ML19308E124
| ML19308E124 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/10/1972 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19308E120 | List: |
| References | |
| NUDOCS 8003200842 | |
| Download: ML19308E124 (3) | |
Text
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Recommended PWR Inservice Inspection Program for Detection of Effects of Reactor Coolant Leakage l
i A.
Inspection Requirements l
(1) Prior to reactor startup following each refueling outage, all pressure-retaining components of the reactor coolant pressure boundary shall be visually examined for evidence of reactor i
coolant leakage while the system is under a test pressure not less than the nominal system operating pressure at rated power.
This examination (which need not require removal of insulation) shall be performed by inspecting (a) the exposed surfaces and joints of insulations, and (b) the floor areas (or equipment) directly underneath these components.
At locations where reactor coolant leakage is normally expected and collected (e.g., valve stems, etc.), the examination shall verify that the leakage collection system is operative and
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leaktight.
(2) During the conduct of the examinations of (1) above, particular attention shall be given to the insulated arean of components constructed of ferritic steels to detect evidence of boric acid residues resulting from reactor coolant leakage which might have accumulated during the service period preceding the refueling outage.
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. (1) The visual. examinations of (1) and (2) above shall be conducted in conformance with :he procedures of Article IS-211 of Section XI of the ASME Boiler and Pressure Vessel Code.
B.
Corrective Measures (1) The source of any reactor coolant leakage detected by the examina-tions of I) above shall be 'ocated by the removal of insulation where necessary and the following corrective measures applied:
(a) Normally expected leakage from component parts (e.g., valve 1
stems) shall be minimized by appropriate repairs and mainten-ance procedurea. Where such leakage may reach the surface of ferritic components of the reactor coolant pressure boundary, the leakage shall be suitably channeled for collection and disposal.
l (b) Leakage from through-wall flaws in the pressure-retaining mem-brane of a component shall be eliminated, either by corrective repairs or by component replacement. Such repairs shall con-form with the requirements of Article IS-400 of Section XI of the ASME Boiler and Pressure Vessel Code.
(2) In the event boric acid residues are detected by the examinations or A(2) above, insulation from ferritic steel components shall be removed to the extent necessary for examination of the component
I i surfaces wetted by reactor coolant leakage to detect evidence of corrosion.
The following corrective measures shall be applied:
(a) An evaluation of the effect of any corroded area upon the structural integrity of the component shall be performed in accordance with the provisions of Article IS-311 of Section XI Code, i
(b) Repairs of corroded areas, if necessary, shall be performed in accordance with the procedures of Article IS-400 of Section XI Code.
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