Text

Local Leak Rate Test Rept.
	ML19339B131
Person / Time
Site:	Crystal River
Issue date:	09/26/1980
From:	Jonathan Brown, Tittle L; FLORIDA POWER CORP.
To:	;
Shared Package
ML19339B132	List: ML19339B131;
References
	NUDOCS 8011060334
	Download: ML19339B131 (56)
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4 FLOFIDA POWER CORPORATION CRYSTAL RIVER UNIT #3 NUCLEAR GENERATING PLANT LOCAL LEAK RATE TEST REPORT Prepared by: u Date: Y 2(o,Iq Ao J.Q. Brown-ResultsEngineer Reviewed by: N b. Date: M JC /f80 L.B.petle-NuclearPerformance U.

Engineering Supervisor 170Ild(o033H

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LOCAL LEAK RATE TEST REPORT TABLE OF CONTENTS I INTRODUCTION II GENERAL DATA III DISCUSSION IV LOCAL LEAK RATE TEST RESULTS V ANALYSIS / ACCEPTANCE CRITERIA VI

SUMMARY

APPENDIX A LOCA'.T"sK RATE TEST SUMfARY INDEX OF VALVES APPENDIX B LOCAL LEAK RATE TYPE C TEST RESULTS APPENDIX C CALCULATIONS OF LOCAL LEAK RATE FROM PRESSURE DECAY TESTS APPENDIX D LOCAL LEAK RATE TESTS PERFORMED BET'JEEN REFUELING OUTAGES l

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- LOCAL LEAK RATE TEST REPORT Page 1 I. Introduction Type B and C tests were conducted in accordance with

+.5 FPC Surveillance Procedure SP-179 at Pa, 49.6 - O psig in conformance with the criteria specified in Appen-dix J of 10CFR50 using the methods and provisions of ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors."

Florida Power Corporation was responsible for conduc-ting the tests. Catalytic, Inc. the contractor, pre-pared the surveillance test procedure and provided technical support during the performance of the tests.

LOCAL LEAK RATE TEST REPORT Page 2 II. General Data Owner: Flori..a Power Corporation Docket No: 50-302 Location: Crystal River Nuclear Power Plant Containment

Description:

Reinforced Concrete Cylinder with Steel Liner.

6 Containment Net Free Volume: 2 x 10 cu. ft.

Design Pressure: 49.6 psig i

Maximum Allowable Leak Rate: .6LA (248,656 sec/ min.)

Recorded Total Leakage: .098 LA (40,596 sec/ min.)

Test Start Date: February 15, 1980 Test Completion Date: July 23, 1980

LOCAL LEAK RATE TEST REPORT Page 3 III. Discussion The methods u;ed to determine the leakage rates of containment isolation valves are as follows:

1. Out-Leakage

2. In-Leakage

3. Pressure Decay The "Out-Leakage" method of testing consisted of ap-plying test pressure to the upstream side of an isolation valve and measuring leakage with a rotometer or Leak Rate Monitor installed on the downstream side of the isolation valve.

The "In-Leakage" method of leak testing consisted of 4 pressurizing a portion of system piping, bounded on at least one side by the isolation valves (and/or blind flanges) to be tested, and measuring the flow of compressed gas required to maintain the test pressure in the test volume using a rotometer or Leak Rate Monitor installed integrally with the pressurization rig.

The " Pressure Decay" method of leak rate testing con-

+.5 sisted of pressurizing the test volume to 49.6 - O psig and measuring the pressure decay rate with a 1% accuracy pres-sure gauge.

The test method consisted of pressurizing the test section slowly, through a " fast charge" line to approximately 45 psig, as indicated on the test rig pressure gauge. After the test section was charged to 45 psig the fast charge line was disconnected and the " Leak Rate Monitor" was cut in ser-vice. Pressure was increased with the Leak Rate Monitor to i

LOCAL LEAK RATE TEST REPORT Page 4 III. Discussion - Continued

+.5 49.6 - O psig. After a stabilization period of approx-imately 15 - 20 min., the leakage rate was directly read from the " Leak Rate Monitor." (See Figure 1)

During pressure a decay measurements leakage rates were estimated using the " decay mode" of the leak rate test monitor or pressure gauge. All instrumentation used during the test was calibrated prior to commence-ment of the test in addition to certified calibration from the instrument supplier.

