ML18318A053: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                  NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                REGION II
REGION II  
                              245 PEACHTREE CENTER AVENUE NE, SUITE 1200
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
                                      ATLANTA, GEORGIA 30303-1257
ATLANTA, GEORGIA 30303-1257  
                                      November 9, 2018
November 9, 2018  
Dennis R. Madison
Dennis R. Madison  
Vice President
Vice President  
Southern Nuclear Operating
Southern Nuclear Operating
   Company, Inc.
   Company, Inc.
Joseph M. Farley Nuclear Plant
Joseph M. Farley Nuclear Plant  
7388 North State Highway 95
7388 North State Highway 95  
Columbia, AL 36319
Columbia, AL 36319  
SUBJECT:         JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION
                  REPORT 05000348/2018003 AND 05000364/2018003
SUBJECT:  
Dear Mr. Madison:
JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2. On October 16, 2018, NRC
inspectors discussed the results of this inspection with you and other members of your staff.
REPORT 05000348/2018003 AND 05000364/2018003  
The results of this inspection are documented in the enclosed report.
NRC inspectors documented one Licensee Identified Violation and one Severity Level (SL) IV
Dear Mr. Madison:  
violation with no associated finding. The NRC is treating the SL IV violation as a non-cited
violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an  
violations or significance of this NCV, you should provide a response within 30 days of the date
inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2. On October 16, 2018, NRC  
of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory
inspectors discussed the results of this inspection with you and other members of your staff.
Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the
The results of this inspection are documented in the enclosed report.  
Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident
inspector at the Joseph M. Farley Nuclear Plant, Units 1 and 2.
NRC inspectors documented one Licensee Identified Violation and one Severity Level (SL) IV  
This letter, its enclosure, and your response (if any) will be made available for public inspection
violation with no associated finding. The NRC is treating the SL IV violation as a non-cited  
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the  
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
violations or significance of this NCV, you should provide a response within 30 days of the date  
Withholding.
of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory  
                                                Sincerely,
Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the  
                                                /RA/
Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident  
                                                Alan Blamey, Branch Chief
inspector at the Joseph M. Farley Nuclear Plant, Units 1 and 2.  
                                                Reactor Projects Branch 2
                                                Division of Reactor Projects
This letter, its enclosure, and your response (if any) will be made available for public inspection  
Docket Nos.: 50-348, 50-364
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document  
License Nos.: NPF-2, NPF-8
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for  
Enclosure:
Withholding.  
IR 05000348/2018003, 05000364/2018003
Sincerely,  
/RA/  
Alan Blamey, Branch Chief  
Reactor Projects Branch 2  
Division of Reactor Projects  
Docket Nos.: 50-348, 50-364  
License Nos.: NPF-2, NPF-8  
Enclosure:  
IR 05000348/2018003, 05000364/2018003  
cc Distribution via ListServ
cc Distribution via ListServ


D. Madison                               2
D. Madison  
SUBJECT:       JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION
2  
              REPORT 05000348/2018003 AND 05000364/2018003
DISTRIBUTION:
SUBJECT:  
S. Price, RII
JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION
M. Kowal, RII
K. Sloan, RII
OE Mail
REPORT 05000348/2018003 AND 05000364/2018003
RIDSNRRDIRS
PUBLIC
RidsNrrPMFarleyResource
DISTRIBUTION:  
ADAMS ACCESSION NUMBER: [Accession Number]
S. Price, RII  
OFFICE       RII/ DRP   RII/ DRP RII/ DRP   RII/ DRP   RII/ DRP RII/ DRP
M. Kowal, RII  
  NAME         K. Miller A. Blamey P. Niebaum N. Staples D. Mas   M. Schwieg
K. Sloan, RII  
  DATE         10/31/2018 11/9/2018 10/31/2018 10/31/2018 11/1/2018 10/31/2018
OE Mail
RIDSNRRDIRS  
PUBLIC  
RidsNrrPMFarleyResource  
ADAMS ACCESSION NUMBER: [Accession Number]  
OFFICE  
RII/ DRP  
RII/ DRP  
RII/ DRP  
RII/ DRP  
RII/ DRP  
RII/ DRP  
   
NAME  
K. Miller  
A. Blamey  
P. Niebaum  
N. Staples  
D. Mas  
M. Schwieg  
   
DATE  
10/31/2018  
11/9/2018  
10/31/2018  
10/31/2018  
11/1/2018  
10/31/2018  


                          U.S. NUCLEAR REGULATORY COMMISSION
Enclosure
                                        Inspection Report
U.S. NUCLEAR REGULATORY COMMISSION  
Docket Number(s):     50-348, 50-364
Inspection Report  
License Number(s):     NPF-2, NPF-8
Report Number(s):     05000348/2018003; and 05000364/2018003
Enterprise Identifier: I-2018-003-0038
Docket Number(s):
Licensee:             Southern Nuclear Operating Company, Inc.
50-348, 50-364  
Facility:             Joseph M. Farley Nuclear Plant
Location:             Columbia, Alabama
Inspection Dates:     July 1, 2018 to September 30, 2018
License Number(s):  
Inspectors:           P. Niebaum, Senior Resident Inspector
NPF-2, NPF-8  
                      M. Schwieg, Senior Resident Inspector
                      K. Miller, Resident Inspector
                      D. Mas-Penaranda, Project Engineer
Report Number(s):  
Approved By:           A. Blamey, Chief
05000348/2018003; and 05000364/2018003  
                      Reactor Projects Branch 2
                      Division of Reactor Projects
                                                                Enclosure
Enterprise Identifier: I-2018-003-0038  
Licensee:  
Southern Nuclear Operating Company, Inc.  
Facility:  
Joseph M. Farley Nuclear Plant  
Location:  
Columbia, Alabama  
Inspection Dates:  
July 1, 2018 to September 30, 2018  
Inspectors:  
P. Niebaum, Senior Resident Inspector  
M. Schwieg, Senior Resident Inspector  
K. Miller, Resident Inspector  
D. Mas-Penaranda, Project Engineer  
Approved By:  
A. Blamey, Chief
Reactor Projects Branch 2
Division of Reactor Projects  


                                              SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance
2
by conducting baseline inspections at Joseph M. Farley, Units 1 and 2 in accordance with the
Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for
SUMMARY  
overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance  
revealed findings, violations, and additional items are summarized in the table below
by conducting baseline inspections at Joseph M. Farley, Units 1 and 2 in accordance with the  
                                  List of Findings and Violations
Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for  
  Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band
overseeing the safe operation of commercial nuclear power reactors. Refer to  
  Cornerstone Severity                                   Crosscutting       Report Section
https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-
        Not         Severity Level (SL) IV               Not Applicable     71153 - Follow-up of
revealed findings, violations, and additional items are summarized in the table below  
  Applicable      NCV 05000348/2018003-01                                  Events and Notices of
                    Closed                                                  Enforcement Discretion
List of Findings and Violations  
A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a
   
routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than
Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band  
allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action
Cornerstone  
completion time.
Severity  
                                    Additional Tracking Items
Crosscutting  
  Type       Issue number               Title                           Report Section       Status
Report Section  
LER         05000348/2018-001-00       Pressurizer Safety Valve Lift   71153 - Follow-up   Closed
Not  
                                        Pressure Outside of            of Events and
Applicable
                                        Technical Specification Limits  Notices of
Severity Level (SL) IV
                                        due to Spring Relaxation        Enforcement
NCV 05000348/2018003-01
                                                                        Discretion
Closed
                                                  2
Not Applicable  
71153 - Follow-up of  
Events and Notices of  
Enforcement Discretion  
A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a  
routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than  
allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action  
completion time.  
Additional Tracking Items  
   
Type  
Issue number  
Title  
Report Section  
Status  
LER  
05000348/2018-001-00
Pressurizer Safety Valve Lift  
Pressure Outside of
Technical Specification Limits
due to Spring Relaxation
71153 - Follow-up  
of Events and  
Notices of  
Enforcement  
Discretion  
Closed


PLANT STATUS
Unit 1 began the report period at or near 100 percent rated thermal power (RTP). On
3
September 8, Unit 1 was reduced to approximately 16 percent RTP to support a containment
entry for an oil addition to the 1C reactor coolant pump motor upper bearing oil reservoir.
PLANT STATUS  
Following this work, Unit 1 achieved 100 percent RTP on September 9. Unit 1 stayed at or near
100 percent RTP until September 24, when the reactor was shut down to support a planned
Unit 1 began the report period at or near 100 percent rated thermal power (RTP). On  
maintenance outage to rework a main steam isolation valve (MSIV) actuator. The reactor was
September 8, Unit 1 was reduced to approximately 16 percent RTP to support a containment  
started on September 28 and RTP was increased to approximately 72 percent by the end of the
entry for an oil addition to the 1C reactor coolant pump motor upper bearing oil reservoir.
report period.
Following this work, Unit 1 achieved 100 percent RTP on September 9. Unit 1 stayed at or near  
Unit 2 began the report period at approximately 100 percent RTP and maintained that power
100 percent RTP until September 24, when the reactor was shut down to support a planned  
level for the entire report period.
maintenance outage to rework a main steam isolation valve (MSIV) actuator. The reactor was  
INSPECTION SCOPES
started on September 28 and RTP was increased to approximately 72 percent by the end of the  
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
report period.  
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
Unit 2 began the report period at approximately 100 percent RTP and maintained that power  
level for the entire 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-
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
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
complete when the IP requirements most appropriate to the inspection activity were met  
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection  
Program - Operations Phase. The inspectors reviewed selected procedures and records,
Program - Operations Phase. The inspectors reviewed selected procedures and records,  
observed activities, and interviewed personnel to assess licensee performance and compliance
observed activities, and interviewed personnel to assess licensee performance and compliance  
with Commission rules and regulations, license conditions, site procedures, and standards.
with Commission rules and regulations, license conditions, site procedures, and standards.  
REACTOR SAFETY
71111.01 - Adverse Weather Protection
REACTOR SAFETY  
    External Flooding (1 Sample)
    The inspectors verified that flood protection barriers, mitigation plans, procedures, and
71111.01 - Adverse Weather Protection  
    equipment were consistent with the licensees design requirements and risk analysis
    assumptions for coping with external flooding for the Service Water Intake Structure.
External Flooding (1 Sample)  
71111.04 - Equipment Alignment
    Partial Walkdown (3 Samples)
The inspectors verified that flood protection barriers, mitigation plans, procedures, and  
    The inspectors evaluated system configurations during partial walkdowns of the following
equipment were consistent with the licensees design requirements and risk analysis  
    systems/trains:
assumptions for coping with external flooding for the Service Water Intake Structure.  
    (1)     Unit 2 containment spray system, A train, on August 13, 2018.
    (2)     Unit 2 A motor driven auxiliary feedwater pump, on August 14, 2018.
71111.04 - Equipment Alignment  
    (3)     Unit 2 residual heat removal system, A train, on August 28, 2018.
                                                  3
Partial Walkdown (3 Samples)  
The inspectors evaluated system configurations during partial walkdowns of the following  
systems/trains:  
(1)  
Unit 2 containment spray system, A train, on August 13, 2018.  
(2)  
Unit 2 A motor driven auxiliary feedwater pump, on August 14, 2018.  
(3)  
Unit 2 residual heat removal system, A train, on August 28, 2018.  


