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MONTHYEARSBK-L-12179, License Amendment Request 12-04 Regarding Cold Leg Injection Permissive2013-03-13013 March 2013 License Amendment Request 12-04 Regarding Cold Leg Injection Permissive Project stage: Request ML13084A1212013-04-0404 April 2013 Acceptance Letter Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive Project stage: Acceptance Review ML13175A1972013-06-28028 June 2013 Request for Additional Information for License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive Project stage: RAI SBK-L-13151, Response to Request for Additional Information Regarding License Amendment Request 12-04, Cold Leg Injection Permissive2013-08-0808 August 2013 Response to Request for Additional Information Regarding License Amendment Request 12-04, Cold Leg Injection Permissive Project stage: Response to RAI ML13224A0912013-09-0606 September 2013 Request for Additional Information for License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive Project stage: RAI SBK-L-13211, Response to Request for Additional Information Regarding License Amendment Request 12-04, Cold Leg Injection Permissive2013-11-22022 November 2013 Response to Request for Additional Information Regarding License Amendment Request 12-04, Cold Leg Injection Permissive Project stage: Response to RAI ML14029A4452014-03-0606 March 2014 Issuance of Amendment Regarding License Amendment Request 12-04, Application Regarding Cold Leg Injection Permissive Project stage: Approval SBK-L-14155, License Amendment Request 14-06 - Change to the Technical Specifications to Remove the Cold Leg Injection Permissive (P-15)2014-09-24024 September 2014 License Amendment Request 14-06 - Change to the Technical Specifications to Remove the Cold Leg Injection Permissive (P-15) Project stage: Request 2013-06-28
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Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML21245A4382021-10-0505 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise 120-Volt AC Vital Instrument Panel Technical Specification Requirements ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20204A5422020-07-21021 July 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding Degraded Voltage Time Delay Setpoint ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML18163A0352018-06-11011 June 2018 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML18121A3992018-05-0101 May 2018 NRR E-mail Capture - Request for Additional Information Regarding ASR Amendment Request ML18113A5292018-04-18018 April 2018 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18026A8792018-01-29029 January 2018 Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application Docket No. 05-443 ML17332A3412017-11-29029 November 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption ML17261B2172017-10-11011 October 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17276B7572017-10-0202 October 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17214A0852017-08-0404 August 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction ML17201Q1072017-07-18018 July 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 ML17150A2862017-05-0505 May 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16337A0082016-12-0101 December 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment Seabrook Station, License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application ML16319A4222016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment ML16319A4212016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to EAL License Amendment ML16230A1062016-10-0303 October 2016 Request for Additional Information Request to Extend Containment Leakage Test Frequency ML16230A5332016-09-22022 September 2016 Request for Additional Information Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML16258A0222016-09-19019 September 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Alkali-Silica Reaction ML16187A2032016-07-0808 July 2016 Requests For Additional Information For The Severe Accident Mitigation Alternatives (SAMA) Review Of The Seabrook Station License Renewal Application (TAC No. Me3959)- Enclosure ML15328A1392015-12-0404 December 2015 November 23, 2015, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning Requests for Additional Information Pertaining to the Seabrook Station ML15251A3332015-10-0202 October 2015 Request for Additional Information Related to the Review of the Seabrook Station, Unit 1, License Renewal Application-SET 25 ML15224A5662015-08-28028 August 2015 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application-Set 24 ML15131A3382015-06-0505 June 2015 Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1,Radiation Monitoring for Plant Operations ML15043A2212015-02-24024 February 2015 Request for Additional Information for the Spring 2014 Steam Generator Tube Inspections ML14363A3672015-01-0909 January 2015 Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements ML14358A0732014-12-24024 December 2014 Request for Additional Information for License Amendment Request 13-05. Fixed Incore Detector System Analysis Methodology ML14324A6372014-11-24024 November 2014 Request for Additional Information Regarding License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement 2023-06-22
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 28, 2013 Mr. Kevin Walsh, Site Vice President clo Michael O'Keefe Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 12-04, APPLICATION REGARDING COLD LEG INJECTION PERMISSIVE (TAC NO. MF1158)
Dear Mr. Walsh:
By letter dated March 13, 2013 (Agencywide Documents Access and Management System Accession No. ML13079A122), NextEra Energy Seabrook, LLC (licensee) submitted license amendment request 12-04 for Seabrook Station, Unit No.1 (Seabrook). The proposed change is to the Seabrook Technical Specifications. The proposed amendment modifies the circuitry that initiates high-head safety injection by adding a new permissive, cold leg injection permissive (P-15). This permissive prevents opening of the high-head safety injection valves until reactor coolant s'ystem pressure decreases to the P-15 set point.
The U.S. Nuclear Regulatory Commission staff has determined that additional information is necessary to complete its review. The request for additional information is enclosed. The licensee agreed to provide answers to the request for additional information within 45 days of the date of this letter.
