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| {{#Wiki_filter:September 3, 2008 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-BV-SEB-1 P.O. Box 4, Route 168 Shippingport, PA 15077 | | {{#Wiki_filter:September 3, 2008 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-BV-SEB-1 P.O. Box 4, Route 168 Shippingport, PA 15077 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION |
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| ==Dear Mr. Sena:== | | ==Dear Mr. Sena:== |
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| By letter dated August 27, 2007, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54), to renew the operating licenses for Beaver Valley Power Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future. | | By letter dated August 27, 2007, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54), to renew the operating licenses for Beaver Valley Power Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future. |
| | | Items in the enclosure were discussed with Mr. Clifford I. Custer of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2989 or by e-mail at Kent.Howard@nrc.gov. |
| Items in the enclosure were discussed with Mr. Clifford I. Custer of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2989 or by e-mail at Kent.Howard@nrc.gov. Sincerely, \RA\ Kent L. Howard, Sr., Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 | | Sincerely, |
| | \RA\ |
| | Kent L. Howard, Sr., Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: See next page
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| ML082401708 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing KHoward RFranovich DATE 8/29/08 9/3/08 9/3/08 BEAVER VALLEY POWER STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 3.3-A In license renewal application (LRA) Tables 3.3.2-1, 3.3.2-2, 3.3.2-11 and 3.3.2-12, the applicant has credited the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program, to manage the aging effects of cracking and reduction of heat transfer of stainless steel, aluminum, and copper alloy <15% Zn moisture separators and heat exchangers.
| | As stated cc w/encl: See next page |
| The applicant has described this program in LRA Section B2.22 and stated that it is consistent with the generic aging lessons learned (GALL) aging management program (AMP) XI.M38. However, the GALL AMP XI.M38 is credited for managing the aging effect of loss of material due to corrosion for steel components only.
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| (a) Please justify how this program will manage the aging effect of reduction of heat transfer or provide a plant-specific program.
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| (b) Please justify how this program will manage the aging effect of cracking of moisture separator or provide a plant-specific program.
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| RAI 3.5-A In LRA Table 3.5.2-36, the applicant states in line 229 that for fire wraps, there is no aging effect requiring management. However, the applicant is proposing to use the Fire Protection Program. The applicant has referenced footnote 524 for this line item. Footnote 524 states that the Fire Protection (B.2.16) Program supplements aging effects management for fire barrier cable trays, conduits, ductwork and structural members.
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| Please clarify what you mean by "supplements aging effects management," when there is no aging effect requiring management.
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| RAI 3.2.2.3.2 - 1
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| In LRA Table 3.2.2.-2, aging management review lines 25 and 36 describe that for reduction of heat transfer, the Water Chemistry Program will be used.
| | ML082401708 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing KHoward RFranovich DATE 8/29/08 9/3/08 9/3/08 |
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| | BEAVER VALLEY POWER STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 3.3-A In license renewal application (LRA) Tables 3.3.2-1, 3.3.2-2, 3.3.2-11 and 3.3.2-12, the applicant has credited the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program, to manage the aging effects of cracking and reduction of heat transfer of stainless steel, aluminum, and copper alloy <15% Zn moisture separators and heat exchangers. |
| | The applicant has described this program in LRA Section B2.22 and stated that it is consistent with the generic aging lessons learned (GALL) aging management program (AMP) XI.M38. |
| | However, the GALL AMP XI.M38 is credited for managing the aging effect of loss of material due to corrosion for steel components only. |
| | (a) Please justify how this program will manage the aging effect of reduction of heat transfer or provide a plant-specific program. |
| | (b) Please justify how this program will manage the aging effect of cracking of moisture separator or provide a plant-specific program. |
| | RAI 3.5-A In LRA Table 3.5.2-36, the applicant states in line 229 that for fire wraps, there is no aging effect requiring management. However, the applicant is proposing to use the Fire Protection Program. |
| | The applicant has referenced footnote 524 for this line item. Footnote 524 states that the Fire Protection (B.2.16) Program supplements aging effects management for fire barrier cable trays, conduits, ductwork and structural members. |
| | Please clarify what you mean by supplements aging effects management, when there is no aging effect requiring management. |
| | RAI 3.2.2.3.2 - 1 In LRA Table 3.2.2.-2, aging management review lines 25 and 36 describe that for reduction of heat transfer, the Water Chemistry Program will be used. |
| The staff noted that the One-Time Inspection Program is not identified to verify the effectiveness of the Water Chemistry Program in ensuring that the aging effect is being managed. | | The staff noted that the One-Time Inspection Program is not identified to verify the effectiveness of the Water Chemistry Program in ensuring that the aging effect is being managed. |
| Explain how verification of the Water Chemistry Program is accomplished to ensure that the aging effect is managed. | | Explain how verification of the Water Chemistry Program is accomplished to ensure that the aging effect is managed. |
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| RAI B.2.17-2 follow-up In RAI B2.17-2, since the frequency of inspections of fire hydrant gaskets of once every 18 months in the LRA is different than the recommended frequency of once every 12 months in the GALL AMP, the staff asked the applicant to justify why this was not an exception.
