ML20206P336
| ML20206P336 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/24/1986 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20206P334 | List: |
| References | |
| NUDOCS 8607020101 | |
| Download: ML20206P336 (3) | |
Text
_
Revised Technical Specifications for Section 6, " Administrative Controls", Item 6.3.2, " Procedures" Revised Page: 226 The attached proposed revision contains clarifying changes to areas of the present Technical Specifications as follows:
1.
The wording of the opening statement in Section 6, Administrative Controls, Item 6.3.2, Procedures, was changed to more closely conform to the wording used in Item 6.8.1 of GE Standard Technical Specifications for BWR No. 4 (NUREG 0123). This was done to clarify the role of written procedures at CNS in order to eliminate misinterpretations.
Evaluation of this Revision with Respect to 10CFR50.92 A.
The enclosed Technical Specification change is judged to involve no significant hazards based on the following:
1.
Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation:
The proposed change simply clarifies one minor administrative item.
The change does not alter existing equipment, surveillances or procedures. Consequently, it is the District's assessment that this change does not increase the possibility or consequences of an accident previously evaluated.
2.
Does the proposed license amendment create the possibility for a new l
or different kind of accident from any accident previously l
evaluated?
Evaluation:
The proposed change does not introduce any changes to the present mode of operation but clarifies one minor point as indicated above.
Therefore, the proposed license amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
Does the proposed amendment involve a significant reduction in the margin of safety?
)
Evaluation:
Due to the purely administrative nature of the change, it does not affect any equipment or procedures that would affect a margin of safety.
The added clarity provided by this change will not result in any reduction in the margin of safety.
l 8887 Mist 80$e l
P
B.
Additional basis for proposed no significant hazards consideration determination:
The commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48CFR14870). The examples include:
"(1) A purely administrative change to Technical Specifications.
For example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature." It is the District's belief the proposed change is encompassed by the above example.
+ *. '
6.3 PROCEDURES AND PROGRAMS 6.3.1 Introduction Station personnel shall be provided detailed written procedures to be used for operation and maintenance of system components and systems that could have an effect on nuclear safety.
6.3.2 Procedures Written procedures and instructions including applicable check off lists shall be established, implemented, and maintained for the following:
A.
Normal startup, operation, shutdown and fuel handling operations of the station including all systems and components involving nuclear safety.
B.
Actions to be taken to correct specific and foreseen potential or actual malfunctions of safety related systems or components including responses to alarms, primary system leaks and abnormal reactivity changes.
C.
Emergency conditions involving possible or actual releases of radio-active materials.
D.
Implementing procedures of the Security Plan and the Emergency Plan.
E.
Implementing procedures for the fire protection program.
F.
Administrative procedures for shift overtime.
6.3.3 Maintenance and Test Procedures The following maintenance and test procedures will be provided to satisfy routine inspection, preventive maintenance programs, and operating license requirements.
A.
Routine testing of Engineered Safeguards and equipment as required by the facility License and the Technical Specifications.
B.
Routine testing of standby and redundant equipment.
C.
Preventive or corrective maintenance of plant equipment and systems that could have an effect on nuclear safety.
D.
Calibration and preventive maintenance of instrumentation that could affect the nuclear safety of the plant.
E.
Special testing of equipment for proposed changes to operational procedures or proposed system design changes.
6.3.4 Radiation Control Procedures Radiation control procedures shall be maintained and made available to all station personnel. These procedures shall show permissible radiation exposure, and shall be consistent with the requirements of 10 CFR 20.
-226-