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Category:Code Relief or Alternative
MONTHYEARML23233A0042023-08-28028 August 2023 – Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-012022-11-28028 November 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML21130A6012021-05-13013 May 2021 Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21110A0372021-04-29029 April 2021 Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML19227A1102019-08-26026 August 2019 Alternative Request for the Turbine Driven Auxiliary Feedwater Pumps 10-Year Interval Inservice Testing Program CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. ML19071A0092019-04-12012 April 2019 Relief Request 1-ISI-21 from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML18227A5992018-08-23023 August 2018 Request to Use a Later Edition of the Asme Boiler and Pressure Vessel Code, Section XI for Containment Inservice Inspection Activities CNL-18-078, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Lnservice Inspection (ISI) Program, Second Ten Year Interval Request for Relief for 1-ISI-212018-05-25025 May 2018 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Lnservice Inspection (ISI) Program, Second Ten Year Interval Request for Relief for 1-ISI-21 ML17292B2952017-10-28028 October 2017 Relief from the Requirements of the American Society of Mechanical Engineers Code (CAC No. MF8515; EPID L-2016-LLR-0003) ML16239A0722016-10-18018 October 2016 Alternative to Inservice Inspection Requirements of the ASME Boiler and Pressure Vessel Code for Examination of Reactor Pressure Vessel Shell-To-Flange Weld ML16238A0432016-10-18018 October 2016 Relief from the Requirements of the ASME Code for Reactor Pressure Vessel Flange Seal Leakoff Piping ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16084A6902016-04-26026 April 2016 Relief from the Requirements of the ASME Code for Reactor Pressure Vessel Flange Seal Leak-Off Piping ML15215A4842015-08-0808 August 2015 Relief from the Requirements of the ASME Code for the First 10-Year Interval of the Containment Inservice Inspection ML14314A9872014-11-28028 November 2014 Request for Alternative 13-ISI-01 to Extend the Second Reactor Vessel Weld Inservice Inspection Interval CNL-14-139, Request for Alternative ISPT-032014-09-12012 September 2014 Request for Alternative ISPT-03 ML1029302992010-10-11011 October 2010 American Society of Mechanical Engineers Section XI Request for Relief WBN-2/PSI-1 ML1027005272010-09-29029 September 2010 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certification ML0830900462008-10-30030 October 2008 Preservice Inspection Program Plan and Request for Relief No. WBN-2/PDI-4 ML0708003612007-06-11011 June 2007 Request for Relief G-RR-1 Regarding Preemptive Weld Overlays on Pressurizer Nozzles ML0703900102007-02-0707 February 2007 Updated Inservice Inspection Program for Second 10-Year Interval and Requests for Relief Nos. PDI-2, PDI-4, and SNBR-1 ML0615901112006-08-30030 August 2006 Relief, One Time Request for Relief from ASME, Section XI, Code Requirements - Tests Following Repair, Modification, or Replacement ML0617303862006-07-11011 July 2006 Relief, Relief Request No. ISPT-09 for the First Ten-Year Inservice Inspection Interval ML0618701442006-06-30030 June 2006 Inservice Test Program Update and Associated Relief Requests for Second Ten-Year Interval ML0528002312005-10-0404 October 2005 NRC First Revised Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors - Request for Relief ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0436305502005-01-25025 January 2005 Relief, Safety Evaluation of Inservice Inspection Relief Nos. 1-ISI-14 and 1-ISI-15 First 10-Year Inspection Interval, MC2368 & MC2369 ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0424300292004-08-27027 August 2004 Relief Request 1-RR-05 Use of Code Case N-597-1 to Evaluate Pipe Wall Thinning, MC1580 ML0329302632003-10-15015 October 2003 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Appendix Viii, Supplement 10 - Qualification Requirements for Dissimilar Metal Piping Welds, Request for Relief PDI-3 ML0300906472003-01-0909 January 2003 Relief, Volumetric Examination for Reactor Vessel Head-to-Flange Weld, MB5693 ML0203101852002-02-0606 February 2002 Relief Request, Evaluation of ISI Program 2023-08-28
[Table view] 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-24-047, 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) 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 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 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-24-025, 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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Tennessee Valley Authority, Post Office 2000, Spring City. Tennessee 37381-2000 Mike Skaggs Site Vice President, Watts Bar Nuclear Plant OCT 0 4 2005 EA-03-009 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-390 Tennessee Valley authority )
WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - NRC FIRST REVISED ORDER EA-03-009 ESTABLISHING INTERIM INSPECTION REQUIREMENTS FOR REACTOR PRESSURE VESSEL HEADS AT PRESSURIZED WATER REACTORS -
REQUEST FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i) and NRC Order EA-03-009 Section IV.F, TVA is requesting relief from NRC Order EA-03-009, Paragraph IV.C.3 schedule requirements. The request for relief is associated with the schedule for performing the nonvisual nondestructive examinations of the reactor pressure vessel head surface penetration nozzles required in Paragraph IV.C(5)(b) at least once prior to February 11, 2008. TVA has determined that an alternative schedule is needed for that specific examination because of the impacts the Order's schedule would otherwise have on WBN's long-planned steam generator replacement project in Cycle 7 Refueling Outage in the Fall 2006. TVA's intent to submit an alternate schedule was discussed with NRC in a teleconference call on September 12, 2005.
