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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] Category:Inspection Plan
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) ML22111A0752022-04-21021 April 2022 Information Request Letter for 2022 Problem Identification and Resolution Inspection at Braidwood Station IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) ML20183A3912020-07-0101 July 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) IR 05000456/20190052019-08-28028 August 2019 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2019005; 05000457/2019005) ML19154A6152019-06-0303 June 2019 Ltr. 06/03/19 Braidwood Station, Unit 1 - Notification of NRC Inspection and Request for Information; Inspection Report 05000456/2019004; 05000457/2019004 (DRS-J.Bozga) ML19136A1852019-05-15015 May 2019 Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, and Quad Cities Nuclear Power Station-Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency IR 05000456/20180062019-03-0404 March 2019 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000457/2018006 and 05000456/2018006) ML18305A3542018-10-31031 October 2018 Ltr. 10/31/18 Braidwood Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000456/2019010; 05000457/2019010 (DRS-J.CorujoSandin) IR 05000456/20180052018-08-28028 August 2018 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2018005 and 05000457/2018005) IR 05000456/20170062018-03-0202 March 2018 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2017006 and 05000457/2017006) IR 05000456/20170052017-08-28028 August 2017 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2017005 and 05000457/2017005) IR 05000456/20160062017-03-0101 March 2017 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016006 and 05000457/2016006) ML16265A5772016-09-20020 September 2016 E-Mail; Braidwood Station, Unit 1 - Baseline Inservice Inspection Onsite Information Request (Msh) IR 05000456/20160052016-08-31031 August 2016 MID-CYCLE Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016005; 05000457/2016005) ML16174A0852016-06-21021 June 2016 Notification of NRC Inspection and Request for Information 05000456/2016004; 05000457/2016004 IR 05000456/20150062016-03-0202 March 2016 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Inspection Report 05000456/2015006 and 05000457/2015006) ML15328A5022015-11-24024 November 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000456/2016008; 05000457/2016008 (Bxj) IR 05000456/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Braidwood, Units 1 and 2 (Report 05000456/2015005; 05000457/2015005) ML15231A1492015-08-17017 August 2015 Ltr. 08/17/15 Braidwood Station, Unit 2 - Notification of NRC Inspection and Request for Information (Txb) IR 05000456/20140012015-03-0404 March 2015 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2014001; 05000457/2014001) ML15021A2322015-01-20020 January 2015 U1 ISI Request for Information ML14245A0692014-09-0202 September 2014 Mid-Cycle Assessment Letter for Braidwood Station, Units 1 and 2 ML14223B2132014-08-11011 August 2014 Heat Sink Request for Information IR 05000456/20130012014-03-0404 March 2014 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2013001; 05000457/2013001) IR 05000456/20130062013-09-0303 September 2013 Mid-Cycle Assessment Letter (IR 05000456-13-006 & 05000457-13-006) ML13120A5842013-04-29029 April 2013 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000456-13-007 05000457-13-007 IR 05000456/20120012013-03-0404 March 2013 Annual Assessment Letter - Braidwood Station, Units 1 and 2, 05000456/2012001 and 05000457/2012001 ML12248A3062012-09-0404 September 2012 Mid-Cycle Assessment Letter for Braidwood Station Units 1 and 2 IR 05000456/20110072012-03-0505 March 2012 Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) IR 05000456/20110062011-09-0101 September 2011 Mid-Cycle Letter for Braidwood Station, Units 1 and 2, - 05000456/2011-006; 05000457/2011-006 ML1024401002010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Braidwood Nuclear Power Plant IR 05000456/20100012010-03-0303 March 2010 Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001) ML0924404022009-09-0101 September 2009 Braidwood - Mid-Cycle Performance Review and Inspection Plan ML0906302842009-03-0404 March 2009 Annual Assessment Letter - Braidwood (05000456/2010-001; 05000457/2010-001) ML0824602282008-09-0202 September 2008 Braidwood, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000456/20080012008-03-0303 March 2008 Braidwood, EOC Annual Assessment Letter (Report 05000456-08-001; 05000457-08-001) ML0735402552007-12-19019 December 2007 Inspection Plan 1/1/08 - 12/31/08 ML0724303542007-08-31031 August 2007 8/31/07 Braidwood - Mid-Cycle Performance Review and Inspection Plan 2023-08-30
[Table view] |
See also: IR 05000456/2013007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210
LISLE, IL 60532-4352
April 29, 2013
Mr. Michael J. Pacilio
Senior Vice President, Exelon Generation Company, LLC
President and Chief Nuclear Officer, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 REQUEST FOR INFORMATION FOR
AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
(CDBI) INSPECTION REPORT 05000456/2013007/05000457/2013007
Dear Mr. Pacilio:
On July 29, 2013, the U. S. Nuclear Regulatory Commission (NRC) will begin a triennial
baseline Component Design Bases Inspection (CDBI) at Braidwood Station. A team of six
inspectors will perform this 3-week inspection. This inspection will be performed in accordance
with NRC Baseline Inspection Procedure (IP) 71111.21.
