ML18134A222
| ML18134A222 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-086) |
| Issue date: | 05/14/2018 |
| From: | Fred Bower Reactor Projects Branch 3 |
| To: | Nazar M NextEra Energy Seabrook |
| References | |
| IR 2018001 | |
| Download: ML18134A222 (13) | |
See also: IR 05000443/2018001
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD.
KING OF PRUSSIA, PA 19406-2713
May 14, 2018
Mr. Mano Nazar
President and Chief Nuclear Officer
Nuclear Division
NextEra Energy Seabrook, LLC
Mail Stop: EX/JB
700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - INTEGRATED INSPECTION REPORT
Dear Mr. Nazar:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Seabrook Station, Unit No. 1 (Seabrook). On April 26, 2018, the NRC inspectors discussed
the results of this inspection with Mr. Christopher Domingos, Site Director, and other members
of the licensee staff. The results of this inspection are documented in the enclosed report.
The inspectors documented a licensee-identified violation which was determined to be of very
low safety significance in this report. The NRC is treating this violation as a non-cited violation
consistent with Section 2.3.2.a of the Enforcement Policy.
No NRC-identified or self-revealing findings were identified during this inspection.
If you contest the violation or significance of the non-cited violation, you should provide a
response within 30 days of the date of this inspection report, with the basis for your denial, to
the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC
20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of
Enforcement; and the NRC Resident Inspector at Seabrook.
M. Nazar
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 the NRC Public Document Room
in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Fred L. Bower, III, Chief
Reactor Projects Branch 3
Division of Reactor Projects
Docket No.
50-443
License No.
Enclosure:
Inspection Report 05000443/2008001
cc w/encl: Distribution via ListServ
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE
RI/DRP
RI/DRP
RI/DRP
NAME
PCataldo
RBarkley
FBower
DATE
5//2018
5/14/2018
5/14/2018
1
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
50-443
License Number:
Report Number:
Enterprise Identifier: I-2018-001-0049
Licensee:
NextEra Energy Seabrook, LLC (NextEra)
Facility:
Seabrook Station, Unit No. 1 (Seabrook)
Location:
Seabrook, NH
Inspection Dates:
January 1, 2018 to March 31, 2018
Inspectors:
P. Cataldo, Senior Resident Inspector
P. Meier, Resident Inspector
D. Beacon, Acting Resident Inspector
J. Furia, Senior Health Physicist
N. Floyd, Reactor Inspector
Approved By:
Fred L. Bower, III, Chief
Reactor Projects Branch 3
Division of Reactor Projects
2
SUMMARY
The NRC continued monitoring NextEras performance at Seabrook by conducting the
baseline inspections described in this report 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.
A licensee-identified non-cited violation is documented in report Section 71111.15.
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PLANT STATUS
Seabrook Station began the inspection period operating at 100 percent rated thermal power.
There were no operational power changes of regulatory significance for the remainder of the
inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures in effect
at the beginning of the inspection unless otherwise noted. Currently approved inspection
procedures 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 inspection procedure requirements most
appropriate to the inspection activity were met consistent with Inspection Manual Chapter
(IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors
performed plant status activities described in IMC 2515 Appendix D, Plant Status and
conducted routine reviews using IP 71152, Problem Identification and Resolution. The
inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel to assess licensee performance and compliance with Commission rules and
regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather (1 sample)
The inspectors evaluated readiness for impending adverse weather conditions for a winter
storm on January 3 and 4.
71111.04 - Equipment Alignment
Partial Walkdown (4 samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) B emergency diesel generator alignment with A emergency diesel generator
inoperable for testing on January 16
(2) A emergency diesel generator alignment with the B emergency diesel generator
inoperable for relay maintenance and testing on January 30
(3) A residual heat removal system with B residual heat removal system out of service on
February 27
(4) B safety injection with A safety injection out of service on March 20
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71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (5 samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Turbine building 75 elevation (TB-F-3-0) on March 8
(2) A emergency diesel generator room (DG-F-2A-A) on March 15
(3) B emergency diesel generator (DG-F-2B-A) on March 15
(4) A emergency diesel generator silencer room (DG-F-3E-A) on March 16
(5) B emergency diesel generator silencer room (DG-F-3F-A) on March 16
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated licensed operator requalification training, in accordance
with 10 CFR 55.59, at Seabrook on February 5, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated the following:
(1) Reactor coolant system dilution activity; alarm response procedure implementation; and,
briefing for engineered safety features actuation system slave relay testing on January 11
(2) Fast start of the B emergency diesel generator; procedure compliance and alarm response
procedure implementation; technical specification entries for off-site power and emergency
diesel generator technical specification acceptance criteria; and, turbine voltage adjustment on
January 30
(3) Completion of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> emergency diesel generator loaded run and hot restart; procedure
compliance and alarm response procedure implementation on January 31
(4) Quarterly control rod surveillance testing; abnormal operating procedure entry for misaligned
control rod; technical specification entries for misaligned control rod; briefs and crew updates
for activities surrounding misaligned control rod; and, alarm response for emergent station air
compressor auto-start due to system demand on March 12
(5) Brief for 'B' condensate pump start after maintenance; expected and unexpected alarm
response procedure implementation; and, normal operating procedure implementation for
pump start on March 29
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) Evaluation of safety-related relay maintenance and replacement schedules associated
with the emergency diesel generators, following the failure of a commercially-dedicated
CR-120BC relay and subsequent 10 CFR Part 21 report submittal in March 2018.
5
(2) B emergency diesel generator lube oil filter and strainer high differential pressure
troubleshooting on February 5
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) Winter storm/grid vulnerability on January 3 and 4
(2) D atmospheric dump valve and B emergency diesel generator maintenance on
January 30
(3) A vital battery disconnect and effects on emergency power sequencer on February 12
(4) Switchyard activities and A emergency diesel generator activities on February 13
(5) Safety Injection activities and entry into Independent System Operator - New England
Master/Local Control Center procedure No. 2 on March 20 and 21
71111.15 - Operability Determinations and Functionality Assessments (6 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) Supplemental emergency power system cooling water leak on January 2
(2) Instrumentation seal table recurrent leak at location J-11 discovered on January 24
(3) Misaligned shutdown bank E rod, H4, following rod operability testing on March 12
(4) Structural evaluation of seven safety-related electrical manholes on March 21
(5) Emergency diesel generator operability following Part 21 report on CR120B relay bench
test failures on March 22
(6) B residual heat removal heat exchanger component cooling vent line weld evaluation in
March 2018
71111.18 - Plant Modifications (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1) Replacement of A emergency diesel generator idle operate Agastat time-delay relay
with an upgraded timing relay, under engineering change No. 289875, on February 13
(2) Temporary modification to re-position A steam generator steam supply condensing pot
vent valve, MS-V-299, under engineering change No. 290828, on March 20
71111.19 - Post Maintenance Testing (6 Samples)
The inspectors evaluated post maintenance testing for the following maintenance/repair
activities:
(1) A battery charger repair on January 2 and 3
(2) B containment enclosure cooling fan, 1-EAH-FN-5B, planned maintenance on
January 10
(3) Diesel fire pump 20B corrective maintenance on January 25
(4) B emergency diesel generator synchronizing relay replacement on January 30
6
(5) Primary component cooling water isolation from residual heat removal heat exchanger
B valve, 1-CC-V-272, environmental qualification maintenance and testing on March 6
(6) B emergency diesel generator voltage transducer replacement on March 27
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (5 Samples)
(1) B emergency safety features actuation system testing under OX1456.64 on January 11
(2) 'B' emergency diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test and hot restart surveillance on
January 30 and 31
(3) Quarterly containment spray pump operability testing under OX1406.02 on March 9
(4) Quarterly control and shutdown rod operability testing under OX1410.02 on March 12
(5) Dose equivalent iodine chemistry sampling and analysis on March 20
In-service (1 Sample)
(1) B safety injection containment isolation valve quarterly stroke test surveillance on
February 9
71114.06 - Drill Evaluation
Emergency Planning Drill (1 Sample)
The inspectors evaluated the conduct of a routine, full participation emergency planning
drill No. 18-01 on February 14.
Drill/Training Evolution (1 Sample)
The inspectors evaluated the emergency planning aspects of a licensed operator annual
simulator evaluation conducted in the Unit 1 plant-reference simulator on February 5.
This evaluation included the initiation conditions and reporting requirements that resulted
in associated emergency classification and notifications in accordance with prescribed
procedures of the NextEra emergency plan.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Instructions to Workers (1 Sample)
The inspectors reviewed high radiation area work permit controls and use, observed
containers of radioactive materials and assessed whether the containers were labeled and
controlled in accordance with requirements.
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71124.02 - Occupational As Low As Reasonably Achievable Planning and Controls
Radiation Worker Performance (1 Sample)
The inspectors observed radiation worker and radiation protection technician performance
during radiological work to evaluate worker as low as reasonably achievable performance
according to specified work controls and procedures.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification (3 Samples)
The inspectors verified licensee performance indicators submittals listed below for the
period January 2017 through December 2017:
(1)
Unplanned scrams per 7000 critical hours
(2)
Unplanned power changes per 7000 critical hours
(3)
Unplanned scrams with complications
71152 - Problem Identification and Resolution
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) Review of Alkali-Silica Reaction Impact on Concrete Structures
71153 - Follow-up of Events and Notices of Enforcement Discretion
Events (1 Sample)
The inspectors evaluated response to the following events:
(1) Response to a seismic event on February 15, in accordance with abnormal operating
procedure OS1200.04, and engineering evaluation of structures and equipment under
ES1802.001
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INSPECTION RESULTS
Licensee-Identified Non-Cited Violation
This violation of very low safety significant 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 Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part,
that measures shall provide for verifying or checking the adequacy of design, such as by the
performance of design reviews, by the use of alternate or simplified calculational methods, or
by the performance of a suitable testing program.
