ML20215E968

Rev 0 to Procedure Bwvp 200-1077, Leak Testing of Potentially Radioactive Components Outside of Containment

ML20215E968
Person / Time
Site:	Braidwood
Issue date:	06/11/1987
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20215E962	List: ML20215E960 ML20215E968
References
BWVP-200-1077, NUDOCS 8706220177
Download: ML20215E968 (5)

Text

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. LEAK TESTING OF POTENTIALLY RADIOACTIVE COMPONENTS OUTSIDE OF CONTAINMENT A. STATEMENT OF APPLICABILIT_Y The purpose of this procedure is to provide a method of leak testing potentially radioactive systems outside of containment, and trending this leakage on a periodic basis. Testing will be performed prior to 20% reactor power and during the ASME quarterly pump surveillances.

B. REFERENCES

1. III D.1.1, NUREG 0737. .

2. August 26, 1986 A. D. Miosi letter to H. R. Denton.

3. BwvS 290-1, Visual Examination (Leakage Test) of Potentially Radioactive Components Outside Containment.

C. PREREQUISITES l

The system being tested must be at its nominal operating pressure (Listed in Attachment A).

D. PRECAUTIONS Equipment being tested is under pressure, exercise caution while performing exams.

E. LIMITATIONS AND ACTIONS The total ECCS leakage shall be compared to Figure 1 of Section.

G. In the event the total leakage is GREATER than the value for that power level, the Shif t Engineer shall be notified immediately. The Shift Engineer shall reduct the leakage to an acceptable value or reduce power in accordance with Figure 1 of Section G within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

F. MAIN BODY

1. Perform leak testing of the following. If only a portion of ,

the list is completed, initial only those portions completed.

Containment Spray A Train /

B Train /

Chem /Vol Control A Train /

B Train /  ;

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Residual Heat Removal A Train /

B Train /

Safety Injection A Train /

B Train /

t 2. RECORD leakage observed (Quantity, GPH), from the applicable sections of BwVP 290-1, in Table 1 on Data Sheet D-1.

t 3. . For subsequent tests, the leakage shall be compared to the previous leakage. The difference shall be noted and added/ subtracted from the Total Leakage.

G. ACCEPTANCE CRITERIA The Total ECCS Leakage Rate, obtained from Table 1 of Data Sheet 1, will be compared to Figure 1. This Leakage Rate must be within the limits specified for the applicable reactor pr.wer level.

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. Sw VP Doo-lo77 Revision 0 TABLE 1 SYSTDt/ LEAKAGE MEASUREMENTS (GALLONS / HOUR)

TRAIN 1 2 3 4 5 6 Baseline Data _

Containment Spray (CS)/A / _,

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Containment Spray (CS)/B / / / / / ,

Ch:mical and Volume Control / / / / /

LCV)/A Ch2mical and Volume Control / / / / /

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Safety Injection j (SI)/B / / / / /

Residual Heat Removal (RH)/A / / / / /

Residual Heat Removal (RH)/B / / / / /

l Total ECCS Leakage t / t / t / t /* t /

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ATTACHMDIT A: SYSTDi NOMINAL OPERATING PRESSURES SYSTEM NOMINAL OPERATING PRESSURE (PSIG) t

1. Containment 2 250 psig Spray (CS)

2. Chemical and 2 2485 psig Volume Control (CV) .

i 3. Safety 2 1500 psig Injection (SI) l_

4. Residual Heat 2 220 psig Removal (RH) i l

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