IR 05000348/2023001
| ML23122A168 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/04/2023 |
| From: | Alan Blamey Division Reactor Projects II |
| To: | Brown R Southern Nuclear Operating Co |
| References | |
| IR 2023001 | |
| Download: ML23122A168 (11) | |
Text
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT-INTEGRATED INSPECTION REPORT 05000348/2023001 AND 05000364/2023001
Dear R. Keith Brown:
On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On April 25, 2023, the NRC inspectors discussed the results of this inspection with Mr. Delson Erb 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, Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000348 and 05000364 License Nos. NPF2 and NPF8
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000348 and 05000364
License Numbers:
Report Numbers:
05000348/2023001 and 05000364/2023001
Enterprise Identifier:
I2023001-0021
Licensee:
Southern Nuclear Operating Company, Inc.
Facility:
Joseph M. Farley Nuclear Plant
Location:
Columbia, AL
Inspection Dates:
January 01, 2023 to March 31, 2023
Inspectors:
P. Meier, Senior Resident Inspector
S. Temple, 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
None.
PLANT STATUS
Unit 1 began the inspection period at approximately 100 percent rated thermal power (RTP). On
February 1, 2023, the unit experienced an unplanned uncomplicated reactor trip associated with
troubleshooting a vital DC ground (Licensee Event Report 05000348/2023001-00). On
February 4, 2023, the unit 1 reactor was restarted and reached approximately 100 percent RTP
on February 6, 2023. Unit 1 remained at approximately 100 percent RTP through the end of the
report period.
Unit 2 began the report period at approximately 100 percent 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 activities described in IMC 2515,
Appendix DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., Plant Status, observed risk significant activities, and completed on-site portions of
IPs. 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
Number 1 diesel-driven fire pump while the number 2 diesel-driven fire pump was out
of service for planned maintenance during the week of January 9, 2023
(FNP0SOP61.0 A; D170366)
(2)
Unit 2 A train high head safety injection system while the C charging pump was
inoperable for quarterly testing on January 24, 2023 (D205039)
(3)
Unit 2 B train auxiliary building 125 vital DC volt distribution system while aligned to
the C battery charger during B battery charger load testing on January 24, 2023
(D207082, D207083)
(4)
Unit 2 'B' motor-driven auxiliary feedwater system following planned system
maintenance and testing on March 21, 2022 (FNP2SOP22.0, D205007)
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a
walkdown and performing a review to verify program compliance, equipment functionality,
material condition, and operational readiness of the following fire areas:
(1)
Unit 2 auxiliary building cable chase (FZ2117) on March 15, 2023 (FNP2FPP1.0)
(2)
Unit 2 auxiliary building cable chase (FZ2246) on March 15, 2023 (FNP2FPP1.0)
(3)
Unit 2 control rod drive mechanism control system cabinet room (FA 2023) on
March 15, 2023 (FNP2FPP1.0)
(4)
Unit 2 electrical penetration room (FA 2035) on March 15, 2023 (FNP2FPP1.0)
(5)
Unit 2 'A' and 'B' motor-driven auxiliary feedwater pump rooms (FA 2006) on
March 15, 2023 (FNP2FPP1.0)
Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)
(1)
Announced fire drill inside the unit 1 radiation-controlled area (1 V motor control
center small electrical fire) on January 9, 2023
(2)
Announced fire drill at the service water pump house on March 8, 2023
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections in the unit 1 cable
spreading room on January 17, 2023 (calculation BM991932-001; FRIE-
IFU00006).
