IR 05000368/2019016
| ML20101P354 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (NPF-006) |
| Issue date: | 04/11/2020 |
| From: | Nick Taylor NRC/RGN-IV/DRS/EB-2 |
| To: | Dinelli J Entergy Operations |
| References | |
| EPID I-2019-016-0000 IR 2019016 | |
| Download: ML20101P354 (10) | |
Text
April 11, 2020
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 - NRC POST-APPROVAL LICENSE RENEWAL INSPECTION REPORT 05000368/2019016
Dear Mr. Dinelli:
On March 20, 2020, U.S. Nuclear Regulatory Commission (NRC) inspectors completed an in-office inspection for Arkansas Nuclear One, Unit 2. The enclosed report documents the inspection results, which were discussed with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-368 License No. NPF-6
Enclosure:
As stated
Inspection Report
Docket Number:
05000368
License Number:
Report Number:
Enterprise Identifier
I-2019-016-0000
Licensee:
Entergy Operations, Inc.
Facility:
Arkansas Nuclear One, Unit 2
Location:
Russellville, AR
Inspection Dates:
December 1, 2019 through March 20, 2020
Inspectors:
I. Anchondo, Reactor Inspector
G. Pick, Senior Reactor Inspector (Lead)
Approved By:
Nicholas H. Taylor, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
IR 05000368/2019016; 12/01/2019 - 03/20/2020; Arkansas Nuclear One, Unit 2; In-Office
Post-Approval Site Inspection for License Renewal
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting a license renewal commitment evaluation for Arkansas Nuclear
One, Unit 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
None.
4.
OTHER ACTIVITIES (OA)
4OA5 Phase 3 Inspection Activities (IP 71003)
Phase 3 Inspection activities are performed after the licensee enters the period of
extended operation. The period of extended operation is the additional 20 years beyond
the original 40-year licensed term. Arkansas Nuclear One, Unit 2, began the period of
extended operation on July 18, 2018.
The inspectors performed this inspection to evaluate whether the licensee completed
outstanding actions required to comply with the license renewal license condition and
commitments and effectively implemented outstanding actions related to aging
management programs.
The inspectors closed Commitments 39, 41, and 42 during this inspection.
a.
Inspection Scope
During this in-office inspection, the inspectors evaluated the licensee actions related to
commitments not closed during the Phase 2 license renewal inspection (Inspection
Report 05000368/2018010 (ML18221A507)).
The inspectors reviewed program documents, design calculations, inspection results,
engineering reports, and corrective action documents. The inspectors interviewed
licensee personnel, including the program owners, and design engineers during several
teleconferences to discuss the technical resolution related to the commitments. In
addition, headquarters personnel assisted in the technical review of these commitments.
b.
Observations
1. Implement the Environmentally Assisted Fatigue Option (Section 4.3.3.1) (17940) -
Commitment 39
This program managed aging effects related to environmentally assisted fatigue. Prior
to entering the period of extended operation, the safety evaluation report required the
licensee to address the effects of environmentally assisted fatigue for several fatigue-
sensitive locations, which included:
- Reactor vessel shell and lower head
Reactor vessel inlet and outlet nozzles
Surge line
Charging nozzle
Safety injection nozzle
Shutdown cooling system Class 1 piping
During the previous inspection, the inspectors determined that the licensee had elected
to perform the inspection option as allowed by their safety analysis report,
Section 4.3.3.1. The licensee identified two locations that would be inspected in
accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel
Code (ASME),Section XI, Appendix L, Operating Plant Fatigue Assessment, and
submitted the fatigue assessment results to the NRC for review. The licensee had
preliminarily calculated that the cumulative usage factor for the other monitored locations
remained less than one (1.0) and did not require inspection. Since the calculations were
not available for review at the time of this inspection, this commitment remained open.
During this inspection, the inspectors reviewed information related to assessing
environmentally assisted fatigue for the affected components. The licensee had
submitted the fatigue assessment inspection methodology and results by
Letter 2CAN051801, License Renewal Pressurizer Surge Line and Safety Injection
Nozzle Inspection Arkansas Nuclear One, Unit 2, dated May 24, 2018 (ML18144A970).
The licensee assessed that a postulated flaw would take more than 50 years to reach an
unacceptable size; therefore, the planned 10-year inspection intervals provided
appropriate condition monitoring. After review of the information in the letter, NRC
issued a safety evaluation report on April 5, 2019 (ML19074A028), which concluded the
licensee met their commitment and established an appropriate scope, method, and
frequency of inspecting for environmentally assisted fatigue.
The inspectors reviewed the inspection results for the affected welds, which identified
that the welds contained no flaws. The inspectors reviewed the detailed fatigue
calculations referenced in Letter 2CAN051801. Overall, the inspectors determined that
the licensee had performed the calculations using an appropriate methodology. The
inspectors determined, after consulting with NRC headquarters, the licensee had not
used factors in their calculation that reflected the changes to our current state of
knowledge since they had originally performed their assessment. Following questioning,
the licensee demonstrated that, even after adjusting the calculation based on our current
state of knowledge, they provided adequate conservatism in their calculation. The
licensee demonstrated that a postulated flaw would not result in failure in less than
30 years, but inspected the affected components every 10 years.
Other than the item described above, the inspectors identified no additional concerns
with implementation of this commitment.
2. B.1.30 Chemistry Control Programs (17937, 17938, and 17939) - Commitment 41
These chemistry programs managed the effects of aging caused by fouling, cracking,
and loss of material. The primary water chemistry program controlled chemistry for the
reactor coolant system, including primary side of the steam generators and the
emergency core cooling systems, spent fuel pool system, and the chemical and volume
control system. The secondary water chemistry program controlled chemistry in the
main feedwater system, emergency feedwater system, main steam system, condensate
storage system, and steam generators.
Commitment 41 specified:
The chemistry procedure and engineering report will be revised to
address loss of the passive layer if chemistry limits are out of specification
for an extended period.
Although the inspectors had reviewed overall implementation of the primary and
secondary water chemistry programs, the inspectors had not reviewed the details
associated with the above commitment.
During this inspection, the inspectors reviewed the engineering report and the chemistry
procedure and discussed the revisions with the program owner. The inspectors
confirmed that the licensee established requirements to address loss of the passive
layer whenever chemistry limits are found out of specification.
The inspectors identified no concerns with implementation of this commitment.
3. B.1.18 Periodic Surveillance and Preventive Maintenance Program (17925) -
Commitment 42
This program managed aging effects related to change in material properties, cracking,
heat exchanger fouling, loss of material, and loss of form. The license identified specific
components included in this program because the other aging management programs
did not monitor for the identified effects.
Commitment 42 specified:
The Periodic Surveillance and Preventive Maintenance Program will be
revised to include an inspection of the alternate AC diesel generator
starting air tank.
Although the inspectors had reviewed overall implementation of the periodic surveillance
and preventive maintenance program, the inspectors had not reviewed the details
associated with the above commitment.
During this inspection, the inspectors verified that the licensee established a
periodic task to inspect that interior of the alternate AC diesel generator starting
air tank. The inspectors confirmed that the licensee identified no adverse aging
effects in the alternate AC diesel generator starting air tanks.
The inspectors identified no concerns with implementation of this commitment.
c.
Conclusion
Based on review of the actions implemented, inspection results reviewed, and interviews
with program owners, the inspectors determined that the licensee provided reasonable
assurance and demonstrated that they had implemented actions to effectively manage
the effects of aging for each respective program. The inspectors determined that the
licensee met the commitments.
4OA6 Meetings, Including Exit
The inspector presented the inspection results on March 20, 2020, to Mr. J. Dinelli, Site
Vice President, and other members of the licensee staff. The licensee acknowledged
the NRC inspection observations. The inspector retained no proprietary information and
verified that no proprietary information was documented in this report.
A-1
Attachment
SUPPLEMENTAL INFORMATION
COMMITMENTS
The inspectors reviewed chemistry control programs, in part, related to Commitments 17937,
17938, and 17939, and reviewed the periodic surveillance and preventive maintenance
program, in part, related to Commitment 17925. As a result of the reviews, the inspectors
closed Appendix A to NUREG-1828, Safety Evaluation Report Related to the License Renewal
of Arkansas Nuclear One, Unit 2, items 41 and 42 in this inspection report.
In addition, the inspectors closed Commitment 17940 and related Appendix A to NUREG-1828,
item 39.