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| | RAI B.2.17-2 follow-up In RAI B2.17-2, since the frequency of inspections of fire hydrant gaskets of once every 18 months in the LRA is different than the recommended frequency of once every 12 months in the GALL AMP, the staff asked the applicant to justify why this was not an exception. |
| In its letter dated July 24, 2008, the applicant stated that although these gaskets perform no license renewal intended function, their condition is monitored by the Fire Water System Program and they are replaced as necessary. However, the frequency of inspection is still different than what the GALL AMP recommends and no justification was provided why this is not an exception. | | In its letter dated July 24, 2008, the applicant stated that although these gaskets perform no license renewal intended function, their condition is monitored by the Fire Water System Program and they are replaced as necessary. However, the frequency of inspection is still different than what the GALL AMP recommends and no justification was provided why this is not an exception. |
| Please provide justification why this is not an exception. | | Please provide justification why this is not an exception. |
| RAI B.2.17-3 follow-up In RAI B.2.17-3, since the fire hydrant hose hydraulic tests are performed at various frequencies different than the GALL AMP recommended frequency of once every 12 months, the staff asked the applicant to justify why this was not an exception. | | RAI B.2.17-3 follow-up In RAI B.2.17-3, since the fire hydrant hose hydraulic tests are performed at various frequencies different than the GALL AMP recommended frequency of once every 12 months, the staff asked the applicant to justify why this was not an exception. |
| In its letter dated July 24, 2008, the applicant responded that fire hoses are consumables, and are routinely tested, inspected, and replaced when necessary. Criteria for inspection and replacement are based on accepted industry standards (e.g.,NFPA-1962). Therefore, while these consumables are within the scope of license renewal, they do not require an aging management review. However, the frequency of hydraulic testing is still different than what the GALL AMP recommends and no justification was provided why this is not an exception. | | In its letter dated July 24, 2008, the applicant responded that fire hoses are consumables, and are routinely tested, inspected, and replaced when necessary. Criteria for inspection and replacement are based on accepted industry standards (e.g.,NFPA-1962). Therefore, while these consumables are within the scope of license renewal, they do not require an aging management review. However, the frequency of hydraulic testing is still different than what the GALL AMP recommends and no justification was provided why this is not an exception. |
| | | Please provide justification why this is not an exception. |
| Please provide justification why this is not an exception. | |
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| Letter to P. Sena III from K. Howard, dated September 3, 2008 DISTRIBUTION | | Letter to P. Sena III from K. Howard, dated September 3, 2008 DISTRIBUTION: |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSbwb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY: |
| ------------- KHoward ESayoc NMorgan MModes, RI PCataldo, RI DWerkheiser, RI | | DLR RF E-MAIL: |
| | | PUBLIC RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSbwb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter |
| Beaver Valley Power Station, Units 1 and 2 cc: Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308
| | ------------- |
| | | KHoward ESayoc NMorgan MModes, RI PCataldo, RI DWerkheiser, RI |
| James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308
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| Paul A. Harden Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-15 76 South Main Street Akron, OH 44308
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| Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44308
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| Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-A P.O. Box 4, Route 168 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
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| Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077
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| Cliff Custer FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077
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| Steve Dort FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077 Mike Banko FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077}} | | Beaver Valley Power Station, Units 1 and 2 cc: |
| | Joseph J. Hagan Manager, Fleet Licensing President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 Mail Stop A-GO-19 76 South Main Street 76 South Main Street Akron, OH 44308 Akron, OH 44308 Director, Fleet Regulatory Affairs James H. Lash FirstEnergy Nuclear Operating Company Senior Vice President of Operations Mail Stop A-GO-2 and Chief Operating Officer 76 South Main Street FirstEnergy Nuclear Operating Company Akron, OH 44308 Mail Stop A-GO-14 76 South Main Street Manager, Site Regulatory Compliance Akron, OH 44308 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Danny L. Pace Mail Stop A-BV-A Senior Vice President, Fleet Engineering P.O. Box 4, Route 168 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Mail Stop A-GO-14 76 South Main Street Regional Administrator, Region I Akron, OH 44308 U.S. Nuclear Regulatory Commission 475 Allendale Road Jeannie M. Rinckel King of Prussia, PA 19406 Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Resident Inspector Mail Stop A-GO-14 U.S. Nuclear Regulatory Commission 76 South Main Street P.O. Box 298 Akron, OH 44308 Shippingport, PA 15077 Paul A. Harden Cliff Custer Vice President, Nuclear Support FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Steve Dort David W. Jenkins, Attorney FirstEnergy Nuclear Operating Company FirstEnergy Corporation Beaver Valley Power Station Mail Stop A-GO-15 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Mike Banko FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077}} |
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Category:Letter
MONTHYEARML24025A0922024-01-25025 January 2024
Requalification Program Inspection
L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023
Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615
IR 05000334/20230112023-12-0404 December 2023
Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011
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
IR 05000334/20233012023-11-27027 November 2023
Initial Operator Licensing Examination Report 05000334/2023301
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
IR 05000334/20230032023-11-0606 November 2023
Integrated Inspection Report 05000334/2023003 and 05000412/2023003
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
ML23279A0612023-10-0505 October 2023
Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23198A3592023-10-0202 October 2023
Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary
IR 05000334/20234022023-09-29029 September 2023
Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only)
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000334/20234012023-09-21021 September 2023
Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only)
ML23263A0192023-09-20020 September 2023
Operator Licensing Examination Approval
ML23243A9272023-09-19019 September 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report
ML23249A1842023-09-18018 September 2023
Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06
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
IR 05000334/20230052023-08-31031 August 2023
Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005)
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000334/20230022023-08-0909 August 2023
Integrated Inspection Report 05000334/2023002 and 05000412/2023002
ML23219A0592023-08-0707 August 2023
Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage
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
ML23188A0982023-07-17017 July 2023
Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML23188A0672023-07-10010 July 2023
Project Manager Assignment
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
ML23157A1072023-06-0707 June 2023
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011
ML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
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
ML23102A1472023-05-22022 May 2023
Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23135A7872023-05-19019 May 2023
Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
ML23124A3882023-05-16016 May 2023
Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
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
IR 05000334/20230012023-05-0808 May 2023
Integrated Inspection Report 05000334/2023001 and 05000412/2023001
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
ML23118A3812023-04-28028 April 2023
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
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23107A2502023-04-18018 April 2023
Requalification Program Inspection
2024-01-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
ML23125A1462023-05-0505 May 2023
NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23125A1602023-05-0505 May 2023
NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23122A0342023-05-0202 May 2023
NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report
ML22312A5912022-11-0808 November 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML22278A0972022-10-0606 October 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes
ML22178A1322022-06-24024 June 2022
Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage
ML22068A1822022-03-0909 March 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5
ML22013A7512022-01-13013 January 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010
ML21292A0482021-10-19019 October 2021
Ti 2515/194 Inspection Documentation Request
ML21259A1642021-09-16016 September 2021
NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits
ML21124A1322021-05-0404 May 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21102A1542021-04-0909 April 2021
Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR
ML21082A4942021-03-23023 March 2021
Final RAIs for GL 04-02 Closure (Email)
ML21068A3502021-03-0909 March 2021
Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR
ML21053A0252021-02-20020 February 2021
NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing
ML21015A5762021-01-14014 January 2021
Final RAIs for Steam Generator 180 Day Tube Inspection Report
ML21007A3732021-01-0707 January 2021
NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff,
ML21004A1442020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff
ML20290B0082020-10-0808 October 2020
Draft Request for Additional Information - Steam Generator Letter
ML20127H8672020-05-0606 May 2020
NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
ML20072N0402020-03-12012 March 2020
Request for Additional Information - Control Envelope Habitability LAR
ML19192A2222019-07-18018 July 2019
Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19143A0732019-05-29029 May 2019
FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments
ML18242A3642018-08-29029 August 2018
Request for Additional Information (Final) -Steam Generator Technical Specification LAR
ML18102B0852018-04-12012 April 2018
NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver
ML18043A0102018-02-0909 February 2018
NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans
ML18024B3642018-01-24024 January 2018
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2023-05-05
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September 3, 2008 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-BV-SEB-1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
Dear Mr. Sena:
By letter dated August 27, 2007, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54), to renew the operating licenses for Beaver Valley Power Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Mr. Clifford I. Custer of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2989 or by e-mail at Kent.Howard@nrc.gov.
Sincerely,
\RA\
Kent L. Howard, Sr., Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
As stated cc w/encl: See next page
ML082401708 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing KHoward RFranovich DATE 8/29/08 9/3/08 9/3/08
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 3.3-A In license renewal application (LRA) Tables 3.3.2-1, 3.3.2-2, 3.3.2-11 and 3.3.2-12, the applicant has credited the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program, to manage the aging effects of cracking and reduction of heat transfer of stainless steel, aluminum, and copper alloy <15% Zn moisture separators and heat exchangers.
