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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 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 ML19043A6962019-02-0808 February 2019 NRR E-mail Capture - Davis-Besse License Amendment Request for the Post-Shutdown Emergency Plan ML18320A1272018-11-16016 November 2018 NRR E-mail Capture - Davis-Besse LAR to Change TS Definitions and Administrative Controls for Permanently Defueled Conditions 2024-07-17
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CuadradoDeJesus, Samuel From: Sheikh, Abdul Sent: Tuesday, December 13, 2011 5:09 PM To: Lehman, Bryce; Auluck, Rajender Cc: CuadradoDeJesus, Samuel
Subject:
RE: Davis Besse Shield Building RAI Attachments:
DB Containment Crack RAI-abdul.DOC I have added request for some specific information on the attached file. Some of the information I have requested is the gray area of part 50/54. However, I feel it is better to ask it since such information has not been formally requested previously by the NRC.From: Lehman, Bryce .~,.-. .....Sent: Tuesday, December 13, 2011 3:52 PM To: Sheikh, Abdul; Auluck, Rajender Cc: CuadradoDejesus, Samuel
Subject:
FW: Davis Besse Shield Building RAI Can you please review the attached RAI and forward it to Samuel once you have concurred?
Thanks, Bryce From: CuadradoDeJesus, Samuel Sent: Tuesday, December 13, 2011 1:31 PM -To: Lehman, Bryce Cc: Davis-BesseHearingFile Resource
Subject:
Davis Besse Shield Building RAI Bryce, With all the parties and frequent interruptions I almost forgot to get in touch with you on the issue with the shield building RAI. Can you let me know when I'll get your final draft?Thanks Samuel Cuadrado de Jesis Project Manager Projects Branch 1 Division of License Renewal U.S. Nuclear Regulatory Commission Phone: 301-415-2946 Samuel.CuadradoDeJesus@nrc.gov I
RAI B.2.39-X
Background:
In order to perform a scheduled reactor head replacement, a construction opening was made in the concrete shield building.
During hydro-demolition of the concrete shield building, cracks were identified in the 'architectural shoulders' of the shield building.
While investigating the extent of the cracking, additional cracks were identified around the shield building.
The additional cracks were identified using an Impulse Response (IR) technique and core bores were used to verify the IR results.Issue: Extensive cracking in the shield building could affect the st:uc:;rl integrity of the shield building and may impact its ability to perform its intended functir'iduning the period of extended operation.
Request: 1. Summarize the shield building degrad0abi'the root cause. and'.he expected corrective actions. 2. Explain Low the recent plant-specific
- o. ng exper4 nce impactsethe Shield Building's ability to perform its intended functions doxti Include a list of any additional agin !§ffects that ma § anagement bas6dfon this operating experience.
' , ......3. Explain how the recent plant-specifiqb.0ratig e nce will be incorporated into the Structures Monitoring ProgramrAMP,':andthe currerbroaram will be adequate to.nmanage aging of.the shield builditddurinbih7eeriod dl,*tended operation, based on this operatina ori eide S ecif iI "ya-do thýfllowh!!
- i. DetailA f te~tS Alned to the longtefm effect of the concrete cracks on the ability dfldbrebars toicarrv ii. -MPlans. if a`Nfto r ir`becrack 6r reinforce the shield building concrete"" laiis to dr-" ent4d thickness of cracks, and corrosion of the;rl; Plans, iffito Der.f'ri detailed'i uctural analysis, with explicit modeling of r6bars. cracks, anrd!concrete.4 demonstrate that the shield building will perform its intiihd design funcroh. over "thit.0nq term. This analysis should also consider the and' nvironm 6it on the concrete and rebar during the period of extended oeration.4. Identify and expliin p iy changes to the license renewal application based on the recent plant specific opleiratifng experience.
or not-Deleted: whether or not a plant-specific program is necessary to-[ Deleted.Formatted:
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