ML20212Q210
| ML20212Q210 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/26/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20212Q208 | List: |
| References | |
| 2025K, NUDOCS 8609040081 | |
| Download: ML20212Q210 (4) | |
Text
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PROPOSED CHANGE TO QUAD CITIES UNIT 1 TECHNICAL SPECIFICATIONS y
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8609040001 860826 PDR ADOCK 05000254 P
PDR 2025K
QUAD CITIES DPR-29 within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
Maximum allowable LNGR for all
'8X8 fuel types is 13.4 KW/ft.
K.
Minimum critical Power Ratio (MCPR)
R.
Minimum Critical Power Ratio (MCPR)
During steady-state operation at The MCPR shall be determined rated core flow, MCPR shall be daily during steady-state greater than or equal to:
power operation above 25% of 1.35 for T 5.
73 sec gyg l
1.40 for T 1
sec AVE l
.385 "C
+ 1.069 AVE for.73 sec 1'f 1 86 see gyg who're 17 = mean 20% scram insertion time for l
all surveillance data from specification 4.3.C which has been generated in the current cycle.
For core flows other than rated, these nominal values o.f MCPR shall be increased by a factor of k where k is as shown in Figure 3.5.2.
Ifanytim$duringoperation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within l
15 minutes to restore operation to within the prescribed limits.
If the steady-state MCPR is not returned to within the pre-scribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
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Amendment No. 87. 36 3.5/4.5-10 l
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ATTACHMENT 2 EVALUATION OF NO SIGNIFICANT HAZARDS CONSIDERATION DESCRIPTION OF AMENDMENT REOUEST Commonwealth Edison proposes to amend the Quad Cities Unit 1 Technical Specification MCPR operating limit to reflect the actual results of the Unit 1 Cycle 9 transient analyses. This change will replace the existing value in the Technical Specifications which is a conservative value carried over from previous cycles to facilitate 10 CFR 50.59 reload reviews.
BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Commonwealth Edison has performed an evaluation of the hazards consideration associated with the proposed Technical Specification amendment utilizing the criteria in 10 CFR 50.92.
Our evaluation is provided below and specifically addresses the three criteria of 10 CFR 50.92(c).
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because the change involves incorporation of an operating limit specifically calculated for Cycle 9.
Adherence to this limit will assure that the core is operated within the a'ssumed initial conditions for previous accident analyses and therefore will not increase the previously established consequences. Since the change only imposes a restriction on operating conditions, it does not directly impact any equipment or systems and therefore has no casual relationship with the probability of an accident.
The proposed amendment will not create the possibility of a new or different kind of accident than previously evaluated because it does not allow any new equipment or modes of operation (nor changes to existing equipment) which could initiate or affect an accident.
l The proposed amendment does not involve a significant reduction in l
the margin of safety because the revised MCPR operating limit value was explicitly calculated for cycle 9 operation, using NRC approved codas and methods, to assure the required margin to safety is maintained. Operation within the revised limit will continue to protect the MCPR safety limit against operational transients.
For the reasons stated above, Commonwealth Edison finds that the proposed amendment does not involve a significant hazards consideration l
based on the criteria of 10 CFR 50.92(c).
We, therefore, request approval l
of the propesed amendment under the provisions of 10 CFR 50.91(a)(4).
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2025K
ATTACHMENT 3 Supplemental Reload Licensing Submittal For Quad-Cities Nuclear Power Station Unit 1, Reload 8 (Cycle 9)
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