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MONTHYEARML1004915352010-02-0909 February 2010 Probabilistic Risk Assessment Individual Plant Examination Summary Report Project stage: Request ML1004801162010-02-18018 February 2010 User Need Memorandum - Request for Review of Individual Plant Examination and Individual Plant Examination of External Events for Watts Bar Nuclear Plant, Unit 2 Project stage: Approval ML1010603652010-04-19019 April 2010 Request for Additional Information, Regarding Individual Plant Examination Project stage: RAI ML1016005592010-06-0808 June 2010 Request for Additional Information Regarding Individual Plant Examination Project stage: Request ML1016800722010-06-23023 June 2010 Supplemental Request for Additional Information Regarding Individual Plant Examination Project stage: RAI ML1022805852010-08-12012 August 2010 Request for Additional Information Regarding Individual Plant Examination Project stage: Request ML1103400402011-01-31031 January 2011 Request for Additional Information (RAI) Regarding Individual Plant Examination Project stage: Request ML1119602282011-08-12012 August 2011 Plant, Unit 2 - Review of Individual Plant Examination Submittal - Internal Events and Internal Flood Project stage: Approval ML14177A1672014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 4 of 4 Project stage: Other ML14177A7262014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 2 of 4 Project stage: Other ML14177A7252014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 1 of 4 Project stage: Other ML14177A1662014-06-25025 June 2014 Probabilistic Risk Assessment (PRA) Summary Report - Information Previously Committed to Provide (TAC ME3334). Part 3 of 4 Project stage: Other 2010-06-08
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, 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) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 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) 2024-09-05
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OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 12, 2011 Mr. Ashok Bhatnagar Senior Vice President Nuclear Generation Development and Construction 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REVIEW OF INDIVIDUAL PLANT EXAMINATION SUBMITTAL -INTERNAL EVENTS AND INTERNAL FLOOD (TAC NO. ME3334)
Dear Mr. Bhatnager:
In a letter dated February 9, 2010 (see Agencywide Documents Access and Management System Accession No. ML100491535), as supplemented by letters dated June 6, and August 12, 2010 ((ML101600559 and ML102280585, respectively), the Tennessee Valley Authority (TVA) submitted its Individual Plant Examination (IPE) for internal events and internal flood for Watts Bar Nuclear Plant (WBN) , Unit 2.
The U.S. Nuclear Regulatory Commission (NRC) staff's review of the WBN Unit 2 IPE submittal was focused strictly on whether the intent of Generic Letter (GL) 88-20, "Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR [Title 10, Code of Federal Regulations] 50.54(f)," had been met. Specifically, the intent of GL 88-20 is for the licensee to perform a systematic examination of the plant to identify any plant-specific vulnerabilities. The review process for TVA's IPE submittal was based on the framework described in Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," and consisted of three general steps. TVA first used the American Society of Mechanical Engineers/American Nuclear Society Probabilistic Risk Assessment (PRA) Standard (as endorsed by the NRC) to construct a technically acceptable PRA. Next, TVA had its PRA model peer reviewed to evaluate and document how well the model meets the PRA standard. Finally, the NRC staff reviewed TVA's submittal, focusing only on the key assumptions and areas identified by the peer review team as being of concern and the areas determined by the staff to be relevant to the application.
Enclosure contains Sensitive Unclassified Non Safeguards Information. When separated from enclosure, the transmittal document is decontrolled.
OfFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAl USE ONlY SEClJ:RITY RElATED INFORMATION A. Bhatnager -2 Because the construction of WBN Unit 2 is not yet complete, TVA developed the WBN Unit 2 PRA model for the IPE based on the assumption that the WBN Unit 2 plant will be identical to the WBN Unit 1 plant. The findings and conclusions from the NRC staff's review rely on (1) TVA's plans, as stated in the originallPE submittal dated February 9, 2010, to confirm that "Prior to [WBN] Unit 2 start up, it will be confirmed that the [WBN] Unit 2 PRA model matches the as-built, as-operated plant" and (2) the list of commitments that were submitted with the response dated August 12, 2010, to the staffs request for additional information (RAI) being incorporated into TVA's program for managing and acting upon these commitments.
As such, it was expected that TVA's WBN Unit 2 evaluation would include, but not be limited to, determinations of whether the model assumptions represent:
- Actual components comprising a given system.
- Actual spatial layout of equipment.
- Normal and emergency configurations of the plant.
- Normal, emergency, and test and maintenance procedures and practices as performed by WBN Unit 2 personnel.
- Engineering aspects of the plant design.
This evaluation should reveal any differences between the model assumptions and the as-built and as-operated configuration of WBN Unit 2. Moreover, the evaluation should assess the impact of those changes needed to match the WBN Unit 2 IPE PRA model to the as-built and as-operated WBN Unit 2 plant, and those changes should be qualified by the degree of the impact on the model results. In addition, TVA provided a list of commitments in its RAI responses that, when fully implemented, will resolve concerns raised by the NRC staff.
TVA defined the term "vulnerability" as the exceeding of the NRC Safety Goals subsidiary values of 1x10*4/reactor-year for the total core damage frequency and 1x10*5/reactor-year for the total large early release frequency. By this definition, TVA identified no vulnerabilities for WBN Unit 2; therefore, no enhancements were identified to specifically address vulnerabilities.
