IR 05000269/2018012
| ML18240A355 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/28/2018 |
| From: | Shane Sandal Reactor Projects Region 2 Branch 6 |
| To: | Burchfield J Duke Energy Corp |
| References | |
| IR 2018012 | |
| Download: ML18240A355 (12) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ust 28, 2018
SUBJECT:
OCONEE NUCLEAR STATION - NUCLEAR REGULATORY COMMISSION TEAM INSPECTION REPORT 05000269/2018012, 050000270/2018012, AND 05000287/2018012
Dear Mr. Burchfield:
On July 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2, and 3. 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.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55
Enclosure:
IR 05000269/2018012, 05000270/2018012, and 05000287/2018012
Inspection Report
Docket Numbers: 50-269, 50-270, 50-287 License Numbers: DPR-38, DPR-47, DPR-55 Report Numbers: 05000269/2018012, 05000270/2018012, 05000287/2018012 Enterprise Identifier: I-2018-012-0011 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC Inspection Dates: July 23 - 26, 2018 Inspectors: R. Rodriguez, Senior Project Engineer (Team Leader)
S. Freeman, Senior Reactor Analyst A. Ruh, Resident Inspector S. Seaton, Project Engineer Approved By: S. Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure
SUMMARY
The NRC continued monitoring licensees performance by conducting 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 Oconee Nuclear Station, Units 1, 2, and 3, 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 (ML17202U791) 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 (ML17202U791) 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 July 26, 2018, the inspectors presented the inspection results to Mr.
- E. Burchfield, Site Vice
President, and other members of the licensees staff.
DOCUMENTS REVIEWED
Condition Reports Initiated as a Result of the Inspection
220256, Fuel Gauge on FLEX pump 0EDM-PU-0006 Faulty
220506, FLEX BUILDING NRC TI-2515/191 INSPECTION
220517, NRC TI-191 Inspection: Low hydraulic fluid identified
220531, NRC TI-191 Inspection: Degraded gaskets on FLEX pumps
220559, NRC TI-191 Inspection: B5b boat ramp overgrowth
220618, NRC TI-191 Inspection Suction Strainer not secured to pump
220963, NRC TI-191 Inspection-Cracked grout under 3SF-PY0011 support
220976, Unit 3 Wide Range SFP Level Channel A Waveguide Piping
221141, NRC TI-191 FLEX Inspection - Shallow Concrete Anchors Found
Procedures
AM/0/A/3009/012 A, Emergency Plan For Refilling Spent Fuel Pools, Revision 12
AP/0/A/1700/025, Standby Shutdown Facility Emergency Operating Procedure, Revision 63
EP/1/A/1800/001 0B, EOP Unit 1 Blackout, Revision 4
EP/1/A/1800/001 0O, Unit 1 EOP Enclosures 5.21-5.30, Revision 1
FG/0/A/1900/003, Alternative Low Pressure Emergency Feedwater, Revision 3
FG/0/A/1900/005, Initial Assessment and FLEX Equipment Strategy, Revision 4
FG/0/A/1900/011, Alternative Spent Fuel Pool Cooling, Revision 1
FG/0/A/1900/023, Phase 3 - NSRC Equipment and Long Term Considerations, Revision 1
FG/1/A/1900/004, Extended Loss of AC Power DC Load Management, Revision 0
FG/1/A/1900/015, Containment Isolation and Closure, Revision 0
FG/1/A/1900/020, FLEX Electrical Distribution, Revision 1
FG/2/A/1900/014, Unit 2 Shutdown RCS Makeup, Revision 1
FG/3/A/1900/020, FLEX Electrical Distribution, Revision 3
Drawings
239760D, Oconee Nuclear Station Unit 3 Flex Repower Primary Strategy One-Line Diagram,
Revision 1
239761D, Oconee Nuclear Station Unit 3 Flex Repower Alternate Strategy One-Line Diagram,
Revision 2
OM-201.3512.001, Oconee Nuclear Station Auxiliary Building - Unit 3 FLEX SFPLI Electrical
Equipment Floor Mounting Details, Revision 1
OM-201.3513.001, Oconee Nuclear Station Vega Waveguide Standard Support Details,
Revision 1