Appendix A was developed to show which penetration are subject to Type B & C testing.

Appendix B shows valves / components tesced between i scheduled Local Leak Rate tests due to maintenance and increased sureveillance.

s LOCAL LEAK RATE TEST REPORT Page 5

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LOCAL LEAK RATE TEST REPORT Page 6 IV. Local Leak Rate Test Results

1. Type B Acceptance Description As-Found Re-Test As-Left Criteria Equipment IIntch Resilient Seals 2 cc/ min N/A ? cc/ min < 500 cc/ min Fuel Transfer Tube Gasket-3B 2 cc/ min N/A 2 cc/ min < 100 cc/ min Fuel Transfer Tube Gasket-3A 2 cc/ min N/A 2 cc/ min < 100 cc/ min LRV-45 and Blind i Flange 560 cc/ min N/A 560 cc/ min < 2740 cc/ min LRV-44 and Blind Flange 175. cc/ min 90 90 cc/ min < 100 cc/ min Chemical Cleaning Penetration Gaskets 119 95 cc/ min N/A 95 cc/ min < 100 cc/ min Chemical Cleaning Penetration Gaskets 120 2 cc/ min N/A 2 cc/ min < 100 cc/ min Total as found Type B Leakage 838 cc/ min.

Total measured Type B Leakage 753 cc/ min.

Total error adjusted Type B Leakage 790.6 cc/ min. '

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i 1

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s LOCAL LEAK RATE TEST REPORT Page 7 t

IV. Local Lesk Rate Test Results

2. Type C Acceptance Description As-Found Re-Test As-Lefr Criteria Decay Heat Sys.

DHV-93 150 cc/ min N/A 150 cc/ min < 2740 cc/ min DHV-91 170 cc/ min N/A 170 cc/ min < 2740 cc/ min Liquid Sacioling Sys.

CAV-126 320 cc/ min N/A 320 cc/ min < 1370 cc/ min CAV-1 240 cc/ min N/A 240 cc/ min < 1370 cc/ min CAV-3 210 cc/ min N/A 210 cc/ min < 1370 cc/ min CAV-2 290 cc/ min N/A 290 cc/ min < 1370 cc/ min Industrial Cooling Water

! CIV-41 10370 cc/ min 210 210 cc/ min < 3425 cc/ min j CIV-40 11930 cc/ min 100 cc/ min 100 cc/ min < 3425 cc/ min CIV-34 485 cc/ min N/A 458 cc/ min < 3425 cc/ min f

CIV-35 667 cc/ min N/A 667 cc/ min < 3425 cc/ min femineralized Water DW-162 193 cc/ min 36.7 cc/ min 193 cc/ min < 4110 cc/ min DW-160 20,000 cc/ min 560 cc/ min 560 cc/ min < 4110 cc/ min Makeup & Purifi-cation System MUV-40 75 cc/ min N/A 75 cc/ min < 3425 cc/ min MUV-41 146 cc/ min N/A 146 cc/ min < 3425 cc/ min MUV-49 750 cc/ min N/A 750 cc/ min < 3425 cc/ min MUV-260 690 cc/ min N/A 690 cc/ min < 1370 cc/ min MUV-261 570 cc/ min N/A 570 cc/ min < 1370 cc/ min MUV-259 580 cc/ min N/A 580 cc/ min < 1370 cc/ min MUV-258 530 cc/ min N/A. 530 cc/ min < 1370 cc/ min MUV-253 840 cc/ min N/A 840 cc/ min < 1370 cc/ min l

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- 1 LOCAL LEAK RATE TEST REPORT Page 8 l

IV. Local Leak Rate Test Results

2. Type C - Continued Acceptance Description As-Found Re-Test As-Left Criteria Core Flood System CFV-20 143 cc/ min N/A 143 cc/ min < 1370 cc/ min CFV-19 223 cc/ min N/A 223 cc/ min < 1370 cc/ min CFV-25 70 cc/ min N/A 70 cc/ min < 1370 cc/ min CFV-28 240 cc/ min N/A 240 cc/ min < 1370 cc/ min CFV-17 1420 cc/ min N/A 1390 cc/ min < 1370 cc/ min CFV-18 1400 cc/ min N/A 1330 cc/ min < 1370 cc/ min CFV-26 327 cc/ min N/A 327 cc/ min < 180 cc/ min CFV-27 40 cc/ min N/A 40 cc/ min < 1370 cc/ min

