Letter Sequence Other |
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TAC:MD8314, Clarify Application of Setpoint Methodology for LSSS Functions, Control Room Habitability, Steam Generator Tube Integrity (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12, CNL-15-137, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 13, CNL-15-150, Pressurizer PORV Block Valves - Dynamic Testing Alternative, ML080370185, ML081490110, ML081490118, ML082140238, ML082560373, ML082750019, ML101200204, ML101260469, ML101680561, ML101760222, ML102170077, ML102290258, ML102700527, ML103010299, ML110210486, ML11213A130, ML11362A056, ML12234A688, ML13023A315, ML13213A194
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MONTHYEARML0803701852008-02-0101 February 2008 Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Case N-520-2, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction. Project stage: Other ML0813008092008-05-22022 May 2008 Request for Additional Information, Renewal of Active or Expired N-Type Certificates for Plants Project stage: RAI ML0814901182008-05-28028 May 2008 NRC Review: Generic Communications Status for TVA Watts Bar Unit 2 Project stage: Other ML0814901102008-05-28028 May 2008 Status of Generic Communications for Review (Tac No. MD8314) Project stage: Other ML0818504592008-07-0202 July 2008 Response to Request for Additional Information Project stage: Response to RAI ML0821402382008-07-29029 July 2008 Generic Communications Status, Revision 1 Project stage: Other ML0827500192008-09-26026 September 2008 Regulatory Framework for the Completion of Construction and Licensing Activities for Unit 2 - Corrective Action and Special Programs, and Unresolved Safety Issues Project stage: Other ML0825603732008-10-0202 October 2008 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates Project stage: Other ML1001204872009-11-12012 November 2009 Application for Special Nuclear Material License in Accordance with 10 CFR 70, Domestic Licensing of Special Nuclear Material Project stage: Request ML1001916842010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 3 - Design of Structures, Components, Equipment, and Systems, Page 3.8.5-1 Through Page 3.11-9 Project stage: Request ML1001914212010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97 Project stage: Request ML1012002042010-04-20020 April 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1012604692010-04-29029 April 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 2, and Status of Generic Communications for Unit 2 - Revision 2 Project stage: Other ML1016805612010-06-17017 June 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1019402362010-06-18018 June 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1017602222010-06-25025 June 2010 Request to Use ASME Boiler and Pressure Vessel Code, Code Case N-520-3, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction, Section III, Division 1 Project stage: Other ML1021700772010-07-30030 July 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 3, and Status of Generic Communications for Unit 2 - Revision 3 Project stage: Other ML1022902582010-07-31031 July 2010 Final Safety Analysis Report - Response to Preliminary Requests for Additional Information and Requests for Additional Information Project stage: Other ML1025001712010-09-0101 September 2010 OL - TVA Letter to NRC - WBN U2 FSAR A100 Project stage: Request ML1027005272010-09-29029 September 2010 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certification Project stage: Other ML1030102992010-10-28028 October 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 4, and Status of Generic Communications for Unit 2 - Revision 4 Project stage: Other ML1031207112010-10-29029 October 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1031207122010-10-29029 October 2010 Edcr 52321 Draft Scope and Intent, Unit Difference and Technical Evaluation, Enclosure 2, Attachment 1 Project stage: Request ML1031403142010-11-0101 November 2010 OL - TVA Letter to NRC_10-29-10_WBN U2 FSAR 101 Project stage: Request ML1032001462010-11-0909 November 2010 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1032106442010-11-17017 November 2010 Revision of Commitment for Implementation of the Maintenance Rule Project stage: Request ML1035405602010-12-17017 December 2010 Safety Evaluation Report Supplement 22 (SSER22) - Response to Requests for Additional Information Project stage: Supplement ML1102104862011-01-21021 January 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 5 and Status of Generic Communications for Unit 2 - Revision 5 Project stage: Other ML1106202192011-02-25025 February 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML1110500092011-04-0808 April 2011 OL - FW: Updated OI List Project stage: Request ML11136A0532011-04-18018 April 2011 OL - TVA Letter to NRC_04-15-11_I&C RAI Response Project stage: Request ML11129A2052011-05-0606 May 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML11178A1552011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104 Project stage: Request ML11167A1102011-06-10010 June 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML11213A1302011-07-27027 July 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 6 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 6 Project stage: Other ML11213A2612011-07-28028 July 2011 Results from Cost-Benefit Analysis of Radwaste System Enhancements Project stage: Request ML11292A1992011-10-17017 October 2011 Revision of Commitment for Unit 2's Implementation of the Maintenance Rule Project stage: Request ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 Project stage: Other ML12234A6882012-08-15015 August 2012 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 8 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 8 Project stage: Other ML12249A1952012-08-30030 August 2012 Instrumentation and Controls Staff Request for Additional Information (RAI) Related to Supplemental Safety Evaluation Report (Sser) Open Item 80 Project stage: Supplement ML12284A5132012-10-0404 October 2012 NRC Bulletin No. 