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| | number = ML18019A072 | | | number = ML18019A072 |
| | issue date = 01/18/2018 | | | issue date = 01/18/2018 |
| | title = 2018/01/18 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024) | | | title = NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule |
| | author name = Venkataraman B | | | author name = Venkataraman B |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Lashley P H | | | addressee name = Lashley P |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000334, 05000412 | | | docket = 05000334, 05000412 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-DMPSPEm Resource From:Venkataraman, Booma Sent:Thursday, January 18, 2018 4:35 PM To:Lashley, Phil H. | | {{#Wiki_filter:NRR-DMPSPEm Resource From: Venkataraman, Booma Sent: Thursday, January 18, 2018 4:35 PM To: Lashley, Phil H. |
| Cc:Danna, James | | Cc: Danna, James |
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| ==Subject:== | | ==Subject:== |
| Beaver Valley Unit No. 1: Request for Addi tional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Wi thdrawal Schedule (EPID: L-2017-LLL-0024) | | Beaver Valley Unit No. 1: Request for Additional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024) |
| Attachments: | | Attachments: Request For Additional Information Beaver Valley 1 RTPTS approval.docx Expires: Monday, March 19, 2018 12:00 AM Mr. Lashley, By letter dated October 6, 2017 (Agencywide Documents Access and Management System Accession No. ML17284A195), FirstEnergy Nuclear Operating Company (FENOC, the licensee), in accordance with 10 CFR 50.61(b)(1) and 10 CFR 50.61(c)(3), submitted a request for approval of the modified pressurized thermal shock reference temperature values (RTPTS) for Beaver Valley Power Station (Beaver Valley), Unit No. 1, reactor vessel beltline and extended beltline region materials. In accordance with the surveillance criteria of 10 CFR 50, Appendix H, Section III.B.3, FENOC also requested approval of the proposed changes to Beaver Valley Unit No. 1 reactor vessel material irradiation surveillance capsule withdrawal schedule in the letter. |
| Request For Additional Information Beaver Valley 1 RTPTS approval.docx Expires:Monday, March 19, 2018 12:00 AMMr. Lashley, By letter dated October 6, 2017 (Agencywide Documents Access and Management System Accession No. ML17284A195), FirstEnergy Nuclear Operating Company (FENOC, the licensee), in accordance with 10 CFR 50.61(b)(1) and 10 CFR 50.61(c)(3), submitted a request for approval of the modified pressurized thermal shock reference temperature values (RTPTS) for Beaver Valley Power Station (Beaver Valley), Unit No. 1, reactor vessel beltline and extended beltline region materials. In accordance with the surveillance criteria of 10 CFR 50, Appendix H, Section III.B.3, FENOC also requested approval of the proposed changes to Beaver Valley Unit No. 1 reactor vessel material irradiation surveill ance capsule withdrawal schedule in the letter. | |
| A draft request for information (RAI) was sent to you on January 9, 2018. You indicated by phone on January 16, 2018, that no clarification call is needed. Further you requested a RAI response period of 90 days due to additional time it will take for you to revise certain calculations. The final RAI is attached to this e-mail. The NRC agrees to your request and requests FENOC to respond to the attached RAI with a supplement by April 18, 2018. | | A draft request for information (RAI) was sent to you on January 9, 2018. You indicated by phone on January 16, 2018, that no clarification call is needed. Further you requested a RAI response period of 90 days due to additional time it will take for you to revise certain calculations. The final RAI is attached to this e-mail. The NRC agrees to your request and requests FENOC to respond to the attached RAI with a supplement by April 18, 2018. |
| Please treat this e-mail as transmittal of formal RAIs. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2934 or via email at Booma.Venkataraman@nrc.gov | | Please treat this e-mail as transmittal of formal RAIs. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2934 or via email at Booma.Venkataraman@nrc.gov. |
| . Sincerely, Booma, Booma Venkataraman, P.E. Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934
| | Sincerely, Booma, Booma Venkataraman, P.E. |
| | Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934 1 |
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| Hearing Identifier: NRR_DMPS Email Number: 104 Mail Envelope Properties (Booma.Venkataraman@nrc.gov20180118163400) | | Hearing Identifier: NRR_DMPS Email Number: 104 Mail Envelope Properties (Booma.Venkataraman@nrc.gov20180118163400) |
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| ==Subject:== | | ==Subject:== |
| Beaver Valley Unit No. 1: Request for Additional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024) Sent Date: 1/18/2018 4:34:49 PM Received Date: 1/18/2018 4:34:00 PM From: Venkataraman, Booma Created By: Booma.Venkataraman@nrc.gov Recipients: "Danna, James" <James.Danna@nrc.gov> Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 1628 1/18/2018 4:34:00 PM Request For Additional Information Beaver Valley 1 RTPTS approval.docx 30648 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: 3/19/2018 Recipients Received: | | Beaver Valley Unit No. 1: Request for Additional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024) |
| 1 REQUEST FOR ADDITIONAL INFORMATION MODIFIED PRESSURIZED THERMAL SHOCK REFERENCE VALUES AND SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 By letter dated October 6, 2017 (Ref. 1), pursuant to 10 CFR 50.61(b)(1) and (c)(3), FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested approval of modified pressurized thermal shock reference temperature (RT PTS) values for Beaver Valley Power Station (Beaver Valley), Unit No. 1, and reactor vessel materials for the period of extended operation. This submittal also requested approval of a modified reactor vessel surveillance capsule withdrawal schedule pursuant to 10 CFR 50, Appendix H, Section Ill, Paragraph 8.3.
