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Category:Federal Register Notice
MONTHYEARML24172A1382024-07-16016 July 2024 Exemption from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - FRN ML24172A1402024-07-16016 July 2024 Exemption from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - FRN ML24089A1142024-06-21021 June 2024 Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) 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) ML24130A0012024-05-16016 May 2024 April 2024, Issuance of Multiple Exemptions Regarding Security Notifications, Reports, and Recording Keeping ML24114A3102024-05-0303 May 2024 Monthly (28-Day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 14, 2024 ML24082A0692024-04-19019 April 2024 FRN for CBS Exemption Decision Watts Bar ML24082A0762024-04-12012 April 2024 FRN: EA-FONSI Availability Watts Bar Combo ML24009A1722024-02-16016 February 2024 Environmental Assessment and Finding of No Significant Impact Related to an Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods (EPID L-2023-LLA-0039) - Federal Register Notice ML23073A2992023-04-0303 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) (FRN) 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) ML22129A0712022-05-0909 May 2022 Federal Register Notice (Correction) ML22117A1862022-04-29029 April 2022 Exemptions from the Requirements of 10 CFR Part 26, Section 26.205(d)(7) (EPID L-2022-LLE-0017) (Exemption) ML21063A1372021-03-18018 March 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity to Request Hearing,Order Imposing Procedures for SUNSI Document Access(Frn) ML21063A1362021-03-18018 March 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity to Request Hearing,Order Imposing Procedures for SUNSI Document Access(Lette ML20358A2202021-01-0505 January 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Sig. Hazards Consideration, and Opportunity for Hearing SUNSI ML20358A2192021-01-0505 January 2021 Cover Letter with Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Sig. Hazards Consideration, and Opportunity for Hearing SUNSI ML20034D6422020-02-12012 February 2020 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures: March ML19337A0312019-12-11011 December 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 12/17/2019 ML19298A6472019-10-31031 October 2019 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Opportunity for a Hearing ML19298A4772019-10-31031 October 2019 Federal Register Notice: Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Application; Opportunity to Comment; Request a Hearing, and Petition for Leave to Intervene ML19241A2962019-09-0606 September 2019 Transmittal of Individual Federal Register Renotice for License Amendment Request TSTF-50 ML19241A2952019-09-0606 September 2019 Individual Federal Register Renotice for License Amendment Request TSTF-500 ML19112A0112019-07-25025 July 2019 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 ML19112A0522019-07-25025 July 2019 Federal Register Notice: Watts Bar Nuclear Plant, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 ML19168A0842019-06-26026 June 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 ML18332A0132019-02-0606 February 2019 Federal Register Notice ML18332A0142019-02-0606 February 2019 Environmental Assessment and Finding of No Significant Impact Related to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, NRC-2019-0046, Federal Register Notice2019-02-0606 February 2019 Federal Register Notice ML18306A4682018-11-0808 November 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML18306A4802018-11-0808 November 2018 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML18295A7442018-10-25025 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/06/18 ML18200A2142018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 NRC-2014-0045, FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 22018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 ML18200A1922018-08-21021 August 2018 Withdrawal of Amd Request to Change Implementation Date for Emergency Action Level Scheme ML18173A1792018-08-0707 August 2018 OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C ML18189A0032018-07-11011 July 2018 FRN: Watts Bar Nuclear Plant, Unit 1, Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML18172A3042018-06-22022 June 2018 Tennessee Valley Authority - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML18173A0532018-06-22022 June 2018 Ind. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards ... ML18128A3062018-06-0404 June 2018 Federal Register Notice on Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Application; Opportunity to Request a Hearing and to Petition for Leave to Intervene; Order Imposing Procedures (Docket Nos. 50-390 and 50-391; NRC-2018-01 ML18128A2932018-05-30030 May 2018 Letter, Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing ML18039A8922018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) L-2016-003, Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034)2018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17200A0652017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement FRN, Paul Gunter, Beyond Nuclear, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and 2024-07-16
[Table view] Category:Letter
MONTHYEARCNL-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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 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) 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-24-028, 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 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 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 3, 2015 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE (TAC NO. MF6286)
Dear Mr. Shea:
The enclosed announcement was forwarded to the Rhea County Hearld-News, Advocate and Democrat, and Daily Post-Athenian newspapers for publication. This announcement relates to your application dated May 29, 2015, for amendment to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant (WBN), Unit 1. The proposed amendment would provide a one-time change to Technical Specification Table 3.3.4-1, Function 4a, "RCS Hot Leg Temperature Indication," to permit the temperature indication for Reactor Coolant System (RCS) Loop 4 to be inoperable for the remainder of WBN Unit 1 Operating Cycle 13.
