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Category:Inspection Report Correspondence
MONTHYEARML20129J8732020-05-0808 May 2020 2020 WBN - POV Inspection Information Request ML18242A2492018-08-30030 August 2018 Notification of Inspection and Request for Information for NRC Confirmatory Order Follow-up Inspection IR 05000390/20154072016-10-11011 October 2016 Watts Barr Nuclear Plant - Amended NRC Material Control and Accounting Inspection Report 05000390/2015407, (Letter Only) IR 05000390/20114022011-09-20020 September 2011 IR 05000390-11-402 & 05000391-11-402 Watts Bar Nuclear Plant - NRC Security Inspection Report ML1106601672011-03-0404 March 2011 Notification of Inspection and Request for Information IR 05000390/20084052008-11-21021 November 2008 IR 05000390-08-405 and 05000391-08-405, on 11/04/2008, Watts Bar Nuclear Plant - NRC Supplemental Inspection Report ML0734000982007-12-0303 December 2007 IR 05000390-08-002 & 05000391-08-002, on 02/11-15/2008 & 02/25-29/2008, Watts Bar Baseline Occupational Radiation Safety Inspection IR 05000390/20070072007-07-30030 July 2007 IR 05000390-07-007, 05000391-07-007, on 05/29/2007 - 06/01/2007 & 06/11-15/2007, Watts Bar, Units 1 and 2; Triennial Fire Protection ML0628504432006-10-12012 October 2006 Notification of Watts Bar Nuclear Power Plant - Component Design Bases Inspection - NRC Inspection Report 05000390/2007006 ML0336401092003-12-18018 December 2003 Notification of Watts Bar Nuclear Plant - Triennial Fire Protection Baseline Inspection - NRC Inspection Report 05000390/2004006 and 05000391/2004006 IR 05000390/20010052002-04-11011 April 2002 IR 05000390/2001-005 & 05000391/2001-005, Watts Bar, Inspection on 12/16/2001-03/16/2001. No Violations Noted IR 05000390/20020062002-04-0404 April 2002 IR 05000390/2002-006 & 05000391/2002-006, Watts Bar Nuclear Plant, Inspection Completed on 03/21/2002. One non-cited Violation Noted. Safeguards Information Removed IR 05000390/20010042002-01-14014 January 2002 IR 05000390/2001-004 & IR 05000391/2001-004, Watts Bar Nuclear Plant, Inspection on 09/16/12/15/2001 Re Heat Sink 2020-05-08
[Table view] Category:Letter
MONTHYEARIR 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 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) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter 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 IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 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 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-24-010, 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) 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 CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML23319A2452024-01-29029 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 2024-08-07
[Table view] |
See also: IR 05000390/2007006
Text
October 12, 2006Tennessee Valley AuthorityATTN:Mr. Karl W. SingerChief Nuclear Officer and
Executive Vice President6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801SUBJECT:NOTIFICATION OF WATTS BAR NUCLEAR POWER PLANT - COMPONENTDESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000390/2007006Dear Mr. Singer:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)Region II staff will conduct a component design bases inspection at your Watts Bar NuclearPower Plant during the weeks of February 12-16, 2007, February 26-March 2, 2007, and March5-9, 2007. The inspection team will be led by Steve Rose, a Senior Reactor Inspector from theNRC's Region II Office. This inspection will be conducted in accordance with the baselineinspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued June
22, 2006.The inspection will evaluate the c
apability of risk significant / low margin components to functionas designed and support proper system operation. The inspection will also include a review ofselected operator actions, operating experience, and modifications. During a telephone conversation on October 11, 2006, Mr. Moore of the Region II staffconfirmed with Mr. Brian Thomas of your staff, arrangements for an information gathering site
visit and the three-week onsite inspection. The schedule is as follows:*Information gathering visit: Week of January 29-February 2, 2007.*Onsite weeks: February 12-16, 2007, February 26-March 2, 2007, and March 5-9, 2007. The purpose of the information gathering visits is to meet with members of your staff to identifyrisk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Rudy Bernhard, a Region II Senior ReactorAnalyst, may accompany Mr. Rose during the information gathering visit to review probabilisticrisk assessment data and identify risk significant components which will be examined during theinspection.
TVA 2The enclosure lists documents that will be needed prior to the information gathering visit. Please provide this information to the Atlanta office by January 15, 2007. Please contact Mr.
