IR 05000348/2018012
| ML18218A291 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/06/2018 |
| From: | Shane Sandal Reactor Projects Region 2 Branch 6 |
| To: | Madison D Southern Nuclear Operating Co |
| References | |
| IR 2018012 | |
| Download: ML18218A291 (13) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ust 6, 2018
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT - NUCLEAR REGULATORY COMMISSION TEAM INSPECTION REPORT 05000348/2018012 AND 05000364/2018012
Dear Mr. Madison:
On June 28, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2. The 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.
The inspection examined activities conducted under your license as they relate to the implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commissions rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. If you have any questions, please contact me at 404-997-4513.
Sincerely,
/RA/
Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8
Enclosure:
IR 05000348/2018012, 05000364/2018012
Inspection Report
Docket Numbers: 50-348, 364 License Numbers: NPF-2, NPF-8 Report Numbers: 05000348/2018012; and 05000364/2018012 Enterprise Identifier: I-2018-012-0013 Licensee: Southern Nuclear Operating Company, Inc.
Facility: Joseph M. Farley Nuclear Plant Location: Columbia, Alabama Inspection Dates: June 25 - 28, 2018 Inspectors: G. MacDonald, Senior Reactor Analyst (Team Leader)
B. Bishop, Project Engineer K. Miller, Resident Inspector K. Roche, Project Manager (NRR/BDBEB)
Approved By: S. Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure
SUMMARY
The NRC continued monitoring licensees performance by conducting a Temporary Instruction (TI) 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP)
Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, inspection (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18191B074) at Joseph M. Farley Nuclear Plant, 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.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items Type Issue number Title Report Status Section TI TI 2515/191 Inspection of the Implementation of Other Closed Mitigation Strategies and Spent Fuel Activities Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans
TABLE OF CONTENTS
INSPECTION SCOPE
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
INSPECTION RESULTS
..............................................................................................................
EXIT MEETINGS AND DEBRIEFS
............................................................................................ 6
DOCUMENTS REVIEWED
.......................................................................................................... 7
INSPECTION SCOPE
Inspections were conducted using the appropriate portions of Temporary Instruction (TI)
procedure 2515/191, Implementation of Mitigation Strategies and Spent Fuel Pool (SFP)
Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose
Assessment Plans, (ADAMS Accession No. ML18191B074). Documents reviewed by
inspectors are listed in the documents reviewed section of this report. 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.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool
Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose
Assessment Plans
Inspectors verified plans for complying with NRC Orders EA-12-049, Order Modifying
Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis
External Events, (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML12056A045) and EA-12-051, Order Modifying Licenses with Regard to
Reliable Spent Fuel Pool Instrumentation, (ML12054A679) were in place and were being
implemented by the licensee. Additionally, the inspection verified implementation of staffing and
communications information provided in response to the March 12, 2012, request for
information letter (ML12053A340) and dose assessment information provided per COMSECY-
13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons
Learned, dated March 27, 2013 (ML12339A262).
(1) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the Diverse and Flexible Coping
Strategies (FLEX) as described in the plant-specific submittals and the associated safety
evaluation (ML17090A457) and determined that the licensee is in compliance with NRC
Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation
Strategies for Beyond-Design-Basis External Events (ML12056A045). The inspectors
verified the licensee satisfactorily:
a) developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX
strategies for postulated external events;
b) integrated their FSGs into their existing plant procedures such that entry into and
departure from the FSGs were clear when using existing plant procedures;
c) protected FLEX equipment from site-specific hazards;
d) developed and implemented adequate testing and maintenance of FLEX equipment
to ensure their availability and capability;
e) trained their staff to ensure personnel proficiency in the mitigation of
beyond-design basis events; and
f) developed the means to ensure the necessary off-site FLEX equipment would be
available from off-site locations.
(2) Based on samples selected for review, the inspectors verified that the licensee
satisfactorily implemented appropriate elements of the FLEX strategy as described in the
plant specific submittals and the associated safety evaluation (ML17090A457) and
determined that the licensee was in compliance with NRC Order NRC Order EA-12-
051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool
Instrumentation (ML12054A679). The inspectors verified that the licensee satisfactorily:
a) installed the spent fuel pool (SFP) instrumentation sensors, cabling and power
supplies to provide physical and electrical separation as described in the plant
specific submittals and safety evaluation;
b) installed the SFP instrumentation display in the location, environmental conditions
and accessibility as described in the plant specific submittals;
c) trained their staff to assure personnel proficiency with the maintenance, testing, and
use of the SFP instrumentation; and
d) developed and issued procedures for maintenance, testing and use of the reliable
SFP instrumentation.
