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Category:Inspection Report
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 IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 IR 05000457/20214202023-03-22022 March 2023 Reissued - Braidwood Generating Station, Unit 1 and 2, Security Inspection Report Cover Letter 05000456 and 05000457-2021420 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220042023-01-26026 January 2023 Integrated Inspection Report 05000456/2022004 and 05000457/2022004 ML22269A4992022-11-0808 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report IR 05000456/20220032022-10-25025 October 2022 Integrated Inspection Report 05000456/2022003 and 05000457/2022003 and Exercise of Enforcement Discretion IR 05000456/20224202022-10-24024 October 2022 Cover Letter Braidwood Station Units 1 and 2 Security Baseline Inspection Report 05000456/2022420 and 05000457/2022420 IR 05000456/20224032022-08-23023 August 2022 Material Control and Accounting Program Inspection Report 05000456/2022403 and 05000457/2022403 IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) IR 05000456/20220022022-07-26026 July 2022 Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001 IR 05000456/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000456/2022011 and 05000457/2022011 IR 05000456/20224012022-07-13013 July 2022 Security Baseline Inspection Report 05000456/2022401 and 05000457/2022401 IR 05000456/20224022022-06-30030 June 2022 Cyber Security Inspection Report 05000456/2022402 and 05000457/2022402 IR 05000456/20220102022-06-22022 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20220012022-05-0303 May 2022 Integrated Inspection Report 05000456/2022001 and 05000457/2022001 IR 05000456/20223012022-04-0606 April 2022 NRC Initial License Examination Report 05000456/2022301 and 05000457/2022301 IR 05000456/20225012022-03-21021 March 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000456/2022501 and 05000457/2022501 IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) IR 05000456/20210042022-01-28028 January 2022 Integrated Inspection Report 05000456/2021004 and 05000457/2021004 IR 05000456/20210032021-10-26026 October 2021 Integrated Inspection Report 05000456/2021003 and 05000457/2021003 IR 05000456/20214022021-09-16016 September 2021 Security Baseline Inspection Report 05000456/2021402 and 05000457/2021402 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) IR 05000456/20210022021-07-22022 July 2021 Integrated Inspection Report 05000456/2021002 and 05000457/2021002 IR 05000456/20210102021-07-19019 July 2021 Triennial Fire Protection Inspection Report 05000456/2021010 and 05000457/2021010 IR 05000456/20214012021-05-20020 May 2021 Security Baseline Inspection Report 05000456/2021401 and 05000457/2021401 IR 05000456/20210012021-04-16016 April 2021 Integrated Inspection Report 05000456/2021001 and 05000457/2021001 IR 05000456/20200062021-03-0404 March 2021 Annual Assessment Letter for Braidwood Station (Report 05000456/2020006 and 05000457/2020006) IR 05000456/20200042021-01-26026 January 2021 Integrated Inspection Report 05000456/2020004; 05000457/2020004; and 07200073/2020001 IR 05000456/20200122020-11-18018 November 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20200032020-11-10010 November 2020 Integrated Inspection Report 05000456/2020003 and 05000457/2020003 IR 05000456/20204022020-10-0202 October 2020 Security Baseline Inspection Report 05000456/2020402 and 05000457/2020402 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) IR 05000456/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000456/2020301 and 05000457/2020301 ML20238B8692020-08-25025 August 2020 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000456/2020004; 05000457/2020004 IR 05000456/20200022020-07-28028 July 2020 Integrated Inspection Report 05000456/2020002 and 05000457/2020002 IR 05000456/20200012020-04-21021 April 2020 Integrated Inspection Report 05000456/2020001 and 05000457/2020001 IR 05000456/20205012020-04-0808 April 2020 Emergency Preparedness Inspection Report 05000456/2020501 and 05000457/2020501 IR 05000456/20204012020-03-31031 March 2020 Security Baseline Inspection Report 05000456/2020401 and 05000457/2020401 IR 05000456/20200102020-03-25025 March 2020 Biennial Problem Identification and Resolution Inspection Report 05000456/2020010 and 05000457/2020010 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) ML20056F2972020-02-25025 February 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2020002 2024-02-02
[Table view] 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 05000456/2008005
Text
November 14, 2008
Mr. Charles G. Pardee
President and Chief Nuclear Officer (CNO), Exelon Nuclear
Chief Nuclear Officer (CNO), AmerGen Energy Company, LLC
4300 Winfield Road
Warrenville IL 60555
SUBJECT: BRAIDWOOD STATION NOTIFICATION OF AN NRC TRIENNIAL HEAT SINK
PERFORMANCE INSPECTION AND REQUEST FOR INFORMATION
05000456/2008005; 05000457/2008005
Dear Mr. Pardee:
On March 26, 2008, we informed you of a Triennial Heat Sink Inspection at your Braidwood
Station planned for June 23, 2008. After agreement with your staff, we rescheduled the
inspection to start on December 15, 2008. This inspection will be performed in accordance with
NRC baseline inspection procedure (IP) 71111.07. The systems that have been selected for
detailed review during this baseline inspection are the 1A SX Pump Lube Oil Cooler and the 2A
RHR Heat Exchanger.
In order to minimize the impact that the inspection has on the site and to ensure a productive
inspection, we have enclosed a request for documents needed for the inspection.
- The first 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 selected heat exchangers, should be available at the Regional Office no later than
December 5, 2008. 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.). During the in-office preparation
activities, the inspector 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 onsite to the inspector on
December 15, 2008. It is also requested that corrective action documents and/or questions
developed during the inspection be provided to the inspector as the documents are
generated.
All requested documents are to cover the time period from the onsite inspection period back to
the last Heat Sink Performance Inspection. If nothing addressing a request was done in that
time period, then the request applies to the last applicable document in the previous time period.
C. Pardee -2-
The lead inspector for this inspection is Michael A. Jones Jr. If there are questions about the
material requested, or the inspection, please call Mr. Michael A. Jones Jr. at (630) 829-9745.
Please send the information to the following e-mail address michael.jones@nrc.gov. A
hard-copy with the required information is also an acceptable option. It is important that these
documents be as complete as possible, in order to minimize the number of documents
requested during the preparation week or during the onsite inspection.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs 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 Nos. 50-456; 50-457
License Nos. NPF-72; NPF-77
Enclosure: TRIENNIAL HEAT SINK INSPECTION
DOCUMENT REQUEST
cc w/encl: Site Vice President - Braidwood Station
Plant Manager - Braidwood Station
Regulatory Assurance Manager - Braidwood Station
Chief Operating Officer and Senior Vice President
Senior Vice President - Midwest Operations
Senior Vice President - Operations Support
Vice President - Licensing and Regulatory Affairs
Director - Licensing and Regulatory Affairs
Manager Licensing - Braidwood, Byron and LaSalle
Associate General Counsel
Document Control Desk - Licensing
Assistant Attorney General
J. Klinger, State Liaison Officer,
Illinois Emergency Management Agency
Chairman, Illinois Commerce Commission
C. Pardee -2-
The lead inspector for this inspection is Michael A. Jones Jr. If there are questions about the material
requested, or the inspection, please call Mr. Michael A. Jones Jr. at (630) 829-9745. Please send the
information to the following e-mail address michael.jones@nrc.gov. A hard-copy with the required
information is also an acceptable option. It is important that these documents be as complete as
possible, in order to minimize the number of documents requested during the preparation week or during
the onsite inspection.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure
will be available electronically for public inspection in the NRC Public Document Room or from the
Publicly Available Records (PARS) component of NRCs 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 Nos. 50-456; 50-457
License Nos. NPF-72; NPF-77
Enclosure: TRIENNIAL HEAT SINK INSPECTION
DOCUMENT REQUEST
cc w/encl: Site Vice President - Braidwood Station
Plant Manager - Braidwood Station
Regulatory Assurance Manager - Braidwood Station
Chief Operating Officer and Senior Vice President
Senior Vice President - Midwest Operations
Senior Vice President - Operations Support
Vice President - Licensing and Regulatory Affairs
Director - Licensing and Regulatory Affairs
Manager Licensing - Braidwood, Byron and LaSalle
Associate General Counsel
Document Control Desk - Licensing
Assistant Attorney General
J. Klinger, State Liaison Officer,
Illinois Emergency Management Agency
Chairman, Illinois Commerce Commission
DOCUMENT NAME: G:\DRS\Work in Progress\Ltr 111408 BRAIDWOOD Request for Information
MAJ.doc
9 Publicly Available 9 Non-Publicly Available 9 Sensitive 9 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
NAME MJones:ls AMStone
DATE 11/14/2008 11/14/08
OFFICIAL RECORD COPY
Letter to Mr. Charles Pardee from Mrs. Ann Marie Stone dated November , 2008.
