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| {{#Wiki_filter:2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy* RES P 0 N S I B L E BY NAT U R E 800.895.4999 xcelenergy.com November 22, 2016 L-MT-16-058 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576) | | {{#Wiki_filter:2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy* |
| | RES P 0 N S I B L E BY NAT U R E 800.895.4999 xcelenergy.com November 22, 2016 L-MT-16-058 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576) |
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| ==References:== | | ==References:== |
| : 1) NSPM (P. Gardner) to NRC, "License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2," (L-MT-16-014), dated April4, 2016 (ADAMS Accession No. ML16099A097) | | : 1) NSPM (P. Gardner) to NRC, "License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2," (L-MT-16-014), dated April4, 2016 (ADAMS Accession No. ML16099A097) |
| : 2) NRC (R. Kuntz) to NSPM (R. Loeffler), "DRAFT Request for Additional Information RE: Monticello license amendment request for Battery Charger SR revision (CAC MF7576)," dated August 31, 2016 3) NSPM (P. Gardner) to NRC, "Response to Request for Additional Information: | | : 2) NRC (R. Kuntz) to NSPM (R. Loeffler), "DRAFT Request for Additional Information RE: Monticello license amendment request for Battery Charger SR revision (CAC MF7576)," dated August 31, 2016 |
| License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576)," (L-MT-16-045), dated October 3, 2016 (ADAMS Accession No. ML16277A486) | | : 3) NSPM (P. Gardner) to NRC, "Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576)," (L-MT-16-045), |
| On April 4, 2016, the Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy, submitted a license amendment request proposing a change to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). The proposed change revises Specification 3.8.4, "DC Sources-Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the required 125 VDC subsystems battery charger output current and to remove the second method specified to perform the surveillance (Reference 1). On August 31,2016, the U.S. Nuclear Regulatory Commission (NRC) requested additional information (RAI) pertaining to this proposed amendment (Reference 2). The responses to this RAI were provided in Reference | | dated October 3, 2016 (ADAMS Accession No. ML16277A486) |
| : 3. During development of the response to RAI 4 in Reference 3, it was clarified that Section 8.5.2.2 of the Updated Safety Analysis Report (USAR) incorrectly indicated that the rated DC L-MT-16-058 Page 2 of 2 output was 80 amps for the 125 VOC main Battery Chargers (010 and 020) and 50 amps for the common standby 125 VOC Battery Charger (040), rather than stating 80 amps for all three chargers to meet TS requirements.
| | On April 4, 2016, the Northern States Power Company, a Minnesota Corporation (NSPM), |
| The response to RAI 4 stated the USAR had been revised and the discrepancy was entered into the Corrective Action Program. Subsequent to submittal of the RAI response a verbal request was made by the NRC Project Manager for a copy of the revised USAR page. The revised USAR page is provided in the enclosure to this letter. Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. | | doing business as Xcel Energy, submitted a license amendment request proposing a change to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). |
| I declare under penalty of perjury, that the foregoing is true and correct. Executed on November :lJ, 2016. | | The proposed change revises Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the required 125 VDC subsystems battery charger output current and to remove the second method specified to perform the surveillance (Reference 1). On August 31,2016, the U.S. Nuclear Regulatory Commission (NRC) requested additional information (RAI) pertaining to this proposed amendment (Reference 2). |
| Peter A Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company-Minnesota | | The responses to this RAI were provided in Reference 3. |
| | During development of the response to RAI 4 in Reference 3, it was clarified that Section 8.5.2.2 of the Updated Safety Analysis Report (USAR) incorrectly indicated that the rated DC |
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| | L-MT-16-058 Page 2 of 2 output was 80 amps for the 125 VOC main Battery Chargers (010 and 020) and 50 amps for the common standby 125 VOC Battery Charger (040), rather than stating 80 amps for all three chargers to meet TS requirements. The response to RAI 4 stated the USAR had been revised and the discrepancy was entered into the Corrective Action Program. Subsequent to submittal of the RAI response a verbal request was made by the NRC Project Manager for a copy of the revised USAR page. The revised USAR page is provided in the enclosure to this letter. |
| | Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. |
| | I declare under penalty of perjury, that the foregoing is true and correct. |
| | Executed on November :lJ, 2016. |
| | ~~~~ |
| | Peter A Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota |
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| ==Enclosure:== | | ==Enclosure:== |
| | Supplement to LAR to Revise Battery Charger Surveillance Surveillance Requirement 3.8.4.2, Revised USAR Page cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota |
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| | ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 REVISED USAR PAGE (1 page follows) |
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| Supplement to LAR to Revise Battery Charger Surveillance Surveillance Requirement 3.8.4.2, Revised USAR Page cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 REVISED USAR PAGE (1 page follows)
| | MONTICELLO UPDATED SAFETY ANALYSIS REPORT USAR-08.05 Revision 32P SECTIONS PLANT ELECTRICAL SYSTEMS Page 4 of 8 Each 125 Vdc battery consists of 58 shock absorbent clear plastic cells of the lead-calcium alloy plate type. The manufacturer's rating for both of the 125 Vdc batteries is 95 Amperes at a 4 hour discharge rate and 458 Amperes for a 1 minute discharge rate. These discharge rates are based on an ending terminal voltage of 1.81 Volts per cell at 7rF. |
