Similar Documents at Byron |
---|
Category:Annual Operating Report
MONTHYEARRS-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 ML22118A3642022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (ARERR) RS-21-046, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-04-0808 April 2021 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML20121A0292020-04-30030 April 2020 Annual Radiological Environmental Operating Report - Part 1 of 4 ML20121A0302020-04-30030 April 2020 Annual Radiological Environmental Operating Report - Part 2 of 4 ML20121A0312020-04-30030 April 2020 Annual Radiological Environmental Operating Report - Part 3 of 4 BYRON 2020-0031, Annual Radiological Environmental Operating Report - Part 4 of 42020-04-30030 April 2020 Annual Radiological Environmental Operating Report - Part 4 of 4 RS-20-043, 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2020-04-0909 April 2020 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-19-042, Submittal of Annual 1O CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2019-04-0909 April 2019 Submittal of Annual 1O CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2018-0042, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0303 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RS-18-039, Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2018-04-0909 April 2018 Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2015-0054, 2014 Annual Radiological Environmental Operating Report (AREOR)2015-05-13013 May 2015 2014 Annual Radiological Environmental Operating Report (AREOR) RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report BYRON 2014-0051, Annual Radioactive Effluent Release Report2014-04-24024 April 2014 Annual Radioactive Effluent Release Report RS-13-090, and Byron Station - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2013-04-0505 April 2013 and Byron Station - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML12342A3882012-12-17017 December 2012 Report of Changes, Tests and Experiments BYRON 2012-0051, Annual Dose Report for 20112012-04-27027 April 2012 Annual Dose Report for 2011 RS-12-054, Submittal of Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2012-04-0606 April 2012 Submittal of Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2011-0067, 2010 Annual Radioactive Effluent Release Report2011-04-29029 April 2011 2010 Annual Radioactive Effluent Release Report RS-11-052, Units 1 and 2 - Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2011-04-0606 April 2011 Units 1 and 2 - Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2010-0029, Annual Radioactive Effluent Release Report2010-04-30030 April 2010 Annual Radioactive Effluent Release Report ML1012301402010-04-30030 April 2010 2009 Annual Radiological Effluent Release Report BYRON 2010-0034, Annual Dose Report for 20092010-04-30030 April 2010 Annual Dose Report for 2009 RS-10-075, Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2010-04-0808 April 2010 Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors BYRON 2010-0017, Regulatory Commitment Change Summary Report2010-03-0101 March 2010 Regulatory Commitment Change Summary Report BYRON 2010-0039, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20092009-12-31031 December 2009 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2009 RS-09-051, Annual 10 CFR 50 .46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2009-04-0909 April 2009 Annual 10 CFR 50 .46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-08-053, Annual & Thirty Day Reports of the Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems..2008-04-11011 April 2008 Annual & Thirty Day Reports of the Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems.. RS-07-052, Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.2007-04-13013 April 2007 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. ML0634902862006-12-13013 December 2006 Report of Changes, Tests and Experiments ML0614303732006-04-30030 April 2006 Annual Radiological Environmental Operating Report BYRON 2004-0043, 2003 Occupational Radiation Exposure Report2004-04-30030 April 2004 2003 Occupational Radiation Exposure Report BYRON 2004-0030, Annual Environmental Operating Report2004-04-16016 April 2004 Annual Environmental Operating Report RS-04-051, Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for light-water Nuclear Power Reactors.2004-04-14014 April 2004 Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for light-water Nuclear Power Reactors. ML0316310162003-05-23023 May 2003 Report of Changes, Tests and Experiments, 10CFR50.59 Summary Report, Design Change Packages Through 50.59 Review Coversheet Form ML0315402802003-05-23023 May 2003 Report of Changes, Tests and Experiments, Special Process Procedures (Spp), Special Process Procedures Through 50.59 Review Coversheet Form ML0315401942003-05-23023 May 2003 Report of Changes, Tests and Experiments, Engineering Requests (Er), Engineering Requests Through 50.50 Review Coversheet Form 2024-04-10
