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Category:Letter
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[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24178A0432024-06-26026 June 2024 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - License Amendment Request Regarding Neutron Flux Instrumentation ML24156A0072024-05-30030 May 2024 NRR E-mail Capture - Final RAI - D.C. Cook Nuclear Plant, Unit Nos. 1 and 2 - License Amendment Request Regarding Reserve Feed Enclosure ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 ML22264A1112022-09-21021 September 2022 Notification of Post-Approval Site Inspection for License Renewal - Phase IV; IR 05000315/2023010; 05000316/2023010 and RFI ML22230A4362022-08-19019 August 2022 Licensed Operator Positive Fitness-For-Duty Test ML22049B4532022-02-22022 February 2022 Notification of NRC Baseline Inspection and Request for Information Report 05000315/2022002 ML21307A3352021-11-0303 November 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Final RAI - License Amendment Request Regarding Containment Water Level Instrumentation ML21215A1242021-08-0303 August 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2021013; 05000316/2021013 ML21140A3052021-05-20020 May 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21049A2682021-02-16016 February 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Final RAI - License Amendment Request for One-Time Extension Containment Type a ILRT ML21026A3472021-01-26026 January 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval IR 05000315/20200112020-09-17017 September 2020 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2020011; 05000316/2020011 ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions IR 05000315/20200202020-04-10010 April 2020 Units 1 and 2 - Information Request for NRC Triennial Evaluation of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000315/2020020 and 05000316/2020020 ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19267A1362019-09-24024 September 2019 NRC Information Request (September 23, 2019) - IP 71111.08 - DC Cook U2 - Documents Selected for Onsite Review (DRS-M.Holmberg) ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19084A0002019-03-20020 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19072A1432019-03-12012 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18263A1542018-09-14014 September 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18204A3722018-07-19019 July 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18143B6292018-05-29029 May 2018 Dtf. RAI ML18142B5312018-05-29029 May 2018 Request for Additional Information Concerning 2017 Decommissioning Funding Status Report ML18060A0212018-02-28028 February 2018 Enclosurequest for Additional Information (Request for Additional Information Regarding Indiana Michigan Power Company'S Decommissioning Funding Update for Donald C Cook Nuclear Plant Units 1 and 2 ISFSI) ML18043A0092018-02-0909 February 2018 NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program ML17304A0102017-11-0101 November 2017 Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001) ML17249A7492017-08-28028 August 2017 E-Mail Sent August 28, 2017, Request for Information for Donald C. Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh) ML17108A7772017-04-18018 April 2017 17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh) ML17068A0652017-03-0808 March 2017 Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj) ML17027A0192017-01-26026 January 2017 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484) ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control IR 05000315/20160042016-07-11011 July 2016 Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16193A6542016-07-11011 July 2016 Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML16025A0552016-01-22022 January 2016 Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316 ML15267A6832015-10-0505 October 2015 Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15231A5542015-08-18018 August 2015 Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd) ML15225A5772015-08-13013 August 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2 ML15163A1672015-06-15015 June 2015 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15149A3832015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15119A3392015-05-0505 May 2015 Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal ML15055A5702015-02-24024 February 2015 Cyber Security RFI Temporary Instruction 2201/004 ML15022A1532015-01-21021 January 2015 Dccook ISI Request for Information 2024-06-26
[Table view] |
See also: IR 05000315/2015008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
August 18, 2015
Mr. Larry Weber
Senior VP and Chief Nuclear Officer
Indiana Michigan Power Company
Nuclear Generation Group
One Cook Place
Bridgman, MI 49106
SUBJECT: DONALD. C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 - REQUEST
FOR INFORMATION FOR AN NRC TRIENNIAL PILOT BASELINE COMPONENT
DESIGN BASES INSPECTION (INSPECTION REPORT 05000315/2015008;
05000316/2015008)
Dear Mr. Weber:
On November 2, 2015, the U. S. Nuclear Regulatory Commission (NRC) will begin the team
portion of the triennial pilot baseline Component Design Bases Inspection (CDBI) at Donald C.
Cook Nuclear Power Plant, Units 1 and 2. This inspection will be performed in accordance with
NRC Baseline Inspection Procedure 71111.21T. A team of six inspectors will perform this
2-week onsite pilot inspection.
The CDBI focuses on the design, maintenance, and operation of risk-significant components
associated with one or more accident scenario or systems. The components to be reviewed
during this baseline inspection will be identified during the in-office preparation weeks that occur
prior to the first onsite inspection week. In addition, operating experience issues, associated
with the component samples, will also be selected for review. The inspection team may request
scenarios to be performed on the simulator. This request would require support from your
simulator staff to validate scenarios, simulator time, and a crew to perform the actions, which
would most likely occur during the second onsite week. The team will work closely with your
staff early on during the inspection process to ensure this activity can be accomplished with
minimal impact.
This pilot inspection will include two weeks onsite. The inspection team will consist of six NRC
inspectors, of which five will focus on engineering/maintenance and one on operations. The
current inspection schedule is as follows:
- Preparatory weeks: October 19 -23, 2015; and
October 26 - 30, 2015.
- On-site inspection weeks: November 2 - 6, 2015; and
November 16 - 20, 2015.
L. Weber -2-
Experience with previous baseline design inspections of similar depth and length has shown
that 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 three groups:
- The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than September 14, 2015.
By September 30, 2015, the lead inspector will communicate the initial selected set of
approximately 10 components.
- The second group of documents requested is those items needed to support our in-office
preparation activities. This set of documents, including the calculations associated with the
initial selected components, should be provided to the lead inspector at the Regional Office
no later than October 14, 2015. During the in-office preparation activities, the team may
identify additional information needed to support the inspection.
- The last group includes the additional information above as well as plant specific reference
material. This information should be available to the team onsite on November 2, 2015. It is
also requested that corrective action documents and/or questions developed during the
inspection be provided to the lead inspector as the documents are generated.
The lead inspector for this inspection is Mr. Néstor Féliz-Adorno. We understand that our
licensing contact for this inspection is Mr. John Nimtz of your organization. If there are any
questions about the inspection or the material requested in the enclosure, please contact the
lead inspector at (630) 829-9739, or via e-mail at Nestor.Feliz-Adorno@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.
L. Weber -3-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management 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/
Christine A. Lipa, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-315; 50-316
License Nos. DPR-58; DPR-74
Enclosure:
Information Request for Component Design Bases Inspection
c w/encl: Distribution via LISTSERV
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
Inspection Report: 05000315/2015008; 05000316/2015008
Inspection Dates: November 2 - 6, 2015; and
November 16 - 20, 2015.
Inspection Procedure: IP 71111.21T, Component Design Bases Inspection (Teams)
Lead Inspector: Néstor Féliz Adorno, Senior Reactor Engineer, DRS
(630) 829-9739
Nestor.Feliz-Adorno@nrc.gov
I. Information Requested Prior to the Onsite Information Gathering/Inspection Week
The following information is requested by September 14, 2015, or sooner, to facilitate
inspection preparation. If you have any questions regarding this information, please
call the team leader as soon as possible. (Please provide the information electronically
in pdf files, Excel, or other searchable formats, preferably on some portable electronic
media (e.g., CDROM, DVD, flash drive, etc.). The portable electronic media 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).
1. Risk-ranking of top 250 components from your site specific Probabilistic Safety
Analysis (PSA) sorted by Risk-Achievement Worth (RAW). Include values for
Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley (as applicable).
2. Risk-ranking of top 100 containment-related components (i.e. Large Early Release
Frequency (LERF)) from your site specific PSA sorted by RAW.
3. Provide a list of the top 200 cut-sets from your PSA.
4. Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that
contributes more than 5 percent to the baseline plant core damage frequency.
5. Copies of PSA system notebooks, and latest PSA summary document.
6. List of time critical operator actions. Identify those actions that do not have job
performance measures.
7. Provide copies of the emergency operating procedures.
8. If you have an External Events or Fire PSA Model, provide the information requested
in Items 1 and 2 for external events and fire. Provide narrative description of each
coded event (including fire, flood zone description).
Enclosure
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
9. Electronic copy of the site Individual Plant Examination of External Events,
if available.
10. Any pre-existing evaluation or list of components and associated calculations with
low-design margins, (i.e., pumps closest to the design limit for flow or pressure,
diesel generator close to design required output, heat exchangers close to rated
design heat removal etc.).
11. List of available design (setup) margins in both the open and closed direction
(identify safety-related direction) for valves in the Motor-Operated Valve and
Air-Operated Valve Programs. Identify the basis for how the margin was determined.
12. List of high-risk Maintenance Rule systems/components based on engineering or
expert panel judgment (i.e., those systems/components not identified in the PRA).
13. Structures, systems, and components in the Maintenance Rule (a)(1) category for
the last 3 years.
14. Site top 10 issues list (if applicable).
15. A list of operating experience evaluations for the last 3 years.
16. Information of any common cause failure of components experienced in the last
5 years at your facility.
17. List of Root Cause Evaluations associated with component failures or design issues
initiated/completed in the last five years.