| MONTICELLO UPDATED SAFETY ANALYSIS REPORT SECTIONS PLANT ELECTRICAL SYSTEMS USAR-08.05 Revision 32P Page 4 of 8 Each 125 Vdc battery consists of 58 shock absorbent clear plastic cells of the lead-calcium alloy plate type. The manufacturer's rating for both of the 125 Vdc batteries is 95 Amperes at a 4 hour discharge rate and 458 Amperes for a 1 minute discharge rate. These discharge rates are based on an ending terminal voltage of 1.81 Volts per cell at 7rF. The battery chargers are 3 phase, full wave, silicon controlled rectifier, constant voltage, and current limiting chargers meeting NEC, NEMA and ASA standards. | | The battery chargers are 3 phase, full wave, silicon controlled rectifier, constant voltage, and current limiting chargers meeting NEC, NEMA and ASA standards. |
| Enclosures are NEMA Type I, convection cooled for operation up to 40oC ambient temperature. | | Enclosures are NEMA Type I, convection cooled for operation up to 40oC ambient temperature. Chargers maintain 1/2% float and equalizing charge voltage regulation from 0-100% capacity with +/- 10% line voltage variation at I ~ <'?~ |
| Chargers maintain 1/2% float and equalizing charge voltage regulation from 0-100% capacity with +/-10% line voltage variation at 60Hz+/-5%. Rated DC output The nominal output current limit setting is ,, 80 Amps for the main chargers and 50 amps for the common standby charger. 8.5.2.3 8.5.2.4 Each 125 Vdc charger is capable of carrying the normal 125 Vdc load and at the same time supplying additional charging current to keep the batteries in a fully charged condition. | | 60Hz+/- 5%. Rated DC output The nominal output current limit setting is ,, |
| The loads provided by the 125 Vdc systems are shown on Drawing NE-36640-3, Section 15. A detailed description of the 125 Vdc system, including associated alarms and operator actions, was provided to the NRC in response (References 35 and 73) to Generic Letter 91-06, "Adequacy of DC Power Supplies" (Reference 74). The NRC acknowledged receipt of the response to Generic Letter 91-06 and considers the issues closed for Monticello (Reference 48). Battery chargers D1 0 and D20 have the ability to be re-powered from an alternate AC source via a permanently mounted local inlet receptacle and an alternate AC source input breaker installed on the charger breaker panel. Performance Analysis The 125 Vdc battery system operates ungrounded with a ground-detection alarm set to annunciate the first ground which has sufficiently low resistance to ground to pick-up the ground detection relay. Multiple grounds, which are the only reasonable mode of failure, are extremely unlikely. | | 80 Amps for the main chargers and 50 amps for the common standby charger. |
| Single ground faults will not blow fuses. Overcurrent protective devices are applied such that failure of a non-safety related load will not result in the loss of safety related equipment that does not itself fail in a safe condition. | | 0 Each 125 Vdc charger is capable of carrying the normal 125 Vdc load and at the same time supplying additional charging current to keep the batteries in a fully charged condition. |
| Alarms are also provided for battery charger supply undervoltage and 125 Vdc bus high/low voltage conditions. | | The loads provided by the 125 Vdc systems are shown on Drawing NE-36640-3, Section 15. |
| The two main chargers have a high-voltage shutdown feature. Loss of 125 Vdc Battery The safeguard systems supported by 125 Vdc power are redundant systems; each of which are supplied from separate 125 Vdc buses. Because of this redundancy, it is concluded that loss of a battery or its bus would not prevent safe shutdown of the plant. 0}} | | A detailed description of the 125 Vdc system, including associated alarms and operator actions, was provided to the NRC in response (References 35 and 73) to Generic Letter 91-06, "Adequacy of DC Power Supplies" (Reference 74). |
| | The NRC acknowledged receipt of the response to Generic Letter 91-06 and considers the issues closed for Monticello (Reference 48). |
| | Battery chargers D1 0 and D20 have the ability to be re-powered from an alternate AC source via a permanently mounted local inlet receptacle and an alternate AC source input breaker installed on the charger breaker panel. |
| | 8.5.2.3 Performance Analysis The 125 Vdc battery system operates ungrounded with a ground-detection alarm set to annunciate the first ground which has sufficiently low resistance to ground to pick-up the ground detection relay. Multiple grounds, which are the only reasonable mode of failure, are extremely unlikely. Single ground faults will not blow fuses. Overcurrent protective devices are applied such that failure of a non-safety related load will not result in the loss of safety related equipment that does not itself fail in a safe condition. |
| | Alarms are also provided for battery charger supply undervoltage and 125 Vdc bus high/low voltage conditions. The two main chargers have a high-voltage shutdown feature. |
| | 8.5.2.4 Loss of 125 Vdc Battery The safeguard systems supported by 125 Vdc power are redundant systems; each of which are supplied from separate 125 Vdc buses. Because of this redundancy, it is concluded that loss of a battery or its bus would not prevent safe shutdown of the plant.}} |
Letter Sequence Supplement |
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CAC:MF7576, DC Electrical Rewrite (Approved, Closed) CAC:MF7676, DC Electrical Rewrite (Withdrawn, Closed) |
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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] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-23-049, 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-23-046, 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-23-037, 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 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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-23-034, 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-23-005, 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) ML22220A2722022-08-0808 August 2022 Response to a Request for Additional Informational Regarding the Monticello Fuel Oil Storage Tank Inspection 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) ML22161A9152022-06-10010 June 2022 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations. 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-21-017, Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 22021-04-20020 April 2021 Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2 L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times2020-12-21021 December 2020 Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times L-MT-20-024, Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-07-20020 July 2020 Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval L-MT-20-015, Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan2020-06-0808 June 2020 Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan ML20045E8942020-02-14014 February 2020 Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS L-MT-19-030, Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.2019-05-15015 May 2019 Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. L-MT-19-024, Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.12019-04-18018 April 2019 Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.1 L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-03-13013 March 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors L-MT-18-058, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...2018-10-23023 October 2018 Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ... L-MT-18-041, Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel2018-07-20020 July 2018 Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-03602018-06-0101 June 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360 ML18131A2232018-05-11011 May 2018 Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di L-MT-18-013, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 152018-04-0505 April 2018 Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 L-MT-17-071, Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves2017-11-20020 November 2017 Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves L-MT-17-066, Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events2017-09-28028 September 2017 Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events L-MT-17-065, License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information2017-09-25025 September 2017 License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information L-MT-17-063, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times L-MT-17-025, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accid2017-04-11011 April 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident L-MT-17-022, Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-03-29029 March 2017 Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-007, Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-02-0707 February 2017 Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-002, Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval2017-01-31031 January 2017 Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval L-MT-16-062, Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-12-16016 December 2016 Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-058, Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-11-22022 November 2016 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 ML16288A0972016-10-14014 October 2016 and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-MT-16-044, Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-10-10010 October 2016 Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-045, Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-10-0303 October 2016 Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 L-MT-16-041, License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties2016-09-14014 September 2016 License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties L-MT-16-038, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2016-08-19019 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) L-MT-16-039, Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2)2016-08-15015 August 2016 Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2) ML16221A2742016-07-31031 July 2016 ANP-3435NP, Revision 2, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. L-MT-16-026, Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection2016-06-0202 June 2016 Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information2016-05-18018 May 2016 Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information L-MT-16-024, Flood Hazard Reevaluation Report2016-04-21021 April 2016 Flood Hazard Reevaluation Report ML16091A2282016-03-29029 March 2016 Monticello Nuclear Generating Plant Exemption Request for Nonconforming Dry Shielded Canister Dye Penetrant Examinations, Supplemental Information to Respond to the Second Request for Additional Information (TAC No. L25058) L-MT-15-081, ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.2015-12-0808 December 2015 ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. ML15274A4732015-09-29029 September 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions ML15348A2172015-08-31031 August 2015 Enclosure 6, Areva Report ANP-3424NP, Non-Proprietary, Areva Responses to RAI from Scvb on MNGP EFW LAR, Revision 0, August 2015 2023-09-05
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2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy*
RES P 0 N S I B L E BY NAT U R E 800.895.4999 xcelenergy.com November 22, 2016 L-MT-16-058 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576)
References:
- 1) NSPM (P. Gardner) to NRC, "License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2," (L-MT-16-014), dated April4, 2016 (ADAMS Accession No. ML16099A097)
- 2) NRC (R. Kuntz) to NSPM (R. Loeffler), "DRAFT Request for Additional Information RE: Monticello license amendment request for Battery Charger SR revision (CAC MF7576)," dated August 31, 2016
- 3) NSPM (P. Gardner) to NRC, "Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 (CAC No. MF7576)," (L-MT-16-045),
dated October 3, 2016 (ADAMS Accession No. ML16277A486)
On April 4, 2016, the Northern States Power Company, a Minnesota Corporation (NSPM),
doing business as Xcel Energy, submitted a license amendment request proposing a change to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP).
The proposed change revises Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the required 125 VDC subsystems battery charger output current and to remove the second method specified to perform the surveillance (Reference 1). On August 31,2016, the U.S. Nuclear Regulatory Commission (NRC) requested additional information (RAI) pertaining to this proposed amendment (Reference 2).
The responses to this RAI were provided in Reference 3.
During development of the response to RAI 4 in Reference 3, it was clarified that Section 8.5.2.2 of the Updated Safety Analysis Report (USAR) incorrectly indicated that the rated DC
L-MT-16-058 Page 2 of 2 output was 80 amps for the 125 VOC main Battery Chargers (010 and 020) and 50 amps for the common standby 125 VOC Battery Charger (040), rather than stating 80 amps for all three chargers to meet TS requirements. The response to RAI 4 stated the USAR had been revised and the discrepancy was entered into the Corrective Action Program. Subsequent to submittal of the RAI response a verbal request was made by the NRC Project Manager for a copy of the revised USAR page. The revised USAR page is provided in the enclosure to this letter.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury, that the foregoing is true and correct.
Executed on November :lJ, 2016.
~~~~
Peter A Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota
Enclosure:
Supplement to LAR to Revise Battery Charger Surveillance Surveillance Requirement 3.8.4.2, Revised USAR Page cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota
ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT SUPPLEMENT TO LICENSE AMENDMENT REQUEST TO REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 REVISED USAR PAGE (1 page follows)
MONTICELLO UPDATED SAFETY ANALYSIS REPORT USAR-08.05 Revision 32P SECTIONS PLANT ELECTRICAL SYSTEMS Page 4 of 8 Each 125 Vdc battery consists of 58 shock absorbent clear plastic cells of the lead-calcium alloy plate type. The manufacturer's rating for both of the 125 Vdc batteries is 95 Amperes at a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> discharge rate and 458 Amperes for a 1 minute discharge rate. These discharge rates are based on an ending terminal voltage of 1.81 Volts per cell at 7rF.
The battery chargers are 3 phase, full wave, silicon controlled rectifier, constant voltage, and current limiting chargers meeting NEC, NEMA and ASA standards.
Enclosures are NEMA Type I, convection cooled for operation up to 40oC ambient temperature. Chargers maintain 1/2% float and equalizing charge voltage regulation from 0-100% capacity with +/- 10% line voltage variation at I ~ <'?~
60Hz+/- 5%. Rated DC output The nominal output current limit setting is ,,
80 Amps for the main chargers and 50 amps for the common standby charger.
0 Each 125 Vdc charger is capable of carrying the normal 125 Vdc load and at the same time supplying additional charging current to keep the batteries in a fully charged condition.
The loads provided by the 125 Vdc systems are shown on Drawing NE-36640-3, Section 15.
A detailed description of the 125 Vdc system, including associated alarms and operator actions, was provided to the NRC in response (References 35 and 73) to Generic Letter 91-06, "Adequacy of DC Power Supplies" (Reference 74).
The NRC acknowledged receipt of the response to Generic Letter 91-06 and considers the issues closed for Monticello (Reference 48).
Battery chargers D1 0 and D20 have the ability to be re-powered from an alternate AC source via a permanently mounted local inlet receptacle and an alternate AC source input breaker installed on the charger breaker panel.
8.5.2.3 Performance Analysis The 125 Vdc battery system operates ungrounded with a ground-detection alarm set to annunciate the first ground which has sufficiently low resistance to ground to pick-up the ground detection relay. Multiple grounds, which are the only reasonable mode of failure, are extremely unlikely. Single ground faults will not blow fuses. Overcurrent protective devices are applied such that failure of a non-safety related load will not result in the loss of safety related equipment that does not itself fail in a safe condition.
Alarms are also provided for battery charger supply undervoltage and 125 Vdc bus high/low voltage conditions. The two main chargers have a high-voltage shutdown feature.
8.5.2.4 Loss of 125 Vdc Battery The safeguard systems supported by 125 Vdc power are redundant systems; each of which are supplied from separate 125 Vdc buses. Because of this redundancy, it is concluded that loss of a battery or its bus would not prevent safe shutdown of the plant.