ML15232A069: Difference between revisions

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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-0751 August 24,2015
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24,2015 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-0751


==SUBJECT:==
==SUBJECT:==
WATERFORD STEAM ELECTRIC STATION, UNIT 3 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISION TO CONTROL ELEMENT ASSEMBLY DROP TIMES (TAC NO. MF6459)  
WATERFORD STEAM ELECTRIC STATION, UNIT 3 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISION TO CONTROL ELEMENT ASSEMBLY DROP TIMES (TAC NO. MF6459)


==Dear Sir or Madam:==
==Dear Sir or Madam:==
By letter dated July 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15197A106), Entergy Operations, Inc. (the licensee) submitted a license amendment request for Waterford Steam Electric Station, Unit 3. The proposed amendment request would modify Technical Specification (TS) 3.1.3.4 to revise control element assembly drop times to be less than or equal to 3.5 seconds. By letter dated August 3, 2015 (ADAMS Accession No. ML15205A306), the U.S. Nuclear Regulatory Commission (NRC) staff informed the licensee that the submittal was incomplete but provided the licensee the opportunity to supplement the application to address the missing information.
 
By letter dated August 14, 2015 (ADAMS Accession No. ML15226A346), the licensee provided the requested supplement.
By letter dated July 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15197A106), Entergy Operations, Inc. (the licensee) submitted a license amendment request for Waterford Steam Electric Station, Unit 3. The proposed amendment request would modify Technical Specification (TS) 3.1.3.4 to revise control element assembly drop times to be less than or equal to 3.5 seconds. By letter dated August 3, 2015 (ADAMS Accession No. ML15205A306), the U.S. Nuclear Regulatory Commission (NRC) staff informed the licensee that the submittal was incomplete but provided the licensee the opportunity to supplement the application to address the missing information. By letter dated August 14, 2015 (ADAMS Accession No. ML15226A346), the licensee provided the requested supplement.
The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request and supplement.
The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request and supplement. 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 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 (10 CFR), 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), 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.
Section 50.34 of 10 CFR addresses the content of technical information required.
The NRC staff has reviewed your application and concluded that it does provide 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
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 does provide 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.
Vice President, Operations                 adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
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 Vice President, Operations 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 301-415-3229 or michael.orenak@nrc.gov.
If you have any questions, please contact me at 301-415-3229 or michael.orenak@nrc.gov.
Docket No. 50-382 cc: Distribution via Listserv Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Vice President, Operations  adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 cc: Distribution via Listserv
If you have any questions, please contact me at 301-415-3229 or michael.orenak@nrc.gov.
 
Docket No. 50-382 cc: Distribution via Listserv DISTRIBUTION:
ML15232A069 OFFICE DORL/LPL4-2/PM     DORL/LPL4-2/LA           DSS/SRXB/BC   DORL/LPL4-2/BC DORL/LPL4-2/PM NAME     MOrenak         PBlechman (LRonewicz for) CJackson     MKhanna         MOrenak DATE     8/21/15         8/20/15                   8/21/15       8/24/15         8/24/15}}
PUBLIC RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrPMWaterford Resource RidsRgn4MailCenter Resource RBeaton, NRR PClifford, NRR RidsNrrDssSrxb Resource ADAMS Accession No.: ML15232A069 OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA Sincerely, IRA Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL4-2 R/F RidsNRRLIC109 Resource RidsNrrDorllpl4-2 Resource RidsNrrLAPBlechman Resource SSun, NRR JParillo, NRR RidsNrrDraArcb Resource RidsNrrDorl Resource DSS/SRXB/BC DORL/LPL4-2/BC DORL/LPL4-2/PM NAME MOrenak PBlechman (LRonewicz for) CJackson MKhanna MOrenak DATE 8/21/15 8/20/15 8/21/15 8/24/15 8/24/15 OFFICIAL RECORD COPY}}

Latest revision as of 07:42, 31 October 2019

Acceptance of Requested Licensing Action Revision to Control Element Assemble Drop Times
ML15232A069
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/24/2015
From: Michael Orenak
Plant Licensing Branch IV
To:
Entergy Operations
Wang A
References
TAC MF6459
Download: ML15232A069 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24,2015 Vice President, Operations Entergy Operations, Inc.

Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-0751

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVISION TO CONTROL ELEMENT ASSEMBLY DROP TIMES (TAC NO. MF6459)

Dear Sir or Madam:

By letter dated July 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15197A106), Entergy Operations, Inc. (the licensee) submitted a license amendment request for Waterford Steam Electric Station, Unit 3. The proposed amendment request would modify Technical Specification (TS) 3.1.3.4 to revise control element assembly drop times to be less than or equal to 3.5 seconds. By letter dated August 3, 2015 (ADAMS Accession No. ML15205A306), the U.S. Nuclear Regulatory Commission (NRC) staff informed the licensee that the submittal was incomplete but provided the licensee the opportunity to supplement the application to address the missing information. By letter dated August 14, 2015 (ADAMS Accession No. ML15226A346), the licensee provided the requested supplement.

The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request and supplement. 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 (10 CFR), 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.

The NRC staff has reviewed your application and concluded that it does provide 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

Vice President, Operations 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 301-415-3229 or michael.orenak@nrc.gov.

Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 cc: Distribution via Listserv

ML15232A069 OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA DSS/SRXB/BC DORL/LPL4-2/BC DORL/LPL4-2/PM NAME MOrenak PBlechman (LRonewicz for) CJackson MKhanna MOrenak DATE 8/21/15 8/20/15 8/21/15 8/24/15 8/24/15