ML21089A156
| ML21089A156 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/30/2021 |
| From: | Jorge Corujo-Sandin NRC/RGN-III/DRS/EB2 |
| To: | Gebbie J Indiana Michigan Power Co |
| References | |
| IR 2021011 | |
| Download: ML21089A156 (10) | |
See also: IR 05000315/2021011
Text
March 30, 2021
Mr. Joel P. Gebbie
Senior VP and Chief Nuclear Officer
Indiana Michigan Power Company
Nuclear Generation Group
One Cook Place
Bridgman, MI 49106
SUBJECT: DONALD C. COOK NUCLEAR PLANT - NOTIFICATION OF NRC DESIGN
BASES ASSURANCE INSPECTION (PROGRAMS) AND INITIAL REQUEST FOR
INFORMATION: INSPECTION REPORT 05000315/2021011; 05000316/2021011
Dear Mr. Gebbie:
On August 9, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin a baseline
Design Bases Assurance Inspection (Programs) at Donald C. Cook Nuclear Plant. This
inspection will be performed in accordance with NRC Baseline Inspection Procedure 71111.21N, Design Bases Assurance 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 (POVs) as required by 10 CFR 50.55a and applicable
10 CFR Part 50, Appendix A and Appendix B, requirements. In conducting this inspection, the
team will select risk-important POVs used to prevent and mitigate the consequences of a design
basis accident.
The inspection will include two weeks of onsite inspection. The inspection team will consist of
three NRC inspectors. The current inspection schedule is as follows:
- Preparation week: August 2 - 6, 2021
- Onsite weeks: August 9 - 13, 2021, and August 23 - 27, 2021
Experience with previous baseline engineering inspections of similar depth and length has
shown this type of inspection is extremely resource intensive, both for the NRC inspectors and
the licensee staff. In order to minimize the inspection impact on the site and to ensure a
productive inspection for both parties, we have enclosed a request for information needed for
the inspection. 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. Insofar as possible, this information should be provided
electronically to the lead inspector. The information request has been divided into four groups:
J. Gebbie -2-
- The first group lists information necessary for our initial risk-informed scoping activities.
This information should be provided to the lead inspector no later than April 16, 2021.
- The second group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than June 4, 2021. By
June 28, 2021, the lead inspector will communicate the initial selected samples and any
additional information needed to support the in-office preparation activities.
- The third group of documents requested are those items needed to support our in-office
preparation activities. This set of documents should be provided to the lead inspector no
later than July 23, 2021. During the preparation activities, the team may identify
additional information needed to support the inspection.
- The fourth group includes the additional information above as well as plant-specific
reference material. This information should be available to the team onsite on
August 9, 2021. It is also requested that corrective action documents and answers to
questions developed during the inspection be provided to the lead inspector as the
documents are generated.
In addition, the enclosure includes information and requests addressing inspection logistics.
These items are requested be provided to the lead inspector by July 16, 2021.
The lead inspector for this inspection is Jorge Corujo-Sandin. We understand that our licensing
contact for this inspection is Mr. M. Ellet of your organization. If there are any questions about
the inspection or the material requested in the enclosure, contact the lead inspector at
630-829-9741 or via e-mail at Jorge.Corujo-Sandin@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. Gebbie -3-
This letter and its enclosure 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/
Jorge Corujo-Sandin, Senior Reactor Inspector
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-315 and 50-316
License Nos. DPR-58 and DPR-74
Enclosure:
Design Bases Assurance Inspection
(Programs)Document Request
cc: Distribution via LISTSERV
J. Gebbie -4-
Letter to Joel P. Gebbie from Jorge Corujo-Sandin dated March 30, 2021.
