ML20214N662
| ML20214N662 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/11/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20214N664 | List: |
| References | |
| NUDOCS 8609160417 | |
| Download: ML20214N662 (1) | |
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I 3.1.2 Heatup and Cooldown Rates (Cont'd)
I (3) The limit lines in Figures 3-1, 3-2 and 3-3 are based on the requirements of Reference 9, Paragraphs IV.A.2 and IV.A.3.
These lines reflect a preservice hydrostatic test pressure of 2400 psig and a vessel flange material reference temperature of 60 F(8) l Basis All components in the primary coolant system are designed to withstand the effects of cyclic loads due to primary system temperature and pressurechanges.II) These cyclic loads are introduced by normal unit load transients, reactor trips and start-up and shutdown operation.
During unit start-up and shutdown, the rates of temperature and pressure changes are limited. A maximum plant heatup and cooldown rate of 100*F per hour is consistent with the design number of cycles and satisfies stress limits for cyclic operation.(2)
The reactor vessel plate and material opposite the core has been purchased to a specified Charpy V-Notch test result of 30 ft-lb or greater at an NDTT of + 10*F or less. The vessel weld has the highest RT f plate, weld and HAZ materials at the fluence to which the NDT Figures 3-1, 3-2 and 3-3 apply. (10) The unirradiated RT has been NDT determined to be -56*F.III) An RT of -56*F is used as an unirradiated NDT value to which irradiation effects are added.
In addition, the plate has been 100% volumetrically inspected by ultrasonic test using both longitudinal and shear wave methods. The remaining material in the reactor vessel, and other primary coolant system components, meets the appropriate design code requirements and specific component function and has a maximum NDTT of +40*F.(5)
As a result of fast neutron irradiation in this region of the core, there will be an increase in the RT with operation. The techniques used to predict the integrated fast neutron (E > 1 MeV) fluxes of the reactor vessel are described in Section 3.3.2.6 of the FSAR and also in Amendment 13 Section II, to the FSAR.
hD obs5 3-5 Amendment No. 27,U,55,87,97 DO 5
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