This relief request provides a one time relief to the February 11, 2008 schedule. Thereafter, TVA plans to perform.
the examinations in accordance with the interim inspection requirements of NRC Order EA-03-009. TVA does not plan for the unit to operate after February 10, 2008, until the requisite examinations have been completed. Therefore, TVA is requesting NRC's review and approval of this alternative schedule by mid-August 2006 to ensure that TVA can adequately plan for Cycle 7 outage activities, if required.
ftud 7c p.
U.S. Nuclear Regulatory Commission Page 2 OCT 0 4 2005 A listing of regulatory commitments is provided in Enclosure
- 2. If you have any questions concerning this matter, please call P. L. Pace at (423) 365-1824.
Sincerely, Mike Skagg Enclosures cc (Enclosures):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. D. V. Pickett, Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF TO NRC ORDER EA-03-009 I. Summary:
The NRC Order EA-03-009 issued on February 11, 2003, as revised on February 20, 2004, established interim inspection requirements for reactor pressure vessel (RPV) heads at pressurized water reactors. One of the requirements is to complete a nonvisual nondestructive examination of the RPV head penetrations by February 11, 2008. In response to the revised Order, TVA notified NRC in a March 11, 2004, letter that a firm schedule for completing the nonvisual nondestructive examination had yet to be determined due to the process of planning a steam generator replacement project.
The letter also stated that WBN would submit appropriate schedule relief in accordance with the Order requirements if relief was needed. It has been determined schedule relief is needed.
During the Cycle 7 Refueling Outage scheduled for the Fall of 2006, WBN will be replacing all four of the Unit 1 steam generators. This project will involve a considerable amount of work in the Unit 1 Containment Building. Scheduling the RPV nonvisual nondestructive examination during this outage will increase general area dose rates to the supplemental steam generator replacement (SGR) personnel, increase critical path time to the outage, and increase the possibility of damage to the head and associated control rod drive assemblies while on the head stand due to the overhead work associated with the SGR project. It is planned to "store" the RPV head on the vessel with the reactor cavity missile shields reinstalled during the SGR project. As a result, the nonvisual nondestructive examination of the RPV head penetrations cannot be performed during this configuration.
In accordance with Paragraph IV.F of the Order, WBN is requesting relief from the schedule requirement to complete the nonvisual nondestructive examination by February 11, 2008.
In the alternative, however, WBN plans to shut down on or before February 10, 2008, for the Cycle 8 Refueling Outage, and perform the nonvisual nondestructive examination prior to restarting the unit. WBN is also proposing to perform the bare metal visual inspection required by Paragraph IV.C(5)(a) of the Order in the Cycle 7 Refueling Outage. This visual inspection was performed in accordance with the Order requirements in the Cycle 5 Refueling Outage and no indication of leakage was reported.
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF TO NRC ORDER EA-03-009 This proposed alternative schedule is submitted in accordance with Paragraph IV.F of the Order and 10 CFR 50.55a (a)(3)(i).
The proposed alternative discussed above and the low susceptibility ranking of the WBN head as calculated by the Order, provide an acceptable level of quality and safety. TVA is requesting NRC's review and approval of this alternative schedule by mid-August 2006 to ensure that TVA can adequately plan for Cycle 7 outage activities.
II. System/Component(s) for Which Relief is Requested:
Reactor Pressure Vessel Closure Head Penetration Welds III. Code Requirement:
NRC Revised Order EA-03-009, Paragraph IV.C.(3) states:
"The requirements of paragraph IV.C.(5)(b) must be completed at least once prior to February 11, 2008, and thereafter, at least every 4 refueling outages or every 7 years, whichever occurs first."
IV. Code Requirements from Which Relief Is Requested:
Relief is requested from the schedule requirement of completing the inspection prior to February 11, 2008 as required by Paragraph IV.C.(3) of the Order.