SUBJECT: DONALD C. COOK NUCLEAR PLANT - NOTIFICATION OF NRC DESIGN
BASES ASSURANCE INSPECTION (PROGRAMS) AND INITIAL REQUEST FOR
INFORMATION: INSPECTION REPORT 05000315/2021011; 05000316/2021011
DISTRIBUTION:
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Kenneth OBrien
DRPIII
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ADAMS Accession Number: ML21089A156
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII RIII
NAME JHanna:mb JCorujo-Sandin
via e-mail via e-mail
DATE 03/30/2021 03/30/2021
OFFICIAL RECORD COPY
DESIGN BASES ASSURANCE INSPECTION - POV PROGRAM
REQUEST FOR INFORMATION
I. ADMINISTRATIVE INSPECTION INFORMATION
Inspection Report Number: 05000315/2021011; 05000316/2021011
Onsite Inspection Dates: August 9 - 13, 2021, and August 23 - 27, 2021
IP 71111.21N, Design Bases Assurance Inspection
Inspection Procedure: (Programs), Attachment 2, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a Requirements
Jorge Corujo-Sandin, Senior Reactor Inspector, RIII/DRS
Lead Inspector: 630-829-9741
Jorge.Corujo-Sandin@nrc.gov
Kevin Barclay, Reactor Inspector, RIII/DRS
Teammate Inspectors:
Michael Jones, Reactor Inspector, RIII/DRS
II. LOGISTICS
Email the following inspection logistics to the lead inspector by July 16, 2021, or sooner:
1. Inspection room name/number, directions from the main access facility, and phone number;
2. Interview room name/number;
3. Response team contact information (names and phone numbers) and team roles (e.g.,
management sponsor, lead, inspector counterpart);
4. Any site access/badging actions needed for each inspector;
5. Any dosimetry actions needed for each inspector;
6. Entrance meeting time and location;
7. Confirmation that the team will have access to a licensee computer with a nearby printer;
8. Confirmation that the team will have Wi-Fi access;
9. Cafeteria location and hours;
10. Inspection response team normal working hours; and
11. Any potential resource conflicts during the inspection (e.g., emergency drills and all-staff
meetings).
Enclosure
III. INFORMATION REQUEST
Contact the lead inspector as soon as possible if you have any questions regarding this
information request. Provide the information electronically in searchable formats, if possible.
The files 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 light water reactor technology.
Important Note: For the purpose of this inspection, POVs are valves with power actuators.
Examples include motor-operated valves (MOVs), air-operated valves (AOVs),
hydraulic-operated valves (HOVs), solenoid-operated valves (SOVs), and pyrotechnic-operated
valves (e.g., squib valves).
1. Information Requested to Support Risk Informed Selections
The following information is requested by April 16, 2021, or sooner, to facilitate the initial
sample selection.
1.1. List of systems, system numbers/designators, and corresponding system names.
1.2. Probabilistic safety analysis (PSA) system notebooks and latest PSA summary
document.
1.3. List of POVs from your site-specific PSA sorted by Risk-Achievement Worth (RAW).
Include values for Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley
(as applicable). The list should include (a) component identification number, including
noun name (i.e. descriptive name); (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. (Please provide in Excel.)
1.4. List of corrective action documents related to the POV programs for the last 5 years,
including the document identifier and brief description. Provide a separate list for each
POV program.
1.5. List of POVs in the Maintenance Rule (a)(1) category for the last 5 years. The list
should include a brief description of the surrounding circumstances.
2. Information Requested for Initial Inspection Scoping Activities
The following information is requested by June 4, 2021, or sooner, to facilitate the initial
sample selection.
2.1. NRC Safety Evaluation Report(s) associated with the In-Service Testing (IST) Program
and relief and alternative requests submitted in accordance with 10 CFR 50.55a for
POVs. 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 self-imposed standards related to the IST Program elements
applicable to POVs.
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2.2. IST Program documents, including implementing procedures, IST plan, and the
document that identifies the in-scope valves and the associated IST Program
requirements for each valve (e.g., IST valve table identifying category, active/passive
function).
2.3. Site (and corporate if applicable) procedures associated with implementation of the
POV programs required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory
Appendix III.
2.4. Joint Owners Group (JOG) MOV program classification evaluation.
2.5. List of any valve removed from a POV program and basis for removal.
2.6. Current list of operator workarounds.
2.7. List of open operability evaluations related to POVs.
2.8. List of permanent plant modifications to POVs completed in the last 5 years. For the
purpose of this inspection, permanent plant modifications include permanent: plant
changes, design changes, set point changes, equivalency evaluations, suitability
analyses, and commercial grade dedications. The list should contain the modification
identifier, title, revision/date, the affected system, completion date, and a brief
modification description.
2.9. Any self-assessment and/or audit of POV programs completed in the last 5 years.
2.10. Updated Final Safety Analysis Report (in one file), Technical Specifications, Technical
Specifications Bases, and Technical Requirements Manual.
2.11. The lead inspector will deliver forms to the licensee point of contact identified in the
letter for approximately 30 valves. Fill out the valve characteristics in the form fields. It
is possible that not all fields can be completed. For those fields that cannot be filled,
leave the fields blank.
2.12. Current management and engineering organizational chart.
3. Information Requested to Support Inspection Preparation Activities
The following information is requested by July 23, 2021, or sooner, to facilitate the final
inspection preparation.
3.1. All corrective action documents, evaluations, and NRC correspondence, including any
associated NRC requests for additional information (RAIs) and Safety Evaluation
Report(s), generated in response to the NRC communications listed below. Also, any
NRC inspection reports that were conducted to close out the sites associated
responses.
