ML19257C280

Primary Containment Leak Rate Testing, for 1978-79

ML19257C280
Person / Time
Site:	Vermont Yankee
Issue date:	12/31/1979
From:	James Anderson, Humphries J VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML19257C278	List: ML19257C277 ML19257C280
References
NUDOCS 8001250492
Download: ML19257C280 (23)

Text

.

VERMONT YANKEE PRIMARY CONTAINMENT LEAKAGE RATE TESTING 1978-1979 Test Coordinators D. A. Reid S. A. Vekasy Prepared By J. W. Anderson J. S. Humphries 1809il7

8 0012 50 f fg

INTRODUCTION During the 1979 Refuel Outage which occurred during the period from September 21, 1979 to November 3, 1979, a Type A Containment Integrated Leakage Rate Test was performed. Previous Leak Rate Test Reports were filed with the USNRC in January 1975 and August 1978.

This report describes all reactor containment testing performed after the 1978 Type A Test and refuel outage up to and including the October 1979 Type A Test. In accordance with the requirements of 10 CFR 50, Appendix J, a summary analysis of all periodic Type B and Type C tests that were performed since then is included in this report. The Type B and Type C test results included in this report are from the 1979 Refuel Outage.

All testing performed during the period covered by this report conformed to the rules and regulations specified in 10 CFR 50, Appendix 3.

SUMMARY

The plant was shut down on September 22, 1979 for refueling.

The Type B and C test program was implemented shortly before the plant shutdown. The Type A test was scheduled for the end of the refuel outage.

Pressurization for the Type A test commenced on October 29, 1979 with two air compressors of 2100 SCFM total capacity and approximately a 6 psi /hr charging rate. Containment pressure was raised to the calculated peak accident pressure of 44 psig over an 8-hour and 50-minute interval. This time period included containment pressure hold points at the 5,15, and 30 psig levels to facilitate detectic a of containment leakage. During the stabilization period, while r. 44 psig, leak deteccion crews located a leak in a copper tube fitting connected with penetration X-101B. The leakage was isolated and later quantified. Af ter stabilizing for seven hours, the 24-hour test period was initiated at 1631 on October 29, 1979. The 24-hour test was completed October 30, 1979 at 1631.

The test was determined to be successful upon correcting the results for the leaking fitting, the change in water level in the drywell sumps, the change in the reactor water level, and the isolation valves of systems required for the test.

The absolute method of leakage determination was employed. The containment leakage rate was determined from the slope af a least-squares fit of a mass of air versus time plot (Figure II). The measured rate at the 95% confidence level was .3271 012%/ day. The f.inal corrected leak rate at the 95% confidence level was .507.%/ day.

1809 1I8

1979 TYPE TEST Description of Test The containment was made ready for the integrated leakage rate test and pressurization commenced at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> on October 29, 1979.

Pressurization was accomplished by using two mobile, oil free air compressors, one with 900 SCFM capacity, and the other with 1200 SCFM capacity. They were connected by hose to the nitrogen purge supply at the flange connection upstream of FCV-1-156-10 as shown on the attached Figura 1. At 0115 the 5 psig containment pressure holdpoint was reached and leakage location survey personnel were dispatched.

As a result of the survey, no leakage was detected.

Pressurization recommenced at 0205 with pressurization rates of 7.1 to 8.3 psig/hr until the 15 psig containment pressure holdpoint was reached. As before, leakage detection crews were dispatched with no reports of leakage. Containment pressurization resumed at 0352 hours0.00407 days <br />0.0978 hours <br />5.820106e-4 weeks <br />1.33936e-4 months <br />. The 30 psig containment pressure holdpoint was reached at 0545. No leakage was detected by the survey crews. At 0654 pressuri-zation resumed once again. At 0825 one air compressor was shut down and flow reduced to 50% at a containment pressure of 41.9 psig.

Pressurization rate was reduced to 2.22 psig/hr by 0800, and down to

.358 psig/hr by 0915. At 0925 the air inbleed was isolated and test pressure of 44.22 psig (119.52" Hg Abs.) was reached at 0931 hcurs on October 29th.

Data collection was initiated to measure the stability of the variable quantities. At 1015 leakage was detected from a fitting connected to spare electrical penetration X-101B. By 1115 the leak was isolated by capping the tube upstream of the leak. The air mass (lbs) loss was later measured and added as a correction to the upper 95%

confidence level. Subsequently, other spare electrica.1 penetrations were evaluated for a similar configuration. None wera identified.

It was determined from the stabilization data that the start of the 24-hour test interval would be 1631 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.205955e-4 months <br />. Test data and computer calculations projected containment leakage with the additional calculated leakage from penetration X-101B would be within the test's acceptance criteria.

The peak pressure Type A Test was completed at 1631 October 30, 1979. A supplemental test, (required by Appendix J,10 CFR 50) to verify the accuracy of the intrumentation was conducted by metering back to the containment a mass of air approximately equal to one half of the allowable leakage. This pump back of 224.7 lbm was completed at 1729 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.578845e-4 months <br />. Sufficient data had been gathered at 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br /> to determine that this verification was successful. Containment de-pressurization commenced at 1843. All systems were normalized as required by operational needs by 0800 on October 31, 1979.

1809 i19

Analysis and Interpretation of Test Data The Vermont Yankee computer performs a computation of the total air mass on the containment every ten minutes. This enmputation is derived from an average of the one-minutes stored values of:

Drywell and Torus average air temperature Dryvell and Torus average dewpoint Containment pressure For a 24-hour test interval, there are 145 independen: data points. The 1979 Tyre A Test had one erroneous point at 1901 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.233305e-4 months <br />.

Based on statistical analysis in accordance with ANS N274 Draft 3, this point was deleted.

The data consists of a series of cass of air calculations made at discrete time intervals. The data lends itself to a statistical analysis based upon a time dependent rate of change of the contained

, mass of air. A small pressure change over the test interval is the basis for the assumption that the containment leakage rate is constant with respect to time.

A linear least square fit is employed to develop the best straight line fit to the data. The slope of this least squares fit line is the leakage rate.

The equation of the least squares fit line is of the form:

, Q = b + mT where: Q = mass of air b = Q intercept (Q value at time 0) m = slope of line (leakage rate)

T = time N = number of data points The values for b and m are determined from the following equations:

~"

b=

N

"" N EQT - EQET ,

2 N ET - (IT)2 ,

g g09 1 0' '

The 95% confidence interval of the leakage rate (slope of line) may be determined from the standard error of the slope and a " students table of t." The standard error is:

Standard error, S(m) = ~*

)

N2 a *

~

= 1 ~ NEQ - (EQ) ~"

2 N-2 NET' - (ET)Z The 95% confidence range on the slope is:

(" 0.95 = m + 0.025 (*}

where:

t 0.025 = the t factor at 95% level for 144 data points, (143 degrees of freedom) = 1.98 This method of applying the confidence range on the slope of a line is a statistically efficient mechod of determining that 19 of 20 points (95%) will lie within the computer range.

~

• Variance = (Standard deviation) =

Test Results A linear least square fit of the 144 data points calculated during this test presented in Table 1979-A, result in the following equation:

Q = 73707 - 10.032T Where 73707 represents the initial mass of contained air in pounds

-10.032 represents the leakage rate in lbs/hr The leakage rate expressed in fractional leakage of the initially contained mass is:

-10.032 lb/hr x 24 hr/ day x 100%

e= = -0.327%/ day 73707 lb.

The 95% confidence range on the slope using the same data is:

, -(10.3872 - 9.6774) lbs/hr x 24hr/ day x 100% = -0.012%/ day 2 x 73707 lb.

1809 121

Correction Factors

1. Correction for Isolation Valves V-3-181 = -0. 001%/ day V-12-68 = -0.005%/ day

2. Correction for Drywell Sumps

-0.025%/ day

3. Correction for Reactor Vessel Water Level

=+0.049%/ day

4. Correction for Isolated Primary Containment Boundary Leak

-0.186% / day The corrected leak rate at the 95% confidence level was .507%/ day.

This measured value is less than the Technical Specification limit of 0.75 La, (where La = 0.80 weight percent of contained mass per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), which is equivalent to 0.60 weight percent of contained mass per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Verification of Instrumentation Sensitivity Section II.A.3(b) of Appendix J to 10 CFR 50 requires that the accuracy of any Type A Test shall be verified by a supplemental test.

The Pumpback Method of verification was selected. In this method, a known quantity (Mass) of air is metered back into the containment and is compared with the change in the computer weight of air calculation.

