|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 5, 2010 MEMORANDUM Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation/ . (, Jason C. Paige, Project Manager c\! Plant Licensing Branch 11-2 Division of Operating Reactor Lice ing Office of Nuclear Reactor Regulation SUB..TURKEY POINT UNIT 3 -VERBAL AUTHORIZATION OF RELIEF REQUEST NO.9, VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR (TAC NO. ME4946) By letter dated October 27, 2010, Florida Power & Light (FPL), the licensee for Turkey Point, Unit 3, submitted Relief Request No.9, Visual Examination of Containment Liner Repair. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), FPL requested Nuclear Regulatory Commission (NRC) approval of an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test. The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3. The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 5, 2010 MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation/ . |
| After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test. The NRC staff reviewed the licensee's submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on October 29, 2010, the NRC staff granted a verbal authorization on the use of Relief Request NO.9 in accordance with 10 CFR 5.55a(a)(3)(i). | | FROM: Jason C. Paige, Project Manager Plant Licensing Branch 11-2 c\~ |
| The script for the verbal authorization is enclosed. | | (, |
| D. Broaddus -2 NRC Participants: | | ! - |
| Licensee Participants: | | Division of Operating Reactor Lice ing Office of Nuclear Reactor Regulation SUB..IECT: TURKEY POINT UNIT 3 - VERBAL AUTHORIZATION OF RELIEF REQUEST NO.9, VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR (TAC NO. ME4946) |
| D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250 | | By letter dated October 27, 2010, Florida Power & Light (FPL), the licensee for Turkey Point, Unit 3, submitted Relief Request No.9, Visual Examination of Containment Liner Repair. |
| | Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), FPL requested Nuclear Regulatory Commission (NRC) approval of an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test. |
| | The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3. |
| | The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221. |
| | After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test. |
| | The NRC staff reviewed the licensee's submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on October 29, 2010, the NRC staff granted a verbal authorization on the use of Relief Request NO.9 in accordance with 10 CFR 5.55a(a)(3)(i). The script for the verbal authorization is enclosed. |
| | |
| | D. Broaddus -2 NRC Participants: Licensee Participants: |
| | D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| | Verbal Authorization Script |
| | |
| | VERBAL AUTHORIZATION FOR RELIEF REQUEST NO.9 VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR TURKEY POINT NUCLEAR PLANT UNIT 3 By letter dated October 27, 2010 and in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), Florida Power and Light Company (FPL, the licensee) submitted Relief Request No.9 for NRC review and approval as an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test. The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3. |
| | The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221. |
| | After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test. |
| | On October 27, 2010, the NRC staff held a teleconference with the licensee to obtain clarification on the technical basis of the proposed relief request. The NRC staff determined during this call that a relief request was needed and when preparing the Turkey Point relief request to follow the precedent set by the Beaver Valley application dated April 28, 2009. |
| | On the basis of the NRC staff evaluation, pursuant to 10 CFR 50.55a (a)(3)(i), the NRC verbally authorizes the use of Relief Request No.9 for the repair of the degraded containment liner plate as of October 29, 2010. The relief is granted on the basis that a VT-1 visual examination prior to the local leak rate testing provides assurance that the affected area has been properly prepared for the testing and no abnormalities exist in the affected area and a post leak rate test VT-1 visual examination provides assurance that the tested area is free of abnormalities that may be exposed by the local leak rate test. Relief Request No.9 is authorized in support of containment liner repairs made during the current 2010 Turkey Point, Unit 3 maintenance and refueling outage. |
| | According to 10 CFR 50.55a (a)(3)(i), the Commission may authorize a licensee-proposed alternative if the staff determines that the alternative provides an acceptable level of quality and safety. |
| | Enclosure |
| | |
| | -2 This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request NO.9 while preparing the subsequent written safety evaluation. The written safety evaluation should be issued within 150 days in accordance with the Office of Nuclear Reactor Regulation standards. This verbal authorization summary will be publicly available in ADAMS in the next few days. |
| | All other ASME Code, Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
|
| |
|
| Verbal Authorization Script VERBAL AUTHORIZATION FOR RELIEF REQUEST NO.9 VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR TURKEY POINT NUCLEAR PLANT UNIT 3 By letter dated October 27, 2010 and in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), Florida Power and Light Company (FPL, the licensee) submitted Relief Request No.9 for NRC review and approval as an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test. The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3. The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221.
