ML20024D707
| ML20024D707 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/24/2020 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Reasoner C Wolf Creek |
| Gaddy V | |
| References | |
| IR 2020011 | |
| Download: ML20024D707 (9) | |
See also: IR 05000482/2020011
Text
January 24, 2020
Mr. Cleve Reasoner, Chief Executive Officer
and Chief Nuclear Officer
Wolf Creek Nuclear Operating Corp.
P.O. Box 411
Burlington, KS 66839
SUBJECT: WOLF CREEK GENERATING STATION - NOTIFICATION OF NRC DESIGN
BASES ASSURANCE INSPECTION (PROGRAMS) (05000482/2020011) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Reasoner:
On April 6, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Wolf Creek Generating Station. 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-
important 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 Wolf Creek
Generating Station 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: February 24-26, 2020
Preparation Weeks: March 30 - April 3, 2020, and April 13-17, 2020
Onsite Weeks: April 6-10, 2020, and April 20-24, 2020
C. Reasoner 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 the Wolf Creek Generating Station. 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 for the inspection. This information should be
made available to the lead inspector during the March 16-17, 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.
It is requested that this information be provided to the lead inspector as the information is
generated during the inspection. 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 of these documents are 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 Wayne C. Sifre. We understand that our licensing
engineer contact for this inspection is Mr. Jason Knust. If there are any questions about
the inspection or the requested materials, please contact the lead inspector by telephone
at 817-200-1193 or by e-mail at Wayne.Sifre@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.
The burden to the public for these voluntary information collections is estimated to average
2,250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per examination including the time for reviewing instructions, searching existing
data sources, gathering and maintaining the data needed, and completing and reviewing the
information collection. You may submit comments on any aspect of the information collection,
including suggestions for reducing the burden, to the FOIA, Privacy and Information Collections
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by
electronic mail to INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of
Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and
Budget, Washington, DC 20503.
C. Reasoner 3
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.
This letter 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: 50-482
License: NPF-42
Enclosure:
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Initial Request for Information
w/Attachment: Wolf Creek Valves of Interest
cc w/ encl: Distribution via LISTSERV
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: WCS Yes No Publicly Available Sensitive NRC-002
OFFICE SRI:EB1 C:EB1
NAME WSifre VGaddy
SIGNATURE /RA/ /RA/
DATE 1/23/2020 1/24/2020
Initial Request for Information
Design Bases Assurance Inspection (Programs), Power-Operated Valves
WOLF CREEK GENERATING STATION
Inspection Report: 05000482/2020011
Information Gathering Dates: March 17-18, 2020
Inspection Dates: April 6-10, 2020, and April 20-24, 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: Wayne C. Sifre, Senior Reactor Inspector
I. Information Requested for Information Gathering Visit (February 24, 2020)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of Wayne Sifre by February 18, 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 Wolf Creek
Generating Station. 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 non-safety 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 component.
3. Listing of the POVs sorted by risk importance, including external risk considerations.
Enclosure
4. Wolf Creek Generating Station 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 Wolf Creek Generating Station
IST program and 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 Code of Record for the current 10-year IST Program interval,
as well as any standards to which the Wolf Creek Generating Station has 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
1. Interview with a Wolf Creek Generating Station representative to discuss site POV
capability analyses, including plant drawings and assumptions. This includes
analysis for accident conditions.
2. Interview with a Wolf Creek Generating Station representative to discuss POV
maintenance elements as integrated into plant programs and procedures.
3. Interview with a Wolf Creek Generating Station 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 (March 30, 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 March 23, 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.
2
Inspector Contact Information:
Wayne C. Sifre Dustin Reinert Fabian Thomas
Senior Reactor Inspector Reactor Inspector Reactor Inspector
817-200-1193 817-200-1534 817-200-1126
Wayne.Sifre@nrc.gov Dustin.Reinert@nrc.gov Fabian.Thomas@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4
3
Wolf Creek Valves of Interest
No. ACT Valve Valve System Name Utility ID Selection Basis
Size Type
1. MOV 4 Globe Auxiliary ALHV0009 Core Damage
Feedwater System Frequency Contributor
2. MOV 4 Globe Auxiliary ALHV0011 Core Damage
Feedwater System Frequency Contributor
3. MOV 4 Globe Auxiliary ALHV0005 Core Damage
Feedwater System Frequency Contributor
4. MOV 4 Globe Auxiliary ALHV0007 Core Damage
Feedwater System Frequency Contributor
5. MOV 8" Gate Auxiliary ALHV0036 Core Damage
Feedwater System Frequency Contributor
6. MOV 18" Butterfly Component EGHV0101 Risk Significant -
Cooling Water Reason not
System determined
7. MOV 18" Butterfly Component EGHV0102 Risk Significant -
Cooling Water Reason not
System determined
8. MOV 3" Gate Chemical and EMHV8803A Core Damage
Volume Control Frequency Contributor
System
9. MOV 3" Gate Essential Service EFHV0091 Core Damage
Water Frequency Contributor
10. MOV 3" Gate Essential Service EFHV0092 Core Damage
Water Frequency Contributor
11. MOV 8" Gate Residual Heat EJHV8804A Core Damage
Removal System Frequency Contributor
12. MOV 8" Gate Residual Heat EJHV8804B Core Damage
Removal System Frequency Contributor
13. MOV 3" Gate Reactor Coolant BBHV8000B Core Damage
System Frequency Contributor
14. MOV 3" Gate Reactor Coolant BBHV8000A Core Damage
System Frequency Contributor
15. MOV 14 Gate Residual Heat BNHV8812A Core Damage
Removal System Frequency Contributor
16. MOV 14 Gate Residual Heat BNHV8812B Core Damage
Removal System Frequency Contributor
17. MOV 14" Gate Residual Heat EJHV8811A Core Damage
Removal System Frequency Contributor
18. MOV 14" Gate Residual Heat EJHV8811B Core Damage
Removal System Frequency Contributor
19. SOV 3" Globe Reactor Coolant BBPCV0456A Core Damage
System Frequency Contributor
20. SOV 3" Globe Chemical and BGHV8160 Expert Panel
Volume Control Recommendation
System
21. HOV 14" Gate Feedwater System AEFV0040 Expert Panel
Recommendation
Attachment
No. ACT Valve Valve System Name Utility ID Selection Basis
Size Type
22. HOV 14" Gate Feedwater System AEFV0042 Expert Panel
Recommendation
23. HOV 28 Gate Main Steam ABV0014 LERF Contributor
24. HOV 28 Gate Main Steam ABV0020 LERF Contributor
25. MOV 4" Gate Auxiliary FCHV0312 Core Damage
Feedwater System Frequency Contributor
26. MOV 6" Butterfly Auxiliary ALHV0031 Core Damage
Feedwater System Frequency Contributor
27. AOV 8" Globe Main Steam ABPV0001 Expert Panel
System Recommendation
28. AOV 8" Globe Main Steam ABPV0002 Expert Panel
System Recommendation
29. MOV 4 Gate High Pressure EMHV8821B Expert Panel
Coolant Injection Recommendation
30. MOV 30 Butterfly Essential Service EFHV0025 Expert Panel
Water Recommendation
2