Agreement between the metered quantity and the computer calculated quantity is specified in Appendix J to be +.25La.

The quantity metered back was selected to be equivalent to about onehalfoftheallowableofQ.8%/ day. The actual quantity metered was 630 ft at 54 psig and 60 F which is equivalent to 224.7 pcunds mass. The air charge required 8.5 minute to complete.

The average of the five computer calculated values of mass of air prior to the charge was 73503.4 lbs. The average of the five computer calculated values of mass of air following the charge was 73712.6.

During the 70 minute elapsed time between before and after measurements, at the measured leakage rate of -10.032 lbs/hr, 11.70 lbs was assumed to leak.

The balance is as follows:

Mass following air charge 73712.60 Mass prior to charge 73503.40 Difference 209.20

" Normal" Leakage + 11.70

• Total Difference 220.9 809 122 The comparison to the actual charge of 224.7 lbs is:

224.7 - 220.9 = 3.80 lbs. difference The allowable Supplement Test error of .25 La = 147.41 lbs.

The 3.8 lbs. in the 1979 Supplement Test was well within the accuracy limits specified in Appendix J.

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TABLE 1979-A PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET (TYPE A) 4 Time. Contained Pressure Temp. $ Time Contained Pressure Temp.

Mass (pounds) "Hg *F (Min) Mass (pounds) "Hg *F (Min)

START STABILIZATION 1541 73746 119.49 81.0 5

1221 73745 119.71 80.7 $ 1551 73723 119.46 81.2

~

1231 73804 119.71 80.8 $ 1601 73738 119.42 81.0 5

1241 73798 119.67 80.8 $ 1611 73746 119.46 80.7 1251 73789 119.67 80.8 $ 1621 73730 119.46 80.7

% REACTOR BULLDING 29.6B" Hg 1301 73001 119.67 80.8 $ START OF 24 HOUR TEST AP 44.08 PSIG 1311 73a03 119.67 80.9 $ 1631 73738 119.42 80.7 2

1321 73799 119.67 80.9 2 1641 73723 119.46 80.8 1331 73797 119.63 80.9 $ 1651 73717 119.46 80.8 a

1341 73818 119.63 80.7 2 1701 73716 119.46 80.9 3

1351 73809 119.59 80.9 $ 1711 73731 119.46 80.9 W

1401 73808 119.55 80.8 $ 1721 73694. 119.46 81.3 1411 73795 119.59 80.9 $ 1731 73747 19.46 80.9 5

1421 73782 119.59 81.0 2 1741 73736 119.42 80.9 1431 73771 119.55 80.8 $ 1751 73708 119.42 81.0 1441 73776 119.55 80.9 $ 1801 73686 119.40 81.3 1451 73766 119.55 81.1 $ 1811 73713 119.42 81.1 1501 73749 119.52 80.9 2 1821 73711 119.40 81.0 E

1511 73757 119.52 81.1 $ 1831 73696 119.42 81.2 E

1521 73751 119.55 81.1 $ 1 41 73699 119.40 81.1 2

1531 73758 119.49 80.9 $ 1851 73707 119.37 80.9 p ~-

Test Asst. /M W

' Date /)Lbv$e l r 31,I$75 Approved ~b b, 1809.127 Test Coordinator VYOPF 4030. 04 Rev. 5

8-PRIMARY CONTAIRIENT LEAKAGE RATE DATA SilEET (TYPE A)

Contained Pressure Temp. $ Time Contained Pressure Temp.

Time. *F (Min) Mass (pounds) "Ilg *F $ (Min) Mass (pounds) "Hg 70181 119.37 103.53 1901 DATA POINT DELETED $ 2231 73665 119.30 80.9 1911 73686 119.37 81.0 $ 2241 73674 119.30 80.9 W

~

1921 73674 119.37 81.0 $ 2251 73661 119.30 81.0 E

1931 73667 119.37 81.0 $ 2301 73655 119.28 81.0 1941 73672 119.33 81.0 2311 73644 119.28 80.9 1951 73672 119.33 81 0 $ 2321 73647 119.28 80.9 2

2001 73667 119.33 81.0 $ 2331 73644 119.28 80.9 s

2011 73663 119.33 81.0 $ 2341 73639 119.25 80.9 2021 73660 119.30 81.0 $ 2351 73639 119.25 80.9 2031 73657 119.33 81.0 0001 73638 119.25 80.9 2041 73661 119.33 80.9 $ 0011 73636 119.25 80.9 s

