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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARW3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2021-0028, Response to an Apparent Violation in NRC Inspection Report 05000382/2021013; EA-20-1142021-04-0202 April 2021 Response to an Apparent Violation in NRC Inspection Report 05000382/2021013; EA-20-114 W3F1-2019-0045, Updated Reply to a Notice of Violation; NRC Inspection Report 05000382/20180082019-06-20020 June 2019 Updated Reply to a Notice of Violation; NRC Inspection Report 05000382/2018008 W3F1-2019-0033, (Waterford 3) - Reply to Notice of Violation EA-18-020 Supplement2019-05-17017 May 2019 (Waterford 3) - Reply to Notice of Violation EA-18-020 Supplement W3F1-2018-0073, (Waterford 3) - Reply to a Notice of Violation; NRC Inspection Report 05000382/20180082018-12-14014 December 2018 (Waterford 3) - Reply to a Notice of Violation; NRC Inspection Report 05000382/2018008 W3F1-2018-0056, Reply to Notice of Violation EA-18-0202018-09-12012 September 2018 Reply to Notice of Violation EA-18-020 W3F1-2013-0072, Reply to a Notice of Violation: EA-12-2572013-12-18018 December 2013 Reply to a Notice of Violation: EA-12-257 W3F1-2012-0097, Reply to a Notice of Violation: EA-12-1982012-12-0303 December 2012 Reply to a Notice of Violation: EA-12-198 W3F1-2009-0043, Reply to Non-Cited Violation2009-09-16016 September 2009 Reply to Non-Cited Violation ML0629303022006-10-18018 October 2006 Response to NRC Inspection Report 05000382/2006009 Notice of Violation W3F1-2006-0053, Reply to Notice of Violation: EA-06-1362006-09-29029 September 2006 Reply to Notice of Violation: EA-06-136 W3F1-2006-0048, Reply to Notice of Violation: EA-06-1922006-09-18018 September 2006 Reply to Notice of Violation: EA-06-192 W3F1-2004-0040, Reply to Notice of Violation, EA-03-230, NRC Inspection Report No. 50-382/03-0072004-05-12012 May 2004 Reply to Notice of Violation, EA-03-230, NRC Inspection Report No. 50-382/03-007 2023-02-20
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Text
Entergy Nuclear South A- Entergy Operations Inc.
17265 River Road
`En terg Killona, LA 70057 Tel 504 739 6247 Fax 504 739 6698 kcook@entergy.com Kimberly S. Cook Director, Nuclear Safety Assurance Nuclear Safety Assurance Waterford 3 W3F1-2006-0048 September 18, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Reply to Notice of Violation: EA-06-192 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
REFERENCE:
- 1. Letter from dated D.N. Graves (NRC) to J.E. Venable (Entergy) dated August 18, 2006, Waterford Steam Electric Station Unit 3 - NRC Integrated Inspection Report 05000382/2006003 and Notice of Violation
Dear Sir or Madam:
In the referenced letter, the NRC documented a violation of 10 CFR 50, Appendix B, Criterion III, involving the failure of Entergy Operations, Inc. (Entergy) to translate into specifications, procedures, and instructions the design criteria for the emergency diesel generator air start system since being identified in September 2003. Entergy has evaluated the Notice of Violation and does not contest the violation or dispute the basis for the Severity Level IV cited violation.
Pursuant to the provisions of 10 CFR 2.201, Entergy hereby submits the reply to the Notice of Violation. The reply is provided in Attachment 1 to this letter. The reply addresses (1) the reason for the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
This submittal contains new commitments that are identified in Attachment 2. If you have any questions or require additional information, please contact Robert Murillo at (504) 739-6715.