If you have questions, you can contact me at 301-415-3100 or bye-mail at John. Lamb@nrc.gov.
'~u John . Lamb, Senior Project Manager Pia Licensing Branch 1-2 Divi ion of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 12-04 APPLICATION REGARDING COLD LEG INJECTION PERMISSIVE NEXTERA ENERGY SEABROOK. LLC.
SEABROOK STATION. UNIT NO.1 DOCKET NO. 50-443 By letter dated March 13, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13079A122), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 12-04 for Seabrook Station, Unit No. 1 (Seabrook). The proposed change is to the Seabrook Technical Specifications (TSs). The proposed amendment modifies the circuitry that initiates high-head safety injection by adding a new permissive, cold leg injection permissive (P-15). This permissive prevents opening of the high-head safety injection valves until reactor coolant system pressure decreases to the P-15 set point.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is necessary to complete its review.
REQUEST FOR ADDITIONAL INFORMATION (RAI)
The following four RAls (1 through 4) support the evaluation of the independence of redundant equipment and components from the sensor to the actuating device.
- 1. Clarify whether the LAR's simplified P-15 cold leg injection permissive (CLIP) logic diagram (ADAMS Accession No. ML13079A122, Attachment 1, Figure 1, Page 5) shows the solid state protection system (SSPS) coincidence logic for only one SSPS train, which is duplicated for the other SSPS train, or does it show the SSPS coincidence logic of both SSPS trains.
- 2. Demonstrate the post-modification allocation of P-15 functions and S-signal functions among the equipment and components related to the P-15 function (e.g., SSPS components, cabinets, channels, trains, actuated devices and the electrical division/separation group associated with each, etc.).
- 3. Regarding the "two relays with contacts in series with an S-signal relay" (ADAMS Accession No. ML13079A122, Attachment 1, Page 4):
- a. Clarify whether these two relays are in series or are in parallel with one another prior to being in series with an S-signal relay;
- b. Clarify whether there are two relays (Le. redundant relays) within each SSPS train, or one-relay in one SSPS train, and another relay in the other SSPS train;
- c. Provide the location(s)/cabinets(s) where the series connections between these two relays and the S-signal relay(s) is/are made;
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- d. Clarify whether each SSPS train affects the S-signal relays for both cold leg injection valves (1-SI-V-138 and 1-SI-V-139), or only a single cold leg injection valve that is associated with one of the two SSPS trains.
- 4. For the equipment affected by this proposed modification, identify each electrical isolation point between otherwise independent redundant channels (SSPS input cabinets) and trains (SSPS logic cabinets), along with any non-safety equipment, and demonstrate that the electrical isolation is adequate for independence between redundant portions of the safety system, and between safety and non-safety equipment (Le., demonstrate how the Institute of Electrical and Electronics Engineers (IEEE) Std 603-1991, "Criteria for Safety Systems for Nuclear Power Generating Stations," Clauses 5.6.1 and 5.6.3, along with General Design Criterion 22, "Protection System Independence," are satisfied). This information should address all monitoring points and indication, including any that the simplified P-15 logic diagram depicts, if applicable (ADAMS Accession No. ML13079A122, Attachment 1, Figure 1, Page 5).
The following three RAls (5 through 7) support the evaluation of continued compliance to the plant's design basis, as applicable to the modified equipment.
- 5. Identify any deviations from the existing SSPS instrumentation design basis, as documented in the Seabrook Updated Final Safety Analysis Report (UFSAR), Revision 12, that is applicable to this modification (e.g., modifications to the SSPS input cabinets or SSPS logic cabinets).
- 6. Identify and describe testing features associated with the proposed modification with respect to the current SSPS instrumentation design basis that solid-state logic testing checks the digital signal path from the input to the logic matrices (as implemented within the SSPS logic cabinets) to the inputs of the slave relays (see Seabrook UFSAR, Chapter 7, Revision 9, Section 7.3, Page 15) (Le., that demonstrates how IEEE Std 603-1991, Clause 6.5, and the testability portion of General Design Criterion 21, "Protection System Reliability and Testability," are satisfied).
- 7. Regarding the Bypass Test Instrumentation (BTl) signals (ADAMS Accession No.
ML13079A122, Attachment 1, Figure 1, Page 5):
- a. Clarify whether their use is consistent with Seabrook UFSAR, Chapter 7, Revision 9, Section 7.3, Page 14, which allows testing of a process channel when in bypass via an active high signal, where there is a unique BTl control for each P-15 process channel's bistable. If not, please provide an explanation of the BTl signal used to control the P-15 process channel bistables;
- b. Describe whether and how indication of each new bypass will be provided (Le.,
demonstrate how IEEE Std 603-1991, Clauses 5.8.3, and 6.7, are satisfied).
The following five RAls (8 through 12) support the evaluation of reliability during normal operations and when a channel is in bypass, as applicable to the modified equipment.
- 8. Clarify whether any bypass capability is provided for the P-15 function coincidence logic in addition to that provided for the P-15 function process channels.