2051 73653 119.30 80.9 $ 0021 73625 119.21 81.0 W

2101 73652 119.30 80.9 $ 0031 73610 119.21 81.0 2111 73650 119.30 80.9 $ 0041 73620 119.21 80.9 2

2121 73659 119.30' 80.9 $ 0051 73599 119.21 81.0 W

2131 73667 119.30 80.9 $ 0101 73607 119.21 80.9 5

2141 73666 119.30 80.8 $ 0111 73605 119.19 80.9

?151 73665 119.30 80.9 $ 0121 73601 119.21 80.9 2

2201 73667 119.30 80.9 $ 0131 73604 119.19 80.9 2211 73669 119.30 80.8 $ 0141 73601 119.19 80.9 2221 73667 119.33 80.9 $ 0151 73595 119.16 80.9 Test Asst. W

' Date Och k '3l 0

/)?C) -

Approved I ('[ '

.j Q ]2h VYOPF 4030 04 Rev. 5

PRIl!ARY CONTAINMENT LEAKAGE RATE DATA SHEET (TYPE A)

Time Contained Pressure Temp. $ Time Contained Pressure Temp.

(Min) Mass (pounds) "Hg *F * (Min) Mass (pounds) "Hg "F 0531 73573 119.04 80.4 0201 73589 119.16 80.8h 0541 73565 119.00 80.4 0211 73594 119.16 80.8h

~

119.16 0551 73555 119.00 80.4 0221 73595 80.8h 119.04 80.4 0231 73592 119.12 9.8 k 0601 73554 119.12 0611 73552 119.00 80.4 0241 73586 80.8h" 73578 119.09 80.7

• 0621 73559 119.00 80.4 0251 0631 73555 118.98 80.3 0301 73579 119.09 80.7h 0311 73577 119.12 80.7h 0641 73557 119.00 80.3 2

0321 73579 119.09 80.7

• 0651 73555 119.00 80.3 0331 73591 119.09 80.6

• 0701 73551 118.98 80.3 0341 73586 119.09 80.6 $ 0711 73543 118.98 80.3 0351 73578 119.09 80.6 $ 0721 73546 118.98 80.3 0401 73578 119.07 80.6$ 0731 73547 118.95 80.2

~

0411 73574 119.07 80.6

• 0741 73540 118.98 80.3 73567 119.04' 80.6$ 0751 73539 118.98 80.3 0421 ~

0431 73565 119.04 80.6$ 0801 73542 118.98 80.2 1

0441 73560 119.07 80.6$ 0811 73538 118.95 80.

0451 73571 119.04 80.6$ 0821 73539 118.95 80.l 73565 119.07 80.6$ 0831 73539 118.92 80.:

0501 1

119.04 80.5$ 0841 73538 118.95 80.:

0511 73572 0521 73571 119.04 80. 5 $ 0851 73340 .118.9'2 80.

Test Asst. 4ks.jc apps '

Date de ro or/2 /. tva 1809 129 Approved [

Test Coordnator VYOPF 4030. 04 Rev. 5

PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET (T'IPE A) 4 Contained lemp. $ Time Cor'.ined Pressure Temp.

Time. Pressure Mass (pounds) "Hg *F (Min) Mass (pounds) "Hg *F (Min) 0901 73539 118.95 80.2 $ 1231 73497 118.83 79.8 3

0911 73542 118.95 80.2 $ 1241 73499 118.79 79.9 s

0921 73548 118.92 80.1 $ 1251 73496 118.83 79.8 0931 73541 118.88 80.2 $ 1301 73505 118.79 79.8 0941 73544 118.95 i 80.1 $ 1311 73510 118.79 79.8 a>

0951 73535 118.88 80.2 $ 1321 73503 118.83 79.8 1001 73533 118.88 80.2 $ 1331 73506 118.83 79.8 x

1011 73533 118.86 80.2 $ 1341 73500 118.79 79.8 1021 73539 118.88 80.1 $ 1351 73502 118.79 79.8 a

1031 73536 118.92 80.2 $ 1411 73502 118.83 79.8 3

1041 73545 J18.88 80.2 $ 1411 73507 118.83 79.8 1051 73534 118.88 80.2 $ 1421 73506 118.79 79.9 e

