ML20044A231
| ML20044A231 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 06/19/1990 |
| From: | Mary Johnson CINTICHEM, INC. |
| To: | |
| Shared Package | |
| ML20044A229 | List: |
| References | |
| NUDOCS 9006280241 | |
| Download: ML20044A231 (3) | |
Text
Cintichen Inc.
(Docket 450-54, License #R-81) 4.0 SURVEILLANCE REQUIREMENTS Sections 4.1, 4.2, 4.3, and 4.10 are listed below with the basis for deleting them. Section 4.8 is stated in its current form followed by the recommended wording.
DELETE 4.1 Measuring and Safety Channel Calibration A channel calibration of each measuring and safety channel shall be performed annually (see Sections 3.3.4 ,
and 3.3.5).
BASIS A defueled core will not require any nuclear i instruments therefore, thcoe instruments do not require i calibration. )
DELETE !
4.2 Reactivity Surveillance
- 1. The- reactivity worth of each control rod !
(including the regulating rod) and the shutdown margin shall be determined whenever operation requires a reevaluation of core physics parameters, or annually, which ever occurs first. )
The rod worth will be determined using the i j reactivity-period or rod-drop methods, j
- 2. The reactivity worth of an experiment shall be estimated, or measured at low power, before j l conducting the experiment. i
- 3. Boron carbide rods shall be gauged quarterly and l
- any dimensional changes reported promptly to the :
Commission. Silver / Indium / Cadmium control rods >
i l chall be gauged annually, or, in the case of newly L
installed. rods, at the end of the first six months. If any Ag/In/Cd or boron aluminum alloy :
rod does not meet the acceptance criteria, it shall be removed from service. In addition, all j other rods manufactured from the same batch shn11 '
be inspected.
l 0006280241 900619 !
PDR ADOCK 05000054 P PDC -), s MDJ/051.90D i
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BASIS A defueled core makes reactivity worth measurements and rod gauging unnecessary.
DELETE 4.3 Control and Safety System Surveillance
- 1. The scram time shall be measured annually. If a control rod is removed from the core temporarily, or if a new rod is installed, its scram time shall be measured before reactor operation. If the bridge is moved, the scram time will be measured before subsequent reactor operation.
- 2. A channel test of each measuring channel in the reactor safety system shall be performed monthly or prior to each reactor operating period, which ever occurs first, unless the preceding shutdown period is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less. A channel test before startup is, however, required on any channel receiving maintenance during the shutdown period.
- 3. A channel check of each measuring channel (except for the pool level) in the reactor safety system shall be performed daily when the reactor is in operation.
BASIS Control and safety systems are not needed with a j defueled core.
I REWORD !
TB Pool Water i
- 1. The pH and specific resistance of the pool water shall be determined each-week.
It is requested that the specification be rewritten to read 4.8 Pool Water j l 1. The pH and specific resistance of the pool water i shall be determined each week, whenever the pool l L contains reactor fuel.
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., f BASIS r Technical Specification 3.8 (Pool Water Quality) specifically says that the pool water quality limits apply only to primary cooling system water in contact with fuel elements. Once the reactor fuel has been removed from the pool, there is no T.S. reason to maintain water quality.
DELETE 4.10 Flux Distribution :
In order to verify that power gradients among fuel f element do not cause peaking factors to exceed those used in the basis of Section 2.1, the radial neutron
,,, flux distribution will be determined whenever a significant core configuration change is made. 1 P. ASIS Flux distributions cannot be performed on the defueled '
Core.
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