Moore or Mr. Rose prior to preparing copies of the materials listed in the enclosure.The inspectors will try to minimize your administrative burden by specifically identifying onlythose documents required for the inspection preparation.During the information gathering visit, the team leader will also discuss the following inspectionsupport administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
February 5, 2007; arrangements for site access; and the availability of knowledgeable plantengineering and licensing personnel to serve as points of contact during the inspection.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom 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).Thank you for your cooperation in this matter. Should you have any questions concerning thisinformation requested or the inspection, please contact Mr. Randy Moore at (404) 562-4628,
Mr. Steve Rose (404) 562 4609, or me at (404) 562-4605.Sincerely,/RA/Scott Freeman, Acting ChiefEngineering Branch 1
Division of Reactor SafetyDocket Nos. 50-390License No. NPF-90Enclosure: Information Request for Watts Bar Nuclear Power Plant Component Design Bases Inspectioncc w/encl - See page 3
TVA 3cc w/encl:Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail DistributionLarry S. Bryant, Vice PresidentNuclear Engineering & Technical Services
Tennessee Valley Authority
Electronic Mail DistributionMichael D. SkaggsSite Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail DistributionPreston D. SwaffordSenior Vice President
Nuclear Support
Tennessee Valley Authority
Electronic Mail DistributionGeneral CounselTennessee Valley Authority
Electronic Mail DistributionJohn C. Fornicola, General ManagerNuclear Assurance
Tennessee Valley Authority
Electronic Mail DistributionRussell R. Thompson, Acting ManagerCorporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801Robert H. Bryan, Jr., General ManagerLicensing & Industry Affairs
Tennessee Valley Authority
Electronic Mail DistributionJames D. Smith, Acting ManagerLicensing and Industry Affairs
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail DistributionJay Laughlin, Plant ManagerWatts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail DistributionCounty ExecutiveRhea County Courthouse
375 Church Street, Suite 215
Dayton, TN 37321-1300County Mayor
P. O. Box 156
Decatur, TN 37322Lawrence E. Nanney, DirectorTN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail DistributionAnn Harris341 Swing Loop
Rockwood, TN 37854James H. Bassham, DirectorTennessee Emergency Management
Agency
Electronic Mail Distribution
_________________________OFFICERII:DRSRII:DRSRII:DRSRII:DRPSIGNATURE/RA//RA//RA//RA//RA/NAMERBernhardRMooreSFreemanMWidmannSRoseDATE10/12/200610/11/200610/12/200610/12/200610/12/200610/ /200610/ /2006
E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO
EnclosureINFORMATION REQUEST FOR WATTS BAR NUCLEAR POWER PLANT COMPONENT DESIGN BASES INSPECTIONPlease provide the information electronically in ".pdf" files, Excel, or other searchable format onCDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Information in "lists" should contain enough information to be easily understood to someone
who has a knowledge of pressurized water reactor technology.1.Risk ranking of components from your site specific probabilistic safety analysis (PSA)sorted by Risk Achievement Worth (RAW) and sorted separately by Birnbaum
Importance. If possible, please provide a correlation between actual plant componentsin plain language, and RAW values.2.Provide a list of the top 500 cut sets from your PSA.
3.Risk ranking of operator actions from your site specific PSA sorted by RAW. Providecopies of your human reliability worksheets for these items.4.If you have an External Event or Fire PSA Model, provide the information requested inItems 1 and 2 for external events and fire.5.Any pre-existing evaluation or list of components and calculations with low designmargins (i.e., pumps closest to the design limit for flow or pressure, diesel generator
close to design required output, heat exchangers close to rated design heat removal,
MOV risk-margin rankings, etc.).6.A list of the last two years of operating experience evaluations, modifications, andcorrective actions sorted by component or system. (Safety related systems only)7.Information of any common cause failure of components experienced in the last 5 yearsat your facility.8.Contact person to discuss PRA information prior to bag man trip: phone number and e-mail address.9.List of equipment on "Station Equipment Problem List", list of equipment in GL 91-18status, list of equipment in MR(a)(1) status, list of equipment for which operabilityevaluation was required in past 2 years.10.A list of failed or missed Technical specification required surveillance for past 2 years(via PER, work order, etc.)