|
|
| (2 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 12/07/2017 | | | issue date = 12/07/2017 |
| | title = TVA Presentation Slides - Watts Bar Nuclear Plant Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 3.6.3, Containment Isolation Valves, Surveillance Requirement 3.6.3.5 - December 7, 2017 | | | title = TVA Presentation Slides - Watts Bar Nuclear Plant Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 3.6.3, Containment Isolation Valves, Surveillance Requirement 3.6.3.5 - December 7, 2017 |
| | author name = Schaaf R G | | | author name = Schaaf R |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
| Line 9: |
Line 9: |
| | docket = 05000390, 05000391 | | | docket = 05000390, 05000391 |
| | license number = NPF-090, NPF-096 | | | license number = NPF-090, NPF-096 |
| | contact person = Schaaf R G | | | contact person = Schaaf R |
| | document type = Meeting Briefing Package/Handouts | | | document type = Meeting Briefing Package/Handouts |
| | page count = 13 | | | page count = 13 |
| | | project = |
| | | stage = Meeting |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Watts Bar Nuclear Plant Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 3.6.3, "Containment Isolation Valves," Surveillance Requirement 3.6.3.5 December 7, 2017 | | {{#Wiki_filter:Watts Bar Nuclear Plant Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 3.6.3, Containment Isolation Valves, Surveillance Requirement 3.6.3.5 December 7, 2017 |
|
| |
|
| Agenda *Opening Remarks and Purpose of the Proposed License Amendment Request (LAR) | | Agenda |
| *Proposed Surveillance Requirement (SR) 3.6.3.5 Changes
| | * Opening Remarks and Purpose of the Proposed License Amendment Request (LAR) |
| *Technical Analysis of the Proposed LAR
| | * Proposed Surveillance Requirement (SR) 3.6.3.5 Changes |
| *Regulatory Precedent
| | * Technical Analysis of the Proposed LAR |
| *Schedule for Submittal
| | * Regulatory Precedent |
| *Summary and Closing Remarks
| | * Schedule for Submittal |
| | * Summary and Closing Remarks l 2 |
|
| |
|
| l 2 Opening Remarks and Purpose of the Proposed LAR
| | Opening Remarks and Purpose of the Proposed LAR |
| *The proposed Technical Specification (TS) amendment revises the Watts Bar Nuclear Plant (WBN) Units 1 and 2 TS 3.6.3, "Containment Isolation Valves," SR 3.6.3.5 and associated Bases to change the frequency to "In accordance with the Containment Leakage Rate Testing Program
| | * The proposed Technical Specification (TS) amendment revises the Watts Bar Nuclear Plant (WBN) Units 1 and 2 TS 3.6.3, Containment Isolation Valves, SR 3.6.3.5 and associated Bases to change the frequency to In accordance with the Containment Leakage Rate Testing Program. |
| ." *The WBN Containment Leakage Rate Testing (CLRT) Program is described in TS 5.7.2.19, "Containment Leakage Rate Testing Program," and implemented in accordance with 10 CFR Part 50, Appendix J, Option B, and Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak
| | * The WBN Containment Leakage Rate Testing (CLRT) Program is described in TS 5.7.2.19, Containment Leakage Rate Testing Program, and implemented in accordance with 10 CFR Part 50, Appendix J, Option B, and Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program. |
| -Test Program." | | * RG 1.163 allows a nominal test interval of 30 months for containment purge and vent valves. |
| *RG 1.163 allows a nominal test interval of 30 months for containment purge and vent valves. | | l 3 |
| l 3 Proposed WBN 1 and WBN 2 SR 3.6.3.5 Changes l 4 l 5 Proposed WBN 1 SR 3.6.3.5 Bases Changes l 6 Proposed WBN 2 SR 3.6.3.5 Bases Changes Technical Analysis of the Proposed LAR | | |
| *Each WBN Unit 1 and 2 Containment Purge System contains ten containment penetrations (i.e., X
| | Proposed WBN 1 and WBN 2 SR 3.6.3.5 Changes l 4 |
| -4, X-5, X-6, X-7, X-9A, X-9B, X-10A, X-10B, X-11, and X-80). *Each penetration contains redundant containment isolation valves (total of 20 valves per unit). | | |
| *The valves are pneumatically-operated POSI-SEAL butterfly valves with resilient seals.