(3) The inspectors reviewed information provided in the licensees dose submittal and in
response to the NRCs March 12, 2012, request for information letter (ML12053A340),
and verified that the licensee satisfactorily implemented enhancements pertaining to
Near-Term Task Force (NTTF) Recommendation 9.3 response to a large-scale natural
emergency event that results in an extended loss of all alternating current (ac) power
(ELAP) to all site units and impedes access to the site The inspectors verified the
following:
a) the licensee satisfactorily implemented required staffing changes to support a
ELAP scenario;
b) emergency preparedness (EP) communications equipment and facilities are
sufficient for dealing with a ELAP scenario; and
c) the licensee implemented dose assessment capabilities (including releases from
SFPs) using the licensees site-specific dose assessment software and approach.
The inspectors verified that noncompliances with requirements, and standards identified during
the inspection were entered into the licensee's corrective action program as appropriate.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
No proprietary information was retained by the inspectors or documented in this report.
On June 28, 2018, the inspectors presented the inspection results to Mr.
- D. Erb, Acting Plant
Manager, and other members of the licensees staff.
On July 19, 2018, the lead inspector presented the final inspection results to Mr.
Licensing Manager.
DOCUMENTS REVIEWED
Condition Reports Initiated as a Result of the Inspection
10509209, NRC Identified - Unit 1 PRIMARY SFP LI (N1G31LI0007) Red Light on UPS
Illuminated
10509496, During NRC Walk-down in FLEX Dome, One Section of Rolled Hose Had Tight
Radius Bend
10509705, Alternate SFP Level Indicators for FLEX are not Operable
10509712, Procedure FNP-1-SOP-36.4A Page 31, Breaker #9 Description Needs to Read
N1G31LI0008/ N2G31LI0008
10509720, Procedure FNP-1-SOP-36.4A Page 29, Breaker #9, Delete Entire Entry (Does Not
Exist)
10509764, Procedures for PRIMARY and ALT SFP LI Need Enhancements to Address
Abnormal Indications
10509896, Fleet Documents for Common SFP LI Not Consistent Across Fleet
10510217, NRC Identified - Perform Training Needs Analysis for Functionality Assessment of
FLEX Equipment
10510402, NRC Identified - Editorial Error in SNC Response to NRC Request for Information
10510406, NRC Identified - Evaluate Enhancing FNP-0-AOP-21 to add FLEX Dome Cold
Weather Actions
Procedures
FNP-0-AOP-21.0, Farley Nuclear Plant Abnormal Operating Procedure Severe Weather,
Revision (Rev.) 46.1
FNP-1-ECP-0.0, Unit 1 Loss of All AC Power, Rev. 30.0
FNP-2-ECP-0.0, Unit 2 Loss of All AC Power, Rev.30.0
FNP-1-IMP-222.0, Unit 1 Spent Fuel Pool Level Instrumentation Calibration, Version (Ver.) 1.0
FNP-2-IMP-222.0, Unit 2 Spent Fuel Pool Level Instrumentation Calibration, Ver. 1.0
FNP-1-SOP-54.0, Spent Fuel Pit Cooling & Purification System, Ver. 75.1
FNP-2-SOP-54.0, Spent Fuel Pit Cooling & Purification System, Ver. 75.0
FNP-1-SOP-36.4A, 120V AC Distribution Systems - AUX BLDG, Rev. 32
FNP-2-SOP-36.4A, 120V AC Distribution Systems Auxiliary Building, Rev. 34
NMP-EP-147, Offsite Dose Assessment, Ver. 2.0
NMP-GM-038, Diverse and Flexible Coping Strategies (FLEX) Program, Ver. 2.0
NMP-OM-002, Shutdown Risk Management, Ver. 5.0
NMP-OS-007-001, Conduct of Operations Standards and Expectations, Ver. 16.2
NMP-OS-019-001, EOF Support for Beyond Design Basis Events, Ver. 3.0
NMP-OS-019-002, Farley Nuclear Plant TSC Options, Ver. 3.0
NMP-OS-017, Severe Weather, Ver. 1.1
NMP-OS-019-013, Unit S, Beyond Design Basis Equipment Unavailability Tracking, Ver. 2.0
NMP-OS-019-100, Unit S Flex Portable Equipment Operating Instructions, Ver. 1.0
NMP-OS-019-111, Farley Unit 1 FSG-11, Alternate SFP Makeup and Cooling, Ver. 1.1
NMP-OS-019-112, Farley Unit 1 FSG-12, Alternate Containment Cooling, Ver. 2.0
NMP-OS-019-103, Unit 1 FSG-3, Alternate Low Pressure Feedwater, Ver. 1.0
NMP-OS-019-123, Unit 2 FSG-3, Alternate Low Pressure Feedwater, Ver. 1.0
NMP-OS-019-104, Unit 1 FSG-4, ELAP DC Load Shed/Management, Ver. 2.0
NMP-OS-019-124, Unit 2 FSG-4, ELAP DC Load Shed/Management, Ver. 2.0
NMP-OS-019-105, Unit 1 FSG-5, Initial Assessment and FLEX Equipment Staging, Ver. 1.2
NMP-OS-019-125, Unit 2 FSG-5, Initial Assessment and FLEX Equipment Staging, Ver. 2.1
NMP-OS-019-114, Unit 1 FSG-14 Shutdown Modes, Ver. 1.1
NMP-OS-019-134, Unit 2 FSG-14 Shutdown Modes, Ver. 1.1
NMP-OS-019-159 Unit S SIG-9, Communications, Ver. 1.0
NMP-OS-019-165, Unit 1 SIG-5, Tank Makeup, Ver. 1.1
NMP-OS-019-108, Farley Unit 1 FSG-8, Alternate RCS Boration, Ver. 1.1
NMP-OS-019-161, Farley Unit S SIG-1 600V Alternate Power, Ver. 2.1
NMP-OS-019-162, Farley Unit S SIG-2 480V Alternate Power, Ver. 1.1
NMP-OS-019-164, Farley Unit 1 SIG-4, Boron Injection and RCS Makeup, Ver. 2.1
NMP-OS=019-166, Farley Unit 1 SIG-6, Containment Integrity, Ver. 1.0
NMP-OS-019-157, Farley Unit S SIG-7, Diesel Fuel Oil Transfer, Ver. 2.1
NMP-OS-019-131, Farley Unit 2 FSG-11, Alternate SFP Makeup and Cooling, Ver. 1.1
NMP-OS-019-151, Farley Unit S FSG-11 Background Document, Ver. 1.0
NMP-OS-019-158, Farley Unit S SIG-8, Spent Fuel Pool Makeup, Ver. 1.1
NMP-OS-019-163, Farley Unit 1 SIG-3, Core Cooling, Ver. 1.1
NMP-OS-019-183, Farley Unit 2 SIG-3, Core Cooling, Ver. 2.1
TRNOPS-TR-417-001, Plant Farley Initial License Training Program Instruction, Ver. 1.0
TRNOPS-TR-415-001, Plant Farley Systems Operator Training Program Instruction
Drawings
A181108, 8.6, Flow Schematic, Ver. 3.0
A181105, 8.1, Flow Schematic, Ver. 2.0
A181106, 8.1, Flow Schematic, Ver. 4.0
A181125, Attachment A, Ver. 1.0
A181115, Site Plot Plan, Ver. 2.0
A181115, Partial Plot Plan, Ver. 2.0
A181106, FLEX Portable System, Spent Fuel Pool Subsystem, Phase 2, Ver. 4.0
D-177001, Single Line Electrical Auxiliary System Emergency 4160 & 600V Worksheet
SNC467063E002, Ver. 2.0
Work Orders
SNC878108, Unit S Flex Communication Modem Replacement
SNC894667, FLEX storage Building (Dome) Standby Walk-down, Rev. 0
SNC913263, Battery is not charging for Unit 2 ALT SFP LI (N2G31LI0008), dated February 8,
2018
SNC872887, Replace Batteries for Unit 2 ALT SFP LI (N2G31LI0008), dated December 11,
2017
SNC874015, Replace Batteries for Unit 2 PRIMARY SFP LI (N2G31LI0007), dated August 4,
2017
SNC824684, Replace Batteries for Unit 2 ALT SFP LI (N2G31LI0008), dated June 9, 2017
SNC824683, Replace Batteries for Unit 1 ALT SFP LI (N1G31LI0008), dated June 9, 2017
SNC871306, SG FLEX Pump Functional Test and Inspection
SNC830921, SG FLEX Pump Operational Inspection
SNC779173, Boron Injection FLEX Pump Skid Operational Inspection
SNC871318, 600V FLEX Diesel Generator Functional Test and Inspection
SNC872281, 600V FLEX Diesel Generator Operational Inspection
SNC829882, 600V FLEX Diesel Generator Functional Test and Inspection
SNC829871, SG FLEX Pump Functional Test and Inspection
Condition Reports
10345426 10263652 10290610 10292439 10296763 10297515
10133337 10345426 10353387 10357521 10509542 10509702
