Letter Sequence Response to RAI |
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Results
Other: L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System., L-08-189, Drawing Lr 2-27A-2, Rev. 4, Auxiliary Steam and Condensate System (Ass)., L-08-261, Schedule for Submittal of Annual Update for License Renewal Application, L-08-262, Drawing, Lr Drawing 2-31-1, Rev. 5, Demineralized Water System (Wtd)., L-08-263, Submittal of Revision to License Renewal Application Amendment No. 24, L-08-292, Lr Drawing 1-21-1, Rev. 7, Main Steam System (Ms)., L-08-316, License Renewal Application Amendment No. 26 (TAC Nos. MD6593 and MD6594), Revisions, L-08-393, License Renewal Application, Amendment No. 33, L-09-058, Comments on Safety Evaluation Report with Open Item Related to the License Renewal, L-09-138, License Renewal Application, Amendment No. 36, L-09-151, License Renewal Application Amendment No. 37, ML081000322, ML081000323, ML081000324, ML081000326, ML081000327, ML081000328, ML081000329, ML081000330, ML081000331, ML081000332, ML081640592, ML081640593, ML081640594, ML081640596, ML081640597, ML081640598, ML081640599, ML081640600, ML081640601, ML081640602, ML081640603, ML081640604, ML082550686, ML082550687, ML082550688, ML083010249, ML092740576, ML092920050, NRC-2009-0496, Beaver Valley Federal Register Notice - Record of Decision to Renew License
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MONTHYEARL-07-130, Submittal of Pressure and Temperature Limits Report, Revision 42007-09-19019 September 2007 Submittal of Pressure and Temperature Limits Report, Revision 4 Project stage: Request ML0805902622008-03-0303 March 2008 Request for Additional Information, License Renewal Application (TAC Nos. MD6593 and MD6594) Project stage: RAI ML0806402162008-03-0505 March 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 and 2, LRA Project stage: RAI ML0806010202008-03-0505 March 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI ML0807202882008-03-21021 March 2008 Request for Additional Information, Section B.2.35 Project stage: RAI ML0807907442008-03-26026 March 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application, for Sections B.2.6, B.2.19, and B.2.23 Project stage: RAI L-08-122, Reply to Request for Additional Information for the Review of the License Renewal Application and Revisions to License Renewal Application Boundary Drawings2008-03-31031 March 2008 Reply to Request for Additional Information for the Review of the License Renewal Application and Revisions to License Renewal Application Boundary Drawings Project stage: Response to RAI ML0807903922008-04-0101 April 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI ML0807905382008-04-0101 April 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI L-08-124, Reply to Request for Additional Information for Review of the License Renewal Application and License Renewal Application Amendment No. 52008-04-0202 April 2008 Reply to Request for Additional Information for Review of the License Renewal Application and License Renewal Application Amendment No. 5 Project stage: Response to RAI ML0807907352008-04-0303 April 2008 RAI for the Reveiw of the Beaver Valley, Units 1 and 2, License Renewal Application Project stage: RAI ML0810002962008-04-0303 April 2008 Reply to Request for Additional Information for the Review of License Renewal Application, Amendment No. 4, and Revised License Renewal Boundary Drawings Project stage: Response to RAI ML0810003222008-04-0303 April 2008 Drawing Lr 1-07-2, Rev. 4, Chemical and Volume Control System. Project stage: Other ML0810003232008-04-0303 April 2008 Drawing Lr 1-07-3, Rev. 6, Chemical and Volume Control System. Project stage: Other ML0810003242008-04-0303 April 2008 Drawing Lr 1-08-1, Rev. 4, Boron Recovery Degasifiers. Project stage: Other ML0810003262008-04-0303 April 2008 Drawing Lr 1-09-2, Rev. 4, Vent and Drain System. Project stage: Other ML0810003272008-04-0303 April 2008 Drawing Lr 1-12-1, Rev. 5, Containment Vacuum and Leakage Monitoring System. Project stage: Other ML0810003282008-04-0303 April 2008 Drawing Lr 1-14A-1, Rev. 7, Sample System. Project stage: Other ML0810003292008-04-0303 April 2008 Drawing Lr 1-14A-2, Rev. 5, Sample System. Project stage: Other ML0810003302008-04-0303 April 2008 Drawing Lr 1-19-1, Rev. 5, Gaseous