1101 73528 118.86 80.2 $ 1431 73509 118.79 79.8 e

1111 73510 118.88 80.1 $ 1441 73498,,, 118.79 79.8 2

1121 73522 118.88' 80.1 $ 1451 73491 118.79 79.8 1131 73518 118.86 80.0 $ 1501 73499 118.79 79.8 1141 73516 118.86 79.9 $ 1511 73500 118.79 79.8 3

1151 73519 118.83 79.9 $ 1521 73493 11R_77 79 R 1201 73513 118.86 79.9 $ 1531 73491 11R_77 79.7 2

1211 73504 118.83 79.9 $ 1541 73486 11R_77 79.7 x

1221 73499 118.83 79.8 $ 1551 73474 11R_77 79.7 Test Asst. h .

' nate fo&W u , m9 1809 130 Approved h st Coor & ator VYOPF 4030 04 Rev. 5

- _11_

PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET (TYPE A) i  ;

Time  ! Contained Pressure Temp. $ Time Contained Pressure Temp.

I Mass (pounds) "Hg *F $ (Min) Fbss (pounds) "Hg *F (Min)

• W 1601 73482 118.74 79.7 $

2 1611 73487 118.77 79.7 $

79.6 2 1621 73499 118.77 5

1631 73504 118.77 79.7 $

3 END OF 24 HOUR TEST -

1641 73501 118.74 79.7 $

2 1651 73501 118.74 79.6 $

1701 73501 118.74 79.6 $

E 1711 73514 118.74 79.6

• N START OF SUPPLEMENT TEST 1721 73500 118.74 79.6 $

W 1731 73618 119.16 79.6$

W 1741 73738 119.12 79.6

• 1751 73737 119.09 79.6$

1801 73714 119.09 79.6$

W 1811 73710 119.07 79.6

• 1821 73697 119.07 79.5$

1831 73505 119.07 79.5$

5 END OF SUPPLEMENT TEST $

1843 END OF 1979 LEAKRATE TEST Test Asst. M kW '

' Date Ocha/t,g/2. 3/,/979 1809 131 Approved h Test Coordinator VYOPF 4030. 04 Rev. 5

1979 TYPE B AND C TESTING Summary Description of Testing During the Fall 1979 refueling outage, all Type B and C primary containment leak rate testing was conducted. All valves with leakage rates in excess of that allowed by the Technical Specifications were reported to the Director of the Office of Inspection and Enforcement, Region I, in a thirty-day licensing event report, LER 79-28/3L.

Following disassembly, repair, and retesting, a satisfactory leakage rate was demonstrated. The resulting data from all leak rate testing is presented in the following pages and tables 1979-B and 1979-C.

Detailed Description of Testing

a. Containment Isolation Valves During the Fall 1979 refueling outage, two primary containment isolation valves were found to have seat leakages in excess of that permitted by the Technical Specifications.

On all valves found to have leakage greater than that allowed, a second valve on the same line provided the proper primary containment isolation capability. The two valves and their "as-found" leakage rates are as follows:

Valve Description As-Found Leakage Rate Date of Event V12-68 2.03 lbm/hr 10/17/79 (Reactor Cleanup Return Line Isolation Valve)

V16-20-20 Indeterminable 9/28/79 (Containment Purge Makeup Isolation Valve)

Testing, repair, and retest details for the three velves found to have excessive seat leakage are described below:

1. Reactor Cleanup Return Line Isolation Valve On October 17, 1979, the Reactor Cleanup System isolation valve V-12-68 was leak rate tested and was determined to have greater than that allowed by the Technical Specifications.

Disassembly and inspection of the valve revealed seating surfaces which required smoothing. The valve plug was replaced, the valve seat was lapped, and the valve rebuilt.

Following this repair, the leakage past.the seat was verified to be 0.140 lbm/hr on October 18, 1979. V-12-68 is a William Powell 4" 1500 lb. "Y" Globe Valve.

g } 32-

2. Containment Purge Makeup Valve On September 28, 1979, the Containment Purge Makeup Isolation Valve V16-20-20 was leak rate tested and the test volume could not be pressurized. Disassembly and inspection of the valve revealed that there was dirt under the valve seat.