The CDBI focuses on the design, maintenance, and operation of risk significant components
associated with one or more accident scenario. The components to be reviewed during this
baseline inspection will be identified during the inoffice preparation week that occurs prior to the
first on-site 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 on-site 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.
The inspection will include three weeks on-site. 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:
- On-site weeks: July 29, 2013;
August 12, 2013; and
August 26, 2013.
The team will be preparing for the inspection, mainly during the week of July 22, 2013, as
discussed in the attached enclosure.
M. Pacilio -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 on-site 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 June 10, 2013. By
June 24, 2013, the lead inspector will communicate the initial selected set of approximately
20 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 July 15, 2013. 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 July 29, 2013. 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 Caroline Tilton. We understand that our licensing
contact for this inspection is Murtaza Abbas 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) 829-9718 or via e-mail at caroline.tilton@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.
M. Pacilio -3-
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide
Documents Access and Management System (ADAMS), accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.: 50-456 and 50-457
License Nos.: NPF-72 and NPF-77
Enclosure: Information Request for Component Design Bases Inspection (CDBI)
cc w/encl: Distribution via ListServ'
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)
Inspection Report: 05000456/2013007/05000457/2013007
Inspection Dates: July 29, 2013;
August 12, 2013; and
August 26, 2013.
Inspection Procedure: IP 71111.21 Component Design Bases Inspection
Lead Inspector: Caroline Tilton, Senior Reactor Engineer, DRS
(630) 829-9718
caroline.tilton@nrc.gov
I. Information Requested Prior to the On-site Information Gathering/Inspection Week
The following information is requested by June 10, 2013, 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 (RRW), and Fussell-Veseley (FV)
(as applicable).
2. Risk-ranking of top 100 containment-related components from your site specific
PSA sorted by Large Early Release Frequency (LERF).
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 five percent to the baseline plant core damage frequency
(CDF).
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 (JPMs).
7. Provide copies of the emergency operating procedures (EOPs).
1 Enclosure
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)
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).
9. Electronic copy of the site IPEEE, 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 (MOV)
and air-operated valve (AOV) 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 (SSCs) in the Maintenance Rule (a)(1)
category for the last three years.
14. Site top ten issues list (if applicable).
15. A list of operating experience evaluations for the last three years.
16. Information of any common cause failure of components experienced in the last
five 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 P&IDs (if available).
2 Enclosure
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION (CDBI)
II. Information Requested (for the approx. 20 selected components) to be Available
by July 15, 2013, Will be Reviewed by the Team in the Regional Office During the
Week of July 22, 2013.
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 four years.
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).
4. System Health Reports, System Descriptions, Design Basis Documents, and/or
Training Lesson Plans that are 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 three 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. Trend data on the selected electrical/mechanical components performance for
last three years (For example, pumps performance including in-service testing,
other vibration monitoring, oil sample results, etc., for valves: stroke time and
leak rate results, etc.).
10. Copy of latest completed surveillance tests for each component (for example, 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.
11. Provide copies of the normal and abnormal operating procedures associated with
the selected components and selected scenarios.
3 Enclosure
12. A copy of any internal/external self-assessments and associated corrective
action documents generated in preparation for the inspection.
13. A copy of engineering/operations related audits completed in the last two years.
III. Additional Information to be Provided on July 29, 2013, On-Site (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 July 22, 2013.
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):
- Procurement documents for components selected (verify retrievable);
- Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
If you have questions regarding the information requested, please contact the lead inspector.
M. Pacilio -3-
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosures will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide
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