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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23100A1072023-04-10010 April 2023 Framatome Part 21 Report Re Erroneous Change of State for Circuit Breaker ML23229A0052022-02-11011 February 2022 Ametek Solidstate Controls, Final 10CFR21 Report of a Potential Defect, Vishay Diodes. Reference Interim Report ML21092A129 Issued April 1, 2021 ML21260A0072021-09-0909 September 2021 Ametek Solidstate Controls, Notification of Potential Defect - 10CFR Part 21 Report Re Omron Timer Relay ML21092A1292021-04-0101 April 2021 Ametek Solidstate Controls - Notification of Potential Defect ML20366A0472020-11-18018 November 2020 Curtiss-Wright 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid Batch 17BLVS293 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19121A1552019-04-15015 April 2019 Curtiss-Wright Nuclear Division, Enertech - 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML17354A0262017-11-27027 November 2017 Paragon Energy Solutions 10 CFR Part 21 Final Report of Potential Defect of Switch Assembly with OT-2 Homewood Products Corp Switch and Contact Block ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16342A9782016-12-0202 December 2016 ATC Nuclear - Part 21 - Pawl Fasteners Failed to Provide Sufficient Structural Support ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16139A8342016-05-10010 May 2016 Electroswitch - Transmittal of 10CFR Part 21 Reporting of Defects and Noncompliance Regarding Vendor Inspection of Electroswitch Corporation Docket No. 99900833 ML16098A4472016-03-21021 March 2016 Emerson Process Management, LLC - Part 21 Report Regarding Plug/Stem Assembly, Per Watts Bar ML16084A3022016-03-18018 March 2016 Emerson Process Management, LLC - Part 21 Report Regarding Groove Pin Dedication, Per Watts Bar ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML15049A4582015-02-0606 February 2015 Thermo Gamma-Metrics, LLC - Part 21 Report Regarding Shutdown Margin Monitor Environmental Qualification Noncompliance ML15014A0612015-01-0808 January 2015 Notification of Potential Part 21 Re Failure of Sbm Type Switches ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14329A0632014-11-19019 November 2014 Notification of Potential Part 21 Re Lack of Proper Power Supply Indication ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14261A1502014-09-17017 September 2014 Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14213A0992014-07-24024 July 2014 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches IR 05000391/20140012014-06-23023 June 2014 Construction Deficiency Report 50-391/2014-01 - Potential Opening of Littelfuse Part Number FLAS005.T Fuses - Final Report ML14174A0422014-06-23023 June 2014 Construction Deficiency Report 50-391/2014-01 - Potential Opening of Littelfuse Part Number FLAS005.T Fuses - Final Report ML14160A7832014-06-0303 June 2014 Part 21 Report Regarding Watts Bar, Unit 2, Potentially Defective Fuses Installed ML14364A1682014-06-0202 June 2014 Flowserve Corp., Vermont, Formal Evaluation of Deviations Reported - Notification of Defect - Watts Bar II ML14034A1882014-01-23023 January 2014 Part 21 Report Regarding Nonconformance of an Electrical Tubular Water Heater ML14042A2002014-01-21021 January 2014 Part 21 Report Regarding Non-Conformance of an Electrical Tubular Water Heater ML13256A1392013-09-13013 September 2013 Notification of Potential Part 21 Report Re Watts Bar Nuclear Plant, Unit 1 - Dresser Masoneilan Valve Stem/Plug Assemblies Found Out-of-Tolerance ML13234A1162013-08-16016 August 2013 Notification of Potential Part 21 Report - Auxiliary Feedwater Level Control Value Stem/Plug Assembly Out of Tolerance ML13204A3812013-07-18018 July 2013 Construction Deficiency Report 50-391/2013-01 - Commercial Grade Dedication Program - Final Report IR 05000391/20130012013-07-18018 July 2013 Construction Deficiency Report 50-391/2013-01 - Commercial Grade Dedication Program - Final Report IR 05000391/20130022013-06-27027 June 2013 Construction Deficiency Report 50-391/2013-02 - Instrument Sense Line Slope Issue - Final Report ML13182A4602013-06-27027 June 2013 Construction Deficiency Report 50-391/2013-02 - Instrument Sense Line Slope Issue - Final Report ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13161A3422013-06-0505 June 2013 ATC Nuclear, Interim Part 21 Report Involving Review of Seismic Testing Methodology ML13129A1762013-05-0606 May 2013 Construction Deficiency Report 50-391/2013-01 - Commercial Grade Dedication Program - Second Interim Report ML13091A3882013-03-28028 March 2013 Interim Part 21 Report Involving Review of Seismic Testing Methodology 2023-04-10
[Table view] Category:Letter
MONTHYEARCNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 2024-09-05
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 June 27, 2013 CDR-50-391/2013-02 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 10 CFR 50.55(e)Subject: Reference:
Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391 WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 -CONSTRUCTION DEFICIENCY REPORT 50-391/2013-02-INSTRUMENT SENSE LINE SLOPE ISSUE -FINAL REPORT TVA letter to NRC dated April 29, 2013, "Watts Bar Nuclear Plant (WBN) Unit 2 -Construction Deficiency report 50-391/2013-02-Instrument Sense Line Slope Issue -Interim Report" The purpose of this letter is to provide a final report for Construction Deficiency Report (CDR) 391/2013-02 regarding a condition that TVA has identified as a significant (programmatic)
breakdown in the instrument sense line installation program and, thus, a significant breakdown in a portion of TVA's quality assurance program. Walkdowns have been completed and have not identified examples where instrument line slopes as installed would have prevented the associated instruments from performing their intended safety function(s).