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System (RCS) - Clarification Project stage: Request ML12284A5142012-10-0404 October 2012 Revision of Commitment for Unit 2's Implementation of the Maintenance Rule Project stage: Request ML12312A1672012-10-25025 October 2012 Unit 1 & 2, Watts Bar, Units 1 & 2, 90-Day Response to NRC Bulletin 2012-01, Design Vulnerability in Electric Power System. Project stage: Request ML12349A3792012-12-10010 December 2012 Instrumentation and Controls Staff Request for Additional Information (RAI) Related to Supplemental Safety Evaluation Report (Sser) Open Item 80 Project stage: Supplement ML13023A3152013-01-17017 January 2013 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 9 (TAC No. MD6311), and Status of Generic Communications for Unit 2 -Revision 9 Project stage: Other ML13030A0322013-01-24024 January 2013 Documentation of Liability Insurance Coverage Requested Per Supplemental Safety Evaluation Report (Sser) Open Item 25 Project stage: Request ML13213A1942013-07-25025 July 2013 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 10 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 10 Project stage: Other CNL-13-149, Updated Inservice Test (IST) Program (Unit 1) and Ist/Preservice Test (Pst) Program2013-12-12012 December 2013 Updated Inservice Test (IST) Program (Unit 1) and Ist/Preservice Test (Pst) Program Project stage: Request CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 122014-09-0202 September 2014 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12 Project stage: Other CNL-15-063, Supplement Safety Evaluation Report - Open Item 33 - Completion of Dcns 53421 and 546362015-04-0707 April 2015 Supplement Safety Evaluation Report - Open Item 33 - Completion of Dcns 53421 and 54636 Project stage: Request 2010-09-01
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Category:Letter
MONTHYEARML24219A0262024-08-12012 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-24-010, 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) 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-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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) 2024-08-07
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, TN 37381-2000 July 29, 2008 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of Tennessee Valley Authority))Docket No. 50-391 WATTS BAR NUCLEAR PLANT (WBN) -UNIT 2 -GENERIC COMMUNICATIONS STATUS FOR UNIT 2 -REVISION 1 (TAC NO. MD8314)
References:
- 1. NRC letter dated May 28, 2008, 'Watts Bar Nuclear Plant, Unit 2 -Status of Generic Communications (TAC NO. MD8314)" 2. TVA letter dated March 20, 2008, 'Watts Bar Nuclear Plant (WBN) -Unit 2 -Generic Communications Status for Unit 2 -Restructured Tables" The purpose of this letter is to respond to an NRC request for additional information (Reference
- 1) regarding several Generic Communications.
TVA provided a comprehensive list of the status of completion of Generic Communications for WBN Unit 2 on March 20, 2008 (Reference 2).In Reference 1, the NRC did not agree with TVA's determination that certain Generic Communications were not applicable for WBN Unit 2. NRC requested further information to reconcile the differences between TVA's determination and the NRC assessment on thirteen specific Generic Communications.
Enclosure 1 provides further information on the Generic Communications in the same form as provided in Reference
- 2. Enclosure 2.provides the listing of open actions required for licensing identified in this letter.C)Eo&Printed on recycled paper U.S. Nuclear Regulatory Commission Page 2 July 29, 2008 As requested, TVA will provide an update to the status of Generic Communications at approximate six month intervals, including references to closure documentation.
If you have any questions, please contact me at (423) 365-2351.Sincerely, Masoud B j tani Watts Ba it 2 Vice President Enclosures cc (Enclosures):
Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Patrick D. Milano, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08H4 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Unit 2 Wafts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 GENERIC COMMUNICATIONS:
REVISION I CHANGES ITEM TITLE REV ADDITIONAL INFORMATION C 79-023 Motor Starters and Contactors Failed to Operate C 79-025 Shock Arrestor Strut Assembly Interference C 81-013 Torque Switch Electrical Bypass Circuit for Safeguard Service Valve Motors C The Circular did not require a response.01 TVA reported a nonconformance under 10 CFR 50.55e on January 17, 1980, that four motor starters of this type had been located in the 480V control and auxiliary vent boards at WBN.Gould factory representatives supervised the replacement of the carrier assemblies in accordance with the Gould instructions.
The starters with replaced carriers were acceptable.
NRC IR 50-390/80-03 and 50-391/80-02 reviewed and closed the associated nonconformance reports.C The Circular did not require a response.01 TVA reported a nonconformance under 10 CFR 50.55e on March 6, 1980, that a review had determined that nine installed supports had brackets with the potential of hindering full function of the support. Additional supports that were not installed had the same potential problem. TVA initially determined that the supports would be modified in accordance with a vendor approved drawing. TVA subsequently determined that no actual problem existed and no field work was required.NRC IR 50-390/83-15 and 50-391/83-11 reviewed and closed the associated nonconformance reports.C The Circular did not require a response.01 TVA reported a nonconformance under 10 CFR 50.55e on April 4, 1986 (NCR W367-P), that required closing torque switches were found improperly wired. This issue (Torque switch and overload relay bypass capability for active safety related valves) is part of the Electrical Issues Corrective Action Program for WBN Unit 2.NA GL 79-24 provided a discussion of an inadvertent reactor scram and safety injection during monthly surveillance tests of the 01 safeguards system at a PWR facility.
