Letter Sequence Draft RAI |
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MONTHYEARML0915205382009-05-28028 May 2009 Inservice Inspection Program Fourth Ten-Year Interval Proposed Alternative No. RR-1-11 Project stage: Request ML0915905242009-06-0808 June 2009 Informs the Licensee That Relief Request RR-1-11 Is Acceptable for Review Project stage: Other ML0918313512009-07-0202 July 2009 E-mail Draft RAI on Proposed Alternative RR-1-11 Project stage: Draft RAI ML0920902962009-07-27027 July 2009 Response to Request for Additional Information for Inservice Inspection Program Fourth Ten-year Interval Proposed Alternative No. RR-1-11 Project stage: Response to RAI ML0926000132009-09-16016 September 2009 Record of Conference Call in Which a Proposed ASME Code Alternative Was Verbally Authorized Project stage: Other ML0934106522009-12-22022 December 2009 Authorization of Proposed Alternative RR-1-11 Regarding Visual Examinations for Reactor Pressure Vessel Bottom-Mounted Instrument Penetrations Project stage: Other 2009-06-08
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Category:E-Mail
MONTHYEARML24030A0672024-01-26026 January 2024 Email EA Fonsi Notice to Kewaunee Solutions for Exemptions on Site Restoration Activities ML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23353A0742023-12-19019 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17 ML23348A3462023-12-14014 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML23268A4362023-09-21021 September 2023 Extension Date Approval for Request for Additional Information for Exemptions on Site Restoration Activities ML23268A0292023-09-20020 September 2023 SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23249A2092023-09-0606 September 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4822023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen ML23228A1212023-08-16016 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397 ML23227A2182023-08-15015 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f) ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23172A1122023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23134A0012023-05-0909 May 2023 NRC Email Acceptance - Kewaunee Solutions Exemption Request Regarding Decommissioning Trust Funds for Site Restoration Activities (Docket No. 50-305) ML23129A0672023-05-0505 May 2023 NRC Email Acceptance - Kewaunee Solutions Exemption Request for Low-Level Radioactive Waste Transport Change from 20 to 45 Days Acknowledgement ML23100A0032023-04-0404 April 2023 Solutions - Acknowledgement Email Regarding Exemption Regarding Decommissioning Trust Funds for Site Restoration Activities (Docket No 50-305) ML23094A1442023-03-31031 March 2023 Solutions - Acknowledgement Email Regarding Exemption for Low-Level Radioactive Waste Transport within 20 Days (Docket No. 50-305) ML23054A3322023-02-23023 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record ML23053A1362023-02-13013 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML23012A2102022-07-26026 July 2022 Letter Submitting Monticello Outline Package ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML22108A1762022-04-14014 April 2022 E-mail: Proposed Order Conditions for In-Direct Transfer of Licenses Held by Energysolutions, LLC (Zion, TMI Unit-2, La Crosse Boiling Water Reactor, Kewaunee, Energysolutions Radioactive Materials License, and Energysolutions Export Licens ML22101A0712022-04-11011 April 2022 NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency ML22089A1302022-03-30030 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency ML22082A1812022-03-23023 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28 ML22075A2612022-03-16016 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26 ML22067A2032022-03-0808 March 2022 Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted) ML22053A2992022-02-18018 February 2022 Email - Additional Time for Request for Additional Information Response Regarding Kewaunee Solutions Decommissioning Quality Assurance Program; NRC Response Included; (EPID L-2021-LLO-0002 and L-2021-DP3-0000) ML22027A3642022-01-26026 January 2022 KPS: CY2022 Inspection Plan, Docket No. 05000305, License No. DPR-43 ML22011A0642022-01-11011 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection ML22007A3182022-01-0707 January 2022 E-mail from C. Adams, State of Wisconsin, to K. Sturzebecher, NRC, Notification and Request Kewaunee Power Station License Transfer (L-2021-LLO-002) ML22005A3612022-01-0505 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22 ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21348A0522021-12-0303 December 2021 E-mail to P. Schmidt, State of Wisconsin, from K. Sturzebecher, NRC - Notification and Request Kewaunee Power Station License Transfer ML21330A0382021-11-18018 November 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing ML21286A7882021-10-0606 October 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing ML21256A1892021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves ML21256A1882021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps ML21256A1862021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing ML21253A2002021-09-10010 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing ML21252A0132021-08-31031 August 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies ML21130A3022021-05-0707 May 2021 Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System 2024-01-26
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Accession No. ML091831351 From: Tam, Peter Sent: Thursday, July 02, 2009 5:02 PM To: 'Jack.Gadzala@dom.com'; Thomas Breene (thomas.l.breene@dom.com);
'Craig.D.Sly@dom.com' Cc: Andruszkiewicz, Edward
Subject:
Kewaunee - Draft RAI on proposed Alternative No. RR-1-11 (TAC ME1394)
Jack:
The NRC staff has reviewed the information provided by Dominion Energy Kewaunee for Kewaunee Power Station in its letter dated May 28, 2009, and has determined that additional information, as set forth below, is necessary to complete the review of RR-1-11.
10 CFR 50.55a(g)(6)(ii)(E) states in part, All licensees of pressurized water reactors shall augment their inservice inspection program by implementing the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-722 subject to the conditions specified in paragraphs (g)(6)(ii)(E) (2) through (4) of this section. Note (4) to ASME Code Case N-722, Table 1, Item B15.80 requires that, Personnel performing the VE shall be qualified as VT-2 visual examiners and shall have completed a minimum of four (4) hours of additional training in detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.
The second paragraph on page 6 of the submittal states: The examiners that performed the RPV BMI penetration examinations during the 2008 refueling outage held current VT-1, VT-2 (non-alternative) and VT-3 qualifications. Each of the examiners successfully completed Boric Acid Corrosion Control (BACC) Inspector Training. In addition to BACC training, each of the examiners was required to review EPRI Technical Report 1006296 (reference 6). Completion of these training activities have been determined to be equivalent to the four (4) hours of additional training cited in Code Case N-722.
- 1. Provide more specific details of the training that the visual examiners received in detection of borated water leakage from Alloy 600/82/182 components.
- 2. Detail the number of hours each inspector completed in training to recognize borated water leakage and also detail how these hours were documented.
- 3. Provide a reference for the Boric Acid Corrosion Control Program.
Please set up a conference call with me to discuss the following draft RAI questions. The sole purpose of this e-mail is to prepare you and others for the requested conference call.
This e-mail does not formally request for additional information, and does not convey an official NRC staff position.
Peter S. Tam Senior Project Manager (for Kewaunee and Monticello)
Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451