, CFV-15 140 cc/ min N/A 140 cc/ min < 1370 cc/ min CFV-16 >20,000 cc/ min N/A 40 cc/ min < 1370 cc/ min CFV-29 150 cc/ min N/A 150 cc/ min < 2055 cc/ min CFV-11 50 cc/ min N/A SC cc/ min < 1370 cc/ min CFV-12 65 cc/ min N/A 65 cc/ min < 1370 cc/ min CFV-42 70 cc/ min N/A 70 cc/ min < 1370 cc/ min Nitrogen System NGV-62 1100 cc/ min N/A 1100 cc/ min < 2055 cc/ min NCV-82 784 cc/ min N/A 784 cc/ min < 1370 cc/ min Station & Instru-ment Air System SAV-24 69 cc/ min N/A 69 cc/ min < 4110 cc/ min IAV-28 1320 cc/ min N/A 1320 cc/ min < 2740 cc/ min IAV-29 168 cc/ min N/A 168 cc/ min < 2740 cc/ min CFV-16 did not close from the Control Room for the As-Found test. The value used for As-Found is 20,000 cc/ min.

- LOCAL LEAK RATE TEST REPORT Page 9 IV. Local Leak Rate Test Results

2. Type C - Continued Acceptance Description As-Found Re-Test As-Left Criteria Spent Fuel Cool-ing System SFV-18 98,320 cc/ min 7680 cc/ min 7680 cc/ min < 13,700 cc/ min SFV-19 98,320 cc/ min >20,000 4640 cc/ min < 13,700 cc/ min ec/ min Waste Disposal System WDV-3 & WDV-4 1470 cc/ min N/A 1470 cc/ min < 5480 cc/ min WDV-60 & UDV-61 330 cc/ min N/A 330 cc/ min < 2740 cc/ min WDV-406 410 cc/ min N/A 410 cc/ min < 2055 cc/ min WDV-405 450 cc/ min N/A 450 cc/ min < 2055 cc/ min WDV-94 70 cc/ min N/A 70 cc/ min < 4110 cc/ min WDV-62 110 cc/ min N/A 410 cc/ min < 2740 cc/ min Containment Moni-toring System WSV-3 114.8 cc/ min N/A 114.8 cc/ min < 1370 cc/ min WSV-4 122.4 cc/ min N/A 122.4 cc/ min < 1370 cc/ min WSV-5 145 cc/ min N/A 145 cc/ min < 1370 cc/ min WSV-6 14 cc/ min N/A 14 cc/ min < 1370 cc/ min WSV-1 180 cc/ min N/A 180 cc/ min < 1370 cc/ min WSV-2 110 cc/ min N/A 110 cc/ min < 1370 cc/ min

LOCAL LEAK RATE TEST REPORT Page 10 IV. Local Leak Rate Test Results

2. Type C - Continued Acceptance Description As Found Re-Test As-Left _ Criteria R. B. Purge System 0

AHV-lc and 8.16 x 10 N/A 310 cc/ min < 2500 cc/ min AHV-lD cc/ min (2 cc/ min)

AHV-1A and 270 cc/ min 270 cc/ min < 2500 cc/ min ARV-1B Containment Leak '

Rate System LRV-50 2 cc/ min N/A 2 cc/ min < 10,960 cc/ min LRV-36 915 cc/ min N/A 915 cc/ min < 10,960 cc/ min LRV-51 85 cc/ min N/A 852 cc/ min < 10,960 cc/ min LRV-35 and LRV-47 3370 cc/ min N/A 3370 cc/ min < 10,960 cc/ min LRV-49 370 cc/ min N/A 370 cc/ min < 10,960 cc/ min LRV-38 and LRV-52 2 cc/ min N/A 2 cc/ min < 10,960 cc/ min 6

AHV-1C leaked 8.16 x 10 cc/ min, but soap test for ILRT and before repairs indicated NO LEAKAGE. (2 cc/ min is used for As-Found above.)

