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Category:Inspection Report Correspondence
MONTHYEARIR 05000237/20224012022-11-30030 November 2022 Security Baseline Inspection Report 05000237/2022401 and 05000249/2022401 (Cover Letter Only) IR 05000237/20214032022-01-26026 January 2022 Security Baseline Inspection Report 05000237/2021403 and 05000249/2021403 IR 05000237/20214042021-08-0909 August 2021 Security Baseline Inspection Report 05000237/2021404 and 05000249/2021404 IR 05000237/20200102020-02-28028 February 2020 Biennial Problem Identification and Resolution Inspection Report 05000237/2020010 and 05000249/2020010 ML19281D2032019-10-0808 October 2019 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000237/2019011; 05000249/2019011 (DRS-I.Hafeez) ML18003A2112018-01-0303 January 2018 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Dresden Nuclear Power Station, Units 2 and 3 ML17313B1912017-11-0707 November 2017 Information Request for an NRC Triennial 10 CFR 50.59 Baseline Inspection Report 05000237/2018011; 05000349/2018011 (DRS-A.Shaikh) RS-17-007, Request for Improvements in NRC SPAR Model and RASP Handbook Use2017-01-12012 January 2017 Request for Improvements in NRC SPAR Model and RASP Handbook Use IR 05000237/20155012016-02-0303 February 2016 NRC Emergency Preparedness Annual Inspection Report No. 05000237/2015501; 05000249/2015501 SVPLTR 15-0055, Notification of Readiness for NRC 95001 Inspection2015-08-25025 August 2015 Notification of Readiness for NRC 95001 Inspection ML15020A0952015-01-15015 January 2015 Ltr 2014 Dresden EP Annual Closeout (Rdj) ML14045A1482014-02-12012 February 2014 EP Annual Closeout (Rdj) IR 05000237/20135022014-02-12012 February 2014 Ltr 02/12/14 Dresden EP Annual Closeout (RDJ) ML13101A4382013-04-11011 April 2013 Ti 186 Notice of Inspection IR 05000237/20085012009-02-13013 February 2009 IR 05000237-08-501, IR 05000249-08-501, on 01/01/200 Through 12/31/2008, Dresden Nuclear Power Station - NRC Emergency Preparedness Annual Inspection Report; NRC Security Annual Inspection Report IR 05000237-08-401, IR 05000249-08-401 IR 05000237/20084082008-10-0707 October 2008 IR 05000237-08-408, & IR 05000249-08-408, 08/25/2008 - 08/29/2008, Dresden Nuclear Power Station, Units 2 and 3, Routine Security Baseline Inspection IR 05000237/20075012008-02-14014 February 2008 IR 05000237-07-501, IR 05000249-07-501, and IR 05000237-07-403, IR 05000249-07-403, on 01/01/2007 - 12/31/2007, Dresden NRC Emergency Preparedness Annual Inspection and NRC Security Annual Inspection Reports IR 05000237/20072012007-12-21021 December 2007 IR 05000237-07-201, and IR 05000249-07-201, Preliminary Greater than Green for Dresden Nuclear Power Station, Units 2 and 3 ML0702905882007-01-29029 January 2007 Information Request for NRC Biennial Baseline Component Design Basis Inspection, IR 05000249-07-006, (Drs); 05000249-07-006 (DRS) IR 07200037/20060012006-12-20020 December 2006 IR 07200037-06-001, on 12/12/2006, Dresden, Units 2 and 3 IR 05000010/20050152006-09-28028 September 2006 IR 05000010-05-015, on 06/01/2006 & 09/20/2006, Dresden, Unit 1 ML0619906072006-07-11011 July 2006 Final Letter Report for Analytical Results for Fifty-five Water Samples, Batch Five, from the Vicinity of the Dresden Generating Station, Dresden, Illinois (Inspection Report No. 050-00237/2006-007) ML0617200952006-06-16016 June 2006 Orise - Interim Letter Report for Analytical Results for Four of Eight Water Samples, Batch Four, from the Vicinity of the Dresden Generating Station, Dresden, Illinois (Inspection Report No. 050-00237/2006-007) (Rfta No. 06-001) ML0500600382005-01-0505 January 2005 Re Information Request for an NRC Biennial Modification and 10 CFR 50.59 (MOD/50.59) Baseline Inspection IR 05000237/20020092002-05-0606 May 2002 IR 05000237/2002-009(DRS), IR 05000249/2002-009(DRS), on April 12, 2002, Exelon Generation Company, Dresden Nuclear Power Station, Units 2 and 3. Physical Protection. Non-cited Violations Identified IR 05000237/20020042002-04-26026 April 2002 IR 05000237/2002-004(DRP), IR 05000249/2002-004(DRP), Exelon Generation Company, Dresden Nuclear Power Station, Units 2 and 3, Inspection on 02/08/2002-03/31/2002 Re Identification and Resolution of Problems IR 05000249/19760201976-12-23023 December 1976 Letter Regarding Steps Taken by Commonwealth Edison to Correct Noncompliance Identified in 10/20/1976 Letter - Dresden Unit 3 Inspection Report 05000249/1976020 2022-11-30
