ML20092C177

Reactor Containment Bldg Integrated Leakage Rate Test Rept

ML20092C177
Person / Time
Site:	Crystal River
Issue date:	11/07/1991
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20092C174	List: 3F0192-16, Forwards Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20092C177
References
NUDOCS 9202110322
Download: ML20092C177 (79)

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4 FIDRIDA POWER CORPORA'llON g Crystal River Unit 3 Nuclear Pswer Plant 1 L

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. REACTOR CONTAINMENT llUllDING INTEGRA'mD .

LEAKAGE RA'm TEST REPORT. -i November 7,1991 ,

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TABLE OF CONTENTS I. INTRODUCTION -

II. TEST SYNOPSIS 111.. TEST DATA

SUMMARY

A. Plant Information B. -- Technical Data C. Type A Test Resuhs D. Type B and C Test Results -

E. Integrated leakage Rate Measurement System F. Information Retained at Plant IV. ANALYSIS AND INTERPRETATION V. REFERENCES VI. APPENDICES A. Stabilization Phase Data B. ILRT Test Data and Plots C. . Verification Phase Data and Plots I D. Instrument Selection Guide Calculations E. Description of General Physics ILRT Computer Program F. Local Leakage Rate Test Summaries G. Sensor Locations and Volume Fractions i

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6 I. INTRODUCTION The Reactor Building Integrated Leakage Rate ' Type A" Test is performed to demonstrate that leakage through the primary reactor containment systems and components penetrating primary reactor containment do not exceed the allowable leakage rates specified in the Plant Technical Specifications.

The purpose of this report is to provide information pertinent to the activities related to the preparation, test performance, and reporting of the Crystal River Unit 3 Nuclear Power Plant Integrated Leakage Rate Test (ILRT).

Ilighlights of activities and events which occurred prior to and during the ILRT are ,

presented in Section II, Test Synopsis.

-Section III, Test Data Summary, contains data and results necessary to demonstrate containment- atmosphere stabilization, acceptable leakage rate, and successful verification test, In addition, plots provided in Appendices B and C supply a visual history of containment atmospheric conditions beginning with the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT test period and ending with the verification test.

Information in Section IV, Analysis and Interpretation, supplies the technical details associated with the ILRT computer program and its associated hardware as well as the instrumentation used during the ILRT.

Section V, References, lists the documents used for the conduct of the ILRT.

The successful periodic Type A and verification test were performed according to the requirements of the Crystal River Unit 3 Technical Specifications and 10CFR50, Appendix J. The test method used was the Absolute Method, as described in ANSI /ANS 56.8-1987, " Containment System Leakage Testing Requirements".

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Leakage rates were calculated using the mass point analysis technique described in ANSI /ANS 56.8-1987. Total Time Analysis equations from ANSI N45.41972,

' Leakage Rate Testing of Containment Structures for Nuclear Reactors' were run concurrently for informational purposes.The test results are reported in accordance with the requirements of 10CFR50, Appendix J, Section V.B.3.

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II. TEST SYNOPSIS Prior to containment pressurization on November 4,1991, site personnel were engaged in prerequisite activities for the conduct of the ILRT. The ILRT was conducted at the end of the SM mideycle outage. The following discussion highlights some of the activities that were essential to the successful and timely completion of the ILRT. These items are presented in chronological order.

A. Pre-pressurization Activities These activities included: local leakage rate testing of penetrations which were to be isolated during the ILRT, "as found" and "as! eft" local leakage rate testing of penetrations which were scheduled for maintenance prior to the ILRT, ILRT procedure review and fmalization, ILRT computer program check out and linkup to the Fluke 2285B Data Acquisition System, ILRT instrumentation installation and operability checks, and containment subvolume weighting factor and sensor failure analysis calculation.

The ILRT test procedure was reviewed against the requirements of the Plant Technical Specifications; 10CFR50, Appendix J: and ANSI /ANS 56.8-1987.

