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| | issue date = 06/11/2012 | | | issue date = 06/11/2012 |
| | title = Request for Additional Information Regarding the Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System | | | title = Request for Additional Information Regarding the Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Freeman P | | | addressee name = Freeman P |
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| | docket = 05000443 | | | docket = 05000443 |
| | license number = | | | license number = |
| | contact person = Lamb J G | | | contact person = Lamb J |
| | case reference number = TAC ME3988 | | | case reference number = TAC ME3988 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 June 11, 2012 Mr. Paul Freeman Site Vice President clo Michael O'Keefe Seabrook Station NextEra Energy Seabrook. LLC P.O. Box 300 Seabrook, NH 03874 |
| D.C. 20555-0001 June 11, 2012 Mr. Paul Freeman Site Vice President clo Michael O'Keefe Seabrook Station NextEra Energy Seabrook. | | |
| LLC P.O. Box 300 Seabrook, NH 03874 SEABROOK STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.5.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" (TAC NO. ME3988) | | ==SUBJECT:== |
| | SEABROOK STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.5.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" (TAC NO. ME3988) |
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| ==Dear Mr. Freeman:== | | ==Dear Mr. Freeman:== |
| By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16, 2011, 3 and March 15, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook).
| |
| The proposed amendment would change TS Surveillance Requirement (SR) 4.6.5.1.d.4 so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS).
| |
| The amendment relocates SR 4.6.5.1.d.4 with modifications to new SR 4.6.5.2.b.
| |
| Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote.
| |
| The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed.
| |
| Conference calls were held on May 25, June 4, and June 7,2012, and Mr. Kilby agreed that NextEra Energy Seabrook, LLC would respond to the RAI within 30 days of the date of this letter. Please note that if you do not respond to the RAI within 30 days, the NRC staff may reject your request for relief under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. "Denial of application for failure to supply information." 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 101390041 2 ADAMS Accession No. ML 102380100 3 ADAMS Accession No. ML 11266A041 4 ADAMS Accession No. ML 120790307 P. Freeman -2 If you have questions, you can contact me at 301-415-3100 and/or G.
| |
| t Licensing Branch is ion of Operating Reactor ffice of Nuclear Reactor Docket No.
| |
| Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.S.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT 1 DOCKET NUMBER S0-443 1.0 SCOPE By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16,2011,3 and March 1S, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) LAR 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook).
| |
| The proposed amendment would change TS Surveillance Requirement (SR) 4.6.S.1.dA so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS).
| |
| The amendment relocates SR 4.6.S.1.dA with modifications to new SR 4.6.S.2.b.
| |
| Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote.
| |
| The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained below.
| |
|
| |
|
| ==2.0 BACKGROUND== | | By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16, 2011, 3 and March 15, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook). The proposed amendment would change TS Surveillance Requirement (SR) 4.6.5.1.d.4 so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS). The amendment relocates SR 4.6.5.1.d.4 with modifications to new SR 4.6.5.2.b. Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote. |
| | The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on May 25, June 4, and June 7,2012, and Mr. Kilby agreed that NextEra Energy Seabrook, LLC would respond to the RAI within 30 days of the date of this letter. Please note that if you do not respond to the RAI within 30 days, the NRC staff may reject your request for relief under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. "Denial of application for failure to supply information." |
| | 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML101390041 2 ADAMS Accession No. ML102380100 3 ADAMS Accession No. ML11266A041 4 ADAMS Accession No. ML120790307 |
| | |
| | P. Freeman -2 If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov. |
| | G. Lamb~&.:f t Licensing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-443 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.S.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT 1 DOCKET NUMBER S0-443 1.0 SCOPE By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16,2011,3 and March 1S, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) LAR 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook). The proposed amendment would change TS Surveillance Requirement (SR) 4.6.S.1.dA so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS). The amendment relocates SR 4.6.S.1.dA with modifications to new SR 4.6.S.2.b. Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote. |
| | The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained below. |
| | |
| | ==2.0 BACKGROUND== |
| | |
| | Under Title 10 of the Code of Federal Regulations (10 CFR), Section SO.36(c)(2), Limiting conditions for operation. Subsection (i) requires: "Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met." |