Contrary to the above, from an unknown date until January 10, 2018, NextEra did not have a
measure for verifying the adequacy of design of seven safety-related electrical manholes.
Specifically, there were no original calculations to support the design of the manholes; and
when NextEra staff reconstituted the structural design calculation, the results concluded that
four of the seven manholes would not meet the design specification unless the loading
demands were reduced from 500 to 200 pounds per square foot.
Significance/Severity Level: Green because all four structures remained capable of
performing their safety function.
Corrective Action References: AR 02243800 and AR 02255652
Observations
71152 Follow-up of
Selected Issues
The NRC performed a periodic site visit to Seabrook Station to review NextEras monitoring of
alkali-silica reaction (ASR) on affected reinforced concrete structures, per their 10 CFR 50.65
Maintenance Rule Structures Monitoring Program, and NextEras corrective action process.
The inspectors verified on a sampling basis that significant changes or different presentations
of ASR on the affected structures were appropriately considered for impact on the existing
Seabrook prompt operability determinations for the affected structures. In addition, the
inspectors performed independent walkdowns of ASR-affected areas; and reviewed reports of
recently collected measurement data, including combined crack index, in-plane expansion,
and extensometers, to verify that the structures were well within the established acceptable
monitoring parameters.
Based on the results of calculations conducted to evaluate the future impact of ASR on the
reinforced concrete structures, the containment enclosure ventilation area (CEVA) North wall
and the B electrical tunnel were identified to not qualify (i.e., demand vs. capacity) in
accordance with structural design code ACI 318-71, Building Code Requirements for
Reinforced Concrete. These results were previously documented in the NRCs fourth quarter
integrated inspector report, IR 05000443/2017004 (ADAMS Accession Number
ML18043A821). The inspectors performed a review to follow-up on NextEras corrective
actions associated with these two structures.
NextEra staff identified remediation methods and planned actions to ensure the long-term
structural performance of the CEVA North wall. The inspectors reviewed the draft engineering
change package that outlined the conceptual repairs to the wall. The inspectors noted that
NextEra staff were still in the design phase. The NRC will review the final design package
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once it has been completed, including the actual implementation of the structural modification.
The inspectors reviewed the January 2018 lateral displacement measurements to verify the
structure maintained its structural stability and noted that there had been no apparent
changes in the displacement since the previous measurements taken in October 2017.
For the B electrical tunnel, NextEra staff revised the methodology used to determine the ASR
loading from the concrete backfill on the electrical tunnel wall, and concluded that this
reanalysis would fully qualify the structure in accordance with ACI 318-71 structural design
code. NextEra plans to provide this revised methodology to the NRC as a supplement to
License Amendment Request 16-03, dated August 1, 2016. Examination of NextEras
methodology for analyzing seismic Category I structures with concrete affected by ASR is
currently under review by the NRC. The inspectors performed an independent walkdown of
the electrical tunnel and did not observe any indications of loading distress or other structural
integrity issues as evident by the absence of structural flexure cracks. NextEra staff planned
to perform more frequent inspections of the electrical tunnel and to predevelop a modification
package in the event that cracking is identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On March 22, 2018, the inspectors presented the Problem Identification and Resolution
annual sample (71152 (1)) inspection results to Larry Nicholson, Director of Nuclear
Licensing & Regulatory Compliance, and other members of NextEra staff.
On March 29, 2018, the inspectors presented the radiation safety inspection results to
Ms. T. Smith, Radiation Protection Manager, and other members of the licensee staff.
On April 26, 2018, the inspectors presented the quarterly resident inspector inspection
results to Mr. Christopher Domingos, Site Director, and other members of the licensee staff.
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DOCUMENTS REVIEWED
71111.15 - Operability Determinations and Functionality Assessments
Condition Reports (*initiated in response to inspection)
Engineering Evaluations
FP101201, Evaluation of Seismic Category I Electrical Manholes - Stage 1, Revision 0
FP101202, ASR Inspections of Electrical Manholes W01, W02, W09 and W13 through W16,
Revision 0
Miscellaneous
SD-66, Structural Design Criteria, Revision 2
71152 - Problem Identification and Resolution
Condition Reports (*initiated in response to inspection)
01664399
02014325
02193235
02210951
02215578
02240426
02227250
Engineering Evaluations
FP101193, Evaluation of Containment Enclosure Ventilation Area (CEVA) Bowing, Revision 0
Miscellaneous
Extensometer Data of through Thickness Expansions, dated March 19, 2018
FP101203, 2017 Tier 2 Inspections - ASR Inspections and Cracking Index Measurements on
Concrete Structures, Revision 0
FP101204, 2017 Tier 2 Inspections - Measurements for ASR Expansion on Concrete
Structures, Revision 0
Structures Monitoring Program Manual, Revision 4