The ILRT instrumentation was calibrated prior to the ILRT as recommended by ANSI N45.4-1972, Sections 6.2 and 6.3. Final ILRT instrumentation operability checxs and in-situ checks, as speciGed in ANSI /ANS 56.8-1987, Section 4.2.3.1, were performed to ensure that all instrumentation was operating correctly. Calibration records for the ILRT instrumentation system components are retained at the plant.

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- 11 Test Summary Time-Line Ettasc Time Frame Dumtion Pressurization From: 22:50 en 11/04/91 24.83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> To: 23:'40 on 11/05/91  ;

Stabilization From: 23:45 on !!/05/91 5.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> To: 05:30 on 11/06/91 ILRT Test From: 05:30 on 11/06/91 24.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> To: 05:30 on i1/07/91 Verification Test From: 05:30 on 11/07/91 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />

To: 09:45 on i1/07/91 C. Containment Pressurization Containment pressurization started at 22:50 on November 4,1991 using six 1500 cfm diesel-driven 100% oil-free air compressors. The pressurization rate.

was maintained at approximately 3.6 psi per hour until containment -pressure reached 48 psig. At this time, the pressurization rate was gradually re<hivd by reducing the number of operating compressors and increasing backpressure with LRV-24. All compressors were stopped when the containment pressure reached 54.5 psig, at 23:40 on November 5,1991. This was within the procedural limits of 53.9 +1,-Opsig.

During pressurization an external containment walkdown was performed to

-identify potential leakage. During _the walkdown a pressure buildup approximating building pressure was noted on the personnel airlock seals.

- Pressurization was stopped at 7 psig and-the seals were inspected. The door seals were found to be in good condition and pressurization was resumed. No-

! measurable : leakage was. observed from any other penetration - in the test-lineup. Pressurization 1 was conducted with the use of the reactor building recirculation fans in slow speed. - The fans were stopped at a pressure of 48.7 psigiand were not used during the ILRT or verification test. Very little h temperature stratification was observed.

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D. C.)ntainment Atmospheric Stabilization The stabilization phase was started at 23:45 on November 5,1991 By 03:45 on November 6,1991, the temperature stabilization criteria of ANSI /ANS 56.81987 had been met. The containment was declared stable at 05:30 of ,

November 6,1991 and the ILRT test period was begun.

E. ILRT Test Period The ILRT was officially started after the 05:15 data point with the next data >

point at 05:30 on November 6,1991 and was successfully completed at 05:30 on November 7,1991. The maximum allowable leakage rate (I ) for the containment is 0.25 % wt.per day with a test acceptance limit of 0.1875 % wt.

per day (0.75 L.). The Total Time and Mass Point Analyses were run concurrently on the General Physics ILRT Computer Frogram. The leakage rate results are as follows:

Total Time Mass Point Analysis Analysis

% wtJday  % wt./ day .

Calculated Leakage Rate 0.0871

• 0.0962

• 95 % Upper Confidence 0.0958

• 0.0968

• Leakage . rate Does not include penalties for nonstandard alignments and water level changes I - F. Verification Test A successful verification test was conducted following the ILRT. At 05:30 on .

November 7,1991, a leakage rate of 15.15 sefm leakage imposed on the -

-primary containment. The 15.15 scfm leakage' imposed -(L.) on the existing -

containment leakage was slightlyless than L. (.25 % wt./ day)at 0.2383 % wt.

per _ day. The verification phase was completed at 09:45 of the same day.

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As a twenty four hour test was performed, the mass point verification test results are presented below:

Mass Point Analysis

% wtJday Leakage Rate (L .) 0.0962 Impased Leak (1,) 0.2383 Lower Limit:

1, + L., -0.25 L, 0.2720 Composite Leakage (I,) 0.2810 Upper Limit:

1, + L,, + 0.25 L, 0.3970 G. local leakage Rate Testing Prior to the start of the ILRT, "as found" local leakage rate testing (LLRT) was performed as required by 10CFR50, Appendix J. Results from this testing were required for those pene'. rations not exposed to the ILRT pressure to complete the analysis of the "as fo' od" ILRT results. The "as found" local leakage rate testing was completed on October 26,1991.