| | Sent Date: 1/18/2018 4:34:49 PM Received Date: 1/18/2018 4:34:00 PM From: Venkataraman, Booma Created By: Booma.Venkataraman@nrc.gov Recipients: |
| RAI 1 The pressurized thermal shock (PTS) evaluation for Beaver Valley Unit No. 1, is contained in Appendix E to WCAP-18102-NP, Revision 0, "Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," which is Enclosure C of the licensee's submittal (Ref. 1).
| | "Danna, James" <James.Danna@nrc.gov> |
| | Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 1628 1/18/2018 4:34:00 PM Request For Additional Information Beaver Valley 1 RTPTS approval.docx 30648 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: 3/19/2018 Recipients Received: |
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| With regard to determination of the RT PTS values, Appendix E cited U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, "Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels," Office of Nuclear Regulatory Research [RES], dated November 14, 2014 (Ref. 2) as a basis for not considering the shift due to irradiation for reactor pressure vessel (RPV) materials for which the predicted shift in the reference temperature (RTNDT) is less than 25 degrees Fahrenheit (
| | REQUEST FOR ADDITIONAL INFORMATION MODIFIED PRESSURIZED THERMAL SHOCK REFERENCE VALUES AND SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 By letter dated October 6, 2017 (Ref. 1), pursuant to 10 CFR 50.61(b)(1) and (c)(3), FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested approval of modified pressurized thermal shock reference temperature (RTPTS) values for Beaver Valley Power Station (Beaver Valley), Unit No. 1, and reactor vessel materials for the period of extended operation. This submittal also requested approval of a modified reactor vessel surveillance capsule withdrawal schedule pursuant to 10 CFR 50, Appendix H, Section Ill, Paragraph 8.3. |
| ° F). Section 4 of TLR-RES/DE/CIB-013-01 concluded that:
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| : 1. The beltline is defined as the region of the RPV adjacent to the reactor core that is projected to receive a neutron fluence level of 1xl0 17 n/cm2 [neutrons per square centimeter] (E > 1.0 MeV [
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| energy > 1 megaelectronvolt]) or higher at the end of the licensed operating period.
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| : 2. Embrittlement effects may be neglected for any region of the RPV if either of the following conditions are met: (1) neutron fluence is less than 1x10 17 n/cm2 (E > 1.0 MeV) at EOL, or (2) the mean value of T30 estimated using an ETC acceptable to the staff is less than 25°F at EOL. The estimate of T30 at EOL shall be made using best-estimate chemistry values Using this basis, the licensee did not add a shift due to irradiation for several beltline materials, including the reactor pressure vessel inlet and outlet nozzles, the inlet and outlet nozzle-to-vessel welds, and certain weld metal heats used in the upper shell-to-intermediate shell girth weld.