Waste Disposal System. Project stage: Other ML0810003322008-04-0303 April 2008 Drawing Lr 1-30-1, Rev. 5, River Water System. Project stage: Other L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System.2008-04-0303 April 2008 Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System. Project stage: Other ML0810003312008-04-0303 April 2008 Drawing Lr 1-24-1, Rev. 6, Feedwater System. Project stage: Other ML0809804832008-04-17017 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI ML0810503332008-04-17017 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI L-08-143, Reply to Request for Additional Information for Review of License Renewal Application and License Renewal Application Amendment No. 62008-04-18018 April 2008 Reply to Request for Additional Information for Review of License Renewal Application and License Renewal Application Amendment No. 6 Project stage: Response to RAI L-08-144, Reply to Request for Additional Information for the Review of License Renewal Application2008-04-25025 April 2008 Reply to Request for Additional Information for the Review of License Renewal Application Project stage: Response to RAI ML0811303942008-04-28028 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI ML0810502702008-04-30030 April 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI L-08-146, Reply to Request for Additional Information for Review, License Renewal Application and License Renewal Application Amendment No. 72008-04-30030 April 2008 Reply to Request for Additional Information for Review, License Renewal Application and License Renewal Application Amendment No. 7 Project stage: Response to RAI L-08-174, Request for Revised Submittal Date for Reply to Request for Additional Information for the Review of the License Renewal Application2008-05-0202 May 2008 Request for Revised Submittal Date for Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-08-149, Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application2008-05-0505 May 2008 Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Response to RAI ML0814104162008-05-0808 May 2008 Transmittal of Correction to Reply to RAI for the Review of License Renewal Application, License Renewal Application Amendment No. 8 & Revised License Renewal Boundary Drawings Project stage: Request ML0810505432008-05-0808 May 2008 Request for Additional Information, Sections 3.5.2.2, B.2.1, B.2.3 and 4.6 of License Renewal Application Project stage: RAI ML0811604672008-05-0808 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI ML0812009202008-05-0808 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC MD6593 and MD6594) Project stage: RAI ML0811205392008-05-15015 May 2008 Request for Additional Information, License Renewal Application (TAC Nos. MD6593 and MD6594) Project stage: RAI ML0814405432008-05-19019 May 2008 Reply to Request for Additional Information for the Review of the License Renewal Application Amendment No. 9. and Revised License Renewal Boundary Drawings Project stage: Response to RAI L-08-169, Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application2008-05-19019 May 2008 Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Response to RAI ML0811304122008-05-22022 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI ML0813605572008-05-22022 May 2008 Revision of Schedule for the Conduct of Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0811505772008-05-28028 May 2008 Request for Additional Information for Sections B.2.27, 4.3 and 4.7.4 of the BVPS LRA Project stage: RAI L-08-180, Reply to Request for Additional Information for the Review of the License Renewal Application2008-05-28028 May 2008 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-08-147, Reply to Request for Additional Information for Renewal License Application2008-06-0202 June 2008 Reply to Request for Additional Information for Renewal License Application Project stage: Response to RAI ML0814306872008-06-0404 June 2008 Request for Additional Information the Review of Beaver Valley, Units 1 and 2, License Renewal Application Project stage: RAI L-08-181, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application, Amendment No. 102008-06-0606 June 2008 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application, Amendment No. 10 Project stage: Response to RAI ML0816405052008-06-0909 June 2008 Reply to Request for Additional Information for the Review of the License Renewal Application License Renewal Application Amendment No. 11, and Revised License Renewal Boundary Drawings Project stage: Response to RAI ML0816405922008-06-0909 June 2008 Drawing Lr 1-14A-1, Rev. 8, Sample System (Ss). Project stage: Other ML0816405932008-06-0909 June 2008 Drawing Lr 1-21-1, Rev. 6, Main Steam System (Ms). Project stage: Other ML0816405942008-06-0909 June 2008 Drawing Lr 1-22-1, Rev. 4, Condensate System (Cn). Project stage: Other 2008-04-03
