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| | issue date = 09/20/2011 | | | issue date = 09/20/2011 |
| | title = IR 05000390-11-402 & 05000391-11-402 Watts Bar Nuclear Plant - NRC Security Inspection Report | | | title = IR 05000390-11-402 & 05000391-11-402 Watts Bar Nuclear Plant - NRC Security Inspection Report |
| | author name = Munday J T | | | author name = Munday J |
| | author affiliation = NRC/RGN-II/DRS | | | author affiliation = NRC/RGN-II/DRS |
| | addressee name = Krich R M | | | addressee name = Krich R |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000390, 05000391 | | | docket = 05000390, 05000391 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ber 20, 2011 |
| [[Issue date::September 20, 2011]]
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| EA-11-217 Mr. R. Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
| | ==SUBJECT:== |
| | WATTS BAR NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000390/2011402 AND 05000391/2011402 |
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| SUBJECT: WATTS BAR NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000390/2011402 AND 05000391/2011402
| | ==Dear Mr. Krich:== |
| | On August 24, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Watts Bar Nuclear Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on August 25, 2011, with Mr. D. Grissette and other members of the TVA staff. |
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| ==Dear Mr. Krich:==
| | This inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations, and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| On August 24, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Watts Bar Nuclear Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on August 25, 2011, with Mr. D. Grissette and other members of the TVA staff. This inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations, and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. This letter transmits a finding that has preliminarily been determined to be greater than Green - i.e., a finding of greater than very low safety significance that may result in the need for further evaluation to determine significance, and therefore the need for additional NRC action. The finding is described in the enclosed inspection report. This finding was assessed based on the best available information, using the Physical Protection Significance Determination Process (PPSDP). The finding was immediately corrected and placed in the licensee's Corrective Action Program, while long term corrective action is being implemented. The finding is also an apparent violation of NRC requirements and is being considered for escalated enforcement action in accordance with the Enforcement Policy, which can be found on the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/enforcement. The finding also had a cross-cutting aspect in the area of Operating Experience (OE) under P.2(a), in that, the licensee failed to systematically collect, evaluate, and communicate to affected internal stakeholders in a timely TVA 2 manner relevant internal and external OE. If you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis of your disagreement to the Regional Administrator, Region II, and the NRC Resident Inspector at the Watts Bar Nuclear Plant. In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete our evaluation using the best available information and issue our final determination of safety significance within 90 days of the date of this letter. The significance determination process encourages an open dialogue between the NRC staff and the licensee, however, the dialogue should not impact the timeliness of the staff's final determination. Before we make our final significance determination, we are providing you with an opportunity (1) to attend a Regulatory Conference where you can present to the NRC your perspective on the facts and assumptions the NRC used to arrive at the finding and assess its significance, or (2) submit your position of the finding to the NRC in writing. If you request a Regulatory Conference, it should be held within 30 days of the receipt of this letter and we encourage you to submit supporting documentation at least one week prior to the conference in an effort to make the conference more efficient and effective. If a Regulatory Conference is held, it will not be open for public observation due to the security-related nature of the issues to be discussed.
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| | This letter transmits a finding that has preliminarily been determined to be greater than Green - |
| | i.e., a finding of greater than very low safety significance that may result in the need for further evaluation to determine significance, and therefore the need for additional NRC action. The finding is described in the enclosed inspection report. This finding was assessed based on the best available information, using the Physical Protection Significance Determination Process (PPSDP). The finding was immediately corrected and placed in the licensees Corrective Action Program, while long term corrective action is being implemented. The finding is also an apparent violation of NRC requirements and is being considered for escalated enforcement action in accordance with the Enforcement Policy, which can be found on the NRCs Web site at http://www.nrc.gov/reading-rm/doc-collections/enforcement. The finding also had a cross-cutting aspect in the area of Operating Experience (OE) under P.2(a), in that, the licensee failed to systematically collect, evaluate, and communicate to affected internal stakeholders in a timely TVA 2 manner relevant internal and external OE. If you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis of your disagreement to the Regional Administrator, Region II, and the NRC Resident Inspector at the Watts Bar Nuclear Plant. |
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| If you decide to submit only a written response, such submittal should be sent to the NRC within 30 days of your receipt of this letter. If you decline to request a Regulatory Conference or submit a written response, you relinquish your right to appeal the final SDP determination, in that by not doing either, you fail to meet the appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2 of IMC 0609.
