ML19312C754

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Div of Reactor Safety Guide on Containment Leak Testing
ML19312C754
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/19/1969
From:
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19312C752 List:
References
NUDOCS 7912190964
Download: ML19312C754 (4)


Text

,

e DRS TECHNICAL SAFETY GUIDE ON

' CONTAINMENT LFM TESTING-Definitions Class A test:

Integrated leak test Class B test:

Penetrations Class C test:

Isolation Valves Class D test:

ESF for leak control Use of B&C tests serve to justify reduced - pressure A-test The guide proposes a graduated increase in the test interval for the first three Class A tests, based in part on the design leak rate and calculated peak accident pressure.

In the section under testing, further definitions are:

P:

calculated peak accident pressure P

P:

test pressure, between 0.5P and 1.0 P t

p p

L

Leakage at P, initially p

p L

leakage at P, initially tg:

tech-spec allowabic operationa'l leak rate, measured at P L

L,:

a measured leak rate at P (re-tes t) g L:

tech spec limit for leak 0 P t

t L:

lictit for leak @ P P

P L,:

DBA-icak rate limit ~

Some' suggested requirements are:

1.

If L > L, revise retest schedule.

2*

If Lm > L, even-for 1-year test interval, then increase margin between tech-spec limit L and L Y912190p

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3.

If,'after repairs,'L

>L n

. pera e.

ass B te'sts will a

to, be performed at P.

Repair and retest. criteria are cited.

Class B test intervals should not exceed one year.

Some mathematical relationships are:

\\

fR T L

=

P P P L

'R T /

a i a a L.=fP g k pl p

to "

t( ~^

L where a represents a margin factor, a function of test' interval and classification.

The proposed tech specs specify peak accident pressure as 53.3 psig (P )

The test pressure P = 1/2 P, or 26.65 psig. Fessing from the tech specs is apecification of L,, margin at P, and a 40-year tes ting scheme.

In fact, it is not clear on the face of the tech spec that leakages are to extrapolated up to P, although measured at P.

No ' individual penetrations (valves, seals, hatches) ' leak rate is listed in the tech. specs.

Our guide. Paragraph 5.31 'has a repair and retest proviso en single-isolation valve leak rates.

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4.

L..

REACTOR BUILDING LEAK RATE CALCULATIONS FOR OCONEE 4

Oconee Tech Spec 15.4.3 (pp15-50 et. seq.) deal with RB leak rate.

They use these terms:

Lev = net equivalent leak rate in terms of iodine total leak rate L

=

T leak rate through liner and untested penetrations L

=

RB L

= leak rates through tested penetrations p

T RB +

~

pent Since L is filtered (90% efficiency for iodines) then Lev " bRB + (

  • pent a

f pent) + (0.10)Lpent (L

~b or L

=

y T

L,

=L

- 0.90 L,

or T

Technical specification 15.4.3A provides :

1.

L < 0.25% by volune/24 hours T

2.

L,

< 0.275%/24 hours Section A2 permits L to be as high as 0.50%/24. hours, provided half or 0.25% goes through'RBthe penetration room.

Tech spec. 15.4.3B indicates a test schedule.

Unit 1 would have an initial full-pressure test and half-pressure before fuel loading, and another half-pressure af ter hot functional testing.

Unit 1 would be retested af ter the first refueling outage.

No further tests are scheduled; the test results would be used to determine future needs.

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e Paragraph C-1 of 15.4.3_ concerns penetration testing. Listed are

a. Valves and' Electrical Penetration
b. '. Ratch seals I

'c.

Fuel transfer tube seals,

d.

Isolation valves Not listed are weld test channels and angles Acceptance criteria-is in-paragraph C-2 for the penetration tests.

Comments:

It appears that the proposed tech specs would permit a leak rate of 2.75%

per day (gross, or L pr vided it all went through the penetration room.

T That is, L = 2.75%

T L

=0 g

L

= 2.75%

pent L

=LRB + 0.'10 L ev pent L,y = 0 + (0.10) (2.75) = 0.275%

This is 'S 1/2 times the leak rate assumed in the FSAR, p 14-65.

Since the noble gases are unfiltered, the whole body dose may be 10 rem instead of the 1.9 - rem mentioned.

It seems like some limit on L is indicated.

^

pent I also wonder how the charcoal heat load was calculated, if these high leak rates to the penetration room do in. fact occur.

Mention is made on p 15-53 about 2/3 down the page, of a "0.5 percent allowable 1imit at the design pressure".

I did not see that limit as a

~

tech spec._ A sentence near the top of p. 5-55 is similarly vague.

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