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 for the following activities:
Unit 1 manipulation of plant equipment, boration, and operator response to
various control room alarms on January 26, 2022
operator response following an unplanned Unit 1 reactor trip on
February 1, 2023
Unit 1 startup on February 4, 2023 following an unplanned reactor trip
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed licensed operator continuing training asleft exam
(LOCT Segment 231) on January 19, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following
structures, systems, and components (SSCs) remain capable of performing their intended
function:
(1)
Unit 1 vital DC ground troubleshooting that resulted in a unit 1 reactor trip
(CR 10944529, CAR372223)
(2)
Repetitive unit 1 main control board annunciator issues associated with grounds
(NMP-OS006002, SNC1364491)
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the
following planned and emergent work activities to ensure configuration changes and
appropriate work controls were addressed:
(1)
Unit 2 service air compressors B and 'C' emergent work on January 23, 2023
(NMP-DP001, CR 10941453, CR 10941558)
(2)
Unit 1 main generator real and reactive capability testing January 30, 2023
(FNP1ETP4223.0, SNC1207915)
(3)
New conduit and electrical cable installation in the unit 1 control room from main
feedwater flow transmitters to steam generator 'A' on January 31 and
February 1, 2023 (FNP0SOP0.0, SNC1424382)
(4)
Splitting out unit 1 supply of auxiliary steam supply from unit 2 on February 10, 2023
(FNP1SOP55.1)
(5)
Static oil pump issues and unit 2 motor auxiliary feedwater system planned motor
operated valve maintenance on February 23, 2023 (CR10950736, WO SNC996415)
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
12 A emergency diesel generator control circuit failure alarm received and identified
on December 27, 2022 (CR10935005)
(2)
Unit 1 reactor coolant loops delta temperature deviation alarm identified on
December 24, 2022 (CR10934242)
(3)
Security diesel generator apparent coolant leak identified on December 25, 2022
(CR10934418)
(4)
Unit 2 containment spray pump discharge valve (Q2E13MOV8820B) failed to close
during a valve stroke surveillance (FNP2STP16.7) identified on February 20, 2023
(CR10949573)
(5)
Unit 1 'B' train emergency diesel generator lube oil leak identified on
February 26, 2023 (CR10951589)
(6)
Unit 2 residual heat removal pump seal coolers pressure ratings and associated
pressure relief valve settings identified on February 17, 2015 (CR 10027796)
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Unit 1 replacement and rerouting of cables for FT447, FT487, FT497, and PT446
(DECP SNC1426773) completed January 17 to February 3, 2023
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system
operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)
(1)
Unit 2 motor-driven auxiliary feedwater pump feed water isolation to the 'A' steam
generator motor operated valve (MOV3764A) breaker and relay replacement on
January 10, 2023 (SNC996413, SNC445522)
(2)
Number 2 diesel-driven fire pump maintenance outage during the week of
January 9, 2023 (WO SNC1253916; SNC1337362)
(3)
Security uninterruptible power supply maintenance on February, 23, 2023
(WO SNC1373970)
(4)
Unit 1 'A' service water pump testing following a planned pump maintenance outage
on March 7, 2023 (WO SNC1081989)
(5)
The number 1 diesel-driven fire pump functional test following pump relief valve
scheduled maintenance on March 10, 2023 (SNC11362475)
Surveillance Testing (IP Section 03.01) (3 Samples)
(1)
Unit 1 'A' train service water pumps 'A', 'B', and 'C' surveillance test on
January 19, 2023 (FNP1STP24.1)
(2)
Unit 2 'C' component cooling water pump surveillance on March 6, 2023
(FNP2STP23.3)
(3)
Unit 1 'B' train containment spray system valve stroke testing on March 28, 2023
(FNP1STP16.7)
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
(1)
Unit 1 'B' residual heat removal pump quarterly inservice test on January 4, 2023
(FNP1STP11.2)
(2)
Unit 2 'A' motor-driven auxiliary feedwater pump inservice test on January 18, 2023
(FNP2STP22.1)
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
(1)
The inspectors observed an emergency response organization drill involving a mode
1 loss of coolant accident and safety injection actuation leading to a radiation release
and a general emergency classification on February 21, 2023.
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
(1)
Licensed operator response during a simulator exam involving a loss of heat sink that
contributed to the drill and exercise performance indicator on January 19, 2023.
OTHER ACTIVITIES-BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (2 Samples)
(1)
Unit 1 (January 1, 2022, through December 31, 2022)
(2)
Unit 2 (January 1, 2022, through December 31, 2022)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
(1)
Unit 1 (January 1, 2022, through December 31, 2022)
(2)
Unit 2 (January 1, 2022, through December 31, 2022)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
(1)
Unit 1 (January 1, 2022, through December 31, 2022)
(2)
Unit 2 (January 1, 2022, through December 31, 2022)
71152 A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
(1)
Higher than expected startup rate during the unit 1 startup following the 1R31
refueling outage identified on December 21, 2022 (CR 10933508)
(2)
Identifying correct operation of the security backup power supply identified on
February 24, 2023 (CR10951055)
INSPECTION RESULTS
Observation: Farley Unit 1 Excessive Startup Rate Issue
71152 A
The inspectors reviewed the licensees corrective action report (CAR 356458) associated with
issues identified by the resident inspector during unit 1 startup in December 2022 following an
extended refueling outage.
