|
|
Line 2: |
Line 2: |
| | number = ML11294A013 | | | number = ML11294A013 |
| | issue date = 09/27/2011 | | | issue date = 09/27/2011 |
| | title = 2011/09/27 Davis-Besse Lr - | | | title = Lr - |
| | author name = | | | author name = |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
Latest revision as of 01:06, 6 December 2019
|
---|
Category:E-Mail
MONTHYEARML24274A1482024-09-30030 September 2024 NRR E-mail Capture - Davis-Besse - RAI Re Relief Request L-23-214 ML24221A0082024-08-0707 August 2024 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Remove the Table of Contents from the Technical Specifications ML24204A0012024-07-17017 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 ML24170B0562024-06-18018 June 2024 NRR E-mail Capture - Acceptance Review Results for Davis-Besse, Unit No. 1 - RR-A1 ISI Impracticality 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 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 ML23086B9862023-03-27027 March 2023 NRR E-mail Capture - Davis-Besse, Unit No. 1 - Acceptance Review Results for Davis-Besse, Unit No. 1 - Proposed Alternative Request RP-5 ML23033A0322023-02-0101 February 2023 NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115) ML22266A1102022-09-23023 September 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure ML22164A8572022-06-13013 June 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan ML22118A6862022-04-28028 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML22112A1092022-04-22022 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building ML22090A1692022-03-30030 March 2022 Re_ Action Tracking Item 2022 SST - 335 - Tom Gurdziel, E-mail Re_ Event Number 55734 at Davis Besse, a Matter of Interpretation 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) ML22055B0382022-02-24024 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Upcoming Steam Generator Tube Inservice Inspection ML22055A0872022-02-23023 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3 ML22045A4962022-02-14014 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Emergency Plan ML22040A1832022-02-0707 February 2022 LTR-22-0033 Tom Gurdziel, E-mail Event Number 55734 at Davis Besse, a Matter of Interpretation ML22034A9472022-02-0303 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Revised Review Estimates for Proposed Alternative to Extend the Steam Generator Weld Inspection Interval ML22033A0632022-02-0101 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Revise the Design Basis for the Shield Building Containment Structure ML21321A3792021-11-16016 November 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval 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 ML21287A0382021-10-14014 October 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of Requests for Relief from Certain Inservice Testing Requirements ML21271A1332021-09-28028 September 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of Proposed Alternative RR-A2 for Certain Steam Generator Weld Inspections 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 ML21041A5452021-02-10010 February 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports 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 ML20329A3832020-11-24024 November 2020 NRR E-mail Capture - Davis Besse Nuclear Power Station, Unit No. 1 - Request for an Exemption from the 2020 Force-on-Force Exercises ML20304A2842020-10-29029 October 2020 50.59 Inspection 2nd Request for Information ML20289A0992020-10-0505 October 2020 NRR E-mail Capture - Energy Harbor Fleet, Results of Acceptance Review Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, EPID-l-2020-LLR-0132 ML20281A3692020-10-0505 October 2020 Energy Harbor Fleet, Results of Acceptance Review Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, EPID-l-2020-LLR-0132 ML20239A7942020-08-25025 August 2020 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Incorporation of Applicable Standard in TS 5.2.2.e ML20203M3722020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 and Part 2 ML20203M3712020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force2020-06-23023 June 2020 Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force ML20154K7642020-06-0202 June 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425 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 ML20058D3152020-02-27027 February 2020 Completion of License Transfer for the Beaver Valley, Davis-Besse and Perry Nuclear Units ML20024E0092020-01-23023 January 2020 NRR E-mail Capture - FENOC License Transfer - January 23, 2020 Call Summary ML20021A3162020-01-21021 January 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing ML19346B3972019-12-11011 December 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Acceptance of License Amendment Request to Adopt TSTF-425 ML19273A1132019-09-27027 September 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Acceptance of License Amendment Request to Extend Containment Leakage Rate Test Interval ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML19161A2132019-06-0606 June 2019 NRR E-mail Capture - Results of Acceptance Review - FENOC Fleet - Request for Approval of Request for Approval of Lrradiated Fuel Management Plans, EPID L-2019-LRO-0016 ML19149A6202019-05-29029 May 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Approval of the Decommissioning Quality Assurance Program ML19130A2082019-05-0808 May 2019 Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition 2024-09-30
[Table view] |
Text
Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Tuesday, September 27, 2011 10:05 AM To: dorts@firstenergycorp.com Cc: Davis-BesseHearingFile Resource Attachments: Davis-Besse LRA Supplemental RAIs for 4.7 TLAAs.docx Steve:
Attached are two draft RAIs. Well discuss them next Thursday.