3.1.1. Generic Letter (GL) 89-10;
3.1.2. GL 96-05;
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3.1.3. GL 95-07;
3.1.4. Bulletin 85-03;
3.1.5. Regulatory Issue Summary (RIS) 2000-03; and
3.1.6. GL 88-14.
3.2. Any NRC correspondence regarding the stations POV programs other than the IST
Program, including any associated NRC RAIs and any NRC Safety Evaluation
Report(s). Identify any self-imposed standards related to these programs.
3.3. Preventive Maintenance (PM) Program document, implementing procedures, and PM
templates applicable to POVs.
3.4. Title 10 CFR 50, Appendix J Program document and implementing procedures.
3.5. Corrective Action Program procedures, including the operability/functionality
determination procedure.
3.6. Quality Assurance Program document.
3.7. Procedure for addressing issues captured in 10 CFR 21 notifications.
3.8. All emergency and abnormal operating procedures
3.9. For each selected POV, including its actuator (the response should be separated by
POV such as by creating a folder for each valve that includes the associated
documents):
3.9.1. Procurement and design specifications, and Certificate of Conformance.
3.9.2. Vendor documents addressing installation, operation, and maintenance.
3.9.3. Piping and instrumentation drawings (PI&Ds) for the associated system.
3.9.4. Electrical diagrams, including control logic diagrams.
3.9.5. Valve and actuator component drawings.
3.9.6. System description and/or training documents associated with the POV.
3.9.7. Operations procedures that direct operators to control the valve, including
alarm response procedures.
3.9.8. Applicable Maintenance Rule scoping document and the Maintenance Rule
performance criteria which would cause the system or component to be
moved from (a)(2) status to (a)(1) status. Also, documents (e.g., corrective
action and work orders) associated with any instance the POV was placed in
(a)(1) status during the last 5 years.
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3.9.9. List of tests, including technical specification surveillances. The list should
identify the test periodicity and test procedure identifier.
3.9.10. Completed tests and surveillances performed during the last 5 years. For
those tests and surveillances performed at a periodicity of less than 1 year or
greater than 5 years, provide the latest three performed. Include the
associated acceptance criteria basis calculations.
3.9.11. Completed preservice testing (PST).
3.9.12. List of applicable PMs. The list should identify the PM periodicity and last
completion date, and briefly describe the PM.
3.9.13. Completed PMs performed during the last 5 years, including any post
maintenance testing. For those PMs performed at a periodicity of less than
1 year or greater than 5 years, provide the latest three performed.
3.9.14. Corrective maintenance work orders performed on the POV during the last
5 years, including any post maintenance testing.
3.9.15. An all-inclusive list of calculation revisions in effect associated with the POV.
The list should include the document identifier, title, and revision number.
3.9.16. Calculations associated with the POV. Data files may be excluded.
Calculation examples include (as applicable):
- Minimum available and required voltage at transient and steady state;
- Thermal overload sizing evaluation;
- Critical setpoint calculations (e.g., limit switch settings);
- Required thrust/torque;
- Maximum allowed leakage;
- Maximum differential pressure;
- Ambient room temperature under normal and accident conditions;
- Environmental qualification (EQ) file;
- (For AOVs) Pneumatic supply sizing and setpoint calculations;
- System hydraulic calculations;
- Pressure locking/thermal binding evaluations; and
- Valve weak link/seismic weak link analysis.
3.9.17. History of permanent modifications performed on the POV since installation.
Include modification identifier and brief modification description.
3.9.18. List of corrective action documents associated with the POV for the last
5 years. The list should include the document identifier, brief description, and
status (e.g., open or completed).
3.9.19. Open and closed operability evaluations originated during the last 5 years.
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4. Additional Information to Be Provided Onsite
4.1. During the in-office preparation activities, the team may identify additional information
needed to support the inspection. The lead inspector may provide a list of the
additional information needed during the week of August 2, 2021.
4.2. Information requested to be provided throughout the inspection:
4.2.1. Any corrective action documents generated as a result of the teams
questions during this inspection as the documents are generated.
4.2.2. List of questions and/or document requests submitted by the team and their
status (e.g., open, closed) sorted by inspector. Provide to each inspector
daily 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> prior to the daily debrief. It is recommended to provide the
team leader with a master list sorted by inspector and each inspector with a
list containing only the items originated by that inspector.
4.2.3. If available in hardcopy form, one complete set of P&IDs and simplified
drawings (e.g., training schematics). If any of these documents is not
available in hardcopy form, contact the lead inspector.
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