotcheck Penetrant SKL-SP2 Certificate of 05/14/2014

Certification, Batch #14E08K

Magnaflux Spotcheck Remover SKC-S Certificate of 05/24/2017

Certification, Batch #17E21K

Olympus Pulse/Receiver Certification; Transducer dated 06-18-

S/N1161144, Instrumentation - Epoch 600, 2018

S/N130521708

Certificate of Calibration for IR Thermometer, serial 8/26/2019

number 19330320, Equipment Number 30006631

Krautkramer Transducer Certification for Transducer S/N dated 2/7/02

00T8K9

Welder Continuity Logs for C. Hughes

Welder Process Qualification Report for C. Hughes

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedure GTAW Manual Revision 0

Qualification Record

B06

Welding Procedure GTAW/Manual Revision 6

Specification 8.20N

NDE Reports Visual Examination of ALA1-4304-7-RB, Pipe to Valve 10/9/19

Weld on Safety Injection Piping

S19F1P001 Liquid Penetrant Examination of ALA1-4304-7-RB, Pipe to 10/9/19

Valve Weld on Safety Injection Piping

S19F1U022 Ultrasonic Examination of ALA2-4507-1-OE-UT, Tee to 10/9/19

Pipe Weld on RHR Piping

S19F1U023 Ultrasonic Examination of ALA2-4507-2-OE-UT, Pipe to 10/9/19

Elbow Weld on RHR Piping

S19F1U024 Ultrasonic Examination of ALA2-4507-3-OE-UT, Elbow to 10/9/19

Pipe Weld on RHR Piping

Procedures 03-1246524 Instructions for Plug Visual Inspection Rev. 015

03-1274986 Framatome Site Requirements for Water Lancing Rev. 010

03-1275114 Framatome Eddy Current Data Management Guidelines Rev. 020

03-9293806 Framatome Farley Unit 1 and Unit 2 Steam Generator Rev. 000

Eddy Current Data Analysis Guidelines

03-9300210 Framatome Secondary Side Visual Inspection Plan for Rev. 000

Joseph M. Farley Unit 1 R29

51-9300171 Framatome Engineering Information Record: Farley Unit 1 Rev. 000

1R29 SG ECT Inspection Plan

FNP-0-ETP-019.0 Leakage Assessment Program Version 2.0

NMP-ES-019 Boric Acid Corrosion Control Program Version 11.1

NMP-ES-019-001 Boric Acid Corrosion Control Program Implementation Version 11.1

NMP-ES-019-003 Boric Acid Deposit Sampling, Analysis and Data Version 2.1

Evaluation

NMP-ES-019-004 Boric Acid Corrosion Control Program - Corrosion Version 5.1

Assessment

NMP-ES-024-301 Liquid Penetrant Examination Color Contrast and Version 13.1

Fluorescent

NMP-ES-024-501 PDI Generic Procedure for the Ultrasonic Examination of Version 7.0

Inspection Type Designation Description or Title Revision or

Procedure Date

Austenitic Pipe Welds (Appendix VIII)

NMP-MA-013 Leak Management Program Version 14.1

Work Orders SNC971494 *OHI - (Pri 2 CA) U1 CTMT BA Walkdown: Boric Acid

Found on Q1B13V094B

60853 Corrective Action CR10528286 ISFSI Expansion Project Site Preparation Tasks Delayed

Documents Due to 1-2A EDG Outage

CR10570292 ISFSI Expansion Construction Area Boundary Violations

Drawings SNC883674C104 ISFSI Storage Facility - Excavation and Backfill - Plan & Version 1.0

Sections

SNC883679C104 ISFSI Expansion Storage Pads F and G - Site Layout Version 1.0

Plan

SNC883679C200 ISFSI Expansion Storage Pads F and G - Neat Line Version 1.0

SNC883679C201 ISFSI Expansion Storage Pads F and G, - Section, Version 1.0

Details & Reinforcing

SNC883679C202 ISFSI Expansion Storage Pads F and G, -Subsurface Version 1.0

Profile and Details

SNC883679C413 ISFSI Storage Facility General Arrangement Version 1.0

SNC883679C415 ISFSI Storage Facility - Miscellaneous Pads Location - Version 1.0

Plan

SNC883679C417 ISFSI Storage Facility - Finished Surface Aggregate Plan Version 1.0

SNC883679C418 ISFSI Storage Facility - Fence and Gate Location Plan Version 1.0

SNC883679SKC001 Independent Spent Fuel Storage Installation (ISFSI) Version 1.0

Expansion Final Site Layout

Engineering DCP SNC883679 ISFSI Storage Pad Revision 2.0

Changes Field Change ISFSI Project Requested Changes Revision 1.0

Request Number

SNC883679FCR01

Engineering 10 CFR 50.59 Screening for DCP SNC883679, ISFSI Version 1.0

Evaluations Storage Pad

CFR 72.48 Screening for DCP SNC883679, ISFSI Version 1.0

Storage Pad

Applicability Determination for DCP SNC883679, ISFSI Version 1.0

Storage Pad

Inspection Type Designation Description or Title Revision or

Procedure Date

SNC88367972.48 10 CFR 72.48 Screening for ISFSI Pad (DCP SNC883679)

Miscellaneous SNC883679SKC005 Configuration Control Activity Worksheet Version 1.1

Procedures BG-QC-C-0001 Construction QC Procedure, Structural Concrete Revision 0

Placement

BG-QC-C-0002 Construction QC Procedure, Structural Concrete Activities Revision 0

BG-QC-C-0003 Construction QC Procedure, Concrete Sampling & Testing Revision 0

BG-QC-E-0001 Construction QC Procedure, Earthwork Revision 0

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