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Category:Inspection Report
MONTHYEARIR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) IR 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 05000456/20234012023-10-18018 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 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 05000456/20220102022-06-22022 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 05000456/20224022022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 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 2024-09-12
[Table view] Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[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