SUBJECT: BRAIDWOOD STATION NOTIFICATION OF AN NRC TRIENNIAL HEAT SINK
PERFORMANCE INSPECTION AND REQUEST FOR INFORMATION
05000456/2008005; 05000457/2008005
DISTRIBUTION:
RidsNrrDorlLpl3-2
Tamara Bloomer
RidsNrrPMBraidwood Resource
RidsNrrDirsIrib Resource
Mark Satorius
Kenneth Obrien
Jared Heck
Roland Lickus
DRPIII
DRSIII
Carole Ariano
Linda Linn
Patricia Buckley
Tammy Tomczak
ROPreports@nrc.gov
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST
Inspection Report: 05000456/2008005; 05000457/2008005
Inspection Dates: December 15, 2008 -- December 19, 2008
Inspection Procedure: IP 71111.07, Triennial Heat Sink Performance Inspection
Lead Inspector: Michael A. Jones Jr.
(630) 829-9745
michael.jones@nrc.gov
I. Information Requested By December 5, 2008
1. For the specific heat exchangers selected:
a. Copies of the two most recent completed tests confirming thermal performance
for those heat exchangers which are performance tested;
b. Copy of system description and design basis document for the heat exchangers
(as applicable);
c. Copy of any operability determinations or other documentation of degradation
associated with the heat exchangers or the systems that support the operation
for the selected heat exchangers;
d. Copy of the Updated Final Safety Analysis Report (UFSAR) sections applicable
for each heat exchanger; and
e. Provide a list of calculations with a description which currently apply to each heat
exchanger.
2. A schedule of all inspections, cleanings, maintenance, or testing of any plant heat
exchanger to be done during the onsite portion of the inspection.
3. Copies of procedures developed to implement the recommendations of GL 89-13,
(e.g., the GL 89-13 Heat Exchanger Program) description.
4. Updated Final Safety Analysis Report pages for the GL 89-13 Heat Exchanger
Program.
5. Maximum Cooling Water system inlet temperature limit that still allows full licensed
power operation of the nuclear reactor. Please provide the document that states this
limit (e.g., USAR or TRM) and the operating procedure that ensures this limit is not
exceeded.
