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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. | ||
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 September 23, 2014 | ||
==SUBJECT:== | ==SUBJECT:== | ||
INDIAN POINT NUCLEAR GENERATING UNIT 3- ACCEPTANCE OF AMENDMENT TO CHANGE VESSEL PRESSURE/TEMPERATURE LIMIT CURVES (TAC NO. MF3754) | INDIAN POINT NUCLEAR GENERATING UNIT 3-ACCEPTANCE OF AMENDMENT TO CHANGE VESSEL PRESSURE/TEMPERATURE LIMIT CURVES (TAC NO. MF3754) | ||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
By {{letter dated|date=April 1, 2014|text=letter dated April 1, 2014}} (Agencywide Document Access and Management System (ADAMS) Accession No. ML14099A333), Entergy Nuclear Operations, Inc. submitted a license amendment request for Indian Point Nuclear Generating Unit 3. The proposed amendment would revise Technical Specifications Figure 3.4.3.1, Heatup Limitations for Reactor Coolant System, Figure 3.4.3-2, Cooldown Limitations for Reactor Coolant System, and Figure 3.4.3-3, Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System, to indicate that the curves are applicable for vacuum fill. 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 request. 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. | |||
By letter dated April 1, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14099A333), Entergy Nuclear Operations, Inc. submitted a license amendment request for Indian Point Nuclear Generating Unit 3. The proposed amendment would revise Technical Specifications Figure 3.4.3.1, Heatup Limitations for Reactor Coolant System, Figure 3.4.3-2, Cooldown Limitations for Reactor Coolant System, and Figure 3.4.3-3, Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System, to indicate that the curves are applicable for vacuum fill. 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 request. 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. | 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 Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the technical specifications) 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. | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the technical specifications) 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. | ||
The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | ||
If you have any questions, please contact me at (301) 415-1364. | If you have any questions, please contact me at (301) 415-1364. | ||
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | Docket No. 50-286 cc: Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | ||
ML14253A048 OFFICE | ML14253A048 Sincerely, IRA/ | ||
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcMaiiCenter Resource LPLI-1 RIF RidsRg1 MaiiCenter Resource RidsNrrDoriLpl-1 Resource RidsNrrPMDPickett Resource RGrover CFairbanks OFFICE N RR/DORULPLI-1/PM NRR/DORULPLI-1/PM NRR/DORL/LPLI-1/LA NRR/DORULPLI-1/BC NAME DRender DPickett KGoldstein BBeasley DATE 09/22/2014 09/22/2014 09/22/14 09/23/2014}} | |||
Latest revision as of 17:04, 10 January 2025
| ML14253A048 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/23/2014 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Pickett D | |
| References | |
| TAC MF3754 | |
| Download: ML14253A048 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 September 23, 2014
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT 3-ACCEPTANCE OF AMENDMENT TO CHANGE VESSEL PRESSURE/TEMPERATURE LIMIT CURVES (TAC NO. MF3754)
Dear Sir or Madam:
By letter dated April 1, 2014 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14099A333), Entergy Nuclear Operations, Inc. submitted a license amendment request for Indian Point Nuclear Generating Unit 3. The proposed amendment would revise Technical Specifications Figure 3.4.3.1, Heatup Limitations for Reactor Coolant System, Figure 3.4.3-2, Cooldown Limitations for Reactor Coolant System, and Figure 3.4.3-3, Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System, to indicate that the curves are applicable for vacuum fill. 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 request. 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 Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the technical specifications) 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.
The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-1364.
Docket No. 50-286 cc: Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML14253A048 Sincerely, IRA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsOgcMaiiCenter Resource LPLI-1 RIF RidsRg1 MaiiCenter Resource RidsNrrDoriLpl-1 Resource RidsNrrPMDPickett Resource RGrover CFairbanks OFFICE N RR/DORULPLI-1/PM NRR/DORULPLI-1/PM NRR/DORL/LPLI-1/LA NRR/DORULPLI-1/BC NAME DRender DPickett KGoldstein BBeasley DATE 09/22/2014 09/22/2014 09/22/14 09/23/2014