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Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
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Text
FENOCf Beaver Valley Power Station Shippin P.O. Box 4 FirstEnergy Nuclear Operating Company Kevin L. Ostrowski 724-682-5234 Director, Site Operations Fax: 724-643-8069 June 1,2009 L-09-139 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC Nos. MD6593 and MD6594), and License Renewal Application Amendment No. 38 Reference 1 provided the FirstEnergy Nuclear Operating Company (FENOC) License Renewal Application (LRA) for the Beaver Valley Power Station (BVPS). Reference 2 requested additional information from FENOC regarding Sections B.2.3 and B.2.5 of the BVPS LRA. This letter provides the FENOC reply to the U.S. Nuclear Regulatory Commission (NRC) request for additional information (RAI). This letter also provides Amendment No. 38 to the BVPS LRA based on changes resulting from the FENOC reply to the NRC.The Attachment provides the FENOC reply to the NRC request for additional information.
The Enclosure provides Amendment No. 38 to the BVPS LRA.There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June /., 2009.Sincerely, Kevin L. Ostrowski OK jNfl,4 Beaver Valley Power Station, Unit Nos. 1 and 2 L-09-139 Page 2
References:
- 1. FENOC Letter L-07-113, "License Renewal Application," August 27, 2007.2. NRC Letter, "Request For Additional Information For The Review Of The Beaver Valley Power Station, Units 1 And 2, License Renewal Application (TAC Nos.MD6593 And MD6594)," May 7, 2009.
Attachment:
Reply to Request for Additional Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Sections B.2.3 and-B.2.5
Enclosure:
Amendment No. 38 to the BVPS License Renewal Application cc: Mr. K. L. Howard, NRC DLR Project Manager Mr. S. J. Collins, NRC Region I Administrator cc: w/o Attachment or Enclosure Mr. B. E. Holian, NRC DLR Director Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRC DORL Project Manager Mr. D. J. Allard, PA BRP/DEP Director Mr. L. E. Ryan, PA BRP/DEP ATTACHMENT L-09-139 Reply to Request for Additional Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Sections B.2.3 and B.2.5 Page 1 of 6 Section B.2.3 Question RAI B.2.3-4
Background:
LRA Section B.2.3 states that American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code Section XI, Subsection IWE inspections have identified containment liner plate deficiencies such as paint flaking, chipping, blistering, and other minor damage. The application further stated that the inspections have been effective in identifying minor irregularities on the inside surface of the liner plate before significant corrosion damage occurred.Issue: In 2006, during a steam generator replacement, three locations of corrosion were discovered on the concrete side of the containment liner. These were attributed to degradation during initial construction, and the locations were either repaired or identified for future inspections.
On April 23, 2009, during an IWE inspection, a paint blister was discovered, which upon further inspection revealed through-wall corrosion of the containment liner.Request: Explain how the recent plant-specific operating experience, both the 2006 and 2009 degradation, will be incorporated into the ASME Section XI, Subsection IWE AMP, and whether or not a plant-specific program is necessary to manage aging of the containment liner.RESPONSE RAI B.2.3-4 A plant-specific program is not necessary.
Modifications to the existing program and corrective actions are described below.Following the liner corrosion discovered in 2006, the containment inspection procedures were modified to address the potential corrosion of the liner material utilizing a visual inspection approach.