LOCAL LEAK RATE TEST REPORT Page 11 Total number of Valves tested - 6j[

Total number of Valves re-tested - lj!,

2 Total rumber of Valves repaired - ljL 5

Total as found leakage

1.88 x 10 j,1, (Type B & C) (* ^

Total as left leakage (Type C) - 3.98 x 10' cc/ min

(.096 LA) a Combined Type B and C leakage - 40.S96.4 cc/ min

(.098 LA)

Note: Error adjusted leakages are based on a maximum instrument calib ation accuracy of 5% applied in the conservative direction for the total as found and left valves. (Ex-cept where pressure decay valves were calculated.)

Note: A minimum sensitivity of 2.0 cc/ min has been used for each test.

x LOCAL LEAK RATE TEST REPORT Page 12 I

i V. Analysis and Interpretation 1

La = 0.25% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the mass of conteinment.

air at 64/3 psa.

PV Mass of Containment Air = yy, where:

-P = Containment Pressure = 64/3 psia V = Containment Free Volume = 2 x 10 cu ft ,

lbf

= Gas Constant = 53.35 lba *R T =-Containment Temperature, assumed 549.69*R (90*F)

I

) Mass of Containment Air = (

#8'" (

6 3

( " ' '}

I 53.35 L3g _ *R .6 R)

\s Mass of Containment Air = 631,467.8 lbm t, , (0.0025/ day) (631,467.8 lbm) 24 hrs / day

= 65.78 lbm/hr sec (65.78 lbm/hr) 471.9 CH

" " 8' "'"

$ 0.0749 lbm/cu ft '

]

j j 0.6 La = 248,656 sec/ min

}

l Excluding the type "B" penetrations and the 48" reactor

! building purge valves, the total number of " nominal inches of

, valve diameter" for all other valves to be leak tested is:

Total D = 169.5 Nominal Inches 1

and 1

D"

= sec/ min / nominal inch.

) Tota 6 5 omina nches k

i n - m. - - , . - - a -,,w- - - . , , v. , , - . - ,. r --,m. e,- , , , -. . , , , , , - - - - .

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i . LOCAL LEAK RATE TEST REPORT Page 13 1

'V. Analysis and Interpretation - Continued I

The action value was based on 95% of the 1450 scc / min / nominal inch.

(0.95 x 1450 = 1370 scc / min / nominal inch)

The' alert value was based on 70% of the 1450 sec/ min / nominal inch.

(0.70 x 1450 = 1000 sec/ min / nominal inch)

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Value Size Alert Value Action Value

-1" 1000 1370 1-1/2" 1500 2055 2" 2000 2740 2-1/2" 2500 3425

-3" 3000 4110 -

4" 4000 5480 6". 6000 8220 8" 8000- 10,960 f 10" 10,000 13,700 (All leakage rates expressed in sec/ min)-

I The remaining 5% was used to develop the Type "B" and reactor building purge value acceptance criteria.

i The distribution was based on plant experience and input ,

, -to LA. Type "B" penetratians and the 48" reactor building l purge valves action and alert values are as follows:

Alert Value Action Value '

i Equipment Hatch.

Resilient Seals- Zero Leakage 500 sec/ min i Fuel Transfer l Tube Gaskets Zero Leakage 100 sec/ min ILRT Gaskets Zero Leakage 100 sec/ min

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. _ _ - ~ - _ _ . _ , . . .. .____ . . _ . . . -

LOCAL LEAK RATE TEST REPORT Page 14 V. Analysis and Interpretation - Continued Alert Value Action Value Steam Generator Chem-ical cleaning Gaskets Zero Leakage 100 cc/ min Reactor Building Purge Valve 500 sec/ min 2500 sec/ min DERIVATION OF PRESSURE DECAY EQUATION The mass contained air at the beginning and end of the test is:

W =P y V/RT 7 and W =P V/RT 1 2 2 2 where the test volume V is constant.

The mass loss is then given by:

1 2 Mass loss = W y -W,=-----

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V_

Ty T R 2

The mass loss can be converted to a volume loss rate at standard conditions since:

P V WRT s s s W= or V =

s p R T s s and thus the leakage rate is standard volume units becomes

l. .

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LOCAL LEAK RATE TEST REPORT Page 15 I

V. Analysis and Interpretation - Continued i

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s s W RT W RT RT 1 s s L = =

fs , .

p (y ,g) t s s s i VT P P k*Ps T 1

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2 1

, Pressure Decay 1

The test volume was pressurized with air to at least PA (49.6 psig). The pressure change within the test vol-ume was recorded as a function of time. The leakage rate was calculated from the pressure decay rate and the free air volume of the test volume. Temperature changes were considered.