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1 Ill. TEST DATA SUMMAld l A. Plant Information Owner Florida Power Corporation Plant Crystal River Unit 3 Nuclear Power Plant Location Approx. 5 miles north 6f Crystal River, FL Docket No. 50-302 Containment Type Reinforced concrete strujture composed

- of cylindrical walls (prestressed with a post-testing tendon system in the _ vertical ar,.1 horizontal directions), with a flat and a shallow dome roof (pres (tressedf utilizing a three-way post tensioning tendon system). The inside surface is lined with a carbon steel liner.

-NSSS Supplier, Type Babcock & Wilcox PWR Date Test Completed November -7,1991.

B. Technical Data Containment Net Free Volume 2,000,000 cubic feet Design Pressure 55 psig Design Temperature 281* F Calculated Peak Accident Pressure 53.9 psig Calculated Peak Accident 278* F Temperature C. Test Results - Type A

- Test Method Absolute Test Pressure 54.5 psig 7

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Integrated Leakage Rate Total Time Analysis Test Results (Presented for information only):

Calculated Leakage Rate,1 3 0.0871 % wt./ day 95 % Upper Confidence Limit leakage Rate 0.0958 % wt./ day Integrated leakage Rate Mass Point Analysis Test Results:

Calculated Leakage Rate,1s. 0.0962 % wt./ day 95 % Upper Confidence Limit Leakage Rate 0.0986 % wt./ day Maximum Allowable Ixakage Rate, L, 0.25 % wt./ day ILRT Acceptance Criteria,0.7513 0.1875 % wt./ day Verification Test Imposed Leakage Rate. I, 15.15 sefm or 0.2383 %

wt./ day Verification Test Mass Point Analysis Results and Limits:

Upper Limit 03970 % wt./ day (l$+ l ..s + 0.25 L.)

Calculated Composite 0.2810 % wt./ day Ixakage Rate,1, Lower Limit _

0.2720 % wt./ day (I, + L . - 0.25 t,)

Report Printouts The report printouts of the II.RT and verification test calculations for the Total Time and Mass Point Analyses are provided in Appendices B and C. Stabilization data is provided in Appendix A.

D. Test Results - Type B and C Tests A summary of local leakage rate test results since the ILRT in November

l. 1987 are included in Appendix F.

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E. Integrated 12akage Rate Measurement System

. 1. Absolute Pressure Quantity 2 Manufacturer Paroscientific i l

Type DigiQuartz Model 740 l Range 0 100 psia Accuracy 10.01 % F.S.  !

Sensitivity i 0.005 psia Repeatability

• 0,005 psia Resolution 0.0001 psia

2. Drybulb Temperature Quantity 24 Manufacturer Rose ~ mount Type 78N0lN00N120100 ohm platinum resistance temperature detectors (RTD)

Range, calibrated 75-125 ' F.

Accuracy 0.5 F Se nsitivity i 0.01 F

3. Water Vapor Pressure Quantity 10

. Manufacturer Phys Chem Scientific Type Humitemp-5 Precision Relative Humidity-Temperature Monitor, Model 2150 with PCRC-11 HPl3 probes 9

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. Range 0 - 100% RH

. Accuracy i 1.8* F (Dewpoint Temperature)

Sensitivity 10.!* F (Dewpoint Temperature) 4.. . Verification Flow Quantity 2 Manufacturer Brooks Type Model 1110-08 Rotometer Range .76-7.6sefm @ 14.7 psig and 70* F Accuracy t 2% F.S.

5.- Readout Device -

Quantity. 1

' Manufacturer Fluke Type Model 2285B

. Repeatability >

Drybulb Temp. 0.054

• F Dewpoint Temp 0.04

• F Resolution i 0.01* F l 10

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The instrumentation . Selection Guide (ISG) value from ANSI /ANS 56.81987 based on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test and the above ILRT iustrumentation configuration is 0.0108 %

wt./ day (Refer .to Appendix D for calculations). The sensor locations and volume fractions as installed for the ILRT are shown in Appendix G.

