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| | number = ML072330440 | | | number = ML072330440 |
| | issue date = 08/20/2007 | | | issue date = 08/20/2007 |
| | title = Prairie Island - RAIs for ISI Summary Report Steam Generator- MD3158 | | | title = RAIs for ISI Summary Report Steam Generator- MD3158 |
| | author name = Kivi J | | | author name = Kivi J |
| | author affiliation = Nuclear Management Co, LLC | | | author affiliation = Nuclear Management Co, LLC |
| | addressee name = Chawla M L | | | addressee name = Chawla M |
| | addressee affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 | | | addressee affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
| | license number = | | | license number = |
| | contact person = Chawla M L, NRR/.DLPM, 415-8371 | | | contact person = Chawla M, NRR/.DLPM, 415-8371 |
| | case reference number = TAC MD3158 | | | case reference number = TAC MD3158 |
| | document type = E-Mail | | | document type = E-Mail |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: "Kivi, Jeffrey L." <Jeffrey.Kivi@nmcco.com>To:"Chawla, Mahesh" <mlc@nrc.gov>Date: 08/20/2007 9:38:43 AM | | {{#Wiki_filter:From: "Kivi, Jeffrey L." <Jeffrey.Kivi@nmcco.com> |
| | To: "Chawla, Mahesh" <mlc@nrc.gov> |
| | Date: 08/20/2007 9:38:43 AM |
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| ==Subject:== | | ==Subject:== |
| RE: Prairie Island - RAIs for ISI Summary Report Steam Generator -MD 3158 | | RE: Prairie Island - RAIs for ISI Summary Report Steam Generator -MD 3158 |
| | | -----Original Message----- |
| -----Original Message-----From: Mahesh Chawla [mailto:MLC@nrc.gov] | | From: Mahesh Chawla [mailto:MLC@nrc.gov] |
| Sent: Tuesday, December 12, 2006 3:39 PM To: Kivi, Jeffrey L. | | Sent: Tuesday, December 12, 2006 3:39 PM To: Kivi, Jeffrey L. |
| Cc: Allen Hiser; John Burke | | Cc: Allen Hiser; John Burke |
| Line 29: |
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| ==Subject:== | | ==Subject:== |
| Prairie Island - RAIs for ISI Summary Report Steam Generator | | Prairie Island - RAIs for ISI Summary Report Steam Generator |
| -MD 3158By a letters dated September 1, 2006 (ML062550530), and May 25, 2006(ML061450543), Nuclear Management Company (the licensee) submitted information summarizing the results of the 2006 steam generator tube inspections at Prairie Island Unit 1. These inspections were performed during the twenty fourth refueling outage (1R24). In addition to this report, the U.S. Nuclear Regulatory Commission staff summarized additional information concerning the 2006 steam generator tube inspections at Prairie Island Unit 1 in a letter dated July 10, 2006 (ML061680006).The NRC staff has reviewed the information the licensee provided anddetermined that additional information is required in order to complete the evaluation. The additional information being requested is enclosed. | | -MD 3158 By a letters dated September 1, 2006 (ML062550530), and May 25, 2006 (ML061450543), Nuclear Management Company (the licensee) submitted information summarizing the results of the 2006 steam generator tube inspections at Prairie Island Unit 1. These inspections were performed during the twenty fourth refueling outage (1R24). In addition to this report, the U.S. Nuclear Regulatory Commission staff summarized additional information concerning the 2006 steam generator tube inspections at Prairie Island Unit 1 in a letter dated July 10, 2006 (ML061680006). |
| | The NRC staff has reviewed the information the licensee provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is enclosed. |
| From discussions with you, the root cause evaluation is not complete. | | From discussions with you, the root cause evaluation is not complete. |
| Please provide your estimated date of completion of the root cause evaluation and arrange a teleconference to discuss the staff request upon availability of the root cause evaluation report. 1. On May 18, 2006, the Nuclear Regulatory Commission (NRC) staffconducted a phone call with representatives from Prairie Island to discuss the steam generator tube inspections during their 24th refueling outage. During the call the there was a discussion of a root cause analysis that was commenced in response to finding more wear indications than expected. Please discuss the scope and results of that analysis. | | Please provide your estimated date of completion of the root cause evaluation and arrange a teleconference to discuss the staff request upon availability of the root cause evaluation report. |
| In addition, please discuss any planned corrective actions in response to the results. Also, please discuss whether there is any axial or radial pattern for the wear indications detected. If so, discuss the significance.2. During the operating cycle prior to the 24th refueling outage, pleasediscuss whether there were any chemical excursions in the steam generators (e.g., from a leaking condenser tube). If so, discuss the extent of the chemical excursion, the corrective action and any long term implications for the steam generators.Thanks}} | | : 1. On May 18, 2006, the Nuclear Regulatory Commission (NRC) staff conducted a phone call with representatives from Prairie Island to discuss the steam generator tube inspections during their 24th refueling outage. During the call the there was a discussion of a root cause analysis that was commenced in response to finding more wear indications than expected. Please discuss the scope and results of that analysis. |
| | In addition, please discuss any planned corrective actions in response to the results. Also, please discuss whether there is any axial or radial pattern for the wear indications detected. If so, discuss the significance. |
| | : 2. During the operating cycle prior to the 24th refueling outage, please discuss whether there were any chemical excursions in the steam generators (e.g., from a leaking condenser tube). If so, discuss the extent of the chemical excursion, the corrective action and any long term implications for the steam generators. |
| | Thanks}} |
|
|---|
Category:E-Mail
MONTHYEARML23348A3472023-12-12012 December 2023
NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment
ML23335A1152023-12-0101 December 2023
NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions
ML23312A0882023-11-0808 November 2023
Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10
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
ML23207A1962023-07-26026 July 2023
NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions
ML23075A2802023-03-16016 March 2023
NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda
ML23065A0592023-02-27027 February 2023
NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions
ML23018A2952023-01-18018 January 2023
Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email)
ML22167A0452022-06-16016 June 2022
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277
ML22166A4112022-06-15015 June 2022
NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage
ML22160A6022022-06-0909 June 2022
NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment
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
ML22045A4972022-02-14014 February 2022
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring
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
ML21321A0452021-11-10010 November 2021
Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request
ML21302A1252021-10-29029 October 2021
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment
ML21305A0102021-10-29029 October 2021
NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment
ML21252A0152021-09-0202 September 2021
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months
ML21252A0122021-08-30030 August 2021
NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island
ML21133A2502021-05-13013 May 2021
NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20253A2782020-09-0909 September 2020
E-Mail Submitting Proposed New License Condition
ML20254A1162020-09-0909 September 2020
Draft License Transmittal E-Mail
ML20223A0632020-08-10010 August 2020
Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation
ML20192A1442020-07-0707 July 2020
NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505
ML20163A4282020-06-10010 June 2020
Email from MPCA Comment Letter - Prairie Island ISFSI
ML20154K7632020-06-0202 June 2020
NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283)
ML20135G8212020-05-14014 May 2020
NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283)
ML20112F4582020-04-21021 April 2020
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection
ML20083F4202020-03-20020 March 2020
NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283)
ML20077L4632020-03-17017 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529
ML20052C7582020-02-21021 February 2020
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05
ML20035F1552020-02-0404 February 2020
NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079)
ML20022A1762020-01-22022 January 2020
NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
ML20021A1832020-01-21021 January 2020
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2
ML19316A0172019-11-0101 November 2019
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request
ML19253B9642019-09-10010 September 2019
NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3
ML19233A0032019-08-14014 August 2019
NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10
ML19193A0142019-07-0909 July 2019
NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals)
ML19057A1652019-02-26026 February 2019
NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request
ML19057A4212019-02-26026 February 2019
NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request
ML19008A3562019-01-0707 January 2019
NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69
ML18351A0142018-12-14014 December 2018
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment
ML18347A3282018-12-12012 December 2018
E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018)
ML18313A0832018-11-0707 November 2018
NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request
ML18235A2982018-08-23023 August 2018
NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request
ML18233A3692018-08-21021 August 2018
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Adoption of 10 CFR 50.69
ML18201A4132018-07-20020 July 2018
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-439
ML18159A3052018-06-0808 June 2018
NRR E-mail Capture - Monticello - Acceptance of Requested Relief Request RR-012: Lnservice Inspection Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval
ML18113A2252018-04-23023 April 2018
NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-425
2023-09-05
[Table view] |
Text
From: "Kivi, Jeffrey L." <Jeffrey.Kivi@nmcco.com>
To: "Chawla, Mahesh" <mlc@nrc.gov>
Date: 08/20/2007 9:38:43 AM
Subject:
RE: Prairie Island - RAIs for ISI Summary Report Steam Generator -MD 3158
Original Message-----
From: Mahesh Chawla [1]
Sent: Tuesday, December 12, 2006 3:39 PM To: Kivi, Jeffrey L.
Cc: Allen Hiser; John Burke
Subject:
Prairie Island - RAIs for ISI Summary Report Steam Generator
-MD 3158 By a letters dated September 1, 2006 (ML062550530), and May 25, 2006 (ML061450543), Nuclear Management Company (the licensee) submitted information summarizing the results of the 2006 steam generator tube inspections at Prairie Island Unit 1. These inspections were performed during the twenty fourth refueling outage (1R24). In addition to this report, the U.S. Nuclear Regulatory Commission staff summarized additional information concerning the 2006 steam generator tube inspections at Prairie Island Unit 1 in a letter dated July 10, 2006 (ML061680006).
The NRC staff has reviewed the information the licensee provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is enclosed.
From discussions with you, the root cause evaluation is not complete.
Please provide your estimated date of completion of the root cause evaluation and arrange a teleconference to discuss the staff request upon availability of the root cause evaluation report.
- 1. On May 18, 2006, the Nuclear Regulatory Commission (NRC) staff conducted a phone call with representatives from Prairie Island to discuss the steam generator tube inspections during their 24th refueling outage. During the call the there was a discussion of a root cause analysis that was commenced in response to finding more wear indications than expected. Please discuss the scope and results of that analysis.
In addition, please discuss any planned corrective actions in response to the results. Also, please discuss whether there is any axial or radial pattern for the wear indications detected. If so, discuss the significance.
- 2. During the operating cycle prior to the 24th refueling outage, please discuss whether there were any chemical excursions in the steam generators (e.g., from a leaking condenser tube). If so, discuss the extent of the chemical excursion, the corrective action and any long term implications for the steam generators.
Thanks