[Table view] Category:Letter type:BYRON
MONTHYEARBYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023 Unit 2 - 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 BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements BYRON 2023-0022, 2022 Annual Radiological Environmental Operating Report (AREOR)2023-05-0404 May 2023 2022 Annual Radiological Environmental Operating Report (AREOR) BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-04-0606 April 2023 Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements BYRON 2023-0012, Cycle 26 Core Operating Limits Report2023-03-16016 March 2023 Cycle 26 Core Operating Limits Report BYRON 2022-0081, CFR72.48 Evaluation Summary Report2022-12-0909 December 2022 CFR72.48 Evaluation Summary Report BYRON 2022-0072, Steam Generator Tube Inspection Report for Refueling Outage 232022-10-27027 October 2022 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2022-0069, 2021 Regulatory Commitment Change Summary Report2022-10-13013 October 2022 2021 Regulatory Commitment Change Summary Report BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment2022-10-13013 October 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment BYRON 2022-0065, Registration of Use of Cask to Store Spent Fuel2022-10-13013 October 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0063, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 20222022-09-29029 September 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report for September 9, 2021 to September 8, 2022 BYRON 2022-0064, Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed)2022-09-28028 September 2022 Letter 2022-0064 Submittal of Byron Integrated Initial License Training Examination Materials(Signed) BYRON 2022-0059, Registration of Use of Cask to Store Spent Fuel2022-09-15015 September 2022 Registration of Use of Cask to Store Spent Fuel BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022 Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) BYRON 2022-0026, Annual Radiological Environmental Operating Report2022-05-0505 May 2022 Annual Radiological Environmental Operating Report BYRON 2022-0030, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report2022-05-0303 May 2022 Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Report BYRON 2022-0028, Cycle 24 Core Operating Limits Report2022-04-28028 April 2022 Cycle 24 Core Operating Limits Report BYRON 2022-0016, Annual Dose Report for 20212022-04-0707 April 2022 Annual Dose Report for 2021 BYRON 2021-0072, Post Exam Submittal Letter2021-10-28028 October 2021 Post Exam Submittal Letter BYRON 2021-0033, Submittal on Initial Operator Licensing Examination Outline2021-10-28028 October 2021 Submittal on Initial Operator Licensing Examination Outline BYRON 2021-0063, Reactor Coolant System Pressure and Temperature Limits Report2021-09-28028 September 2021 Reactor Coolant System Pressure and Temperature Limits Report BYRON 2021-0064, Cycle 25 Core Operating Limits Report2021-09-28028 September 2021 Cycle 25 Core Operating Limits Report BYRON 2021-0032, 2020 Annual Radiological Environmental Operating Report (AREOR)2021-05-0606 May 2021 2020 Annual Radiological Environmental Operating Report (AREOR) BYRON 2021-0031, 2020 Annual Radioactive Effluent Release Report2021-04-21021 April 2021 2020 Annual Radioactive Effluent Release Report BYRON 2021-0027, Annual Dose Report for 20202021-03-30030 March 2021 Annual Dose Report for 2020 BYRON 2021-0023, Registration of Use of Cask to Store Spent Fuel2021-03-25025 March 2021 Registration of Use of Cask to Store Spent Fuel BYRON 2021-0024, 2020 Regulatory Commitment Change Summary Report2021-03-19019 March 2021 2020 Regulatory Commitment Change Summary Report BYRON 2021-0001, Day