The GL requested a review to determine if similar errors had or could have occurred at other PWRs. The GL further requested a review of management policies and procedures to assure that multiple equipment failures in safety-related systems will be vigorously pursued and analyzed to identify significant reduction in the ability of safety systems to function as required.
A response was requested within 30 days of receipt of the GL with the results of these reviews. TVA does not have a record of receiving or responding to this GL. Thus, WVA concluded that this item was applicable only to PWRs with an operating license at the time the GL was issued.NA GL 79-51 provided follow-up actions resulting from the Three Mile Island Unit 2 accident.
GL 79-51 was provided for planning 01 and guidance purposes.
Its principal element was a report titled"TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations" (NUREG-0573).
This GL and the NUREG were superseded by GL 80-90 and NUREG-0737.
See GL 80-90 for further information.
GL 79-024 Multiple Equipment Failures in Safety-Related Systems GL 79-051 Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident Page I of 3* = See last page for status code definition.
- A ITEM TITLE REV ADDITIONAL INFORMATION GL 79-063 Upgraded Emergency Plans C GL 79-63 advised applicants for licenses of proposed rulemaking that NRC concurrence in State and local emergency plans would 01 be a condition for issuing an operating license. TVA responded to GL 79-63 on January 3, 1980, and confirmed the intent to revise the Emergency Plan to address the NRC requirements.
...........................................................................................................................................
GL 80-011 B 80-03, "Loss of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells"-..-..--.--------.-----------.--.-..-..-----.-----.-..-...
GL 80-028 B 80-08, "Examination of Containment Liner Penetration Welds" GL 80-032 Information Request on Category I Masonry Walls Employed by Plants Under CP and OL Review GL 80-092 B 80-21, "Valve Yokes Supplied by Malcolm Foundry Company, Inc."....... .D...................
.m.........................
...GL 86-004 Policy Statement On Engineering Expertise On Shift GL 89-002 Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products C GL 80-11 transmitted Bulletin 80-03. TVA responded to B 80-03 on March 21, 1980. See B 80-03 for further information.
01.............................................................................
C GL 80-28 transmitted Bulletin 80-08. TVA responded to B 80-08 on July 8, 1980. See B 80-08 for further information.
01 C GL 80-32 transmitted NRC questions on masonry walls.TVA provided the information requested by letters dated 01 February 12, 1981, for reinforced walls and August 20, 1981, for nonreinforced walls. TVA provided a final response on January 22, 1982. See B 80-11 for further information.
C GL 80-92 transmitted Bulletin 80-21. TVA responded to B 80-21 on May 6, 1981. See B 80-21 for further information.
01 C TVA responded to GL 86-04 on May 29, 1986. TVA provides engineering expertise on shift in the form of a dedicated Shift 01 Technical Advisor (STA) or an STA qualified Senior Reactor Operator.C GL 89-02 did not require a response.01 WBN Unit 2 program for procurement and dedication of materials is based in part on and complies with the guidance of GL 89-02. The program is implemented through project procedures.
O TVA responded to GL 89-21 with the status of USIs for both units on November 29, 1989. NRC provided an assessment of WBN 01 USI status on May 1, 1990. The NRC assessment included a list of incomplete USIs for WBN. USIs were initially reviewed for WBN in the SER Appendix C. USIs were subsequently reviewed in SSER 15 Appendix C (June 1995) and SSER 16 (September 1995).Unit 2 actions: Provide a status of WBN Unit 2 USIs.Complete implementation of USIs.GL 89-021 Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements Page 2 of 3* = See last page for status code definition.
- ITEM TITLE REV ADDITIONAL INFORMATION STATUS CODE DEFINITIONS C: CLOSED: Previous staff review of NUREG-0847 and/or supplements has closed the item either for both units at WBN or explicitly for WBN Unit 2.CI: CLOSED/IMPLEMENTATION:
Staff has approved either for both units at WBN or explicitly for WBN Unit 2; there is no change to the approved design; and implementation is recommended through Regional Inspection.
CT: CLOSED/TECHNICAL SPECIFICATIONS:
Item has been approved either for both units at WBN or explicitly for WBN Unit 2; however, a change to the original approval requires submittal of the Technical Specifications and staff review.NA: NOT APPLICABLE:
Justification as to why a section / subsection is not applicable is provided in the ADDITIONAL INFORMATION column.0: OPEN: No action or documentation is provided that shows the staff has reviewed the item for WBN Unit 2.OT: OPEN/TECHNICAL SPECIFICATIONS:
No action or documentation is provided that shows the staff has reviewed the item for WBN Unit 2, and the resolution is through submittal of a Technical Specification.
OV: OPEN/VALIDATION:
The proposed approach has been approved for Watts Bar Unit 1; the same approach is proposed for use on WBN Unit 2 without change.Page 3 of 3* = See last page for status code definition.
Enclosure 2 Listing of Open Actions Required for Licensing 1. TVA will provide an update to the status of generic communications at approximately six month intervals, including references to closure documentation.
- 2. Provide a status of WBN Unit 2 Unresolved Safety Issues by August 21, 2008.