  Complete Walkdown (1 Sample)
  The inspectors evaluated system configurations during a complete walkdown of the Unit 2
4
  auxiliary feedwater system on August 30, 2018.
71111.05AQ - Fire Protection Annual/Quarterly
Complete Walkdown (1 Sample)  
  Quarterly Inspection (5 Samples)
  The inspectors evaluated fire protection program implementation in the following selected
The inspectors evaluated system configurations during a complete walkdown of the Unit 2  
  areas on August 8, 2018:
auxiliary feedwater system on August 30, 2018.  
  (1) Fire Area 072, Service Water Pump Room.
  (2) Fire Area 073, Service Water Intake Structure Battery Room Train B.
  (3) Fire Area 074, Service Water Intake Structure Battery Room Train A.
71111.05AQ - Fire Protection Annual/Quarterly  
  (4) Fire Area 075, Service Water Intake Structure 5kV Switchgear Room B & West Stairs.
  (5) Fire Area 076, Service Water Intake Structure 5kV Switchgear Room A & East Stairs.
Quarterly Inspection (5 Samples)  
  Annual Inspection (1 Sample)
  The inspectors evaluated fire brigade performance on August 16, 2018.
The inspectors evaluated fire protection program implementation in the following selected  
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
areas on August 8, 2018:  
  Operator Requalification (1 Sample)
(1) Fire Area 072, Service Water Pump Room.  
  The inspectors observed and evaluated a crew of licensed operators in the plants simulator
(2) Fire Area 073, Service Water Intake Structure Battery Room Train B.  
  during the licensed operator annual simulator exam on August 1, 2018.
(3) Fire Area 074, Service Water Intake Structure Battery Room Train A.  
  Operator Performance (1 Sample)
(4) Fire Area 075, Service Water Intake Structure 5kV Switchgear Room B & West Stairs.  
  The inspectors observed and evaluated the power ascension of Unit 1 following an oil addition
(5) Fire Area 076, Service Water Intake Structure 5kV Switchgear Room A & East Stairs.  
  to the 1C reactor coolant pump on September 8, 2018.
Annual Inspection (1 Sample)  
71111.12 - Maintenance Effectiveness
  Routine Maintenance Effectiveness (2 Samples)
The inspectors evaluated fire brigade performance on August 16, 2018.  
  The inspectors evaluated the effectiveness of routine maintenance activities associated
  with the following equipment and/or safety significant functions:
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance  
  (1) The maintenance rule program periodic (a)(3) evaluation on Aug. 29, 2018.
  (2) Unit 1 and 2 shared 1-2A diesel generator degraded mode selector switch on Sept. 6,
Operator Requalification (1 Sample)  
        2018.
71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)
The inspectors observed and evaluated a crew of licensed operators in the plants simulator  
  The inspectors evaluated the risk assessments for the following planned and emergent
during the licensed operator annual simulator exam on August 1, 2018.  
  work activities:
                                                4
Operator Performance (1 Sample)  
The inspectors observed and evaluated the power ascension of Unit 1 following an oil addition  
to the 1C reactor coolant pump on September 8, 2018.  
71111.12 - Maintenance Effectiveness  
Routine Maintenance Effectiveness (2 Samples)  
The inspectors evaluated the effectiveness of routine maintenance activities associated  
with the following equipment and/or safety significant functions:  
(1) The maintenance rule program periodic (a)(3) evaluation on Aug. 29, 2018.  
(2) Unit 1 and 2 shared 1-2A diesel generator degraded mode selector switch on Sept. 6,  
2018.  
71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)  
The inspectors evaluated the risk assessments for the following planned and emergent  
work activities:


  (1) Unit 2 elevated risk due to 2B emergency diesel generator corrective maintenance on
      August 10, 2018.
5
  (2) Unit 2 elevated risk due to 2B containment spray pump preventive maintenance on
      August 13, 2018.
(1) Unit 2 elevated risk due to 2B emergency diesel generator corrective maintenance on  
  (3) Units 1 and 2 elevated risk due to modification work in the high voltage switchyard on
August 10, 2018.  
      September 5, 2018.
(2) Unit 2 elevated risk due to 2B containment spray pump preventive maintenance on  
  (4) Unit 1 MSIV A emergent work on September 26, 2018.
August 13, 2018.  
71111.15 - Operability Determinations and Functionality Assessments (5 Samples)
(3) Units 1 and 2 elevated risk due to modification work in the high voltage switchyard on  
  The inspectors evaluated the following operability determinations and functionality
September 5, 2018.  
  assessments:
(4) Unit 1 MSIV A emergent work on September 26, 2018.  
  (1) The 2B residual heat removal (RHR) pump radial bearing reservoir leaked oil during
      performance of the FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test on July
71111.15 - Operability Determinations and Functionality Assessments (5 Samples)  
      16, 2018.
  (2) Unit 2 pressurizer pressure transmitter PT-457 drifted high on July 1, 2018.
The inspectors evaluated the following operability determinations and functionality  
  (3) Mounting bolt broken during replacement of mechanism operated cell switch on circuit
assessments:  
      breaker Q2R15BKRDH07 on July 24, 2018.
  (4) Unit 1, reactor coolant pump under voltage relay test review on July 28, 2018.
(1) The 2B residual heat removal (RHR) pump radial bearing reservoir leaked oil during  
  (5) Unit 1, impacts of potential oil leak on 1C reactor coolant pump motor upper bearing oil
performance of the FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test on July  
      reservoir on July 6, 2018.
16, 2018.  
71111.19 - Post Maintenance Testing (4 Samples)
(2) Unit 2 pressurizer pressure transmitter PT-457 drifted high on July 1, 2018.  
  The inspectors evaluated the following post maintenance tests:
(3) Mounting bolt broken during replacement of mechanism operated cell switch on circuit  
  (1) FNP-0-STP-80.2, Diesel Generator 1C Operability Test, after replacement of MOC
breaker Q2R15BKRDH07 on July 24, 2018.  
      switch on circuit breaker Q2R15BKRDH07 on July 24, 2018.
(4) Unit 1, reactor coolant pump under voltage relay test review on July 28, 2018.  
  (2) FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, after
(5) Unit 1, impacts of potential oil leak on 1C reactor coolant pump motor upper bearing oil  
      replacement of an automatic voltage regulator control card on August 22, 2018.
reservoir on July 6, 2018.  
  (3) FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and
      Operational Test, after replacement of pressurizer pressure transmitter on September
71111.19 - Post Maintenance Testing (4 Samples)  
      11, 2018.
  (4) FNP-1-STP-21.2, MSIV Air System Leak Test, after replacement of air actuator on
The inspectors evaluated the following post maintenance tests:  
      September 26, 2018.
71111.20 - Refueling and Other Outage Activities (1 Sample)
(1) FNP-0-STP-80.2, Diesel Generator 1C Operability Test, after replacement of MOC  
  The inspectors evaluated Unit 1 forced outage activities from September 24, 2018 to
switch on circuit breaker Q2R15BKRDH07 on July 24, 2018.  
  September 28, 2018.
(2) FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, after  
71111.22 - Surveillance Testing
replacement of an automatic voltage regulator control card on August 22, 2018.  
  The inspectors evaluated the following surveillance tests:
(3) FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and  
  Routine (1 Sample)
Operational Test, after replacement of pressurizer pressure transmitter on September  
  (1) Unit 1, FNP-1-STP-109.1, Power Range Neutron Flux Channel Calibration Using The
11, 2018.  
      Plant Computer performed on July 16, 2018.
(4) FNP-1-STP-21.2, MSIV Air System Leak Test, after replacement of air actuator on  
                                                5
September 26, 2018.  
71111.20 - Refueling and Other Outage Activities (1 Sample)  
The inspectors evaluated Unit 1 forced outage activities from September 24, 2018 to  
September 28, 2018.  
71111.22 - Surveillance Testing  
The inspectors evaluated the following surveillance tests:  
Routine (1 Sample)  
(1) Unit 1, FNP-1-STP-109.1, Power Range Neutron Flux Channel Calibration Using The  
Plant Computer performed on July 16, 2018.  


  In-Service Testing (1 Sample)
  (1) Unit 1, FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, on July 24, 2018.
6
  RCS Leakage Detection (1 Sample)
  (1) FNP-1-STP-9.0, RCS Leakage Test, on October 24, 2018.
In-Service Testing (1 Sample)  
71114.06 - Drill Evaluation
  Emergency Planning Drill (1 Sample)
(1) Unit 1, FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, on July 24, 2018.  
  The inspectors evaluated an emergency preparedness drill that involved the failure of the
  reactor to trip which led to an Alert Emergency, the loss of two fission product barriers
RCS Leakage Detection (1 Sample)  
  which lead to a Site Area Emergency and the subsequent loss of the third barrier which
  led to a General Emergency on August 14, 2018.
(1) FNP-1-STP-9.0, RCS Leakage Test, on October 24, 2018.  
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
71114.06 - Drill Evaluation  
  The inspectors verified licensee performance indicators submittals listed below for the
  period from July 2017, through June 2018. (6 Samples)
Emergency Planning Drill (1 Sample)  
  (1) Safety System Functional Failure (SSFF), Units 1 and 2.
  (2) RCS specific activity, Units 1 and 2.
The inspectors evaluated an emergency preparedness drill that involved the failure of the  
  (3) RCS leakage, Units 1 and 2.
reactor to trip which led to an Alert Emergency, the loss of two fission product barriers  
71152 - Problem Identification and Resolution
which lead to a Site Area Emergency and the subsequent loss of the third barrier which  
  Semiannual Trend Review (1 Sample)
led to a General Emergency on August 14, 2018.  
  The inspectors reviewed the licensees corrective action program for trends that might be
  indicative of a more significant safety issue.
OTHER ACTIVITIES - BASELINE  
  (1) Condition Report 10529513, Trend in Missed Fire Watches.
  Annual Follow-up of Selected Issues (1 Sample)
71151 - Performance Indicator Verification  
  The inspectors reviewed the licensees implementation of its corrective action program
  related to the following issues:
The inspectors verified licensee performance indicators submittals listed below for the  
  (1) Condition Report 10527200, Failure of Emergency Diesel Generator 1-2A to Run on
period from July 2017, through June 2018. (6 Samples)  
      August 20, 2018.
                                                  6
(1) Safety System Functional Failure (SSFF), Units 1 and 2.  
(2) RCS specific activity, Units 1 and 2.  
(3) RCS leakage, Units 1 and 2.  
71152 - Problem Identification and Resolution  
Semiannual Trend Review (1 Sample)  
The inspectors reviewed the licensees corrective action program for trends that might be  
indicative of a more significant safety issue.  
(1) Condition Report 10529513, Trend in Missed Fire Watches.
Annual Follow-up of Selected Issues (1 Sample)  
The inspectors reviewed the licensees implementation of its corrective action program  
related to the following issues:  
(1) Condition Report 10527200, Failure of Emergency Diesel Generator 1-2A to Run on  
August 20, 2018.  


