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| {{#Wiki_filter:}} | | {{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 March 13, 2014 10 CFR 50.55a ATTN. Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C . 20555-0001 |
| | |
| | ==Subject:== |
| | Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 Response to Request for Clarifying lnformation Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 1O-Year lnservice lnterva!2001 Edition |
| | |
| | ==References:== |
| | : 1. Letter from TVA to NRC, "American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 10 Year lnservice lnterval 2001 Edition," dated January 10, 2014 Electronic Mail from NRC to TVA, "Watts Bar Nuclear Station, Unit 1 -Request for Additional lnformation Related Request for Alternative Number ISPT-O2, Regarding System Leakage Test of Reactor Pressure Vessel Head Flange Seal Leak-Off Piping," dated February 11,2014 Letter from TVA to NRC, "Response to Request for Additional lnformation Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 10-Year lnservice lnterval 2001 Edition," dated February 21,2014 By letter dated January 10,2014 (Reference 1), the Tennessee Valley Authority (TVA)submitted a request for alternative regarding system leakage test of reactor pressure vessel head flange seal leak-off piping. By Electronic Mail from NRC to TVA dated February 11,2014 (Reference 2), TVA received a Request for Additional lnformation (RAl) regarding the proposed request for alternative. |
| | TVA provided its response to the Reference 2 RAI in the Reference 3 letter on February 21,2014. ln a teleconference on February 26,2014, the NRC requested additional clarification regarding the proposed alternative visual inspection provided in Reference 1 and additional details regarding the configuration of the reactor vessel flange provided in Reference 3.2 U.S. Nuclear Regulatory Commission Page 2 March 13,2014 The enclosure to this letter provides the requested clarifying information. |
| | Please address any questions regarding this request to Gordon Arent at (423) 365-2004.Site Vice President Watts Bar Nuclear Plant |
| | |
| | ==Enclosure:== |
| | |
| | Response to NRC Request for Clarifying lnformation cc (Enclosure): |
| | NRC RegionalAdministrator - Region ll NRC Resident lnspector - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT {Response to NRC Request for Clarifying lnformation Additional lnsoection Details: The lnservice lnspection Program Augmented Examinations of the Reactor Vessel Hot Leg (HL)nozzle safe ends are performed with qualified personnelfrom the TVA lnspection Services Organization (lSO). These examinations are an enhanced visualexam (VE) that requires a W-2 qualified individual. |
| | To reduce the dose associated with this examination and the proposed VT-2 examination of the Reactor Vessel Seal Leakoff Monitoring lines, TVA shall perform both examinations simultaneously utilizing the same personnelfor both tasks while making a single entry inside the Biological Shield (Bioshield) |
| | Wallto employ ALARA considerations in reducing dose to station personnel. |
| | ln order to comply with the requirements of ASME Code Case N-805, these examinations will be scheduled for performance during the core off-load period with the Reactor Cavity flooded to the normal refueling level. This level will provide the static head as described in the response to RAI Question 5 on the WBN Relief Request submittal (Reference 3 from the cover letter). Both the Reactor HL nozzle safe end and Reactor Vessel Flange Leakoff Line examinations will be performed to detect evidence of past leakage (boric acid residue, staining, or any other indications of past leakage)Additional Confiouration Details: The inner and outer O-ring monitoring tube taps in the reactor vesselflange are located at elevation 723'-6 5/8'. As shown on Attachment 1, the approximate location of the inner O-ring monitoring tube is on the 253 degree azimuth and the approximate location of the outer O-ring monitoring tube is on the 286 degree azimuth. As shown on Attachment 2, the inner O-ring monitoring tube is located radially between the inner O-ring and outer O-ring. The outer O-ring monitoring tube is located radially outboard of the outer O-ring. The tubing for each monitoring tube travels radially around the outside of the vessel to a sleeve in the Bioshield wall at the 338 degree azimuth, then travels approximately 10 feet through the Bioshield wall. The inner and outer monitoring tubing travel through lower containment to a sleeve in the crane wall at the 296 degree azimuth. The inner and outer tubing connect to a common header to the Reactor Coolant Drain Tank downstream of their respective manual isolation valves.Attachment 1: Reactor Vessel Flange Attachment 2: Flange Detail E'}c OT l-o?-c o=Eg J'a otr CD c L-o=c o=bP--Lrl- d t- l--t (u OD trl GI-a tLI J ol ol ttl ol:t ol UI CJI G[u a |
| | -a.-l cr!{J!oi oi o!ol trI GI-l LI CD c a-L o ,=c o=L-o-=CD E a-L-o y a-c o=L-(D C s tr,-t-.E A6\r, ?b EE_E6}} |
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MONTHYEARML14013A3022014-01-10010 January 2014 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Section XI Code of Record for Second 10-Year Lnservice Interval 2001 Edition Project stage: Request ML14017A0972014-01-17017 January 2014 Accepted for Review of Watts Bar Nuclear Plant, Unit 1, Request for an Alternative System Leakage Test (Rfa) ISPT-02, TAC MF3354 Project stage: Approval ML14042A3212014-02-11011 February 2014 E-mail - Request for Additional Information Related to Request for Alternative Number ISPT-02 Regarding System Leakage Test of Reactor Pressure Vessel Head Flange Seal Leak-off Piping Project stage: RAI ML14055A2712014-02-21021 February 2014 Response to Request for Additional Information Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel(B&Pv) Section Xl Code of Record for Second 10-Year Inservice Interval 2001 Edition Project stage: Response to RAI ML14073A6002014-03-13013 March 2014 Response to Request for Clarifying Lnformation Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Section Xl Code of Record for Second 10-Year Lnservice Lnterval 2001 Edition Project stage: Request ML14079A4772014-03-27027 March 2014 Request for Alternate ISPT-02 Regarding System Leakage Test of Reactor Pressure Vessel Head Flange Seal Leak-Off Piping Project stage: Other 2014-02-11