Sincerely, KSC/RJM/MEM/ssf Attachments: 1. Reply to Notice of Violation: EA-06-192
- 2. List of Regulatory Commitments
W3F1-2006'-0048 Page 2 cc: (w/Attachments)
Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Mel B. Fields MS O-7E1 Washington, DC 20555-0001 (w/o Attachment 2)
Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers 95 Glastonbury Blvd - Suite 300 Glastonbury, CT 06033-4443
Attachment I to W3FI -2006-0048 Reply to Notice of Violation, EA-06-192
Attachment 1 to "W3FI-2006-0048 Page 1 of 4 Reply to a Notice of Violation; EA-06-192 1.0 Restatement of Violation During an NRC inspection completed on July 7, 2006 and documented in NRC Inspection Report 05000382/2006003, a violation of NRC requirements was identified.
In accordance with the NRC Enforcement Policy, the violation is listed below.
"10 CFR 50, Appendix B, Criterion III, 'Design Control,' requires, in part, that applicable regulatory requirements and the design basis for systems to which Appendix B applies are correctly translated into specifications, procedures, and instructions. The Final Safety Analysis Report requires that the diesel generator air start system be capable of providing sufficient air capacity to start each diesel a minimum of five times.
Contrary to the above, the licensee failed to translate into specifications, procedures, and instructions the design criteria for the diesel generator air start system. This resulted in the failure to maintain each diesel generator air receiver capable of starting the diesel engine five times as required since being identified in September 2003.
This violation is associated with a Green SDP finding."
2.0 Reason for the Violation The reason for the violation is that Waterford 3 did not consistently pursue the resolution of the issue with a sense of urgency. Other contributing factors were that the Waterford 3 initial resolution approach was based on partial technical information, Waterford 3 did not effectively plan and prioritize the tasks required for timely resolution, and Waterford 3 placed overreliance on an analytical solution.
On September 5, 2003, Waterford 3 issued Condition Report CR-WF3-2003-2502 to document the NRC position that Waterford 3 is not in compliance with General Design Criteria 17 for five-start capability for the diesel generator air start system.
The initial technical resolution undertaken by Waterford 3 was to prepare a license amendment for NRC review and approval for four-start capability for the diesel generator air start system. However, at the time this decision was made, there was neither additional analysis nor additional testing in place, other than initial plant startup data, that would provide a substantive technical basis for a four-start license amendment.
Therefore, the initial decision was predicated on partial technical information.
Attachment I to
,W3F1-2006-0048 Page 2 of 4 Many collaborative efforts were taken over a long period of time to determine the analytical and testing baseline required to support a license amendment for four-start capability. However, these efforts were unsuccessful in achieving timely resolution.
In January 2006, Waterford 3 performed a test of the diesel generator air start system, and the diesel started four times. In April 2006, Waterford 3 completed an updated analysis of the January 2006 test data that concluded the diesel generator starting air system had five-start capability, with small margin, if time dependent variables, such as starting air system leakage are excluded. The January 2006 test and the analysis of the test data did not demonstrate five-start capability because the diesel started four times during the test, and the analysis did not account for technical factors discussed in NRC Inspection Report 05000382/2006003. Therefore, Waterford 3 personnel relied on the analytical treatment of data to conclude the diesel generator starting air system had five-start capability.
In summary, Waterford 3, based on partial technical information, placed too much emphasis on an analytical solution to the issue.
3.0 Corrective Steps Taken and the Results Achieved The following are the corrective steps that have been taken and the results that have been achieved.
Operations Procedure, OP-100-014, was updated in September 2003 to specify the operational requirements for the diesel generator starting air system. This change was made as a compensatory measure pursuant to Generic Letter 91-18 (RIS 2005-20).
This issue is still being tracked as a RIS 2005-20 issue due to non-conformance with Standard Review Plan 9.5.6, five start capacity requirement. There was no actual degradation of the diesel generator starting air system. The diesel generator starting air system remains operable and capable of performing its safety function.
The Licensing Manager and the Manager, Corrective Actions and Assessments, have conducted a review of Waterford 3 RIS 2005-20 issues and other regulatory issues to assess the approach for and the timeliness of the resolution. The Site Senior Management has been briefed on the initial assessment. Additional efforts will be taken as discussed in Section 4.0 of this attachment.