| | Novmber 5, 2010 D. Broaddus -2 NRC Participants: Licensee Participants: |
| After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test. On October 27, 2010, the NRC staff held a teleconference with the licensee to obtain clarification on the technical basis of the proposed relief request. The NRC staff determined during this call that a relief request was needed and when preparing the Turkey Point relief request to follow the precedent set by the Beaver Valley application dated April 28, 2009. On the basis of the NRC staff evaluation, pursuant to 10 CFR 50.55a (a)(3)(i), the NRC verbally authorizes the use of Relief Request No.9 for the repair of the degraded containment liner plate as of October 29, 2010. The relief is granted on the basis that a VT-1 visual examination prior to the local leak rate testing provides assurance that the affected area has been properly prepared for the testing and no abnormalities exist in the affected area and a post leak rate test VT-1 visual examination provides assurance that the tested area is free of abnormalities that may be exposed by the local leak rate test. Relief Request No.9 is authorized in support of containment liner repairs made during the current 2010 Turkey Point, Unit 3 maintenance and refueling outage. According to 10 CFR 50.55a (a)(3)(i), the Commission may authorize a licensee-proposed alternative if the staff determines that the alternative provides an acceptable level of quality and safety. Enclosure
| | D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250 |
| -2 This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request NO.9 while preparing the subsequent written safety evaluation.
| |
| The written safety evaluation should be issued within 150 days in accordance with the Office of Nuclear Reactor Regulation standards.
| |
| This verbal authorization summary will be publicly available in ADAMS in the next few days. All other ASME Code, Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
| |
| Novmber 5, 2010 D. Broaddus -2 NRC Participants: | |
| Licensee Participants: | |
| D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250 | |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
|
| |
| Verbal Authorization Script DISTRIBUTION: | | Verbal Authorization Script DISTRIBUTION: |
| PUBLIC LPL2-2 R/F RidsNrrPMTurkey Point RidsNrrDorlLpl2-2 RidsNrrDeEmcb RidsRgn2MailCenter GThomas, NRR RidsNrrLABClayton ADAMS Accession No 'ML103050225" OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME ...IPaige BClayton DBroaddus(CGratton for) DATE 11/2/10 11/2/10 11/05/2010 OFFICIAL RECORD COpy}} | | PUBLIC LPL2-2 R/F RidsNrrPMTurkey Point RidsNrrDorlLpl2-2 RidsNrrDeEmcb RidsRgn2MailCenter GThomas, NRR RidsNrrLABClayton ADAMS Accession No " 'ML103050225 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME ...IPaige BClayton DBroaddus(CGratton for) |
| | DATE 11/2/10 11/2/10 11/05/2010 OFFICIAL RECORD COpy}} |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML22123A1922022-05-10010 May 2022
Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds
ML22069A7112022-03-16016 March 2022
Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping
ML21302A0902021-10-29029 October 2021
Verbal Authorization by the Office Nuclear Regulation Relief Request No. 10 Use of ASME Code Case N-513-4 for Extended Period Not to Exceed Six Months
L-2021-107, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure2021-05-13013 May 2021
Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure
ML20308A7472020-12-0707 December 2020
Withdrawal of Request for Relief Concerning Train a and B Component Cooling Water Supply and Return Piping
ML20287A5512020-11-0606 November 2020
Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping
ML18106B1212018-04-25025 April 2018
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
ML17213A8632017-08-29029 August 2017
Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation
L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-07-24024 July 2017
Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
ML17122A1402017-05-10010 May 2017
Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval
ML17082A5102017-04-0606 April 2017
Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval
L-2017-050, Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 52017-03-22022 March 2017
Fifth Ten-Year Lnservice Inspection Interval Relief Request No. 5
ML16330A1182016-12-15015 December 2016
NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201)
ML16293A7782016-10-26026 October 2016
Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278)
ML16047A1182016-03-0909 March 2016
Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387)
ML15352A1622015-12-23023 December 2015
Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations
ML15328A2402015-12-11011 December 2015
Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations
ML13329A1202014-01-14014 January 2014
SE for RR No. 11 for 4th 10-Year Inservice Inspection Interval - Alternative Through-Wall Sizing Requirements for Implementation of ASME Code, Section XI, Appendix V111, Supplement 10 (TAC Nos. MF1391-92)
L-2012-381, Fourth Ten-Year Interval, Relief Request No. 102012-11-13013 November 2012
Fourth Ten-Year Interval, Relief Request No. 10
L-2012-193, Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.72012-06-0505 June 2012
Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.7
ML1030502252010-11-0505 November 2010
Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair
ML0533903272005-12-0606 December 2005
Relief Request, Safety Evaluation for Temporary Non-Code Repair of Spent Fuel Pool Cooling Line
ML0520901822005-08-15015 August 2005
Relief, Regarding Mechanical Clamping Device on Pressure Boundary Piping
ML0503503632005-03-0303 March 2005
Relief Request 1, Authorization of ISI Interval
ML0428204702004-10-0606 October 2004
Safety Evaluation for Relief Requests PR-01 and PR-04
L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds2004-07-22022 July 2004
ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds
ML0416100682004-06-0404 June 2004
Correction Ltr, RAI Regarding Fourth Interval Inservice Test Relief Requests
ML0330404922003-10-31031 October 2003
Relaxation of the Requirements of Order (EA-03-009) Regarding Reactor Pressure Vessel Head Inspections
ML0306203852003-04-25025 April 2003
Relief, Associated with Reactor Vessel Closure Head Repair
L-2003-063, ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 102003-03-10010 March 2003
ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 10
L-2002-085, Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 252002-05-0606 May 2002
Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 25
L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-4242002-03-0101 March 2002
Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424
2022-05-10
[Table view]
Category:Memoranda
MONTHYEARML23166A0042023-06-15015 June 2023
Summary of Meeting Concerning 2023 Annual Assessment of the Saint Lucie and the Turkey Point Nuclear Plants
ML22276A2302022-10-0606 October 2022
Summary of September 13, 2022, Public Meeting with FPL Concerning Supplemental Information Needed for Acceptance of License Amendment Request to Replace Instrumentation with Digital Systems on Turkey Point, Units 3 and 4
ML22238A3142022-08-0707 August 2022
Documentation of Approval for Longer Review Period for Turkey Point Digital Instrumentation and Control License Amendment Requests Acceptance Review
ML22145A3932022-05-25025 May 2022
Public Meeting Summary 2021 Annual Assessment Meeting 20220434
ML22034A3932022-02-16016 February 2022
Calendar Year 2021 Security Baseline Completion Memo
ML21159A1352021-06-0808 June 2021
Public Meeting Summary Regarding the Saint Lucie Nuclear Plant, Units 1 and 2, Docket No. 50-335 and 389, and the Turkey Point Nuclear Generating Station Units 3 and 4, Docket No. 50-250 and 50-251; Meeting Number 20210505
ML20315A2642020-12-14014 December 2020
November 5, 2020, Summary of Drop-In Meeting with Nextera-Florida Power and Light to Discuss Pending Submittals Related to Digital Instrumentation and Controls and Improved Standard Technical Specifications
ML20150A4732020-05-29029 May 2020
EOC Meeting Summary
ML19330G0542019-11-22022 November 2019
Reconciliation - Analysis of EDO Response to ACRS Ltr - Response to ACRS Report on the Safety Aspects of the SLR Application of the Turkey Point Nuclear Generating Units 3 & 4 - December 2019 Fc Meeting
ML19121A6072019-05-0101 May 2019
Summary of Public Meeting with Turkey Point Nuclear Plant to Discuss Annual Assessment of the Turkey Point Nuclear Plant with Public for Period of January 1, 2018 - December 31, 2018
ML18360A4452018-12-26026 December 2018
06/18/18 Summary of Interagency Meeting Related to Subsequent License Renewal for Turkey Point Nuclear Generating Unit Nos. 3 and 4
ML18221A2652018-08-0909 August 2018
Referral Memorandum from the Secretary to the Atomic Safety and Licensing Board Panel
ML18144A1242018-05-24024 May 2018
Summary of Public Meeting Concerning Annual Assessment of Turkey Point Nuclear Generating Station Unit 3 and Unit 4, for Period of January 1, 2017 December 31, 2017
ML18074A2522018-04-12012 April 2018
Status of Subsequent License Renewal Application
ML17082A5102017-04-0606 April 2017
Verbal Authorization of Relief Request No. 5 for Repair of High Head Safety Injection Recirculation Test Line - Fifth 10-Year Inservice Inspection Interval
ML18187A0332016-07-19019 July 2016
County Resolution to Seek a Commitment from FPL to Discontinue Use of the Cooling Canal System at the Turkey Point Power Plant
ML16097A1402016-04-0404 April 2016
March 30, 2016, Summary of Public Meeting Turkey Point Nuclear Plant
ML23333A0162016-03-0707 March 2016
Att H - MDC Report on Biscayne Bay Wq at Turkey Point CCS (March 4, 2016)-1
ML15222A5332015-08-10010 August 2015
Regulatory Audit in Support of Relief Request 1, Revised, for Fifth Ten-Year Inservice Inspection Interval
ML14156A2212014-06-0404 June 2014
Public Meeting Summary - Turkey Point Nuclear Generating Station Docket Nos. 50-250 and 50-251
ML12222A0392012-08-0909 August 2012
8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto
ML12213A0612012-08-0101 August 2012
8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol
ML1117101092011-06-22022 June 2011
Independent Spent Fuel Storage Installation Physical Security Plan and Verification of ASM Incorporation
ML11160A0482011-06-10010 June 2011
Notice of Forthcoming Meeting with Florida Power & Light, to Discuss Turkey Point Extended Power Uprate License Amendment Request Currently Under Review
ML1107405982011-03-16016 March 2011
Notice of Forthcoming Meeting with Florida Power & Light, Turkey Point, Units 3 & 4, to Discuss Extended Power Uprate License Amendment Request That Is Currently Under Review
ML1106104272011-03-0707 March 2011
Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold
ML1100704852011-02-0404 February 2011
Close-out of National Fire Protection Association Frequently Asked 07-0030 on Establishing Recovery Actions
ML1031205002010-11-10010 November 2010
Notice of Forthcoming Teleconference with Florida Power & Light to Discuss Differences Between the Turkey Point Spent Fuel Pool Criticality Analysis License Amendment Request Currently Under Review & Draft Division of Safety Systems Interim
ML1030502252010-11-0505 November 2010
Verbal Authorization of Relief Request No. 9, Visual Examination of Containment Liner Repair
ML1030100892010-11-0505 November 2010
Verbal Authorization of Relief Request No. 8, Transfer Canal Drain Line Piping Repairs
ML1025601362010-09-0707 September 2010
Notice of Meeting with Florida Power & Light Company to Discuss the Florida Power & Light Company'S Forthcoming Applications for the Extended Power Uprates of St. Lucie Units 1 & 2 and Turkey Point Units 3 & 4, Focusing on the Topic of Spen
ML1019405202010-07-14014 July 2010
Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02
ML1018806202010-07-0808 July 2010
Notice of Forthcoming Meeting with Florida Power & Light, to Discuss with Representatives of Florida Power & Light Company (FPL) the Turkey Point, Units 3 and 4 Proposed Extended Power Uprate License Amendment Request
ML1016704282010-06-17017 June 2010
Meeting Summary Notice
ML1014501902010-05-26026 May 2010
Notice of Meeting with Florida Power & Light to Discuss the Turkey Point Alternative Source Term License Amendment Request That Is Currently Under Review
ML1009105332010-04-0505 April 2010
U.S. Nuclear Regulatory Commission Staff Review of the Department of Homeland Security Consultation Reports
ML1001900112010-01-19019 January 2010
Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response
ML1000800922010-01-0808 January 2010
Notice of Meeting with Florida Power & Light - Turkey Point Units 3 and 4, to Discuss Proposed License Amendment Request to Update Turkey Point Unit 3 Spent Fuel Pool Licensing Basis
ML0934911442009-12-16016 December 2009
Summary of Category 2 Public Meeting with Nuclear Energy Institute to Discuss Health Physics Issues for New Reactors
ML0925404602009-09-10010 September 2009
Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ
ML0921805182009-08-0606 August 2009
Notice of Public Meeting with Florida Power & Light Energy
IR 05000250/20090032009-07-30030 July 2009
IR 05000250-09-003, 05000251-09-003, on 04/01/2009 - 06/30/2009; Turkey Point Nuclear Power Plant, Units 3 and 4; Equipment Alignment, Fire Protection, Maintenance Effectiveness, Plant Modifications, Refueling and Other Outage Activities
ML0910302212009-04-13013 April 2009
Meeting Notice, Meeting with Florida Power & Light Company Turkey Point Nuclear Plant, Units 3 and 4
ML0832502332008-12-0202 December 2008
Summary of Public Meeting with Operators of Vogtle Units 1 & 2, San Onofre Units 2 & 3, St. Lucie Unit 1, Turkey Point Unit 3, Indian Point Units 2 & 3, Nuclear Energy Institute, and Alion Science and Technology
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0706400412007-03-0606 March 2007
Commitment Lists for Renewed Operating License (ROL) Plants with No Commitment Appendix Attached to Its ROL Sers/Nuregs for Use with IP-71003
ML0617805592006-07-10010 July 2006
Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0614505922006-05-26026 May 2006
Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report
ML0518904892005-07-14014 July 2005
Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0506300702005-03-0202 March 2005
January Monthly Report on the Status of Open TIAs Assigned to NRR
2023-06-15
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 5, 2010 MEMORANDUM TO: Douglas A. Broaddus, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation/ .
