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| {{#Wiki_filter:November 22, 2006Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874 | | {{#Wiki_filter:November 22, 2006 Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSEAMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791) | | REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791) |
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| ==Dear Mr. St. Pierre:== | | ==Dear Mr. St. Pierre:== |
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| By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendmentrequest (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changesproposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." The Nuclear Regulatory Commission staff has been reviewing the submittal and hasdetermined that additional information is needed to complete its review. These questions were discussed with Mr. Michael O'Keefe of your staff on October 12, 2006. In order to complete our review of LAR 06-03 in a timely manner, a response to this request foradditional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter. Please note that if you do not respond to this letter within 45 days or provide an acceptablealternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can bereached at (301) 415-2481. Sincerely,/RA Richard Ennis for/G. Edward Miller, Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-443 | | By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink. |
| | The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. Michael OKeefe of your staff on October 12, 2006. |
| | In order to complete our review of LAR 06-03 in a timely manner, a response to this request for additional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter. |
| | Please note that if you do not respond to this letter within 45 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-2481. |
| | Sincerely, |
| | /RA Richard Ennis for/ |
| | G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page November 22, 2006Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874 | | |
| | Request for Additional Information cc w/encl: See next page |
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| | November 22, 2006 Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSEAMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791) | | REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791) |
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| ==Dear Mr. St. Pierre:== | | ==Dear Mr. St. Pierre:== |
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| By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendmentrequest (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changesproposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." The Nuclear Regulatory Commission staff has been reviewing the submittal and hasdetermined that additional information is needed to complete its review. These questions were discussed with Mr. Michael O'Keefe of your staff on October 12, 2006. In order to complete our review of LAR 06-03 in a timely manner, a response to this request foradditional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter. Please note that if you do not respond to this letter within 45 days or provide an acceptablealternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can bereached at (301) 415-2481. Sincerely,/RA Richard Ennis for/G. Edward Miller, Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-443 | | By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink. |
| | The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. Michael OKeefe of your staff on October 12, 2006. |
| | In order to complete our review of LAR 06-03 in a timely manner, a response to this request for additional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter. |
| | Please note that if you do not respond to this letter within 45 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-2481. |
| | Sincerely, |
| | /RA Richard Ennis for/ |
| | G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc w/encl: See next page DISTRIBUTION:PUBLICRidsNrrDorlLpl1-2RidsNrrPMGMillerRidsOgcMailCenter LPL1-2 R/FRidsNrrLACRaynorRidsAcrsAcnwMailCenterJTatum
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| RidsNrrDssSbpbADAMS Accession Number:
| | Request for Additional Information cc w/encl: See next page DISTRIBUTION: |
| ML063050698OFFICELPL1-2/PMLPL1-2/LADSS/SBPB/BCLPL1-2/BCNAMEGEMillerCRaynorJSegalaHchernoff (REnnis for)DATE11/14/200611/14/200611/01/0611/22/2006OFFICIAL RECORD COPY Seabrook Station, Unit No. 1 cc:
| | PUBLIC RidsNrrDorlLpl1-2 RidsNrrPMGMiller RidsOgcMailCenter LPL1-2 R/F RidsNrrLACRaynor RidsAcrsAcnwMailCenter JTatum RidsNrrDssSbpb ADAMS Accession Number: ML063050698 OFFICE LPL1-2/PM LPL1-2/LA DSS/SBPB/BC LPL1-2/BC NAME GEMiller CRaynor JSegala Hchernoff (REnnis for) |
| Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. Peter BrannAssistant Attorney General State House, Station #6 Augusta, ME 04333Resident InspectorU.S. Nuclear Regulatory Commission Seabrook Nuclear Power Station P.O. Box 1149 Seabrook, NH 03874Town of Exeter10 Front Street Exeter, NH 03823Regional Administrator, Region IU.S. Nuclear Regulatory Commission | | DATE 11/14/2006 11/14/2006 11/01/06 11/22/2006 OFFICIAL RECORD COPY |