On December 21, 2022, while conducting startup, the startup rate (SUR) exceeded the Farley
plant procedure (FNP1UOP1.2, Startup of Unit from Hot Standby to Minimum Load) limit
due to excessive control rod withdrawal. This resulted in an imprecise recognition of the
approach to criticality by the control room staff. Upon recognition, operators prevented a
reactor startup trip by inserting control rods before the source range trip actuation setpoints.
Control rods were inserted to lower power on the source range and intermediate range
meters and to stabilize the SUR to a considerably lower level at criticality before proceeding
on to the point of adding heat.
Immediately following the event, the resident inspector reviewed various startup trends to
determine the significance of the issue and whether a startup trip should have occurred. Upon
review of the trends, the inspector identified the SUR exceeded the procedurally required limit
of one decade per minute (dpm). Specifically, the source range and intermediate range SURs
exceeded two dpm before control rods were inserted to slow the startup. Although the highest
source range SUR approached the trip setpoint, the inspector noted that it was not exceeded
based on the computer data available.
Based on the event, the resident inspector identified a minor violation:
a.
Minor issue: The inspectors identified a minor violation of Farleys Technical Specifications (TS) 5.4.1.a for the licensees failure to implement written procedures
covering activities applicable in Regulatory Guide (RG) 1.33, Revision 2, Appendix A,
February 1978. Specifically, while conducting a unit 1 reactor startup on December 21,
2022, the licensee exceeded the SUR limit specified in the procedure governing nuclear
startup from hot standby to minimum load (RG 1.33, App. A, Section 2.b),
FNP1UOP1.2.
b.
Screening: The failure to implement the SUR limit of startup procedure FNP1UOP1.2
was a performance deficiency. The performance deficiency was determined to be minor
in accordance with IMC 0612 Appendix B because it did not adversely affect the Reactor
Safety-Initiating Events cornerstone. The inspector referenced Inspection Manual
Chapter 0612 Appendix E, 12/10/20, example 4.b and 9.a, to further inform the minor
determination. A reactor trip was prevented (example 4.b) and the thermal power limits
were not exceeded (example 9.a) thus preventing any actual safety consequences that
challenged the reactor, fuel integrity, or any other safety systems.
c.
Enforcement: The failure to comply with TS 5.4.1.a constitutes a minor violation that is not
subject to enforcement action in accordance with the NRCs Enforcement Policy.
The inspectors reviewed the licensees casual report and associated corrective actions
documented in CAR 356458. Farley determined the direct causes to be inadequate
monitoring of diverse indication and the failure to establish critical parameters to minimize the
significance. For the primary cause, the licensee determined that supervisory and
management oversight failed to ensure adequate preventive actions were in place prior to the
startup activity and failed to timely intervene during the actual startup.
The licensee corrective actions to address the issue were implemented and/or in progress.
The inspectors summarized the corrective actions below:
A change to FNP1UOP1.2, Startup of Unit From Hot Standby to Minimum Load,
lowered the allowed SUR to 0.5 dpm and now requires more hold points during the
approach to criticality. Additional enhancements were added to align with industry
normal startup practices and improved monitoring point options or parameters via the
plant computer. The inspectors observed these changes implemented during training
on the simulator in January 2023 and during an actual startup observed in
February 2023.
The licensee is using their training process (Systematic Approach to Training) to
address the use of diverse indications, critical parameters, and to improve oversight
intervention. The inspectors reviewed the specific training process corrective actions
with the operations training manager.
Operations supervisors performed various actions to address supervisor intervention
skills for all plant activities via oversight preparation and verification of impactful
interventions. The inspectors observed several actions associated with this which
included end-ofshift and weekly meetings between the shift supervisors and
operations managers to discuss and trend daily learnings.
The inspectors did not identify any new findings or violations as a result of this inspection.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 25, 2023, the inspectors presented the integrated inspection results to Mr.
Delson Erb and other members of the licensee staff.