Therefore, no substantial safety hazards have been identifie Initial notification was made on April 1, 2013, via Event Notification 48871.The apparent cause of this condition involved a misinterpretation of construction procedure 25402-000-GPP-0000-N3401, "Instrument and Instrument Line Installation," which lacked proper detail to define the boundary of the sense line from the panel isolation valve to process connection including the root valve. Further details of this condition can be found in the CDR 391/2013-02 provided in the enclosure.
There are no new commitments contained in this lette U.S. Nuclear Regulatory Commission Page 2 June 27, 2013 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 2 7 th day of June, 2013.If you have any questions, please contact me at (423) 365-1260 or Gordon Arent at (423) 365-2004.Respectfully, Raymond A. Hruby, Jr.General Manager, Technical Services Watts Bar Unit 2 Enclosure:
Construction Deficiency Report (CDR) 391/2013-02, Instrument Sense Line Slope Issue -Final Report cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 U.S. Nuclear Regulatory Commission Page 3 June 27, 2013 bcc (Enclosure):
Jessie Quichocho U.S. Nuclear Regulatory Commission MS 08G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Fred Brown, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 REGARDING INSTRUMENT SENSE LINE SLOPE CONDITION 10 CFR 50.55(e) CONSTRUCTION DEFICIENCY REPORT (CDR) 50-391/2013-02 FINAL REPORT DESCRIPTION OF DEFICIENCY TVA has identified a condition that was a significant (programmatic)
breakdown in the instrument sense line installation program and, thus, a significant breakdown in a portion of TVA's quality assurance program. Specifically, TVA determined that a condition existed where certain portions of the instrument line installations in multiple systems have not been completely inspected to ensure that proper slope requirements (1/4 inch per foot) were met. Inadequate sense line slope could result in the degradation of the associated safety-related instrument due to the effects of air entrapment which could adversely affect the accuracy or time response of the instrument or cause noise.Walkdowns have been completed for those systems that contained the identified issue.Inspection results did not identify examples where instrument line slopes as installed would have prevented the associated instruments from performing their intended safety function(s).
Therefore, no substantial safety hazards have been identifie Since this condition had the potential to be a significant (programmatic)
breakdown in the instrument sense line installation program and, thus, a potential breakdown in TVA's quality assurance program, this condition was conservatively reported previously in accordance with 10 CFR 50.55(e).
Initial notification was made on April 1, 2013, via Event Notification 48871.The issues documented in CDR 50-391/2013-02 were captured in TVA's corrective action program as Problem Evaluation Report (PER) 680826.CAUSE OF THE DEFICIENCY The apparent cause for PER 680826 involved a misinterpretation of construction procedure 25402-000-GPP-0000-N3401, "Instrument and Instrument Line Installation." The construction procedure lacked proper detail to define the boundary of the sense line from the panel isolation valve to the process connection including the root valve.The standard Engineering Document Construction Release (EDCR) work scope statement for defining the sense line boundary is "Sense line connection from the process connection (e.g. root valve) to the panel isolation valve." However, the manner in which construction procedure 25402-000-GPP-0000-N3401 was written could be interpreted to mean that the required slope inspection did not include the root valve.TVA believes the misinterpretation was a more recent condition rather than a historical one. Early in the project, work was performed by Knowledge, Skill and Rule-based personne The Knowledge was developed through design review meetings that were conducted for the EDCRs prior to issuanc These meetings provided the expectations and level of detail needed to resolve the issues related to the Instrument Line corrective action plan through extensive walkdowns involving construction and design personnel.
As the project progressed, the Skill and Rule base traits have remaine However, the Knowledge base has been diminished given the length of time that elapses between the issuance of design packages and the work that takes place to complete their implementation.
E-1 9.ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 REGARDING INSTRUMENT SENSE LINE SLOPE CONDITION 10 CFR 50.55(e) CONSTRUCTION DEFICIENCY REPORT (CDR) 50-391/2013-02 FINAL REPORT SAFETY IMPLICATIONS Walkdowns have been completed for those systems which contained the issue.Inspection results did not identify examples where instrument line slopes as installed would have prevented the associated instruments from performing their intended safety function(s).
Therefore, no substantial safety hazards have been identified.
CORRECTIVE ACTIONS 1. Procedure 25402-000-GPP-0000-N3401, "Instrument and Instrument Line Installation," has been revised to identify the sense line boundary from the process connection through the root valve to the panel isolation valve.2. Training to the above revised procedure has been provided to applicable Field Engineers, Planners, and Design personnel to eliminate any Knowledge gap.3. The standard statement in the EDCRs discussed above has been removed from each EDCR through approved procedures for revising EDCRs.4. TVA has revalidated instrument line slopes for the affected systems and has subsequently prepared and processed Field Change Requests to document changes requiring correction found during these walkdown None of these changes would have resulted in a substantial safety hazard had they remained uncorrecte For the remaining systems yet to be completed, TVA has corrected the program as described above to complete those systems as intended from this time forward.E-2