ML20134G414
| ML20134G414 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/07/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20134G402 | List: |
| References | |
| NUDOCS 9611130190 | |
| Download: ML20134G414 (9) | |
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l ATTACIIMENT B ZION NUCLEAR GENERATING STATION MARKED UP ANNOTATED COPY AND CLEAN COPY OF TECIINICAL SPECIFICATIONS FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECIINICAL SPECIFICATIONS STEAM LINE SAFETY VALVES AND REDUCED POWER RANGE NEUTRON l
FLUX SETPOINT TRIP 9611130190 961107 PDR ADOCK 05000295 P
Maximum Allowable Power Range '
Inoperable Safety Valves on Neutron Flux High Trip Setpoint Any Doeratina Steam Generator (Percent of Rated Power) 0
+ GO R
B& J'(
0+0
-7+ V 7 Q+R 6 & #/ /
R+R 59.7 6 0+0+R 49 2 8 0+R+R 4t 22 R+R+R 0+ / 7 Maximum Allowable Power Range Neutron Flux High Trip Setpoint with Inoperable Steam Line Safety Valves During 4 Loop Operation.
1 TABLE 3.7-1 160a.
Amendment Nos. 17 and 14
Maximum Allowable Power Range l
Inoperable Safety Valves on Neutron Flux High Trip Setpoint 1
Any Operatina Steam Generator (Percent of Rated Power)
Q 60l-f i
R 54l i
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~.
Q+0 47l Q+R 41l R+R 36 28l t
Q + Q +- R
~
Q+R+R 22 l
l 17l R+R+R r
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Maximum Allowable Power Range Neutron Flux High Trip Setpoint with Inoperable '
Steam Line Safety Valves During 4. Loop Operation.
TABLE 3.7-1
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160a Amendment Nos. 17 and 14
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l ATTACIIMENT C ZION NUCLEAR GENERATING STATION EVALUATION OF SIGNIFICANT IIA 7ARD CONSIDERATIONS FOR PROPOSED CIIANGES TO FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECIINICAL SPECIFICATIONS STEAM LINE SAFETY VALVES AND REDUCED POWER RANGE NEUTRON FLUX SETPOINT TRIP
l Comed has evaluated this proposed license amendment and determined that it involves no significant hazard considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazard considerations if operation of the facility in accordance with the proposed amendment would not:
1.
Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated; i
2.
Create the possibility of a new or different kind of accident from any previously analyzed; or, 1
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Involve a significant reduction in the margin of safety.
l This determination has been performed as indicated below:
1.
The proposed changes do not involve a significant increase in the probability or consequences of occurrence of any accident previously evaluated.
The requirement to change the Power Range Neutron Flux High Trip setpoints to the Reduced Setpoint Values of Table 3.7-1 for the most restrictive loop if one or more code MSSVs are d
inoperable is not changed by this amendment. As mch, no change in operating practices or plant configuration is being made.
i The amendment provides new reduced setpoint values for the Power Range Neutron Flux High Trip to ensure that for the limiting transient (Loss of Load / Turbine Trip), a secondary j
side overpressurization condition does not occur. The new values were the result of calculation using an algorithm provided by Westinghouse in Reference 1. The new values are much more restrictive than the previous values and ensure that the probability or consequences of an accident previously evaluated is not increased. Therefore, the new reduced setpoint values do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed changes do not create the possibility of a new or ditTerent kind of accident from any accident previously evaluated.
The proposed change does not require a physical alteration of the plant (no new or different equipment will be installed to implement this change). The Reduced Neutron Flux Ifigh Trip setpoints ensure that a secondary side overpressurization transient does not occur for the most limiting transient. In addition, no new modes of operations will be introduced by this change.
Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
The proposed chnnges do not involve a significant reduction in a margin of safety.
This amendment provides new Reduced Power Range Neutron Flux High Trip setpoints.
The Specification that requires the Power Range Neutron Flux High Trip setpoints be changed to the reduced values for one or more inoperable MSSVs is not changed. The
- reduced Trip setpoints are the result of new calculations usir.g an algorithm provided by -
j Westinghouse in Reference 1, and ensure 'the LOUTT transient does not result in a secondary overpressurization. Therefore, this change does not involve a significant r
reduction in a margin of safety,
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1 ATTACllh1ENT D i
ZION NUCLEAR GENERATING STATION j
ENVIRONh1 ENTAL ASSESSh!ENT STATEN1ENT FOR PROPOSED CIIANGES TO FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECIINICAL SPECIFICATIONS STEAM LINE SAFETY VALVES AND REDUCED POWER RANGE NEUTRON FLUX SETPOINT TRIP
)
Comed has evaluated this proposed changes of this license amendment request against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR 51.22(c)(9). The following is a discussion of how the proposed changes meet the criteria for categorical exclusion.
10 CFR 51.22(c)(9): Although the proposed change involves a change to a requirement with respect to the installation or use of facility components or to an inspection or surveillance requirements:
(i)
The proposed change involves no significant hazards considerations (refer to Attachment C of this license amendment request);
(ii)
There is no significant change in the types or a significant increase in the amounts of any effluent that may be released offsite, since the proposed changes do not affect the generation of any radioactive effluent nor do they affect any of the permitted release paths; and (iii)
There is no significant increase in individual or cumulative occupational radiation exposure.
The actions proposed in this request for an amendment do not significantly affect plant radiation levels, and therefore do not significantly affect dose rates and occupational exposure.
Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Based on the aforementioned and pursuant to 10 CFR 51.22(b), no environmental assessment or environmental impact statement need be prepared in connection with issuance of a license amendment incorporating the proposed change.
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Reference:
- 1. Westinghouse Nuclear Safety Advisory Letter NSAL-94-001, " Operation at Reduced Power Levels with Inoperable MSSVs," January 25, 1994.
- 2. Nuclear F 3el Services Letter NFS:PSS:94-044, " Power Range Neutron Flux Higl' Trip Setpoints with inoperable Main Steam Safety Valves,"
dated Fe';ruary 28,1994.