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Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:Inspection Report
MONTHYEARIR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23296A0242023-10-24024 October 2023 Biennial Problem Identification and Resolution Inspection Report and Preliminary Greater than Green Finding and Apparent Violation IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 IR 05000390/20234012023-03-13013 March 2023 Security Baseline Inspection Report 05000390 2023401 and 05000391 2023401 IR 05000390/20220062023-03-0101 March 2023 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022006 and 05000391/2022006 IR 05000390/20220042023-02-10010 February 2023 Integrated Inspection Report 05000390/2022004 and 05000391/2022004 IR 05000390/20224202022-12-0101 December 2022 Security Baseline Inspection 05000390/2022420 and 05000391/2022420 Cover Letter ML22318A0072022-11-14014 November 2022 Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20220102022-10-28028 October 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000390/2022010 and 05000391/2022010 IR 05000390/20223012022-09-30030 September 2022 NRC Operator License Examination Report 05000390/2022301 and 050000391/2022301 ML22256A2952022-09-14014 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07201048/2022001 IR 05000390/20220052022-08-31031 August 2022 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022005 and 05000391/2022005 - Final IR 05000390/20220022022-08-12012 August 2022 Integrated Inspection Report 05000390/2022002 and 05000391/2022002 and Exercise of Enforcement Discretion IR 05000390/20224012022-08-0303 August 2022 Security Baseline Inspection Report 05000390/2022401 and 05000391/2022401 IR 05000390/20220012022-05-11011 May 2022 Integrated Inspection Report 05000390/2022001 and 05000391/2022001 ML22123A2412022-05-11011 May 2022 Review of the Fall 2021 Mid-Cycle Steam Generator Tube Inspection Report IR 05000390/20210062022-03-0202 March 2022 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 (Report No. 05000390/2021006 and 05000391/2021006) IR 05000390/20210042022-02-10010 February 2022 Integrated Inspection Report 05000390/2021004 and 05000391/2021004 IR 05000390/20210032021-11-10010 November 2021 Integrated Inspection Report 05000390/2021003 and 05000391/2021003 IR 05000390/20214022021-11-0202 November 2021 Security Baseline Inspection Report 05000390/2021402 and 05000391/2021402 IR 05000390/20214032021-10-26026 October 2021 Material Control and Accounting Program Inspection Report 05000390/2021403 and 05000391/2021403 (OUO Removed) ML21263A0042021-09-24024 September 2021 Review of the Fall 2020 Steam Generator Tube Inspection Report IR 05000390/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000390/2021401 and 05000391/2021401 IR 05000390/20210052021-08-24024 August 2021 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 & 2 Report 05000390/2021005 and 05000391/2021005 IR 05000390/20210022021-08-0404 August 2021 Integrated Inspection Report 05000390/2021002 and 05000391/2021002 IR 05000390/20210122021-07-0101 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000390/2021012 and 05000391/2021012 IR 05000390/20210102021-05-0606 May 2021 NRC Inspection Report 05000390/2021010 and 05000391/2021010 IR 05000390/20210012021-05-0505 May 2021 Integrated Inspection Report 05000390/2021001 and 05000391/2021001 IR 05000390/20210112021-04-13013 April 2021 Triennial Fire Protection Inspection Report 05000390/2021011 and 05000391/2021011 IR 05000390/20200062021-03-0303 March 2021 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020006 and 05000391/2020006 IR 05000390/20200042021-02-11011 February 2021 Integrated Inspection Report 05000390/2020004, 05000391/2020004, 07201048/2020002, and Exercise of Enforcement Discretion IR 05000390/20203012021-01-19019 January 2021 Reissue - Watts Bar Nuclear Plant - NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 IR 05000390/20204032020-12-15015 December 2020 Security Baseline Inspection Report 05000390/2020403 and 05000391/2020403 IR 05000390/20204012020-11-30030 November 2020 Security Baseline Inspection Report 05000390/2020401 and 05000391/2020401 IR 05000390/20200032020-11-10010 November 2020 Integrated Inspection Report 05000390/2020003 and 05000391/2020003 IR 05000390/20200112020-10-20020 October 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000390/2020011 and 05000391/2020011 IR 05000390/20200052020-08-31031 August 2020 Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005 IR 05000390/20200022020-08-11011 August 2020 Nuclear Regulatory Commission Integrated Inspection Report 05000390/2020002, 05000391/2020002, and 07201048/2020001 IR 05000390/20200012020-05-0505 May 2020 Integrated Inspection Report 05000390/2020001 and 05000391/2020001 IR 05000390/20204102020-03-31031 March 2020 Security Baseline Inspection Report 05000390/2020410 and 05000391/2020410 IR 05000390/20190062020-03-0303 March 2020 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - NRC Report 05000390/2019006 and 05000391/2019006 2023-08-09
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Text
UNITED STATES uly 6, 2012
SUBJECT:
ERRATA WATTS BAR NUCLEAR PLANT- NRC INTEGRATED INSPECTION REPORT 05000390/2010005 (ML110280456)
Dear Mr. Shea:
The purpose of this errata is to correct references to the tracking number associated with the closure of Unresolved Item (URI)05000390/2010006-02, Worst Case 6900 VAC Bus Voltage in Design Calculations contained in the Watts Bar 2010 4th quarter integrated inspection report 05000390/2010005 (ML110280456).