Lg = Leakage rate, standard cubic centimeter per min, sec/ min.

1 V = total test free air volume, cubic feet i

t = test duration, hours T y,T 2

= test volume absolute temperature at start and 1 end of test, respectively, absolute Units P ,P = test volume absolute pressure at start and y 2 end of test respectively, absolute units I

T, = standard temperature standard pressure P =

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LOCAL LEAK RATE TEST REPORT Page 16 V. Analysis and Interpretation - Continued Pressure Decay - Continued The formula for computing leal: age reate is:

1 - P2 T s 471.9 sec/ min T T t P SCFH /

1 2 s ,e

(

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. LOCAL LEAK RATE TEST REPORT Page 17 VI. Summary Local leak rate test were performed on the contain-ment isolation valves and penetrations listed in technical specification table 3.6-1.

A total of 67 valves were tested with ten (10) valves requiring repair or replacement. The following valves had a higher than acceptable as-found leakage and were repaired and retested:

CIV-40 CFV-18 CIV-41 WDV-4 DWV-160 AHV-lC CFV-16 SFV-18 CFV-17 SFV-19 These 11 valves represent a threefold increase (4 last year) in the number of valves determined unaccept-able from the as-found leak rate test. Of these, two valves (CIV-40 and DWV-160) were also found unacceptable during last year's testing. If these valves continue to demonstrate an excessive failure rate, a design review or change in the testing periodicity may be warranted.

Valve CFV-17 was found to have leakage in the action range. Replacement of the valve and subsequent retest produced results slightly in excess of the action range limit, however, these results were determined acceptable based on: (1) the inability to conclusively determine if leakage was from CFV-17 or from one of the other test boundary valves, and (2) the low overall leakage rate.

Three tests (CFV-16, SFV-18 and 19, and DWV-160) produced leakage rates which required the values to be determined analytically using.the pressure decay method.

Values were determined for DWV-160 and SFV-18 and 19, 8

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LOCAL LEAK RATE TEST REPORT Page 18

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VI. Summarv - Continued however, leakage through CFV-16, which was not closed during the first test, was too gross to develop suffi-l cient test pressure. All four valves were repaired or replaced and successfully retested.

I From visiual inspections, thirty valves were found to have been previously tested in the direction opposite 1

of post accident flow. Procedural changes were incorpor-ated for 8 valves allowing them to be tested in the direc-tion of post accident flow. However in each case this change resulted in higher radiation exposures for test i personnel. One valve, WDV-406, could not be successfully 2

tested using the revised procedure due to excessive leak-age past the untested boundary valves. For this valve 4

the test was conducted using the initial procedure re-l sulting in an acceptable leakage rate. The procedure for testing the remaining 23 valves in the reverse di-

]

j rection was determined acceptable, because the require-ments of ASME Section XI article IWV-3423 were met.

} The final recorded leakage rate for both Category B and C valves reflects a five percent increase over the measured value to account for inaccuracy in the test

measurement equipment. This change to the recorded leak-age rate is required by FPC.

Finally, comparing-previous results with those com-

! piled this year, the as-left.value indicates a 44 percent

increase over last year's cummulative leakage rate. Al-1 l though a significant increase, this total represents only i

16% of that allowed by section III.C.3 of Appendix J to 10CFR 50. No comparison could be made from the as-found leakage rates due to the inability to determine a leak-

, age-rate through CFV-16.

Table I provides a side by side comparison of 1979 4

and 1980 test results.

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LOCAL LEAK RATE TEST REPORT 4

APPENDIX A LOCAL LEAK RATE TEST

SUMMARY

INDEX i

)

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- LOCAL LEAK RATE TEST REPORT APPENDIX A: Type "B" Test Results Acceptance Description As-Found Re-Test As-Left Criteria Equipment Hatch Resilient Seals 2 N/A 2 500 SCCM Fuel Transfer Tube Gasket - 3B 2 N/A 2 100 SCCM Fuel Transfer Tube Gasket - 3A 2 N/A 2 100 SCCM LRV-45 & LRV-46 560 N/A 560 2740 SCCM LRV-44 and Blind Flange 175 N/A 175 2740 SCCM Chemical Cleaning Penertration Gaskets 119 95 N/A 95 100 SCCM Chemical Cleaning Penetration Gaskets 120 2 N/A 2 100 SCCM Total Measured Type B Leakage 832 SCCM

Total Type B Leakage 874 SCCM

Represents 105% of measured leakage due to 5% inaccuracy of measurement equipment.