| | Proposed WBN 1 SR 3.6.3.5 Bases Changes l 5 |
| *During normal plant operations, these valves are normally closed except containment penetration X
| | |
| -80 (containment vent penetration), which is normally open. l 7 Technical Analysis of the Proposed LAR | | Proposed WBN 2 SR 3.6.3.5 Bases Changes l 6 |
| | |
| | Technical Analysis of the Proposed LAR |
| | * Each WBN Unit 1 and 2 Containment Purge System contains ten containment penetrations (i.e., X-4, X-5, X-6, X-7, X-9A, X-9B, X-10A, X-10B, X-11, and X-80). |
| | * Each penetration contains redundant containment isolation valves (total of 20 valves per unit). |
| | * The valves are pneumatically-operated POSI-SEAL butterfly valves with resilient seals. |
| | * During normal plant operations, these valves are normally closed except containment penetration X-80 (containment vent penetration), which is normally open. |
| | l 7 |
| | |
| | Technical Analysis of the Proposed LAR |
| | * Table 1 of the LAR provides a table of the last ten years of as-found leak rate history of the WBN Unit 1 Containment Purge System valves. |
| | * Table 2 of the LAR provides a similar table for the WBN Unit 2 Containment Purge System valves. |
| | - Two years of as-found leak rate history is provided due to the limited operating experience of WBN Unit 2. |
| | - The long term leakage performance of the WBN Unit 2 valves is expected to be similar to their WBN Unit 1 counterparts, because the valves are the same design including manufacturer and model number. |
| | l 8 |
|
| |
|
| l 8 *Table 1 of the LAR provides a table of the last ten years of as-found leak rate history of the WBN Unit 1 Containment Purge System valves. *Table 2 of the LAR provides a similar table for the WBN Unit 2 Containment Purge System valves. -Two years of as
| |
| -found leak rate history is provided due to the limited operating experience of WBN Unit 2. -The long term leakage performance of the WBN Unit 2 valves is expected to be similar to their WBN Unit 1 counterparts, because the valves are the same design including manufacturer and model number.
| |
| Technical Analysis of the Proposed LAR | | Technical Analysis of the Proposed LAR |
| | * The administrative limit for the Containment Purge System valve leakage rate is 12.32 standard cubic feet per hour (scfh). |
| | * Since the initial startup for Unit 1 (1996) and Unit 2 (2016), the administrative limit has never been exceeded. |
| | * The largest leakage rate over the past ten years for Unit 1 was 3.18 scfh for penetration X-7 on 10/17/2008. |
| | * The largest leak rate for Unit 2 was 8.84 scfh for penetration X-10A on 8/8/2016. |
| | * The as-found leak rate history of these valves supports extending the test interval beyond the current frequency of 184 days and within 92 days of any opening, to the NRC Regulatory Guide 1.163 recommended frequency of once every 30 months. |
| | l 9 |
|
| |
|
| l 9 *The administrative limit for the Containment Purge System valve leakage rate is 12.32 standard cubic feet per hour (scfh). *Since the initial startup for Unit 1 (1996) and Unit 2 (2016), the administrative limit has never been exceeded. *The largest leakage rate over the past ten years for Unit 1 was 3.18 scfh for penetration X
| |
| -7 on 10/17/2008. *The largest leak rate for Unit 2 was 8.84 scfh for penetration X
| |
| -10A on 8/8/2016.
