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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 NL-17-022, Reply to a Notice of Violation; EA-16-1932017-02-16016 February 2017 Reply to a Notice of Violation; EA-16-193 NL-16-116, Response to Integrated Inspection Report 05000247/2016002 and 05000286/2016002; Denial of Green Non-Cited Violation 05000286/2016002-022016-09-29029 September 2016 Response to Integrated Inspection Report 05000247/2016002 and 05000286/2016002; Denial of Green Non-Cited Violation 05000286/2016002-02 ML12354A4152012-12-0707 December 2012 Revision to the Reply to Notices of Violation Regarding Unapproved III.G.2 Operator Manual Actions ML12272A2872012-09-19019 September 2012 Violations of Federal Fire Safety Regulations at Indian Point Nuclear Reactors NL-12-122, Reply to Notices of Violation Regarding Unapproved III.G.2 Operator Manual Actions2012-09-17017 September 2012 Reply to Notices of Violation Regarding Unapproved III.G.2 Operator Manual Actions NL-10-022, Reply to Notice of Violation2010-03-0909 March 2010 Reply to Notice of Violation NL-08-039, Cynthia Carpenter Ltr. Reply of Notice of Violation EA-08-009 - Entergy Nuclear Operations, Inc2008-02-22022 February 2008 Cynthia Carpenter Ltr. Reply of Notice of Violation EA-08-009 - Entergy Nuclear Operations, Inc NL-08-034, Cynthia Carpenter Ltr. Notice of Violation and Proposed Imposition of Civil Penalty $650.000, Indian Point Nuclear Generating Unit Nos. 2 & 32008-02-22022 February 2008 Cynthia Carpenter Ltr. Notice of Violation and Proposed Imposition of Civil Penalty $650.000, Indian Point Nuclear Generating Unit Nos. 2 & 3 NL-07-070, Cynthia Carpenter Ltr. Reply to Notice of Violation EA-07-092 Regarding Failure to Meet Implementation Deadline NRC Order EA-05-1902007-05-23023 May 2007 Cynthia Carpenter Ltr. Reply to Notice of Violation EA-07-092 Regarding Failure to Meet Implementation Deadline NRC Order EA-05-190 NL-02-163, Amended Response to Notice of Violation and Proposed Imposition of Civil Penalty2002-12-31031 December 2002 Amended Response to Notice of Violation and Proposed Imposition of Civil Penalty NL-02-154, Reply to a Notice of Violation - EA-02-1622002-12-0909 December 2002 Reply to a Notice of Violation - EA-02-162 2024-06-18
[Table view] |
Text
A*~*Entergx Entergy Nuclear Operations. Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President NL-17-022 February 16, 2017 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk*
Washington, DC 20555-0001
Subject:
Reply to a Notice of Violation: EA-16-193 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26
Reference:
NRC letter dated January 17, 2017 "Indian Point Nuclear Generating -
lnt~grated Inspection Report 05000247/2016003 and 05000286/2016003 and Notice of Violation (EA-16-193)"
Dear Sir:
By letter dated January 17, 2017 (Reference), a violation for Indian Point Nuclear Generating Unit No. 2 (IP2) was issued for failure to conduct operations to minimize the introduction of residual radioactivity into the subsurface (groundwater) of the site.
Entergy Nuclear Operations, Inc. (Entergy) is not contesting the violation. This was entered into the Entergy Corrective Action Program as CR-IP2-2016-00264, CR-IP2-2016-00266, CR-IP2-2016-00564, CR-IP2-2016-04559, CR-IP2-2016-05060, and CR-IP2-2016-05814. The reply to the violation is contained in the Attachment to this letter.
Entergy is making no commitments in this letter. Should you have any questions regarding this matter, please contact* Mr. Robert Walpole, Manager, Regulatory Assurance, Indian Point Energy Center at (914) 254-6710.
Sincerely,
(
AJV/gd
NL-17-022 Docket No. 50-247 Page 2 of 2
Attachment:
Reply to a Notice of Violation; EA-16-193 cc: Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Douglas V. Pickett, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA NRC Resident Inspectors
.ATTACHMENT TO NL-17-022 Reply to a Notice of Violation; EA-16-193 ENTERGY NUCLEAR OPERATIONS, INC.
lnqian Point Nuclear Generating Unit No. 2 Docket No. 50-24 7 License No. DPR-26
. NL-17-022 Docket No. 50,.247 Attachment Page 1 of 4 REPLY TO A NOTICE OF VIOLATION; EA-16-193 Violation During an NRC inspection conducted between July 1 and September 23, 2016, a violation of NRC requirements was Identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Title 10 of the Code of Federal Regulations (10 CFR) 20.1406(c) requires, in part, that licensees shall, to the extent practical, conduct operations to minimize the introduction of residual radioactivity into the site, including the subsurface.
