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
[Table view] |
Text
FENOC FirstEnergyNuclear OperatingCompany Peter P. Sena III 724-682-5234 Site Vice President Fax: 724-643-8069 June 9, 2008 L-08-190 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. 12 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 the BVPS license renewal integrated plant assessment in Sections B.2.6 and 3.3.2 of the BVPS LRA.
The Attachment provides the FENOC reply to the U.S. Nuclear Regulatory Commission request for additional information. The Enclosure provides Amendment No. 12 to the BVPS License Renewal Application.
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 4*, 2008.
Sinc ely, Peter P. Sena Ill c1/0
Beaver Valley Power Station, Unit Nos. 1 and 2 L-08-190 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 8, 2008.
Attachment:
Reply to Request for Additional Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Sections B.2.6 and 3.3.2
Enclosure:
Amendment No. 12 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 Dr. S. S. Lee, NRC DLR Acting 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-08-190 Reply to Request for Additional Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Sections B.2.6 and 3.3.2 Page 1 of 3 Section B.2.6 Question RAI B.2.6-3 In the BVPS LRA, there are many AMR line items which reference VII.I-4 of GALL.
However, no items could be found which reference V1I.l-5 of GALL; even though the two share the same component, material, and environment descriptions. The exclusion of item VII.l-5 leads to the assumption that the associated aging effect, "Loss of preload/thermal effects, gasket creep, and self-loosening" for the component, material, and environment combination are not experienced at BVPS.
Similarly, VIII.H-4 of GALL is referenced in the BVPS LRA and VIII.H-5 of GALL is not. Please provide your technical basis for these exclusions and why, specifically, the associated aging effect is not expected to be experienced at BVPS.
RESPONSE RAI B.2.6-3 Electric Power Research Institute (EPRI) 1010639, Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools, Revision 4, was consulted for the aging management review methodologies for FENOC license renewal. Based on the guidance provided by EPRI 1010639, FirstEnergy Nuclear Operating Company (FENOC) did not identify loss of preload as an applicable aging effect. Therefore, the NUREG-1801, "Generic Lessons Learned (GALL) Report," line items associated with this aging effect do not appear in the Beaver Valley Power Station (BVPS) License Renewal Application (LRA). However, as stated in LRA Section B.2.6, the Bolting Integrity Program includes periodic inspection for indication of loss of preload (i.e.,
leakage), and preventive measures to preclude or minimize loss of preload during the installation process.
EPRI 1010639, Appendix F, Bolted Closures, Section 3.1, Loss of Pre-Load, states:
"Pre-loadis the tension force developed in a fastener when it is tightened againsta joint. The pre-load in a bolt is often less than expected and decrease of the pre-load may be attributedto, but not limited to, one or more of the following effects: embedment, cyclic load embedment, gasket.
creep, thermal effects (e.g., yield stress effect, modulus of elasticity effect, and stress relaxation), and self-loosening. ... These effects are typically addressed upon installationand subsequent maintenance of the joint."
Attachment L-08-190 Page 2 of 3
"... the loss of pre-load in a mechanicaljoint can only result in leakage, not failure of thatjoint. This leakage does not impact the pressure boundary such that the component's intended function is not accomplished. It is noted that in ASME Section III (NX-2121), gaskets, seals, and O-rings are not considered to perform a pressure retaining function and therefore, these parts are typically not considered to support a component intended function. It follows that the loss of pre-load from the above mechanisms does not result in loss of mechanical closure or loss of pressure boundary integrity. Therefore, loss of pre-load is not an applicableaging effect."
Because loss of preload in a mechanical joint results in leakage, and the effects that contribute to loss of preload are addressed upon installation and subsequent maintenance of the joint, FENOC manages loss of preload through leakage monitoring and proper installation and maintenance of the components in accordance with industry standards.
Table 3.3.2-7 Question RAI 3.3.2-7-1 In the BVPS LRA, Item 55 of Table 3.3.2-7, "Heat exchanger (Tube-diesel cooling water)," includes footnote H-aging effect not in NUREG-1801 (Chapter VII) for this component, material and environment combination. The aging management program (AMP) designated by BVPS to manage this item is B.2.15 - External Surfaces Monitoring, with the aging effect listed as "Reduction of Heat Transfer".
Although the diesel generator jacket water radiator fins are clearly identified as being within the scope of the program, it is not clear whether or not the heat exchanger tubes are included. Because of this, it is not apparent how this AMP is able to manage the detection of aging effects element of the GALL for Item 55 of Table 3.3.2-7. Please elaborate on the scope and detection of aging effects for this AMP as it relates to Item 55 of Table 3.3.2-7.
RESPONSE RAI 3.3.2-7-1 BVPS LRA Sections A. 1.15 and B.2.15, "External Surfaces Monitoring Program," are revised to state that inspection is required of radiators (fins and tubes) associated with diesel engines and diesel-driven equipment for build-up of dust, dirt and debris.
BVPS LRA Sections A.1. 15 and B.2.15 previously stated that inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, referring to Table 3.3.2-17, "Auxiliary Systems -
Attachment L-08-1 90 Page 3 of 3 Emergency Response Facility Substation System - Summary of Aging Management Evaluation," row 32. However, as shown in LRA Table 3.3.2-7, "Auxiliary Systems -
Compressed Air System - Summary of Aging Management Evaluation," the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program descriptions in LRA Appendices A and B.