| | Under 10 CFR SO.36(3) Surveillance requirements, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." |
| | 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML101390041 2 ADAMS Accession No. ML102380100 3 ADAMS Accession No. ML11266A041 4 ADAMS Accession No. ML120790307 Enclosure |
| | |
| | - 2 3.0 REQUEST FOR ADDITIONAL INFORMATION Seabrook CEB Integrity TS 3.6.5.2 limiting condition for operation requires that CEB integrity shall be maintained during Modes 1, 2, 3 and 4. TS 3.6.5.2 includes an Action requirement to restore CEB integrity within 24 hours or be in Hot Standby within the next 6 hours and in Cold Shutdown within the following 30 hours when CEB integrity is not met for any reason. |
| | SR 4.6.5.2 requires that "Containment enclosure building integrity shall be demonstrated: a. At least once per 31 days by verifying that the door in each access opening is closed, except when the access opening is being used for normal transit entry or exit." Thus, the proposed SR 4.6.5.2 would not require entry into the TS 3.6.5.2 Action for opening access doors for normal transit entry or exit. |
| | While the Seabrook action requirements to restore CEB integrity within 24 hours of discovery of not having integrity for any reason (emphasis added) is consistent with the NRC staff position for enclosure building integrity not being met per NUREG-1431, Revision 4, Standard Technical Specifications for Westinghouse Plants, the comparison does not apply because the Seabrook access opening design departs from the design assumed by Standard Technical Specifications (STS). Seabrook CEB access openings are designed with a single door at each entry point whereas the STS design presumes an airlock with two doors at each entry point. Routine preventative maintenance (PM) on the Seabrook CEB doors, therefore, represents a loss of safety function, whereas, in the design modeled in the STS, there is no loss of safety function for the same maintenance activity. The NRC staff concern is that 24 hour allowance to restore CEB integrity (for any reason) is not an appropriate limit for operating Seabrook, because Seabrook TS 3.6.5.2 Actions do not address the additional CEB loss of safety function due to PM on door seals and door hardware. Routine maintenance on access opening doors is accomplished for the STS design without rendering CEB integrity not being met. Please revise Seabrook TS 3.6.5.2 Actions to provide appropriate limits that address the NRC staff concern. |
| | |
| | P. Freeman - 2 If you have questions, you can contact me at 301-415-3100 and/or 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:== |
|
| |
|
| Under Title 10 of the Code of Federal Regulations (10 CFR), Section SO.36(c)(2), Limiting conditions for operation.
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| Subsection (i) requires: "Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
| | PUBLIC LPLI-2 RIF RidsAcrsAcnw MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resource RidsRgn1 MailCenter Resource RidsNrrDssStsb Resource RidsNrrPMSeabrook Resource RidsNrrLAABaxter Resource RidsOgcRp Resource RidsNrrDraAadb Resource RidsNrrDraAhpb Resource |
| When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met." Under 10 CFR SO.36(3) Surveillance requirements, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 101390041 2 ADAMS Accession No. ML 102380100 3 ADAMS Accession No. ML 11266A041 4 ADAMS Accession No. ML 120790307 Enclosure
| | *via email OFFICE LPL1 STSB LPL1-21BC NAME CSchulten* MKhanna J.b,;;;D;.;..A~T,;;;;.E==:!b,;;;;"';;;;';;';;"====ib=6~/8~/2=-=O~12~ 6/0812012 6111/2012 OFFICIAL RECORD COpy}} |
| -3.0 REQUEST FOR ADDITIONAL Seabrook CEB Integrity TS 3.6.5.2 limiting condition for operation requires that CEB integrity shall be maintained during Modes 1, 2, 3 and 4. TS 3.6.5.2 includes an Action requirement to restore CEB integrity within 24 hours or be in Hot Standby within the next 6 hours and in Cold Shutdown within the following 30 hours when CEB integrity is not met for any reason. SR 4.6.5.2 requires that "Containment enclosure building integrity shall be demonstrated:
| |
| : a. At least once per 31 days by verifying that the door in each access opening is closed, except when the access opening is being used for normal transit entry or exit." Thus, the proposed SR 4.6.5.2 would not require entry into the TS 3.6.5.2 Action for opening access doors for normal transit entry or exit. While the Seabrook action requirements to restore CEB integrity within 24 hours of discovery of not having integrity for any reason (emphasis added) is consistent with the NRC staff position for enclosure building integrity not being met per NUREG-1431, Revision 4, Standard Technical Specifications for Westinghouse Plants, the comparison does not apply because the Seabrook access opening design departs from the design assumed by Standard Technical Specifications (STS). Seabrook CEB access openings are designed with a single door at each entry point whereas the STS design presumes an airlock with two doors at each entry point. Routine preventative maintenance (PM) on the Seabrook CEB doors, therefore, represents a loss of safety function, whereas, in the design modeled in the STS, there is no loss of safety function for the same maintenance activity.
| |
| The NRC staff concern is that 24 hour allowance to restore CEB integrity (for any reason) is not an appropriate limit for operating Seabrook, because Seabrook TS 3.6.5.2 Actions do not address the additional CEB loss of safety function due to PM on door seals and door hardware.