[Table view] Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, 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-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 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 SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] |
See also: IR 05000249/2007006
Text
January 29, 2007
Mr. Christopher M. Crane
President and Chief Nuclear Officer
Exelon Nuclear
Exelon Generation Company, LLC
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, INFORMATION
REQUEST FOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES
INSPECTION (CDBI) 05000237/2007006(DRS); 05000249/2007006(DRS)
Dear Mr. Crane:
On April 9, 2007, the NRC will begin a biennial baseline Component Design Bases Inspection
(CDBI) at the Dresden Nuclear Power Station. A team of six inspectors will perform this 3-week
inspection. This inspection will be performed in accordance with revised NRC Baseline
Inspection Procedure (IP) 71111.21 and replaces the biennial Safety System Design and
Performance Capability inspection.
The CDBI inspection focuses on components which have high risk and low design margins.
The components to be reviewed during this baseline inspection will be identified during an
in-office preparation week prior to the first week of on-site inspection. In addition, a number of
risk significant operator actions and operating experience issues, associated with the
component samples, will also be selected for review.
The inspection will include three weeks of on-site inspection. The inspection team will consist
of six NRC inspectors, of which, five will focus on engineering and one on operations. The
current inspection schedule is as follows:
- On-site weeks: April 9, 2007, April 23, 2007, and May 7, 2007
The team will be preparing for the inspection mainly during the week of April 2, 2007, as
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the
inspection team during the week of April 9, 2007, to review probabilistic risk assessment data
and assist in identifying risk significant components, which will be reviewed during the
inspection.
C. Crane -2-
Experience with previous baseline design inspections of similar depth and length has shown
that these types of inspections are 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 available to the lead inspector no later than March 8, 2007.
By March 16, 2007, the lead inspector will communicate the initial selected set of 30
high risk components;
- The second group of documents requested are 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 available at the Regional
Office no later than March 28, 2007. During the in-office preparation activities, the team
may identify additional information needed to support the inspection; and
- The last group includes the additional information identified above, as well as plant
specific reference material. This information should be available to the team on
April 9, 2007. 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. John Jacobson. 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. If there are any
questions about the inspection or the material requested in the Enclosure, please contact the
lead inspector at (630) 829-9736 or via e-mail at jmj3@nrc.gov
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and
its enclosure will be available electronically for public inspection in the NRC Public Document
C. Crane -3-
Room or from the Publicly Available Records (PARS) component of NRC's document 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 No. 50-237; 50-249
License No. DPR-019; DPR-025
Enclosure: Component Design Bases Inspection Document Request
cc w/encl: Site Vice President - Dresden Nuclear Power Station
Dresden Nuclear Power Station Plant Manager
Regulatory Assurance Manager - Dresden
Chief Operating Officer
Senior Vice President - Nuclear Services
Senior Vice President - Mid-West Regional
Operating Group
Vice President - Mid-West Operations Support
Vice President - Licensing and Regulatory Affairs
Director Licensing - Mid-West Regional
Operating Group
Manager Licensing - Dresden and Quad Cities
Senior Counsel, Nuclear, Mid-West Regional
Operating Group
Document Control Desk - Licensing
Assistant Attorney General
Illinois Emergency Management Agency
State Liaison Officer
Chairman, Illinois Commerce Commission
C. Crane -3-
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
Public Electronic Reading Room).
