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| | number = ML16147A284 | | | number = ML16147A284 |
| | issue date = 06/14/2016 | | | issue date = 06/14/2016 |
| | title = Beaver Valley Power Station, Unit 2 - Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections (CAC No. Mf7472) | | | title = Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections |
| | author name = Lamb T A | | | author name = Lamb T |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Richey M L | | | addressee name = Richey M |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000334, 05000412 | | | docket = 05000334, 05000412 |
| | license number = DPR-066, NPF-073 | | | license number = DPR-066, NPF-073 |
| | contact person = Taylor L A, NRR/DORL/LPL1-2, 415-7128 | | | contact person = Taylor L, NRR/DORL/LPL1-2, 415-7128 |
| | case reference number = CAC MF7472 | | | case reference number = CAC MF7472 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 5 | | | page count = 5 |
| | revision = 0 | | | project = CAC:MF7472 |
| | | stage = Other |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 14, 2016 Mr. Marty L. Richey, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 |
| | |
| | ==SUBJECT:== |
| | BEAVER VALLEY POWER STATION, UNIT 2- REQUEST FOR ADDITIONAL INFORMATION REGARDING FALL 2015 REFUELING OUTAGE STEAM GENERATOR TUBE INSPECTIONS (CAC NO. MF7472) |
| | |
| | ==Dear Mr. Richey:== |
| | |
| | By letters dated January 22, 2016, and April 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16025A168 and ML16097A452, respectively), FirstEnergy Nuclear Operating Company submitted information summarizing the results of the fall 2015 steam generator tube inspections at the Beaver Valley Power Station, Unit 2. These inspections were performed during the eighteenth refueling outage. In addition, the U.S. Nuclear Regulatory Commission (NRC) staff summarized information related to the 2015 inspections in a letter dated November 24, 2015 (ADAMS Accession No. ML15320A391 ). |
| | To complete its review, the NRC staff requests a response to the enclosed Request for Additional Information questions. |
| | The draft questions were sent to Mr. Phil Lashley, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Please respond to the enclosed questions within 30 days from the date of this letter. |
| | |
| | M. Richey If you have any questions regarding this matter, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov. |
| | Sincerely, Tay~ect Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/enclosure: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION FALL 2016 STEAM GENERATOR TUBE INSPECTIONS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated January 22, 2016, and April 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16025A168 and ML16097A452, respectively), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections at the Beaver Valley Power Station, Unit 2. These inspections were performed during the eighteenth refueling outage. In addition, the U.S. Nuclear Regulatory Commission (NRC) staff summarized information related to the 2015 inspections in a letter dated November 24, 2015 (ADAMS Accession No. ML15320A391). |
| | In order to complete its review of the documents listed above, the NRC staff requests the following additional information: |
| | Regarding the January 22. 2016. letter: |
| | : 1. On page 3-2, the criteria for identifying dents with indication is described. This process is used for the detection of signals, which could be confirmed as primary water stress corrosion cracking (PWSCC) at tube support plate (TSP) intersections. Please confirm that the voltage screening criteria (greater than or equal to 1.25 volts) were used for the identification of dents and that the detection of PWSCC at both dented and non-dented TSP intersections did not implement a voltage screening criteria (i.e., all PWSCC indications were identified/reported regardless of the signal amplitude). |
| | : 2. The last sentence on page 3-3 states, "The growth during Cycle 18 for all indications was under 0.4 volts." Table 3-4 lists a column titled "Largest Growth, Volts." Please verify that this column lists the size of the indication that experienced the largest voltage growth (and not the largest growth rate experienced at the tube support elevation, since some of the values are greater than 0.4 volts). If not, please clarify. |
| | : 3. Table 3-1 indicates the number of indications not tested with a +Point probe. It does not appear that the larger indications were inspected with a +Point probe. Please discuss how you decided which indications to inspect with a +Point probe (e.g., were indications more likely to exhibit extreme voltage growth selected? If extreme voltage growth is observed, it could result in a flaw exceeding the tube integrity performance criteria). |
| | : 4. In Table 6-1, the "Input" column for Steam Generator (SG) C appears to be missing a value for the 1.3 volt bin. Please clarify. Were 4 indications detected in the 1.3 volt bin? |
| | If so, did your leakage and burst calculations assume there were 6. 7 indications in this bin? |
| | Enclosure |
| | |
| | Regarding the April 6, 2016, letter: |
| | : 5. Please confirm that no degradation was associated with any of the plugs. |
| | : 6. Please identify all tubes with axial or circumferential cracking at freespan dings. What were the sizes of the dings? Were the flaws detected by bobbin and/or rotating probe? |
| | If the flaws were initially only detected with the rotating probe, and the dent/ding signal was close to the inspection threshold (e.g., 1 volt for freespan dings), please discuss why no additional rotating probe inspections below the original inspection threshold were necessary. |
| | : 7. Please identify the tubes with axial outside diameter stress corrosion cracking associated with freespan scratches or gouges at U-bend tangents. How were these indications originally detected (e.g., bobbin and/or rotating probe)? If the flaws were initially only detected with a rotating probe, please discuss whether any sample expansions were performed or why none were necessary. |
| | : 8. Please discuss whether any ligament breach indications were detected and discuss the size/extent of these indications. |
| | : 9. Please confirm that none of the sleeved tubes were plugged. |
| | |
| | ML16147A284 *via memo **via email OFFICE DORL/LPLl-2/PM DORL/LPLl-2/LA DE/ESGB/BC DORL/LPLl-2/BC DORL/LPLl-2/PM NAME GKulesa* DBroaddus** Tlamb Tlamb LRonewicz (REnnis for) |
| | DATE 6/01/2016 5/31/2016 5/16/2016 6/14/2016 6/14/2016}} |
|
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Category:Letter