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Category:Letter
MONTHYEARCNL-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) 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-24-010, 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 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-24-007, 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 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 ML24009A1712024-02-16016 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) - Letter ML24019A0722024-02-14014 February 2024 Request for Withholding Information from Public Disclosure IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation 2024-09-05
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 March 13, 2014 10 CFR 50.55a ATTN. Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C . 20555-0001
Subject:
Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 Response to Request for Clarifying lnformation Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 1O-Year lnservice lnterva!2001 Edition
References:
- 1. Letter from TVA to NRC, "American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 10 Year lnservice lnterval 2001 Edition," dated January 10, 2014 Electronic Mail from NRC to TVA, "Watts Bar Nuclear Station, Unit 1 -Request for Additional lnformation Related Request for Alternative Number ISPT-O2, Regarding System Leakage Test of Reactor Pressure Vessel Head Flange Seal Leak-Off Piping," dated February 11,2014 Letter from TVA to NRC, "Response to Request for Additional lnformation Regarding American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Section Xl Code of Record for Second 10-Year lnservice lnterval 2001 Edition," dated February 21,2014 By letter dated January 10,2014 (Reference 1), the Tennessee Valley Authority (TVA)submitted a request for alternative regarding system leakage test of reactor pressure vessel head flange seal leak-off piping. By Electronic Mail from NRC to TVA dated February 11,2014 (Reference 2), TVA received a Request for Additional lnformation (RAl) regarding the proposed request for alternative.
TVA provided its response to the Reference 2 RAI in the Reference 3 letter on February 21,2014. ln a teleconference on February 26,2014, the NRC requested additional clarification regarding the proposed alternative visual inspection provided in Reference 1 and additional details regarding the configuration of the reactor vessel flange provided in Reference 3.2 U.S. Nuclear Regulatory Commission Page 2 March 13,2014 The enclosure to this letter provides the requested clarifying information.
Please address any questions regarding this request to Gordon Arent at (423) 365-2004.Site Vice President Watts Bar Nuclear Plant
Enclosure:
Response to NRC Request for Clarifying lnformation cc (Enclosure):
NRC RegionalAdministrator - Region ll NRC Resident lnspector - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT UNIT {Response to NRC Request for Clarifying lnformation Additional lnsoection Details: The lnservice lnspection Program Augmented Examinations of the Reactor Vessel Hot Leg (HL)nozzle safe ends are performed with qualified personnelfrom the TVA lnspection Services Organization (lSO). These examinations are an enhanced visualexam (VE) that requires a W-2 qualified individual.
To reduce the dose associated with this examination and the proposed VT-2 examination of the Reactor Vessel Seal Leakoff Monitoring lines, TVA shall perform both examinations simultaneously utilizing the same personnelfor both tasks while making a single entry inside the Biological Shield (Bioshield)
Wallto employ ALARA considerations in reducing dose to station personnel.
ln order to comply with the requirements of ASME Code Case N-805, these examinations will be scheduled for performance during the core off-load period with the Reactor Cavity flooded to the normal refueling level. This level will provide the static head as described in the response to RAI Question 5 on the WBN Relief Request submittal (Reference 3 from the cover letter). Both the Reactor HL nozzle safe end and Reactor Vessel Flange Leakoff Line examinations will be performed to detect evidence of past leakage (boric acid residue, staining, or any other indications of past leakage)Additional Confiouration Details: The inner and outer O-ring monitoring tube taps in the reactor vesselflange are located at elevation 723'-6 5/8'. As shown on Attachment 1, the approximate location of the inner O-ring monitoring tube is on the 253 degree azimuth and the approximate location of the outer O-ring monitoring tube is on the 286 degree azimuth. As shown on Attachment 2, the inner O-ring monitoring tube is located radially between the inner O-ring and outer O-ring. The outer O-ring monitoring tube is located radially outboard of the outer O-ring. The tubing for each monitoring tube travels radially around the outside of the vessel to a sleeve in the Bioshield wall at the 338 degree azimuth, then travels approximately 10 feet through the Bioshield wall. The inner and outer monitoring tubing travel through lower containment to a sleeve in the crane wall at the 296 degree azimuth. The inner and outer tubing connect to a common header to the Reactor Coolant Drain Tank downstream of their respective manual isolation valves.Attachment 1: Reactor Vessel Flange Attachment 2: Flange Detail E'}c OT l-o?-c o=Eg J'a otr CD c L-o=c o=bP--Lrl- d t- l--t (u OD trl GI-a tLI J ol ol ttl ol:t ol UI CJI G[u a
-a.-l cr!{J!oi oi o!ol trI GI-l LI CD c a-L o ,=c o=L-o-=CD E a-L-o y a-c o=L-(D C s tr,-t-.E A6\r, ?b EE_E6