ML20203F899
| ML20203F899 | |
| Person / Time | |
|---|---|
| Site: | 070*****, 07003095 |
| Issue date: | 03/26/1997 |
| From: | ENVIROCARE OF UTAH, INC. |
| To: | |
| Shared Package | |
| ML20202J577 | List:
|
| References | |
| 9301-1, NUDOCS 9803020085 | |
| Download: ML20203F899 (1) | |
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t TABLE OF CONTENTS 16.0 TECHNICAL SPECIFICATIONS 16.1 PROPOSF,0 TECHNICAL SPECIFICATIONS (NOT USED) 16-1 16.2 TECHNICAL SPECIFICATIONS 16-1 16.3 RELOCATED SPECIFICATIQNS 16-2 16.3.1 Discussion 16.3-1 16.3.2 Document Control 16-2 16.3.3 Changes to the Relocated Specifications 16-2 s
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16.1 PROPOSED TECHNICAL SPECIFICATION.S (NOT USED) 16.2 TECHNICAL SPECIFICATIONS This Section describes the Watts Bar plan for implementing the Restructured Standara Technical Specifications @STS) based on the Westinghouse Owners Group MERITS Program and NUREG 1431 m lieu of the previous Standard Technical Spe:ification (STS)in NUREG 0452.
The RSTS are structured for the broadest possible use on Westinghouse plants. Accordingly, the document contains specifications whia.h may not be applicable to ell 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 m 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 illustratr a purposes only.
During Technical Specification development for Watts Bar, specifications which did not apply were removed, and specificatic.a which were required by the Safety Evalnation Report (SER) i were added. 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. AAer resolution of the comments from this process, a Final DraA Technical Specification was issued by NRC with a request for certification. Watts Sar certified the Technical Specifications prior to requesting en operating license. The Certified Technical Specification were issued by the NRC as Appendit "A" of the Operating Lic.nse.
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16.3 RFI OCATED SPECIFICATIONS 16.3.1 Dist.ussion 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 improvement of Technical Specifications for nuclear power plant:H'l. The majority ofrelocated information is now contained in a separate document called the Technical Requirements Manual (TRM) Other information has been relocated into site procedures or other 'echnical Specification required programs such as the Offsite Dose Calculation Manual (ODCM), Fire Protection Report, and the Procers Control Program as pertrJtted by generi:: guidance These documents became effective upon receipt of the operating license for each unit. 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.
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l 16.3.2 Document Control l'
Overall control of the relocated material documents is in accordance with site procedures for document control. Changes to the TRM are ism.ed on a replacement page basis to controlled document holjers following approval of the change in accordance with site procedures.
i 16.3.3 Chanaan to the Raiar=*ad Snacine=*iana 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 site procedures to ensure that appropriate reviews and approvals are obtained. The relocated mateiial contained in the TRM may subsequently be relocated into site procedures and the TRM eliminated. Changes to the requirements of the i-relocated material are evalucted in accordance with 10CFR50.59.
L Changes to the TRM are reported as part of the 10CFR50.59 annual report.
REFERENCES 1.
" Interim Policy Statement on Technical Specification li.;provements 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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