BVPS LRA, Tables 3.3.2-7 and 3.3.2-17, each contain two rows which independently provide the external surface aging management review results for a "reduction of heat transfer" aging effect for the heat exchanger aluminum fins and copper alloy tubes of the Unit 2 diesel-driven air compressor jacket water radiator and the ERF diesel generator jacket water radiator, respectively. These rows credit the External Surfaces Monitoring Program for managing this aging effect. Although they were evaluated as two components in the aging management review tables, the fins and tubes are part of the same assembly that performs the intended function of "heat transfer". The fin and tube assembly can be seen externally, and will be inspected for build-up of dust, dirt, and debris that would affect its intended function.
See the Enclosure to this letter for the revision to the BVPS LRA.
ENCLOSURE Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2 Letter L-08-190 Amendment No. 12 to the BVPS License Renewal Application Page 1 of 4 Sections Affected Section A.1.15 Section B.2.15 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 top of the affected page or at the start of the affected section, as applicable. Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text lined-out and added text underlined.
Enclosure L-08-190 Page 2 of 4 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Section A.1.15 Page A.1-7 st Paragraph, 3 rd Sentence BVPS LRA Section A. 1.15, "External Surfaces Monitoring Program," states that inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, but does not address the radiator tubes. Additionally, the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program description. LRA Section A.1.15 is revised to read:
The External Surfaces Monitoring Programis based on system inspections and walkdowns. This program consists of periodicinspections to monitor the external surfaces of in-scope steel components and other metal components for material degradationand leakage, and periodicinspection of in-scope elastomer components for hardening,loss of strength or cracking through physical manipulation. The program will also require inspection of radiators(fins and tubes) associatedwith diesel engines and diesel-driven equipment for build-up of dust, dirt and debris. The program will also rqie.. ction of the Emergen*y Responso Faeiliy 6'ERF) diesel generao 'Jacketateiriradiat-or-fins for buil up oe dust, dirt and debris. Additionally, the program is credited with managing aging effects of internal surfaces, for situations in which materialand environment combinations are the same for internaland external surfaces such that external surface condition is representativeof internal surface condition.
Enclosure L-08-190 Page 3 of 4 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Section B.2.15 Page B.2-39 2 nd Paragraph, 3 rd Sentence BVPS LRA Section B.2.15, "External Surfaces Monitoring Program," states that inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, but does not address the radiator tubes. Additionally, the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program description. LRA Section B.2.15 is revised to read:
The External Surfaces Monitoring Programis based on system inspections and walkdowns. This program will consist of periodicinspections to monitor the external surfaces of in-scope steel components and other metal components for materialdegradationand leakage, and periodic inspection of in-scope elastomer components for hardening,loss of strength or cracking through physical manipulation. The program will also require inspection of radiators(fins and tubes) associatedwith diesel engines and diesel-driven equipment for build-up of dust, dirt and debris. The program will also ruIr, n.... tion of the Emorgc*. .y Response Faciliy (E-RF) dieseol gnctoict 14phor radiator fine for-build up oe dust, dirt and deb.,s. Additionally, the program is credited with managing aging effects of internal surfaces, for situations in which materialand environment combinations are the same for internaland external surfaces such that external surface condition is representativeof internalsurface condition.
Section B.2.15 Pages B.2-39&-40 Last Paragraph, 3 rd Sentence BVPS LRA Section B.2.15, under the headings "Aging Management Program Elements," "Scope of Program," states that inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, but does not address the radiator tubes.
Additionally, the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program description. LRA Section B.2.15, page B.2-39, last paragraph, 3 rd sentence is revised to read:
The program will also require inspection of radiators(fins and tubes) associated with diesel engines and diesel-driven equipment for build-up of dust, dirt and debris.Th pregran* ,; also mqui,
,r;n fi;n of the ERF= diesel nerator Jacket water radiator-fins for build up of dust, dirt and debris.
Enclosure L-08-190 Page 4 of 4 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Section B.2.15 Page B.2-40 2 nd Paragraph, 3 rd Sub-bullet BVPS LRA Section B.2.15, under the headings "Aging Management Program Elements," "Scope of Program," states that visual inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, but does not address the radiator tubes.
Additionally, the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program description. LRA Section B.2.15, page B.2-40, 2n paragraph, 3 rd sub-bullet is revised to read:
Visual inspection of radiators(fins and tubes) associatedwith diesel engines and diesel-driven equipment for build-up of dust, dirt and debris. Visual inpection o, the ERE= diesel generFator Jacket water-radiator fins for build up of dust, dirt an debris. The E-RF-dieselgen orator jacket water radiator-is a coilfin typc heat exchanger-whec the fins arc exposed to an air outdoor environment. The applicable aging effect is reduction of heat transferdue to build-up of dust, dirt and debris.
Section B.2.15 Page B.2-41 1 st Paragraph, 3 rd Sentence BVPS LRA Section B.2.15, under the headings "Aging Management Program Elements," "Detection of Aging Effects," states that inspection is required of the Emergency Response Facility (ERF) diesel generator jacket water radiator fins for build-up of dust, dirt and debris, but does not address the radiator tubes.
Additionally, the diesel in the Unit 2 Compressed Air System also credits the program, but the inspection requirement was not specifically stated in the program description. LRA Section B.2.15, page B.2-41, 1 st paragraph, 3 rd sentence is revised to read:
The program will also require inspection of radiators(fins and tubes) associated with diesel engines and diesel-driven equipment for build-up of dust, dirt and debris. The program will also req.ir.. periodic inpection of the ERF diesel generator jacket water radhiatorfi~n.S ifor build up of dust, dirt and debris.