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Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARL-PI-16-010, Reply to Notice of Violation; VIO 05000306/2015008-012016-02-0404 February 2016 Reply to Notice of Violation; VIO 05000306/2015008-01 L-PI-13-083, Reply to a Notice of Violation2013-08-28028 August 2013 Reply to a Notice of Violation L-PI-11-071, Prairie Island. Units 1 & 2, Supplemental Information Regarding Inspection Report 05000282/2011010; 05000306/2011010 (EA-11-110)2011-07-13013 July 2011 Prairie Island. Units 1 & 2, Supplemental Information Regarding Inspection Report 05000282/2011010; 05000306/2011010 (EA-11-110) L-PI-11-039, Response to Violation in Nuclear Regulatory Commission (NRC) Exercise of Enforcement Discretion Inspection Report 05000282/2011008; 05000306/2011008 (EA-11-029)2011-04-20020 April 2011 Response to Violation in Nuclear Regulatory Commission (NRC) Exercise of Enforcement Discretion Inspection Report 05000282/2011008; 05000306/2011008 (EA-11-029) L-PI-10-060, Supplemental Information Regarding NRC Inspection Report 05000282/2010010, 05000306/2010010 (EA-10-070)2010-06-14014 June 2010 Supplemental Information Regarding NRC Inspection Report 05000282/2010010, 05000306/2010010 (EA-10-070) L-PI-09-078, Position on a Green Non-Cited Violation2009-06-12012 June 2009 Position on a Green Non-Cited Violation L-PI-08-101, Position on Two Apparent Violations and Preliminary White Findings, EA-08-272 and EA-08-2732008-12-0505 December 2008 Position on Two Apparent Violations and Preliminary White Findings, EA-08-272 and EA-08-273 L-PI-06-068, Response to an Apparent Violation in Inspection Report 05000282/2006013; 05000306/2006013; EA-06-1622006-08-14014 August 2006 Response to an Apparent Violation in Inspection Report 05000282/2006013; 05000306/2006013; EA-06-162 L-PI-05-059, Reply to Non-Cited Violation 05000306-05-003-022005-06-13013 June 2005 Reply to Non-Cited Violation 05000306-05-003-02 2016-02-04
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(l Xcel Energy AUG 2 8 2013 L-PI-13-083 10 CFR 2.201 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Reply to a Notice of Violation Pursuant to the provisions of 10 CFR 2.201, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby submits a written statement in reply to the Notice of Violation included with NRC Inspection Report 05000282/2013003; 05000306/2013003 for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, dated July 30, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13212A038).
This violation was cited because of failure to restore compliance with NRC regulations in 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", (Maintenance Rule) after the NRC identified a non-cited violation in 2011 and NSPM identification of additional issues approximately 18 months ago.
The enclosure to this letter provides the following information required by 10 CFR 2.201 and requested in the Notice of Violation:
( 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, and (4) the date when full compliance will be achieved.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
d~ti Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC
Enclosure Reply to Notice of Violation Cited Violation During an NRC inspection conducted from April 1 to June 30, 2013, at the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Title 10 CFR 50.65(a)(1), requires, in part, that the holders of an operating license shall monitor the performance or condition of structures, systems and components (SSCs) within the scope of the rule as defined by 10 CFR 50.65(b),
against licensee-established goals, in a manner sufficient to provide reasonable assurance that such SSCs are capable of fulfilling their intended functions.
Title 10 CFR 50.65(a)(2) states, in part, that monitoring as specified in 10 CFR 50.65(a)(1) is not required where it has been demonstrated that the performance or condition of an SSC is being effectively controlled through the performance of appropriate preventive maintenance, such that the SSC remains capable of performing its intended function.
Contrary to the above, from November 11, 2011 through June 30, 2013, the Prairie Island Nuclear Generating Plant, Units 1 and 2, failed to demonstrate that the performance or condition of SSCs specified in 10 CFR 50.65(b) were being effectively controlled through the performance of appropriate preventive maintenance. In addition, the Prairie Island Nuclear Generating Plant, Units 1 and 2, failed to establish goals sufficient to provide reasonable assurance that such SSCs were capable of performing their intended safety function after demonstrating that the condition of the SSCs was not being effectively controlled through the performance of appropriate preventive maintenance. Specifically, goals sufficient to provide reasonable assurance that the D5/D6 ventilation system and the 21 inverter were capable of fulfilling their intended functions were not established after the demonstration showing that the performance or condition of these systems was being effectively controlled became invalid. In addition, more than 300 examples existed where the monitoring described in 10 CFR 50.65(a)(2) had not been performed.
