IR 05000348/2019004
| 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
February 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:
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
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 M. Farley Nuclear Plant, Unit 2, Manual Reactor Trip due to 2C Reactor Coolant Pump High Vibration Indication 71153 Closed
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.
REACTOR SAFETY
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
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 Sample)
- (1) U1 service water system on October 10 to 13, 2019 (Dwg D170119)
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
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) (1 Sample)
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) (1 Sample)
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) (2 Samples)
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) (3 Samples)
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) (4 Samples)
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 Sample)
- (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 Sample)
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.08P Corrective Action
Documents
CR 10491728
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
Evaluations
Corrosion
Assessment 1B13-
2018-001
4/24/2018
Corrosion
Assessment 1B31-
2019-001
04/17/2019
Corrosion
Assessment 1E13-
2019-001
10/02/2019
Corrosion
04/16/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Assessment 1E21-
2019-001
Corrosion
Assessment 1E21-
2019-003
04/21/2019
Miscellaneous
Krautkramer Transducer Certification for Transducer S/N
00X125
dated
1/17/03
Framatome Certificate of Personnel Qualification: ET III-
QDA (Greene)
January 30,
2019
Framatome Certificate of Vision Examination (Greene)
January 30,
2019
Framatome Certificate of Personnel Qualification: ET III-
QDA (LaReau)
February 23,
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
- 19A061
01/18/2019
Magnaflux Spotcheck Developer SKD-S2 Certificate of
Certification, Batch #15F11K
06/16/2015
Magnaflux Spotcheck Penetrant SKL-SP2 Certificate of
Certification, Batch #14E08K
05/14/2014
Magnaflux Spotcheck Remover SKC-S Certificate of
Certification, Batch #17E21K
05/24/2017
Olympus Pulse/Receiver Certification; Transducer
S/N1161144, Instrumentation - Epoch 600,
S/N130521708
dated 06-18-
2018
Certificate of Calibration for IR Thermometer, serial
number 19330320, Equipment Number 30006631
8/26/2019
Krautkramer Transducer Certification for Transducer S/N
00T8K9
dated 2/7/02
Welder Continuity Logs for C. Hughes
Welder Process Qualification Report for C. Hughes
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedure
Qualification Record
B06
GTAW Manual
Revision 0
Welding Procedure
Specification 8.20N
GTAW/Manual
Revision 6
NDE Reports
Visual Examination of ALA1-4304-7-RB, Pipe to Valve
Weld on Safety Injection Piping
10/9/19
S19F1P001
Liquid Penetrant Examination of ALA1-4304-7-RB, Pipe to
Valve Weld on Safety Injection Piping
10/9/19
S19F1U022
Ultrasonic Examination of ALA2-4507-1-OE-UT, Tee to
10/9/19
S19F1U023
Ultrasonic Examination of ALA2-4507-2-OE-UT, Pipe to
10/9/19
S19F1U024
Ultrasonic Examination of ALA2-4507-3-OE-UT, Elbow to
10/9/19
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
Eddy Current Data Analysis Guidelines
Rev. 000
03-9300210
Framatome Secondary Side Visual Inspection Plan for
Joseph M. Farley Unit 1 R29
Rev. 000
51-9300171
Framatome Engineering Information Record: Farley Unit 1
Rev. 000
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
Evaluation
Version 2.1
NMP-ES-019-004
Boric Acid Corrosion Control Program - Corrosion
Assessment
Version 5.1
NMP-ES-024-301
Liquid Penetrant Examination Color Contrast and
Fluorescent
Version 13.1
NMP-ES-024-501
PDI Generic Procedure for the Ultrasonic Examination of
Version 7.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Documents
CR10528286
ISFSI Expansion Project Site Preparation Tasks Delayed
Due to 1-2A EDG Outage
CR10570292
ISFSI Expansion Construction Area Boundary Violations
Drawings
SNC883674C104
ISFSI Storage Facility - Excavation and Backfill - Plan &
Sections
Version 1.0
SNC883679C104
ISFSI Expansion Storage Pads F and G - Site Layout
Plan
Version 1.0
SNC883679C200
ISFSI Expansion Storage Pads F and G - Neat Line
Version 1.0
SNC883679C201
ISFSI Expansion Storage Pads F and G, - Section,
Details & Reinforcing
Version 1.0
SNC883679C202
ISFSI Expansion Storage Pads F and G, -Subsurface
Profile and Details
Version 1.0
SNC883679C413
ISFSI Storage Facility General Arrangement
Version 1.0
SNC883679C415
ISFSI Storage Facility - Miscellaneous Pads Location -
Plan
Version 1.0
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)
Expansion Final Site Layout
Version 1.0
Engineering
Changes
DCP SNC883679
ISFSI Storage Pad
Revision 2.0
Field Change
Request Number
SNC883679FCR01
ISFSI Project Requested Changes
Revision 1.0
Engineering
Evaluations
CFR 50.59 Screening for DCP SNC883679, ISFSI
Storage Pad
Version 1.0
CFR 72.48 Screening for DCP SNC883679, ISFSI
Storage Pad
Version 1.0
Applicability Determination for DCP SNC883679, ISFSI
Storage Pad
Version 1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SNC88367972.48
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
Placement
Revision 0
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