ML19310A105
| ML19310A105 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/08/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Ahearne J, Gilinsky V, Kennedy R NRC COMMISSION (OCM) |
| Shared Package | |
| ML19310A106 | List: |
| References | |
| NUDOCS 8006060098 | |
| Download: ML19310A105 (2) | |
Text
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UNITED ST ATES 8 Y:.. f (h NUCLEAR REGULATORY COMMISSION
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%' s., =. e MAY 8 1999 MEr'ORAUDUE. FOR: Criairman Ahearne Commissioner Gilinsky Co.a:aissioner Kennedy Commissioner Hendrie Commissioner Bradford FROM:
Harold R. Denton, Director Office of Nuclear Reactor Regulation THRU:
William J. Dircks l
Acting Executive Director for OperationsDN da I MO
SUBJECT:
SEQUOYAH OPERATING LICENSE In accordance with the April 11, 1980 memorandum from S. Chilk to W. Dircks on the above subject, NRR will take the lead in reviewing the proposed Sequoyah operating license, before it is submitted to the Commission, with the objective of making it as clear and as enforceable as time and resources permit before full power operation is authorized.
To this end, prior to the issuance of the full power license on Sequoyah, the staff will accomplish the following objectives:
1.
Review all TMI-related staffing and management-oriented requirements and equipment-oriented requirements that are specified as conditions in the current Sequoyah license or are contained in Sections 7, 8 and 9 of the current Sequoyah technical specifications for clarity and enforce-ability, rewrite them as necessary, and incorporate them as appropriate, into the Sequoyah technical specifications for full power operation in the format of the standard technical specifications.
2.
Review all other TMI-related requirements specified in the current Sequoyah license or technical specifications (i.e., those that are not appropriate for incorporation in the technical specifications) for clarity and enforceability, rewrite them as necessary, and incorporate them as conditions in the full power license.
3.
Review, as practicable, consistent with avoiding unnecessary delay in issuance of the full power license, the standard technical specifica-tions as used in the current Sequoyah license to provide improvements in clarity and enforceability where significant improvement is found
Contact:
D. Skovholt, DST, NRR
~
49-27492 800606009%
t The Commissioners.
to be necessary or practical. Operations and inspection experience obtained during the low power test program will be considered in this effort.
These reviews will be performed by the Standard Technic:1 Spccificatiens Section of the NRR Licensing Guidance Branch, with assistance and input from the URR licensing project manager, the IE resid:nt in:pector and IE headquarters.
We will also request comments on the revised license and technical specifications from 0 ELD, OPE and 0GC before they are submitted to the Commission.
When this review is complete, we plan to apply the results to the other near-term OL applications and to future license applications.
In addition to this effort, the staff has initiated a program for long-term improvements in the existing system of standard technical specifications.
We have prepared a proposed Advance Notice of Proposed Rulemaking to solicit industry and public comments regarding the establishment of standards for the content of technical specifications and for modifying the definitions of categories of technical specifications. This proposed advance notice will be forwarded to the Commission for approval in the near future.
It has been prepared by the same Standard Technical Specifications Section that will be involved in upgrading the Sequoyah license. We expect that the rulemaking process and subsequent development and imple entation of a new set of standard technical specifications will result in further improve-ments in the clarity and enforceability of our requirements.
Harold R. Denton, Director 'M: i
Office of Nuclear Reactor Regulation cc: OGC OPE SECY e
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