Both the Unit I and Unit 2 procedures were modified to include the following acceptance criteria:
Attachment L-09-139 Page 2 of 6 1. When paint or coatings are to be removed for further inspection, the paint or coatings shall be visually examined by a qualified VT-3 inspector prior to removal.2. If the visual examination detects surface flaws on the liner or suspect areas on the liner plate that could potentially impact the leak tightness or structural integrity of the liner, then surface or volumetric examinations shall be performed to characterize the condition (i.e., depth, size, shape, orientation).
Two of the three degraded areas were removed and replaced with new plate material.The third area was reinstalled upon restoration of the containment construction opening in 2006. The reinstalled area was inspected by ultrasonic testing (UT) during the current refueling outage (April/May 2009) to confirm that additional corrosion'is not occurring.
Wall thickness measurements were within the calibration tolerances of the installed (2006) condition.
In 2009, an approximately 1 inch by 3/8 inch defect area of through-wall corrosion was identified by visual observation of a paint blister and subsequent use of the actions in the modified procedure.
The affected area containing the defect (identified in 2009) was replaced in accordance with IWE 3122.2. The defect was associated with the presence of a piece of wood embedded in the concrete directly behind the through-wall corrosion defect and is considered an event-based occurrence.
The next ASME Section XI, Subsection IWE program visual examinations of accessible containment liner surfaces are currently scheduled for Unit 1 refueling outage 1 R21 (April 2012 at Unit 1) and Unit 2 refueling outage 2R1 5 (April/May 2011 at Unit 2).Corrective actions for the degradation identified in 2009 include visual examinations of 100% of the accessible liner area in 1 R20 in October/November 2010 and 2R1 4 in October/November 2009 to confirm that additional through wall corrosion has not occurred.
A UT inspection of the replaced area is scheduled during 1 R20 to confirm that no new unacceptable corrosion is occurring as a result of the replacement.
These future actions are tracked in the corrective action program.Additionally, supplemental volumetric examinations will be performed on the Unit I and Unit 2 containment liners prior to the period of extended operation.
Seventy five (one foot square) sample locations at each unit will be examined.
If no degradation is found, this sample size will provide 95% confidence that 95% of the liner is not degraded (using the methodology in chapter 4 of EPRI TR-107514).
If degradation is identified, the degraded area(s) will be evaluated and follow-up examinations will be performed to ensure the continued reliability of the containment liner. A commitment to perform these supplemental examinations is provided in Appendix A of the LRA.The existing BVPS ASME Section XI, Subsection IWE program is in accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWE with the limitations and modifications required by the Code of Federal Regulations in 10 CFR 50.55a.
Attachmenf L-09-139 r Page 3 of 6 Question RAI B.2.3-5
Background:
During a presentation to the ACRS sub-committee, on February 4, 2009, the applicant stated that their ASME Section XI, Subsection IWE Program'had been enhanced in response to the degradation discovered in 2006.Issue: The applicant has not discussed the relationship, if any between an enhanced IWE Program and an augmented IWE Program.Request: Explain how the IWE Program was enhanced, with a focus on how the enhancements relate to the ASME code required augmented inspections.
The explanation should be in sufficient detail to allow for a one to one comparison between an enhanced IWE Program and the augmented inspections required by ASME Section XI, Subsection IWE.RESPONSE RAI B.2.3-5 The program was not enhanced to achieve GALL consistency as described in NUREG-1 800. The procedures used by the program were modified, as described below, to identify additional actions to be followed in the event suspect surfaces were identified by the IWE visual inspection.
In 2006, the containment inspection procedures of the existing IWE program for both units were modified to address the potential corrosion of the liner material utilizing a visual inspection approach.
The procedure modifications were the outcome of corrective actions from the 2006 occurrence.
At Beaver Valley, these procedures satisfy ASME XI, Subsection IWE General Visual Examination requirements for examination of Class MC (Metal Containment) surfaces.