10076939 10076943 10095022 10260819 10263553 10292907
292440 10292441 10301430 10370275 10370351 10372991
10372995 10374860 10375223 10437010 10439000 10477767
10477769 10496998 10494961 10280106 10424345 10261671
10453055 10281806 10382284 10493500 10373488 10232249
257129 10244627 10296763
Other
A181163, Flex Portable System Steam Generator FLEX Pump Vendor Manual, Ver. 1.0
A181102, Att. A, Phase 2 480V and 600V Alternating Power Subsystem, Ver. 3.0
Enercon Project No: SNCF206, Report of Liquefaction Potential Assessment
RapidCase Functional Test and Inspection Work Instructions
Flex Training Records for System Operators and Licensed Operators
RER SNC 546909-02
NEI 12-01 Farley On-Shift Staffing Analysis, Ver.2.0
SNC Dose Assessment Form - Plant Farley, June 27, 2018 - 0730
NEI 12-01, Guideline for Assessing Beyond Design Basis Accident Response Staffing and
Communications Capabilities, Rev. 0
NEI-12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide Rev. 2
Fukushima Response NEI 12-01 On-Shift Staffing Analysis Phase 2 Report Version 2.0
Standard Emergency Plan, Ver.2.0
FHC-S-13-001/X1AR50, Flex Equipment Storage Building, Ver. 2.0
Southern Nuclear Operating Company Letter (NL-13-0987), Joseph M. Farley Nuclear Plant -
Units 1 & 2, Edwin
- I. Hatch Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Nuclear
Plant - Units 1& 2, Capability to Perform Emergency Multi-Unit Offsite Dose Assessments,
dated June 24, 2013
U612262, Spent Fuel Pool Instrumentation System Standard Product Technical Manual,
Ver. 1.0
NMP-TR-212-F08, Training Needs Analysis, F-LT-NL-2014050, dated august 22, 2014
Adams Accession Number ML15182A175, Letter NL-15-0699, Joseph
- M. Farley, Unit 1 -
Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Level
Instrumentation, dated June 26, 2015
Adams Accession Number ML14239A328, Letter NL-14-1109, Joseph
- M. Farley, Units 1 and 2
- Third Six-Month Status Report of the Implementation of the Requirements of the
Commission Order with Regard to Reliable Spent Fuel Pool Level Instrumentation (EA-12-
051), dated August 26, 2014
RER SNC56909, RER for FLEX Storage Building Site Evaluation and Documentation, Ver. 1.1
SNC Standard Emergency Plan Annex for FNP Units 1 and 2, Ver. 1.0
Diesel Fuel Supply Assurance Letter, dated June 27, 2018
SAFER Response Plan for Joseph
- M. Farley Generating Station, Rev. 1
Documentation of Engineering Judgement, DOEJ-FDSNC467063-E001, Voltage Drop Cable
Sizing, and Train Separation Evaluation for Flex Power Cables for 600V Buses 1D, 1E, 2D,
and 2E, Ver. 3.0
A-181103, Flex Portable System Phase 3 4160V Alternate Power System, Ver. 2.0
Calculation SM-SNC458207-006, Auxiliary Building El. 100 Corridor Heat up Evaluation during
an Extended Loss of all AC Power ELAP, Ver. 1.0
Joseph
- M. Farley, Units 1 and 2, Safety Evaluation Regarding Implementation of Mitigating
Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and
EA-12-051 (CAC Nos. MF0716, MF0717, MF1429 and MF1430), dated April 24, 2017
Final Integrated Plan,
- U. S. Nuclear Regulatory Commission Order EA-12-049, Strategies for
Beyond Design Basis External Events, November 2016
Farley Nuclear Plant Flex Validation Report, dated April 27, 2016
Plant Farley FLEX Overview NRC TI-191 Inspection, dated June 25, 2018
SNCF166-PR-002, Diverse and Flexible Coping Strategies (FLEX) in Response to NRC Order
EA-12-049 Mitigating Strategies for Beyond-Design -Bases External Events, Rev. 3
Fukushima Response, NEI-12-01, On-Shift Staffing Analysis Phase 2 Report, Ver. 2.0
10