Thanks Samuel Cuadrado de Jesús Project Manager Projects Branch1 Division of License Renewal U.S. Nuclear Regulatory Commission Phone: 301-415-2946 Samuel.CuadradoDeJesus@nrc.gov 1
Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 1576 Mail Envelope Properties (377CB97DD54F0F4FAAC7E9FD88BCA6D0805071A9E0)
Subject:
Sent Date: 9/27/2011 10:05:21 AM Received Date: 9/27/2011 10:05:37 AM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients:
"Davis-BesseHearingFile Resource" <Davis-BesseHearingFile.Resource@nrc.gov>
Tracking Status: None "dorts@firstenergycorp.com" <dorts@firstenergycorp.com>
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 350 9/27/2011 10:05:37 AM Davis-Besse LRA Supplemental RAIs for 4.7 TLAAs.docx 24765 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION, SECTIONS 4.7.3 AND 4.7.4 TIME-LIMITED AGING ANALYSES DAVIS-BESSE NUCLEAR POWER STATION FIRST ENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 LRA Section 4.7.3 - Reactor Vessel (RV) Thermal Shock Due to Borated Water Storage Tank (BWST) Water Injection RAI 4.7.3-1
Background
LRA Section 4.7.3 discusses a fracture mechanics analysis for evaluating the integrity of the RV during the pressurized thermal shock (PTS) event associated with low-temperature (35 ºF) water injection from the BWST following a small steam line break. LRA Section 4.7.3 states that the current licensing basis (CLB) analysis for this event is addressed in the Davis-Besse Updated Safety Analysis Report (USAR), Section 5.2 and that the subject analysis was revised to consider the period of extended operation (52 EFPY).
Issue The staff reviewed USAR Section 5.2 and could not locate the CLB analysis for evaluating RV integrity under the subject PTS conditions. Furthermore, the staff found no references in LRA Section 4.8 for reports documenting the analysis of RV integrity under these PTS conditions for the period of extended operation, based on the 52 EFPY RTPTS values.
Request
- a. Please state the USAR section and page number where the summary of the CLB analysis of the subject PTS event is located. If a summary of the CLB analysis is not located in the USAR, please state where it can be found.
- b. Please provide the reports documenting the projected 52 EFPY analysis of RV integrity under the subject PTS conditions LRA Section 4.7.4 - High Pressure Injection (HPI) / Makeup Nozzle Thermal Sleeves RAI 4.7.4-1
Background
By letter dated June 3, 2011, the applicant provided Amendment 8 to Davis-Besse LRA. LRA Amendment 8 revised the disposition for the analysis of the HPI/Makeup Nozzle Thermal Sleeves in LRA Section 4.7.4 from 10 CFR 54.21(c)(1)(iii) to Not a TLAA. As an explanation for the revised disposition, LRA Section 4.7.4, as amended, now states that [b]ased on the
[USAR Supplement] commitment [to replace the subject thermals sleeves], the HPI/Makeup nozzle thermal sleeves are short-lived (not 40-year) parts and therefore this analysis is not a TLAA. Similarly, LRA Amendment 8 revised the corresponding USAR Supplement section in LRA Section A.2.7.4 to reflect the changed disposition. LRA Section A.2.7.4, as revised by LRA Amendment 8, now states that, [b]ased on the commitment [to replace the subject thermal sleeves], the HPI/makeup nozzle thermal sleeves are short lived (not 40-year) parts and therefore this analysis is not a TLAA. Finally, LRA Section 4.1, Table 4.1-1, was amended per LRA Amendment 8 to state that the evaluation of the subject thermal sleeves is Not a TLAA.
Issue The staff determined that aging of the subject thermal sleeves, as discussed in LRA Section 4.7.4, should be identified as a TLAA in LRA Sections 4.1, 4.7.4, and the USAR Supplement, because the aging mechanism is time dependent (i.e., it is dependent on the number of transient cycles incurred), and the staff cannot accept future commitments to replace components as a means for disposition of the currently-installed components undergoing time-dependent aging processes, without a TLAA of the currently-installed components.
Request Request Based on the above, the staff requests that the applicant amend LRA Sections 4.1, 4.7.4, and A.2.7.4 to identify HPI/makeup thermal sleeve aging as a TLAA. The staff also requests that the applicant select an appropriate disposition under 10 CFR 54.21(c)(1). If the applicant proposes a 10 CFR 54.21(c)(1)(iii) disposition for this analysis, then the staff requests that the applicant amend LRA Sections 4.7.4 and A.2.7.4 to propose an appropriate aging management program (AMP) for managing the effects of aging on the intended function of the thermal sleeves. Any AMP identified in LRA Sections 4.7.4 and A.2.7.4 for a 10 CFR 54.21(c)(1)(iii) disposition of this analysis should ensure that the effects of aging on the subject thermal sleeves are appropriately managed for the period of extended operation.