Inservice Inspection Report for Interval 4, Period 2, (B2R22)2021-01-13013 January 2021 Day Inservice Inspection Report for Interval 4, Period 2, (B2R22) BYRON 2020-0087, National Pollutant Discharge Elimination System (NPDES) Permit No. IL00483132020-12-16016 December 2020 National Pollutant Discharge Elimination System (NPDES) Permit No. IL0048313 BYRON 2020-0084, 10 CFR 72.48 Evaluation Summary Report2020-12-10010 December 2020 10 CFR 72.48 Evaluation Summary Report BYRON 2020-0085, 10 CFR 50.59 Summary Report2020-12-10010 December 2020 10 CFR 50.59 Summary Report BYRON 2020-0067, Cycle 22 Core Operating Limits Report2020-10-20020 October 2020 Cycle 22 Core Operating Limits Report BYRON 2020-0063, Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo2020-10-0101 October 2020 Independent Spent Fuel Storage Installation - Transmittal of Annual Radioactive Effluent Release Repo BYRON 2020-0053, Steam Generator Tube Inspection Report for Refueling Outage 232020-09-10010 September 2020 Steam Generator Tube Inspection Report for Refueling Outage 23 BYRON 2020-0025, Annual Dose Report 20192020-03-24024 March 2020 Annual Dose Report 2019 BYRON 2020-0015, Cycle 24 Core Operating Limits Report2020-03-17017 March 2020 Cycle 24 Core Operating Limits Report BYRON 2020-0010, Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 172020-02-13013 February 2020 Revision to Byron Station Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 17 BYRON 2020-0008, 2019 Regulatory Commitment Change Summary Report2020-02-0707 February 2020 2019 Regulatory Commitment Change Summary Report BYRON 2019-0105, Post Examination Submittal Letter2019-11-26026 November 2019 Post Examination Submittal Letter BYRON 2019-0095, Registration of Use of Cask to Store Spent Fuel2019-10-10010 October 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0090, Registration of Use of Cask to Store Spent Fuel2019-09-18018 September 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0078, Registration of Use of Cask to Store Spent Fuel2019-08-22022 August 2019 Registration of Use of Cask to Store Spent Fuel BYRON 2019-0041, Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 162019-04-25025 April 2019 Revision to Site Security Plan, Safeguards Contingency Plan, Training and Qualification Plan, and Independent Spent Fuel Storage Installation Plan, Revision 16 2024-05-09
[Table view] |
Text
Exel n,,~
8yron Station
'vvvvw,c~x('ion(()r p.COn"i Nuclear 44S0 North Cerrndn Crun.hRoJd Byron, 'L 61010-9794 March 1, 2010 LTR; BYRON 2010-0017 File: 1.10.0101 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
2009 Regulatory Commitment Change Summary Report Enclosed please find the "Regulatory Commitment Change Summary Report" for Byron Station.
This report contains summary information from January 1, 2009 through December 31, 2009.
Revisions to docketed regulatory commits were processed using the current revision of Nuclear Energy Institutes' document NEI 99-04, "Guidelines for Managing Nuclear Regulatory Commission (NRC) Commitment Changes."
If you have any questions concerning this report, please contact David Gudger, Regulatory Assurance Manager at (815) 406-2800.
Respectfully, Daniel J. Enright Site Vice President Byron Station DJE ffLHI cy Enclosure
ATTACHMENT BYRON STATION REGULATORY COMMITMENT CHANGE
SUMMARY
REPORT FOR 2009 Original Document and Commitment:
Commitment AR 10651 - Response to NRC Generic Letter 89-13 letter to US NRC from M. H.
Richter, Commonwealth Edison Co., dated January 29, 1990. Quarterly scheduled Essential Service Water (SX) make-up pump performance test will identify significant fouling of piping between the river screen house and the SX cooling towers. Fouling will be detected by trending the throttle position of the pumps discharge valve required to achieve proper pump differential pressure and flow rate.
Subject of Change:
Change made: Currently the SX make-up pumps discharge valves are operated at locked full open. An evaluation of potential fouling is completed by trending pump differential pressure and flow rate.
The change is needed to indicate the station is trending for fouling based off of the flow rate and differential pressure, not by throttling the OSX029A1B valves. The Generic Letter 89-13 requirements continue to be satisfied.
Status:
The commitment was changed under Commitment Change Number 09-008.