Section 4OA5.3 (report pages 21 and 22) and the List of Items Opened, Closed and Discussed (supplemental page 2) of the above inspection report incorrectly identify that URI tracking number 05000390/2010008-02 is being closed by the inspection report. The correct URI tracking number is05000390/2010006-02. Replace Section 4OA5.3 (page numbers 21 and 22) and Supplemental Information (page number 2) of ML110280456 with the pages enclosed to correct the URI tracking number reference error.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room). I apologize for any inconvenience this error may have caused. If you have any questions, please contact me at (404) 997- 4530.
Sincerely,
/RA: Jason Eargle for/
Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety Docket No.: 50-390 License No.: NPF-90 Enclosure: As stated w/ Attachment: Supplemental Information cc w/encl: (See page 3)
_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS SIGNATURE RA:EARGLE FOR RA RA NAME NEASE RILEY SANDLE DATE 7/6/2012 7/6/2012 7/6/2012 7/ /2012 7/ /2012 7/ /2012 7/ /2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO :cc w/encl: Senior Resident Inspector D. E. Grissette Watts Bar Nuclear Plant Site Vice President U.S. Nuclear Regulatory Commission Watts Bar Nuclear Plant 1260 Nuclear Plant Road Tennessee Valley Authority Spring City, TN 37381-2000 Electronic Mail Distribution Ann Harris David H. Gronek 341 Swing Loop Plant Manager Rockwood, TN 37854 Watts Bar Nuclear Plant, MOB 2R-WBN Tennessee Valley Authority P.O. Box 2000 MOB 2R Spring City, TN 37381 Donna K. Guinn Manager, Licensing Watts Bar Nuclear Plant, ADM 1L-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 Edward J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution Gordon P. Arent New Generation Licensing Manager Watts Bar Nuclear Plant, EQB 1B-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 County Mayor P.O. Box 156 Decatur, TN 37322 County Executive 375 Church Street Suite 215 Dayton, TN 37321 Tennessee Department of Environment &
Conservation Division of Radiological Health 401 Church Street Nashville, TN 37243 Enclosure Letter to Joseph from Rebecca L. Nease dated July 6, 2012.
SUBJECT: ERRATA WATTS BAR- 2010 4th QUARTER INTEGRATED INSPECTION REPORT (ML110280456)
Distribution w/encl:
J. Hamman, RII, PE, DRP B. Monk, SRI K. Miller, RI RIDSNRRDIRS PUBLIC RidsNrrPMWattsBar1 Resource RidsNrrPMWattsBar2 Resource
.3 (Closed) URI 05000390/2010006-02, Worst Case 6900 VAC Bus Voltage in Design Calculations Introduction: The NRC identified a Green non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, for the failure to correctly translate the 6900 VAC emergency bus undervoltage trip value specified in Technical Specifications (TS)
into design calculations for motor starting and loading. The values used by the licensee in the design calculations were non-conservative with respect to the specified TS values.
This issue was initially discussed as URI 05000390/2010006-02: Worst Case 6900 VAC Bus Voltage in Design Calculations.
Description: Offsite power at Watts Bar is normally provided to the Class 1E 6900 VAC buses from the 161 kV offsite power system through the Common Station Service Transformers (CSSTs). Watts Bar TS Section 3.3.5-1, item 2, Loss of Power Diesel Generator Start Instrumentation, requires and specifies the undervoltage and degraded voltage relay trip setpoints, including allowable values and time delays associated with the safety-related 6900 VAC buses. These degraded voltage setpoints provide the bases for the minimum voltage available to all safety-related equipment such as motors, contactors, and solenoid valves during a postulated degraded voltage scenario.
