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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] |
See also: IR 05000456/2019011
Text
October 8, 2019
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2INFORMATION REQUEST TO
SUPPORT UPCOMING TEMPORARY INSTRUCTION 2515/194 INSPECTION;
INSPECTION REPORT 05000456/2019011; 05000457/2019011
Dear Mr. Hanson:
This letter is to request information to support our inspection of the Industry Initiative Associated
with the Open Phase Condition Design Vulnerabilities in Electric Power Systems (U.S. Nuclear
Regulatory Commission (NRC) Bulletin 2012-01) beginning November 18, 2019, at your
Braidwood Station. This inspection will be performed in accordance with the NRC Temporary
Instruction 2515/194.
In order to minimize the impact that the inspection has on the site and to ensure a productive
inspection, we have enclosed a list of documents requested for the inspection. Please provide
this information prior to November 8, 2019. 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 inspections. Insofar as possible, this
information should be provided electronically to the lead inspector.
The lead inspector for this inspection is Mr. Ijaz Hafeez. We understand that our licensing
contact for this inspection is Mr. Dan Mearhoff of your organization. If there are any questions
about the inspection or the material requested in the enclosure, please contact the lead
inspector at 630-829-9843 or via e-mail at Ijaz.Hafeez@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.
B. Hanson -2-
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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
Sincerely,
/RA/
Ijaz Hafeez, Reactor Engineer
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-456; 50-457
License Nos. NPF-72; NPF-77
Enclosure:
Document Request for Temporary
Instruction 2515/194 Inspection
cc: Distribution via LISTSERV
B. Hanson -3-
Letter to Bryan C. Hanson from Ijaz Hafeez dated October 8, 2019.
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2INFORMATION REQUEST TO
SUPPORT UPCOMING TEMPORARY INSTRUCTION 2515/194 INSPECTION;
INSPECTION REPORT 05000456/2019011; 05000457/2019011
DISTRIBUTION:
Jessie Quichocho
RidsNrrDorlLpl3
RidsNrrPMBraidwood Resource
RidsNrrDirsIrib Resource
Darrell Roberts
John Giessner
Jamnes Cameron
Allan Barker
DRSIII
DRPIII
ADAMS Accession Number: ML19281D013
OFFICE RIII
NAME IHafeez:jw
DATE 10/08/19
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR TEMPORARY INSTRUCTION 2515/194 INSPECTION
Inspection Report: 05000456/2019011; 05000457/2019011
Inspection Dates: November 18-22, 2019
Inspection Procedures: 2515/194-TI-2515-Phase 5
Inspector: Ijaz Hafeez
630-829-9843
Ijaz.Hafeez@nrc.gov
Please provide the following documentation (Items 1-8) to the lead inspector prior to the onsite
inspection date, preferably no later than November 8, 2019. Whenever practical, please provide
copies electronically. Please provide an index of the requested documents which includes a
brief description of the document and the numerical heading associated with the request
(i.e., where it can be found in the list of documents requested).
1. Copies of any calculations, analyses, and/or test reports performed to support the
implementation of your open phase condition (OPC) solution. If, in your implementation,
OPCs are not detected and alarmed in the control room please include documentation
that: (a) demonstrates the OPC will not prevent functioning of important-to-safety
structures, systems, and components; and (b) detection of an OPC will occur within a
short period of time (e.g., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
2. Copies of any modification packages, including Title 10 of the Code of Federal
Regulations, Part 50.59 evaluations if performed, used for or planned for the
implementation of your OPC solution.
3. Copies of periodic maintenance, surveillance, setpoint calibration, and/or test
procedures implemented or planned, for your OPC solution.
4. Copies of your licensing basis changes to Updated Final Safety Analysis Report and/or
Technical Specifications (TS), as applicable, which discuss the design features and
analyses related to the effects of, and protection for, any open phase condition design
vulnerability.
5. Copies of any procurement specifications and acceptance testing documents related to
the installation of your OPC solution.
6. Copies of any site training the team will need to accomplish to gain access to areas with,
or planned, major electrical equipment used in your OPC solution (i.e., switchyard).
7. Provide documentation showing that with an OPC occurrence and no accident condition
signal present, either:
a. An OPC does not adversely affect the function of important-to-safety structures,
systems, and components, or
Enclosure
DOCUMENT REQUEST FOR TEMPORARY INSTRUCTION 2515/194 INSPECTION
b. TS LCOs are maintained or the TS actions are met without entry into TS
LCO 3.0.3, and
i. Important-to-safety equipment is not damaged by the OPC, and
ii. Shutdown safety is not compromised.
8. With OPC occurrence and an accident condition signal present:
a. Provide documentation showing that automatic detection and actuation will
transfer loads required to mitigate postulated accidents to an alternate source
and ensure that safety functions are preserved, as required by the current
licensing bases, or
b. Provide documentation showing that all design basis accident acceptance criteria
are met with the OPC, given other plant design features. Accident assumptions
must include licensing provisions associated with single failures. Typically,
licensing bases will not permit consideration of the OPC as the single failure
since this failure is a non-safety system.
Please provide the following documentation to the team when they arrive onsite. Whenever
practical, please provide copies electronically, except for drawings. Drawings should be
provided as paper copies of sufficient size (ANSI C or D) such that all details are legible.
1. A brief presentation describing your electric power system design and typical electrical
transmission and distribution system alignments; OPC design schemes installed to
detect, alarm and actuate; bus transfer schemes; and maintenance and surveillance
requirements. This presentation should be a general overview of your system. Please
schedule the overview shortly after the entrance meeting.
2. Plant layout and equipment drawings for areas that identify: (a) the physical plant
locations of major electrical equipment used in your open phase condition solution;
(b) the locations of detection and indication equipment used in the OPC sensing circuits.
3. If OPC actuation circuits are required, provide documentation that demonstrates
continued coordination with the other protective devices in both the offsite electrical
system (within Plant area of responsibility) and the onsite electrical systems.
4. Access to locations in which open phase condition equipment is installed or planned
(i.e., switchyard, etc.).
5. Copies of documentation or testing that demonstrates your OPC solution minimizes
spurious actuation or misoperation in the range of voltage imbalance normally expected
in the transmission system that could cause undesired separation from an operable
off-site power source.
2