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| | Seabrook Station, Unit No. 1 cc: |
| | Mr. J. A. Stall Ms. Cristine McComb, Director Senior Vice President, Nuclear and ATTN: John Giarrusso Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Ms. Kelly Ayotte, Attorney General Mr. Peter Brann Mr. Orvil Fitch, Deputy Attorney General Assistant Attorney General 33 Capitol Street State House, Station #6 Concord, NH 03301 Augusta, ME 04333 Mr. Christopher M. Pope, Director Resident Inspector Homeland Security & Emergency Mgmt. |
| | U.S. Nuclear Regulatory Commission New Hampshire Department of Safety Seabrook Nuclear Power Station Bureau of Emergency Management P.O. Box 1149 33 Hazen Drive Seabrook, NH 03874 Concord, NH 03301 Town of Exeter Mr. M. S. Ross, Managing Attorney 10 Front Street Florida Power & Light Company Exeter, NH 03823 P.O. Box 14000 Juno Beach, FL 33408-0420 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Rajiv S. Kundalkar 475 Allendale Road Vice President - Nuclear Engineering King of Prussia, PA 19406 Florida Power & Light Company P.O. Box 14000 Office of the Attorney General Juno Beach, FL 33408-0420 One Ashburton Place, 20th Floor Boston, MA 02108 James M. Peschel Regulatory Programs Manager Board of Selectmen FPL Energy Seabrook, LLC Town of Amesbury PO Box 300 Town Hall Seabrook, NH 03874 Amesbury, MA 01913 Ms. Marjan Mashhadi Mr. Robert Poole Senior Attorney Federal Emergency Management Agency Florida Power & Light Company Region I 801 Pennsylvania Ave., NW Suite 220 J.W. McCormack P.O. & Washington, DC 20004 Courthouse Building, Room 401 Boston, MA 02109 Mr. Mark E. Warner Vice President, Nuclear Operations Support Mr. Tom Crimmins Florida Power & Light Company Polestar Applied Technology P.O. Box 14000 One First Street, Suite 4 Juno Beach, FL 33408-0420 Los Altos, CA 94019 |
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| | REQUEST FOR ADDITIONAL INFORMATION MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES FPL ENERGY SEABROOK, LLC SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated August 7, 2006, FPL Energy Seabrook, LLC (FPLE) submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 (Seabrook) Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink. The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that the following additional information is needed to complete its review with respect to the aforementioned TS sections: |
| | : 1. TS Table 3.3-9 lists components requiring operable remote safe shutdown controls. |
| | The table currently includes the turbine driven emergency feedwater (TDEFW) pump steam supply valves MS-V-127 and MS-V-128. These valves were also relied upon for addressing Title 10 of the Code of Federal Regulations (CFR 50), Appendix A, General Design Criteria (GDC) 57. FPLE stated that a design change was implemented in 1991 to replace the pneumatic actuators on these valves with gear operated manual actuators. The design change also upgraded the downstream branch header remote/manual isolation valves MS-V-393 and MS-V-394 for use as the containment isolation valves. |
| | : a. Among other things, GDC 57 states that the containment isolation valve be located as close to the containment as practical, and valves MS-V-393 and MS-V-394 are located downstream of valves MS-V-127 and MS-V-128. Please elaborate on the 1991 plant design changes that were made and justify how they continue to address this particular provision of GDC 57. |
| | : b. Explain what impact the 1991 plant design change has on the capability to mitigate a high energy line break of the TDEFW pump steam supply line, taking into consideration single active failure considerations. |
| | : 2. Seabrook TS 3.7.4 specifies the actions that are required for an inoperable service water system/ultimate heat sink. Action e. requires the portable tower makeup pump system to be restored to its required condition within 72 hours if the system is not stored in its operational readiness state. Action e. also contains a requirement to notify the NRC within one hour in accordance with 10 CFR 50.72 if the portable tower makeup pump system is not restored to its design operational readiness state within 72 hours. |
| | The LAR proposes to eliminate the 1 hour reporting requirement because the condition does not meet the immediate reporting requirements of 10 CFR 50.72; and the LAR also proposes a requirement to implement actions, within the next 96 hours, that ensure |
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| 475 Allendale Road King of Prussia, PA 19406Office of the Attorney GeneralOne Ashburton Place, 20th Floor Boston, MA 02108Board of SelectmenTown of Amesbury Town Hall Amesbury, MA 01913Mr. Robert PooleFederal Emergency Management Agency Region I J.W. McCormack P.O. &
| | an adequate supply of makeup water for the service water cooling tower for a minimum of 30 days. |
| Courthouse Building, Room 401 Boston, MA 02109Mr. Tom CrimminsPolestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019Ms. Cristine McComb, DirectorATTN: John Giarrusso Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399Ms. Kelly Ayotte, Attorney GeneralMr. Orvil Fitch, Deputy Attorney General 33 Capitol Street Concord, NH 03301Mr. Christopher M. Pope, DirectorHomeland Security & Emergency Mgmt.