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LOCAL LEAK RATE TEST REPORT Page A-1 i

NOTES

1. Valves are required to be open during post-accident conditions.

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2. Locked open.

3. Not a containment boundary; does not " provide a direct connection".

}

4. Connected to the secondary side of steam generator, i

l S. Low Pressure Injection System.

6. 10CFR50 Appendix J, II H-4, Main Steam and Feedwater exclusion for PWR's.

i.

7. High Pressure Injection System.

I i.

8. 10CFR50 Appendix J, III C-3, Seal Water System pressure greater

! than 1.10 Pa.

9. GeneralDesignCriteria'#5h.

4 1 10. Tested in reverse direction, ASME Section XI, IWV-3420(c) j " Exceptions".

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. 11. Not testable in direction of post-accident flow.

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12. These valves isolate to main steam piping only.

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! .13. Cannot be tested with fuel in core.

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Symbol designates valves exempted from type "C" test per Tech Spec (Table 3.6-1), and is followed by the applicable-notes as the official reason for exemption.

i 2

Valve categoried per ASME,Section XI Article IWV-2100.

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k LOCAL LEAK RATE TEST REPORT 1

I 1

1 i

a a

]

1 1

APPENDLX B Type "C" Test Results

]

I 9

4 it i

i 1

d f

I I

l l

l

~

renar. enose

^ CATALYTIC. INC. Sheet 31 of s

Centre Square West.1500 Market Street. Philadelphia, Pennsylvania 19102

'.. Rev.

( g- i f

,e Date:

LOCAL LEAK RATE TEST REPORT APPENDIX B: Type "C" Test Results Acceptance Description As Fsund Re-Test As-Left Criteria Decav Heat Svs.

150 N/A 150 2740 SCCM DHV-93 170 N/A 170 2740 SCCM DHV-91 Licuid Samoling Svs.

CAV-126 320 N/A 320 1370 SCCM 240 N/A 240 1370 SCCM CAV-1 CAV-3 210 N/A 210 1370 SCCM CAV-2 290 N/A 290 1370 SCCM Industrial Cooling Water CIV-41 10,370 210 210 3425 SCCM CIV-40 11,930 90 90 3425 SCCM CIV-34 485 N/A 458 3425 SCCM 667 N/A 667 3425 SCCM CIV-35 Demineralized Water 193 N/A 193 4110 SCCM DW-162 36,500* 560 560 4110 SCCM DW-160 Make & Purifi-cation Svstem 75 N/A 75 3425 SCCM MUV-40 146 N/A 146 3425 SCCM NUV-41 750 N/A 750 3425 SCCM MUV-49 690 N/A 690 1370 SCCM NUV-260 570 N/A 570 1370 SCCM NUV-261

Calculated - see Appendix C.

s..:, .....

I M. CATALYTIC, INC. Sheet 32 of Centre Square West.1500 Market Street, Philadelphia, Pennsylvania 19102

/g Rew.

.W

" Date LOCAL LEAK RATE TEST REPORT Type "C" (Continued)

Acceptance Description As Found . Re-Test As-Left Criteria Make & Purifi-cation Svstem 580 N/A 580 1370 SCCM MUV-259 530 N/A 530 1370 SCCM MUV-258 840 N/A 840 1370 SCCM MUV-253 Core Flood System 143 N/A 143 1370 SCCM f CFV-20 223 N/A 223 1370 SCCM t CTV-19 70 N/A 70 1370 SCCM CTV-25 24J N/A 240 1370 SCCM CFV-28 1420 1390 1390 1370 SCCM CTV-17 1400 1330 1330 1370 SCCM CTV-18 327 N/A 327 1370 SCCM CTV-26 40 N/A 40 1370 SCCM CTV-27 140 N/A 140 1370 SCCM CTV-15

40 40 1370 SCCM CFV-16 15 0 N/A 150 2055 SCCM CW-29 50 N/A 50 1370 SCCM CW-11 65 N/A 65 1370 SCCM CFV-12 70 N/A 70 1370 SCCM CW-42 Nitrogen System 1100 N/A 1100 2055 SCCM NGV-62 784 N/A 784 1370 SCCM NGV-82

Could not develop sufficient pressure to ecst.