71153 - Follow-up of Events and Notices of Enforcement Discretion
    Licensee Event Reports (1 Sample)
7
    The inspectors evaluated the following licensee event reports which can be accessed at
    https://lersearch.inl.gov/LERSearchCriteria.aspx:
71153 - Follow-up of Events and Notices of Enforcement Discretion  
    (1) Licensee Event Report (LER) 05000348/2018-001-00, Pressurizer Safety Valve Lift
        Pressure Outside of Technical Specification Limits due to Spring Relaxation
Licensee Event Reports (1 Sample)  
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation
The inspectors evaluated the following licensee event reports which can be accessed at  
    The inspectors evaluated the licensees independent spent fuel storage installation cask
https://lersearch.inl.gov/LERSearchCriteria.aspx:  
    loadings on September 20, 2018.
INSPECTION RESULTS
(1) Licensee Event Report (LER) 05000348/2018-001-00, Pressurizer Safety Valve Lift  
  Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band
Pressure Outside of Technical Specification Limits due to Spring Relaxation
  Cornerstone Severity                                   Crosscutting       Report Section
      Not           SL IV                                 Not Applicable     71153 - Follow-up of
    Applicable      NCV 05000348/2018003-01                                  Events and Notices of
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL  
                    Closed                                                  Enforcement Discretion
A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a
60855.1 - Operation of an Independent Spent Fuel Storage Installation  
routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than
allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action
The inspectors evaluated the licensees independent spent fuel storage installation cask  
completion time.
loadings on September 20, 2018.  
Description: On April 12, 2018, pressurizer safety valve Q1B13V0031C was removed from
service at Farley Nuclear Plant Unit 1, and on April 16, 2018, the valve was tested with steam at
INSPECTION RESULTS  
an offsite facility. As-found lift testing determined that the valve opened at 2420 psig steam
   
pressure, which was low outside the plant technical specification allowable lift setting range of
Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band  
2460 psig to 2510 psig. The valve had been installed and placed in service at Farley Nuclear
Cornerstone  
Plant Unit 1 on October 8, 2013, and remained in service during three complete 18-month fuel
Severity  
cycles. Upon removal of valve Q1B13V0031C from Unit 1 on April 12, 2018, it was replaced with
Crosscutting  
a similar operable refurbished valve. Licensee Event Report (LER) 05000348/2018-001-00,
Report Section  
Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Limits due to Spring
Not  
Relaxation, was submitted by the licensee for this event.
Applicable
  Corrective Action(s): The valve was replaced with a similar operable refurbished valve during the
SL IV
refueling outage prior to plant startup.
NCV 05000348/2018003-01
  Corrective Action Reference(s): The licensee entered this issue into their corrective actions
Closed
program as CR10483091 - PZR safety valve test results.
Not Applicable  
  Performance Assessment
71153 - Follow-up of  
The inspectors determined the condition was not reasonably foreseeable and preventable by the
Events and Notices of  
licensee and therefore was not a performance deficiency. Specifically, random setpoint drift is a
Enforcement Discretion  
recognized valid phenomenon that can occur despite routine testing and maintenance.
A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a  
                                                    7
routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than  
allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action  
completion time.  
Description: On April 12, 2018, pressurizer safety valve Q1B13V0031C was removed from  
service at Farley Nuclear Plant Unit 1, and on April 16, 2018, the valve was tested with steam at  
an offsite facility. As-found lift testing determined that the valve opened at 2420 psig steam  
pressure, which was low outside the plant technical specification allowable lift setting range of  
2460 psig to 2510 psig. The valve had been installed and placed in service at Farley Nuclear  
Plant Unit 1 on October 8, 2013, and remained in service during three complete 18-month fuel  
cycles. Upon removal of valve Q1B13V0031C from Unit 1 on April 12, 2018, it was replaced with  
a similar operable refurbished valve. Licensee Event Report (LER) 05000348/2018-001-00,  
Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Limits due to Spring  
Relaxation, was submitted by the licensee for this event.  
   
Corrective Action(s): The valve was replaced with a similar operable refurbished valve during the  
refueling outage prior to plant startup.  
   
Corrective Action Reference(s): The licensee entered this issue into their corrective actions  
program as CR10483091 - PZR safety valve test results.  
   
Performance Assessment  
The inspectors determined the condition was not reasonably foreseeable and preventable by the  
licensee and therefore was not a performance deficiency. Specifically, random setpoint drift is a  
recognized valid phenomenon that can occur despite routine testing and maintenance.  


Enforcement:
8
Severity: Traditional Enforcement is being used to disposition this violation with no associated
Reactor Oversight Process performance deficiency per NRC Memorandum Interim Guidance for
Dispositioning Severity Level IV Violations with No Associated Performance Deficiency
Enforcement:  
(ML18158A220). The inspector assessed the severity of the violation using Section 6.1 of the
Severity: Traditional Enforcement is being used to disposition this violation with no associated  
Enforcement Policy and determined the significance is appropriately characterized as Severity
Reactor Oversight Process performance deficiency per NRC Memorandum Interim Guidance for  
Level IV, due to the inappreciable potential safety consequences. The licensee determined that
Dispositioning Severity Level IV Violations with No Associated Performance Deficiency  
the safety valve low as-found lift set-point did not have an adverse impact on reactor coolant
(ML18158A220). The inspector assessed the severity of the violation using Section 6.1 of the  
system over-pressurization protection, since the valve continued to perform its reactor coolant
Enforcement Policy and determined the significance is appropriately characterized as Severity  
system over-pressure protection function to prevent the system from exceeding the design
Level IV, due to the inappreciable potential safety consequences. The licensee determined that  
pressure of 2485 psig. Therefore, the plant remained bounded by the accident analysis in the
the safety valve low as-found lift set-point did not have an adverse impact on reactor coolant  
FSAR, based on the as-found condition.
system over-pressurization protection, since the valve continued to perform its reactor coolant  
Violation: Farley Nuclear Plant Unit 1 TS LCO 3.4.10, Pressurizer Safety Valves, required three
system over-pressure protection function to prevent the system from exceeding the design  
operable pressurizer safety valves with lift settings between 2460 psig and 2510 psig, while the
pressure of 2485 psig. Therefore, the plant remained bounded by the accident analysis in the  
Unit was in modes 1, 2, and 3. With one pressurizer safety valve inoperable, Action Statement,
FSAR, based on the as-found condition.  
Condition A. Required Action A.1, required restoration of the valve to operable status within 15
minutes. If the required action and associated completion time is not met, Action Statement,
Violation: Farley Nuclear Plant Unit 1 TS LCO 3.4.10, Pressurizer Safety Valves, required three  
Condition B, required that the unit be in mode 3 within 6 hours. Contrary to the above, the
operable pressurizer safety valves with lift settings between 2460 psig and 2510 psig, while the  
licensee determined the pressurizer safety valve setting was outside the TS limits longer than 6
Unit was in modes 1, 2, and 3. With one pressurizer safety valve inoperable, Action Statement,  
hours and 15 minutes during the last three operating cycle, between October 8, 2013 and April 12,
Condition A. Required Action A.1, required restoration of the valve to operable status within 15  
2018, while the Unit was in modes 1, 2, and 3.
minutes. If the required action and associated completion time is not met, Action Statement,  
Disposition: This violation is being treated as an NCV, consistent with Section 2.3.2 of the
Condition B, required that the unit be in mode 3 within 6 hours. Contrary to the above, the  
Enforcement Policy.
licensee determined the pressurizer safety valve setting was outside the TS limits longer than 6  
Licensee Identified Non-Cited Violation                         71152
hours and 15 minutes during the last three operating cycle, between October 8, 2013 and April 12,  
This violation of very low safety significance was identified by the licensee and has been
2018, while the Unit was in modes 1, 2, and 3.
entered into the licensee corrective action program and is being treated as a Non-Cited
Violation, consistent with Section 2.3.2 of the Enforcement Policy.
Disposition: This violation is being treated as an NCV, consistent with Section 2.3.2 of the  
Violation: Farley Unit 1 Operating License Condition 2.C.(4) and Unit 2 Operating License
Enforcement Policy.  
Condition 2.C.(6), Fire Protection, required in part that Plant Farley shall implement and
maintain in effect all provisions of the approved fire protection program that comply with 10
Licensee Identified Non-Cited Violation
CFR 50.48(c) and NFPA 805. NFPA 805 section 3.2.3 stated, in part, procedures to
71152
accomplish compensatory actions implemented when fire protection systems and other
This violation of very low safety significance was identified by the licensee and has been  
systems credited by the fire protection program and this standard cannot perform their
entered into the licensee corrective action program and is being treated as a Non-Cited  
intended function shall be established. Licensee procedure FNP-0-SOP-0.4, Fire Protection
Violation, consistent with Section2.3.2 of the Enforcement Policy.  
Operability and LCO Requirements section 4.0 establishes compensatory action when fire
Violation: Farley Unit 1 Operating License Condition 2.C.(4) and Unit 2 Operating License  
protection systems and other systems credited by the fire protection program cannot perform
Condition 2.C.(6), Fire Protection, required in part that Plant Farley shall implement and  
their intended functions.
maintain in effect all provisions of the approved fire protection program that comply with 10  
Contrary to the above, since January 16, 2018 through August 28, 2018, the licensee failed to
CFR 50.48(c) and NFPA 805. NFPA 805 section 3.2.3 stated, in part, procedures to  
accomplish compensatory actions implemented when fire protection systems and other  
systems credited by the fire protection program and this standard cannot perform their  
intended function shall be established. Licensee procedure FNP-0-SOP-0.4, Fire Protection  
Operability and LCO Requirements section 4.0 establishes compensatory action when fire  
protection systems and other systems credited by the fire protection program cannot perform  
their intended functions.
 