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| 2 Discounting the shift in RT NDT due to irradiation if the predicted shift is less than 25 | | ===RAI 1=== |
| °F does not meet the NRC regulation in 10 CFR 50.61. 10 CFR 50.61 (a)(4) states that for the reactor | | The pressurized thermal shock (PTS) evaluation for Beaver Valley Unit No. 1, is contained in Appendix E to WCAP-18102-NP, Revision 0, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," which is Enclosure C of the licensees submittal (Ref. 1). |
| | With regard to determination of the RTPTS values, Appendix E cited U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, "Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels," Office of Nuclear Regulatory Research [RES], dated November 14, 2014 (Ref. 2) as a basis for not considering the shift due to irradiation for reactor pressure vessel (RPV) materials for which the predicted shift in the reference temperature (RTNDT) is less than 25 degrees Fahrenheit (° F). Section 4 of TLR-RES/DE/CIB-013-01 concluded that: |
| | : 1. The beltline is defined as the region of the RPV adjacent to the reactor core that is projected to receive a neutron fluence level of 1xl017 n/cm2 [neutrons per square centimeter] (E > 1.0 MeV [energy > 1 megaelectronvolt]) or higher at the end of the licensed operating period. |
| | : 2. Embrittlement effects may be neglected for any region of the RPV if either of the following conditions are met: (1) neutron fluence is less than 1x1017 n/cm2 (E > 1.0 MeV) at EOL, or (2) the mean value of T30 estimated using an ETC acceptable to the staff is less than 25°F at EOL. The estimate of T30 at EOL shall be made using best-estimate chemistry values Using this basis, the licensee did not add a shift due to irradiation for several beltline materials, including the reactor pressure vessel inlet and outlet nozzles, the inlet and outlet nozzle-to-vessel welds, and certain weld metal heats used in the upper shell-to-intermediate shell girth weld. |
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| vessel beltline materials, RT NDT must account for the effects of neutron radiation. | | Discounting the shift in RTNDT due to irradiation if the predicted shift is less than 25 °F does not meet the NRC regulation in 10 CFR 50.61. 10 CFR 50.61 (a)(4) states that for the reactor vessel beltline materials, RTNDT must account for the effects of neutron radiation. |
| 10 CFR 50.61(c) details how RTNDT must be calculated. The staff notes that RIS 2014-11, "Information On Licensing Applications For Fracture Toughness Requirements For Ferritic Reactor Coolant Pressure Boundary Components," (Ref. 3) clarifies that the 10 CFR 50 Appendix G and 10 CFR 50 Appendix H define the beltline as including all RPV materials that will receive a neutron fluence greater than or equal to 1x10 17 n/cm2 (E> 1 MeV). | | 10 CFR 50.61(c) details how RTNDT must be calculated. The staff notes that RIS 2014-11, Information On Licensing Applications For Fracture Toughness Requirements For Ferritic Reactor Coolant Pressure Boundary Components, (Ref. 3) clarifies that the 10 CFR 50 Appendix G and 10 CFR 50 Appendix H define the beltline as including all RPV materials that will receive a neutron fluence greater than or equal to 1x1017 n/cm2 (E> 1 MeV). |
| The staff also notes that TLR-RES/DE/CIB-2013-01 is not NRC guidance, and the recommendation that the shift due to irradiation can be discounted if it is less than 25 | | The staff also notes that TLR-RES/DE/CIB-2013-01 is not NRC guidance, and the recommendation that the shift due to irradiation can be discounted if it is less than 25 °F is not endorsed in any NRC guidance document or regulation. Therefore, to apply the recommendation of the TLR that the shift in RTNDT may be discounted if it is less than 25 °F, the licensee would need to submit a request for exemption accompanied by a detailed technical basis. The staff therefore requests that, unless it plans to submit an exemption, the licensee: |
| °F is not endorsed in any NRC guidance document or regulation. Therefore, to apply the recommendation of the TLR that the shift in RTNDT may be discounted if it is less than 25 | | : 1. Revise its PTS evaluation to include RTPTS values for all RPV beltline and extended beltline materials calculated in accordance with 10 CFR 50.61. |
| °F, the licensee would need to submit a request for exemption accompanied by a detailed technical basis. The staff therefore requests that, unless it plans to submit an exemption, the licensee: | | : 2. Revise its submittal to remove the reference to TLR-RES/DE/CIB-2013-01. |
| : 1. Revise its PTS evaluation to include RT PTS values for all RPV beltline and extended beltline materials calculated in accordance with 10 CFR 50.61. 2. Revise its submittal to remove the reference to TLR-RES/DE/CIB-2013-01. | | References |
