ML19316D041
| ML19316D041 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/12/2019 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Dent J Nebraska Public Power District (NPPD) |
| References | |
| IR 2020010 | |
| Download: ML19316D041 (7) | |
See also: IR 05000298/2020010
Text
November 12, 2019
Mr. John Dent, Jr.
Vice President-Nuclear and CNO
Nebraska Public Power District
Cooper Nuclear Station
72676 648A Avenue
P.O. Box 98
Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - NOTIFICATION OF NRC DESIGN BASES
ASSURANCE INSPECTION (PROGRAMS) (05000298/202010) AND INITIAL
REQUEST FOR INFORMATION
Dear Mr. Dent:
On January 27, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Cooper Nuclear 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 Cooper
Nuclear 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: December 16-20, 2019
Preparation Weeks: January 13-17, 2020, and February 3-7, 2020
Onsite Weeks: January 27-31, 2020, and February 10-14, 2020
J. Dent, Jr.
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 Cooper Nuclear 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 December 16-20, 2019, 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 week 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 Ronald A. Kopriva. We understand that our licensing
engineer contact for this inspection is Mr. Thomas Forland. If there are any questions about
the inspection or the requested materials, please contact the lead inspector by telephone
at 817-200-1104 or by e-mail at Ron.Kopriva@nrc.gov.
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget, control
number 3150-0011. The NRC may not conduct or 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 Office of Management and Budget control
number.
J. Dent, Jr.
3
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice and Procedure," a copy of
this letter will be made available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-000298
License No. DPR-46
Enclosure:
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Request for Information
cc w/ encl: Distribution via LISTSERV
Enclosure
Initial Request for Information
Design Bases Inspection (Programs), Power-Operated Valves
COOPER NUCLEAR STATION
Inspection Report: 05000298/202010
Information Gathering Dates:
December 16-20, 2019
Inspection Dates:
January 27-31, 2020, and February 10-14, 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:
Ronald A. Kopriva, Senior Reactor Inspector
I.
Information Requested for Information Gathering Visit (December, 2019)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of Ronald Kopriva by December 10, 2019, 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 boiling 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. Fill out the characteristics in the attached Excel spreadsheet containing
30 valves. The valve characteristics are in the blanks on the assorted fields of
the attached Excel spreadsheet. It is possible that not all fields can be completed,
for those fields that cannot be filled, there is no additional action requested by
Cooper Nuclear Station.
2. List of power-operated valves (POVs) important to safety for the Cooper Nuclear
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 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 component.
2
3. Listing of the POVs sorted by risk importance, including external risk considerations.
4. Cooper Nuclear 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 Cooper Nuclear 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 Cooper Nuclear 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 Cooper Nuclear Station representative to discuss site POV capability
analyses, including plant drawings and assumptions. This includes analysis for
accident conditions.
2. Interview with a Cooper Nuclear Station representative to discuss POV maintenance
elements as integrated into plant programs and procedures.
3. Interview with a Cooper Nuclear 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 (January 20, 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 January 13, 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:
Ronald A. Kopriva
Senior Reactor Inspector
817-200-1104
Ron.Kopriva@nrc.gov
Reactor Inspector
817-200-1563
Wes.Cullum@nrc.gov
Reactor Inspector
630-829-9745
Michael.Jones@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Ronald Kopriva
1600 East Lamar Blvd.
Arlington, TX 76011-4511
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002
By: RAK Yes No
Publicly Available Sensitive
OFFICE
SRI:EB1
C:EB1
NAME
RKopriva
VGaddy
SIGNATURE
/RA/
/RA/
DATE
11/12/19
11/12/19