| |
| *The as-found leak rate history of these valves supports extending the test interval beyond the current frequency of 184 days and within 92 days of any opening, to the NRC Regulatory Guide 1.163 recommended frequency of once every 30 months.
| |
| Regulatory Precedent | | Regulatory Precedent |
| *The proposed TS change is similar to those approved by NRC for the following nuclear power plants that also revised their SR frequency for the containment purge valves to be in accordance with the Containment Leakage Rate Testing Program:
| | * The proposed TS change is similar to those approved by NRC for the following nuclear power plants that also revised their SR frequency for the containment purge valves to be in accordance with the Containment Leakage Rate Testing Program: |
| -McGuire Nuclear Station, Units 1and 2 (ML022540102) | | - McGuire Nuclear Station, Units 1and 2 (ML022540102) |
| -Catawba Nuclear Station, Units 1 and 2 (ML051590203) -River Bend Station, Unit 1 (ML051590203) -Waterford Steam Electric Station, Unit 3 (ML071290447) l 10 Schedule for Submittal | | - Catawba Nuclear Station, Units 1 and 2 (ML051590203) |
| *12/7/17 - Pre-submittal teleconference with NRC
| | - River Bend Station, Unit 1 (ML051590203) |
| *1/31/18 - Submit LAR to NRC
| | - Waterford Steam Electric Station, Unit 3 (ML071290447) l 10 |
| *Request NRC approval by 1/31/19 with a 30
| |
| -day implementation dat e *March 2018 - Telecon or meeting to discuss any NRC questions (if needed)
| |
|
| |
|
| l 11 Closing Remarks
| | Schedule for Submittal |
| *Proposed LAR reflects the operating experience of the WBN Containment Purge System valves. *Proposed LAR w ill result in decreased radiological exposure to personnel and reduces the safety risk associated with performing this SR in the WBN Unit1 and Unit 2 Annulus. *Proposed LAR is consistent with industry precedence.
| | * 12/7/17 - Pre-submittal teleconference with NRC |
| | * 1/31/18 - Submit LAR to NRC |
| | * Request NRC approval by 1/31/19 with a 30-day implementation date |
| | * March 2018 - Telecon or meeting to discuss any NRC questions (if needed) l 11 |
|
| |
|
| l 12}} | | Closing Remarks |
| | * Proposed LAR reflects the operating experience of the WBN Containment Purge System valves. |
| | * Proposed LAR will result in decreased radiological exposure to personnel and reduces the safety risk associated with performing this SR in the WBN Unit1 and Unit 2 Annulus. |
| | * Proposed LAR is consistent with industry precedence. |
| | l 12}} |
|
|---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24312A0532024-11-0707 November 2024
FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0
ML24312A1432024-11-0707 November 2024
SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0
ML24284A0042024-10-16016 October 2024
Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides
ML24228A2312024-08-15015 August 2024
TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement
ML24225A2542024-08-14014 August 2024
August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating
ML24137A2872024-05-16016 May 2024
Pre-Submittal Meetingfor Proposed 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
ML24127A0412024-05-0606 May 2024
May 6, 2024 Meeting Slides
ML24067A2832024-03-27027 March 2024
2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides
ML24044A0872024-02-14014 February 2024
TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System
ML23291A1562023-10-18018 October 2023
NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides
ML23264A0412023-09-27027 September 2023
NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides
ML23251A1252023-09-12012 September 2023
Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1
ML23251A1212023-09-12012 September 2023
RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides
ML23178A0832023-07-10010 July 2023
Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs
ML23128A2882023-05-0808 May 2023
TVA Nuclear Plants -2022 EOC Media Slides
ML23052A0362023-02-22022 February 2023
February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides
ML23041A3562023-02-15015 February 2023
February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides)
ML23044A5182023-02-15015 February 2023
Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension
ML22318A1042022-11-14014 November 2022
Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation
ML22157A4132022-06-0606 June 2022
Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides
ML22102A3032022-04-12012 April 2022
Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation
ML22080A1662022-03-21021 March 2022
TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play
ML21343A0282021-12-14014 December 2021
TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule
ML21281A2282021-10-13013 October 2021
Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides)
ML21250A3652021-09-0808 September 2021
Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis
ML21229A1992021-08-19019 August 2021
Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides)
ML21217A2872021-08-19019 August 2021
TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board
ML21231A0972021-08-18018 August 2021
TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning
ML21117A0722021-04-27027 April 2021
Meeting Slides for April 28, 2021 Meeting with TVA
ML21096A1312021-04-0707 April 2021
Pre-submittal Meeting for Inservice Testing (IST) Program Request for One-Time Extension of Test Frequency of WBN Unit 1 Group 6 Relief Valves
ML21041A1552021-02-11011 February 2021
Meeting Slides for February 11, 2021 Meeting with TVA
ML20345A0262020-12-10010 December 2020
Replacement Steam Generator Project Planned License Amendment Request (Lars). LAR Descriptions and Submittal Schedule Meeting Slides
ML20329A3722020-11-24024 November 2020
Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 5.9.9, Steam Generator Tube Inspection Report, to Use Popcd Methodology
ML20302A1232020-10-28028 October 2020
Pre-Submittal Meeting Slides Non-Voluntary Application to Modify WBN Unit 1 and Unit 2 TS Surveillance Requirement 3.6.15.4, Shield Building
ML20239A8672020-08-27027 August 2020
Pre-Submittal Meeting Slides License Amendment Request for Technical Specification 5.7.2.19
ML20175A0552020-06-23023 June 2020
TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting
ML20125A3242020-05-0505 May 2020
Pre-Submittal Meeting Slides for License Amendment Request - Main Control Room Chiller Completion Time Extension
ML20049G1822020-02-18018 February 2020
February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel
ML20009C3962020-01-0808 January 2020
Pre-Submittal Telecon for Expedited License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation
ML19347B0722019-12-12012 December 2019
TVA and Xcel Energy Slides for Joint Presubmittal Meeting to License Amendment Requests to Adopt WCAP-17661, Revision 1
ML19282A0082019-10-0909 October 2019
TVA Slides for Pre-Submittal Meeting for License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values
ML19298A0042019-09-12012 September 2019
Presentation Slides for 9/12/19 Public Meeting
ML19255H5522019-09-12012 September 2019
August 27, 2019, Summary of Public Meeting - Tennessee Valley Safety Conscious Work Environment Update at Watts Bar, Docket 50-390 and 50-391
ML19252A0532019-09-0909 September 2019
TVA Presentation Slides: Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request Revised Offsite Electrical Power Sources
ML19235A2882019-08-23023 August 2019
2019 WBN SCWE Public Meeting Slides 8-27-2019 (NRC Slides)
ML19235A2712019-08-23023 August 2019
2019 TVA Watts Bar Nuclear Plant Public Meeting Slides 08-27-2019 (TVA Slides)
ML19178A2462019-07-0101 July 2019
Presentation Material for July 1, 2019 Pre-submittal Meeting with TVA on Full Spectrum LOCA Methodology for Watts Bar, Units 1 and 2
ML19161A2412019-06-11011 June 2019
Pre-Application Meeting for Proposed License Amendment Request (LAR) Regarding Change to the WBN Unit 2 Technical Specifications (TS) 3.4.17, Steam Generator Tube Integrity and 5.7.2.12 Steam Generator Program
ML19161A2392019-06-10010 June 2019
Plants Pre-Submittal Meeting for Proposed License Amendments Hydrological Analysis Updates June 10, 2019
ML19142A3602019-05-21021 May 2019
May 9, 2019 Summary of Public Meeting; Watts Bar Nuclear Plant
2024-08-15
[Table view] |
Text
Watts Bar Nuclear Plant Pre-Submittal Teleconference for Proposed License Amendment Request Regarding Technical Specification 3.6.3, Containment Isolation Valves, Surveillance Requirement 3.6.3.5 December 7, 2017
Agenda
- Opening Remarks and Purpose of the Proposed License Amendment Request (LAR)
- Technical Analysis of the Proposed LAR
- Summary and Closing Remarks l 2
Opening Remarks and Purpose of the Proposed LAR
- The proposed Technical Specification (TS) amendment revises the Watts Bar Nuclear Plant (WBN) Units 1 and 2 TS 3.6.3, Containment Isolation Valves, SR 3.6.3.5 and associated Bases to change the frequency to In accordance with the Containment Leakage Rate Testing Program.
