ML20107M024
| ML20107M024 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/29/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20107M018 | List: |
| References | |
| NUDOCS 8411130742 | |
| Download: ML20107M024 (2) | |
Text
,y UNITED STATES NUCLE.1R REGULATORY COMMISS:ON v., v '
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'VASHING TON D C. 20M5 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACT 0P REGULATION SUPPORTING AMENDMENTS NOS. 85 AND 57 TO FACILITY OPERATING LICENSES NOS. DPR-51 AND NPF-6 ARKANSAS POWER & LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNITS NOS. 1 AND 2
- DOCKETS NOS. 50-313 AtlD 50-368 Introduction By "0CAN038401, Application to Amend Licenses DPR-51 & NPF-6,changing Tech Specs Re RCS vents,post-accident sampling,long-term [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Sys Evaluation,Noble Gas Monitor & Iodine Particulate Sampling,Per NUREG-0737 Items|letter dated March 16, 1984]], Arkansas Power and Light Ccmoeny (AP&L cr the licensee) requested amendments to the Technical Specifications (TSs),
Appendix A, appended to Facility Operating Licenses OPR-51 and f!PF-6 for Arkansas Nuclear One, Units Nos.1 & 2 (AN0-1&2). The proposed amendments would change the TSs for both AN0-182 by requiring administrative controls for shift overtime for all plant staff who perform safety-related functions.
The proposed amendments would also provide other changes which will be considered in a separate action.
Background
Following the accident at Three Mile Island, Unit 2, the NRC staff developed NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident", to provide a comprehensive and integrated plan to inprove safety at nuclear power reactors.
Specific NUREG-0660 items that were approved by the Commission #or implementation were issued in " Clarification of TMI Action Plan Requiremen'ts",
NUREG-0737 and its Supplement 1 (Generic Letter (GL) 82-33,
" Requirements for Emergency Response Capability") specified that amended TSs would be rcquired in order to implement several of the items.
Subsequently, on September 20, 1982, NRC issued GL 82-16, "NUREG-0737 Technical Specifications", requesting all pressurized "sater reactor licensees to (a) review their existing TSs against the GL 82-16 guidance and Ibi submit proposed TSs for those items that deviated from the GL 82-16 guidance.
On December 28, 1982 and March 16, 1984, AP&L responded to GL 82-16.
The latter submittal to the NRC proposed one change to the ANO-1&2 TSs m1ated to GL S2-16 and several changes related to a subsequent ceneric letter, GL 83-37.
Only the proposed changes relating to GL 82-16 are considered in this action.
Proposed changes relating to GL 83-37 will be considered in a separate action.
The proposed changes considered herein are responsive to NUREG-0737 Item I.A.1.3, " Limit Overtime".
Discussion and Evaluation Cn June 15,198?, the staff issued GL 82-12, which contained a revised version of the Commission's Policy Statement on nuclear power plant staf# working hours.
Subsecuently, by GL 82-16 dated September 20, 1982, AP&L was requested hk h
0 P
_p-to revise the administrative controls section of the A40-152 TSs to adhere to the policy statement guidelines.
The objective of the controls is to assure that, to the extent practicable, personnel are not assigned to shift duties while in a fatigued condition that could significantly reduce their mental alertness or their decision making capability.
The controls are to be applicable to all plant staff who perform safety-related functions (e.g.,
senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel).
Subsequently, AP&L responded with the proposed TSs for ANO-1&2 that incorporate administrative procedures for controlling shift overtime.
The proposed TSs generally satisfy the intent and requirements of GL 82-12.
Therefore, we have determined that the proposed TSs are acceptable and that AP&L has fulfilled the necessary requisites of NUREG-0737 Item I. A.1.3.
Environmental Consideration These amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
Conclus' ions We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission'$ regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: October 29, 1984 Principal Contributors:
M. Nevius D. Powers G. Vissing l
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