LS-AA-110 Revision 6 Page 14 of 29 ATTACHMENT 1 Commitment Change Evaluation Form Part 1: Commitment Change Description Page 1 of 7 Commitment Change Tracking # CJ9 -tJE:3 (Provided by Licensing/Regulatory Assurance as applicable)
CT Number: ~L /39 -0 Commitment Source Document: ~B...JQ\#61 J]CMT trcorcL9.D-l81QO k:. .-::r Requestor: Tony Ziegelbauer Dept: PEO Date: >J.!.!-I.!!1.. Phone: 2090 Functional Area Manager Approval: l utt 1t7l1!,~61 KrJ;/llnn l~ate: 51J1.Jo't Phone: 0fR I LicenslngiRegulatory Assurance ,auor.1Jw. ! <... r. IY r r:, -, Dolo: "I!-J!L Ph0110: ? V'J Commitment Tracking Coordinator. ~rt1ul11 ,Ill lO 1'..1111-- u Date: -iJJl,09 2f2..() I
. Phone:
Orioinal Commitment
Description:
See Attachment 2 Revised Commitment
Description:
See Attachment 2 JustificatiQfl for Change The;~tS needed to indicate the station is trending for fouling based off of the flow rate and differential I press ,ot by throttling the OSX029A1B.
Is there a potential adverse reoulatorv impact? Explain No, the station has been and will continue to meet the intent of Commitment Letter 90-08400 by trending for fouling in the SX make-up lines.
I Summarize and attach part 2 (i.e. what is the appropriate change process?)
The commitment may be changed. Obtain management approval on Part 1.
SRS 5A.106 or 5A.107 I Notify NRC in next annual Commitment Change Summary Report or UFSAR Update? .L YES NO
LS-AA-110 Revision 6 Page 15 of 29 ATTACHMENT 1 Commitment Change Evaluation Form Part 2: Determination of Appropriate Change Process Page 2 of 7 NOTE: The following questions correlate to the Figures 1 and 2 decision process flowcharts.
- 1. Is the existing commitment located in the Updated Final Safety Analysis Report, Emergency Plan, Quality Assurance Plan, Fire Protection Program, Security Plan, or Decommissioning Plan (Le. 10 CFR 50.54(a), 10CFR50.54(p), 10CFR50.54(q),
10CFR50.82(a), 10CFR72.48, 10CFR50.71(e))?
NOTE: Certain types of commitments described in the UFSAR do not require evaluation under a codified process, (e.g., 10 CFR 50.59), and therefore should be evaluated within the commitment management program. (Reference Decision 1 of Attachment 2.)
~ Continue with Question 2.
Yes. STOP. Refer to and use the codified process as appropriate to evaluate commitment. This form may be discarded.
- 2. Could the change negatively impact the ability of a structure, system, or component to perform its safety function or negatively impact the ability of personnel to ensure the structure, system or component is capable of performing its intended safety function?
(Reference Fig. 2 of Attachment 2.)
~ Briefly describe the rationale and continue with Question 3.
This change does not impact how the system is operated.
Yes. Perform an evaluation using 10 CFR 50.92 criteria. Does a significant hazard consideration exist?
LS*AA*110 Revision 6 Page 16 of 29 ATTACHMENT 1 Commitment Change Evaluation Form Part 2: Determination of Appropriate Change Process Page 30f7 Yes. STOP. DO NOT MAKE THE CHANGE. Work through Licensing/Regulatory Assurance to obtain prior NRC approval prior to making the change. This form may be discarded.
No. Attach a copy of the evaluation and continue with Question 3.
NOTE: If the original commitment was made in response to a NRC Notice of Violation and has been implemented for less than two years, then supplement the NRC Notice of Violation response identifying that the commitment is being changed or deleted, as applicable. This supplement to the violation should be submitted to the NRC prior to making the commitment change. .
- 3. Was the original commitment (e.g., response to NOV, NCV etc.) necessary for compliance with an obligation (Le., rule, regulation, Order, or license. condition?
No. Continue with Question 4.
~. Does the changed commitment preserve compliance?