OM-201.3514.001, Qualifications for a Waveguide Type B Horn Support and Horn End
Assembly for AREVA Spent Fuel Pool Level Monitoring Instrumentation
OM-201.3515.001, Qualifications for a Waveguide Type A Horn Support and Horn End
Assembly for AREVA Spent Fuel Pool Level Monitoring Instrumentation
OM-201-3508.001, Oconee Nuclear Station Unit 3 Southwest SFP Vega Waveguide Support
Isometric [Primary / CH A], Revision 1
OM-201-3517.001, ONS FLEX SFPLI - Power Control Panel and Digital Display Mounting and
Anchorage Design for Units 1, 2 & 3, Revision 1
OM-201.3518.001, ONS SFPLI - Vega Waveguide Span Criteria, Standard Pipe Support
Design and Anchorage Verification for VEGA Waveguide Supports, Revision 1
Design Changes
EC 112453, FLEX Phase 2 Portable Equipment and Supplies Storage Building, Revision 3
EC 105805, Unit 1&2 Spent Fuel Pool Instrumentation, Revision 11
EC 105806, Unit 3 Spent Fuel Pool Instrumentation, Revision 13
Calculations
OSC-11347, ONS Permanent FLEX Storage Building Structural Analysis, Revision 1
OSC-11349, Flex Spent Fuel Pool Makeup, Revision 1
OSC-11232, Flow Model for Portable Pump Feeding Steam Generators Through SSF ASW
Piping from CTP #1 or Intake Canal, Revision 0
OSC-10937, Extended Loss of AC Power FLEX RELAP5 Analysis, Revision 3
OSC-11383, Attachment 4, Fukushima Diesel Fuel Oil Analysis, Revision 0
OSC-11670.05, Seismic Evaluation of FLEX Deployment Paths, Revision 0
OSS-0176.00-00-0005, Design Basis Specification for the Permanent FLEX Storage Building
(PFSB), Revision 0
Condition Reports
2169528 02154953 02130598
202996 02220055 02169897
2169897 02220506 02171976
2187259 02065552 02191847
2134612 02098793 02216719
Other
OMP 1-18, Implementation Standard During Abnormal And Emergency Events, Revision 41
CSD-EG-ONS-1619.1000, Diverse and Flexible Coping Strategies Program Document -
Oconee Nuclear Station, Revision 4
CSD-EG-ONS-1619.1004, NEI FLEX Time Validation for Oconee Nuclear Station, Revision 1
CSD-EG-ONS-1619.1005, FLEX Electrical Repower Strategies - Deployment, Cable Routing,
and Strategy Information, Revision 0
CSD-EG-ONS-1619.1007, Select Fukushima Related Technical Evaluations, Analyses, and
Position Papers for Compliance with NRC Order EA-12-049 and NRC Order EA-12-051
(OSC-11383), Revision 0
OM-201-3543.001, FLEX Diesel Generator Vender Manual
OSS-0176.00-00-0005, Design Basis Specification for the Permanent FLEX Storage Building
(PFSB), Revision 1
OP-OC-EAP-FG, Flex Guides, Revision 2
OM 261.0051.001, FLEX Hale FP3000DJ-TC Pump and Engine Manual, Revision 0
ASTM D975-15b, Standard Specification for Diesel Fuel Oils
ONS SSF Diesel Fuel Oil Cloud Point sample results between October 5, 2011 and April 11,
2017
TT&R LP Terminal Report Cloud Point results between July 16, 2017 and July 28, 2018
OSS-0020.00-00-0006, Specification for the Design, Installation, and Inspection of Hilti
Concrete Anchors, Revision 6
Duke Energy Carolinas, LLC, Capability to Perform Multi-Unit Dose Assessment
Capability, June 26, 2013
AD-EP-ALL-0105, Activation And Operation Of The Technical Support Center, Revision 1
AD-EP-ALL-0202, Emergency Response Offsite Dose Assessment, Revision 6
CSD-EG-ONS-1619.1001, SAFER Response Plan for Oconee Nuclear Station, Revision 1
CSD-EG-ONS-1619.1007, Select Fukushima Related Technical Evaluations, Analyses, and
Position Papers for Compliance with NRC Order EA-12-049 and NRC Order EA-12-051
(OSC-11383) Revision 0
PT/0/A/2000/002, Periodic Test of Emergency Response Communications Equipment, Revision
005 - Monthly Test completed 7/7/18
PT/0/A/2000/002, Periodic Test of Emergency Response Communications Equipment, Revision
005 - Quarterly Test completed 4/2/18
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