G. Information Retained at Plant t

The' following information is available for review at Crystal River Unit 3 Nuclear Power Plant site:

1. A listing of all containment penetrations including the total number, .

size, and function.

~ 2. . A listing of normal operating ; instrumentation used for the leakage test, ,

3. ~ A system lineup (at time'of test) showing required valve positions and

. status of piping systems.

4 . A continuous, sequential log of events from the initial survey of

. containment to restoration of tested systems. -

5. Documentation ofinstrumentation calibrations and standards, including a sensor failure analysis.

6. Data to verify temperature stabilization criteria as established by test procedure (Appendix - A).

7._ The working copy of the test procedure that includes signature sign offs of procedural- steps.

8. The procedure and data that' verifies completion of penetration and valve testing including as-found leak rates, corrective action, and final leak rates. -

9. - Computer- printouts of ILRT data and automated data acquisition printouts along'with a summary description of the computer-program.

10. ' A review of confidence limits of test results with accompanying'_ .

computer printouts.

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11; Description of the method of leakage rate verification.

12, - ILRT data plots obtained during the test.

13. The P&lDs of pertinent systems.

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l IV. - ANALYSIS AND TNTERPRETATION l

The upper 95% confidence limit (UCL) Total Time and hiass Point leakage rates calculated during the ILRT were less than the test acceptance criteria of 0.75 L.

(0,1875% wt/ day). Additions to the calculated leakage rates must be made to account for penetration paths not exposed to the ILRT pressure and for changes in the net free containment voltime due to changes to containment water levels. These additions are discussed below.

A. Type C Penalties Penetration paths not exposed to the ILRT pressure and the corresponding minimum pathway leakage rates are as follows:

Ecc.2L Sysicln Leakage Rate _(seem) 116 RB Leak Rate 41 122 RB Leak Rate 15 202 RB Leak Rate 69.6 314- hiain Steam 420 316- hiain Steam- 1030 318 hiain Steam 20 320 hiain Steam 20 427 hiain Steam 605 428 hiain Steam 1255 The total applicable. local leakage rate Type C penalty addition is 3,475.6 teem whic'-

is equivalent to 0.0019% wt. per day.

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B. Volume Change Corrections i

The following volumes were monitored for liquid level changes which would affect the containment net free volume:

Volume Monitored Level Change Volume Change Pressurizer -10 !, hes +30.8 cu. ft.

Reactor Building Sump + 3 inches 9.48 cu ft.

Conservatively, level decreases c m be disregarded since their effect is already included in the measured leakage rate. The increase in reactor building sump resulted in a decrease of 9.48 cubic feet in the containment net free volume.

This is equivalent to a leakage rate of 0.0005 % wt. per day.

C. As Ixft ILRT Results The as left ILRT leakage rate including the required additions is as follows:

Total Time Mass Point Analysis Analysis

(% wt./ day) (% wt./ day) 95 % UCL leakage Rate 0.0958 0.0986 Type C Penalties 0.0019 0.0019 Volume Change 0.0005 0.0005 As Left 95 % UCL Leakage Rate .0.0982 0.1010 The as left Total Time and Mass Point 95 % UCL leakage rates are less than the maximum allowable leakage rate value stated in the technical specifications of 0.751, (0.1875 % wt./ day).

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1 D. As Found ILRT Results Repairs or adjustments were made to the following penetrations which would require correction to the as left ILRT result.

leakage Eccetration Savings (scem) 113 595 439 105.7 The total leakage savings is 700.7 seem based on minimum pathway analysis.

This is equivalent to 0.0004 % wt. per day. The as found ILRT leakage is determined as follows:

Total Time Mass Point Analysis Analysis

(% wt./ day) (% wt./ day)

As left 95 % UCL Leakage Rate 0.0982 0.1010 Leakage Savings 0.0004 0.00N As Found 95 % UCL Leakage Rate 0.0986 _0.1014 15

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1 V. RFFERENCES  :

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~ A. Crystal River Unit 3 Nuclear Power Plant Surveillance Procedure SP 178 Rev.

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-17, Reactor Containment Building Integrated Leakage Rate Test.