Contrary to the above, since January 16, 2018 through August 28, 2018, the licensee failed to  
establish compensatory measures (fire watches) as required by licensee procedure FNP-0-
establish compensatory measures (fire watches) as required by licensee procedure FNP-0-
SOP-0.4 on thirteen occasions. The cause of the fire watch discrepancies were mainly
SOP-0.4 on thirteen occasions. The cause of the fire watch discrepancies were mainly  
because Farley Operations staff lacked an adequate understanding and ownership of the fire
because Farley Operations staff lacked an adequate understanding and ownership of the fire  
watch implementation process.
watch implementation process.  
                                                  8
 


  Significance/Severity Level: The inspectors evaluated this finding in accordance with NRCs
  inspection manual chapter (IMC) 0609 App F, Fire Protection Significance Determination
9
  Process, issued May 2, 2018. The finding screened to Green (very low safety significance)
  because the inspectors determined that the missed fire watches would not adversely impact
Significance/Severity Level: The inspectors evaluated this finding in accordance with NRCs  
  equipment important to safe shutdown of the unit in the respective fire areas.
inspection manual chapter (IMC) 0609 App F, Fire Protection Significance Determination  
   Corrective Action Reference(s): Condition report (CR) 10529513 is the trend CR that
Process, issued May 2, 2018. The finding screened to Green (very low safety significance)  
  documented several missed fire watches. Corrective actions are planned and currently in
because the inspectors determined that the missed fire watches would not adversely impact  
  progress to address this issue.
equipment important to safe shutdown of the unit in the respective fire areas.  
EXIT MEETINGS AND DEBRIEFS
    
The inspectors verified no proprietary information was retained or documented in this report.
Corrective Action Reference(s): Condition report (CR) 10529513 is the trend CR that  
The inspectors confirmed that proprietary information was controlled to protect from public
documented several missed fire watches. Corrective actions are planned and currently in  
disclosure.
progress to address this issue.  
*   On October 16, 2018, the inspectors presented the quarterly baseline inspection results,
    respectively to Dennis Madison, Site Vice President, and Scott Briggs, Plant Manager, and
EXIT MEETINGS AND DEBRIEFS  
    other members of the licensee staff.
DOCUMENTS REVIEWED
The inspectors verified no proprietary information was retained or documented in this report.  
71111.01: Adverse Weather Protection
Procedures:
The inspectors confirmed that proprietary information was controlled to protect from public  
FNP-0-AOP-21, Severe Weather, Rev. 46.1
disclosure.  
NMP-OS-017, Severe Weather, Ver. 1.1
NMP-AD-014, Requirements for Compliance with NERC Standards, Ver. 6.1
*  
NMP-AD-014-GL01, Guidelines for Compliance with NERC Standards, Ver. 6.0
On October 16, 2018, the inspectors presented the quarterly baseline inspection results,  
Documents:
respectively to Dennis Madison, Site Vice President, and Scott Briggs, Plant Manager, and  
Regulatory Guide 1.27, Ultimate Heat Sink
other members of the licensee staff.  
D-171417, Pond Fill Discharge Structure, Rev. 3
D-170178, Piping- River Water Pumps Discharge To Storage Pond, Rev. 19
DOCUMENTS REVIEWED  
D-176981, Storage Dam and Dike - General Plan, Rev. 8
D-171419, River Water discharge to pond structure, Rev. 0
71111.01: Adverse Weather Protection  
71111.04: Equipment Alignment
Procedures:  
Procedures:
FNP-0-AOP-21, Severe Weather, Rev. 46.1  
FNP-2-SOP-9.0, Containment Spray System, Ver. 38.1
NMP-OS-017, Severe Weather, Ver. 1.1  
FNP-2-SOP-9.0A, Containment Spray System, Ver. 8
NMP-AD-014, Requirements for Compliance with NERC Standards, Ver. 6.1  
FNP-2-SOP-7.0, Residual Heat Removal System, Ver. 99.0
NMP-AD-014-GL01, Guidelines for Compliance with NERC Standards, Ver. 6.0  
FNP-2-SOP-7.0A, Residual Heat Removal System, Ver. 11.0
FNP-2-SOP-22.0, Auxiliary Feedwater System, Ver. 77.2
Documents:  
FNP-2-SOP-22.0A, Auxiliary Feedwater System, Ver. 14.0
Regulatory Guide 1.27, Ultimate Heat Sink  
Drawings:
D-171417, Pond Fill Discharge Structure, Rev. 3  
D-205007, Unit 2 P&ID - Auxiliary Feedwater System, Sheet 1, Ver. 29.0
D-170178, Piping- River Water Pumps Discharge To Storage Pond, Rev. 19  
D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 1,
D-176981, Storage Dam and Dike - General Plan, Rev. 8
   Ver. 39.0
D-171419, River Water discharge to pond structure, Rev. 0  
                                                9
71111.04: Equipment Alignment  
Procedures:  
FNP-2-SOP-9.0, Containment Spray System, Ver. 38.1  
FNP-2-SOP-9.0A, Containment Spray System, Ver. 8  
FNP-2-SOP-7.0, Residual Heat Removal System, Ver. 99.0  
FNP-2-SOP-7.0A, Residual Heat Removal System, Ver. 11.0  
FNP-2-SOP-22.0, Auxiliary Feedwater System, Ver. 77.2  
FNP-2-SOP-22.0A, Auxiliary Feedwater System, Ver. 14.0  
Drawings:  
D-205007, Unit 2 P&ID - Auxiliary Feedwater System, Sheet 1, Ver. 29.0  
D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 1,  
   Ver. 39.0  


D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 2,
10
Ver. 25.0
D-205038, Unit 2 P&ID - Safety Injection System, Sheet 1, Ver. 39
D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 2,  
D-205038, Unit 2 P&ID - Safety Injection System, Sheet 2, Ver. 24
  Ver. 25.0  
D-205038, Unit 2 P&ID - Safety Injection System (Containment Spray), Sheet 3,
D-205038, Unit 2 P&ID - Safety Injection System, Sheet 1, Ver. 39  
Ver. 34
D-205038, Unit 2 P&ID - Safety Injection System, Sheet 2, Ver. 24  
D-205041, Unit 2 P&ID - Residual Heat Removal System, Sheet 1, Ver. 20
D-205038, Unit 2 P&ID - Safety Injection System (Containment Spray), Sheet 3,
Condition Reports:
  Ver. 34  
10530528     10530671
D-205041, Unit 2 P&ID - Residual Heat Removal System, Sheet 1, Ver. 20  
71111.05: Fire Protection Annual/Quarterly
Procedures:
Condition Reports:  
FNP-0-FPP-3.0, Owner Controlled Area Pre-Fire Plan, Ver. 2.0
10530528  
FNP-2-FPP-1.0, Unit 2 Auxiliary Building Pre-Fire Plan, Ver. 1.0
10530671  
NMP-TR-425-F14, Fire Drill Package, Ver. 1.0
Condition Reports:
71111.05: Fire Protection Annual/Quarterly  
10508072     10508079       10516723       10517136       10523359  10523468
Procedures:  
10523467
FNP-0-FPP-3.0, Owner Controlled Area Pre-Fire Plan, Ver. 2.0  
Work Orders:
FNP-2-FPP-1.0, Unit 2 Auxiliary Building Pre-Fire Plan, Ver. 1.0  
SNC913159 SNC719746           SNC885164       SNC641901       SNC881904 SNC644350
NMP-TR-425-F14, Fire Drill Package, Ver. 1.0  
SNC538103 SNC776088           SNC737915       SNC952320       SNC952321
Drawings:
Condition Reports:  
D513635, Unit No. 1/2 - Fire Barriers and Fire Boundaries - Service Water Intake Structure
10508072  
  (SWIS), Ver. 1.0
10508079  
Documents:
10516723  
A-181805, NFPA 805 Fire Protection Program Design Basis Document, Ver. 5.0
10517136  
71111.11: Licensed Operator Requalification Program
10523359  
Procedures:
10523468
FNP-1-UOP-3.1, Power Operation, Ver. 131.0
   
Documents:
10523467  
Operations Training Simulator Exam Scenario #31, Approved on July 26, 2018
71111.12: Maintenance Effectiveness
Work Orders:  
Procedures:
SNC913159  
NMP-ES-027, Maintenance Rule Program, Ver. 8
SNC719746  
Documents:
SNC885164  
EVAL-F-Y41-04230, MR evaluation for 1-2A diesel generator MR function Y41-F05
SNC641901  
Maintenance Rule Expert Panel (MREP) Meeting 18-16 Agenda, August 29, 2018.
SNC881904  
Technical Evaluation (TE) 1016165
SNC644350  
MREP meeting minutes from Meeting 18-16 on August 29, 2018.
SNC538103  
                                                10
SNC776088  
SNC737915  
SNC952320  
SNC952321  
Drawings:  
D513635, Unit No. 1/2 - Fire Barriers and Fire Boundaries - Service Water Intake Structure  
(SWIS), Ver. 1.0  
Documents:  
A-181805, NFPA 805 Fire Protection Program Design Basis Document, Ver. 5.0  
71111.11: Licensed Operator Requalification Program  
Procedures:  
FNP-1-UOP-3.1, Power Operation, Ver. 131.0  
Documents:  
Operations Training Simulator Exam Scenario #31, Approved on July 26, 2018  
71111.12: Maintenance Effectiveness  
Procedures:  
NMP-ES-027, Maintenance Rule Program, Ver. 8  
Documents:  
EVAL-F-Y41-04230, MR evaluation for 1-2A diesel generator MR function Y41-F05  
Maintenance Rule Expert Panel (MREP) Meeting 18-16 Agenda, August 29, 2018.  
Technical Evaluation (TE) 1016165  
MREP meeting minutes from Meeting 18-16 on August 29, 2018.  


