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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
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] |
See also: IR 05000390/2007006
Text
October 12, 2006
Tennessee Valley Authority
ATTN: Mr. Karl W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF WATTS BAR NUCLEAR POWER PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
05000390/2007006
Dear 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 Nuclear
Power Plant during the weeks of February 12-16, 2007, February 26-March 2, 2007, and March
5-9, 2007. The inspection team will be led by Steve Rose, a Senior Reactor Inspector from the
NRC's Region II Office. This inspection will be conducted in accordance with the baseline
inspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued June
22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and support proper system operation. The inspection will also include a review of
selected operator actions, operating experience, and modifications.
During a telephone conversation on October 11, 2006, Mr. Moore of the Region II staff
confirmed 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 identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. Rudy Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Rose during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
inspection.
TVA 2
The 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 only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support 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 plant
engineering 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 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).
Thank you for your cooperation in this matter. Should you have any questions concerning this
information 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 Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-390
License No. NPF-90
Enclosure: Information Request for Watts Bar Nuclear Power Plant
Component Design Bases Inspection
cc w/encl - See page 3
TVA 3
cc w/encl: Robert H. Bryan, Jr., General Manager
Ashok S. Bhatnagar Licensing & Industry Affairs
Senior Vice President Tennessee Valley Authority
Nuclear Operations Electronic Mail Distribution
Tennessee Valley Authority
Electronic Mail Distribution James D. Smith, Acting Manager
Licensing and Industry Affairs
Larry S. Bryant, Vice President Watts Bar Nuclear Plant
Nuclear Engineering & Technical Services Tennessee Valley Authority
Tennessee Valley Authority Electronic Mail Distribution
Electronic Mail Distribution
Jay Laughlin, Plant Manager
Michael D. Skaggs Watts Bar Nuclear Plant
Site Vice President Tennessee Valley Authority
Watts Bar Nuclear Plant Electronic Mail Distribution
Tennessee Valley Authority
Electronic Mail Distribution County Executive
Rhea County Courthouse
Preston D. Swafford 375 Church Street, Suite 215
Senior Vice President Dayton, TN 37321-1300
Nuclear Support
Tennessee Valley Authority County Mayor
Electronic Mail Distribution P. O. Box 156
Decatur, TN 37322
General Counsel
Tennessee Valley Authority Lawrence E. Nanney, Director
Electronic Mail Distribution TN Dept. of Environment & Conservation
Division of Radiological Health
John C. Fornicola, General Manager Electronic Mail Distribution
Nuclear Assurance
Tennessee Valley Authority Ann Harris
Electronic Mail Distribution 341 Swing Loop
Rockwood, TN 37854
Russell R. Thompson, Acting Manager
Corporate Nuclear Licensing and James H. Bassham, Director
Industry Affairs Tennessee Emergency Management
Tennessee Valley Authority Agency
4X Blue Ridge Electronic Mail Distribution
1101 Market Street
Chattanooga, TN 37402-2801
_________________________
OFFICE RII:DRS RII:DRS RII:DRS RII:DRP
SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/
NAME RBernhard RMoore SFreeman MWidmann SRose
DATE 10/12/2006 10/11/2006 10/12/2006 10/12/2006 10/12/2006 10/ /2006 10/ /2006
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
INFORMATION REQUEST FOR WATTS BAR NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. 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 components
in 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. Provide
copies of your human reliability worksheets for these items.
4. If you have an External Event or Fire PSA Model, provide the information requested in
Items 1 and 2 for external events and fire.
5. Any pre-existing evaluation or list of components and calculations with low design
margins (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, and
corrective actions sorted by component or system. (Safety related systems only)
7. Information of any common cause failure of components experienced in the last 5 years
at 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 91-18
status, list of equipment in MR(a)(1) status, list of equipment for which operability
evaluation 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.)
Enclosure