B. Crystal River Unit 3 Nuclear Power Plant Technical Specifications. [

C. Crystal River Unit 3 Nuclear Powei Plant Updated Final Safety' Analysis. j Report.

i D. Code of Federal Regulations, Title 10, Part 50, Appendix J, Primary Reactor ,

Containment Leakage Testing for Water Cooled Power Reamors.

E. - ANSI N45,4-1972, Leakage-Rate Testing of Containment Structures for Nuclear Reactors.

F, ANSI /ANS 56.8-1987, Containment System Leakage Testing Requirements.

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VI APPENDICES 17

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. APPENDIX A -

STABILIZATION PliASE DATA

'BTABLIZATION MODE TIME : 0515 OPTIONS MODE

SUMMARY

1~ - MANUAL DATA ENTRY- # OF DATA POINTS = 23 2 - PARAMATER GRAPHS MODE DURATION (IN HRS) : 5.5 3 --SENSOR PLOTS. TOT TIME MEASURED LEAE = 0.2696

.4-'- SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK = 0.1632 5 - ANSI-STABIL!ZATION CRITERIA TOT TIME 95% UCL = 0.5072 6 - BN-TOP-1-STAB. CRITERIA MASS PT LEAK = 0.2415 7 - ANSI-CRITERIA PRINTOUT MASS PT 95% UCL = 0.2551 8 - BN -TOP-1 CRITERI A PRINTOUT 9 REPRINT CURRENT DATA POINT P - PASS WORD MENU 0.--FLASH OFF ANSI TEMPERATURE STABLIZATION CRITERIA MET BN-TOP TEMPERATURE STABLIZATION CRITERIA MET POINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 78.610/ -0.029 AVG PRESS: 68.818/ -0.005

MASS: 688156.50/ -10.000 AVG DEW PRESS: 0.4208/-0.0013 TOTAL PRESS: 69.039/ -0.006 1

LEAK RATE ANALYSIS UNIT # 3 TorAL TIME MASS POINT MEASURED CALCULATFD UCL CALC. L95 bhk ------ -

Nhk ------ - ------- -

Nhk ------ -

310 0.25 1.2029 0.0000 0.0000 0.0000 0.0000 320 0.50 0.7145 0,7145 0.0000 0.7167 3.1L00 310 0.75 0.5437 0.4908 1.7472 0.5124 1.0186 310 1.00 0.4529 0.3654 1.0963 0.4060- 0.6812 -

310 1 25 0.4143 0.2979 0.9158 0.3532 0.528".

310 1.50 0.4468 0.2884 0.8933 0.3625 0.4799 310 1.75 0.3699 0.2532 0.7948 0.3286 0.4213 310 e.00 0.3604 0.2319 0.7374 0.3098 0.3826 310 2.25 0.3403 0.2140 0.6911 0.2937 0.3533 310 2.50 0.3785 0.2177 0.6873 0.3046 0.3538 310 2.75- 0.3194 0.2039 0.6508 0.2886 0.3325 310 3.00 0.3181 0.1963 0.6256 0.2798 0.3178 310 3.25 0.3186 0.1905 0.6082 0.2751 0.3077 310 3.50 0.2990 0.1831 0.5876 0,1664 0.2959 310 3.75 0.2963 0.1778 0.5715 0.2608 0.2871 310 4.00 0.2941 0.1741 0.5586 0.2563 0.2797 310 4,25 0.3017 -0.1737 0.5513 0.2504 0.2772 310 4.50 0.2895 0.1715 0.5416 0.2534 0.2721 310 4.75- 0.2837 0.1693 0.5322 0.2507 0.2677 310 5.00 0.2789 0.1671 0.5234 0.2475 0.2631 310 5.25 0.2758 0.1653 0.5153 0.2446 0.2591 310 0.50 0.2696 0.1632 0.5072 0.2415 0.2551-