Condition Reports:
11
10500679
71111.13: Maintenance Risk Assessments and Emergent Work Evaluation
Condition Reports:  
Procedures:
10500679
NMP-OS-010-001, Farley Protected Equipment Logs, Ver. 15
NMP-GM-031-001, Online Maintenance Rule (a)(4) Risk Calculations, Ver. 5
71111.13: Maintenance Risk Assessments and Emergent Work Evaluation  
Condition Reports:
Procedures:  
10532482
NMP-OS-010-001, Farley Protected Equipment Logs, Ver. 15  
Documents:
NMP-GM-031-001, Online Maintenance Rule (a)(4) Risk Calculations, Ver. 5  
Unit 2 EOOS Operators Risk Report for August 10, 2018
Unit 2 EOOS Operators Risk Report for August 13, 2018
Condition Reports:  
Unit 1 EOOS Operators Risk Report for September 5, 2018
10532482  
Unit 2 EOOS Operators Risk Report for September 5, 2018
71111.15: Operability Determinations and Functionality Assessments
Documents:  
Procedures:
Unit 2 EOOS Operators Risk Report for August 10, 2018  
FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test, Ver. 43.0
Unit 2 EOOS Operators Risk Report for August 13, 2018  
FNP-0-GMP-30.1, Tribology Program, Ver. 25.0
Unit 1 EOOS Operators Risk Report for September 5, 2018  
FNP-0-GMP-37.0, Residual Heat Removal Pump Lubrication Procedure, Ver. 4.0
Unit 2 EOOS Operators Risk Report for September 5, 2018  
FNP-0-M-50, Master List of Surveillance Requirements, Ver. 30
Documents:
71111.15: Operability Determinations and Functionality Assessments  
U418156, Instruction Manual RHR Pumps, Ver. 4.0
Procedures:  
Administrative Tracking Item (ATI) 1705, dated May 22, 2018
FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test, Ver. 43.0  
A508632, Pressurizer Pressure Protection Scaling Document, Ver. 5.0
FNP-0-GMP-30.1, Tribology Program, Ver. 25.0  
A-177048, Relay Settings, Sheet 328, Rev. 1
FNP-0-GMP-37.0, Residual Heat Removal Pump Lubrication Procedure, Ver. 4.0  
WCAP-1375-P, Westinghouse Setpoint Methodology for Protection Systems Farley Nuclear
FNP-0-M-50, Master List of Surveillance Requirements, Ver. 30  
Plant Units 1 and 2, Rev. 2
ATI-1705, Administrative Tracking Item for drifting PT-457
Documents:  
ODMI-18-04, 1C RCP motor bearing oil reservoir low level alarm, Ver. 3.0
U418156, Instruction Manual RHR Pumps, Ver. 4.0  
Condition Reports:
Administrative Tracking Item (ATI) 1705, dated May 22, 2018  
10515924       10495878       10489880     10518144       10518931     10518992
A508632, Pressurizer Pressure Protection Scaling Document, Ver. 5.0  
10520001
A-177048, Relay Settings, Sheet 328, Rev. 1  
Work Orders:
WCAP-1375-P, Westinghouse Setpoint Methodology for Protection Systems Farley Nuclear
SNC880406 SNC830329           SNC810896     SNC810891     SNC955428
  Plant Units 1 and 2, Rev. 2  
71111.19: Post Maintenance Testing
ATI-1705, Administrative Tracking Item for drifting PT-457  
Procedures:
ODMI-18-04, 1C RCP motor bearing oil reservoir low level alarm, Ver. 3.0  
FNP-0-EMP-1313.12, Maintenance of Siemens-Allis 4.16 kV Metal-Clad Switchgear MOC
Switch, Ver. 9.3
Condition Reports:  
FNP-0-EMP-1313.19, Inspection and Adjustment of Cutler Hammer 4.16 kV Circuit Breakers
10515924  
Type MA-VR350, Ver. 17.0
10495878  
FNP-0-EMP-1313.20, Enhanced Inspection of Cutler Hammer 4.16 kV Circuit Breakers Type
10489880  
MA-VR350, Ver. 24.1
10518144  
FNP-0-STP-80.2, Diesel Generator 1C Operability Test, Ver. 67.0
10518931  
                                                11
10518992  
10520001
Work Orders:  
SNC880406  
SNC830329  
SNC810896  
SNC810891  
SNC955428  
71111.19: Post Maintenance Testing  
Procedures:  
FNP-0-EMP-1313.12, Maintenance of Siemens-Allis 4.16 kV Metal-Clad Switchgear MOC
  Switch, Ver. 9.3  
FNP-0-EMP-1313.19, Inspection and Adjustment of Cutler Hammer 4.16 kV Circuit Breakers
  Type MA-VR350, Ver. 17.0  
FNP-0-EMP-1313.20, Enhanced Inspection of Cutler Hammer 4.16 kV Circuit Breakers Type
  MA-VR350, Ver. 24.1  
FNP-0-STP-80.2, Diesel Generator 1C Operability Test, Ver. 67.0  


FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, Ver. 23.1
12
FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and Operational Test,
   Ver. 53.0
FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, Ver. 23.1  
FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0
FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and Operational Test,
Condition Reports:
   Ver. 53.0  
10518144       10518931       10527200
FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0  
Work Orders:
SNC830329 SNC964137           SNC955428
Condition Reports:  
71111.20: Refueling and Other Outage Activities
10518144  
Procedures:
10518931  
FNP-1-UOP-2.4 Planned Reactor Shutdown and Cooldown to Cold Shutdown
10527200  
Condition Reports:
10540912       10541123
Work Orders:  
Documents:
SNC830329  
NMP-OS-003-F01, Operational-Making Issue Worksheet, Ver. 6.4
SNC964137  
71111.22: Surveillance Testing
SNC955428  
Procedures:
FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, Ver. 45.0
71111.20: Refueling and Other Outage Activities  
FNP-1-STP-109.0, Power Range Neutron Flux Channel Calibration, Ver. 61
Procedures:  
FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5
FNP-1-UOP-2.4 Planned Reactor Shutdown and Cooldown to Cold Shutdown
Condition Reports:
10515973       10515992       10520944
Condition Reports:  
Work Orders:
10540912  
SNC918430
10541123  
Documents:
Integrated Plant Computer (IPC) printouts of reactor thermal power, reactor coolant loop delta-
Documents:  
   temperature 1 min. average from July 11 through July 18, 2018
NMP-OS-003-F01, Operational-Making Issue Worksheet, Ver. 6.4  
S-2018-014, Ver. 1, Standing order for CR10515992
71114.06: Drill Evaluation
71111.22: Surveillance Testing  
Procedures:
Procedures:  
NMP-EP-141, Event Classification, Ver. 2.0
FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, Ver. 45.0  
NMP-EP-144, Protective Actions, Ver. 3.0
FNP-1-STP-109.0, Power Range Neutron Flux Channel Calibration, Ver. 61  
NMP-EP-141-001-F01, Farley - Hot Initiating Condition Matrix, Ver. 2.0
FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5  
Documents:
Emergency Preparedness Drill Controller Guide, August 14, 2018
Condition Reports:  
Reactor Plant Event Notification Worksheet, Drill message 1, August 14, 2018
10515973  
Reactor Plant Event Notification Worksheet, Drill message 2, August 14, 2018
10515992  
Reactor Plant Event Notification Worksheet, Drill message 3, August 14, 2018
10520944  
Reactor Plant Event Notification Worksheet, Drill message 4, August 14, 2018
                                              12
Work Orders:  
SNC918430  
Documents:  
Integrated Plant Computer (IPC) printouts of reactor thermal power, reactor coolant loop delta-  
   temperature 1 min. average from July 11 through July 18, 2018  
S-2018-014, Ver. 1, Standing order for CR10515992  
71114.06: Drill Evaluation  
Procedures:  
NMP-EP-141, Event Classification, Ver. 2.0  
NMP-EP-144, Protective Actions, Ver. 3.0  
NMP-EP-141-001-F01, Farley - Hot Initiating Condition Matrix, Ver. 2.0  
Documents:  
Emergency Preparedness Drill Controller Guide, August 14, 2018  
Reactor Plant Event Notification Worksheet, Drill message 1, August 14, 2018  
Reactor Plant Event Notification Worksheet, Drill message 2, August 14, 2018  
Reactor Plant Event Notification Worksheet, Drill message 3, August 14, 2018  
Reactor Plant Event Notification Worksheet, Drill message 4, August 14, 2018  


Reactor Plant Event Notification Worksheet, Drill message 5, August 14, 2018
13
Reactor Plant Event Notification Worksheet, Drill message 6, August 14, 2018
71151: Performance Indicator Verification
Reactor Plant Event Notification Worksheet, Drill message 5, August 14, 2018  
Procedures:
Reactor Plant Event Notification Worksheet, Drill message 6, August 14, 2018  
FNP-0-AP-54.0, Preparation and Reporting of NRC Performance Indicator Data and NRC
Operating Data, Ver. 15
71151: Performance Indicator Verification  
FNP-1-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28
Procedures:  
FNP-2-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28
FNP-0-AP-54.0, Preparation and Reporting of NRC Performance Indicator Data and NRC  
FNP-0-CCP-25, Dose Equivalent Iodine-131 Determination, Ver. 15
  Operating Data, Ver. 15  
FNP-1-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27
FNP-1-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28  
FNP-2-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27
FNP-2-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28  
FNP-1-CCP-651.1, Routine Sampling of the Reactor Coolant System, Ver. 18.2
FNP-0-CCP-25, Dose Equivalent Iodine-131 Determination, Ver. 15  
FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5
FNP-1-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27  
FNP-2-STP-9.0, RCS Leakage Test, Ver. 47.5
FNP-2-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27  
FNP-0-SOP-0.13, Recording Limiting Conditions For Operations, Ver. 35
FNP-1-CCP-651.1, Routine Sampling of the Reactor Coolant System, Ver. 18.2  
FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0
FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5  
FNP-1-STP-45.7, MSIV Air System Leak Test, Ver. 24.0
FNP-2-STP-9.0, RCS Leakage Test, Ver. 47.5  
Documents:
FNP-0-SOP-0.13, Recording Limiting Conditions For Operations, Ver. 35  
Main Control Room logs, various dates
FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0  
Chemistry Surveillance logs, various dates
FNP-1-STP-45.7, MSIV Air System Leak Test, Ver. 24.0  
Farley Key Performance Indicators Report, August 2018
Licensee Event Reports (LERs):
Documents:  
05000348/2016007-02
Main Control Room logs, various dates  
05000348/2016008-00
Chemistry Surveillance logs, various dates  
05000348, 364/2016009-00
Farley Key Performance Indicators Report, August 2018  
05000348/2017001-00
05000364/2017001-00
Licensee Event Reports (LERs):  
05000364/2017002-00
05000348/2016007-02  
05000364/2017003-00
05000348/2016008-00  
05000364/2017004-00
05000348, 364/2016009-00  
05000364/2017005-00
05000348/2017001-00  
71152: Problem Identification and Resolution
05000364/2017001-00  
Procedures:
05000364/2017002-00  
NMP-ES-006-GL02, Preventative Maintenance Change Requests, Version 11.0
05000364/2017003-00  
NMP-GM-002-001, Corrective Action Program Instructions, Version 3.0
05000364/2017004-00  
NMP-GM-008, Operating Experience Program, Version 3.0
05000364/2017005-00  
NOS -105, Internal Nuclear Oversight Audits, Version 5.6
NOS-104-001-F07, Engineering Audit Planning Guide, Version 2.0
71152: Problem Identification and Resolution  
NOS-104-001F17, Maintenance Audit Planning Guide, Version 3.0
Procedures:  
PS-004, Vendor Technical Information Program, Version 4.0
NMP-ES-006-GL02, Preventative Maintenance Change Requests, Version 11.0  
Condition Reports:
NMP-GM-002-001, Corrective Action Program Instructions, Version 3.0  
10527200     2007100531 10540109           10540120     10540234       10540246
NMP-GM-008, Operating Experience Program, Version 3.0  
10540350     10529513       10513247     10529663     10529242       10525415
NOS -105, Internal Nuclear Oversight Audits, Version 5.6  
10450707     10463785       10464160     10464292     10464719       10481328
NOS-104-001-F07, Engineering Audit Planning Guide, Version 2.0  
10529963
NOS-104-001F17, Maintenance Audit Planning Guide, Version 3.0  
                                              13
PS-004, Vendor Technical Information Program, Version 4.0  
Condition Reports:  
10527200  
2007100531 10540109  
10540120  
10540234  
10540246  
10540350  
10529513  
10513247  
10529663  
10529242  
10525415  
10450707  
10463785  
10464160  
10464292  
10464719  
10481328  
10529963  