1 Enclosure
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST
II. Information Requested to be Available on First Day of Inspection,
December 15, 2008
1. For the specific heat exchangers selected:
a. Provide the Design Basis Documents and Updated Final Safety Analysis Report
pages for the selected heat exchangers;
b. Copy of the design specification and heat exchanger data sheets for each heat
exchanger;
c. Copy of the vendor manuals including component drawings for each heat
exchanger;
d. Copy of the calculation which establishes the limiting (maximum) design basis
heat load which is required to be removed by each of these heat exchangers;
e. Copy of the calculation which correlates surveillance testing results from these
heat exchangers with design basis heat removal capability (e.g., basis for
surveillance test acceptance criteria);
f. Copy of the calculations or documents which evaluate the potential for water
hammer or excessive tube vibration in the heat exchanger or associated piping;
g. List of engineering-related Operator Workarounds/Temporary Modifications for
these heat exchangers since the last Heat Sink Performance;
h. Copy of the evaluations of data for the two most recent completed tests
confirming the thermal performance of each heat exchanger;
i. Documentation and procedures that identify the types, accuracy, and location of
any special instrumentation used for the two most recently completed thermal
performance tests for the heat exchangers (e.g., high accuracy ultrasonic flow
instruments or temperature instruments). Include calibration records for the
instruments used during these tests;
j. Copies of those documents that describe the methods taken to control water
chemistry in the heat exchangers;
k. Copies of the documents that verify the structural integrity of the heat exchanger,
e.g., eddy current summary sheets, ultrasonic testing results, and visual
inspection results;
l. The cleaning and inspection maintenance schedule for each heat exchanger for
the next five years;
m. Copy of the document describing the inspection results for the last two clean and
2 Enclosure
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST
inspection activities completed on each heat exchanger;
n. Copy of the document which identifies the current number of tubes in service for
each heat exchanger and the supporting calculation which establishes the
maximum number of tubes which can be plugged in each heat exchanger;
o. Copy of the document establishing the repair criteria (plugging limit) for degraded
tubes which are identified in each heat exchanger; and
p. Information regarding any alarms that monitor on-line performance.
2. For the ultimate heat sink:
a. Maintenance or inspection of inaccessible below-water portions of the UHS
system including results of underwater diving inspections and assessments of
sediment intrusion and/or removal of sediment;
b. Inspections and/or maintenance related to preventing macrofouling (silt, dead
mussel shells, debris, etc.) and aquatic life such as fish, algae, grass, or kelp;
c. Inspections and/or maintenance related to preventing biotic fouling;
d. Copies of chemistry procedures and surveillances that monitor for pH, calcium
hardness, etc.;
e. Copies of any design change performed on the system;
f. Copies of procedures for a loss of UHS;
g. Copies of procedures associated with operating during adverse weather
conditions, (e.g., icing or high temperatures or low levels);
h. Copies of calculations and surveillances that determine the UHS reservoir
capacity and heat transfer capability; and
i. Copies of surveillance procedures and testing results conducted on the level
instrumentation relied upon to determine UHS reservoir capability.
3. For the safety-related service water system (or equivalent):
a. Last two performance tests, such as the ASME in service test, for all pumps, all
valves, and the cooling towers, if applicable, in the safety-related service water
system. If the components are not performance tested, please provide
documentation verifying performance by the methods actually used;
b. Copies of the documents that verify flow testing was done at maximum design flow
during the last two years or since the last time it was done. Copies of the
3 Enclosure
TRIENNIAL HEAT SINK PERFORMANCE INSPECTION DOCUMENT REQUEST
documents that verify maximum design flow testing will continue to be periodically
done in the future;
c. Copies of any design changes performed on the system;
d. Copies of procedures for a loss of service water system;
e. Copies of inspections and/or maintenance related to macrofouling (silt, dead
mussel shells, debris, etc.) and aquatic life such as fish, algae, grass or kelp;
f. Copies of inspections and/or maintenance related to preventing biotic fouling;
g. Copies of chemistry procedures and surveillances that monitor for pH, calcium
hardness, etc.;
h. Copies of procedures and/or test results to survey or monitor interface valves
between the safety-related section of the service water system and the non-safety-
related section;
i. Copies of the pipe testing and/or inspection program procedures and surveillances;
j. Copies of the documents that verify the structural integrity of the heat exchanger,
e.g., eddy current summary sheets, ultrasonic testing results, and visual inspection
results;
k. History of any thru wall pipe leak on the system; and
l. Copies of the procedures to monitor assess and disposition active thru wall pipe
leaks, including structural evaluations and/or planned corrective actions.
If the information requested above will not be available, please contact Mr. Michael Jones, Jr. as
soon as possible at (630) 829-9745 or email Michael.jones@nrc.gov.
4 Enclosure