The applicant has described this program in LRA Section B2.22 and stated that it is consistent with the generic aging lessons learned (GALL) aging management program (AMP) XI.M38.
However, the GALL AMP XI.M38 is credited for managing the aging effect of loss of material due to corrosion for steel components only.
(a) Please justify how this program will manage the aging effect of reduction of heat transfer or provide a plant-specific program.
(b) Please justify how this program will manage the aging effect of cracking of moisture separator or provide a plant-specific program.
RAI 3.5-A In LRA Table 3.5.2-36, the applicant states in line 229 that for fire wraps, there is no aging effect requiring management. However, the applicant is proposing to use the Fire Protection Program.
The applicant has referenced footnote 524 for this line item. Footnote 524 states that the Fire Protection (B.2.16) Program supplements aging effects management for fire barrier cable trays, conduits, ductwork and structural members.
Please clarify what you mean by supplements aging effects management, when there is no aging effect requiring management.
RAI 3.2.2.3.2 - 1 In LRA Table 3.2.2.-2, aging management review lines 25 and 36 describe that for reduction of heat transfer, the Water Chemistry Program will be used.
The staff noted that the One-Time Inspection Program is not identified to verify the effectiveness of the Water Chemistry Program in ensuring that the aging effect is being managed.
Explain how verification of the Water Chemistry Program is accomplished to ensure that the aging effect is managed.
RAI B.2.17-2 follow-up In RAI B2.17-2, since the frequency of inspections of fire hydrant gaskets of once every 18 months in the LRA is different than the recommended frequency of once every 12 months in the GALL AMP, the staff asked the applicant to justify why this was not an exception.
In its letter dated July 24, 2008, the applicant stated that although these gaskets perform no license renewal intended function, their condition is monitored by the Fire Water System Program and they are replaced as necessary. However, the frequency of inspection is still different than what the GALL AMP recommends and no justification was provided why this is not an exception.
Please provide justification why this is not an exception.
RAI B.2.17-3 follow-up In RAI B.2.17-3, since the fire hydrant hose hydraulic tests are performed at various frequencies different than the GALL AMP recommended frequency of once every 12 months, the staff asked the applicant to justify why this was not an exception.
In its letter dated July 24, 2008, the applicant responded that fire hoses are consumables, and are routinely tested, inspected, and replaced when necessary. Criteria for inspection and replacement are based on accepted industry standards (e.g.,NFPA-1962). Therefore, while these consumables are within the scope of license renewal, they do not require an aging management review. However, the frequency of hydraulic testing is still different than what the GALL AMP recommends and no justification was provided why this is not an exception.
Please provide justification why this is not an exception.
Letter to P. Sena III from K. Howard, dated September 3, 2008 DISTRIBUTION:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE BEAVER VALLEY POWER STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY:
DLR RF E-MAIL:
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KHoward ESayoc NMorgan MModes, RI PCataldo, RI DWerkheiser, RI
Beaver Valley Power Station, Units 1 and 2 cc:
Joseph J. Hagan Manager, Fleet Licensing President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 Mail Stop A-GO-19 76 South Main Street 76 South Main Street Akron, OH 44308 Akron, OH 44308 Director, Fleet Regulatory Affairs James H. Lash FirstEnergy Nuclear Operating Company Senior Vice President of Operations Mail Stop A-GO-2 and Chief Operating Officer 76 South Main Street FirstEnergy Nuclear Operating Company Akron, OH 44308 Mail Stop A-GO-14 76 South Main Street Manager, Site Regulatory Compliance Akron, OH 44308 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Danny L. Pace Mail Stop A-BV-A Senior Vice President, Fleet Engineering P.O. Box 4, Route 168 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Mail Stop A-GO-14 76 South Main Street Regional Administrator, Region I Akron, OH 44308 U.S. Nuclear Regulatory Commission 475 Allendale Road Jeannie M. Rinckel King of Prussia, PA 19406 Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Resident Inspector Mail Stop A-GO-14 U.S. Nuclear Regulatory Commission 76 South Main Street P.O. Box 298 Akron, OH 44308 Shippingport, PA 15077 Paul A. Harden Cliff Custer Vice President, Nuclear Support FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Steve Dort David W. Jenkins, Attorney FirstEnergy Nuclear Operating Company FirstEnergy Corporation Beaver Valley Power Station Mail Stop A-GO-15 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Mike Banko FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4, Route 168 Shippingport, PA 15077