Contrary to the above, on two occasions between January 2016 and July 2016, Entergy failed to conduct operations to minimize the introduction of residual radioactivity into the subsurface of the site. Specifically, Entergy has not maintained its floor drain system clear of obstructions and interferences, and has not verified the ability of the floor drains to handle the volume and flowrates for draining activities being conducted. As a result, repeated spills of contaminated water within the radiologically controlled area leaked into the groundwater (subsurface of the site). Specifically, in January 2016, a spill caused by floor drain obstructions resulted in the backup of contaminated water onto the floor and subsequent leakage to the subsurface of the site. Similarly, a subsequent June/July 2016 groundwater contamination event occurred due to an obstructed flow path through a floor drain in the Unit 2 spent fuel building, which spilled to the subfloor and contaminated the subsurface of the site.
This violation is associated with a Green Significance Determination Process finding.
Reason for the Violation A Root Cause Evaluation was performed to determine the reason for the violation. This evaluation determined the following:
- The Direct Cause of the events was that activities as~ociated with transfer of reverse osmosis reject water during silica clean-up of Refueling Water Storage Tank inventory in preparation for the 2016 Unit 2 refueling outage resulted in groundwater contamination due to a spill in the Primary Auxiliary Building (PAB) on~o the 35' Service Water Pipe Chase and due to backflow from the Fuel Storage Building (FSB) Sump 28 through the drain line connected to the FSB T~uck Bay sub-floor.
/
- The root cause of these events is less than adequate plant organizational rigor in the implementation of Objective 1.2, Site Risk Assessment, of Nuclear Energy Institute (NEI)
Document 07-07, "NEI Industry Ground Water Protection Initiative."
\
NL-17-022 Docket No. 50-247 Attachment Page 2 of 4 Examples include identification and control of work practices, material condition of drain systems and implementation of actions to seal building seams that have a credible mechanism for licensed material to reach ground water.
Specifically, the site Radiological Groundwater Monitoring Program (RGWMP), which was developed using NEI 07-07, did not identify floor drains as a system with a credible means of contaminating groundwater, and did not adequately assess work practices to determine their potential for unintended groundwater releases. Also, the existing work management process at the time of the event did not reflect the appropriate level of risk and work priority for conditions that can result in unintended groundwater releases.
Corrective Steps Taken and Results Achieved Material Improvements:
Material conditions have been improved by making repairs to the floor drain system and Fuel Storage Building Sump Pump 28. The floor drain piping in the overhead of the 35' elevation of the Unit 2 Primary Auxiliary Building has been re-welded and integrity of the system restored.
Sump Pump 28 has been replaced which has restored the automatic level-dependent pumping fur:iction and the direct flow path to the PAS Sump Tank. The floor drain systems located in the radiologically controlled areas at both Units 2 and 3 have been cleaned and inspected.
Preventive maintenance work orders have been created to caus~ the periodic cleaning and inspection of the floor drain systems. These actions will help ensure that these drains remain capable of handling the volume and flowrate for expected draining activities. Further, a remediation well, designated RW-1, has been installed in the area of highest groundwater tritium concentration. This well is designed to reduce the inventory of tritium in this area and*
increase the sensitivity of the nearby monitoring wells.
Future enhancements consist of the following:
- The temporary or permanent plugging of the north sole plate drain line and the installation of a backwater valve in the subfloor drain line, both located in the FSB truck bay, are being evaluated by Engineering. Both of these drain lines were associated with the contamination found on the truck bay subfloor. These actions will help prevent the possibility of liquid back-flowing into the subfloor from the floor drain system.
- A plan is under development to harden site structures to minimize potential releases of radiologically-contaminated fluids to groundwater from normal and temporary plant systems and operations. These modifications may include installation of a high level alarm in FSB Sump 28, sealing and coating of the FSB Truck Bay subfloor, and sealing or replacing designated. building/structural joints that provide potential paths to groundwater.