If you have any questions, please contact me at 301-415-1349 or by email at Jeanne.Dion@nrc.gov.
Sincerely, Jeanne A. Dion, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Public Notice cc w/encl: Distribution via Listserv
PUBLIC NOTICE THE U.S. NUCLEAR REGULATORY COMMISSION PROPOSES TO AMEND THE FACILITY OPERATING LICENSE FOR THE WATTS BAR NUCLEAR PLANT, UNIT 1 The U.S. Nuclear Regulatory Commission (NRC, the Commission) has received an application dated May 29, 2015, from the Tennessee Valley Authority (TVA, the licensee) for an exigent amendment to the facility operating license for the Watts Bar Nuclear Plant (WBN),
Unit 1 located in Rhea County, Tennessee.
The proposed exigent amendment would provide a one-time change to Technical Specification (TS) Table 3.3.4-1, Function 4a, "RCS Hot Leg Temperature Indication," to permit the temperature indication for Reactor Coolant System (RCS) Loop 4 to be inoperable for the remainder of WBN Unit 1 Operating Cycle 13, the refueling outage for which is scheduled to start in September 2015. Specifically, the proposed exigent amendment would revise Note A at the bottom of TS Table 3.3.4-1, "Remote Shutdown System Instrumentation and Controls," to state: "For Function 4a, the temperature indicator for RCS hot leg 4 is not required to be operable for the remainder of Cycle 13." Additionally, should WBN Unit 1 experience a shutdown prior to the WBN Unit 1 Cycle 13 refueling outage, the temperature indicator will be repaired prior to startup.
The request is necessary because on May 16, 2015, TVA discovered that Temperature Indicator (Tl) 1-Tl-68-65C was not operable. Upon the discovery of this condition, TVA entered TS 3.3.4, "Remote Shutdown System," Condition A. Condition A requires restoration of the temperature indicator within 30 days. TVA has isolated the problem to components of the temperature indicator (modifier circuit or thermocouple) that are both located inside the Reactor Building Polar Crane Wall. The 30-day completion time for Condition A of TS 3.3.4 expires on June 15, 2015, at approximately 0448 EDT, at which point a plant shutdown is required.
Accordingly, TVA requested approval of the proposed TS change by June 14, 2015, and that the implementation of the revised TS be effective immediately to avoid the requirement to shutdown WBN Unit 1. The temperature indicator is one of four instruments that provide indication in the Auxiliary Control Room (ACR) for the hot leg temperature of RCS Loop 4. The other three instruments remain operable.
The licensee requested that the proposed amendment be processed on an exigent basis, in accordance with the provisions in Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.91 (a)(6). Under 10 CFR 50.91 (a)(6)(i)(B), where the Commission finds that exigent circumstances exist, in that a licensee and the Commission must act quickly and that time does not permit the Commission to publish a Federal Register notice allowing 30 days for prior public comment, and it also determines that the amendment involves no significant hazards considerations, the Commission will use local media to provide reasonable notice to the public in the area surrounding a licensee's facility of the licensee's amendment and of its proposed determination that no significant hazards consideration is involved, consulting with the licensee on the proposed media release and on the geographical area of its coverage.
The licensee bases its claim of exigent circumstances on the following considerations.
TVA could not have reasonably anticipated the failure of the instrumentation. Although WBN Unit 1 did experience a failure of the RCS Loop 4 hot leg instrument in 2004, the issues in the 2004 failure resulted in a full scale reading. The issues associated with the current failure (failing low scale) have been isolated to the modifier circuit or the thermocouple. Nothing in the 2004 failure could have led TVA to reasonably anticipate the current failure. The repair of the affected instrumentation precludes repair at power because the affected instrumentation is located inside the Reactor Building Polar Crane Wall, which is a high dose area during power operations. The shutdown of the plant to implement the repairs is not necessary because the
remaining temperature indications available in the ACR are adequate to safely shutdown the unit should an emergency arise.