| References | | : 1. Beaver Valley, Unit 1 - Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule, October 6, 2017 (ADAMS Accession No. ML17284A195) |
| : 1. Beaver Valley, Unit 1 - Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule, October 6, 2017 (ADAMS Accession No. ML17284A195) 2. U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, "Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels," Office of Nuclear Regulatory Research [RES], dated November 14, 2014. (ADAMS Accession No. ML14318A177) 3. NRC Regulatory Issue Summary 2014-11, "Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components." October 14, 2017 (ADAMS Accession No. ML14149A165)}} | | : 2. U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels, Office of Nuclear Regulatory Research |
| | [RES], dated November 14, 2014. (ADAMS Accession No. ML14318A177) |
| | : 3. NRC Regulatory Issue Summary 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components. October 14, 2017 (ADAMS Accession No. ML14149A165) 2}} |
Letter Sequence RAI |
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MONTHYEARML17307A2422017-11-0303 November 2017
NRR E-mail Capture - Acceptance Review: Beaver Valley Power Station Unit No. 1: Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule
Project stage: Acceptance 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
Project stage: RAI
ML18099A1232018-04-0606 April 2018
Response to Request for Additional Information Regarding Request to Modify Rtpts Values
Project stage: Response to RAI
2018-01-18
[Table View] |
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Category:E-Mail
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
ML24144A1082024-05-22022 May 2024
Acceptance Review Adoption of TSTF-569, Revise Response Time Testing Definition (EPID L-2024-LLA-0059) - Email
ML24061A1002024-03-29029 March 2024
Energy Harbor Fleet- Closing of Transaction Between Vistra Operations Company LLC and Energy Harbor Nuclear Corporation (Email)
ML24080A3922024-03-20020 March 2024
NRR E-mail Capture - Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Power Station Unit No. 1, and Perry Nuclear Power Plant, Unit No. - Acceptance of Requested Licensing Action Exemption for Final Safety Analysis Report Update
ML23129A3122023-05-0909 May 2023
NRR E-mail Capture - Beaver Valley Unit 2 - Verbal Authorization of Alternative Request, 2-TYP-4-RV-06
ML23128A1612023-05-0808 May 2023
NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing
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
ML23089A1252023-03-30030 March 2023
NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection
ML23079A1202023-03-20020 March 2023
NRR E-mail Capture - Acceptance Review for Beaver Valley 1 & 2 Exemption from Specific Provisions in 10 CFR 50 Appendix H
ML23065A0782023-03-0303 March 2023
Final RAIs Regarding the Beaver Valley Emergency LAR (EPID L-2023-LLA-002) - Email
ML22321A2392022-11-17017 November 2022
NRR E-mail Capture - (External_Sender) Beaver Valley Power Station, Units 1&2 - Clarification on LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
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
ML22273A1132022-09-30030 September 2022
NRR E-mail Capture - Acceptance of Requested Licensing Action to Add Full Spectrum LOCA Methodology to COLR
ML22277A5122022-09-19019 September 2022
NRR E-mail Capture - (External_Sender) Eh Response to Corrected SE Associated with Beaver Valley Amendments 315 and 205 Changes to the EPP
ML22238A2812022-08-25025 August 2022
Request for Additional Information for Beaver Valley Unit 2 - 2R22 Steam Generator 180 Day Report
ML22202A4642022-06-29029 June 2022
Emergency Plan Safety Evaluation
ML22178A1322022-06-24024 June 2022
Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage
ML22173A0402022-06-21021 June 2022
NRR E-mail Capture - Acceptance of Requested Licensing Action Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML22147A0392022-05-27027 May 2022
NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley, Units 1 & 2 Amendment - Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Separation Instrumentation
ML22129A0122022-05-0606 May 2022
NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Unit 2 Amendment - Correct TS 3.1.7 Change Made by TSTF-547
ML22123A0232022-05-0202 May 2022
NRR E-mail Capture - Acceptance of Requested Licensing Action for Beaver Valley Power Station, Units 1 and 2 - Adoption of TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML22153A5212022-04-15015 April 2022
Email Error in Energy Harbor Submittal and Associated SE for Beaver Valley 1 & 2 - Containment Isolation Valve Relief Request
ML22101A0122022-04-0808 April 2022
NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR)