Although no vulnerabilities were identified, TVA did identify several plant improvements as part of the severe accident mitigation alternatives (SAMAs) analysis and committed to implement four SAMAs. These SAMAs included: (1) a review of station blackout procedures for improvements in direct current (DC) load shedding, (2) enhancement of procedural guidance for the use of cross-tied component cooling or service water pumps, (3) enhancement of procedural guidance for the use of essential raw cooling water for reactor coolant pump thermal barrier cooling, and (4) one SAMA that enhances a procedure for the temporary control of alterations to reduce fire risk associated with temporary cables.
GL 88-20 states that the "maximum benefit from the IPE would be realized if the licensee's staff were involved in all aspects of the examination" and recommends that each licensee "use its staff to the maximum extent possible in conducting the IPE by having utility engineers ...
involved in the analysis as well as in the technical review."
OFFICIAl USE ONlY SECURITY RElATED INFORMATION
OFFICIAL US. ONLY S.CURITY R.lAT.D INFORMATION A. Bhatnager -3 Based on the NRC staff's discussions with TVA during the review process, the NRC staff believes that TVA could enhance TVA staff's understanding of the WBN Unit 2 PRA model.
Although the NRC staff understands that TVA will fix the problems identified by the peer review, the NRC staff concluded that TVA could take actions to better gain {1} an overall appreciation of severe accidents that could occur at WBN Unit 2, {2} an understanding of the most likely severe accident sequences, (3) a quantitative understanding of core damage and fission product release, and (4) the ability to implement safety improvement opportunities that would help prevent or mitigate severe accidents.
Based on its review, the NRC staff finds TVA's definition of vulnerability and its conclusion that no severe accident vulnerabilities exist at WBN Unit 2 to be reasonable. Consequently, the NRC staff finds the WBN Unit 2 IPE to be consistent with the intent of GL 88-20, subject to the completion of the applicable commitments and TVA's plan to confirm, prior to WBN Unit 2 startup, that the WBN Unit 2 PRA model matches the as-built, as-operated plant. The NRC staff review was not intended to validate the accuracy of TVA's findings (or quantification estimates) that stemmed from the examination. Therefore, the enclosed technical evaluation report does not constitute NRC approval or endorsement of any IPE material for purposes other than those associated with meeting the intent of GL 88-20.
If you have any questions regarding the NRC staff review, please contact Patrick Milano at (301) 415-1457.
Sincerely, IRA!
Stephen J. Campbell, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Technical Evaluation Report cc w/o encl: Distribution via Listserv OFFICIAL US. ONLY S.CURITY R.lAT.D INFORMATION
OFFICIAl USE ONlY SECURITY RElATED INFORMATION A. Bhatnager - 3 Based on the NRC staff's discussions with TVA during the review process, the NRC staff believes that TVA could enhance TVA staff's understanding of the WBN Unit 2 PRA model.
Although the NRC staff understands that TVA will fix the problems identified by the peer review, the NRC staff concluded that TVA could take actions to better gain (1) an overall appreciation of severe accidents that could occur at WBN Unit 2, (2) an understanding of the most likely severe accident sequences, (3) a quantitative understanding of core damage and fission product release, and (4) the ability to implement safety improvement opportunities that would help prevent or mitigate severe accidents.
Based on its review, the NRC staff finds TVA's definition of vulnerability and its conclusion that no severe accident vulnerabilities exist at WBN Unit 2 to be reasonable. Consequently, the NRC staff finds the WBN Unit 2 IPE to be consistent with the intent of GL 88-20, subject to the completion of the applicable commitments and TVA's plan to confirm, prior to WBN Unit 2 startup, that the WBN Unit 2 PRA model matches the as-built, as-operated plant. The NRC staff review was not intended to validate the accuracy of TVA's findings (or quantification estimates) that stemmed from the examination. Therefore, the enclosed technical evaluation report does not constitute NRC approval or endorsement of any IPE material for purposes other than those associated with meeting the intent of GL 88-20.
If you have any questions regarding the NRC staff review, please contact Patrick Milano at (301) 415-1457.
Sincerely, IRA!
Stephen J. Campbell, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Technical Evaluation Report cc w/o enc!: Distribution via Listserv DISTRIBUTION:
Non-PUBLIC RidsAcrsAcnw_MailCTR Resource LP-WB RlF RidsNRRDorILp_WB Resource RidsOgcRp Resource DCoe, RES RidsNrrPMWattsBar 2 Resource RidsRgn2mailCenler Resource (RHaag) RidsNrrLABClayton s JLamb. NRR MDrouin. RES ADAMS ACCESSION NO: Non-Public Package ML111960242 Non-Public Letter ML111960062 Non- Public Enclosure ML111960218 Public Letter ML111960228 'via memo OFFICE DORULPWB/PM DORULPWB/LA RES/DRAID DORULPWB/BC NAME PMilano BClayton KCoyne for DCoe* SCampbell DATE 08/11111 08/11/11 03114111 08/12/11 OFFICIAL RECORDS COpy OFFICIAl USE ONlY SECURITY RElATED INFORMATION