Both the Unit 1 and Unit 2 procedures were modified to include the following acceptance criteria: 1.. When paint or coatings are to be removed for further inspection, the paint or coatings shall be visually examined by a qualified.
VT-3 inspector prior to removal.2. If the visual examination detects surface flaws on the liner or suspect areas on the liner plate that could potentially impact the leak tightness or structural integrity of the liner, then surface or volumetric examinations shall be performed to characterize the condition (i.e., depth, size, shape, orientation).
Following the discovery of the corrosion on the concrete side of the liner plate in 2006, two of the three degraded areas were removed and replaced with new plate material.The third area was acceptable for continued use and was left in place. As part of the Attachment L-09-139 Page 4 of 6 corrective actions from the discovery, this area is monitored with subsequent examinations.
The area is defined on the interior surface of the liner plate to allow examination from the surfaces inside the Containment Building.
A baseline UT thickness measurement was performed in 2006. In May 2009, in accordance with this corrective action, UT measurements were taken of the third area. Wall thickness measurements were within the calibration tolerances of the installed (2006) condition.
These corrective actions from 2006 are not characterized as ASME Xl, Subsection IWE augmented examinations.
The degradation was discovered outside of scheduled ASME Xl, Subsection IWE examinations.
In April 2009, during the performance of the ASME Xl, Subsection IWE containment liner interior visual examination, a suspect area was discovered which exhibited blistered paint and protruding corrosion product. The area was cleaned, which revealed a through-wall hole approximately 1" by 3/8". Wood debris was found within the concrete, directly adjacent to the hole. Laboratory analysis concluded that the wood debris most likely promoted the corrosion.
The affected area was replaced and pressure tested to ensure leak tightness.
The next ASME Section XI, Subsection IWE program visual examinations of accessible containment liner surfaces are currently scheduled for Unit 1 refueling outage 1 R21 (April 2012 at Unit 1) and Unit 2 refueling outage 2R15 (April/May 2011 at Unit 2).Corrective actions for the degradation identified in 2009 include visual examinations of 100% of the accessible liner area in 1 R20 in October/November 2010 and 2R1 4 in October/November 2009 to confirm that additional through wall corrosion has not occurred.
A UT inspection of the replaced area is scheduled during 1 R20 to confirm that no new unacceptable corrosion is occurring as a result of the replacement.
These future actions are tracked in the corrective action program.Additionally, supplemental volumetric examinations will be performed on the Unit 1 and Unit 2 containment liners prior to the period of extended operation.
Seventy five (one foot square) sample locations at each unit will be examined.
If no degradation is found, this sample size will provide 95% confidence that 95% of the liner is not degraded (using the methodology in chapter 4 of EPRI TR-1 07514). If degradation is identified, the degraded area(s) will be evaluated and follow-up examinations will be performed to ensure the continued reliability of the containment liner. A commitment to perform these supplemental examinations is provided in Appendix A of the LRA.These corrective actions are not characterized as ASME XI, Subsection IWE augmented examinations.
The affected area has been replaced.The existing BVPS ASME Section Xl, Subsection IWE program is in accordance with ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWE, within the limitations and modifications required by the Code of Federal Regulations in 10 CFR 50.55a.
Attachment L-09-139 Page 5 of 6 Section B.2.5 Question RAI B.2.5-1
Background:
During a steam generator replacement in 2006, three areas of corrosion were identified on the concrete side of the containment liner. In response to previous license renewal RAIs, the applicant explained that when visual examinations detect indications of degradation, surface or volumetric examinations will be performed on suspect areas of the liner plate.Issue: On April 23, 2009, during an IWE inspection, a paint blister was discovered, which upon further inspection revealed through-wall corrosion of the containment liner.During the applicant's inspection of the corrosion, a piece of wood was discovered in the concrete behind the containment liner, which the applicant has indicated may have led to degradation of the containment concrete.Request: Explain whether or not the concrete or rebar, located behind the through-wall flaw, were degraded.
