ML17111A701
| ML17111A701 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/22/2017 |
| From: | Robert Schaaf Plant Licensing Branch II |
| To: | James Shea Tennessee Valley Authority |
| Schaaf R, LPL2-2, 415-6020 | |
| References | |
| CAC MF9393, CAC MF9394 | |
| Download: ML17111A701 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. J. W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 June 22, 201 7 SUBJECT WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - WITHDRAWAL OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT TO CLARIFY SHIELD BUILDING TECHNICAL SPECIFICATION (CAC NOS. MF9393 AND MF9394)
Dear Mr. Shea:
By letter dated March 6, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML17065A301 ), the Tennessee Valley Authority (TVA) submitted a license amendment request for Watts Bar Nuclear Plant, Units 1 and 2. The proposed amendment would revise Technical Specification (TS) 3.6.15, "Shield Building," Condition B.
and the associated Bases. The purpose of this letter is to acknowledge your request to withdraw your application and 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 (10 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.
On April 19, 2017, NRC staff provided a draft of the results of its acceptance review of your application via e-mail (ADAMS Accession No. ML17170A172). The NRC staff identified that your application did not provide technical information in sufficient detail to enable the staff to complete its detailed review and identified the supplemental information needed in order to accept the application for review. The NRC staff facilitated a teleconference with TVA staff on April 28, 2017, to provide clarification of the requested supplemental information and to confirm that TVA could provide timely response to the NRC staff's supplemental information request.
By letter dated May 10, 2017 (ADAMS Accession No. ML17131A206), TVA requested to withdraw this application from NRC review. The NRC acknowledges your request to withdraw the application. NRC staff activities on the review have ceased and the associated Cost Activity Code number has been closed. Notice of Consideration of Issuance of the proposed amendment had not been published in the Federal Register.
As noted above, the NRC identified that your application did not provide technical information in sufficient detail to enable the staff to complete its detailed review. Therefore, if you decide to resubmit the request, it must include the following information:
A proposed change to TS 3.6.15 that is consistent with the NRG-approved design basis as reflected in the analysis in Updated Final Safety Analysis Report Section 15.5.3, "Environmental Consequences of a LOCA [Loss-of-Coolant Accident]"; or Sufficient explanation regarding how the dose reference values of 10 CFR Part 100 and the dose criterion of General Design Criterion (GDC) 19 of 10 CFR Part 50, Appendix A, are met using the proposed administrative controls. The inputs, assumptions, methodology, technical basis, and results of the analysis should be provided; and, Sufficient explanation regarding what administrative controls will be used to ensure that the integrity of the pressure boundaries can be restored so that the LOCA analysis results meet the dose reference values in 10 CFR Part 100 and the dose criterion in GDC 19, and in what document(s) the administrative controls are maintained.
If you have any questions, please contact me at (301) 415-6020 or Robert.Schaaf@nrc.gov.
Docket Nos. 50-390 and 50-391 cc w/encl: Distribution via Listserv Sincerely,
!1VvA4J
(
Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML17111A701 OFFICE NRR/DORL/LPL2-2/PM NRR/DORLILPL2-2/LA NAME RSchaaf BClayton DATE 06/19/17 06/19/17 OFFICE NRR/DORLILPL2-2/BC NRR/DORLILPL2-2/PM NAME UShoop RSchaaf DATE 06/20/17 06/22/19