Text

Local Leak Rate Test Rept.
	ML20049H797
Person / Time
Site:	Crystal River
Issue date:	02/19/1982
From:	Fay T, Primo S; FLORIDA POWER CORP.
To:	;
Shared Package
ML20049H796	List: ML20049H795; ML20049H797;
References
	NUDOCS 8203040008
	Download: ML20049H797 (43)
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT #3 NUCLEAR GENERATING PLANT e

I. 4i LOCAL LEAK RATE

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([ I INTRODUCTION

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II GENERAL DATA

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III DISCUSSION s.

w l IV LOCAL LEAK RATE TEST RESULTS it i V ANALYSIS / ACCEPTANCE CRITERIA 45' ' - .

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VI -

SUMMARY

i e 3 APPENDIX A LOCAL LEAK RATE TEST

SUMMARY

INDEX OF VALVES i

-APPENDIX B LOCAL LEAK RATE TESTS PERFORMED BETWEEN REFUELING OUTAGES f

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LOCAL LEAK RATE TEST REPORT Page 1 !

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I.- Introduction Type B and C tests were conducted in accordance with

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

Structures for Nuclear Reactors."

i Florida Power Corporation was responsibic for conduc-

' ting the tests. Catalytic, Inc., the contractor, pre-l

pared the surveillance test procedure and provided technical support during the performance of the tests.

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. i LOCAL LEAK RATE TEST REPORT Page 2 l II. General Data Owner: Florida Power Corporation Docket No: 50-302 Location: Crystal River Nuclear Power Plant Containmert

Description:

Reinforced Concrete Cylinder with Steel Liner.

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

Design Pressure: 49.6 psig s

Maximum Allowable Leak Rate: 248,656 sec/m = .6La Recorded Total Leakage: 80377 sec/m = .194La Test Start Date: October 8, 1981 ;

Test Completion Date: November 30, 1981

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e LOCAL LEAK RATE TEST REPORT Page 3 III. Discussion The methods used to determine the icakage rates of containment isolation valves are as follows:

1. Out-Leakage

2. In-Leakage

3. Pressure Decay The "Out-Leakage" method of testir3 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 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-sisted of pressurizing the test volume to 49.6 I'bpsigand 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

e 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 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 penetrations are subject to Type B & C testing.

Appendix B shows valves / components tested between scheduled Local Leak Rate tests due to maintenance and increased surveillance.

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IV. Local Leak Rate Test Results i 1. Type B Acceptance i

Description As-Found Re-Test As-Left Criteria l

Equipment llatch 0 N/A 0 4500 cc/ min Resilient Seals l

Fuel Transfer 0 N/A 0 4100 cc/ min Tube Casket-3B Fuel Transfer 0 N/A 0 <100 cc/ min Tube Casket-3A l

LRV-45 and Blind 2 N/A 2 42740 cc/ min Flange LRV-44 and Blind 90 N/A 90 (100 cc/ min Flange Chemical Cleaning 2 N/A 2 (100 cc/ min Penetration Caskets 119 Chemical Cleaning 2 N/A 2 4100 cc/ min Penetration Caskets 120 l

l Total as found Type B Leakage: 96 seem

! Total measured Type B Leakage: 88 scem l

! Total instrument error Type B Leakage: 8 seem

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LOCAL LEAK RATE TEST REPORT Page 10 IV. Local Leak Rate Test Results C. Combined Type B & C l Total number of Valves tested - 69 Total number of Valves re-tested - 14 Total number of Valves repaired - 11 Total as found leakage - >126692 SCC /M (Type B & C)

Total as left leakage (Type C) - 80276 SCC /M Combined Type B and C leakage - 80372 SCC /M Note: Error adjusted Icakages are based on a maximum instrument

calibration accuracy of 5% applied in the conservative l direction for the total as found and 1cf t valves.

(Except where pressure decay valves were calculated.)

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

1. Exceeded assigned action values but were determined to be acceptabic because of low overall leakage.

2. SFV-18 was repaired but showed no improvement on Icahrate. See Summary, page 17.

6 LOCAu LEAK RATE TEST REPORT Page 11 l l

1 V. Analysis and Interpretation 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 containment air at 64/3 psa.

PV Mass of Containment Air = g , where:

P = Containment Pressure = 64.'3 psia 6

V = Containment Free Volume = 2 x 10 cu. ft.