ML22087A1302022-03-28028 March 2022
NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Adopt TSTF-577
ML22080A2512022-03-18018 March 2022
NRR E-mail Capture - (External_Sender) ASME OM Code Case OMN-27, Alternative Requirements for Testing Category a Valves (Non- Piv/Civ)
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
ML21344A0392021-12-0909 December 2021
NRR E-mail Capture - Beaver Valley TSTF-577-A Acceptance Review
ML21321A3782021-11-16016 November 2021
NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193
ML21286A7892021-10-0707 October 2021
NRR E-mail Capture - Beaver Valley Acceptance Review for LAR Regarding TS 3.1.7.2 to Correct a Logic Error (L-2021-LLA-0160)
ML21266A2222021-09-23023 September 2021
NRR E-mail Capture - Beaver Valley Loss of Power Diesel Generator Start and Bus Separation Instrument
ML21259A1642021-09-16016 September 2021
NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits
ML21225A0362021-08-12012 August 2021
NRR E-mail Capture - Beaver Valley Unit Nos. 1 and 2 - Acceptance Review Determination Emergency Plan Amendment Request
ML21197A0242021-07-15015 July 2021
NRR E-mail Capture - Beaver Valley No. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Emergency Plan Amendment Request
ML21137A0082021-05-14014 May 2021
Acceptance of License Amendment Request: Beaver Valley COLR TS LAR
ML21119A2152021-04-28028 April 2021
NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27
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
ML21032A2582021-02-0101 February 2021
Acceptance of License Amendment Request: Beaver Valley Steam Generator Inspection Deferral
ML21015A5762021-01-14014 January 2021
Final RAIs for Steam Generator 180 Day Tube Inspection Report
ML21014A1142021-01-12012 January 2021
Correction Letter Notification from Licensee
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
ML20329A4562020-11-24024 November 2020
Acceptance of License Amendment Request: Beaver Valley RCS and PTLR TS Changes
ML20325A2312020-11-20020 November 2020
Request for Additional Information - Beaver Valley Request for Exemption - Part 73 Force-on-Force Exemption
ML20324A0872020-11-19019 November 2020
Acceptance of Requested Licensing Action: Beaver Valley Unit 2 Capsule Pull
ML20323A0452020-11-17017 November 2020
2.206 Petition
2024-07-17
[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
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Draft Request for Additional Information - Steam Generator Letter
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NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
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ML15320A4132015-11-24024 November 2015
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ML15125A4162015-05-11011 May 2015
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ML15016A4392015-01-20020 January 2015
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Request for Additional Information Steam Generator Inspection Reports
2024-07-17
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Text
NRR-DMPSPEm Resource From: Venkataraman, Booma Sent: Thursday, January 18, 2018 4:35 PM To: Lashley, Phil H.
Cc: Danna, James
Subject:
Beaver Valley Unit No. 1: Request for Additional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024)
Attachments: Request For Additional Information Beaver Valley 1 RTPTS approval.docx Expires: Monday, March 19, 2018 12:00 AM Mr. Lashley, By letter dated October 6, 2017 (Agencywide Documents Access and Management System Accession No. ML17284A195), FirstEnergy Nuclear Operating Company (FENOC, the licensee), in accordance with 10 CFR 50.61(b)(1) and 10 CFR 50.61(c)(3), submitted a request for approval of the modified pressurized thermal shock reference temperature values (RTPTS) for Beaver Valley Power Station (Beaver Valley), Unit No. 1, reactor vessel beltline and extended beltline region materials. In accordance with the surveillance criteria of 10 CFR 50, Appendix H, Section III.B.3, FENOC also requested approval of the proposed changes to Beaver Valley Unit No. 1 reactor vessel material irradiation surveillance capsule withdrawal schedule in the letter.
A draft request for information (RAI) was sent to you on January 9, 2018. You indicated by phone on January 16, 2018, that no clarification call is needed. Further you requested a RAI response period of 90 days due to additional time it will take for you to revise certain calculations. The final RAI is attached to this e-mail. The NRC agrees to your request and requests FENOC to respond to the attached RAI with a supplement by April 18, 2018.
Please treat this e-mail as transmittal of formal RAIs. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2934 or via email at Booma.Venkataraman@nrc.gov.
Sincerely, Booma, Booma Venkataraman, P.E.