Sincerely,
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-237; 50-249
License No. DPR-019; DPR-025
Enclosure: Component Design Bases Inspection Document Request
cc w/encl: Site Vice President - Dresden Nuclear Power Station
Dresden Nuclear Power Station Plant Manager
Regulatory Assurance Manager - Dresden
Chief Operating Officer
Senior Vice President - Nuclear Services
Senior Vice President - Mid-West Regional
Operating Group
Vice President - Mid-West Operations Support
Vice President - Licensing and Regulatory Affairs
Director Licensing - Mid-West Regional
Operating Group
Manager Licensing - Dresden and Quad Cities
Senior Counsel, Nuclear, Mid-West Regional
Operating Group
Document Control Desk - Licensing
Assistant Attorney General
Illinois Emergency Management Agency
State Liaison Officer
Chairman, Illinois Commerce Commission
DOCUMENT NAME:ML070290588.wpd
G Publicly Available G Non-Publicly Available G Sensitive G 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 MJones: ls AMStone
DATE 1/29/07 1/29/07
OFFICIAL RECORD COPY
C. Crane -4-
ADAMS DISTRIBUTION:
TEB
JFW1
RidsNrrDirsIrib
GEG
KGO
GLS
CJP3
CAA1
DRPIII
DRSIII
PLB1
TXN
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
Inspection Report: 05000237/249/2007006(DRS)
Inspection Dates: April 9, 2007, April 23, 2007, and May 7, 2007
Inspection Procedure: IP 71111.21, Component Design Bases Inspection
Lead Inspector: John Jacobson, Lead Inspector
(630) 829-9736 JMJ3@nrc.gov
I. Information Requested Prior to the On-site Inspection Activities
(by March 8, 2007, or sooner)
The following information is requested by March 8, 2007, 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 CDROM (two copies). The
CDROM 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 a knowledge of pressurized water reactor technology).
1. Risk ranking of top 100 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. Provide a list of the top 500 cut-sets from your PSA;
3. Risk ranking of operator actions from your site specific PSA sorted by RAW.
Provide copies of your human reliability worksheets for these items;
4. If you have an External Events or Fire PSA Model, provide the information
requested in Items 1 and 2 for external events and fire;
5. 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.);
6. List of high risk Maintenance Rule systems/components based on engineering
or expert panel judgement;
7. A list of operating experience evaluations for the last 3 years;
8. A list of modifications sorted by component identified in Item 1;
Enclosure
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
9. List of and information on any common cause failure of components experienced
in the last 5 years at your facility;
10. A list of the design calculations which provide the design margin information for
components included in Item 1;
11. List of Root Cause Evaluations associated with component failures or design
issues initiated/completed in the last 5 years;
12. Current management and engineering organizational chart;
13. List of Motor Operator Valves in the program, design margin and risk ranking;
14. List of System, Structures and Components in the maintenance rule (a)(1)
category; and
15. Site Top Ten issues list.
II. Information Requested (for the approximate 30 selected components) to be
Available by March 28, 2007
1. List of condition reports (corrective action documents) associated with each of the
selected components for the last 3 years.
2. The corrective maintenance history associated with each of the selected
components for the last 2 years.
3. Copies of calculations associated with each of the selected components,
excluding data files. Please review the calculations and also provide copies of
referenced material (such as drawings, engineering requests, vendor letters);
4. Copies of operability evaluations associated with each of the selected
components and plans for restoring operability, if applicable;
5. Copies of selected operator work-around evaluations associated with each of the
selected components and plans for resolution, if applicable;
6. Copies of any open temporary modifications associated with each of the selected
components, if applicable;
7. 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., as applicable); and
8. Audits completed in the last 2 years.
Enclosure
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
III. Additional Information to be Provided on April 9, 2007, On-site
Request for any additional information as needed will be provided during the week of
April 2, 2007. The lead inspector will provide a list of added information.
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. Reference materials (if available on electronic media, please provide a copy);
4. General set of plant drawings;
5. IPE/PRA report; and
6. Procurement documents for components selected (verify retrievable):
- Plant procedures (normal, abnormal, emergency, surveillance, etc.);
- Technical Specifications;
If you have questions regarding the information requested, please contact the lead inspector.
Enclosure