| | TS 3.7.4 for Seabrook differs from the Standard Technical Specification (STS) in that it allows continued plant operation when the UHS is inoperable due to insufficient water inventory; whereas the STS requires that the plant enter a shutdown action requirement. |
| New Hampshire Department of Safety Bureau of Emergency Management 33 Hazen Drive Concord, NH 03301Mr. M. S. Ross, Managing AttorneyFlorida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. Rajiv S. KundalkarVice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420James M. PeschelRegulatory Programs Manager FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874Ms. Marjan MashhadiSenior Attorney Florida Power & Light Company 801 Pennsylvania Ave., NW Suite 220 Washington, DC 20004Mr. Mark E. WarnerVice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 REQUEST FOR ADDITIONAL INFORMATION MISCELLANEOUS TECHNICAL SPECIFICATION CHANGESFPL ENERGY SEABROOK, LLCSEABROOK STATION, UNIT NO. 1DOCKET NO. 50-443By letter dated August 7, 2006, FPL Energy Seabrook, LLC (FPLE) submitted licenseamendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 (Seabrook) Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, "Remote Shutdown System," and TS 3.7.4, "Service Water System/Ultimate Heat Sink." The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that the following additional information is needed to complete its review with respect to the aforementioned TS sections: 1.TS Table 3.3-9 lists components requiring operable remote safe shutdown controls. The table currently includes the turbine driven emergency feedwater (TDEFW) pump steam supply valves MS-V-127 and MS-V-128. These valves were also relied upon for addressing Title 10 of the Code of Federal Regulations (CFR 50), Appendix A, GeneralDesign Criteria (GDC) 57. FPLE stated that a design change was implemented in 1991 to replace the pneumatic actuators on these valves with gear operated manual actuators. The design change also upgraded the downstream branch header remote/manual isolation valves MS-V-393 and MS-V-394 for use as the containment isolation valves.a.Among other things, GDC 57 states that the containment isolation valve belocated as close to the containment as practical, and valves MS-V-393 and MS-V-394 are located downstream of valves MS-V-127 and MS-V-128. Please elaborate on the 1991 plant design changes that were made and justify how they continue to address this particular provision of GDC 57.b.Explain what impact the 1991 plant design change has on the capability tomitigate a high energy line break of the TDEFW pump steam supply line, taking into consideration single active failure considerations.2.Seabrook TS 3.7.4 specifies the actions that are required for an inoperable servicewater system/ultimate heat sink. Action e. requires the portable tower makeup pump system to be restored to its required condition within 72 hours if the system is not stored in its operational readiness state. Action e. also contains a requirement to notify the NRC within one hour in accordance with 10 CFR 50.72 if the portable tower makeup pump system is not restored to its design operational readiness state within 72 hours.
| | Because the cooling tower basin for Seabrook is not large enough to store 30 days worth of cooling water, the NRC staff allowed the makeup capability of a portable cooling tower makeup pump system to be credited. However, means other than the portable cooling tower makeup pump system for ensuring the required 30 day cooling water inventory for Seabrook have not been approved by the NRC. Therefore, if the portable cooling tower makeup pump system should become inoperable for more than the allowed outage time, prompt NRC notification and oversight would be necessary to assure that: (a) the situation is being adequately resolved, and (b) alternate means that are credited in the interim for ensuring cooling tower makeup capability are acceptable to the NRC staff. |
| The LAR proposes to eliminate the 1 hour reporting requirement because the condition does not meet the immediate reporting requirements of 10 CFR 50.72; and the LAR also proposes a requirement to implement actions, within the next 96 hours, that ensure an adequate supply of makeup water for the service water cooling tower for a minimumof 30 days.TS 3.7.4 for Seabrook differs from the Standard Technical Specification (STS) in that itallows continued plant operation when the UHS is inoperable due to insufficient water inventory; whereas the STS requires that the plant enter a shutdown action requirement.