FROM: Jason C. Paige, Project Manager Plant Licensing Branch 11-2 c\~
(,
! -
Division of Operating Reactor Lice ing Office of Nuclear Reactor Regulation SUB..IECT: TURKEY POINT UNIT 3 - VERBAL AUTHORIZATION OF RELIEF REQUEST NO.9, VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR (TAC NO. ME4946)
By letter dated October 27, 2010, Florida Power & Light (FPL), the licensee for Turkey Point, Unit 3, submitted Relief Request No.9, Visual Examination of Containment Liner Repair.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), FPL requested Nuclear Regulatory Commission (NRC) approval of an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test.
The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3.
The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221.
After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test.
The NRC staff reviewed the licensee's submittal and determined that the proposed alternative will provide an acceptable level of quality and safety. During a conference call with the licensee on October 29, 2010, the NRC staff granted a verbal authorization on the use of Relief Request NO.9 in accordance with 10 CFR 5.55a(a)(3)(i). The script for the verbal authorization is enclosed.
D. Broaddus -2 NRC Participants: Licensee Participants:
D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250
Enclosure:
Verbal Authorization Script
VERBAL AUTHORIZATION FOR RELIEF REQUEST NO.9 VISUAL EXAMINATION OF CONTAINMENT LINER REPAIR TURKEY POINT NUCLEAR PLANT UNIT 3 By letter dated October 27, 2010 and in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i), Florida Power and Light Company (FPL, the licensee) submitted Relief Request No.9 for NRC review and approval as an alternative to the requirement in the 2001 Edition with 2003 Addenda (current code-of-record) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, sub-article IWE-5240, to perform a detailed visual examination of the repaired area during the post-repair pressure test. The relief request is related to the repair of the containment liner plate in the sump area due to significant corrosion in a localized region of the vertical wall section, immediately adjacent to the concrete floor at Turkey Point, Unit 3.
The licensee plans to repair the degraded area by removing the corroded liner plate and welding a replacement plate. As required by sub-article IWE-5221, following the repairs, FPL is to complete a pneumatic leakage test. However, the local leak rate test requires the use of a test device that will make the areas affected by the repair activities inaccessible during the local leak rate test. The licensee requested relief from the direct visual examination requirement specified in sub-article IWE-5240 during the leakage test required by sub-article IWE-5221.
After completing the welding of the liner plate and the required nondestructive examination of the repair welds, the licensee proposed to perform a VT-1 visual examination of the affected area, both prior to and following the local leak rate test.
On October 27, 2010, the NRC staff held a teleconference with the licensee to obtain clarification on the technical basis of the proposed relief request. The NRC staff determined during this call that a relief request was needed and when preparing the Turkey Point relief request to follow the precedent set by the Beaver Valley application dated April 28, 2009.
On the basis of the NRC staff evaluation, pursuant to 10 CFR 50.55a (a)(3)(i), the NRC verbally authorizes the use of Relief Request No.9 for the repair of the degraded containment liner plate as of October 29, 2010. The relief is granted on the basis that a VT-1 visual examination prior to the local leak rate testing provides assurance that the affected area has been properly prepared for the testing and no abnormalities exist in the affected area and a post leak rate test VT-1 visual examination provides assurance that the tested area is free of abnormalities that may be exposed by the local leak rate test. Relief Request No.9 is authorized in support of containment liner repairs made during the current 2010 Turkey Point, Unit 3 maintenance and refueling outage.
According to 10 CFR 50.55a (a)(3)(i), the Commission may authorize a licensee-proposed alternative if the staff determines that the alternative provides an acceptable level of quality and safety.
Enclosure
-2 This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request NO.9 while preparing the subsequent written safety evaluation. The written safety evaluation should be issued within 150 days in accordance with the Office of Nuclear Reactor Regulation standards. This verbal authorization summary will be publicly available in ADAMS in the next few days.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Novmber 5, 2010 D. Broaddus -2 NRC Participants: Licensee Participants:
D. Broaddus B. Tomonto M. Khanna R. Gill G. Thomas O. Hanek J. Paige Docket No. 50-250
Enclosure:
Verbal Authorization Script DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrPMTurkey Point RidsNrrDorlLpl2-2 RidsNrrDeEmcb RidsRgn2MailCenter GThomas, NRR RidsNrrLABClayton ADAMS Accession No " 'ML103050225 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME ...IPaige BClayton DBroaddus(CGratton for)
DATE 11/2/10 11/2/10 11/05/2010 OFFICIAL RECORD COpy
