ML20085F828
| ML20085F828 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/31/2020 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Dinelli J Entergy Operations |
| References | |
| IR 2020011 | |
| Download: ML20085F828 (9) | |
See also: IR 05000313/2020011
Text
March 31, 2020
Mr. John Dinelli, Site Vice President
Arkansas Nuclear One
Entergy Operations, Inc.
N-TSB-58
1448 S.R. 333
Russellville, AR 72802-0967
SUBJECT:
ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS)
(05000313/2020011, 05000368/2020011) AND INITIAL REQUEST FOR
INFORMATION
Dear Mr. Dinelli:
On May 20, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Arkansas Nuclear One, Units 1 and 2. A three-person team will perform this
inspection using NRC Inspection Procedure 71111.21N.02, Design Bases Inspection
(Programs), Attachment 2, Design-Basis Capability of Power-Operated Valves Under 10 CFR
50.55a Requirements.
This inspection will evaluate the reliability, functional capability, and design basis of risk-
significant power-operated valves as required by 10 CFR 50.55a and applicable
10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Arkansas
Nuclear One Operating License. Additionally, the team will perform an inspection of
the documentation files to verify that the plant activities associated with safety-related
motor-operated valves meet your commitments to Generic Letter (GL) 89-10, Safety-Related
Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic Verification of
Design-Basis Capability of Safety-Related Motor-Operated Valves." In conducting this
inspection, the team will select power-operated valves used to prevent and mitigate the
consequences of a design basis accident.
The inspection will include an information gathering site visit by the team leader and 2 weeks of
onsite inspection by the team. The inspection will consist of three NRC inspectors. The current
inspection schedule is as follows:
Onsite Information Gathering Visit: May 20, 2020 (Tentative)
Preparation Week: June 1-5, 2020
Onsite Weeks: June 8-12, 2020, and June 22-26, 2020
J. Dinelli
2
The purpose of the information gathering visit is to meet with members of your staff to become
familiar with the power-operated valve activities at Arkansas Nuclear One. The lead inspector
will request a meeting with your personnel to discuss the site power-operated valve procedures.
Additionally, the lead inspector will request a discussion with your staff to become familiar with
the regulations and standards applicable to power-operated valves at the site. Additional
information and documentation needed to support the inspection will be identified during the
inspection, including interviews with engineering managers and engineers.
In order to minimize the inspection impact on the site and to ensure a productive inspection, we
have enclosed a request for information needed prior to the inspection. This information should
be made available to the lead inspector prior to the May 20, 2020, visit. Since the inspection will
be concentrated on safety-related and risk-significant power-operated valves, a list of such
power-operated valves should be available to review during and following the information
gathering visit to assist in our selection of appropriate power-operated valves to review.
Additional requests by inspectors will be made during the onsite weeks for specific documents
needed to complete the review of specific power-operated valves and associated activities. It is
important that all documentation is up-to-date and complete in order to minimize the number of
additional documents requested during the preparation and/or the onsite portions of the
inspection. In order to facilitate the inspection, we request that a contact individual be assigned
to each inspector to ensure information requests, questions, and concerns are addressed in a
timely manner.
The lead inspector for this inspection is Gerond George. We understand that our licensing
engineer contact for this inspection is Ms. N. Mosher. If there are any questions about
the inspection or the requested materials, please contact the lead inspector by telephone
at 817-200-1562 or by e-mail at Gerond.George@nrc.gov.
PAPERWORK REDUCTION ACT STATEMENT
This letter contains mandatory information collections that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
approved these information collections (approval number 3150-0011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Budget, Washington, DC 20503.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request
for information or an information collection requirement unless the requesting document
displays a currently valid OMB control number.
J. Dinelli
3
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/
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-313 and 50-368
Enclosure:
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Request for Information
Arkansas Nuclear One Valves of Interest
cc w/ encl: Distribution via LISTSERV
SUNSI Review
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By:
GAG
Yes No
Publicly Available
Sensitive
OFFICE
R4/DRS/EB1
DRS/EB1
NAME
GGeorge
VGaddy
SIGNATURE
/RA/
/RA/
DATE
03/31/20
03/31/20
Enclosure
Initial Request for Information
Design Bases Inspection (Programs), Power-Operated Valves
ARKANSAS NUCLEAR ONE
Inspection Report: 05000313/2020011 AND 05000368/2020011
EPID Number:
I-2020-011-0015
Information Gathering Dates:
May 20, 2020
Onsite Inspection Dates:
June 8-12, 2020, and June 22-26, 2020
Inspection Procedure:
IP 71111, Attachment 21N.02, Design Bases Assurance
Inspection (Programs) Attachment 2, Design-Basis
Capability of Power-Operated Valves Under
10 CFR 50.55a Requirements
Lead Inspector:
Gerond A. George, Senior Reactor Inspector
I.
Information Requested for Information Gathering Visit (due May 13, 2020)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of the lead inspector by May 13, 2020, to facilitate the
reduction in the items to be selected for a final list of components. The inspection team
will finalize the selected list during the prep week using the documents requested in this
enclosure. The specific items selected from the lists shall be available and ready for
review on the day indicated in this request. *Please provide requested documentation
electronically in pdf files, Excel, or other searchable formats, if possible. The
information should contain descriptive names and be indexed and hyperlinked to
facilitate ease of use. Information in "lists" should contain enough information to be
easily understood by someone who has knowledge of pressurized water reactor
technology. If requested documents are large and only hard copy formats are available,
please inform the inspectors, and provide subject documentation during the first day of
the onsite inspection.
