ML13262A374: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 22, 2013 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 | ||
==SUBJECT:== | ==SUBJECT:== | ||
SEABROOK STATION, UNIT NO.1 -ACCEPTANCE LETTER REGARDING LICENSE AMENDMENT REQUEST 13-05, "FIXED INCORE DETECTOR SYSTEM ANALYSIS METHODOLOGY" (TAC NO. MF2751) | SEABROOK STATION, UNIT NO.1 -ACCEPTANCE LETTER REGARDING LICENSE AMENDMENT REQUEST 13-05, "FIXED INCORE DETECTOR SYSTEM ANALYSIS METHODOLOGY" (TAC NO. MF2751) | ||
==Dear Mr. Walsh:== | ==Dear Mr. Walsh:== | ||
By letter dated September 10, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13260A159), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-05 for Seabrook Station, Unit No. 1 (Seabrook). | |||
The proposed change is to the Seabrook Technical Specification (TS). Specifically, the proposed amendment would revise TS 6.8.1.6.b, "Core Operating Limits Report," by adding Areva Licensing Report ANP-3243P, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis Supplement to YAEC-1855PA," which supplements and modifies the previously approved methodology in YAEC-18855PA, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis," October 1992. The proposed change also modifies the surveillance requirements associated with the heat flux hot channel factor and nuclear enthalpy rise hot channel factor to include revised uncertainty values when measurement is obtained using the fixed incore detector system. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment. | By letter dated September 10, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13260A159), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-05 for Seabrook Station, Unit No. 1 (Seabrook). The proposed change is to the Seabrook Technical Specification (TS). Specifically, the proposed amendment would revise TS 6.8.1.6.b, "Core Operating Limits Report," by adding Areva Licensing Report ANP-3243P, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis Supplement to YAEC-1855PA," which supplements and modifies the previously approved methodology in YAEC-18855PA, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis," October 1992. The proposed change also modifies the surveillance requirements associated with the heat flux hot channel factor and nuclear enthalpy rise hot channel factor to include revised uncertainty values when measurement is obtained using the fixed incore detector system. | ||
The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | ||
Section 50.34 of 10 CFR addresses the content of technical information required. | Consistent with Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | |||
K. Walsh The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | K. Walsh The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | ||
If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | |||
If you have any questions, please contact me at (301) 415-3100. | If you have any questions, please contact me at (301) 415-3100. | ||
Sincerely, | |||
. Lamb, Senior Project Manager t Licensing Branch 1-2 1 ision of Operating Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv | |||
Docket No. 50-443 cc: Distribution via Listserv | ML13262A374 OFFICE LPL 1-2/PM LPL 1-2/LA* LPL 1-2/PM NAME Jlamb ABaxter Jlamb DATE 11/22/13 09/23/13 11/22/13}} | ||
Latest revision as of 13:21, 4 November 2019
| ML13262A374 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/22/2013 |
| From: | John Lamb Plant Licensing Branch 1 |
| To: | Ossing M, Walsh K NextEra Energy Seabrook |
| Lamb J | |
| References | |
| LAR 13-05, TAC MF2751 | |
| Download: ML13262A374 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 22, 2013 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO.1 -ACCEPTANCE LETTER REGARDING LICENSE AMENDMENT REQUEST 13-05, "FIXED INCORE DETECTOR SYSTEM ANALYSIS METHODOLOGY" (TAC NO. MF2751)
Dear Mr. Walsh:
By letter dated September 10, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13260A159), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-05 for Seabrook Station, Unit No. 1 (Seabrook). The proposed change is to the Seabrook Technical Specification (TS). Specifically, the proposed amendment would revise TS 6.8.1.6.b, "Core Operating Limits Report," by adding Areva Licensing Report ANP-3243P, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis Supplement to YAEC-1855PA," which supplements and modifies the previously approved methodology in YAEC-18855PA, "Seabrook Station, Unit 1 Fixed lncore Detector System Analysis," October 1992. The proposed change also modifies the surveillance requirements associated with the heat flux hot channel factor and nuclear enthalpy rise hot channel factor to include revised uncertainty values when measurement is obtained using the fixed incore detector system.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
K. Walsh The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3100.
Sincerely,
. Lamb, Senior Project Manager t Licensing Branch 1-2 1 ision of Operating Reactor Licensing ice of Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv
ML13262A374 OFFICE LPL 1-2/PM LPL 1-2/LA* LPL 1-2/PM NAME Jlamb ABaxter Jlamb DATE 11/22/13 09/23/13 11/22/13