| | In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete our evaluation using the best available information and issue our final determination of safety significance within 90 days of the date of this letter. The significance determination process encourages an open dialogue between the NRC staff and the licensee, however, the dialogue should not impact the timeliness of the staffs final determination. |
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| Please contact Mr. Michael Ernstes, Chief, Plant Support Branch 2, Division of Reactor Safety, at (404) 997-4540 or in writing within 10 days from the issue date of this letter, to notify the NRC of your intentions. If we have not heard from you within 10 business days, we will continue with our significance determination and enforcement decision. The final resolution of this matter will be conveyed in separate correspondence. Because the NRC has not made a final determination in this matter, a Notice of Violation will not be issued for these inspection findings at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. However, because of the security related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not be available for public inspection. Because this issue involves security-related information, your response, should you choose to respond in writing, will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If Safeguards Information is TVA 3 necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response "Proprietary Information in accordance with 10 CFR 2.390(d)(1)" and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
| | Before we make our final significance determination, we are providing you with an opportunity (1) to attend a Regulatory Conference where you can present to the NRC your perspective on the facts and assumptions the NRC used to arrive at the finding and assess its significance, or (2) submit your position of the finding to the NRC in writing. If you request a Regulatory Conference, it should be held within 30 days of the receipt of this letter and we encourage you to submit supporting documentation at least one week prior to the conference in an effort to make the conference more efficient and effective. If a Regulatory Conference is held, it will not be open for public observation due to the security-related nature of the issues to be discussed. |
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| Sincerely,/ RA / Joel T. Munday, Director Division of Reactor Safety Docket Nos.: 50-390, 50-391 License Nos.: NPF-90; Construction Permit No. CPPR-92
| | If you decide to submit only a written response, such submittal should be sent to the NRC within 30 days of your receipt of this letter. If you decline to request a Regulatory Conference or submit a written response, you relinquish your right to appeal the final SDP determination, in that by not doing either, you fail to meet the appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2 of IMC 0609. |
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| ===Enclosure:===
| | Please contact Mr. Michael Ernstes, Chief, Plant Support Branch 2, Division of Reactor Safety, at (404) 997-4540 or in writing within 10 days from the issue date of this letter, to notify the NRC of your intentions. If we have not heard from you within 10 business days, we will continue with our significance determination and enforcement decision. The final resolution of this matter will be conveyed in separate correspondence. |
| Inspection Report 05000390/2011402 and 05000391/2011402
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| ===w/Attachment:===
| | Because the NRC has not made a final determination in this matter, a Notice of Violation will not be issued for these inspection findings at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review. |
| Supplemental Information (OUO) cc w/Encl.: (See page 4) TVA 3 necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response "Proprietary Information in accordance with 10 CFR 2.390(d)(1)" and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
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| Sincerely,/ RA / Joel T. Munday, Director Division of Reactor Safety Docket Nos.: 50-390, 50-391 License Nos.: NPF-90; Construction Permit No. CPPR-92
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. However, because of the security related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection. |
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| ===Enclosure:===
| | Because this issue involves security-related information, your response, should you choose to respond in writing, will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If Safeguards Information is TVA 3 necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Proprietary Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
| Inspection Report 05000390/2011402 and 05000391/2011402
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| ===w/Attachment:===
| | Sincerely, |
| Supplemental Information (OUO) cc w/Encl.: (See page 4) | | / RA / |
| Distribution w/encl: RidsNrrPMWattsBar1 Resource RidsNrrPMWattsBar2 Resource C. Evans, RII EICS (Part 72 Only) L. Douglas, RII EICS (Linda Douglas) B. Westreich, NSIR (hard copy w/ encl) RIDSNRRDIRS OE Mail (email address if applicable) X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE ADAMS: X Yes ACCESSION NUMBER: ML112640085 X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII: DRS/PSB2 RII: DRS/PB2 RII: DRSPSB2 RII: DRP/BR6 RII: EICS RII: DRS SIGNATURE RA RA RA RA RA RA NAME J. SHEHEE R. PATTERSON M. ERNSTES S. SHAEFFER S. SPARKS J. MUNDAY DATE 09/16/2011 09/16/2011 09/19/2011 09/19/2011 09/19/2011 09/20/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\DRSII\PSBII\REACTORS\WATTS BAR\REPORTS\2011\WATTS BAR INSP REPORT 2011402 REV1.DOCX B 4 TVA cc w/Encl:
| | Joel T. Munday, Director Division of Reactor Safety Docket Nos.: 50-390, 50-391 License Nos.: NPF-90; Construction Permit No. CPPR-92 Enclosure: |
| D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381 C. J. Riedl Acting Manager, Licensing Watts Bar Nuclear Plant, ADM 1L-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 Mark Findlay General Manager, Security Operations Tennessee Valley Authority 1101 Market Street, EB 10B-C Chattanooga, TN 37402-2801 J. B. Wilcox Manager, Site Security (WBN) Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381-2000 | | Inspection Report 05000390/2011402 and 05000391/2011402 w/Attachment: Supplemental Information (OUO) |
| | cc w/Encl.: (See page 4) ML112640085 X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII: DRS/PSB2 RII: DRS/PB2 RII: DRSPSB2 RII: DRP/BR6 RII: EICS RII: DRS SIGNATURE RA RA RA RA RA RA NAME J. SHEHEE R. PATTERSON M. ERNSTES S. SHAEFFER S. SPARKS J. MUNDAY DATE 09/16/2011 09/16/2011 09/19/2011 09/19/2011 09/19/2011 09/20/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO B 4 TVA cc w/Encl: |
| | D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381 C. J. Riedl Acting Manager, Licensing Watts Bar Nuclear Plant, ADM 1L-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 Mark Findlay General Manager, Security Operations Tennessee Valley Authority 1101 Market Street, EB 10B-C Chattanooga, TN 37402-2801 J. B. Wilcox Manager, Site Security (WBN) |
| | Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381-2000 |
| }} | | }} |
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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
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)
IR 05000390/20250102024-11-0404 November 2024
Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI)
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
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
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
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
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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
CNL-24-010, 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
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)
2024-09-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 20, 2011
SUBJECT:
WATTS BAR NUCLEAR PLANT - NRC SECURITY INSPECTION REPORT 05000390/2011402 AND 05000391/2011402
Dear Mr. Krich:
On August 24, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at your Watts Bar Nuclear Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on August 25, 2011, with Mr. D. Grissette and other members of the TVA staff.
This inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations, and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
This letter transmits a finding that has preliminarily been determined to be greater than Green -
i.e., a finding of greater than very low safety significance that may result in the need for further evaluation to determine significance, and therefore the need for additional NRC action. The finding is described in the enclosed inspection report. This finding was assessed based on the best available information, using the Physical Protection Significance Determination Process (PPSDP). The finding was immediately corrected and placed in the licensees Corrective Action Program, while long term corrective action is being implemented. The finding is also an apparent violation of NRC requirements and is being considered for escalated enforcement action in accordance with the Enforcement Policy, which can be found on the NRCs Web site at http://www.nrc.gov/reading-rm/doc-collections/enforcement. The finding also had a cross-cutting aspect in the area of Operating Experience (OE) under P.2(a), in that, the licensee failed to systematically collect, evaluate, and communicate to affected internal stakeholders in a timely TVA 2 manner relevant internal and external OE. If you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis of your disagreement to the Regional Administrator, Region II, and the NRC Resident Inspector at the Watts Bar Nuclear Plant.
In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete our evaluation using the best available information and issue our final determination of safety significance within 90 days of the date of this letter. The significance determination process encourages an open dialogue between the NRC staff and the licensee, however, the dialogue should not impact the timeliness of the staffs final determination.
Before we make our final significance determination, we are providing you with an opportunity (1) to attend a Regulatory Conference where you can present to the NRC your perspective on the facts and assumptions the NRC used to arrive at the finding and assess its significance, or (2) submit your position of the finding to the NRC in writing. If you request a Regulatory Conference, it should be held within 30 days of the receipt of this letter and we encourage you to submit supporting documentation at least one week prior to the conference in an effort to make the conference more efficient and effective. If a Regulatory Conference is held, it will not be open for public observation due to the security-related nature of the issues to be discussed.
If you decide to submit only a written response, such submittal should be sent to the NRC within 30 days of your receipt of this letter. If you decline to request a Regulatory Conference or submit a written response, you relinquish your right to appeal the final SDP determination, in that by not doing either, you fail to meet the appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2 of IMC 0609.
Please contact Mr. Michael Ernstes, Chief, Plant Support Branch 2, Division of Reactor Safety, at (404) 997-4540 or in writing within 10 days from the issue date of this letter, to notify the NRC of your intentions. If we have not heard from you within 10 business days, we will continue with our significance determination and enforcement decision. The final resolution of this matter will be conveyed in separate correspondence.
Because the NRC has not made a final determination in this matter, a Notice of Violation will not be issued for these inspection findings at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. However, because of the security related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection.
Because this issue involves security-related information, your response, should you choose to respond in writing, will not be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If Safeguards Information is TVA 3 necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response Proprietary Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/ RA /
Joel T. Munday, Director Division of Reactor Safety Docket Nos.: 50-390, 50-391 License Nos.: NPF-90; Construction Permit No. CPPR-92 Enclosure:
Inspection Report 05000390/2011402 and 05000391/2011402 w/Attachment: Supplemental Information (OUO)
cc w/Encl.: (See page 4) ML112640085 X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII: DRS/PSB2 RII: DRS/PB2 RII: DRSPSB2 RII: DRP/BR6 RII: EICS RII: DRS SIGNATURE RA RA RA RA RA RA NAME J. SHEHEE R. PATTERSON M. ERNSTES S. SHAEFFER S. SPARKS J. MUNDAY DATE 09/16/2011 09/16/2011 09/19/2011 09/19/2011 09/19/2011 09/20/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO B 4 TVA cc w/Encl:
D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Spring City, TN 37381 C. J. Riedl Acting Manager, Licensing Watts Bar Nuclear Plant, ADM 1L-WBN Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 Mark Findlay General Manager, Security Operations Tennessee Valley Authority 1101 Market Street, EB 10B-C Chattanooga, TN 37402-2801 J. B. Wilcox Manager, Site Security (WBN)
Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381-2000
