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Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024
Subsequent License Renewal Application Supplement 8
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023
License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2
L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023
2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023
Subsequent License Renewal Application Supplement 7
L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023
Update to the Technical Specification Bases
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1
L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023
10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09
L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023
License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6
L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023
Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1
L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023
Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 3
L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 1
L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023
10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11
L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023
Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1
L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
Subsequent License Renewal Application Supplement 3
L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023
Subsequent License Renewal Application Supplement 2
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023
Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023
2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023
Subsequent License Renewal Application Supplement 1
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023
Core Operating Limits Report (COLR) for Cycle 31, Revision 3
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023
Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023
10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023
CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023
Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022
L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022
2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022
Update to the Monticello Technical Specification Bases
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022
Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022
Letter Submitting Post-Exam Package
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022
Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
[Table view] |
Text
Xcel Energy@ Monticello Nuclear Generating Plant 2807 W. CR 75, Monticello Monticello, MN 55362 March 29, 2013 L-MT-13-032 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Correction to the MNGP Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. NSPM Letter to NRC, "MNGP Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 27,2012, ADAMS Accession No. ML12333A348.
- 2. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12,2012, ADAMS Accession No. ML12053A340.
In Reference 1, the Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy, provided the results of the external flooding walkdowns performed at the Monticello Nuclear Generating Plant (MNGP). These results were provided to the NRC as a result of information requested per 10 CFR 50.54(f) in a letter dated March 12,2012 (Reference 2). During subsequent reviews of the flooding walkdown report, NSPM identified two items in the Reference 1 report that require correction.
They do not impact the original conclusion of the Reference 1 report that the external flooding program is effective.
The purpose of this letter is to provide replacement pages to correct the original report.
The enclosure to this letter provides a description of the corrections needed. The attachment to the enclosure contains the replacement pages for the report.
Document Control Desk Page 2 If there are any questions on these corrections, or if additional information is needed, please contact Ms. Jennie Eckholt, Licensing Engineer, at 612-330-5788.
Summary of Commitments This letter proposes the following new commitment and no revisions to existing commitments.
Regulatory Commitments Due Date NSPM will submit an updated external flooding walkdown November 20, 2013 report with a summary of the results of the restricted access walkdowns.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 29, 2013.
Mark A. Schimmel Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Director, Office of Nuclear Reactor Regulation (NRR)
NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC
ENCLOSURE Description of Corrections and Attachment with Replacement Pages for MNGP's External Flooding Walkdown Report Page 1 of 3
ENCLOSURE Description of Corrections and Attachment with Replacement Pages for MNGP's External Flooding Walkdown Report On March 12,2012, the NRC Staff issued Reference 2 to all NRC power reactor licensees and holders of construction permits in active or deferred status. Enclosure 4 of the March 12, 2012 letter contains specific Requested Actions, Requested Information, and Required Responses associated with Near-Term Task Force (NTTF)
Recommendation 2.3, Flooding. In Enclosure 4 of Reference 2, the NRC requested licensees to perform flooding walkdowns to verify that plant features credited in the current licensing basis (CLB) for protection and mitigation from external flood events are available, functional, and properly maintained. Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, provided the results of Monticello Nuclear Generating Plant's (MNGP) external flooding walkdowns in a letter with an enclosed report dated November 27,2012 (Reference 1).
During subsequent reviews of the Reference 1 flooding walkdown report, NSPM identified two items requiring correction.
- Procedure Step Incorrectly Referenced
- Building Incorrectly Classified as Locked High Radiation These corrections are described in more detail in the following sections. Two replacement pages are provided in the Attachment to this enclosure to correct the flooding walkdown report.
1.0 Procedure Step Incorrectly Referenced Item 3 in Table 3.6-1, "Deficiency List," of Reference 1 incorrectly references the procedure step 5.2.11.H of the MNGP procedure A.6, "Acts of Nature." The table should reference step 5.2.11.W. One replacement page (page 23) is provided in the attachment to this enclosure to correct the flooding walkdown report.
2.0 Building Incorrectly Classified as Locked High Radiation Areas or buildings which were not readily accessible during the flooding walkdowns were provided in Table 3.6-3, "Restricted Access," of Reference 1. Item number 25 of this table identified the Compressed Gas Storage Building as a locked high radiation area. However, it was identified during the work order planning process that the areas requiring inspection are not locked high radiation areas and are accessible during normal plant operations. NSPM has entered this issue into the Corrective Action Program, and will complete the walkdown of the Compressed Gas Storage Building by October 31, 2013 per the commitment in Reference 1. One replacement page (page 28) is provided in the attachment to this enclosure to correct the flooding walkdown report.
Page 2 of 3
ENCLOSURE Description of Corrections and Replacement Pages for Monticello Nuclea'r Generating Plant's External Flooding Walkdown Report 3.0 Updated External Flooding Walkdown Report NSPM originally committed to complete the inspection of flood protection features identified in Table 3.6-3, "Restricted Access," of Reference 1 by October 31,2013. Any deficiencies identified as a result of the completion of these inspections will be provided to the NRC in an updated external flooding walkdown report. NSPM will submit an updated external flooding walkdown report with a summary of the results of the restricted access walkdowns by November 20, 2013.
References:
- 1. NSPM Letter to NRC, "MNGP Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 27,2012, ADAMS Accession No. ML12333A348.
- 2. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated March 12,2012, ADAMS Accession No. ML12053A340.
Page 3 of 3
ENCLOSURE Description of Corrections and Attachment with Replacement Pages for MNGP's External Flooding Walkdown Report Attachment Replacement Pages for MNGP's External Flooding Walkdown Report (Markup)
Page 23 Page 28 2 pages follow
Monticello Nuclear Generating Plant External Flooding Walkdown Report Table 3.6-1: Deficiency list Description of CAP Action Anticipated No. Condition Actions Feature Request No. Completion Date 1 Penetrations in Plant Provides a path for flood Revise Procedure A.6 to 01358177 February 15, 2013 Administration Building water to enter the PAB remove pathway.
(PAB) 939 Telephone Control Building.
Room 2 Windows in PAB Provides a potential path Actions to mitigate effects 01358177 February 15, 2013 Lunchroom for flood water to enter the from flood water could PAB Control Building. include, but are not limited to 1) replacing windows or 2) revising Procedure A.6 to include sandbag berm in PAB Control Buildin(:J.
3 Conflict with steps in Current step 5.2.11.8 is not Revise Procedure A.6 to 01358177 February 15, 2013 Procedure A.6 to in agreement with step clarify protection of tank protect tank T-44 5.2.11.W regarding T-44.
protection of tank T -44 if the ring levee option is not chosen.
4 Seal gap between the Successful completion of Revise Procedure A.6 to 01353929 February 15, 2013 Intake Structure and step 5.2.9.1 may not be provide improved method access tunnel or assured as currently of sealing the gap.
between the tunnel and written.
Turbine Building (Procedure A.6, Step 5.2.9.1)
Page 23
Monticello Nuclear Generating Plant External Flooding Walkdown Report Table 3.6-3: Restricted Access No. Location Description/Justification Work Order No. Remarks 18 Intake Structure Tunnel Conduit Penetrations /Install 466385, Task 11 Install cap on conduit as Extension Elev. 916' - West Scaffolding & Verify Conduit needed.
Wall Penetrations Sealed.
19 Intake Structure Elev. 916' Inspect Open Conduit 466385, Task 27 Conduit does not correspond (East Wall Tunnel Penetration. Verify seal. to any known equipment.
Extension) 20 Reactor Building Elev. 935' - Complete Inspection / Locked 466385, Task 26 None.
Steam Chase High Radiation Area 21 Condenser Room (Turbine Complete Inspection / Locked 466385, Task 20 None.
Building Elev. 911 ') High Radiation Area 22 Condensate Resin Receiver Complete Inspection / Locked 466385, Task 21 None.
Tank Room (Turbine High Radiation Area Building Elev. 908')
23 Steam Jet Air Ejector Room Complete Inspection / Locked 466385, Task 22 None.
(Turbine Building Elev. 911 ') High Radiation Area 24 Condensate Demineralizer Complete Inspection / Locked 466385, Task 23 None.
Area (Turbine Building Elev. High Radiation Area 937')
25 Compressed Gas Storage Complete Inspection 466385, Task 25 None.
Building 26 Diesel Fuel Oil Storage Tank Complete Inspection / 466385, Task 24 None.
(Elev. 930') Confined Space Page 28