| |
| Routine maintenance on access opening doors is accomplished for the STS design without rendering CEB integrity not being met. Please revise Seabrook TS 3.6.5.2 Actions to provide appropriate limits that address the NRC staff concern.
| |
| P. Freeman -If you have questions, you can contact me at 301-415-3100 and/or 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 Request for Additional cc w/encl: Distribution via DISTRIBUTION:
| |
| PUBLIC LPLI-2 RIF RidsAcrsAcnw MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resource RidsRgn1 MailCenter Resource RidsNrrDssStsb Resource RidsNrrPMSeabrook Resource RidsNrrLAABaxter Resource RidsOgcRp Resource RidsNrrDraAadb Resource RidsNrrDraAhpb Resource *via email LPL1 OFFICE STSB LPL 1-21BC NAME CSchulten* | |
| MKhanna 6/0812012 6111/2012 OFFICIAL RECORD COpy}} | |
Letter Sequence RAI |
|---|
TAC:ME3988, Ventilation System Envelope Allowed Outage Time (Approved, Closed) |
|
MONTHYEARSBK-L-10074, License Amendment Request 10-022010-05-14014 May 2010
License Amendment Request 10-02
Project stage: Request
ML1016605532010-06-15015 June 2010
E-mail, Miller, to O'Keefe, Seabrook Acceptance Review LAR 10-02 Ceeacs LCO
Project stage: Acceptance Review
ML1021800132010-08-0505 August 2010
Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request Related to Containment Emergency Air Cleanup System
Project stage: Draft RAI
ML1122101392011-08-10010 August 2011
Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request 10-02 Regarding the Containment Enclosure Emergency Air Cleanup System
Project stage: Draft RAI
SBK-L-11184, Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System2011-09-16016 September 2011
Response to Request for Additional Information Regarding License Amendment Request 10-02, Regarding the Containment Enclosure Emergency Air Cleanup System
Project stage: Response to RAI
SBK-L-12054, Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2012-03-15015 March 2012
Response to Request for Additional Information Regarding License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
Project stage: Response to RAI
ML12156A2892012-06-11011 June 2012
Request for Additional Information Regarding the Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System
Project stage: RAI
SBK-L-12266, Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System2013-01-31031 January 2013
Supplement to License Amendment Request 10-02, Application for Change to the Technical Specifications for the Containment Enclosure Emergency Air Cleanup System
Project stage: Supplement
ML1130000632013-04-23023 April 2013
Issuance of Amendment Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System
Project stage: Approval
ML13114A3172013-04-25025 April 2013
Correction to Issuance of Amendment 136 Addition of Action Statement to Limiting Condition for Operation 3.6.5.1, Containment Enclosure Emergency Air Cleanup System
Project stage: Approval
2011-09-16
[Table View] |
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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024
Integrated Inspection Report 05000443/2024003
ML24303A0352024-10-29029 October 2024
Operator Licensing Examination Approval
IR 05000443/20244022024-10-17017 October 2024
Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only)
L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024
Core Operating Limits Report for Reload Cycle 24
ML24254A2552024-09-25025 September 2024
Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24239A5382024-09-20020 September 2024
Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000443/20240052024-08-29029 August 2024
Updated Inspection Plan for Seabrook Station (Report 05000443/2024005)
ML24232A1142024-08-21021 August 2024
Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024
Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be
L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024
Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .
IR 05000443/20240022024-08-0606 August 2024
Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001
L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024
Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024
Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024
Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
IR 05000443/20240102024-05-29029 May 2024
Biennial Problem Identification and Resolution Inspection Report 05000443/2024010
IR 05000443/20240112024-05-24024 May 2024
Age-Related Degradation Inspection Report 05000443/2024011
IR 05000443/20240012024-05-13013 May 2024
Integrated Inspection Report 05000443/2024001
L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024
NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio
ML24046A0512024-05-0707 May 2024
Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024
2023 Annual Radioactive Effluent Release Report
L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report
IR 05000443/20245012024-04-22022 April 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501
05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024
Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources
SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024
2023 Annual Environmental Operating Report
L-2024-011, 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 Applications2024-03-13013 March 2024
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
ML24067A2622024-03-0808 March 2024
Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances)
L-2024-038, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024
to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-037, to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024
to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
ML24065A2522024-03-0505 March 2024
Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033)
L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024
Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024
Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024
Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B
L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024
Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
IR 05000443/20230062024-02-28028 February 2024
Annual Assessment Letter for Seabrook Station (Report 05000443/2023006)
L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024
Radiological Emergency Plan (Ssrep), Revision 82
IR 05000443/20230042024-02-12012 February 2024
Integrated Inspection Report 05000443/2023004
ML24009A1152024-01-29029 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
2024-09-25
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
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
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
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 June 11, 2012 Mr. Paul Freeman Site Vice President clo Michael O'Keefe Seabrook Station NextEra Energy Seabrook. LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.5.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" (TAC NO. ME3988)
Dear Mr. Freeman:
By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16, 2011, 3 and March 15, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook). The proposed amendment would change TS Surveillance Requirement (SR) 4.6.5.1.d.4 so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS). The amendment relocates SR 4.6.5.1.d.4 with modifications to new SR 4.6.5.2.b. Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote.