As required by 10 CFR 50.91 (a), the licensee has provided its analysis of the issue of no significant hazards consideration using the standards in 10 CFR 50.92. The licensee and the NRC have evaluated the proposed change with regard to the determination of whether or not a significant hazards consideration is involved.
Operation of WBN Unit 1, in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed TS change to allow operation with only three of four loop remote shutdown indications for RCS hot leg temperature until the Cycle 13 refueling outage scheduled for September 2015 is only applicable to the following conditions:
A. Fire or smoke in the Main Control Room (MCR).
B. An evacuation of the MCR due to some other (non-fire) unspecified reason.
C. The design basis flood.
The inoperability of the one hot leg temperature indicator does not change the probability of occurrence for these events because the indicator is not an accident initiator. The hot leg temperature indicators on the four RCS loops are used for indication only and have no automatic control functions. During safe shutdown for an MCR evacuation event, design basis flood, or fire related event, no fuel damage is postulated to occur, nor is the integrity of the reactor coolant pressure boundary or containment barriers postulated to be lost. Sufficient redundancy exists with the operational instrumentation to ensure that decay heat removal functions are not adversely affected by this change. Therefore, the proposed change does not
involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment will not create the possibility of a new or different kind of accident from any previously analyzed. The proposed TS change does not alter the function of the Remote Shutdown System, which is to achieve and maintain safe reactor shutdown from outside the MCR. The TS instrumentation and controls required are such that sufficient capability is retained for decay heat removal via the Steam Generators to provide the indication required for safe shutdown capabilities. The proposed change will not result in the installation of any new equipment or system. The hot leg temperature instrument is used for indication only and has no automatic control functions. No new operations procedures will be created by this change. Appropriate operational procedures will be updated to clarify that the RCS Loop 4 hot leg temperature indication in the ACR is not available during the remainder of Cycle 13. No new operating conditions or modes will be created by this proposed change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed amendment will not involve a significant reduction in a margin of safety.
Sufficient redundancy exists with the operational instrumentation to ensure that decay heat removal functions are not adversely affected by this change. Because the conduit, cables, and equipment that provide hot leg temperature indication in the ACR are routed outside the Control Building, removal of the RCS Loop 4 hot leg temperature indication is acceptable due to the redundant paths not being affected by a Control Building fire. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Following an initial review of this application, the requested amendment has been evaluated against the standards in 10 CFR 50.92 and the NRC has made a proposed
(preliminary) determination that the requested amendment involves no significant hazards considerations. Operation of WBN Unit 1 in accordance with the proposed amendment would not significantly increase the probability or consequences of any accident previously considered, nor create the possibility of a new or different kind of accident, nor significantly reduce any margin of safety.
If the proposed determination that the requested exigent license amendment involves no significant hazards consideration becomes final, the NRC will issue the amendment without first offering an opportunity for a public hearing. An opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.
If the NRC decides in its final determination that the requested exigent license amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before the amendment is issued.
Comments on the proposed determination of no significant hazards consideration may be (1) telephoned to Jessie Quichocho, Chief, Watts Bar Special Projects Branch, by collect call to 301-415-0209, or by facsimile to 301-415-1222, (2) e-mailed to Jessie.Quichocho@nrc.gov, or (3) submitted in writing to the Chief, Rules, Announcements and Directives Branch, Division of Administrative Services, Office of Administration, Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. All comments received by 5:00 p.m. on June 11, 2015, will be considered in reaching a final determination. A copy of the application may be examined electronically through the NRC's Agencywide Documents Access and Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html by using the Accession No. ML15149A511 and at the Commission's Public
Document Room (PDR), located at One White Flint North, Public File Area 01-F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737, or by e-mail to pdr.resource@nrc.gov.
PKG ML15152A469 LTR ML15152A465 Public Notice ML15152A473 *via e-mail OFFICE DORL/LPWB/PM DORL/LPWB/LA OGC-NLO* DORL/LPWB/BC DORL/LPWB/PM NAME JD ion BClayton JWachutka JQuichocho JDion (RKuntz for) (RSchaaf for) (RKuntz for)
DATE 6/2/15 6/1/15 6/2/15 6/3/15 6/3/15