R = Gas Constant = 53.35 - 'R T = Containment Temperature, assumed 549.69'R (90*F)

Mass of Containment Air = (

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bf 53.35 lbm "R (549.69'R)

Mass of Containment Air = 631,467.8 lbm g , (0.0025/ day) (631,467.8 lbm) = 65.78 lbm/hr 24 hrs / day se n (65.78 lbm/hr) 471.9 0.0749 lbm/cu ft 0.6 La = 248,656 sec/ min 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 and 0.6 La = 248,656 sec/ min Total D 169.5 nominal inches = 1450 sec/ min / nominal inch.

LOCAL LEAK RATE TEST REPORT Page 12 V. Analysis and Interpretation - Continued The action value was based on 95% of the 1450 sec/ min / nominal inch.

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

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

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

Value Size Alert Value Action Value 1" 1000 1370 1-1/3" 1500 2055 2" 2000 2740 2-1/2" 2500 3425 3" 3000 4110 4" 4000 5480 6" 6000 8220 8" 8000 10,960 10" 10,000 13,700 (All leakage rates expressed in sec/ min)

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

The distribution was based on plant experience and input to La. Type "B" penetrations and the 48" reactor building purge valves action and alert values are as follows:

Alert Value Action Value Equipment Hatch Resilient Seals Zero Leakage 500 sec/ min Fuel Transfer Tube Caskets Zero Leakage 100 sec/ min ILRT Caskets Zero Leakage 100 sec/ min

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LOCAL LEAK RATE TEST REPORT Page 13 V. Analysis and Interpretation - Continued Alert Value Action Value l Steam Generator Chem-ical cleaning Gaskets Zero Leakage 100 cc/ min Reactor Building l Purge Valve 500 sec/ min 2500 scc / min DERIVATION OF PRESSURE DECAY EQUATION The mass contained air at the beginning and end of the test is:

W g =P V/RT g and W =P V/RT 2 1 2 2 l

where the test volume V is constant.

The mass loss is then given by:

1 2 Mass loss = W 3 -W 2" - -

1 2 j[

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

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LOCAL LEAK RATE TEST REPORT Page 14 V. Analysis and Interpretation - Continued t

s s [WRT8 W RT RT L =

=fI kp -p

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p s (g -g)2 s s s VT P P L"Pt s Pressure Decay 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.

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

V = total test free air volume, cubic feet t = test duration, hours

-T ,T g 2 = test volume absolute temperature at start and end of test, respectively, absolute units P ,P = test volume absolute pressure at start and y 2 end of test respectively, absolute units l

T, = standard temperature 1

P, = standard pressure l

~0 CAL LEAK RATE TEST REPORT Page 15 V. Analysis and Interpretation - Continued Pressure Decay - Continued The formula for computing leakage rate is:

V Ts 471.9 scc / min t

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N, LOCAL LEAK RATE TEST REPORT Page 16 VI. Summary Local Leak Rate Tests were performed on the containment isolation valves and penetrations listed in Technical Speci-fications table 3.6-1. In addition, two valves installed during the outage were tested for a total of 69 valves.

Through the course of the program eighteen valves exceeded their action limit. Eleven of these valves were repaired and retested while the remaining seven were found acceptable due to the low path leakage and ALARA considera-tions. An additional three valves were inspected and retested with no change in the path leakage.

When testing both valves simultaneously on a penetration, the problem valve was identified by further testing using alternate test lineups or by applying SNDOP to the valves to determine the extent of leakage through each barrier. The results of this effort confirmed that SFV-19, AHV-1D, and WDV-60 recorded zero leakage. Also, AHV-1A was leaking on an arc of 35 degrees, but not sufficiently to prevent pres-surization. Conversely AHV-1B was blowing badly in three areas of the seat. A review of the penetrations which could not be. pressurized to P showed that in all cases one valve had grossly failed while the second valve performed its in-tended function.

The valves that exceeded their assigned action values but were determined to be acceptable because of low overall leakage, parts problems and ALARA considerations were the following.

(See Chart on next page)

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LOCAL LEAK RATE TEST REPORT Page 17 VI. Summary - Continued Pen. No. Valve No. Inb./Outb. (valve) 439 CAV-126 v' 373 CFV-19 v/'

373 CFV-25 #

V 124 CFV-17 /

124 CFV-27 /

350 CFV-18 gr 350 CFV-26 /

347 SFV-18 V' SFV-18 was repaired but showed no improvement on Leakrate.

Since SFV-19 was in the same path and was determined to have zero leakage further repairs were curtailed due to critical path allowances.

