|
---|
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-Besses 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: Thursday, June 16, 2011 9:04 AM To: 'dorts@firstenergycorp.com' Cc: 'custerc@firstenergycorp.com'; Medoff, James
Subject:
RE: Today's Conference Call with Davis Besse Steve Below are the topics our staff will be discussing during the conference call today. Please forward it to your team.
- 1) Discuss absence of a TLAA on their bases for non-Class 1, non-piping components.
- 2) Discuss extension of the scope of RAI 4.1-2 to both the time-dependent J-integral analysis in and the time-dependent fatigue flaw growth analysis in Structural Integrity Associates (SIA) Topical Report No.
SIR-99-040, Revision 1, "ASME Code Case N-481 of Davis Besse Reactor Coolant Pumps." (ADAMS Accession No. ML011200090). The scope of the RAI, as issued, only talked about the fatigue flaw growth analysis in the Report, which forms the basis for applying VT-1 or EVT-1 visual examinations of the outside surfaces of the reactor coolant pump (RCP) casing welds in lieu of the UT examinations that would be required by the ASME Section XI Code of Record. There is a possibility, that 10 CFR 50.55a made them update to a more recent edition of the ASME Section XI Code that has incorporated the visual examinations requirements for the pump casings. If this is the case we need to know whether their CLB is still relying on the SIA report in support using the visual methods cited in the updated ASME Section XI Code of Record.
- 3) Discuss their UFSAR Appendix 5A design basis for RCP flywheel integrity - we agree that the RTndt analysis for the flywheels in that appendix does not need to include a time-dependent neutron fluence-based RTndt adjustment in the manner that they are included in the RTndt analyses for the reactor vessel beltline components (i.e. beltline base metals and weld components). However, USFAR Appendix 5A states that the SRP 5.4.1.1 acceptance basis is an 80ºF difference basis between the RTndt value and the operating temperature (which according to the UFSAR Appendix, puts the minimum 120ºF operating temperature for them). Contrary to this statement, we determined that the SRP 5.4.1.1 states (recommends) that the difference between the RTndt value and the operating temperature should be at least 100ºF, which for full conformance with the SRP basis would dictate a minimum operating temperature of 140 ºF for the RCP flywheels at Davis Besse. The UFSAR Section 5A also states that Section 3.1 of the UFSAR gives the 120 ºF operating temperature basis for the flywheels, but we could not find any such basis in UFSAR Section 3.1. The other thing we need to inform them is that SRP 5.4.1.1 on flywheel integrity (which they use as the UFSAR Appendix 5A basis) states that the RTndt values for the RCP flywheel plate will be based on actual drop-weight testing results; however, they establish the RTndt value for the SA-533 flywheel plates materials using generic application of the RTndt values for their SA-533 plate materials for the RV beltline materials (pick 40ºF as the highest value. We are aware that this is a current licensing basis issue - thus no RAI will be issued.
- 4) DCI/CVIB will discuss aging management of reactor vessel internal (RVI) components with them, with Seung Mins (DLR) participation on CASS AMRs for RVI components. Chris Sydnor is DCI/CVIBs lead review. Ganesh Cheruvenki may attend. The discrepancy between the Technical Specification 5.5.4 inspection requirements for their RVI vent valve discs and their plant-specific PWR Vessel Internals Program criteria are among one matter that needs to be discussed with them. The other is on the adequacy of the AMRs for the RVI components.
1
The call will be held at 1:00 PM EDT, 12 noon CDT and 10:00 PDT.
The phone number and pass code for the conference call are:
Phone Number: 877-917-9488 Participant passcode: 60937 2
Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 134 Mail Envelope Properties (Samuel.CuadradoDeJesus@nrc.gov20110616090300)
Subject:
RE: Today's Conference Call with Davis Besse Sent Date: 6/16/2011 9:03:44 AM Received Date: 6/16/2011 9:03:00 AM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients:
"'custerc@firstenergycorp.com'" <custerc@firstenergycorp.com>
Tracking Status: None "Medoff, James" <James.Medoff@nrc.gov>
Tracking Status: None
"'dorts@firstenergycorp.com'" <dorts@firstenergycorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3741 6/16/2011 9:03:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: