ML19262C692
| ML19262C692 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/06/1980 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19262C672 | List: |
| References | |
| NUDOCS 8002150418 | |
| Download: ML19262C692 (5) | |
Text
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ATTACH'iEtG 3
REFERENCE:
ITEM 4 b_.
8002150
'0
3.1. 2 P ssurization, Heatup, and Cooldown Limitations Speci fica tion _
3.1.2.1 Hydro Tests For thermal steady state system hydro tests the system may be pressurized to the limits set forth in Specification 2.2 when there are fuel assemblies in the core, under the provisions of 28 3.1.2.3, and to ASME Code limits when no fuel assemblies are present provide the reactor coolant system limits are to the right of and below the limit line in Figure 3.1.2-1.
3.1.2.2 Leak Tests 28 Leak tests required by Specification 4.3 shall be conducted under provision of 3.1.2.3.
3.1.2.3 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall b= limited in accordance with Figure 3.1.2-2, Figure 3.1.2-3, and Figure 28 3.1.2-4, and are as follows:
Normal Operation Heatup:
Allowable combinations of pressure and temperature shall be to the right of and below the limit line in Figure 3.1.2-2.
The 28 heatup rates shall not exceed those shown on Figure 3.1.2-2.
Normal Operation Cooldown:
Allowable combinations of pressure and temperature for a specific 28 cooldown shall be to the right of and below the limit line in Figure 3.1.2-3.
Cooldown rates shall not exceed those shown in Figt.e 3.1.2-3.
Emergency Operation:
During emergency conditions when there is no forced flow in the RCS and HPI has been actuated, allowable combinations of pres-sure and temperature shall be to the right of and below the limit line in Figure 3.1.2-4.
3.1.2.4 The secondary side of the steam generator shall not be pressurized above 200 psig if the temperature of the steam generator shell is below 100F.
3.1.2.5 The pressur er heatup and cooldown rates shall not exceed 100F/hr.
The spray snall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 430F.
Amendment 22, 28 18
3.1.2.6 Prior to completing five effective full power years of operation, Figures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service period in accordance with 10 CFR 50, Appendix G, Section V. B.
The service period shall be of sufficient duration to permit the scheduled evaluation of a portion of the surveillance data scheduled in accordance with Specification 4.2.7.
The highest predicted adjusted reference temperature of all the beltline region materials shall be used to determine the adjusted reference temper-ature at the end of the service period. The basis for this predic-tion shall be submitted for NRC staff review in accordance with Specification 3.1.2.7.
3.1.2.7 The updated proposed technical specifications referred to in 3.1.2.6 shall be submitted for NRC review at least 90 days prior to the end of the service period. Appropriate additional NRC review time shall be allowed for proposed technical specifications submitted in accor-dance with 10 CFR 50, Appendix G, Section V. C.
Bases All reactor coolant system ccmponents are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. (1) These cyclic loads are introduced by unit load transients, reactor trips, and unit heatup and cooldown operations.
The number of thermal and loading cycles used for design purposes are shown in Table 4-8 of the FSAR. The maximum unit heatup and cooldown rate of 100F per hour satisfies stress limits for cyclic operation. (2) The 200 psig pressure limit for the secondary side of the steam gererator at a temperature less than 100F satisfies strex levels for temperatures below the DTT. (3)
The major components of the reactor coolant pressure boundary have been analyzed in accordance with Appendix G to 10 CFR E0.
Results c,f this anal-ysis, including the actual pressure-temperature limitations of the reactor coolant pressure boundary, are given in BAW-1440. (4)
Figures 3.1.2-1, 3.1.2-2, and 3.1.2-3 present the pressure-temperature limit curves for hydrostatic test, rormal heatup, and normal cooldown respectively.
The limit curves are applidle through the fifth effective full power year of operation.
These curves are adjusted by 25 psi and 10F fo possible errors in the pressure and temperature sensing instruments.
The pressure limit is also adjusted for the pressure differential between the point of system pres-sure measurement and the limiting component for all operating reactor coolant pump corbinations.
The pressure-temperature limit lines shown on Figure 3.1.2-2 for reactor critically and on Figure 3.1.2-1 for hydrostatic testing have been pro-vided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice hydro-static testing.
The actual shift in RTNDT of the beltline region material will be established periodically during operation by removing and evaluating, in accordance with Appendix H to 10 CFR 50, reactor vessel material irradiation surveillance specimens which are installed near the inside wall of this or a similar reactor vessel in the core region.
The spray temperature difference restriction based on a stress analysis of the spray line nozzle is imposed to maintain the termal stresses at the pressurizer spray line nozzle below the design limit.
Temperature requirements for the steam generator correspond with the measured f4DTT for the shell.
The heatup and cooldown rate', stated in this specification are intended as the maximum changes in temperature in one direction in one hour period.
The actual temperature linear ramp rote may exceed the stated limits for a time period pro-vided that the maximum total temperature difference does not exceed the limit and that a temperature hold is observed to prevent the total temperature dif-ference from exceeding the limit for the one hour period.
Figure 3.1.2-4 presents the pressure-temperature limit curves to be applied only during extreme emergency conditions.
These conditions are specifically foreseen to include a situation of interrupted normal (forced or natural) RCS loop cir-culation combined with High Pressure Injection necessary t.o maintain acceptable margin to saturation.
However, this should not be construed to allow operation beyond the limits of Specification 2.2.1.
REFEREllCES (1)
FSAR, Section 4.1.2.4 (2) ASME Boiler and Pressure Code,Section III, fi-415 (3) FSAR, Section 4.3.10.5 (4) BAW-1440 Amendment 28 20
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Indicated Reactor Coolang Tempera {0ure,Tc, ggo 320 360 400 REACTOR COOLANT SYSTEM, EMERGENCY OPERATION FOR FIRST 5.0 EFFECTIVE FULL POWER YEARS LIMITATIONS APPLICABLE Figure 3.1.2-4
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