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Category:Letter type:SBK
MONTHYEARSBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request 2023-06-22
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NExTera ENERGY 0 SEAROO January 9, 2015 10 CFR 50.90 SBK-L- 14225 Docket No. 50-443 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station Response to Request for Additional Information Regarding License Amendment Request 14-02 Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement
References:
- 1. NextEra Energy Seabrook letter SBK-L- 14126, "License Amendment Request 14-02 Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement," dated July 24, 2014 (ML14209A918).
- 2. NRC letter, "Request for Additional Information Regarding License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement (TAC No. MF4578)," dated November 24, 2014 (ML14324A637).
In Reference 1, NextEra Energy Seabrook, LLC (NextEra) requested, in part, to revise Technical Specification (TS) 3.8.1.1, "A.C. Sources - Operating," to increase the voltage limit for a full load rejection test of the emergency diesel generator specified in TS surveillance requirement (SR) 4.8.1.1.2.f.3.
In Reference 2, the NRC requested additional information (RAI) in order to complete its review of the license amendment request. of this letter provides the responses to NRC RAIs 1 and 2. Attachment 2 contains the single line diagrams requested by NRC RAI 3.
This letter contains no new regulatory commitments.
NBoee NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
'U.S. Nuclear Regulatory Commission SBK-L- 14225/Page 2 If you have any questions regarding this report, please contact Mr. Michael Ossing, Licensing Manager, at (603) 773-7512.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January ? ,2015.
Sincerely, NextEra Energy Seabrook, LLC Dean Curtland Site Vice President Attachments cc: NRC Region I Administrator J.G. Lamb, NRC Project Manager, Project Directorate 1-2 NRC Senior Resident Inspector Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
Attachment 1 to SBK-L-14225 Response to NRC RAIs Regarding License Amendment Request 14-02 Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement
Response to NRC RAIs Regarding License Amendment Request 14-02 Proposed Change to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement NRC RAI No. 1.
On page 1 of the license amendment request (LAR), the licensee states: "When an EDG
[emergency diesel generator] is operated in parallel with the grid for the purpose of the full load rejection test, the emergency bus voltage is further increased as excitation is adjusted to meet the required VAR [volt-ampere reactive] loading."
Please provide the value of the required VAR loading considered for the full load rejection test and the basis for that value. Since the overvoltage limit is also dependent on the VAR loading, please explain why the VAR loading is not considered as part of SR 4.8.1.1.2.f.3.
NextEra Response There is no Technical Specification requirement for a specific VAR loading associated with the EDG full load rejection. The existing TS overvoltage limit of 4784V was not based on any specific VAR loading requirement. The existing VAR loading requirement for the full load rejection test as described in station procedure OX1426.34, "Diesel Generator IA 18 Month Operability Surveillance," is 3900 kVAR (3700 - 4100 kVAR range). Section 1.2.24 of OX1426.34 describes the basis for this value. OX1426.32, "Diesel Generator lB 18 Month Operability Surveillance," contains the same requirement.
OX1426.34 (OX1426.32) Section 1.2.24 states:
NRC IN 91-13 identified a concern with EDG tests not using adequate kW and kVAR loading. Seabrook's review of IN 91-13 is documented in Yankee Memo SBP-91-580, dated 10/16/91. The memo included a recommendation to increase the kVAR loading used during the tests when the EDG was paralleled with offsite power. The memo also indicated that it was acceptable to continue testing if the specified kVAR loading could not be achieved as long as an evaluation was performed to determine whether the limitation was because of grid conditions (high voltage) or was a problem with the EDG excitation system. The EDG T.S. Background Document (Memo CEM-98-061, dated 2/19/98) identified that the procedure steps, which accepted a kVAR loading less than the limits, also specify that an evaluation be performed to verify that the kVAR limitation is due to grid conditions and not problems with the voltage regulator. For this evaluation an observation that grid & bus voltages are higher than normal, that EDG VARS can be raised and lowered indicating VAR control, and no abnormal EDG operating parameters that could indicate a voltage regulator problem will be utilized.
The referenced "TS Background document" further describes that the selected VAR loading verifies that the EDG surveillance is performed at a power factor that represents the design load as determined in the EDG loading calculation.
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The Tech Spec Bases 3/4.8.1 state:
Note that although no power factor requirements are established by SR 4.8.1.1.2a.6), the EDG is normally operated at a power factor between 0.8 lagging and 1.0. The 0.8 value is the design rating of the machine, while the 1.0 is an operational limitation to ensure circulating currents are minimized. The load band is provided to avoid routine overloading of the EDG. Routine overloading may result in more frequent tear down inspections in accordance with vendor recommendations in order to maintain EDG OPERABILITY. Similarly, though not stated in footnote ****, momentary kVAR transients above the limit do not invalidate the test.
Per UFSAR 8.1, Seabrook islicensed to IEEE 387-77 and RG 1.9 Rev. 2. Previous reviews by the station have concluded that Seabrook EDG surveillance testing meets these requirements.
NRC RAI No. 2.
On pages 2 and 3 of the LAR, the licensee states: "NextEra evaluated why previous voltage excursions on April 24, 2005 and December 7, 2005, on EDG-IB did not affect its ability to perform its safety function of providing backup power to the emergency bus. The subject voltage excursions lasted approximately 4.7 minutes and 5.3 minutes. The evaluation concluded that a voltage of about 6000 volts, although undesirable, will not damage the generator or exciter components."
Please provide the peak voltages experienced during the previous voltage excursions on EDG-1B on April 24, 2004, and December 7, 2005, and explain the reasons for these voltage excursions.
NextEra Response Engineering Evaluation EE-05-021 addresses the April 24, 2005 and December 7, 2005 voltage excursions on DG-IB.
April 24, 2005 event: MCB voltage indicator went off scale at about 5200V. The exact upper value was indeterminate due to instrument limitations.
Per AR170423 (CR 05-05540), the Apparent Cause Evaluation and Engineering Evaluation EE-05-022 identified a rectifier chassis SCR failure as the most probable cause for the voltage excursion..
December 7, 2005 event: MCB voltage indicator went off scale at about 5331V. The exact upper value was indeterminate due to instrument limitations.
Per AR88835 (CR 05-14748), the Apparent Cause Evaluation identified a degraded voltage regulator gate firing circuit board as the apparent cause.
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NRC RAI No. 3.
Please provide a copy of the single line diagram showing the connection of one of the EDGs to an emergency bus and associated protections (protective relays, etc.) provided for the EDG.
NextEra Response See Attachment 2 for drawing 1-NHY-310007, 4160V Switchgear Bus 1-E5 One Line Diagram.
This drawing shows Bus-E5 and DG-1A, See Attachment 2 for drawing 1-NHY-3 10010, Sh. 1, Diesel Generator DG-1A and DG-1B One Line Diagram, for DG-1A protective relays.
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Attachment 2 to SBK-L-14225 Drawing 1-NHY-310007, 4160V Switchgear Bus 1-E5 One Line Diagram Drawing 1-NHY-310010, Sh. 1, Diesel Generator DG-1A and DG-1B One Line Diagram DG-1A protective relays