4.0 Corrective Steps to be taken to Avoid Further Violations The following are the corrective steps that will be taken to prevent recurrence.
Waterford 3 will implement a modification to the diesel generator starting air system to provide additional margin beyond the 5 start capacity requirement of Standard Review Plan 9.5.6. The modification will include an approximate target of an additional thirty percent margin to each of the four receivers for the two diesel generator starting air systems, beyond the 5 start capacity requirement of Standard Review Plan 9.5.6. The modification is expected to be completed by May 31, 2007.
Attachment I to W3F1 -2006-0048 Page 3 of 4 This schedule includes the time for engineering analysis, contract development, hardware installation, testing, and design records completion. Also, the schedule takes into consideration Refuel 14 commencing in November 2006 and ending the latter part of December 2006 for which resources are already or will be committed for engineering and licensing work.
Appropriate operational procedures will be revised to establish the operational requirements, for example, number of receivers and minimum receiver pressure, for the diesel generator starting air system.
Waterford 3 has selected the diesel generator air start system modification as the resolution because this alternative provides additional margin, and the proposed resolution is the most expeditious course of action for resolution.
Prior to implementing the modification, Waterford 3 will perform another test of the diesel generator air start system before the end of September 2006. The purpose of this test is to establish a more accurate baseline for the current capacity of the diesel generator air start system, which can then be used as an input into the planned modification.
The NRC technical issues documented in NRC Inspection Report 05000382/2006003 will be addressed as follows:
Air Leakage The analysis of the January 2006 test removed most of the affect of system leakage in Calculation ECM98-017. Upon completion of the diesel generator starting air system test, currently scheduled before the end of September 2006, Waterford 3 will revise the calculation to analyze the new data. The revised analysis will no longer include the removal of the system leakage between starts.
Rolling Resistance and Temperature Effects Analysis of the January 2006 test results in Calculation ECM98-017 did not completely address rolling resistance and temperature effects. The calculation will be revised to analyze the new data from the September 2006 test. The revision will address rolling resistance and temperature effects.
Regarding the effective and timely resolution of this regulatory issue, a review will be completed of regulatory issues that are complex and long term in nature to ensure the resolution approach is appropriate and timely. A review will also be performed of the process for monitoring and resolving complex and long term regulatory issues. This evaluation will be completed by November 15, 2006. Appropriate changes will be implemented that improve the monitoring and timely resolution of such regulatory issues.
Attachment 1 to
- W3F1-2006-0048 Page 4 of 4 5.0 Date when Full Compliance will be Achieved Waterford 3 will be in full compliance by May 31, 2007 after completion of the modification for the diesel generator starting air system and update of the corresponding operational, design, and licensing basis documentation.
Attachment 2 to W3Fi -2006-0048 List of Regulatory Commitments to
,W3F1-2006-0048 Page 1 of I List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check One) SCHEDULED ONE- COMPLETION TIME CONTINUING DATE COMMITMENT ACTION COMPLIANCE (If Required)
A review will be completed of regulatory November 15, 2006 issues that are complex and long term in nature to ensure the resolution approach is appropriate and timely. A review will also be performed of the process for monitoring and resolving complex and long term regulatory issues. This evaluation will be completed by November 15, 2006.
Appropriate changes will be implemented that improve the monitoring and timely resolution of such regulatory issues.
Waterford 3 will be in full compliance by May 31, 2007 May 31, 2007 after completion of the modification for the diesel generator starting air system and update of the corresponding operational, design, and licensing basis documentation.
Prior to implementing the modification, September 30, Waterford 3 will perform another test of 2006.
the diesel generator air start system before the end of September 2006. The purpose of this test will be to establish a more accurate baseline for the current capacity of the diesel generator air start system, which can then be used as an input into the planned modification.