| | Although the current 1-hour reporting requirements specified by 10 CFR 50.72 may no longer be applicable to the condition referred to in TS 3.7.4, the considerations discussed above continue to be valid. Therefore, to justify that the proposed changes are still considered to be appropriate, please address the considerations referred to above.}} |
| Because the cooling tower basin for Seabrook is not large enough to store 30 days worth of cooling water, the NRC staff allowed the makeup capability of a portable cooling tower makeup pump system to be credited. However, means other than the portable cooling tower makeup pump system for ensuring the required 30 day cooling water inventory for Seabrook have not been approved by the NRC. Therefore, if the portable cooling tower makeup pump system should become inoperable for more than the allowed outage time, prompt NRC notification and oversight would be necessary to assure that: (a) the situation is being adequately resolved, and (b) alternate means that are credited in the interim for ensuring cooling tower makeup capability are acceptable to the NRC staff.Although the current 1-hour reporting requirements specified by 10 CFR 50.72 may nolonger be applicable to the condition referred to in TS 3.7.4, the considerations discussed above continue to be valid. Therefore, to justify that the proposed changes are still considered to be appropriate, please address the considerations referred to above.}} | |
Letter Sequence RAI |
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MONTHYEARML0630506982006-11-22022 November 2006
Request for Additional Information Regarding License Amendment Request for Miscellaneous Technical Specification Changes
Project stage: RAI
SBK-L-06243, Response to Request for Additional Information Regarding License Amendment Request 06-03, Application for Amendment to Technical Specifications for Miscellaneous Changes2007-01-22022 January 2007
Response to Request for Additional Information Regarding License Amendment Request 06-03, Application for Amendment to Technical Specifications for Miscellaneous Changes
Project stage: Response to RAI
ML0712404492007-05-0303 May 2007
Draft Request for Additional Information
Project stage: Draft RAI
SBK-L-07087, Revised No Significant Hazards Consideration Determination for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes.2007-05-14014 May 2007
Revised No Significant Hazards Consideration Determination for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes.
Project stage: Request
SBK-L-07139, Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes2007-08-0707 August 2007
Response to Request for Additional Information for License Amendment Request 06-03, Application for Amendment to the Technical Specifications for Miscellaneous Changes
Project stage: Response to RAI
ML0723901902007-08-23023 August 2007
Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity.
Project stage: Other
ML0722604592007-08-23023 August 2007
Issuance of Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity.
Project stage: Approval
ML0735320412008-03-0707 March 2008
Summary of Conference Call and Request for Additional Information Regarding the Fall 2006 Steam Generator Inspections
Project stage: RAI
SBK-L-08102, Response to Request for Additional Information Related to Steam Generator Inspections Performed During the Eleventh Refueling Outage2008-06-18018 June 2008
Response to Request for Additional Information Related to Steam Generator Inspections Performed During the Eleventh Refueling Outage
Project stage: Response to RAI
2007-05-03
[Table View] |
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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
[Table view] |
Text
November 22, 2006 Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791)
Dear Mr. St. Pierre:
By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink.
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. Michael OKeefe of your staff on October 12, 2006.
In order to complete our review of LAR 06-03 in a timely manner, a response to this request for additional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter.
Please note that if you do not respond to this letter within 45 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-2481.
Sincerely,
/RA Richard Ennis for/
G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: See next page
November 22, 2006 Mr. Gene F. St. Pierre, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES (TAC NO. MD2791)
Dear Mr. St. Pierre:
By letter dated August 7, 2006, FPL Energy Seabrook, LLC submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink.
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. These questions were discussed with Mr. Michael OKeefe of your staff on October 12, 2006.
In order to complete our review of LAR 06-03 in a timely manner, a response to this request for additional information is required to be provided within 45 days. If you cannot respond within 45 days, please inform us in writing why you cannot response and provide an alternate response date. This alternate response date must be no later than 60 days from the date of this letter.
Please note that if you do not respond to this letter within 45 days or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-2481.
Sincerely,
/RA Richard Ennis for/
G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-2 RidsNrrPMGMiller RidsOgcMailCenter LPL1-2 R/F RidsNrrLACRaynor RidsAcrsAcnwMailCenter JTatum RidsNrrDssSbpb ADAMS Accession Number: ML063050698 OFFICE LPL1-2/PM LPL1-2/LA DSS/SBPB/BC LPL1-2/BC NAME GEMiller CRaynor JSegala Hchernoff (REnnis for)
DATE 11/14/2006 11/14/2006 11/01/06 11/22/2006 OFFICIAL RECORD COPY
Seabrook Station, Unit No. 1 cc:
Mr. J. A. Stall Ms. Cristine McComb, Director Senior Vice President, Nuclear and ATTN: John Giarrusso Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Ms. Kelly Ayotte, Attorney General Mr. Peter Brann Mr. Orvil Fitch, Deputy Attorney General Assistant Attorney General 33 Capitol Street State House, Station #6 Concord, NH 03301 Augusta, ME 04333 Mr. Christopher M. Pope, Director Resident Inspector Homeland Security & Emergency Mgmt.
