ML20323A312
| ML20323A312 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/29/2020 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20323A313 | List: |
| References | |
| WBL-20-047 | |
| Download: ML20323A312 (3) | |
Text
WBN TABLE OF CONTENTS Section Title Page 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16-1 16.2 TECHNICAL SPECIFICATIONS 16-1 16.3 RELOCATED SPECIFICATIONS 16-2 16.3.1 Discussion 16-2 16.3.2 Document Control 16-2 16.3.3 Changes to the Relocated Specifications 16-2 References 16-2 16-i
WBN 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSED TECHNICAL SPECIFICATIONS (NOT USED) 16.2 TECHNICAL SPECIFICATIONS This Section describes Watts Bars 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 document 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 was issued by NRC with a request for certification. Watts Bar certified the Technical Specifications prior to requesting an operating license. The Certified Technical Specifications were issued by the NRC as Appendix "A" of the Operating License.
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WBN 16.3 RELOCATED SPECIFICATIONS 16.3.1 Discussion As 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
[1,2]
improvement of Technical Specifications for nuclear power plants. 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 became 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 Control Overall 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 Specifications Activities 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.
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