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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 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 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 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 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 ML20203M3712020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 ML20203M3722020-07-21021 July 2020 Ultimate Heat Sink Request for Information Part 1 and Part 2 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 ML19106A2512019-04-16016 April 2019 NRR E-mail Capture - Davis-Besse - Proposed License Condition and Draft Safety Evaluation for the License Amendment Request to Adopt NFPA 805 ML19073A1112019-03-14014 March 2019 NRR E-mail Capture - Davis-Besse - Acceptance of License Amendment Request for Permanently Defueled License and Technical Specifications 2024-07-17
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I1 r are E 1 3 :Gul- D -af-8ese Safety Significance Telecon __ _ _ _
From: Douglas Pickett ' '
To: DB Daily Call; DB0350; Wallace Norris Date: 5129102 12:35PM
Subject:
Davis-Besse Safety Significance Telecon To all:
to We have scheduled a telecon with the Davis-Besse licensee for Thursday, May 30, at 1:00 p.m.Is to better discuss the attached questions concerning the Safety Significance Assessment The purpose I have understand the differences between the licensee's and our contractor's calculated failure pressure.
reserved room 13B4 for headquarters personnel from 1:00 to 3:00 p.m.
We will use the usual conference bridge (301-231-5539 or 800-838-8081) witlascode _ J Information in this record was deleted in accordance with the Freedom of Information Act, exemptions FOIA- -2=s 3-00 IY
b--*
SAFETY SIGNIFICANCE NRC STAFF COMMENTS AND QUESTIONS ON DAVIS-BESSEAPRIL 8, 2002 ASSESSMENT (SIA-W-DB-1IQ-301) SUBMITTED FAILURE CRITERION exceeding 11.15%) used to (1) What Is the technical basis of the failure criterion (e.g., strain specific technical determine the failure conditions of the cladding layer? Provide used in this evaluation.
references in the literature that support the failure criterion in a uniaxial tensile test)
(2) How does the failure criterion (e.g., based on ultimate strain triaxial loading in the cladding account for the effects of biaxial loading in the cladding, or at the edges of the degradation cavity?
the minimum cross-(3) The failure criterion applied in SIA report W-DB-1 Q-301 (e.g.,the strain levels in the sectional strain exceeding the failure strain of 11.15%) allows thickness, leading to very the cladding to exceed the critical strain value entirely through 5 of the SIA report. What large strains at the surface of the cladding, up to 49% in Table average cross-sectional strain, is the technical basis for this approach, as opposed to the or the maximum cross-sectional strain?
to give guidance of the failure (4) Did you explore a continuum damage mechanics analysis growth starts? If criterion once the strains exceed the critical strain where neckinghoid mechanics analysis.
damage not, provide the technical basis for not using a continuum level Is exceeded, so the
[Poisson's ratio of 0.5 no longer applies once this critical strain changing as the voids grow analysis is strictly not valid. (Poisson's ratio is continuously stress redistribution that is at the strains beyond the start of necking.) This results in a not accounted for in a standard elastic-plastic analysis.]
was assumed to be (5) How would the strain values change if the stress free temperature accounted for the the stress relief temperature instead'of 700F, and the analysisat the operating differential thermal expansion of the cladding and head steel temperature of 605OF?
GEOMETRYIMESHING the cladding thickness to (A) Does the size of the degradation cavity and the transition from knowledge regarding the head thickness that was used in the SIA report reflect current In Figure 13 on page 103 the cavity geometry, In particular the undercut area described dated April 15, 2002?
of the Davis-Besse Root Cause Analysis Report (CR2002-0891),
What Isthe transition geometry assumed in the analyses?
to adequately capture (B) Is there sufficient mesh refinement through the cladding thickness any sensitivity studies the bending and shear strains at the edge of the cavity? Describe used to demonstrate the adequacy of the mesh refinement thickness (C) Was the cladding deposited by weld wire? Do the thinner cladding toes? In what direction of weld bead measurements from UT coincide with the locations the degradation cavity?
do the cladding weld beads run relative to the long axis of