NL-17-022 Docket No. 50-24 7 Attachment Page 3 of 4 Procedure and Process Improvements:
Improvements have been made to the site procedures associated with work activity risk analysis, EN-WM-104, "On Line Risk Assessment," and groundwater protection, IP-SMM-CY-110, "Radiological Ground Water Monitoring Program." The revision to EN-WM-104 improves the identification of activities that if performed incorrectly, can cause an unmonitored release or discharge of radioactive material to the environment. For example, the procedure specifically identifies as an environmental risk the use of temporary hoses or equipment containing radioactive liquids, and the use of floor drains for draining contaminated liquids. In response to this risk, mitigating actions are identified and applied to the work, such as assigning additional technical oversight or providing spill containment. Changes to IP-SMM-CY-110 include the establishment of a site Groundwater Protection Steering Committee and identification of site- ,
specific maintenance, operational and support activities which have the potential to result in groundwater contamination, as well as actions that can be taken to mitigate these adverse consequences. The intent of these changes is to introduce more rigor into the risk assessment process and to increase senior managementoversight of the groundwater protection program.
Site procedures 2-0SP-4.3.1, "Support Procedure-Spent Fuel Pit Cooling," and 3-SOP-SFP-003, "Operation of the Backup Spent Fuel Pool Cooling System," have been revised to include additional guidance requiring operators to confirm with Engineering that drain pathways are verified adequate for component draining prior to use, and to monitor the drain down to prevent leaks or spills. The intent of these changes is to introduce greater caution and oversight when
. utilizing floor drains for the draining of the supplemental heat exchanger at both units.
Intrusive Oversight and Assessment:.
A Groundwater Protection Steering Committee has been formed. The committee consists of senior representatives of those site departments having the greatest influence on groundwater protection, such as the General Manager of Plant Operations, Chemistry Manager and Radiation Protection Manager. The committee meets at a frequency specified in site procedure IP-SMM-CY-110 to evaluate the groundwater protection program, program roles and responsibilities and the effectiveness of its implementation.
Entergy has completed an internal self-assessment of the site groundwater protection program to help the site in identifying compliance gaps. Subject matter experts from the Electric Power Research Institute also conducted an assessment of the site implementation of the objectives listed in NEI 07-07. All enhancements, negative observations and standards deficiencies and their corresponding corrective actions have been or will be documented ,in the site corrective action program, where they will be tracked to closure.
NL-17-022 Docket No. 50-24 7 Attachment Page 4 of 4 Increased Awareness:
Station awareness of this event and the associated lessons learned has improved and
, continues to improve. Station management and staff were thoroughly briefed on the event, the cause evaluation, and consequences during a periodic Leadership & Alignment meeting, and again via a site-wide "tailgate" communication. A poster campaign to further engage site personnel is planned to coincide with the upcoming Unit 3 refueling outage that begins in March 2017. The purpose of this campaign i,s to raise employee awareness regarding contaminated liquids, and to align them to the goal of zero leaks or spills that could impact the environment.
Description of the More Comprehensive Corrective Action Plan for Maintaining an Effective Floor Drain System:
The open floor drain piping cuts at Unit 2 that resulted in the January 2016 event were re-welded to restore the integrity of the floor drain system. Additionally, the floor drains in the radiologically controlled areas at Units 2 and 3 were inspected and hydrolased and flushed by a third party that specializes in such work, with the goal being to remove debris and clogs to restore the floor drain flow capacity. This work, begun in February 2016, was successfully completed on June 3, 2016.
- Equipment Identification numbers have been established for the floor drains in the radiologically controlled areas at Units 2 and 3, and entered into the site Equipment Database. This ensures that work requests can be generated against specific floor drain issues, and tracked from issue identification through problem resolution.
New preventive maintenance items have been created to cause the floor drains located in radiologically controlled areas at Units 2 and 3 to be internally inspected, cleaned and flushed as necessary to maintain flow capacity. These actions were entered into the work control process on . November 28, 2016. The action and frequency of conducting this preventive maintenance is based on best industry practice.
- Date When Full Compliance Will Be Achieved:
Full compliance for the cited violation was achieved on November 28, 2016. The repairs, cleaning, and inspection of the floor drain systems at Units 2 and 3 were completed on June 3, 2016. Those activities restored the effectiveness of the floor drains in handling the flow of liquids. The preventive maintenance items created on November 28, 2016 will ensure that drains remain free of clogs and debris.