This violation is associated with a Green Significance Determination Process finding.
Reason for the Violation Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM), failed to monitor structures, systems and components (SSCs) specified in 10 CFR 50.65. The causes for this failure were identified as follows:
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Enclosure
- Inadequate Organizational Structure: Engineering management has disregarded the Maintenance Rule (MR) Program by leaving the Maintenance Rule Coordinators (MRCs) exclusively responsible for assuring 10 CFR 50.65 requirements were met for PINGP.
- Inadequate Standards and Enforcement: The plant staff has not been consistently sensitive to MR regulatory concerns. MR regulatory issues have not received the needed level of plant visibility and ownership to ensure all aspects are addressed from problem identification (Corrective Action Program) through issue resolution.
Corrective Steps That Have Been Taken and the Results Achieved NSPM has taken the following actions at PINGP in response to the conditions described in the Notice of Violation:
- The Maintenance Rule Expert Panel (MREP) reviewed more than 300 outstanding Maintenance Rule Evaluations (MREs) which includes the D5/D6 ventilation, 21 inverter and the more than 300 examples (backlog) specifically cited in the Notice of Violation.
- As the result of this review, the D5/D6 ventilation, 21 inverter and other systems in the MRE backlog were classified for monitoring within the provisions of 10 CFR 50.65(a)(1).
- Radiation Monitors were evaluated for inclusion in the MR Program scope under 10 CFR 50.65(b)(2)(i) at an MREP meeting. The Radiation Monitor basis document was approved by the MREP.
- The Radiation Monitoring System was classified for monitoring within the provisions of 10 CFR 50.65(a)(1) at an MREP meeting.
Corrective Steps That Will Be Taken NSPM will take the following steps in accordance with the Corrective Action Program to restore compliance:
- MREP will complete the review and disposition of outstanding (backlog) MREs from November 11, 2011 to June 30, 2013.
- Emergency Operating Procedure (EOP) equipment will be evaluated by the MREP for inclusion in the MR Program scope under 10 CFR 50.65(b)(2)(i).
Applicable EOP equipment will be added to the MR Program.
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Enclosure
- Performance of EOP equipment included in the MR Program will be compared to the new performance criteria and the EOP equipment will be properly classified for monitoring within the provisions of 10 CFR 50.65(a)(1) or 10 CFR 50.65(a)(2).
- Plant system engineers will review the PINGP power history for the last two years to assure plant level events have been appropriately captured in the MR Program. Results will be presented to the MREP.
- Plant system engineers will review PINGP Licensee Event Reports for the last two years to assure they were appropriately captured in the MR Program.
Results will be presented to the MREP.
- MR Program systems will be evaluated to assure they have been properly classified for monitoring within the provisions of 10 CFR 50.65(a)(1) or 10 CFR 50.65(a)(2). Results will be presented to the MREP.
NSPM will take the following steps to prevent recurrence:
- Revise fleet procedure FP-E-MR-05, Maintenance Rule Expert Panel (MREP) to include MRC experience requirements under Section 5.2.2, Expert Panel Member Specific Experience Requirements. The minimum requirements shall be five years of nuclear power plant experience and two years PINGP engineering experience.
- Develop and implement Roles and Responsibilities for regulatory program positions and qualified full-time equivalents (backups) identified on the engineering organizational chart. This will include daily, weekly, monthly, quarterly, and annual requirements for these positions. Implementation will include roles and responsibilities procedure development for the PINGP Engineering Department.
- Develop and implement a Program Engineering Steering Committee to monitor the effectiveness of engineering program health and implementation, and provide the appropriate level of management oversight and line ownership. Completion of this action will include defining the charter, identifying the members, and implementing monthly meetings.
- Evaluate and implement industry standard (benchmarking) prerequisite requirements for the MRC position.
- Create an engineering supervisor position to oversee MR and Mitigating System Performance Index (MSPI) Program recovery efforts; this position will report to the Equipment Reliability Manager and directly supervise the MRC position.
- Develop and implement a knowledge transfer procedure to ensure subject matter expert knowledge can be captured.
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Enclosure
- Develop a comprehensive desk guide for the MRC position to consistently maintain the continuity of MRC duties required per fleet procedure FP-E-MR-05.
Date When Full Compliance Will Be Achieved For the violation described above, full compliance will be achieved by March 28, 2014.
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