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- 9. Describe any fail safe behavior of the P-15 function (e.g., the permissive state under complete loss of offsite power, etc.).
- 10. Describe the reliability of the implementation (e.g., circuits and any programmable device) of the P-15 function that supports the statement, "NextEra concludes that the reliability of the P-15 permissive is commensurate with the safety function performed" (ADAMS Accession No. ML13079A122, Attachment 1, Page 6) (i.e., demonstrate how the P-15 function reliability has been established in accordance with IEEE Std 603-1991, Clause 4.9, and how IEEE Std 603-1991, Clause 5.15 is satisfied).
- 11. Clarify whether the design-basis exception of IEEE Std 279-1971, Paragraph 4.11, for "the single failure criterion for one-out-of-two systems during channel bypass where acceptable reliability of operation can be demonstrated, as justified by WCAP-1 0271, Supplement 2,"
will be applied to any equipment that performs any portion of the P-15 function (see Seabrook UFSAR, Revision 12, Section 7.2, Page 34). If so, the demonstration of "acceptable reliability of operation" should also be provided.
- 12. The NRC staff requests additional information that clarifies whether any of the four reactor coolant pressurizer pressure transmitter channels (I-PB 455 H, II-PB 456 H, III-PB 457 H, IV-PB 458 H) are shared by control functions in addition to the P-15 function (Le.,
demonstrate that General Design Criterion 24, "Separation of Protection and Control Systems," is satisfied beyond the electrical separation provided by isolators, as discussed in Seabrook UFSAR, Revision 12, Section 7.1.2.2a, Page 14).
The following RAI (13) supports the evaluation of the P-15 setpoint for reliable operation of the P-15 function.
- 13. Regarding the evaluation of the P-15 setpoint and its allowable values under increasing and decreasing pressurizer pressure (see marked up TS, Table 3.3-4, FUNCTIONAL UNIT 10.d):
- a. Provide a representative calculation of the setpoint methodology used to establish the allowable values of nominal permissive set/reset points for P-15 and the limiting acceptable values for the as-found and as-left tolerances, as measured during periodic surveillance testing;
- b. Identify any related analytical limit or other limiting design value for the P-15 setpoint along with the source of the limit(s);
- c. Provide a summary description that addresses each of the following, consistent with Regulatory Issue Summary 2006-17, "NRC Staff Position on the Requirements of 10 CFR 50.36, 'Technical Specifications,' Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," for the P-15 function:
L the channel performance data that has been used to establish the value of the limiting permissive setpoint (Le., least conservative as-left value associated with the nominal permissive setpoint);
iL the channel performance data that has been used to establish the values of the as-found and as-left tolerances;
-4 iii. representative pressurizer pressure signal conversion and circuit error performance data that has been (or will be) used within the calculation, to demonstrate that the analysis of this data for each P-15 channel meets the acceptance criteria of 95/95 for the performance of the P-15 function (see Regulatory Guide 1.105, "Instrument Setpoints for Safety-Related Systems,"
Position 1);
iv. how the channel performance data is used to establish the nominal permissive setpoint and its associated as-left and as-found tolerances.
June 28, 2013 Mr. Kevin Walsh, Site Vice President c/o Michael O'Keefe Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1- REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 12-04, APPLICATION REGARDING COLD LEG INJECTION PERMISSIVE (TAC NO. MF1158)
Dear Mr. Walsh:
By letter dated March 13, 2013 (Agencywide Documents Access and Management System Accession No. ML13079A122), NextEra Energy Seabrook, LLC (licensee) submitted license amendment request 12-04 for Seabrook Station, Unit No.1 (Seabrook). The proposed change is to the Seabrook Technical Specifications. The proposed amendment modifies the circuitry that initiates high-head safety injection by adding a new permissive, cold leg injection permissive (P-15). This permissive prevents opening of the high-head safety injection valves until reactor coolant system pressure decreases to the P-15 set point.
The U.S. Nuclear Regulatory Commission staff has determined that additional information is necessary to complete its review. The request for additional information is enclosed. The licensee agreed to provide answers to the request for additional information within 45 days of the date of this letter.
If you have questions, you can contact me at 301415-3100 or bye-mail at John. Lamb@nrc.gov.
Sincerely, Ira!
John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLI-2 R/F RidsNrrLAABaxter Resource RidsNRRDor1Lp11-2 Resource RidsNrrPMSeabrook Resource RidsRgn1 MailCenter Resource RidsAcrsAcnw MailCTR Resource RidsNrrDorlDpr Resource ADAMS Accession No' ML13175A197 *via email **via memo OFFICE LPL1-21PM LPL1*21LA* EICBIBC LPL1*2/BC (A) LPL1*2/PM JThorp**
NAME ,ILamb ABaxter VRodriguez JLamb DATE 06126/13 06126/13 06/10/13 06/28/13 06/28/13 OFFICIAL RECORD COpy