.a,..

,.a.,

I CATALYTIC, INC. Sheet 33 of a Centre Square West,1500 Market Street, Phdadelphia, Pennsva vania 19102 Y ;

'M LOCAL LEAK RATE TEST REPORT Date l

Type "C" (Continued) 1.cceptance Description Ar. Found Re-Test As-Left Crite ria t Station & Instru-ment Air Svstem SAV-24, 23, 122 69 N/A 69 4110 SCCM IAV-28 1320 N/A 1320 2740 SCCM IAV-29 168 N/A 168 2740 SCCM Spent Fuel Cool-ing Svstem SFv-18 and 58,000* 7680 7680 13700 SCCM 4640 4640 13700 SCCM STV-19 Waste Disposal Svstem WDV-3 870 N/A 870 5480 SCCM WDV-4 640 N/A 640 5480 SCCM k"JV-60 & WDV-61 330 N/A 330 2740 SCCM k3V-406 410 N/A 410 2055 SCCM WDV-405 450 N/A 450 2055 SCCM WDV-94 70 N/A 70 4110 SCCM WDV-62 410 N/A 410 2740 SCCM Containment Moni-toring System WSV-3 115 N/A 115 1370 SCCM WSV-4 122 N/A 122 1370 SCCM WSV-5 145 N/A 145 1370 SCCM WSV-6 140 N/A 140 1370 SCCM WSV-1 180 N/A 180 1370 SCCM WSV-2 110 N/A 110 1370 SCCM

Calculated - see Appendix C.

?

LOCAL LEAK RATE TEST REPORT Page B4 Type "C" - Continued Acceptance Description As-Found Re-Test As-Left Criteria R.B. Purge System AHV-lC and 6

AHV-lD 8.16 x 10 310 310 2500 SCCM AHV-1A and AHV-1B 270 N/A 270 2500 SCCM Containment Leak Rate System LRV-50 2 N/A 2 10,960 SCCM LRV-36 915 N/A 915 10,960 SCCM LRV-51 852 N/A 852 10,960 SCCM LRV-35 $ LRV-47 3370 N/A 3370 10,960 SCCM LRV-49 370 N/A 370 10,960 SCCM LRV-38 & LRV-52 2 N/A 2 10,960 SCCM Total Measured Type C Leakage 37861 SCCM

Total Typ- C Leakage 39754 SCCM

Represents 105% of measured leakage due to 5% inaccuracy of measurement equipment.

LOCAL LEAK RATE TEST REPORT APPENDIX C Calculation of Local Leak Rate from Pressure Decay Test

a.te s . nose

CATALYTIC, INC. Sheet c1 og

,g Centre Square West,1500 Market Street. Philadelphia, Pennsylvama 19102

, f.;

Res.

[

4/ Date I4 CAL LEAK RATE TEST REPORT APPENDIX C: Calculation of Local Leak Rate from Pressure Decay Test Pressure Decay The test volume was pressurized with air to at least PA (49.6). The pres-sure change within the test volume was recorded as a function of time. The leakage rate was calculated from the pressure decay rate and the free air volume of the test volume. Temperature changes were considered.

k = leakage rate, standard cubic feet per hour (SCI 5)

V = total test free air volume, cubic feet t = test duration, hours T ,T = test v lume absolute temperature at start and end of test, 7 2 respectively, Absolute Units l' 2 = test volume absolute pressure at start and end of test respectively, absolute units.

T, = standard temperature P,

= standard pressure The formula for computing leakage rate is:

P VT s

(=PT 1 -

T 2

t P, 3

l l

1 l

l 1

l

a ear .nos

<O CATALYT:C, INC. Sheet C2 of

- Centre Square West.1500 Market Street. Pheladelphia. Pennsylvania 19102

,n LOCAL LEAK RATE TEST REPORT Date:

APPENDIX C: (Continued)

Calculation of Leakage for DW-160 To deter:nine the test volume the following conservative assumptions were made:

1. For 3" IPS pipe a 3.5" ID was assumed.

2. Length of 1000 feet of pipe was estimated for inside the reactor building. This estimate was based on FPC drawing P-304-776.