V. Basis for Relief:
Licensees proposing to deviate from the requirements of the Order are allowed to seek relaxation in accordance with the requirements of Paragraph IV.F. In response to issuance of the revised Order, WBN responded in the March 11, 2004 letter:
"WBN is in the process of planning and scheduling a considerable amount of work in Unit 1 containment associated with steam generator replacement project. Until that planning and scheduling process is complete, WBN is unable to develop a firm schedule for completing the nonvisual nondestructive examination of the RPV head penetrations addressed in Paragraph XV.C.(3) of the Order.
Should WBN require any schedule relief, TVA will submit an appropriate relief request in accordance with Paragraph IV.F of the Order and 10 CFR 50. 55a(a) (3). "
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF TO NRC ORDER EA-03-009 VI. Alternative Examinations:
WBN proposes to:
(1) Perform the bare metal visual examination of 100 percent of the RPV head surface as required by Paragraph IV.C.(5)(a) of the Order during the Cycle 7 Refueling Outage in Fall of 2006. Successive bare metal visual examinations will be scheduled in accordance to the requirements of Paragraph IV.C.(3) of the Order.
(2) Shut down the unit on or before February 10, 2008, for Cycle 8 Refueling Outage, and perform the nonvisual nondestructive examination in accordance with the requirements of Paragraph IV.C.(5)(b) of the Order prior to restarting the unit.
VII. Justification for the Granting of Relief:
In response to the revised Order, TVA notified NRC in a March 11, 2004 letter that a firm schedule for completing the nonvisual nondestructive examination had yet to be determined due to the process of planning the replacement of the four Unit 1 steam generators. The letter also stated WBN would submit appropriate schedule relief in accordance with the Order requirements if relief was needed.
The nonvisual nondestructive examination is normally performed during the core empty period with the head set on a modified head stand. The modified head stand is required to elevate the head in the stored position to allow the inspection tool to be placed under the head. The location of the WBN head stand is in a critical work path for SGR upper containment work scope and will have a significant impact to the project.
The SGR project will involve a considerable amount of work in the Unit 1 Containment Building. Scheduling the RPV nonvisual nondestructive examination during this outage will increase general area dose rates to the supplemental SGR personnel, increase critical path time to the outage, and increase the possibility of damage to the head and associated control rod drive assemblies while on the head stand due to the overhead work associated with the SGR project. It is planned to "store" the RPV head on the vessel with the reactor cavity missile shields reinstalled during the SGR project. The nonvisual nondestructive examination of the RPV head penetrations cannot be performed during this configuration.
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF TO NRC ORDER EA-03-009 As noted in the referenced response letter, WBN is a low susceptibility plant as defined by the Order. WBN will not exceed the NRC established threshold of low susceptibility for the current licensed life of the plant primarily due to the low operating head temperature.
WBN performed the bare metal visual examination of the reactor vessel head surface described in Paragraph IV.C(5)(a) of the Order during the Cycle 5 Refueling Outage in September 2003.
No leakage was reported. The inspection results were provided to NRC by letter dated December 10, 2003. As required by Paragraph IV.C(3) of the Order, this examination must be completed at least every third refueling outage or every 5 years, (i.e. by the WBN Cycle 8 refueling outage); however, WBN proposes to perform this bare metal visual examination during the Cycle 7 Refueling Outage scheduled for Fall of 2006. Successive bare metal visual examinations will be scheduled in accordance with Paragraph IV.C(3).
WBN plans to shut down Unit 1 from operation on or before February 10, 2008. The nonvisual nondestructive examination of the closure head will be performed in accordance with Paragraph IV.(5)(b) of the Order prior to restarting the unit.
Based on information discussed above and the proposed action of placing the unit in a safe shutdown mode prior to February 11, 2008, an acceptable level of quality and safety is achieved. Therefore, WBN submits this proposed alternative in accordance with 10 CFR 50.55a(a)(3)(i) and requests relief be authorized.
VIII.IImplementation Schedule:
WBN plans to shut down Unit 1 on or before February 10, 2008 for the Cycle 8 Refueling Outage and will perform the nonvisual nondestructive examination in accordance with the requirements of Paragraph IV.C.(5)(b) of the Order prior to restarting the unit.
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT 1 FIRST 10-YEAR INTERVAL REQUEST FOR RELIEF TO NRC ORDER EA-03-009 LIST OF COMMITMENTS
- 1. WBN will perform the bare metal visual examination of 100 percent of the RPV head surface as required by Paragraph IV.C.(5)(a) during the Cycle 7 Refueling Outage in Fall of 2006.
- 2. WBN will perform the nonvisual nondestructive examination in accordance with the requirements of Paragraph IV.C.(5)(b) of the Order prior to restarting the unit from the Cycle 8 Refueling Outage.
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