The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained in the enclosed RAI. A draft of these questions was previously sent to Mr. Gary Kilby of your staff with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. Conference calls were held on May 25, June 4, and June 7,2012, and Mr. Kilby agreed that NextEra Energy Seabrook, LLC would respond to the RAI within 30 days of the date of this letter. Please note that if you do not respond to the RAI within 30 days, the NRC staff may reject your request for relief under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. "Denial of application for failure to supply information."
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML101390041 2 ADAMS Accession No. ML102380100 3 ADAMS Accession No. ML11266A041 4 ADAMS Accession No. ML120790307
P. Freeman -2 If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov.
G. Lamb~&.:f t Licensing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION THE ADDITION OF ACTION STATEMENT TO LIMITING CONDITION FOR OPERATION 3.6.S.1, "CONTAINMENT ENCLOSURE EMERGENCY AIR CLEANUP SYSTEM" NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT 1 DOCKET NUMBER S0-443 1.0 SCOPE By letter dated May 14, 2010,1 as supplemented by letters dated August 24,2010,2 September 16,2011,3 and March 1S, 2012,4 NextEra Energy Seabrook, LLC (NextEra or the licensee) submitted license amendment request (LAR) LAR 10-02 to revise the technical specifications (TSs) for Seabrook Station, Unit No.1 (Seabrook). The proposed amendment would change TS Surveillance Requirement (SR) 4.6.S.1.dA so that it will demonstrate integrity of the containment enclosure building (CEB) rather than operability of the Containment Enclosure Emergency Air Cleanup System (CEEACS). The amendment relocates SR 4.6.S.1.dA with modifications to new SR 4.6.S.2.b. Additionally, the amendment makes some minor wording changes, deletes a definition, and removes a moot footnote.
The U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required to complete its review. The NRC staff's request for additional information (RAI) is contained below.
2.0 BACKGROUND
Under Title 10 of the Code of Federal Regulations (10 CFR), Section SO.36(c)(2), Limiting conditions for operation. Subsection (i) requires: "Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met."
Under 10 CFR SO.36(3) Surveillance requirements, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML101390041 2 ADAMS Accession No. ML102380100 3 ADAMS Accession No. ML11266A041 4 ADAMS Accession No. ML120790307 Enclosure
- 2 3.0 REQUEST FOR ADDITIONAL INFORMATION Seabrook CEB Integrity TS 3.6.5.2 limiting condition for operation requires that CEB integrity shall be maintained during Modes 1, 2, 3 and 4. TS 3.6.5.2 includes an Action requirement to restore CEB integrity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> when CEB integrity is not met for any reason.
SR 4.6.5.2 requires that "Containment enclosure building integrity shall be demonstrated: a. At least once per 31 days by verifying that the door in each access opening is closed, except when the access opening is being used for normal transit entry or exit." Thus, the proposed SR 4.6.5.2 would not require entry into the TS 3.6.5.2 Action for opening access doors for normal transit entry or exit.
While the Seabrook action requirements to restore CEB integrity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of not having integrity for any reason (emphasis added) is consistent with the NRC staff position for enclosure building integrity not being met per NUREG-1431, Revision 4, Standard Technical Specifications for Westinghouse Plants, the comparison does not apply because the Seabrook access opening design departs from the design assumed by Standard Technical Specifications (STS). Seabrook CEB access openings are designed with a single door at each entry point whereas the STS design presumes an airlock with two doors at each entry point. Routine preventative maintenance (PM) on the Seabrook CEB doors, therefore, represents a loss of safety function, whereas, in the design modeled in the STS, there is no loss of safety function for the same maintenance activity. The NRC staff concern is that 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance to restore CEB integrity (for any reason) is not an appropriate limit for operating Seabrook, because Seabrook TS 3.6.5.2 Actions do not address the additional CEB loss of safety function due to PM on door seals and door hardware. Routine maintenance on access opening doors is accomplished for the STS design without rendering CEB integrity not being met. Please revise Seabrook TS 3.6.5.2 Actions to provide appropriate limits that address the NRC staff concern.
P. Freeman - 2 If you have questions, you can contact me at 301-415-3100 and/or 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:
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