At Watts Bar, the degraded voltage relays initiate the nominal 10 second time delay at the TS specified relay voltage setting. When the 10 second time delay has elapsed, the plant loads are removed from the offsite power supply and transferred to the onsite emergency diesel generators. The degraded voltage relays drop-out (de-energize)
when sufficient voltage is not available and normally pick-up (energize) if voltage is recovered within the 10 second delay on the 6900 VAC bus. The degraded voltage relay settings at Watts Bar are in accordance with TS Table 3.3.5-1 which states the values to be as follows: Allowable Value 6570 VAC, Trip Setpoint between 6606 VAC and 6593 VAC.
The inspector reviewed licensee calculation of record WBN-EEB-MS-TI-06-0029, Degraded Voltage Analysis, Rev. 31, which evaluated motor starting voltages at the beginning of a design basis loss of coolant accident (LOCA) concurrent with a degraded grid condition. This calculation used the degraded voltage setpoint of 6672 V to analyze post LOCA load motor starting. This voltage of 6672 VAC used in the calculation was non-conservative with respect to the voltage specified in TS which specified a maximum value of 6606 VAC.
Analysis: The failure to use the degraded voltage relay setpoint values as specified in TS and installed in the plant for the 6900 VAC bus electrical design calculation was a performance deficiency. This finding is more than minor because it affects the Design Control attribute of the Mitigating Systems Cornerstone. It impacts the cornerstone objective of ensuring the availability, reliability, and operability of the 6900 VAC safety buses to perform the intended safety function during a design basis event. The potential availability, reliability, and operability of the 6900 VAC safety buses during a potential degraded voltage condition was impacted as the licensee calculation used a non conservative degraded voltage input, with respect to the values specified in TS, into their safety-related motor starting and running calculations. The inspectors assessed the Enclosure
finding using the SDP and determined that the finding was of very low safety significance (Green) because the finding represented a design deficiency confirmed not to result in the loss of functionality of safety-related loads due to the availability of load tap changers (LTCs) that are installed to improve a degraded voltage condition.
The inspectors reviewed the performance deficiency for cross-cutting aspects and determined that none were applicable since this performance deficiency was not indicative of current licensee performance as the design calculation discussed above was not recently performed.
Enforcement: 10 CFR 50, Appendix B, Criterion III, Design Control, states, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis for structures, systems, and components are correctly translated into specifications, drawings, procedures, and instructions. This appendix also states in part that measures shall be established for the selection and review for suitability of application of processes that are essential to the safety-related functions of the structures, systems, and components. Watts Bar TS Section 3.3.5-1, Loss of Power Diesel Generator Start instrumentation, table 3.3.5-1, item 2 specifies the 6900 VC emergency bus undervoltage (degraded) relay trip setpoints to be as follows: Allowable Value, 6570 VAC, Trip Setpoint, 6606 VAC and 6593 VAC.
Contrary to the above, since at least December 2001, the licensee failed to assure that applicable regulatory requirements for undervoltage (degraded) voltage protection, including those prescribed in TS 3.3.5-1, item 2, were correctly translated into design calculation, WBN-EEB-MS-TI-06-0029, Degraded Voltage Analysis, Revision 31, which evaluated motor starting voltages at the beginning of a design basis loss of coolant accident (LOCA) concurrent with a degraded grid condition. Further, the process used by the licensee for the selection of input voltage value in the design calculation was non-conservative with respect to the TS. Specifically, the licensee used the input value of 6672 VAC which was higher than the maximum value of 6606 VAC specified in TS. This did not result in a loss of function of safety-related loads.
Because this finding is of very low safety significance and was entered into the licensees corrective action program as PER 296306 this violation is being treated as a NCV, consistent with the NRC Enforcement Policy. This finding is identified as NCV 05000390, 2010005-03: Failure to Use Worst Case 6900 VAC Bus Voltage in Design Calculations. URI 05000390/2010006-02, Worst Case 6900 VAC Bus Voltage in Design Calculations is closed.
Enclosure
05000390/2010005-03 NCV Failure to Use Worst Case 6900 VAC Bus Voltage in Design Calculations. (Section 4OA5.3)
Closed 05000390/2515/172 TI Reactor Coolant System Dissimilar Metal Butt Welds (Section 4OA5.1)05000390/2009002-03 URI Acceptability of Seismic Qualification of 120VAC Vital Instrumentation Board Circuit Breakers05000390/2010006-02 URI Worst Case 6900 VAC Bus Voltage in Design Calculations Discussed None Attachment