MONTHYEARML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) IR 05000334/20240102024-08-20020 August 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 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 L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 2024-09-17
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - 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 NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review ML18019A0722018-01-18018 January 2018 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule ML17353A1582017-12-19019 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17352B2612017-12-18018 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17256A2502017-09-13013 September 2017 NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6, ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request ML17031A0362017-02-0303 February 2017 Request for Additional Information Regarding Relief Request Numbers PR6 and PR7 ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16147A2842016-06-14014 June 2016 Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15279A1252015-10-0505 October 2015 Licensed Operator Positive for Fitness-for-Duty-Test ML15181A2142015-07-14014 July 2015 Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055) ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) ML15016A4392015-01-20020 January 2015 Draft Request for Additional Information ML15007A5582015-01-15015 January 2015 Request for Additional Information Steam Generator Inspection Reports 2024-07-17
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 14, 2016 Mr. Marty L. Richey, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 2- REQUEST FOR ADDITIONAL INFORMATION REGARDING FALL 2015 REFUELING OUTAGE STEAM GENERATOR TUBE INSPECTIONS (CAC NO. MF7472)
Dear Mr. Richey:
By letters dated January 22, 2016, and April 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16025A168 and ML16097A452, respectively), FirstEnergy Nuclear Operating Company submitted information summarizing the results of the fall 2015 steam generator tube inspections at the Beaver Valley Power Station, Unit 2. These inspections were performed during the eighteenth refueling outage. In addition, the U.S. Nuclear Regulatory Commission (NRC) staff summarized information related to the 2015 inspections in a letter dated November 24, 2015 (ADAMS Accession No. ML15320A391 ).
To complete its review, the NRC staff requests a response to the enclosed Request for Additional Information questions.
The draft questions were sent to Mr. Phil Lashley, of your staff, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Please respond to the enclosed questions within 30 days from the date of this letter.
M. Richey If you have any questions regarding this matter, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov.
Sincerely, Tay~ect Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION FALL 2016 STEAM GENERATOR TUBE INSPECTIONS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated January 22, 2016, and April 6, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16025A168 and ML16097A452, respectively), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections at the Beaver Valley Power Station, Unit 2. These inspections were performed during the eighteenth refueling outage. In addition, the U.S. Nuclear Regulatory Commission (NRC) staff summarized information related to the 2015 inspections in a letter dated November 24, 2015 (ADAMS Accession No. ML15320A391).
In order to complete its review of the documents listed above, the NRC staff requests the following additional information:
Regarding the January 22. 2016. letter:
- 1. On page 3-2, the criteria for identifying dents with indication is described. This process is used for the detection of signals, which could be confirmed as primary water stress corrosion cracking (PWSCC) at tube support plate (TSP) intersections. Please confirm that the voltage screening criteria (greater than or equal to 1.25 volts) were used for the identification of dents and that the detection of PWSCC at both dented and non-dented TSP intersections did not implement a voltage screening criteria (i.e., all PWSCC indications were identified/reported regardless of the signal amplitude).
- 2. The last sentence on page 3-3 states, "The growth during Cycle 18 for all indications was under 0.4 volts." Table 3-4 lists a column titled "Largest Growth, Volts." Please verify that this column lists the size of the indication that experienced the largest voltage growth (and not the largest growth rate experienced at the tube support elevation, since some of the values are greater than 0.4 volts). If not, please clarify.
- 3. Table 3-1 indicates the number of indications not tested with a +Point probe. It does not appear that the larger indications were inspected with a +Point probe. Please discuss how you decided which indications to inspect with a +Point probe (e.g., were indications more likely to exhibit extreme voltage growth selected? If extreme voltage growth is observed, it could result in a flaw exceeding the tube integrity performance criteria).
- 4. In Table 6-1, the "Input" column for Steam Generator (SG) C appears to be missing a value for the 1.3 volt bin. Please clarify. Were 4 indications detected in the 1.3 volt bin?
If so, did your leakage and burst calculations assume there were 6. 7 indications in this bin?
Enclosure
Regarding the April 6, 2016, letter:
- 5. Please confirm that no degradation was associated with any of the plugs.
- 6. Please identify all tubes with axial or circumferential cracking at freespan dings. What were the sizes of the dings? Were the flaws detected by bobbin and/or rotating probe?
If the flaws were initially only detected with the rotating probe, and the dent/ding signal was close to the inspection threshold (e.g., 1 volt for freespan dings), please discuss why no additional rotating probe inspections below the original inspection threshold were necessary.
- 7. Please identify the tubes with axial outside diameter stress corrosion cracking associated with freespan scratches or gouges at U-bend tangents. How were these indications originally detected (e.g., bobbin and/or rotating probe)? If the flaws were initially only detected with a rotating probe, please discuss whether any sample expansions were performed or why none were necessary.
- 8. Please discuss whether any ligament breach indications were detected and discuss the size/extent of these indications.
- 9. Please confirm that none of the sleeved tubes were plugged.
ML16147A284 *via memo **via email OFFICE DORL/LPLl-2/PM DORL/LPLl-2/LA DE/ESGB/BC DORL/LPLl-2/BC DORL/LPLl-2/PM NAME GKulesa* DBroaddus** Tlamb Tlamb LRonewicz (REnnis for)
DATE 6/01/2016 5/31/2016 5/16/2016 6/14/2016 6/14/2016