18. List of open operability evaluations.
19. List of components/systems considered operable but degraded/nonconforming.
20. Current management and engineering organizational chart.
21. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications,
Technical Specifications Bases, and Technical Requirements Manual.
22. Major one line electrical drawings (ac and dc), and key diagrams (paper copies).
23. Electronic copy of Piping and Instrumentation Drawings (P&IDs) (if available).
II. Information Requested (for the approximate 10 selected components) to be
Available by October 14, 2015, (will be reviewed by the team in the Regional
office during the weeks of October 19 - 23, 2015, and October 26 - 30, 2015).
This information should be separated for each selected component, especially if
provided electronically (e.g., folder with component name that includes calculations,
condition reports, maintenance history, etc.).
1. List of condition reports (corrective action documents) associated with each of the
selected components for the last 6 years.
2
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
2. The maintenance history (corrective, preventive, and elective) associated with each
of the selected components for the last 10 years. Identify frequency of preventive
maintenance activities.
3. Copies of calculations associated with each of the selected components (if not
previously provided), excluding data files. Please review the calculations and also
provide copies of important referenced material (such as drawings, engineering
requests, and vendor letters). Pipe stress calculations are excluded from this
request.
4. System Health Reports, System Descriptions, Design Basis Documents, and/or
Training Lesson Plans associated with each of the selected components.
5. A list of modifications, including equivalency evaluations and setpoint changes,
associated with each of the selected components. This list should include a
descriptive paragraph on the purpose of the modification. Please ensure this list
only includes design completed (not canceled) modifications.
6. Copies of operability evaluations (open/closed for last 3 years) associated with
each of the selected components and plans for restoring operability, if applicable.
7. Copies of selected operator work-around evaluations associated with each of the
selected components and plans for resolution, if applicable.
8. Copies of any open temporary modifications associated with each of the selected
components, if applicable.
9. Copy of latest completed surveillance tests for each component (e.g., for pumps this
would include: comprehensive test, quarterly test, flow balance, etc.; for valves:
stroke time testing, diagnostic testing, leak testing, etc.). Acceptance criteria basis
calculations should also be included.
10. Provide copies of the normal and abnormal operating procedures associated with the
selected components and selected scenarios.
11. A copy of any internal/external self-assessments and associated corrective action
documents generated in preparation for the inspection.
12. Copy of the last three completed tests and surveillances for each component, for
example:
- Pumps: comprehensive test, quarterly test, flow balance, etc.
- Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc.
- Heat Exchangers/room coolers: thermal performance, clean/inspect, fan
flows, etc.
Acceptance criteria basis calculations should also be included.
13. A copy of engineering/operations related audits completed in the last 2 years.
3
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
III. Additional Information to be Provided on November 2, 2015, Onsite (for final
selected components)
1. During the in-office preparation activities, the team will be making final selections and
may identify additional information needed to support the inspection. The lead
inspector will provide a list of the additional information needed during the week of
October 19 - 23, 2015.
2. Schedule of any testing/maintenance activities to be conducted on the selected
components during the three onsite inspection weeks.
IV. Information Requested to be Provided Throughout the Inspection
1. Copies of any corrective action documents generated as a result of the teams
questions or queries during this inspection.
2. Copies of the list of questions submitted by the team members and the
status/resolution of the information requested (provide daily during the inspection to
each team member).
3. One complete set of P&IDs (paper copies).
4. Reference materials. (make available if needed during all on-site weeks):
- Individual Plant Examination/ PRA report;
- Procurement documents for components selected (verify retrievable);
- Plant procedures (normal, abnormal, emergency, surveillance, etc.);
- Original Final Safety Analysis Report; and
If you have questions regarding the information requested, please contact the lead inspector.
4
L. Weber -3-
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management 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/
Christine A. Lipa, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-315; 50-316
License Nos. DPR-58; DPR-74
Enclosure:
Information Request for Component Design Bases Inspection
c w/encl: Distribution via LISTSERV
DISTRIBUTION w/encl:
Kimyata MorganButler
RidsNrrDorlLpl3-1 Resource
RidsNrrPMDCCook Resource
RidsNrrDirsIrib Resource
Cynthia Pederson
Darrell Roberts
Richard Skokowski
Allan Barker
Carole Ariano
Linda Linn
DRPIII
DRSIII
Jim Clay
Carmen Olteanu
ADAMS Accession Number ML15231A554
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII RIII RIII RIII
NAME ADunlop for NFéliz-Adorno:cl CLipa
DATE 08/18/15 08/18/15
OFFICIAL RECORD COPY