ML19320A218

Proposed Tech Specs 3.1 Re Pressurization Heatup & Cooldown Limitations

ML19320A218
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/08/1977
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19320A209	List: ML19320A208 ML19320A218
References
NUDOCS 8004210519
Download: ML19320A218 (8)

Text

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[ 3.1.2 Pressurization, Heatup, and Cooldown Limitations Specification 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 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 ti.e provision of 3.1.2.3.

3.1.3.3 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figure 3.1.2-2 and Figure 3.1.2-3, and are as follows:

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 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.

The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 430F.

3.1.2.6 Prior to reaching nine 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 10CFRS0 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 sheeduled 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.

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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 prier 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 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 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 stress 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 10CFR50. Results of this analysis, 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, normal heatup, and normal cooldown respectively. The limit curves are applicable through the eighth effective full power _ year of operation. These curves are adjusted by ~

25 psi and 10F for possible errors in the pressure and temperature 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 hate 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::le is imposed to maintain the thennal stresses at the pressurizer spray line nozzle below the design limit. Temperature require-ments for the steam generator correspond with the measured NITTT for the shell.

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4 The heatup and cooldown rates stated in this specification are intended as the maximum changes in tenperature 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 tenerature difference does not exceed the limit and that a temperature hold is

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observed to prevent the total temperature difference from exceeding the limit for the one hour period.

REFERENCES (1) FSAR, Section 4.1.2.4 (2) ASME Boiler and Pressure Code,Section III, N-41S (3) FSAR, Section 4.3.10.S (4) BAW-1440 4

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3.1.3 Minimum Conditions For Criticality Specification 3.1.3.1 The. reactor coolant temperature shall be above 525F except for portions of- low power physics testing when the requirements of Specification 3.1.8 sb .11

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3.1.3.2 Reactor coolant temperature shall be to the right of the criti-

.cality limit of Figure 3.1.2-2.

3.1.3.3 When the reactor coolant temperature is below the minimum tempera-ture specified in 3.1.3.1 above, except for portions of low power physics testing when the requirements of Specification 3.1.8 shall apply, the reactor shall be suberitical by an amount equal to or greater than the calculated reactivity insertion due to depressurization.

3.1.3.4 The reactor shall be maintained suberitical by at least 1 percent ak/k until a steam bubble is formed and an indicated water level between 45 and 305 inches is established in the pressurizer.

3.1.3.5 Except for physics tests and as limited by 3.5.2.1, safety rod groups shall be fully withdrawn and the regulating rods shall be positioned within their position limits as defined by Specifi-cation 3.5.2.5 prior to any other reduction in shutdown margin by deboration or regulating rod withdrawal during the approach to criticality.

Bases .

At the beginning of life of the initial fuel cycle, the moderator temperature '

coefficient is expected to be slightly positive at operating temperatures with the. cperating configuration of control rods.(1) Calculations show that above .

~ 525F the- positive moderator coefficient is acceptable.

Since the moderator temperaturc coefficient at lower temperatures will be less negative or more positive than at operating temperature,(2) startup ,

and operation of the reactor when reactor coolant temperature is less that -

525F is prohibited except where necessary for low power physics tests.

The potential reactivity insertion due to the moderator pressure coeffi-cient(2) that could result from depressurizing the coolant from 21 psia to saturation pressure of 900 psia is approximately 0.1 percent ak/k.

During physics tests, special operating precautions will be taken. In addition,- the strong negative Doppler coefficient (1) and the small integrated ak/k would limit the magnitude of a power excursion resulting from a reduction of moderator density.

. The requirement that the reactor is not to be made critical below the

- limits of Figure 3.1.2-2 provides increased assurances that the proper relationship. between primary coolant pressure and temperatures will be maintained relative 'to the NDTT of the primary coolant system. Heatup to .this temperature will be accomplished by operating the reactor coolant

. pumps.

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. - ,s 3.1. 8 Lower Power Physics Testing Restrictions Specification The following special limitations are placed on low power physics testing.

3.1.8.1 Reactor Protective System Requirements

.A. Below 1720 psig, shutdown bypass trip setting limits shall apply in accordance with Table 2.3-1.

B. Above 1800 psig, nuclear overpower trip shall be set at less than 5.0 percent. Other settings shall be in accordance with '

Table 2.3-1.

3.1.8.2 Startup rate rod withdrawal hold (1) shall be in effect at all times.

3.1.8.3 During low power physics testing the minimum reactor coolant temper-ature for criticality shall be to the right of the criticality Itmit ,

of Figure 3.1.2-2. A minimum shutdown margin of 1% ak/k shall be maintained with the highest worth control rod fully withdrawn. -

Bases The above specification provides additional safety margins during low power physics testing.

REFERENCES ,

(1) FSAR, Se tion 7. 2. 2.1.3.

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