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| {{#Wiki_filter:}} | | {{#Wiki_filter:ADAMS Accession No. ML110950640 |
| | |
| | From: Lingam, Siva Sent: Tuesday, April 05, 2011 12:10 PM To: 'Cook, Rodney Michael' Cc: Broaddus, Doug; Karwoski, Kenneth; Johnson, Andrew; Franke, Mark; Obodoako, Aloysius |
| | |
| | ==Subject:== |
| | Sequoyah 2 - Spring 2011 Steam Generator RFO Call (TAC No. ME5977) |
| | Inservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. As discussed with you and agreed by you this morning, a telephone conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Sequoyah Nuclear Generating Station Unit 2 spring 2011 refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Please note the following list of discussion points during this call. |
| | : 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle. |
| | : 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results. |
| | : 3. Discuss any exceptions taken to the industry guidelines. |
| | : 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria. |
| | : 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g., |
| | number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit). |
| | : 6. Describe repair/plugging plans. |
| | : 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available). |
| | : 8. Discuss the following regarding loose parts: |
| | $ what inspections are performed to detect loose parts |
| | |
| | $ a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known) |
| | $ if the loose parts were removed from the SG |
| | $ indications of tube damage associated with the loose parts |
| | : 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc). |
| | : 10. Discuss any unexpected or unusual results. |
| | : 11. Provide the schedule for steam generator-related activities during the remainder of the current outage. |
| | The NRC staff will document a summary of the conference call, including any material that you provide to the NRC staff in support of the call. |
| | |
| | Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2) |
| | Sequoyah Nuclear Plant Location: O8-D5; Mail Stop: O8-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov}} |
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MONTHYEARML1109506402011-04-0505 April 2011 Memorandum Regarding Sequoyah, Unit 2 - Spring 2011 RFO Steam Generator RFO Conference Call Project stage: Other ML11208C2162011-08-16016 August 2011 Spring 2011 Refueling Outage Steam Generator Tube Inservice Inspection Conference Call Summary Project stage: Other 2011-04-05
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Category:E-Mail
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23165A2862023-06-14014 June 2023 Tennessee Multi-Sector Permit (Tmsp), 2023 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, SW-17, SW-18, SW-19, and SW-21 ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23046A3552023-02-15015 February 2023 Annual Water Withdrawal Report 2022 ML23019A3442023-01-19019 January 2023 Tennessee Multi-Sector Permit (Tmsp), 2022 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, and SW-19 ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22348A0432022-11-28028 November 2022 NRR E-mail Capture - State Consultation - Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Modify the Approved 10 CFR 50.69 Categorization Process (L-2022-LLA-0033) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22196A0732022-07-15015 July 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - TSTF-505 RICT (L-2021-LLA-0145) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A0332022-06-17017 June 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - Reactor Trip System Instrumentation (L-2021-LLA-0200) ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22137A2692022-05-17017 May 2022 Notice of Termination, TNR192066, Gravel Lot Restoration Project ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22132A1762022-05-12012 May 2022 Tennessee Multi-Sector Permit (Tmsp), 2021 Annual Discharge Monitoring Report for Outfalls SW-2, SW-3, SW-4, SW-6, SW-8, SW-9, and SW-13 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 ML22095A0182022-04-0404 April 2022 NRR E-mail Capture - Sequoyah Nuclear Plant - Acceptance of Request for Alternative - Pressure Isolation Valve Leakage ISTC-3630 (L-2022-LLR-0034) ML22125A1422022-03-22022 March 2022 1 and 2 - March 22, 2022 e-mail - Sequoyah TSTF-505 LAR Supplemental Information ML22075A0942022-03-16016 March 2022 NRR E-mail Capture - Acceptance Review for Sequoyah Units 1 and 2 - LAR to Use of Fire and Seismic PRAs to Modify Approved 10 CFR 50.69 Categorization Process ML22046A2742022-02-15015 February 2022 NRR E-mail Capture - Audit Question (Snsb 02) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML22047A0552022-02-15015 February 2022 Annual Water Withdrawal Report 2021 ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22035A0182022-02-0303 February 2022 NRR E-mail Capture - Audit Questions (Eeb follow-up) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21347A9022021-12-13013 December 2021 Discharge Monitoring Report (DMR) Quality Assurance Study 41 Follow-up Report 2021 ML21336A3942021-12-0101 December 2021 NRR E-mail Capture - Audit Questions for Sequoyah Units 1 and 2 - LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML21323A0432021-11-18018 November 2021 NRR E-mail Capture - Acceptance Review for Sequoyah Units 1 and 2 - LAR to Eliminate the High Negative Flux Rate Trip Requirement ML21252A2152021-09-0909 September 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Unit 2 - Acceptance of Request for Alternative Inspection for Upper Head Injection J-groove Welds (L-2021-LLR-0059) ML21239A0712021-08-27027 August 2021 Acceptance of License Amendment Request to Adopt TSTF-505, Revision 2 ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 2024-01-31
[Table view] |
Text
ADAMS Accession No. ML110950640
From: Lingam, Siva Sent: Tuesday, April 05, 2011 12:10 PM To: 'Cook, Rodney Michael' Cc: Broaddus, Doug; Karwoski, Kenneth; Johnson, Andrew; Franke, Mark; Obodoako, Aloysius
Subject:
Sequoyah 2 - Spring 2011 Steam Generator RFO Call (TAC No. ME5977)
Inservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. As discussed with you and agreed by you this morning, a telephone conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Sequoyah Nuclear Generating Station Unit 2 spring 2011 refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Please note the following list of discussion points during this call.
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
- 3. Discuss any exceptions taken to the industry guidelines.
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g.,
number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
- 6. Describe repair/plugging plans.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
- 8. Discuss the following regarding loose parts:
$ what inspections are performed to detect loose parts
$ a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known)
$ if the loose parts were removed from the SG
$ indications of tube damage associated with the loose parts
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc).
- 10. Discuss any unexpected or unusual results.
- 11. Provide the schedule for steam generator-related activities during the remainder of the current outage.
The NRC staff will document a summary of the conference call, including any material that you provide to the NRC staff in support of the call.
Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2)
Sequoyah Nuclear Plant Location: O8-D5; Mail Stop: O8-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov