ML20006A638
| ML20006A638 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/15/1990 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20006A634 | List: |
| References | |
| 0526T, 526T, NUDOCS 9001290246 | |
| Download: ML20006A638 (3) | |
Text
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t PROPOSED TECHNICAL SPECIFICATION CHANGE r
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I Quad Cities Unit 2 (DPR-30) Appendix A l
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DPP.-30 1
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1.1/2.1 FUEL CLADDING INTEGRITY l
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.$AFETY LIMIT LIMITING $ArtTY SYSTEM SETTING j
I Applicablltty:
Applicability:
The safety limits estabitshed to preserve The limiting safety system settin s apply
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the fuel cladding integrity apply to to trip settings of the instrumen s and l
those variables which monttor the fuel devices which are provided to prevent the j
thermal behavior.
fuel cladding integrity safety limits from being exceeded.
Objective:
Objective:
The objective of the safety limits is to The objective of the limiting safety sys-l estabitsh limits below which the integ-tem settings is to define the level of rity of the fuel cladding ts preserved.
-the process variables at mhtch automatic protective action is initiated to pre-vent the fuel cladding integrity safety limits from being exceeded.
SPECIFICATION $
A.
Reactor Pressure > 800 psig and Core A.
Neutron Flux Trip $ettings Flow > 10% of Rated The existence of a minimum critical The 1;miting safety system trip set-power ratio (MCPR) less than 1.06 l
tings shall be as specified below; shall constitute violation of the fuel cladding integrity safety Itmit.
1.
APRM Flux scram Trip setting (Run Mode) 8.
Core Thermal Power Limit (Reactor Pressure 1 800 psig)
When the reactor mode switch is j
in the Run position, the APRM i
J When the reactor pressure is 1 800 flux scram setting shall be as psig or core flow is less than 10% of shown in Figure 2.1.1 and shall l
rated, the core thermal power shall be*
not exceed 25% of rated thermal power.
C.
Power Transient with a maximum setpoint of 120%
1.
The neutron flux shall not fogcoreflowequalto98x exceed the scram setting estab-10 lb/hr and greater.
Itshed in Specification 2.1A for longer than 1.5 seconds as indi.
where cated by the process computer.
$ = setting in percent of rated 2.
When the process computer is out power of service, this safety limit shall be assumed to be exceeded WD: percent of drive flow if the neutron flux exceeds the required to produce a rated core scram setting established by flow of 98 million 1b/hr. In
$ pacification 2.1.A and a con-the event of operation with a trol rod scram does not occur.
maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows:
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$1 (.58WD + 62 [ MFLPD )
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l 09258/03942 1.1/2.1-1 Amendment No.
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i EVALUAn0N OF SIGNIEICANT HAZARDS C.ONSIDERATION l
Commonwealth Edison Company proposes an amendment to Facility Operating License DPR-30 which would change the Technical Specifications to allow for operation during Cycle 11 and subsequent cycles with a fuel type which, while new to Quad Cities reloads, has been previously approved by the NRC on a generic basis.
1.
Description of Amendment Request.
The proposed change to Facility Operating License DPR-30, Appendix A (Technical Specifications and Bases), 1.1/2.1.1, is to raise the safety limit Minimum Critical Power Ratio (MCPR) from 1.04 to 1.06.
f 2.
Basis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated the proposed Technical Specifications change and determined that it does not represent a significant hazards consideratien.
Based on the criteria for defining a significant hazard l
established in 10 CTR 50.92(c), the proposed change:
a.
will not involve a significant increase in the probability or consequences of an accident previously evaluated because the 1.06 safety limit MCPR value will preserve the required margin of safety for clad integrity. Not only will the margin of safety be preserved for GE8x8NB, but, additionally, this margin of safety will be increased for the other (non-limiting) fuel types present in the core. The new fuel type (GE8x8NB) and analytical methods for establishing the safety limit have previously received NRC approval.
b.
will not create the possibility of a new or different kind of accident from any accident previously evaluated because the primary fission product barrier will continue to be protected during normal and transient operation. The fuel design, associated analytical methods, and safety limit were previously reviewed and approved by the NRC based on the fuel vendor's generic Licensing Topical Report for reload fuel, NEDE-24011-P-A-9.
The Quad Cities Unit 2 reactor is within the range of plant designs for which the application of this fuel type has been found acceptable from all safety and licensing acpects.
c.
will not involve a significant reduction in the margin of rately because the required margins will be at least maintained for all fuel types and increased for some fuel types.
The proposed Technical Specification change reflects the previously approved safety limit for GE8x8NB fuel.
Based on the above evaluation. Commonwealth Edison concludes that the proposed amendment does not represent a significant hazards consideration.
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