Work Orders:
14
SNC812826
Documents:
Work Orders:  
CR 10527200 Support Refute Matrix, dated 8/30/18
SNC812826  
Fairbanks Morse Owners Group Fax Query 0709-09b, IEN Engineering Additional Follow-up
Information Item concerning SBSR Voltage Regulator Part 21, dated 9/21/07
Documents:  
Nuclear Oversight Audit of Engineering 1/4/17
CR 10527200 Support Refute Matrix, dated 8/30/18  
Nuclear Oversight Audit of Maintenance 11/6/17
Fairbanks Morse Owners Group Fax Query 0709-09b, IEN Engineering Additional Follow-up
PMCR 22107, Extend EDG 1-2A PM Frequency, dated 8/4/10
  Information Item concerning SBSR Voltage Regulator Part 21, dated 9/21/07  
Technical Decision Making Form, dated 8/30/18
Nuclear Oversight Audit of Engineering 1/4/17  
CARs 272781, 274383
Nuclear Oversight Audit of Maintenance 11/6/17  
71153: Event Follow-up
PMCR 22107, Extend EDG 1-2A PM Frequency, dated 8/4/10  
Documents:
Technical Decision Making Form, dated 8/30/18  
Licensee Event Report (LER) 05000364/2018-001-00, Pressurizer Safety Valve Lift Pressure
CARs 272781, 274383  
Outside of Technical Specification Limits during to Spring Relaxation
Condition Reports:
71153: Event Follow-up  
10483091
Documents:  
Work Orders:
Licensee Event Report (LER) 05000364/2018-001-00, Pressurizer Safety Valve Lift Pressure
SNC594727
  Outside of Technical Specification Limits during to Spring Relaxation
60855.1 - Operation of an Independent Spent Fuel Storage Installation
Procedures:
Condition Reports:  
FNP-0-MP-110.0, Dry Fuel Storage Campaign Guidelines, Ver. 19.0
10483091  
FNP-0-MP-111.1, Hi-Storm System Site Transportation, Ver. 19.0
FNP-0-MP-111.11, MPC Helium Dehydration System Operation, Ver. 3.0
Work Orders:  
FNP-0-MP-111.12, Forced Helium Dehydration System Operation, Ver. 10.0
SNC594727  
FNP-0-MP-111.13, Supplemental Cooling System Operation, Ver. 7.0
FNP-0-MP-111.2, Hi-Storm System Preparation and Loading Operation, Ver. 23.0
60855.1 - Operation of an Independent Spent Fuel Storage Installation  
Procedures:  
FNP-0-MP-110.0, Dry Fuel Storage Campaign Guidelines, Ver. 19.0  
FNP-0-MP-111.1, Hi-Storm System Site Transportation, Ver. 19.0  
FNP-0-MP-111.11, MPC Helium Dehydration System Operation, Ver. 3.0  
FNP-0-MP-111.12, Forced Helium Dehydration System Operation, Ver. 10.0  
FNP-0-MP-111.13, Supplemental Cooling System Operation, Ver. 7.0  
FNP-0-MP-111.2, Hi-Storm System Preparation and Loading Operation, Ver. 23.0  
FNP-0-MP-111.3, MPC Fuel Loading Operations, Ver. 29.0
FNP-0-MP-111.3, MPC Fuel Loading Operations, Ver. 29.0
                                              14
}}
}}

Latest revision as of 09:34, 5 January 2025

NRC Integrated Inspection Report 05000348/2018003 and 05000364/2018003
ML18318A053
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 11/09/2018
From: Alan Blamey
NRC/RGN-II/DRP/RPB2
To: Madison D
Southern Nuclear Operating Co
References
IR 2018003
Download: ML18318A053 (14)
v • d • e


See also: IR 05000348/2018003

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

November 9, 2018

Dennis R. Madison

Vice President

Southern Nuclear Operating

Company, Inc.

Joseph M. Farley Nuclear Plant

7388 North State Highway 95

Columbia, AL 36319

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION

REPORT 05000348/2018003 AND 05000364/2018003

Dear Mr. Madison:

On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an

inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2. On October 16, 2018, NRC

inspectors 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.

NRC inspectors documented one Licensee Identified Violation and one Severity Level (SL) IV

violation with no associated finding. The NRC is treating the SL IV violation as a non-cited

violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. If you contest the

violations or significance of this NCV, you should provide a response within 30 days of the date

of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory

Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the

Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident

inspector at the Joseph M. Farley Nuclear Plant, Units 1 and 2.

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/

Alan Blamey, Branch Chief

Reactor Projects Branch 2

Division of Reactor Projects

Docket Nos.: 50-348, 50-364

License Nos.: NPF-2, NPF-8

Enclosure:

IR 05000348/2018003, 05000364/2018003

cc Distribution via ListServ

D. Madison

2

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - NRC INTEGRATED INSPECTION

REPORT 05000348/2018003 AND 05000364/2018003

DISTRIBUTION:

S. Price, RII

M. Kowal, RII

K. Sloan, RII

OE Mail

RIDSNRRDIRS

PUBLIC

RidsNrrPMFarleyResource

ADAMS ACCESSION NUMBER: [Accession Number]

OFFICE

RII/ DRP

RII/ DRP

RII/ DRP

RII/ DRP

RII/ DRP

RII/ DRP

NAME

K. Miller

A. Blamey

P. Niebaum

N. Staples

D. Mas

M. Schwieg

DATE

10/31/2018

11/9/2018

10/31/2018

10/31/2018

11/1/2018

10/31/2018

Enclosure

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number(s):

50-348, 50-364

License Number(s):

NPF-2, NPF-8

Report Number(s):

05000348/2018003; and 05000364/2018003

Enterprise Identifier: I-2018-003-0038

Licensee:

Southern Nuclear Operating Company, Inc.

Facility:

Joseph M. Farley Nuclear Plant

Location:

Columbia, Alabama

Inspection Dates:

July 1, 2018 to September 30, 2018

Inspectors:

P. Niebaum, Senior Resident Inspector

M. Schwieg, Senior Resident Inspector

K. Miller, Resident Inspector

D. Mas-Penaranda, Project Engineer

Approved By:

A. Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

2

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance

by conducting baseline inspections at Joseph M. Farley, Units 1 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. NRC and self-

revealed findings, violations, and additional items are summarized in the table below

List of Findings and Violations

Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band

Cornerstone

Severity

Crosscutting

Report Section

Not

Applicable

Severity Level (SL) IV

NCV 05000348/2018003-01

Closed

Not Applicable

71153 - Follow-up of

Events and Notices of

Enforcement Discretion

A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a

routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than

allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action

completion time.

Additional Tracking Items

Type

Issue number

Title

Report Section

Status

LER 05000348/2018-001-00

Pressurizer Safety Valve Lift

Pressure Outside of

Technical Specification Limits

due to Spring Relaxation

71153 - Follow-up

of Events and

Notices of

Enforcement

Discretion

Closed

3

PLANT STATUS

Unit 1 began the report period at or near 100 percent rated thermal power (RTP). On

September 8, Unit 1 was reduced to approximately 16 percent RTP to support a containment

entry for an oil addition to the 1C reactor coolant pump motor upper bearing oil reservoir.

Following this work, Unit 1 achieved 100 percent RTP on September 9. Unit 1 stayed at or near

100 percent RTP until September 24, when the reactor was shut down to support a planned

maintenance outage to rework a main steam isolation valve (MSIV) actuator. The reactor was

started on September 28 and RTP was increased to approximately 72 percent by the end of the

report period.

Unit 2 began the report period at approximately 100 percent RTP and maintained that power

level for the entire 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 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

71111.01 - Adverse Weather Protection

External Flooding (1 Sample)

The inspectors verified that flood protection barriers, mitigation plans, procedures, and

equipment were consistent with the licensees design requirements and risk analysis

assumptions for coping with external flooding for the Service Water Intake Structure.

71111.04 - Equipment Alignment

Partial Walkdown (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems/trains:

(1)

Unit 2 containment spray system, A train, on August 13, 2018.

(2)

Unit 2 A motor driven auxiliary feedwater pump, on August 14, 2018.

(3)

Unit 2 residual heat removal system, A train, on August 28, 2018.

4

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the Unit 2

auxiliary feedwater system on August 30, 2018.

71111.05AQ - Fire Protection Annual/Quarterly

Quarterly Inspection (5 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas on August 8, 2018:

(1) Fire Area 072, Service Water Pump Room.

(2) Fire Area 073, Service Water Intake Structure Battery Room Train B.

(3) Fire Area 074, Service Water Intake Structure Battery Room Train A.

(4) Fire Area 075, Service Water Intake Structure 5kV Switchgear Room B & West Stairs.

(5) Fire Area 076, Service Water Intake Structure 5kV Switchgear Room A & East Stairs.

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on August 16, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated a crew of licensed operators in the plants simulator

during the licensed operator annual simulator exam on August 1, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated the power ascension of Unit 1 following an oil addition

to the 1C reactor coolant pump on September 8, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (2 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

(1) The maintenance rule program periodic (a)(3) evaluation on Aug. 29, 2018.

(2) Unit 1 and 2 shared 1-2A diesel generator degraded mode selector switch on Sept. 6,

2018.