Four of the valves which failed the "As Found" test during. Refuel III also failed during the previous LLRT program.

These valves are identified as CIV-40, AHV-lC, SFV-18, and CFV-17. A complete history of these valves will be pursued and investigated to determine the best solution to improve operability.

There are presently fifteen valves which are being tested opposite the direction of post-accident flow. Of the fifteen, only WDV-94 has been identified as less conservative in reverse pressure testing and a Request for Engineering

-Information will be submitted to resolve this issue.

The total type 'C' leakage is determined by path. This is done by crediting the penetrations with the worst valve in each case. This philosophy is in accordance with the

single failure criteria for containment isolation functions

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LOCAL LEAK RATE TEST REPORT Page 18 j

VI. Summary - Continued

, and is conservative since the best valve (s) associated with the penetrations are assumed to fail during the postulated Loss of Coolant Accident.

The 'As Found" leakage could only be correlated to the best valve in some paths remaining intact during the postu-lated LOCA. This assumption allowed determination that the containment would have functioned as required.

The eleven valves which were repaired this outage com-pares with the same number of valves during the last outage.

As stated previously, four of the valves were determined to have had excessive leakage during the last LLRT program.

In conclusion, no comparison was attempted with the

previous LLRT data due to the change using path leakage to determine the 'As Found/As Left' leakage rate for the type

'C' tests. Florida Power Corporation is determined to iden-tify the true 'As Found' for containment integrity and improve this value by improving the performance of existing valves or replacement of those valves with histories of chronic failure.

The 'As Left' leakage rate for type 'B' and 'C' tests repre-sents 31% of that allowed by section III C-3 of Appendix J to 10CFR50. The 'As Found' icakage rate represents 51% of that allowed. The final recorded leakage rate for both type 'B' and 'C' tests reflects a five percent increase over the measured value to account for inaccuracy in the_ test measurement equipment. This change to the recorded leakage rate is required by FPC. Appendix B reflects all tests (type 'C') that were performed between outages.

LOCAL LEAK RATE TEST REPORT Page A-1 NOTES

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

2. Locked open.

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

4.- Connected to the secondary side of steam generator.

5. Low Pressure Injection System.

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

7. liigh' Pressure injection System.

8. Deleted.

9. General Design Criteria #57.

10. Tested in reverse direction, ASME Section XI, IWV-3420(c)

" Exceptions".

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

12. These valves isolate the main steam piping only.

13. Cannot be tested with fuel in core.

~# 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.

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

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b-LOCAL LEAK RATE TEST REPORT Page B-1

- l APPENDIX B i LLRT'S PERFORMED BETWEEN REFUELING OUTAGES As-Found'- Retest As Left- Acceptance i

Description SCC /M SCC /M SCC /M . Criteria AHV-1C/D 61,327 N/A 290 12/17/80 '

AHV-1A/B 894 0 0 2/6/81 - 2/11/81*

AHV-1C/D 0 N/A 0 2/12/81 AHV-1C/D- 285,000 24,276 24,276 3/2/81*

CFV-15/16 330 N/A 330 3/5/81 AHV-1C/D ~72 N/A 72 3/11/81*

AHV-1A/B :19,890 N/A 19,890- 4/4/81 AHV-1C/D 35 6

N/A 35 3/20/81*

'AHV-1C/D 2.2 x 10 2,732 2.732 4/4/81*

AHV-1C/D 0 N/A 0 4/9/81*

AHV-1C/D' 686 N/A 686 4/15/81*

AHV-1C/D 0 N/A 0 4/24/81*

AHV-1C/D 0 N/A 0 5/1/81*

CAV-2 230 N/A 230 6/7/81 AHV-1C/D 522,778 0 0 6/26/81*

-AHV-1A/B 0 N/A 0 6/26/81 AHV-1C/D 0 N/A 0 6/29/81 AHV-1C/D 658 5- ~.N/A 658 7/1/81 AHV-1C/D- 5.2 x 10 1,253 1,253 7/8/81*

Series of tests run to insure operability of valves.

^-

,

ML20049H797

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