ML19262A483

Inservice Insp for Effects of Reactor Coolant Leakage.

ML19262A483
Person / Time
Site:	Three Mile Island
Issue date:	02/28/1972
From:	METROPOLITAN EDISON CO.
To:
Shared Package
ML19262A481	List: ML19262A480 ML19262A483
References
PROC-720228, NUDOCS 7910300424
Download: ML19262A483 (2)

Text

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TMI U:IIT 1 IIISERVICE I:!SPECTIO:I FOR EFFECS OF REACTCR C00LA'IT LEAKAGE A. Inspection Pecuirements (1) During the period of reactor shutdown, refueling and startup for each scheduled, normal refueling outage, the accessible pressure-retaining cc=ponents of the reactor coolant pressure boundary will be visually examined for evidence of reacter coolant leakage.

This examination (which will 1.ot require the removal of insulation) vill be performed as follows :

(a) The exposed surface and joints of insulation which are accessible for direct visual examination vill be visually inspected for evidence of reactor ecclant leakage. This era 4naticn vill be performed while the system is under a test pressure not less than the nominal operating pressure at rated power.

Most of the inaccessible surfaces are en the reactor vessel. The reacter vessel closure vill be examined for evidence of leakage on the flange surfaces and for CRD and instrument nozzle leakage. The reactor vessel flange surfaces and the insulation

.under the reactor vessel lever head and incore instrument no :les vill likewise be examined. The remaining external surfaces of the reactor vessel are not accessible during refueling cutage. These areas will be examined for evidence of leakage during scheduled inservice inspections of reactor vessel sea velds. -

(b) The floor areas (or equiptent) directly underneath these ec=ponents which are accessible for direct visual examination vill be visually inspected for evidence of reactor coolant leakage. This examination vill be performed either while the system is under a test pressure not less than the nc=inal operating pressure at rated pcVer or i==ediately after it has been at that pressure.

(2) Prior to reactor startup following each refueling outage, all connactions on pressure-retaining ec=pcnents of the reactor coolant pressure boundary which have been cpened during the cutage vill be visually examined for evidence of reactor coolant leakage. This exa i-a-i n vill be performed while the syster is under a test pressure not less than the nc=inal Operating pressure at rated power.

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(3) During the conduct of the examination of (1) above, particular attention vill be given to the insulated areas of co=ponents constructed of ferritic steels to detect evidence of boric acid residues resulting frem reactor coolant leakage which might have accumulated during the service period preceding the refueling cutage.

(h) The visual examinations of (1) and (2) above vill be conducted in conformance with Article IS-211.1 of Section XI of the ASME Boiler and Pressure

'lessel Code to the extent required for detection of leakage, and as accessibility permits.

B. Corrective Measures (1) The source of any reactor coolant leakage detected by the examinations of A(1) above vill be located by the re= oval of insulation wherr necessary and the following corrective measures applied:

(a) Normally expected leakage fres component parts (e.g.,

valve stems ) vill be =inimized by appropriate repairs and main-tenance procedures. Where such leakage may reach the surface of ferritic compenents of the reacter coolant pressurt boundary, the leakage vill be suitably channeled for collection and disposal.

(b) Leakage frc through-vall flaws in the pressure-retaining membrane of a compcnent vill be eliminated, either by corrt -tive .

repairs or by ec=penent replacement. Such repairs vill conform with the applicable code requirements .

(2) In the event boric acid residues are detected by the examinations of A(3) above, insulatien free ferritic steel ec=penents will be re=cved to the extent necessary for exasination of the cc penent surfaces vetted by reactor coolant leakase to detect evidence of corrosion.

The following corrective measures will be applied:

(a) An evaluation of the effect of any corroded areas upon the structural integrity of the ec=ponent will be performed in accordance with the applicable code requirements.

(b) Repairs of corroded areas , if necessary, vill be performed in accordance vi;h the applicable code requirements.

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