71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent

work activities:

5

(1) Unit 2 elevated risk due to 2B emergency diesel generator corrective maintenance on

August 10, 2018.

(2) Unit 2 elevated risk due to 2B containment spray pump preventive maintenance on

August 13, 2018.

(3) Units 1 and 2 elevated risk due to modification work in the high voltage switchyard on

September 5, 2018.

(4) Unit 1 MSIV A emergent work on September 26, 2018.

71111.15 - Operability Determinations and Functionality Assessments (5 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) The 2B residual heat removal (RHR) pump radial bearing reservoir leaked oil during

performance of the FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test on July

16, 2018.

(2) Unit 2 pressurizer pressure transmitter PT-457 drifted high on July 1, 2018.

(3) Mounting bolt broken during replacement of mechanism operated cell switch on circuit

breaker Q2R15BKRDH07 on July 24, 2018.

(4) Unit 1, reactor coolant pump under voltage relay test review on July 28, 2018.

(5) Unit 1, impacts of potential oil leak on 1C reactor coolant pump motor upper bearing oil

reservoir on July 6, 2018.

71111.19 - Post Maintenance Testing (4 Samples)

The inspectors evaluated the following post maintenance tests:

(1) FNP-0-STP-80.2, Diesel Generator 1C Operability Test, after replacement of MOC

switch on circuit breaker Q2R15BKRDH07 on July 24, 2018.

(2) FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, after

replacement of an automatic voltage regulator control card on August 22, 2018.

(3) FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and

Operational Test, after replacement of pressurizer pressure transmitter on September

11, 2018.

(4) FNP-1-STP-21.2, MSIV Air System Leak Test, after replacement of air actuator on

September 26, 2018.

71111.20 - Refueling and Other Outage Activities (1 Sample)

The inspectors evaluated Unit 1 forced outage activities from September 24, 2018 to

September 28, 2018.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (1 Sample)

(1) Unit 1, FNP-1-STP-109.1, Power Range Neutron Flux Channel Calibration Using The

Plant Computer performed on July 16, 2018.

6

In-Service Testing (1 Sample)

(1) Unit 1, FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, on July 24, 2018.

RCS Leakage Detection (1 Sample)

(1) FNP-1-STP-9.0, RCS Leakage Test, on October 24, 2018.

71114.06 - Drill Evaluation

Emergency Planning Drill (1 Sample)

The inspectors evaluated an emergency preparedness drill that involved the failure of the

reactor to trip which led to an Alert Emergency, the loss of two fission product barriers

which lead to a Site Area Emergency and the subsequent loss of the third barrier which

led to a General Emergency on August 14, 2018.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below for the

period from July 2017, through June 2018. (6 Samples)

(1) Safety System Functional Failure (SSFF), Units 1 and 2.

(2) RCS specific activity, Units 1 and 2.

(3) RCS leakage, Units 1 and 2.

71152 - Problem Identification and Resolution

Semiannual Trend Review (1 Sample)

The inspectors reviewed the licensees corrective action program for trends that might be

indicative of a more significant safety issue.

(1) Condition Report 10529513, Trend in Missed Fire Watches.

Annual Follow-up of Selected Issues (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program

related to the following issues:

(1) Condition Report 10527200, Failure of Emergency Diesel Generator 1-2A to Run on

August 20, 2018.

7

71153 - Follow-up of Events and Notices of Enforcement Discretion

Licensee Event Reports (1 Sample)

The inspectors evaluated the following licensee event reports which can be accessed at

https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) Licensee Event Report (LER) 05000348/2018-001-00, Pressurizer Safety Valve Lift

Pressure Outside of Technical Specification Limits due to Spring Relaxation

OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation

The inspectors evaluated the licensees independent spent fuel storage installation cask

loadings on September 20, 2018.

INSPECTION RESULTS

Unit 1 Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Tolerance Band

Cornerstone

Severity

Crosscutting

Report Section

Not

Applicable

SL IV

NCV 05000348/2018003-01

Closed

Not Applicable

71153 - Follow-up of

Events and Notices of

Enforcement Discretion

A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when a

routine lift pressure test revealed that pressurizer safety valve Q1B13V0031C was lower than

allowed by TS SR 3.4.10.1 for a duration that was longer than the conditions TS required action

completion time.

Description: On April 12, 2018, pressurizer safety valve Q1B13V0031C was removed from

service at Farley Nuclear Plant Unit 1, and on April 16, 2018, the valve was tested with steam at

an offsite facility. As-found lift testing determined that the valve opened at 2420 psig steam

pressure, which was low outside the plant technical specification allowable lift setting range of

2460 psig to 2510 psig. The valve had been installed and placed in service at Farley Nuclear

Plant Unit 1 on October 8, 2013, and remained in service during three complete 18-month fuel

cycles. Upon removal of valve Q1B13V0031C from Unit 1 on April 12, 2018, it was replaced with

a similar operable refurbished valve. Licensee Event Report (LER) 05000348/2018-001-00,

Pressurizer Safety Valve Lift Pressure Outside of Technical Specification Limits due to Spring

Relaxation, was submitted by the licensee for this event.

Corrective Action(s): The valve was replaced with a similar operable refurbished valve during the

refueling outage prior to plant startup.

Corrective Action Reference(s): The licensee entered this issue into their corrective actions

program as CR10483091 - PZR safety valve test results.

Performance Assessment

The inspectors determined the condition was not reasonably foreseeable and preventable by the

licensee and therefore was not a performance deficiency. Specifically, random setpoint drift is a

recognized valid phenomenon that can occur despite routine testing and maintenance.

8

Enforcement:

Severity: Traditional Enforcement is being used to disposition this violation with no associated

Reactor Oversight Process performance deficiency per NRC Memorandum Interim Guidance for

Dispositioning Severity Level IV Violations with No Associated Performance Deficiency

(ML18158A220). The inspector assessed the severity of the violation using Section 6.1 of the

Enforcement Policy and determined the significance is appropriately characterized as Severity

Level IV, due to the inappreciable potential safety consequences. The licensee determined that

the safety valve low as-found lift set-point did not have an adverse impact on reactor coolant

system over-pressurization protection, since the valve continued to perform its reactor coolant

system over-pressure protection function to prevent the system from exceeding the design

pressure of 2485 psig. Therefore, the plant remained bounded by the accident analysis in the

FSAR, based on the as-found condition.

Violation: Farley Nuclear Plant Unit 1 TS LCO 3.4.10, Pressurizer Safety Valves, required three

operable pressurizer safety valves with lift settings between 2460 psig and 2510 psig, while the

Unit was in modes 1, 2, and 3. With one pressurizer safety valve inoperable, Action Statement,

Condition A. Required Action A.1, required restoration of the valve to operable status within 15

minutes. If the required action and associated completion time is not met, Action Statement,

Condition B, required that the unit be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Contrary to the above, the

licensee determined the pressurizer safety valve setting was outside the TS limits longer than 6

hours and 15 minutes during the last three operating cycle, between October 8, 2013 and April 12,

2018, while the Unit was in modes 1, 2, and 3.

Disposition: This violation is being treated as an NCV, consistent with Section 2.3.2 of the

Enforcement Policy.

Licensee Identified Non-Cited Violation

71152

This violation of very low safety significance was identified by the licensee and has been

entered into the licensee corrective action program and is being treated as a Non-Cited

Violation, consistent with Section2.3.2 of the Enforcement Policy.

Violation: Farley Unit 1 Operating License Condition 2.C.(4) and Unit 2 Operating License

Condition 2.C.(6), Fire Protection, required in part that Plant Farley shall implement and

maintain in effect all provisions of the approved fire protection program that comply with 10

CFR 50.48(c) and NFPA 805. NFPA 805 section 3.2.3 stated, in part, procedures to

accomplish compensatory actions implemented when fire protection systems and other

systems credited by the fire protection program and this standard cannot perform their

intended function shall be established. Licensee procedure FNP-0-SOP-0.4, Fire Protection

Operability and LCO Requirements section 4.0 establishes compensatory action when fire

protection systems and other systems credited by the fire protection program cannot perform

their intended functions.

Contrary to the above, since January 16, 2018 through August 28, 2018, the licensee failed to

establish compensatory measures (fire watches) as required by licensee procedure FNP-0-

SOP-0.4 on thirteen occasions. The cause of the fire watch discrepancies were mainly

because Farley Operations staff lacked an adequate understanding and ownership of the fire

watch implementation process.

9

Significance/Severity Level: The inspectors evaluated this finding in accordance with NRCs

inspection manual chapter (IMC) 0609 App F, Fire Protection Significance Determination

Process, issued May 2, 2018. The finding screened to Green (very low safety significance)

because the inspectors determined that the missed fire watches would not adversely impact

equipment important to safe shutdown of the unit in the respective fire areas.

Corrective Action Reference(s): Condition report (CR) 10529513 is the trend CR that

documented several missed fire watches. Corrective actions are planned and currently in

progress to address this issue.

EXIT MEETINGS AND DEBRIEFS

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

The inspectors confirmed that proprietary information was controlled to protect from public

disclosure.

On October 16, 2018, the inspectors presented the quarterly baseline inspection results,

respectively to Dennis Madison, Site Vice President, and Scott Briggs, Plant Manager, and

other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01: Adverse Weather Protection

Procedures:

FNP-0-AOP-21, Severe Weather, Rev. 46.1

NMP-OS-017, Severe Weather, Ver. 1.1

NMP-AD-014, Requirements for Compliance with NERC Standards, Ver. 6.1

NMP-AD-014-GL01, Guidelines for Compliance with NERC Standards, Ver. 6.0

Documents:

Regulatory Guide 1.27, Ultimate Heat Sink

D-171417, Pond Fill Discharge Structure, Rev. 3

D-170178, Piping- River Water Pumps Discharge To Storage Pond, Rev. 19

D-176981, Storage Dam and Dike - General Plan, Rev. 8

D-171419, River Water discharge to pond structure, Rev. 0

71111.04: Equipment Alignment

Procedures:

FNP-2-SOP-9.0, Containment Spray System, Ver. 38.1

FNP-2-SOP-9.0A, Containment Spray System, Ver. 8

FNP-2-SOP-7.0, Residual Heat Removal System, Ver. 99.0

FNP-2-SOP-7.0A, Residual Heat Removal System, Ver. 11.0

FNP-2-SOP-22.0, Auxiliary Feedwater System, Ver. 77.2

FNP-2-SOP-22.0A, Auxiliary Feedwater System, Ver. 14.0

Drawings:

D-205007, Unit 2 P&ID - Auxiliary Feedwater System, Sheet 1, Ver. 29.0

D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 1,

Ver. 39.0

10

D-205033, Unit 2 P&ID - Main Steam and Auxiliary Steam Systems, Sheet 2,

Ver. 25.0

D-205038, Unit 2 P&ID - Safety Injection System, Sheet 1, Ver. 39

D-205038, Unit 2 P&ID - Safety Injection System, Sheet 2, Ver. 24

D-205038, Unit 2 P&ID - Safety Injection System (Containment Spray), Sheet 3,

Ver. 34

D-205041, Unit 2 P&ID - Residual Heat Removal System, Sheet 1, Ver. 20

Condition Reports:

10530528

10530671

71111.05: Fire Protection Annual/Quarterly

Procedures:

FNP-0-FPP-3.0, Owner Controlled Area Pre-Fire Plan, Ver. 2.0

FNP-2-FPP-1.0, Unit 2 Auxiliary Building Pre-Fire Plan, Ver. 1.0

NMP-TR-425-F14, Fire Drill Package, Ver. 1.0

Condition Reports:

10508072

10508079

10516723

10517136

10523359

10523468

10523467

Work Orders:

SNC913159

SNC719746

SNC885164

SNC641901

SNC881904

SNC644350

SNC538103

SNC776088

SNC737915

SNC952320

SNC952321

Drawings:

D513635, Unit No. 1/2 - Fire Barriers and Fire Boundaries - Service Water Intake Structure

(SWIS), Ver. 1.0

Documents:

A-181805, NFPA 805 Fire Protection Program Design Basis Document, Ver. 5.0

71111.11: Licensed Operator Requalification Program

Procedures:

FNP-1-UOP-3.1, Power Operation, Ver. 131.0

Documents:

Operations Training Simulator Exam Scenario #31, Approved on July 26, 2018

71111.12: Maintenance Effectiveness

Procedures:

NMP-ES-027, Maintenance Rule Program, Ver. 8

Documents:

EVAL-F-Y41-04230, MR evaluation for 1-2A diesel generator MR function Y41-F05

Maintenance Rule Expert Panel (MREP) Meeting 18-16 Agenda, August 29, 2018.

Technical Evaluation (TE) 1016165

MREP meeting minutes from Meeting 18-16 on August 29, 2018.

11

Condition Reports:

10500679

71111.13: Maintenance Risk Assessments and Emergent Work Evaluation

Procedures:

NMP-OS-010-001, Farley Protected Equipment Logs, Ver. 15

NMP-GM-031-001, Online Maintenance Rule (a)(4) Risk Calculations, Ver. 5

Condition Reports:

10532482

Documents:

Unit 2 EOOS Operators Risk Report for August 10, 2018

Unit 2 EOOS Operators Risk Report for August 13, 2018

Unit 1 EOOS Operators Risk Report for September 5, 2018

Unit 2 EOOS Operators Risk Report for September 5, 2018

71111.15: Operability Determinations and Functionality Assessments

Procedures:

FNP-2-STP-11.2, 2B RHR Pump Quarterly Inservice Test, Ver. 43.0

FNP-0-GMP-30.1, Tribology Program, Ver. 25.0

FNP-0-GMP-37.0, Residual Heat Removal Pump Lubrication Procedure, Ver. 4.0

FNP-0-M-50, Master List of Surveillance Requirements, Ver. 30

Documents:

U418156, Instruction Manual RHR Pumps, Ver. 4.0

Administrative Tracking Item (ATI) 1705, dated May 22, 2018

A508632, Pressurizer Pressure Protection Scaling Document, Ver. 5.0

A-177048, Relay Settings, Sheet 328, Rev. 1

WCAP-1375-P, Westinghouse Setpoint Methodology for Protection Systems Farley Nuclear

Plant Units 1 and 2, Rev. 2

ATI-1705, Administrative Tracking Item for drifting PT-457

ODMI-18-04, 1C RCP motor bearing oil reservoir low level alarm, Ver. 3.0

Condition Reports:

10515924

10495878

10489880

10518144

10518931

10518992

10520001

Work Orders:

SNC880406

SNC830329

SNC810896

SNC810891

SNC955428

71111.19: Post Maintenance Testing

Procedures:

FNP-0-EMP-1313.12, Maintenance of Siemens-Allis 4.16 kV Metal-Clad Switchgear MOC

Switch, Ver. 9.3

FNP-0-EMP-1313.19, Inspection and Adjustment of Cutler Hammer 4.16 kV Circuit Breakers

Type MA-VR350, Ver. 17.0

FNP-0-EMP-1313.20, Enhanced Inspection of Cutler Hammer 4.16 kV Circuit Breakers Type

MA-VR350, Ver. 24.1

FNP-0-STP-80.2, Diesel Generator 1C Operability Test, Ver. 67.0

12

FNP-1-STP-80.20, Diesel Generator 1-2A 1000 KW Load Rejection Test, Ver. 23.1

FNP-2-STP-201.6, Pressurizer Pressure Q2B31PT0457 Loop Calibration and Operational Test,

Ver. 53.0

FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0

Condition Reports:

10518144

10518931

10527200

Work Orders:

SNC830329

SNC964137

SNC955428

71111.20: Refueling and Other Outage Activities

Procedures:

FNP-1-UOP-2.4 Planned Reactor Shutdown and Cooldown to Cold Shutdown

Condition Reports:

10540912

10541123

Documents:

NMP-OS-003-F01, Operational-Making Issue Worksheet, Ver. 6.4

71111.22: Surveillance Testing

Procedures:

FNP-1-STP-22.1, Auxiliary Feedwater Pump 1A Inservice Test, Ver. 45.0

FNP-1-STP-109.0, Power Range Neutron Flux Channel Calibration, Ver. 61

FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5

Condition Reports:

10515973

10515992

10520944

Work Orders:

SNC918430

Documents:

Integrated Plant Computer (IPC) printouts of reactor thermal power, reactor coolant loop delta-

temperature 1 min. average from July 11 through July 18, 2018

S-2018-014, Ver. 1, Standing order for CR10515992

71114.06: Drill Evaluation

Procedures:

NMP-EP-141, Event Classification, Ver. 2.0

NMP-EP-144, Protective Actions, Ver. 3.0

NMP-EP-141-001-F01, Farley - Hot Initiating Condition Matrix, Ver. 2.0

Documents:

Emergency Preparedness Drill Controller Guide, August 14, 2018

Reactor Plant Event Notification Worksheet, Drill message 1, August 14, 2018

Reactor Plant Event Notification Worksheet, Drill message 2, August 14, 2018

Reactor Plant Event Notification Worksheet, Drill message 3, August 14, 2018

Reactor Plant Event Notification Worksheet, Drill message 4, August 14, 2018

13

Reactor Plant Event Notification Worksheet, Drill message 5, August 14, 2018

Reactor Plant Event Notification Worksheet, Drill message 6, August 14, 2018

71151: Performance Indicator Verification

Procedures:

FNP-0-AP-54.0, Preparation and Reporting of NRC Performance Indicator Data and NRC

Operating Data, Ver. 15

FNP-1-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28

FNP-2-STP-746, Primary Coolant System Dose Equivalent Iodine-131 Determination, Ver. 28

FNP-0-CCP-25, Dose Equivalent Iodine-131 Determination, Ver. 15

FNP-1-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27

FNP-2-CCP-42, Primary Coolant Liquid Gamma Spectroscopy Analysis, Ver. 27

FNP-1-CCP-651.1, Routine Sampling of the Reactor Coolant System, Ver. 18.2

FNP-1-STP-9.0, RCS Leakage Test, Ver. 51.5

FNP-2-STP-9.0, RCS Leakage Test, Ver. 47.5

FNP-0-SOP-0.13, Recording Limiting Conditions For Operations, Ver. 35

FNP-1-STP-21.2, MSIV Air System Leak Test, Ver. 18.0

FNP-1-STP-45.7, MSIV Air System Leak Test, Ver. 24.0

Documents:

Main Control Room logs, various dates

Chemistry Surveillance logs, various dates

Farley Key Performance Indicators Report, August 2018

Licensee Event Reports (LERs): 05000348/2016007-02

05000348/2016008-00

05000348, 364/2016009-00 05000348/2017001-00

05000364/2017001-00

05000364/2017002-00

05000364/2017003-00

05000364/2017004-00

05000364/2017005-00

71152: Problem Identification and Resolution

Procedures:

NMP-ES-006-GL02, Preventative Maintenance Change Requests, Version 11.0

NMP-GM-002-001, Corrective Action Program Instructions, Version 3.0

NMP-GM-008, Operating Experience Program, Version 3.0

NOS -105, Internal Nuclear Oversight Audits, Version 5.6

NOS-104-001-F07, Engineering Audit Planning Guide, Version 2.0

NOS-104-001F17, Maintenance Audit Planning Guide, Version 3.0

PS-004, Vendor Technical Information Program, Version 4.0

Condition Reports:

10527200

2007100531 10540109

10540120

10540234

10540246

10540350

10529513

10513247

10529663

10529242

10525415

10450707

10463785

10464160

10464292

10464719

10481328

10529963

14

Work Orders:

SNC812826

Documents:

CR 10527200 Support Refute Matrix, dated 8/30/18

Fairbanks Morse Owners Group Fax Query 0709-09b, IEN Engineering Additional Follow-up

Information Item concerning SBSR Voltage Regulator Part 21, dated 9/21/07

Nuclear Oversight Audit of Engineering 1/4/17

Nuclear Oversight Audit of Maintenance 11/6/17

PMCR 22107, Extend EDG 1-2A PM Frequency, dated 8/4/10

Technical Decision Making Form, dated 8/30/18

CARs 272781, 274383

71153: Event Follow-up

Documents:

Licensee Event Report (LER) 05000364/2018-001-00, Pressurizer Safety Valve Lift Pressure

Outside of Technical Specification Limits during to Spring Relaxation

Condition Reports:

10483091

Work Orders:

SNC594727

60855.1 - Operation of an Independent Spent Fuel Storage Installation

Procedures:

FNP-0-MP-110.0, Dry Fuel Storage Campaign Guidelines, Ver. 19.0

FNP-0-MP-111.1, Hi-Storm System Site Transportation, Ver. 19.0

FNP-0-MP-111.11, MPC Helium Dehydration System Operation, Ver. 3.0

FNP-0-MP-111.12, Forced Helium Dehydration System Operation, Ver. 10.0

FNP-0-MP-111.13, Supplemental Cooling System Operation, Ver. 7.0

FNP-0-MP-111.2, Hi-Storm System Preparation and Loading Operation, Ver. 23.0

FNP-0-MP-111.3, MPC Fuel Loading Operations, Ver. 29.0

Retrieved from "https://kanterella.com/w/index.php?title=ML18318A053&oldid=4952191"