U.S. Nuclear Regulatory Commission New Hampshire Department of Safety Seabrook Nuclear Power Station Bureau of Emergency Management P.O. Box 1149 33 Hazen Drive Seabrook, NH 03874 Concord, NH 03301 Town of Exeter Mr. M. S. Ross, Managing Attorney 10 Front Street Florida Power & Light Company Exeter, NH 03823 P.O. Box 14000 Juno Beach, FL 33408-0420 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Rajiv S. Kundalkar 475 Allendale Road Vice President - Nuclear Engineering King of Prussia, PA 19406 Florida Power & Light Company P.O. Box 14000 Office of the Attorney General Juno Beach, FL 33408-0420 One Ashburton Place, 20th Floor Boston, MA 02108 James M. Peschel Regulatory Programs Manager Board of Selectmen FPL Energy Seabrook, LLC Town of Amesbury PO Box 300 Town Hall Seabrook, NH 03874 Amesbury, MA 01913 Ms. Marjan Mashhadi Mr. Robert Poole Senior Attorney Federal Emergency Management Agency Florida Power & Light Company Region I 801 Pennsylvania Ave., NW Suite 220 J.W. McCormack P.O. & Washington, DC 20004 Courthouse Building, Room 401 Boston, MA 02109 Mr. Mark E. Warner Vice President, Nuclear Operations Support Mr. Tom Crimmins Florida Power & Light Company Polestar Applied Technology P.O. Box 14000 One First Street, Suite 4 Juno Beach, FL 33408-0420 Los Altos, CA 94019
REQUEST FOR ADDITIONAL INFORMATION MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES FPL ENERGY SEABROOK, LLC SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443 By letter dated August 7, 2006, FPL Energy Seabrook, LLC (FPLE) submitted license amendment request (LAR) 06-03. The LAR requested to revise various sections of the Seabrook Station, Unit No. 1 (Seabrook) Technical Specifications (TSs). This letter relates specifically to the changes proposed for TS 3.3.9, Remote Shutdown System, and TS 3.7.4, Service Water System/Ultimate Heat Sink. The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that the following additional information is needed to complete its review with respect to the aforementioned TS sections:
- 1. TS Table 3.3-9 lists components requiring operable remote safe shutdown controls.
The table currently includes the turbine driven emergency feedwater (TDEFW) pump steam supply valves MS-V-127 and MS-V-128. These valves were also relied upon for addressing Title 10 of the Code of Federal Regulations (CFR 50), Appendix A, General Design Criteria (GDC) 57. FPLE stated that a design change was implemented in 1991 to replace the pneumatic actuators on these valves with gear operated manual actuators. The design change also upgraded the downstream branch header remote/manual isolation valves MS-V-393 and MS-V-394 for use as the containment isolation valves.
- a. Among other things, GDC 57 states that the containment isolation valve be located as close to the containment as practical, and valves MS-V-393 and MS-V-394 are located downstream of valves MS-V-127 and MS-V-128. Please elaborate on the 1991 plant design changes that were made and justify how they continue to address this particular provision of GDC 57.
- b. Explain what impact the 1991 plant design change has on the capability to mitigate a high energy line break of the TDEFW pump steam supply line, taking into consideration single active failure considerations.
- 2. Seabrook TS 3.7.4 specifies the actions that are required for an inoperable service water system/ultimate heat sink. Action e. requires the portable tower makeup pump system to be restored to its required condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the system is not stored in its operational readiness state. Action e. also contains a requirement to notify the NRC within one hour in accordance with 10 CFR 50.72 if the portable tower makeup pump system is not restored to its design operational readiness state within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The LAR proposes to eliminate the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reporting requirement because the condition does not meet the immediate reporting requirements of 10 CFR 50.72; and the LAR also proposes a requirement to implement actions, within the next 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, that ensure
an adequate supply of makeup water for the service water cooling tower for a minimum of 30 days.
TS 3.7.4 for Seabrook differs from the Standard Technical Specification (STS) in that it allows continued plant operation when the UHS is inoperable due to insufficient water inventory; whereas the STS requires that the plant enter a shutdown action requirement.
Because the cooling tower basin for Seabrook is not large enough to store 30 days worth of cooling water, the NRC staff allowed the makeup capability of a portable cooling tower makeup pump system to be credited. However, means other than the portable cooling tower makeup pump system for ensuring the required 30 day cooling water inventory for Seabrook have not been approved by the NRC. Therefore, if the portable cooling tower makeup pump system should become inoperable for more than the allowed outage time, prompt NRC notification and oversight would be necessary to assure that: (a) the situation is being adequately resolved, and (b) alternate means that are credited in the interim for ensuring cooling tower makeup capability are acceptable to the NRC staff.
Although the current 1-hour reporting requirements specified by 10 CFR 50.72 may no longer be applicable to the condition referred to in TS 3.7.4, the considerations discussed above continue to be valid. Therefore, to justify that the proposed changes are still considered to be appropriate, please address the considerations referred to above.