No. EXIT PROCESS. DO NOT MAKE THE CHANGE.
Work with Licensing/Regulatory Assurance to obtain prior NRC approval before making the change. This form may be discarded.
~ Briefly describe the rationale and proceed to Question 6.
The station has been and will continue to meet the intent of Commitment Letter 90-08400 by trending for fouling in the SX make-up lines.
- 4. Was the original commitment:
- a. Explicitly credited as the basis for a safety decision in an NRC SER,
LS*AA*110 Revision 6 Page 17 of 29 ATTACHMENT 1 Commitment Change Evaluation Form Part 2: Determination of Appropriate Change Process Page 4 of 7 OR
- b. Made in response to an NRC Bulletin or Generic Letter, OR
- c. Made in response to a request for information under 10 CFR 50.54(f),
10 CFR 2.204, or a Confirmatory Action Letter.
OR
- d. Identified as a corrective action in response to a NRC Notice of Violation?
rI (~+\e No. Continue with Question 5.
Go to Question 6.
- 5. Was the original commitment made to minimize recurrence of an adverse condition (Le.,
a promise to take a corrective action by a given date stated in an LER)?
@ STOP. The commitment may be changed without NRC notification. Obtain management approval on Part 1, and submit to Licensing/Regulatory Assurance.
Yes. Is the changed commitment necessary to minimize recurrence of the adverse condition?
No. STOP. The commitment may be changed without NRC notification.
Document rationale, obtain management approval on Part 1, and submit to Licensing/Regulatory Assurance.
Yes. STOP. The commitment may be changed. Obtain management approval on Part 1, and submit to Regulatory Assurance/
Licensing for notification to the NRC in the next annual Commitment Change Summary Report or UFSAR Update.
I I
LS-AA*110 Revision 6 Page 18 of 29 ATTACHMENT 1 Commitment Change Evaluation Form Part 2: Determination of Appropriate Change Process Page 50f7
- 6. Has the original commitment been implemented?
No. EXIT PROCESS. Work with Licensing/Regulatory Assurance to provide notification of the changed commitment to the NRC. This will be accomplished by submitting a supplement of the original document.
Notification to the NRC of the intent to change a commitment should be made as soon as practicable after the change is approved by licensee management but before any committed completion date. Timely notification should normally be made within 30 days or before the committed completed date whichever is sooner. This form may be discarded.
STOP. The commitment may be changed. Obtain management approval on Part 1, and submit to Licensing/Regulatory Assurance for notification of the NRC in the next annual Commitment Change Summary Report or UFSAR Update.
Attachment 2 Original Commitment
Description:
Genelic Letter 89-13 item I requires: Implementation and Maintenance of an ongoing program of Surveillance and Control Techniques to significantly reduce the incidence of flow blockage problems as a result of bio-fouling. In response to this requirement, Byron Station, via Corporate Response of Reference 2 committed to a Surveillance Technique "A", which states in part" ... Quarterly scheduled SX make-up pump performance test will identify significant fouling of piping between the RSH and the SX cooling Tower."
To enhance OBVS O.5-3.SX.l-l, a step will be added to record the pump discharge valve throttle position required to achieve proper pump differential pressure and flow rate.
Revised Commitment
Description:
Generic Letter 89-13 item I requires: Implementation and Maintenance of an ongoing program of Surveillance and Control Techniques to significantly reduce the incidence of flow blockage problems as a result of bio-fouling. In response to this requirement, Byron Station, via Corporate Response of Reference 2 committed to a Surveillance Technique "A", which states in part " ... Quarterly scheduled SX make-up pump performance test will identify significant fouling of piping between the RSH and the SX cooling Tower~"
Currently the OSX029NB are operated at locked full open and is documented in procedures, OBVSR 5.5.8.SX.5-1I2AfB and OBOSR 5.5.8.SX.5-1I2C and an evaluation of a potential degraded condition is completed by trending pump differential pressure and flow rate for fouling or pump degradation.