Letter Sequence Response to RAI |
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Category:E-Mail
MONTHYEARML24304B0562024-10-30030 October 2024
Acceptance of LAR to Revise TS to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
ML24284A2822024-10-0707 October 2024
Cover Email Re Monticello SLRA-3rd Round Request for Additional Information
ML24254A3932024-08-26026 August 2024
SLRA - 2nd Round Request for Additional Information
ML24239A3722024-08-26026 August 2024
SLRA - 2nd Round Request for Additional Information
ML24218A2282024-08-0505 August 2024
Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval
ML24131A0802024-05-10010 May 2024
Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML24036A2462024-04-24024 April 2024
NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations
ML24092A2152024-03-27027 March 2024
Email: Requests for Information to Support Deis
ML24068A0612024-03-0707 March 2024
Extension of Audit for License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML24064A1802024-03-0404 March 2024
Acceptance of Relief Request RR-017, Inservice Inspection (ISI) Impracticality During the Fifth Ten-Year Interval
ML24036A0932024-02-0202 February 2024
Acceptance of License Amendment Request to Revise TS 5.6.5 and Update PTLR Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
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
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
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
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)
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
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
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
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
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
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
ML21110A7042021-04-20020 April 2021
Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees
ML21084A2522021-03-24024 March 2021
NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062)
2024-08-05
[Table view] |
Text
Package Accession No. ML12223A086 E-mail Accession No. ML12223A081 Attachment Accession No. ML12223A091 From: Rippy, L. Randal [1]
Sent: Thursday, August 09, 2012 4:21 PM To: Tam, Peter Cc: Loeffler, Richard A.; Kissinger, Peter W.; Anderson, Paula K.; Bridgeman, Jim L.; Young, Paul B.;
Atkinson, Ross M.
Subject:
Monticello - Draft RAI on Relief Request (TAC ME8093)
NSPM is pleased to provide the following responses to the NRC's Requests for Additional Information (RAIs) dated July 24th as docketed in the attached email.
RAI (1) Section 5 states that: For determination of whether the In-service Testing (IST) Acceptance Criteria is met, Table 1 and Table 2 are proposed to be used to analyze the data. Both Tables have a note that states For Information Only, actual data may change during 5th IST Interval. Please explain how the tables can be used to analyze the data, when the tables are for information only and the data may change.
Response (1): Tables 1 and 2 currently contain the data used to analyze the pump performance for pump P-209. However, in compliance with ISTB-3310, Effect of Pump Replacement, Repair, and Maintenance on Reference Values, the pump reference values are subject to change during the ten year interval because of pump maintenance which would affect the hydraulic characteristics and change the values in Tables 1 and 2. The format of Tables 1 and 2 will remain the same to be used to analyze the test data. The actual numerical values are subject to change as applicable under ISTB-3310. In order to provide clarity, For Information Only will be removed from the notes above Tables 1 and 2.
(2) Table 2 has a column titled Lower Alert Range (<psid). The values in this column are 0.93 times the differential pressure reference value, which is the upper end of the alert range. Based on these values, should this column not be titled Upper Alert Range (<psid) instead?
Response (2): This column uses the term Lower based on its value compared to the reference value. This section is technically the upper limit on the Alert Range which is lower than the reference value. The Relief Request will be revised to state Alert Range (<psid) which is consistent with the terminology used in table ISTB-5121-1.
A revision to the original PR-06 10 CFR 50.55a Request is attached reflecting the changes described above. They are identified by change bars.
L. Randal Rippy, PE, PMP Xcel Energy l Responsible By Nature Nuclear Licensing Principal Engineer 414 Nicollet Mall, MP-4 Minneapolis, MN 55401 P: 612.330.6911 F: 612.330.7788 C: 651.366.2308 E: randy.rippy@xenuclear.com From: Tam, Peter [2]
Sent: Tuesday, July 24, 2012 4:26 PM
To: Rippy, L. Randal; Loeffler, Richard A.; Kissinger, Peter W.
Cc: Wolfgang, Robert; McMurtray, Anthony; Frankl, Istvan
Subject:
Monticello - Draft RAI on Relief Request (TAC ME8093)
Randy and Rick:
The NRC staff is reviewing the licensees September 28, 2011, letter which conveys a number of relief requests. The NRC staff has developed the following two questions regarding Relief Request PR-06:
(1) Section 5 states that: For determination of whether the In-service Testing (IST)
Acceptance Criteria is met, Table 1 and Table 2 are proposed to be used to analyze the data. Both Tables have a note that states For Information Only, actual data may change during 5th IST Interval. Please explain how the tables can be used to analyze the data, when the tables are for information only and the data may change.
(2) Table 2 has a column titled Lower Alert Range (<psid). The values in this column are 0.93 times the differential pressure reference value, which is the upper end of the alert range. Based on these values, should this column not be titled Upper Alert Range (<psid) instead?
You may choose to accept this e-mail as conveying a formal RAI. If you need clarification of the questions, the NRC staff would be glad to discuss these questions with you in a conference call. In order to meet your need date of September 1, 2012, we request that you formally respond no later than August 15, 2012.
Peter S. Tam Senior Project Manager (for D. C. Cook and Monticello)
Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451