- RG 1.163 allows a nominal test interval of 30 months for containment purge and vent valves.
l 3
Proposed WBN 1 and WBN 2 SR 3.6.3.5 Changes l 4
Proposed WBN 1 SR 3.6.3.5 Bases Changes l 5
Proposed WBN 2 SR 3.6.3.5 Bases Changes l 6
Technical Analysis of the Proposed LAR
- Each WBN Unit 1 and 2 Containment Purge System contains ten containment penetrations (i.e., X-4, X-5, X-6, X-7, X-9A, X-9B, X-10A, X-10B, X-11, and X-80).
- Each penetration contains redundant containment isolation valves (total of 20 valves per unit).
- The valves are pneumatically-operated POSI-SEAL butterfly valves with resilient seals.
- During normal plant operations, these valves are normally closed except containment penetration X-80 (containment vent penetration), which is normally open.
l 7
Technical Analysis of the Proposed LAR
- Table 1 of the LAR provides a table of the last ten years of as-found leak rate history of the WBN Unit 1 Containment Purge System valves.
- Table 2 of the LAR provides a similar table for the WBN Unit 2 Containment Purge System valves.
- Two years of as-found leak rate history is provided due to the limited operating experience of WBN Unit 2.
- The long term leakage performance of the WBN Unit 2 valves is expected to be similar to their WBN Unit 1 counterparts, because the valves are the same design including manufacturer and model number.
l 8
Technical Analysis of the Proposed LAR
- The administrative limit for the Containment Purge System valve leakage rate is 12.32 standard cubic feet per hour (scfh).
- Since the initial startup for Unit 1 (1996) and Unit 2 (2016), the administrative limit has never been exceeded.
- The largest leakage rate over the past ten years for Unit 1 was 3.18 scfh for penetration X-7 on 10/17/2008.
- The largest leak rate for Unit 2 was 8.84 scfh for penetration X-10A on 8/8/2016.
- The as-found leak rate history of these valves supports extending the test interval beyond the current frequency of 184 days and within 92 days of any opening, to the NRC Regulatory Guide 1.163 recommended frequency of once every 30 months.
l 9
Regulatory Precedent
- The proposed TS change is similar to those approved by NRC for the following nuclear power plants that also revised their SR frequency for the containment purge valves to be in accordance with the Containment Leakage Rate Testing Program:
- McGuire Nuclear Station, Units 1and 2 (ML022540102)
- Catawba Nuclear Station, Units 1 and 2 (ML051590203)
- River Bend Station, Unit 1 (ML051590203)
- Waterford Steam Electric Station, Unit 3 (ML071290447) l 10
Schedule for Submittal
- 1/31/18 - Submit LAR to NRC
- Request NRC approval by 1/31/19 with a 30-day implementation date
- March 2018 - Telecon or meeting to discuss any NRC questions (if needed) l 11
Closing Remarks
- Proposed LAR reflects the operating experience of the WBN Containment Purge System valves.
- Proposed LAR will result in decreased radiological exposure to personnel and reduces the safety risk associated with performing this SR in the WBN Unit1 and Unit 2 Annulus.
- Proposed LAR is consistent with industry precedence.
l 12
