ML13255A289
| ML13255A289 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/14/2013 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13255A164 | List:
|
| References | |
| Download: ML13255A289 (12) | |
Text
Table of Contents16-iWATTS BARTABLE OF CONTENTS SectionTitle Page16.0TECHNICAL SPECIFICATIONS16.1PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)16.1-116.2PROPOSED FINAL TECHNICAL SPECIFICATIONS16.2-1 16.3RELOCATED SPECIFICATIONS16.3-116.3.1DISCUSSION16.3-116.3.2DOCUMENT CONTROL16.3-1 16.3.3CHANGES TO THE RELOCATED SPECIFICATIONS16.3-1 Table of Contents16-iiWATTS BARTABLE OF CONTENTS SectionTitle Page THIS PAGE INTENTIONALLY BLANK List of Figures16-vWATTS BAR LIST OF FIGURES SectionTitleTHIS PAGE INTENTIONALLY BLANK List of Figures16-viWATTS BAR LIST OF FIGURES SectionTitleTHIS PAGE INTENTIONALLY BLANK List of Tables16-iiiWATTS BARLIST OF TABLES SectionTitleTHIS PAGE INTENTIONALLY BLANK 16-ivList of TablesWATTS BARLIST OF TABLES SectionTitleTHIS PAGE INTENTIONALLY BLANK PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-1WATTS BARWBNP-110 16.0 TECHNICAL SPECIFICATIONS16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED)
PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.1-2WATTS BARWBNP-110THIS PAGE INTENTIONALLY BLANK PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-1WATTS BARWBNP-11016.2 PROPOSED FINAL TECHNICAL SPECIFICATIONSThis Section describes Watts Bar's plan for implementation of the Restructured Standard Technical Specifications (RSTS) based on the Westinghouse Owners Group
MERITS Program and NUREG-1431 in lieu of the previous Standard Technical Specification (STS) in NUREG-0452.The RSTS (NUREG-1431) is structured for the broadest possible use on Westinghouse plants. Accordingly, the docu ment contains specifications which may not be applicable to all plants. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The values of parameters and variables which may vary because of plant design appear as either blanks or bracketed numbers throughout the RSTS for illustration purposes only. During Technical Specification development for Watts Bar, specifications were removed as justified or added as required. The actual plant specific value for each parameter and variable was provided during the development process. A Proof and Review edition of the Watts Bar Technical Specifications was issued by NRC for review within NRC and Watts Bar. After resolution of the comments from this process, a Final Draft Technical Specification will be issued by NRC with a request for certification. Watts Bar must certify the Technical Specifications prior to requesting an operating license. The Certified Technical Specification will be issued by the NRC as Appendix "A" of the Operating License.Prior to issuance of the Final Draft Technical Specification, Watts Bar may maintain a controlled copy of the proposed Technical Specifications, based on the NRC approved changes from the Proof and Review version, for use in procedure development and training.
PROPOSED FINAL TECHNICAL SPECIFICATIONS 16.2-2WATTS BARWBNP-110THIS PAGE INTENTIONALLY BLANK RELOCATED SPECIFICATIONS 16.3-1WATTS BARWBNP-11016.3 RELOCATED SPECIFICATIONS 16.3.1 DiscussionAs part of the implementation of the improved Technical Specifications program, Watts Bar has relocated certain information from the previous Standard Technical Specifications (NUREG-0452) to separate controlled documents based on the Commission's Policy Statement for improvement of Technical Specifications for nuclear power plants.
[1,2] The majority of relocated information is now contained in a separate document called the Technical Requirements Manual (TRM). Other information has been relocated into site procedures or other Technical Specification required programs such as the Offsite Dose Calculation Manual (ODCM), Fire Protection Report (FPR), and the Process Control Program (PCP) as permitted by generic guidance. These documents become effective upon receipt of the operating license. The following is a description of the administrative program for control and amending the relocated specification material. The requirements for changing the ODCM are specified in the Technical Specifications. 16.3.2 Document ControlOverall control of the relocated material documents is in accordance with the procedures for control of documents. Changes to the TRM, ODCM, and FPR are issued on a replacement page basis to controlled document holders following approval of the change in accordance with TVA procedures.16.3.3 Changes to the Relocated SpecificationsActivities at Watts Bar have the potential to affect the relocated specifications. These include design modifications, procedure changes, other licensing document changes, etc. Changes to the relocated material are controlled by procedures to ensure that appropriate reviews and approvals are obtained. The relocated material contained in the TRM may subsequently be relocated into other procedures and the TRM eliminated. Changes to the requirements of the relocated material are evaluated in accordance with 10CFR50.59.Changes to the TRM are reported as required by TRM Section 5.0, "Administrative Controls".REFERENCES (1)"Interim Policy Statement on Technical Specification Improvements on Nuclear Power Reactors," Nuclear Regulatory Commission, 52 FR 3788, February 6, 1987.
(2)"Watts Bar Unit 1 Technical Specifications Criteria Application Report," WCAP-13470, August 1, 1992.
16.3-2RELOCATED SPECIFICATIONS WATTS BARWBNP-110THIS PAGE INTENTIONALLY BLANK