ML20235D684

Submits Summary of Items Modified in New Guide Re Reactor Containment Leakage Testing for Water Cooled Power Reactors

ML20235D684
Person / Time
Issue date:	06/23/1987
From:	Norian P NRC
To:	Hard J NRC
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References
FOIA-87-40 NUDOCS 8707100261
Download: ML20235D684 (2)

Text

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e u l w adMr/ew'd Jidw-aIk mA"a NOIE FOR JAMES E. HARD W t REACIOR CONTAINMENT LEAKAGE TESTING FOR WATER COOLED POWER REACIOPS

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l Tne following is a sumary of those items that have been modified l in the new guide.

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1. The most significant diange is in the frequency for perfoming l the integrated leakage rate tests. The old guide (page 13) {

presented a table for testing based on allowable leak rate

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and maximum pmssure following the DBA. This system gave a '

large reward for high leakage rates and everyone pushed to get the maximum possible. To avoid this problem, the new guide proposes the sane schedule for_ all facilities .regardless of the maximum allowable leakage rate. Since ihajor shutdowns ~ i wil1~o 'ccur'Every tefi 9siBi Tor in Frvice inspection, we decided upon a test every ten test every 373 years, years and two inbetween. That is, a

2. l The second change concerns the containment test ' atmosphere as j compared with the actual anticipated DBA environment. To i account for this difference, we have an "RT" correction (gas constant-temperature) in equation 1 cn page 11 of the old guide.

However, tests at the CVTR (reinforced concrete vessel) and the CSE (steel vessel) both showed lower leakage with hot 2 air so the "T" correction wa9 droppe'd (ETe~s~tir'witTi steam

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showed that the leakage just about stopped, so the "R" correction was dropped (steam leakage tests were not done at CVfR).

Standard leakage rate tests following steam injection at both CVTR and CSE showed no increase in leakage as a result of the steam injection. -

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3. The previous guide proposed leakage limits for individual 44 Ye y, k

penetrations (Type B tests) and individual valves (Type C tests). The total for all trations and all valves can now ' leak no more than 30% .i This change was made mainly as a convenience to the op tors.

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4. Credit is given for the Penetration Pressurization System and

. Isolation Valve Seal Water System (both installed at Indian Point 2, for example). The satisfactory performance of these systems replaces the need to perform Type B and Type C tests on those components.

5. Credit is given for cont'inuous leakage monitoring systems. Facilities l having this feature need perform Type B tests only every other '

shutdown rather than every shutdown.

6. In my opinion, the main item not resolved by this guide. is the isolation valves on BWR steam lines. We are still reviewing l this in house, so the guide now treats this leakage on an ad hoc basis.

f%AbY Paul E. Norian Systems Analysis Branch Division of Reactor Standards

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