Also explain how the recent plant-specific operating experience will be incorporated into the ASME Section Xl, Subsection IWL AMP, and whether or not a plant-specific program is necessary to manage aging of the containment concrete.RESPONSE RAI B.2.5-1 The concrete exposed during the removal of the wood and replacement of the flawed liner section was not degraded.
No structural rebar was exposed. No enhancement to the ASME Section XI, Subsection IWL program is needed, and no plant-specific program is needed to manage aging of the containment concrete.The concrete behind the liner defect contained a small void associated with the volume of embedded wood. Some concrete immediately around the wood was removed to support removal of the embedded wood, and the area was repaired with grout prior to replacement of the liner section. The concrete behind the through-wall flaw was not degraded.
No structural rebar was exposed during the removal of the wood and replacement of the affected section of the liner.A section of vertical rebar (with visible corrosion adjacent to the location of the wood)was encountered during removal of the wood and concrete for the repair associated with the liner corrosion.
Based on the location and orientation of the steel rebar encountered, the rebar was determined to be an extra, non-structural member of the Attachment L-09-1 39 Page 6 of 6 containment concrete structure used in forming the rebar skeleton prior to and during the concrete pour.No structural rebar was exposed during the 2009 liner repair. During the 2006 steam generator replacement project, the structural rebar within the (approximately 23 ft x 21 ft) construction dpening was exposed. Within the expanse of rebar exposed by the concrete removal, corrosion was noted on only one small section approximately nine inches in length. This observation provides reasonable assurance that the structural rebar is in good condition.
The BVPS ASME Section Xl, Subsection IWL program is in accordance with ASME Boiler and Pressure Vessel Code, Section Xl, Subsection IWL, within the limitations and modifications required by the Code of Federal Regulations in 10 CFR 50.55a. No enhancement to the ASME Section Xl, Subsection IWL program is needed, and no plant-specific program is needed.
ENCLOSURE Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2 Letter L-09-139 Amendment No. 38 to the BVPS License Renewal Application Page 1 of 3 License Renewal Application Sections Affected Table A.4-1 Table A.5-1 The Enclosure identifies the correction by Affected License Renewal Application (LRA)Section, LRA Page No., and Affected Paragraph and Sentence.
The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate.
Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text fined-ou and added text underlined.
Enclosure L-09-139 Page 2 of 3 Affected LRA Section LRA Page No.Affected Paragraph and Sentence New Item No. 32 Table A.4-1 Page A.4-9 LRA Table A.4-1, "Unit I License Renewal Commitments," is amended to add new Item No. 32 regarding examination of the containment liner as follows: Item Number Commitment Related LRA Section No./Comments 32 Supplemental volumetric examinations will be performed on the Unit I containment liner prior to the Deriod of extended ooeration.
Seventy January 29, 2016 None five (one foot sauare) sample locations will be examined.
If dearadation is identified, the deQraded area(s) will be evaluated and follow-up examinations will be Derformed to ensure the continued reliability of the containment liner.
Enclosure L-09-139 Page 3 of 3 Affected LRA Section LRA Page No.Page A.5-10 Affected Paragraph and Sentence New Item No. 33 Table A.5-1 LRA Table A.5-1, "Unit 2 License Renewal Commitments," is amended to add new Item No. 33 regarding examination of the containment liner as follows: Related LRA Item ImplementationRead A temCommitment Ipeme Source Section No./Number ComtetSchedule Cmet Comments 33 Supplemental volumetric May 27, 2027 FENOC None examinations will be performed on the Letter Unit 2 containment liner prior to the L-09-139 period of extended operation.
Seventy five (one foot square) sample locations will be examined.
If degradation is identified, the degraded area(s) will be evaluated and follow-up examinations will be performed to ensure the continued reliability of the containment liner.