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Category:E-Mail
MONTHYEARML23128A1612023-05-0808 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 ML18282A1482018-10-0909 October 2018 NRR E-mail Capture - Results of Acceptance Review - FENOC Fleet - Request for Exemption Related to the Suspension of Security Measures in an Emergency or During Severe Weather, EPID L-2018-LLL-0016 ML18282A2422018-10-0808 October 2018 OEDO-18-00160, FENOC Fleet, 2.206 Petition, Submission of Supplement Dated October 8, 2018, from the Petitioners - PRB and Petitioners (Elpc), Includes Email, Cover Letter from Elpc, and the Attachments to the Email 2023-05-08
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1 NRR-PMDAPEm Resource From:Purnell, Blake Sent: Friday, August 26, 2016 9:19 AM To:Lashley, Phil H.
Cc:Wolf, Gerald M.; Davisbesse.regulatory.affairs@firstenergycorp.com; Miller, Ed
Subject:
Davis-Besse License Renewal Commitment 42 (CAC No. MF7626)
Attachments:
DB LR Commitment 42 RAI.docx Mr. Lashley:
By letter dated April 21, 2016 (Agencywide Docum ents Access and Management System Accession No. ML16112A079), FirstEnergy Nuclear Operating Company (FENOC, the licensee) provided a fatigue monitoring program evaluation for Davis-Besse Nuclear Power Station, Unit No. 1. This submittal was in response to license renewal Commitment No. 42.
The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is required to complete the review. A response to the attached request for additional information is to be provided within 30 days. This request was discussed with FENOC personnel on August 23, 2016.
Sincerely,
Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
Docket No. 50-346 Hearing Identifier: NRR_PMDA Email Number: 3013 Mail Envelope Properties (Blake.Purnell@nrc.gov20160826091800)
Subject:
Davis-Besse License Renewal Commitment 42 (CAC No. MF7626) Sent Date: 8/26/2016 9:18:58 AM Received Date: 8/26/2016 9:18:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients: "Wolf, Gerald M." <gmwolf@firstenergycorp.com>
Tracking Status: None "Davisbesse.regulatory.affairs@firstenergycorp.com" <Davisbesse.regulatory.affairs@firstenergycorp.com> Tracking Status: None "Miller, Ed" <Ed.Miller@nrc.gov>
Tracking Status: None "Lashley, Phil H." <phlashley@firstenergycorp.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 902 8/26/2016 9:18:00 AM DB LR Commitment 42 RAI.docx 29701
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL COMMITMENT NO. 42 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 By letter dated April 21, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16112A079), FirstEnergy Nuclear Operating Company (the licensee) provided a fatigue monitoring program evaluation for Davis-Besse Nuclear Power Station (DBNPS), Unit No. 1. This submittal was in response to license renewal Commitment No. 42. The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review.
Background Section 2.C(11), "License Renewal Conditions," of Renewed Facility Operating License No. NPF-3 specifies that the Commitments in Appendix A of NUREG-2193, Supplement 1, "Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station,"
published April 2016 (ADAMS Accession No. ML16104A350), are part of the DBNPS Updated Final Safety Analysis Report. License renewal Commitment No. 42 in Appendix A of NUREG-2193, Supplement 1, states the following:
Enhance the Fatigue Monitoring Program to:
- Evaluate additional plant-specific component locations in the reactor coolant pressure boundary that may be more limiting than those considered in NUREG/CR-6260
[1]. This evaluation will include identification of the most limiting fatigue location exposed to reactor coolant for each material type (i.e.,
[carbon steel] CS, [low-alloy steel] LAS, [stainless steel] SS, and [nickel-based alloy] NBA) and that each bounding material/location will be evaluated for the effects of the reactor coolant environment on fatigue usage. Nickel-
based alloy items will be evaluated using NUREG/CR-6909[2]. Submit the evaluation to the NRC 1 year prior to the period of extended operation.
Enclosure B of the licensee's letter dated June 17, 2011 (ADAMS Accession No. ML11172A389), provides AREVA Report No. 51-9157140-001. Table 3-9 of the AREVA Report contains the environmentally-assisted fatigue (EAF) values for the NUREG/CR-6260 locations. Table 3-8 of the AREVA Report contains a summary of the reactor coolant system pressure boundary locations with environmentally-adjusted cumulative usage factor (CUF en) values that exceed the limit of 1.0.
In its April 21, 2016, letter, the licensee submitted the results of its evaluations associated with Commitment No. 42. The letter stated that locations were screened in accordance with the 1 NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, dated February 1995, ADAMS Accession No. ML031480219.
2 NUREG/CR-6909 "Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials," dated February 2007 methodology of Electric Power Research Institute (EPRI) Technical Report 1024995, "Environmentally Assisted Fatigue Screening, Process and Technical Basis for Identifying EAF Limiting Locations," dated 2012. The letter also identified the most limiting locations for each of the four material types (i.e., CS, LAS, SS, and NBA). The CUF en values are provided for two of the four limiting locations. The CUF en values are not provided for the LAS and NBA locations. The LAS and NBA locations reference EPRI Technical Report 1024995.
I s sue The April 21, 2016, letter, describes the results of the licensee's evaluation and references the generic methodologies (e.g., EPRI Technical Report 1024995) used, but it does not provide sufficient details about the actual evaluation. The plant-specific methodology and criteria used to select the most limiting locations for EAF is not clearly described. The letter does not explain
how the plant-specific screening methodology conservatively evaluates EAF effects, with the same degree of analytical rigor for all locations, to identify the bounding locations. Additionally, the licensee uses different material types to bound limiting locations for LAS and NBA without justification.
EPRI Technical Report 1024995 has not been submitted to the NRC for approval and has not been endorsed by the NRC. The licensee does not explain how the plant-specific implementation of the generic procedures in EPRI Technical Report 1024995 will identify the most limiting plant-specific locations. The NRC sta ff lacks sufficient information to evaluate the plant-specific methodology and criteria used to select the most limiting locations for EAF.
Request (1) Describe the plant-specific methodology and criteria used to rank locations and select the most limiting locations for EAF. Describe relevant factors for each step of the process, such as thermal zones, material types, transient complexity, temperature effects, and complexity of the systems (as applicable). Justify the use of different material types to bound locations. Justify that the process is appropriately conservative.
(2) Describe and justify any engineering judgement, plant-specific assumptions, and plant-specific criteria used in the EAF analysis or screening process. This should include the systematic process used to eliminate locations as limiting and examples showing how the process was implemented.
(3) Describe how the screening process was applied to the locations in Table 3-8 of the AREVA Report No. 51-9157140-001.
(4) State the locations being managed by the fatigue monitoring program to maintain the CUF en values below the limit of 1.0 through the period of extended operation. Provide the CUF en values for the locations being managed by the fatigue monitoring program.