ML19326C085
| ML19326C085 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/14/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326C083 | List: |
| References | |
| NUDOCS 8004180752 | |
| Download: ML19326C085 (3) | |
Text
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'V 3.1.2 Pressurization, Heacuo, and Cooldown Limitations Specification 3.1.2.1 Hydro Tests For thernal steady state system hydro tests the system may be pressurized to the limits set forth in Specifiestion 2.2 when there are fuel assemblies in the core, under the provisions of 3.1.2.3, and to ASME Code limits when no fuel assemblies are present provided 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 Leak tests required by Specification 4.3 shall be conducted under the provision of 3.1.2.3.
3.1. 2. 3 The reactor coolant pressure and the system heatup and cooldown
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rates (with the exception of the pressurizer) shall be limited in accordance with Figure 3.1.2-2 and Figure 3.1.2-3, an<'. are as follows:
Heatup:
Allowable combinations of pressure and te perature shall be to the right of and below the limit line in Figure 3.1.2-2.
The heatup rates shall not exceed those shown on Figure 3.1.2-2.
Cooldown:
Allowable combinations of pressure and temperature for,a specific 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 Figure 3.1.2-3.
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 pressurizer heatup and cooldown rates shall not exceed 100F/hr.
De spray shall not be used if the temperature difference between the pressuri:er and the spray fluid is greater than 430F.
3.1.2.6 Prior to reaching six 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 10CFR50 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 wi'th Specification 4.2.7.
he highest predicted adjusted reference temperature of all the beltline region materials shall be used to deter.nine the adjusted reference temper-ature at the end of the service period. The basis for this predic-l tion shall be submitted for NRC staff review in accordance with i
Specification 3.1.2.7.
I Amendment No. 22, 28 8 004180 7fg
s 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 specifi-cations submitted in accordance with 10CFR Part 50, Appendix G, Section V.C.
Bases All reactor coolant system components 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 hestup and cooldown operations. The number of thermal and loading cycles used for design purposes are shown in Table 4-8 of the FSAR. The maxi-mum 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 generator at a temperature less than 100F satisfies strgps levels for temperatures below the DTT.(3)
The major components of the reactor coolant pressure boundary have been analy:ed in accordance with Appendix G to 10CFR50. Results of this analysis, including the actual pressure-temperature limitations of the reacter coolant pressure boundary, are given in RAW-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, normal heatup, and normal cooldown respectively. The limit curves are applicable through the fifth effective full power year of operation. Thes. curves are adjusted by 25 psi and 10F for possible errors in the pressure and te=perature sensing instruments. The pressure limit is also adjusted for the pressure differen-tial between the point of system pressure measurement and the limiting com-ponent for all operating reactor coolant pump combinations.
The pressure-temperature limit lines shown on Figure 3.1.2-2 for reactor criticality and on Figure 3.1.2-1 for hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10CFR50 for reactor criticality and for inservice hydrostatic 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 10CFR50, 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 no:tle is imposed to maintain the thermal stresses at the pressuri:er spray line no:-le below the design limit. Temperature requira-ments for the steam generator correspons with the measured NDTT for the shell.
Amendment No. 22, 28 19
The heatup and cooldown rates stated in this specification are intended as the maximum changes in temperature in one direction in a one hour period. The actual temperature linear ramp rate may exceed the stated limits for a time period provided that the maximum total tegerature difference does not exceed the limit and that a tempera *.ure hold is observed to prevent the total temperature difference from exceeding the 1 Lait for the one hour period.
REFERENCES (1) FSAR, Section 4.1.2.4 (2) ASME Boiler and Pressure Code,Section III, N-415 (3) FSAR, Section 4.3.10.5 (4) BAW-1440 1
s Amendment No. 2, 22, 28 20