Project Manager, NRR/DORL/LPL1 Office of Nuclear Reactor Regulation Booma.Venkataraman@nrc.gov 301.415.2934 1
Hearing Identifier: NRR_DMPS Email Number: 104 Mail Envelope Properties (Booma.Venkataraman@nrc.gov20180118163400)
Subject:
Beaver Valley Unit No. 1: Request for Additional Information - Modified RTPTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule (EPID: L-2017-LLL-0024)
Sent Date: 1/18/2018 4:34:49 PM Received Date: 1/18/2018 4:34:00 PM From: Venkataraman, Booma Created By: Booma.Venkataraman@nrc.gov Recipients:
"Danna, James" <James.Danna@nrc.gov>
Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1628 1/18/2018 4:34:00 PM Request For Additional Information Beaver Valley 1 RTPTS approval.docx 30648 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: 3/19/2018 Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION MODIFIED PRESSURIZED THERMAL SHOCK REFERENCE VALUES AND SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 By letter dated October 6, 2017 (Ref. 1), pursuant to 10 CFR 50.61(b)(1) and (c)(3), FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested approval of modified pressurized thermal shock reference temperature (RTPTS) values for Beaver Valley Power Station (Beaver Valley), Unit No. 1, and reactor vessel materials for the period of extended operation. This submittal also requested approval of a modified reactor vessel surveillance capsule withdrawal schedule pursuant to 10 CFR 50, Appendix H, Section Ill, Paragraph 8.3.
RAI 1
The pressurized thermal shock (PTS) evaluation for Beaver Valley Unit No. 1, is contained in Appendix E to WCAP-18102-NP, Revision 0, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," which is Enclosure C of the licensees submittal (Ref. 1).
With regard to determination of the RTPTS values, Appendix E cited U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, "Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels," Office of Nuclear Regulatory Research [RES], dated November 14, 2014 (Ref. 2) as a basis for not considering the shift due to irradiation for reactor pressure vessel (RPV) materials for which the predicted shift in the reference temperature (RTNDT) is less than 25 degrees Fahrenheit (° F). Section 4 of TLR-RES/DE/CIB-013-01 concluded that:
- 1. The beltline is defined as the region of the RPV adjacent to the reactor core that is projected to receive a neutron fluence level of 1xl017 n/cm2 [neutrons per square centimeter] (E > 1.0 MeV [energy > 1 megaelectronvolt]) or higher at the end of the licensed operating period.
- 2. Embrittlement effects may be neglected for any region of the RPV if either of the following conditions are met: (1) neutron fluence is less than 1x1017 n/cm2 (E > 1.0 MeV) at EOL, or (2) the mean value of T30 estimated using an ETC acceptable to the staff is less than 25°F at EOL. The estimate of T30 at EOL shall be made using best-estimate chemistry values Using this basis, the licensee did not add a shift due to irradiation for several beltline materials, including the reactor pressure vessel inlet and outlet nozzles, the inlet and outlet nozzle-to-vessel welds, and certain weld metal heats used in the upper shell-to-intermediate shell girth weld.
1
Discounting the shift in RTNDT due to irradiation if the predicted shift is less than 25 °F does not meet the NRC regulation in 10 CFR 50.61. 10 CFR 50.61 (a)(4) states that for the reactor vessel beltline materials, RTNDT must account for the effects of neutron radiation.
10 CFR 50.61(c) details how RTNDT must be calculated. The staff notes that RIS 2014-11, Information On Licensing Applications For Fracture Toughness Requirements For Ferritic Reactor Coolant Pressure Boundary Components, (Ref. 3) clarifies that the 10 CFR 50 Appendix G and 10 CFR 50 Appendix H define the beltline as including all RPV materials that will receive a neutron fluence greater than or equal to 1x1017 n/cm2 (E> 1 MeV).
The staff also notes that TLR-RES/DE/CIB-2013-01 is not NRC guidance, and the recommendation that the shift due to irradiation can be discounted if it is less than 25 °F is not endorsed in any NRC guidance document or regulation. Therefore, to apply the recommendation of the TLR that the shift in RTNDT may be discounted if it is less than 25 °F, the licensee would need to submit a request for exemption accompanied by a detailed technical basis. The staff therefore requests that, unless it plans to submit an exemption, the licensee:
- 1. Revise its PTS evaluation to include RTPTS values for all RPV beltline and extended beltline materials calculated in accordance with 10 CFR 50.61.
- 2. Revise its submittal to remove the reference to TLR-RES/DE/CIB-2013-01.
References
- 1. Beaver Valley, Unit 1 - Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule, October 6, 2017 (ADAMS Accession No. ML17284A195)
- 2. U.S. NRC Technical Letter Report TLR-RES/DE/CIB-2013-01, Evaluation of the Beltline Region for Nuclear Reactor Pressure Vessels, Office of Nuclear Regulatory Research
[RES], dated November 14, 2014. (ADAMS Accession No. ML14318A177)
- 3. NRC Regulatory Issue Summary 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components. October 14, 2017 (ADAMS Accession No. ML14149A165) 2