1. Provide the valve characteristics for the valves listed in the attached list as described
in Appendix C of NRC Inspection Procedure 71111.21N.02, Design Bases
Inspection (Programs), Attachment 2, Design-Basis Capability of Power-Operated
Valves Under 10 CFR 50.55a Requirements.
2. List of power-operated valves (POVs) important to safety for the Arkansas Nuclear
One. The list should include (a) component identification number; (b) applicable
plant system; (c) ASME Boiler and Pressure Vessel Code (BPV Code) Class;
(d) safety-related or nonsafety-related classification; (e) valve type, size and
manufacturer; and (f) actuator type, size, and manufacturer. If the NRC has granted
a license amendment to categorize structures, systems, and component in
accordance with 10 CFR 50.69, please provide the risk-informed safety category of
the structure, system, or component.
2
3. Listing of the POVs sorted by risk importance, including external risk considerations.
4. Word-searchable updated final safety analysis report (UFSAR), License Conditions,
Technical Specifications, and most recent Inservice Testing (IST) program plan.
Specifically identify which UFSAR sections address environmental, seismic, and
functional qualification of POVs.
5. NRC Safety Evaluation Report(s) associated with the IST program including relief
and alternative requests submitted in accordance with 10 CFR 50.55a for POVs.
6. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
(OM Code) that is the OM Code of record for the current 10-year IST Program
interval, as well as any standards to which has been committed with respect to POV
capability and testing.
7. List of systems, system numbers/designators and corresponding names.
8. List of site contacts that will be associated with the inspection.
II.
Discussions Requested During the Information Gathering Visit (May 20, 2020)
1. Interview with a representative to discuss site POV capability analyses, including
plant drawings and assumptions. This includes analysis for accident conditions.
2. Interview with a representative to discuss POV maintenance elements as integrated
into plant programs and procedures.
3. Interview with a representative to discuss maintaining the design-basis capability of
POVs if they have entered a period of extended operation, if applicable.
III.
Information Requested for Inspection Preparation (June 1, 2020)
1. Documentation files, including test reports, for the electrical and mechanical
components associated with the POVs selected by the lead inspector (10 specific
valves will be identified and communicated to you prior to June 1, 2020).
2. References associated with the electrical and mechanical components document
files.
3. Vendor manuals and technical sheets associated with the selected POVs.
4. Tours of the rooms in which the selected POVs are installed.
3
Inspector Contact Information:
Gerond A. George
Senior Reactor Inspector
817-200-1562
Gerond.George@nrc.gov
Reactor Inspector
817-200-1469
Jonathan.Braisted@nrc.gov
Reactor Inspector
817-200-1534
Dustin.Reinert@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Gerond A. George
1600 East Lamar Blvd.
Arlington, TX 76011-4511
2
Arkansas Nuclear One Valves of Interest
No. ACT
Valve
Size
Valve
Type
System Name
Utility ID
1.
MOV 4
Gate
"A" DH Loop Disch to MU Pump 36A
Suction
CV-1276
2.
MOV 4
Gate
"B" DH Loop Disch to MU Pump 36C
Suction
CV-1277
3.
MOV 12
Gate
RCS Suction MOV CV-1404 To LPI
CV-1404
4.
MOV 14
Gate
LPI Suction MOV CV-1407 From BWST
(a Suction HDR)
CV-1407
5.
6
Butterfly
Decay Heat Cooler E-35B Bypass
CV-1432
6.
4
Globe
Control AOV 2646 To SG A (from MDP)
CV-2646
7.
CV-2660A
8.
36
Globe
Main Steam Isolation Valve CV-2691
CV-2691
9.
MOV 18
Butterfly
B Discharge to Loop II SW
CV-3640
10.
MOV 18
Butterfly
CV-3646
11.
MOV 6
Gate
SWS Supply MOV CV-3806 To DGN 1
Cooling
CV-3806
12.
MOV 14
Butterfly
SERVICE WATER SYSTEM
CV-3811
13.
MOV 18
Butterfly
SW Return to Discharge Flume
CV-3824
14.
1.5
Globe
CV-3840
15.
2
Gate
RB Coolers VCC-2A/B SW Fill Bypass
SV-3812
16.
MOV 4
Gate
Steam Supply MOV 2CV-0340-2
17.
MOV 4
Gate
EFW TDP Disch Line MOV 2CV-1026-2
To SG A
18.
MOV 4
Gate
EFW TDP Disch Line MOV 2CV-1037-1
To SG A
19.
MOV 4
Gate
EFW TDP Disch Line MOV 2CV-1039-1
To SG B
20.
21.
MOV 42
Gate
SERVICE WATER SYSTEM
22.
MOV 14
Gate
LPI/sdc Suct Line MOV 2CV-5084-1
From RCS Hot Leg 2
23.
4
Gate
24.
MOV 4
Gate
HIGH PRESSURE SAFETY INJECTION
25.
MOV 20
Gate
Reactor Building Spray MOV 2CV5631-2 2CV-5631-2
3
No. ACT
Valve
Size
Valve
Type
System Name
Utility ID
26.
MOV 24
Gate
HPI Train A Outbd Sump Isol MOV 2CV-
5649-1
27.
MOV 24
Gate
HPI Train A Outbd Sump Isol MOV 2CV-
5650-2
28.
29.
Bearing Oil Cooling AOV SV-0317
30.
2
Diaphragm FUEL OIL SYSTEM