The valve internals were cleaned and the valve reassembled. Following this maintenance, the leakage past the seat was verified to be .022 lbm/hr on October 1, 1979. V16-20-20 is an Aktomatic 1" 300 lb. gate valve.

b. Drywell Head The Drywell Head was satisfactorily tested on September 22, 1979. Subsequently, the drywell head was removed. Prior to dryeell head installation, normal plant preventative maintenance practice results in both sealing gaskets being replaced to provide increased reliability during the next operating cycle. The drywell head was retested and verified to have a leakage rate of 0.0044 lbm/hr on October 24, 1979.

c. Type B Testing of Gasketed Seals Generally, it is the plant's practice that prior to opening containment penetrations utilizing gasketed seals, a Type B leakage test is performed. In so doing, accurate as-found leakage data is available for the previous operating cycle.

During the outages, containment penetrations are opened for personnel and/or equipment entry, or performance of preven-tative maintenance. Subsequent to a containment penetration closeout, a Type B leakage test is performed. This leakage data is cembined with all measured leakages of the various containment penetrations as a baseline for the upcoming operating cycle. The summary test results for Type B Testing, Table 1979-B, provides both the initial and retest leakage data associated with those contained penetrations opened during the refuel outage,

d. Containment Air Sampling System Return Valves On September 25, 1979, while conducting leak rate testing on primary containment isolation valves in the Containment Radiation Monitor return line, the volume between the blocking valve CAM-77A and the CAM-76B (109-76B) valve could not be pressurized. Presently, the CAM-76B valve is listed in Technical Specifications Table 4.7.2b as a primary containnent isolation valve not subject to Type C leakage tests.

1809 133.

. This is an interim situation in that NRC acceptance of Technical Sprcifications Proposed Change No. 41 will include the subject valve in Table 4.7.2a, and therefore require the performance of Type C leakage testing, with results included in this report. Disassembly of the CAM-76B valve revealed an accumulation of scale of the valve's seating surface. On September 25, 1979, following cleaning of the seating surfaces and reassembly of the valve, the leakage past the seat was verified to be .022 lbm/hr. Quantitative Calculations of Technical Specification Limits

1. The combined leak rate of all penetrations and valves subject to Type B and C tests shall be less than 0.60 La. Sixty (60) percent of La = 355 lbm/ day.

2. The leakage from any one isolation valve shall not exceed 5%

of Ltm. Five (5) percent of Ltm = 12.53 lbm/ day or .522 lbm/hr.

3. The leakage from any one main steam line isolation valve shall not exceed 11.5 SCFH st 24 PSIG (Pt).

GENERAL CONCLUSIONS Based on the successful completion of the Type A, B, and C leak rate test programs, along with the corrective action taken as a result of the test data, it is concluded that the condition of the Primary Containment System is acceptable for continued plant operation. The plant was returned to service with a containment leakage of less than

 .321%/ day. This compares to the allowed leakage of .600%/ day.

