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| number = ML14111A100
| number = ML14111A100
| issue date = 04/30/2014
| issue date = 04/30/2014
| title = Wolf Creek Generating Station - Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term (TAC No. MF25
| title = Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
| author name = Lyon C F
| author name = Lyon C
| author affiliation = NRC/NRR/DORL/LPLIV-1
| author affiliation = NRC/NRR/DORL/LPLIV-1
| addressee name = Heflin A C
| addressee name = Heflin A
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| docket = 05000482
| docket = 05000482
| license number = NPF-042
| license number = NPF-042
| contact person = Lyon C F
| contact person = Lyon C
| case reference number = TAC MF2574
| case reference number = TAC MF2574
| document type = Letter, Request for Additional Information (RAI)
| document type = Letter, Request for Additional Information (RAI)
| page count = 3
| page count = 3
| project = TAC:MF2574
| stage = RAI
}}
}}
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
==SUBJECT:==
WOLF CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION RE: TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS (TAC NO. MF2574)
==Dear Mr. Heflin:==
By application dated August 13, 2013, to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents Access and Management System (ADAMS) package Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (the licensee) requested a license amendment for Wolf Creek Generating Station, to revise the Technical Specifications to support transition to the Westinghouse core design and safety analysis.
The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed questions were provided to Mr. S. Wideman of your staff on April18, 2014. Please provide a response to the questions within 90 days of the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of NRC staff resources. If circumstances result in the need to revise the requested response date, please contact me at 301-415-2296 or via e-mail at Fred. Lyon@nrc.gov.
Sincerely, 0Rr Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 Enclosure Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 By application dated August 13, 2013, to the U.S. Nuclear Regulatory Commission (NRC)
(Agencywide Documents Access and Management System (ADAMS) package Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) requested a license amendment for Wolf Creek Generating Station (WCGS), to revise the Technical Specifications (TSs) to support transition to the Westinghouse core design and safety analysis.
The proposed amendment would revise the WCGS Operating License by incorporating a full scope implementation of the Alternative Source Term (AST) radiological analysis in accordance with Title 10 of the Code of Federal Regulations, Section 50.67 (10 CFR 50.67), "Accident Source Term," revising TS definitions and adopting Technical Specification Task Force Traveler 51 (TSTF-51 ), Revision 2, "Revise Containment Requirements during Handling Irradiated Fuel and Core Alterations," dated November 1, 1999 (ADAMS Accession No. ML993190284).
Based on its review, the NRC staff requests the following additional information to complete its safety evaluation of the application.
SRXB-RAI-1 In the Summary of Analysis Codes Utilized in Postulated Accident Analyses, there are two Non-Loss-of-Coolant Accident (LOCA) Safety Analysis Codes listed for the Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, RETRAN, and LOFTRAN. Please provide the information that is obtained from each code and used as the basis for the updated analysis.
Enclosure
ML14111A100                                          *memo OFFICE  NRR/DORULPL4*1/PM NRR/DORULPL4-1/LA    NRR/DSS/SRXB/BC* NRR/DORULPL4-1/BC    NRR/DORULPL4-1/PM NAME    Flyon            JBurkhardt          CJackson        MMarkley            Flyon DATE    4/29/14          4/29/14              4/2/14          4/30/14              4/30/14}}

Latest revision as of 20:54, 5 February 2020

Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
ML14111A100
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 04/30/2014
From: Lyon C
Plant Licensing Branch IV
To: Heflin A
Wolf Creek
Lyon C
References
TAC MF2574
Download: ML14111A100 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2014 Mr. Adam C. Heflin President, Chief Executive Officer, and Chief Nuclear Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839

SUBJECT:

WOLF CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION RE: TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS (TAC NO. MF2574)

Dear Mr. Heflin:

By application dated August 13, 2013, to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System (ADAMS) package Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (the licensee) requested a license amendment for Wolf Creek Generating Station, to revise the Technical Specifications to support transition to the Westinghouse core design and safety analysis.

The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed questions were provided to Mr. S. Wideman of your staff on April18, 2014. Please provide a response to the questions within 90 days of the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of NRC staff resources. If circumstances result in the need to revise the requested response date, please contact me at 301-415-2296 or via e-mail at Fred. Lyon@nrc.gov.

Sincerely, 0Rr Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 Enclosure Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSIS WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 By application dated August 13, 2013, to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System (ADAMS) package Accession No. ML13247A075), Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) requested a license amendment for Wolf Creek Generating Station (WCGS), to revise the Technical Specifications (TSs) to support transition to the Westinghouse core design and safety analysis.

The proposed amendment would revise the WCGS Operating License by incorporating a full scope implementation of the Alternative Source Term (AST) radiological analysis in accordance with Title 10 of the Code of Federal Regulations, Section 50.67 (10 CFR 50.67), "Accident Source Term," revising TS definitions and adopting Technical Specification Task Force Traveler 51 (TSTF-51 ), Revision 2, "Revise Containment Requirements during Handling Irradiated Fuel and Core Alterations," dated November 1, 1999 (ADAMS Accession No. ML993190284).

Based on its review, the NRC staff requests the following additional information to complete its safety evaluation of the application.

SRXB-RAI-1 In the Summary of Analysis Codes Utilized in Postulated Accident Analyses, there are two Non-Loss-of-Coolant Accident (LOCA) Safety Analysis Codes listed for the Uncontrolled Rod Cluster Control Assembly Bank Withdrawal at Power, RETRAN, and LOFTRAN. Please provide the information that is obtained from each code and used as the basis for the updated analysis.

Enclosure

ML14111A100 *memo OFFICE NRR/DORULPL4*1/PM NRR/DORULPL4-1/LA NRR/DSS/SRXB/BC* NRR/DORULPL4-1/BC NRR/DORULPL4-1/PM NAME Flyon JBurkhardt CJackson MMarkley Flyon DATE 4/29/14 4/29/14 4/2/14 4/30/14 4/30/14

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