Test volume:

V = nR 2 L R= 3.5 = .146 feet 2(12)

V = TIR 2 L = 3.14 (.146)2 (1000) = 66.9 f t.3 67 ft.3 Leakage rate:

( "= P ,

P 2 W T T 1 2 cP, P = 50 PSIG, P = 48.5 PSIG, P, = 14.7 PSIA 2

T y =T 2

= 92 F = 551.7 R T, = 60 F = 519.7 R t = 5 min = 1/12 hr.

3 50 - 48.5 67 (519.7) ft /hr

( = 551.7 551.7 1/12 (14.7) 1.5 67 (519.7) f t /hr

( = 551.7 1/12 (14.7) 3 g = 77.3 ft /hr hakage rata = (77.3 f t /hr) (471.9 scem/SCFH) ,

= 36,469 SCCM 36,500 SCCM

/

s...: . nase 9

s CATALYTIC. INC. Shbet C3 of

Centre Seuare West.1500 Market Street. Pheladelphia. Pennsylvania 19102 I .' Rev.

( f ,r'.'

LOCAL LEAK RATE TEST REPORT g,,,

APPENDIX C: (Continued)

Calculation of Leakage for SFV-18,19 To determine the test volume the following conservative assumptions were made:

1. For 10" IPS pipe a 10.75" ID was assumed.

2. Length of 13.5 feet of pipe was estimated for inside the reactor building. This estimate was based on FPC drawings P-304-621 and P-304-622.

Test Volume: ,

V = ttR*L R = 10.75 = .448 ft.

2(12)

V = ltR L = 3.14 (.448) (13.5) = 7.8 ft.3 Leakage Rate:

LL.Pi _

P 2 VT, T *# s 1 2 P =

51.5 PSIG, P2 = 47.5 PSIG, P, = 14.7 PSIA Ty = T = 86 F = 545.7 R 2

T,= 60 F = 519.7 R t = 1 min. = 1/60 hr.

51.5 - 47.5 7.8 (519.7) ft.3/hr.

( = 545.7 545.7 1/60 (14.7)

= 121.3 ft.3/hr.

Leakage race = (131.3 ft. /hr) (471.9 seem/SCFH)

= 57,241 seem 58,000 seem

9 LOCAL LEAK RATE TEST REPORT Page C4 Appendix "C" - Continued Calculation of Leakage for AHV-1C using the Pressure Decay Data.

Leakage Rate:

P P VT 1 2 s P = 14.7 psia t ,

t ___ _. ___

Ty T 2

tP Py = 50 psig s

P = 45 psig 2

Ts = 60*F = 519.7*R t= 5 see Ty =T 2

= 92* = 551.7*R

~

50-45 3 i l l

75ft 519.7*R 60 sec ; 28317 sec.

L 551.7 5 see 14.7 psia min 3' ft

, _ L. _. _. _

= 8.16 x 10 SCCM A

9 LOCAL LEAK RATE TEST REPORT APPENDLX D LLRT'S PERFORMED BETWEEN REFUELING OUTAGES

r e

LOCAL LEAK RATE TEST REPORT ,

Page D-1 LLRT'S PERFORMED BETWEEN REFUELING OUTAGES Acceptance Description As-Feund Re-Test As-Left ,c riteria CAV-1 35 N/A 35 9/4/79 CAV-2 290 N/A 290 7/8/80 252 N/A 250 12/12/79 CAV-3. 25 N/A 25 9/4/79 CAV-126 1900 N/A 1900 9/4/79 Fuel Transfer Tube 3A 0 N/A 0 9/2/78 Fuel Transfer Tube 3B 0 N/A 0 9/2/80 Equipment Hatch 57.1 N/A 57.1 9/7/78 Personnel Access Hatch 326 N/A 326 6/28/80 21 N/A 21 1/7/80 Equipment Hatch Airlocks 483 N/A 483 6/26/80 252 N/A 252 1/4/80 AHV-1A & IB 15.7 N/A 15.7 1/5/80 AHV-1C & 1D 2 x 10 0 25 25 1/5/80 and 1/11/80

, . _ .

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