180P9~T34 Table 1979-B Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST X-2 Personnel Lock 3.87 1.72 Bellows Seals X-7A Main Steam Line A 0 X-7B Main Steam Line B 0 X-7C Main Steam Line C 0 X-7D Main Steam Line D 0 X-9A Feedwater A 0 X-9B Feedwater B 0 X-ll HPCI Steam Line 0 X-12 RHR Suction 0 X-13A RHR Return A 0 X-13B RHR Return B 0 X-14 Cleanup Suction 0 X-16A Core Spray A 0 X-16B Core Spray B 0 Electrical Penetrations 100A Electrical Penetration 0 100B Electrical Penetration 0 100C Electrical Penetration 0.0004 100D Electrical Penetration 0 101A Electrical Penetration 0.791 101C Electrical Penetration 0 101D Electrical Penetration 0.0004 102 Electrical Penetration 0.0002 103 Electrical Penetration 0 Table 1979-B (cont'd) Sumnary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST 104A Electrical Penetration 0.0003 104B Electrical Penetration 0 104C Electrical Penetration 0 105A Electrical Penetration 0 105B Electrical Penetration 0 105C Eleccrical Penetration 0 105D Electrical Penetration 0 214 Electrical Penetration 0 Double Gasketed Seals X-1 Equipment Hatch 0.001 X-4 Drywell Head Access Hatch 0.00008 X-6 Control Rod Drive Removal 0 0.00002 Hatch X-200A Torus Access Hatch 0.00002 0.00001 X-200B Torus Access Hatch 0 0 VBC-A Vacuum Breaker Access Cover 0.00002 0 VBC-B Vacuum Breaker Access Cover 0 0.00002 VBC-C Vacuum Breaker Access Cover 0.00001 VBC-D Vacuum Breaker Access Cover 0 VBC-E Vacuum Breaker Access Cover 0.00001 VBC-F Vacuum Breaker Access Cover 0.00001 0 VBC-G Vacuum Breaker Access Cover 0.00001 0 VBC-H Vacuum Breaker Access Cover 0.00003 VBC-I Vacuum Breaker Access Cover 0.00004 VBC-J Vacuum Breaker Access Cover 0.00001 . 1809 136 Table 1979-B (cont'd) Summary Test Results for Type B Testing PENETRATION LEAKAGE (LBM/HR) NUMBER DESCP.IPTION INITIAL RETEST SLH-A Shear Lug Access Cover 0.00025 SLH-B Shear Lug Access Cover 0 SLH-C Shear Lug Access Cover 0.00009 SLH-D Shear Lug Access Cover 0.00002 SLH-E Shear Lug Access Cover 0.00006 SLH-F Shear Lug Access Cover 0.00003 SLH-G Shear Lug Access Cover 0.00001 SLH-H Shear Lug Access Cover 0.00002 Drywell Head Flange 0.01021 .0044 X-213-A Torus Drain 0 0 X-213-B Tour Drain 0 0 Total B Penetration as found Leakage 4.67423 Total B Penetration Leakage After 2.51841 Repairs 1809 137

Summary Test Results for Type C Testing Table 1979-C LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS-77 Main Steam Drain .122 RV39 & 40 Recirc. Sample 0.022 RHR-57 RHR Disch. to Radwaste 0.024 LRW-83 Drywell Floor Drain <0.015 LRW-95 Drywell Equipment Drain <0.015 SB-16-19-8,9,10 & 23 Containment Purge .233 SB-16-19-11A & 12A Vacuum Relief 0.022 SB-16-19-llB & 12B Vacuum Reilef 0.067 SB-16-19-6,7,6A,6B,7A&7B Containment Exhaust 1.29 RCU-18 Reactor Cleanup 0.024 V16-20-20 Containment Purge Could not Makeup pressurize .022 V16-20-22A Containment Purge Makeup 0.068 V16-20-22B Containment Purge Makeup .022 RCU-68 Reactor Cleanup 2.03 0.140 HPCI-16 HPCI Steam Supply .053 RCIC-16 RCIC Steam Supply 0.37 CA-96A Cont. Air Compressor 0.022 Suction CA-96B Cont. Air Compressor 0.041 Suction CA-89B Containment Air Check 0.316 Valve CA-89C Containment Air Check 0.057 Valve , NG 13A & 13B CAD Injection 0.05 } 8(l9' } 3h' NG 12A & 12B CAD Injection 0.123 NG 11A & 11B CAD Injection 0.022 VG-9A CAD Vent 0.022 VG-22A CAD Vent 0.121 VG-9B CAD Vent 0.177

. Table 1979-C (cont'd) Summary Test Results for Type C Testing LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST VG-22B CAD Vent 0.151 VG-23 CAD Rad. Mon. Supply 0.021 VG-26 CAD Rad. Mon. Supply 0.07 VG-76A Rad. Mon. Return 0.150 VG-76B Rad. Mon. Feturn Could not .022 pressurize CRD-181 CRD Return Check Valve 0 MS-74 Main Steam Drain 0.018 HPCI-15 HPCI Steam Supply <0.053 RCIC-15 RCIC Steam Supply 0.086 RCU-15 Reactor Cleanup 0 LRW-82 Drywell Floor Drain 0.0032 LRW-94 Drywell Equipment Drain 0.0021 RHR-66 RHR Discharge to Radwaste 0 Total Type C Leakage Following Repairs 4.0363 LEAKAGE (SCFH) VALVE (TESTED) DESCRIPTION INITIAL RETEST MS80A A Main Steam Line 0 MS86A A Main Steam Line 4.78 MS80B B Main Steam Line 1.35 MS86B B Main Steam Line 3.879 MS80C C Main Steam Line 0 MS86C C Main Steam Line 6.72 MS80D D Main Steam Line 0 MS86D D Main Steam Line 2.12 1809 139

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