Commitments previously closed include:
NRC closed Commitments 17908, 17909, 17914, and 17939 in Inspection Report 05000368/2017009, which included NUREG-1828, Appendix A items 6 and 28.
NRC closed the following commitments in Inspection Report 05000368/2018010:
17905, 17910, 17911, 17912, 17913, 17915, 17916, 17917, 17918, 17919, 17920, 17921,
17922, 17923, 17924, 17925, 17926, 17927, 17928, 17929, 17930, 17931, 17932, 17933,
17934, 17935, 17936, 17937, 17938, 18175, 18207, and 20017.
During review of these commitments the inspectors confirmed that the licensee had met the
conditions prescribed in NUREG-1828, Appendix A, Items 1, 2, 3, 4, 5, 7, 8, 9,10, 11, 12,
13, 14, 15, 16, 17, 18, 19, 20, 21, 22, 23, 24, 25, 26, 27, 29, 30, 31, 32, 33, 34, 35, 36, 37,
38, and 40.
DOCUMENTS REVIEWED
1. Implement the Environmentally Assisted Fatigue Option (Section 4.3.3.1) (17940) -
Commitment 39
Condition Reports (CR-ANO-2-)
2020-00106*
- This condition report was issued as a result of this inspection.
Calculations
Number
Title
Revision/Date
CALC-17-E-0300-06
Arkansas Nuclear One - Unit 2 Pressurizer
Surge Line 60-YR Fatigue Assessment
CALC-17-E-0300-08
Arkansas Nuclear One - Unit 2 Safety
Injection Nozzle 60-YR Fatigue Assessment
A-2
Examinations
Number
Report Number
Date
2R23 16-011
2-ISI-UT-14-016, Component 16-011
05/21/2014
2R23 16-012
2-ISI-UT-14-015, Component 16-012
05/21/2014
2R23 21-001
2-ISI-VE-14-017, Component 21-001
05/30/2014
2R23 22-001
2-ISI-VE-14-015, Component 22-001
05/31/2014
2R23 23-001
2-ISI-VE-14-018, Component 23-001
05/30/2014
2R23 24-001
2-ISI-VE-14-016, Component 24-001
05/31/2014
Miscellaneous Documents
Number
Title
Revision/Date
Basis for ASME Section XI Code Case for
Flaw Tolerance Evaluation of CASS Piping
Arkansas Nuclear One, Unit 2 - Review of
License Renewal Commitment Submittal
Regarding Environmentally-Assisted Fatigue
04/05/2019
Case N-809
Reference Fatigue Crack Growth Rate Curves
for Austenitic Stainless Steels in Pressurized
Water Reactor Environments,Section XI,
Division 1
06/23/2015
Case N-838
Flaw Tolerance Evaluation of Cast Austenitic
Stainless Steel Piping,Section XI, Division 1
08/03/2015
Letter 2CAN051801
License Renewal Pressurizer Surge Line and
Safety Injection Nozzle Inspection
05/24/2018
Application of NUREG/CR-5999 Interim
Fatigue Curves to Selected Nuclear Power
Plant Components
02/1995
PVP2015-45191
Further Validation of the Technical Basis of
Code Case N-838 for Flaw Tolerance
Evaluation of CASS Piping
PVP2017-66100
Technical Basis for Flaw Acceptance Criteria
for Cast Austenitic Stainless Steel Piping
A-3
2. B.1.30 Chemistry Control Programs (17937, 17938, and 17939) - Commitment 41
Condition Reports (CR-ANO-2-)
2017-04159
2018-00914
2018-03639
2019-02859
Miscellaneous Documents
Number
Title
Revision/Date
A2-EP-2002-002 2
ANO-2 License Renewal Project Evaluation
of Aging Management Programs,
Section 4.18.1 Primary and Secondary
Water Chemistry Control Program
Letter 2CAN120403
License Renewal Application Draft Safety
Evaluation Report Comments
12/09/2004
Procedure EN-CY-100 Conduct of Chemistry
3. B.1.18 Periodic Surveillance and Preventive Maintenance Program (17925) -
Commitment 42
Miscellaneous Documents
Number
Title
Date
Letter 2CAN120403
License Renewal Application Draft Safety Evaluation
Report Comments
12/09/2004
Work Orders
00469663
00469664