AVG DATA VALUES UNITi# 3

- DATE TIME- T(I) P(I) DT(I) VP(I) MASS (1) 309 0.00 80.498 68.901 0.000 0.425 688582.00

- 310 0.25 80.245 68,030 0.000 0.424 688495.69 310 0.50 50.030 68.831 0.000 0.423 688479.50 310 0.75 79.858 68.808 0.000 0.423 688465.00 310 1.00 79.719 68,789 0.000 0.423 688452.00 310 1.25 79.601 68.772 0.000 0.423 688433.38 310 1.50 79.502 68.755 0.000 0.425 688389.69 310 1.75 79.401 68.743 0.000 0.424 688396.31 310 2.00 79.320 68.730 0.000 0.424 688375.19 310 2.25 79.241 68.719 0.000 0.423 688362.31 310 2.50 79.174 68.705 0.000 0.426 688310.50 310 2.75 79.102 68.698 0.000 0.423 688329.88 310 3.00 79.046 68.689 0.000 0.423 688308.13  ;

- 310 3.25 78.997- 68.660 0.000 0.423 688284.88 310 3.50 78.937 38.672 0.000 0.422 688281.69 310 3.75 78.889 S8.664 0.000 0.422 688263.13 310 4.00 78.847 68.657 0.000 0.421 688244.38 310 4.25 78.801 68.648 0.000 0.423 688214.00 310 4.50 78.758 68.642 0.000 0.422 688208.19 310 4.75 78.716 68.635 0.000 0.422 688195.38 310 5.00 78.680 68.629 0.000 0.422 688181.88

- 310 5.25 78.640 68.623 0.000 0.422 688166.50 310 5.50 78.610 68.618 0.000 0.421 688156.:7 5

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h ;G,50 78.6103 -0.1634 0.0606 5125 .78.6396 -0.1785 0.0183

" > 5. 00- 78.6803 -0.1831 0.0399 4.75 78.7162- -0.1931 0.0600 4.60 78.7579 -0.2081 0.0492 4.25 78.8005- -0.2204 0.0643

'4.00 78.8474 - -0.2365 0.0781 3.75 78.8893 -0.2560 0.1061 3.50 78.9370 -0.2825 0.0791 3.25 78.9966 -0.3023 0.1353 3.00 79.0465 -0.3361 0.1672 2.75 79.1023 -0.3779 0.1995 2.50 79.1741l -0.4278- 0.2957 2.25 79.2413 -0.5017 0.3490 2.00 79.3203 -0.5890 0.0000 1.75 79.4013 0.0000 0.0000 1.50 1 79.5021 0.0000 0.0000 1.25 79.6012 0.0000 0.0000 2.00 79.7187 0.0000 0.0000 0.75 79.8582 0.0000 0.0000 0.50 80.0297: 0.0000 0.0000

'O.25 80.2447 0.0000 0.0000 0.00 80.4983 0.0000 0.0000 4

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- 1 STABILIZATION AH8150.8

. TIME TEMP 56.8 56.8 4-1 1 HR 4 RR HR F/HR F/HR 5.50 78.010 0.148 0.223 0.075  :

5.25 78.640 0.161 0.240 0.079 l 0.00 78.680 0.367 0.200 0.093 4.75 78.716 0.173 0.285 0.112 '

4.50 78.758 0.179 0.318 0.139 4.25 78.801 0.196 0.361 0.165 4.00 78.847 0.199 0.413 0.214 ,

3.75 78.889 0.213 0.000 -0.2?" >

3.50 73.957 0.237 0.000 -0.22 3.25 78.097 0.245 0.000 -0.245 3.00 79.046 0.274 0.000 -0.274 2.75 79.102 0.299 0.000 -0.299 2.50 79.174 0.328 0.000 -0 328 2.25 79.241 0.360 0.000 -0.360 ,

2.00 79.320 0.398 0.000 -0.398 t 1.75 79.401 0.457 0.000 -0.457 1.50 79.502 0.528 0.000 -0.528 1.25 79.601 0.644 0.000 -0.644 1.00 79.719 0.780 0.000 -0.780 0.75 79.850 0.000 0.000- 0.000 0.50 80.030 0.000 0.000 0.000

'O.25 60.245 0.000 0.000 0.000 S

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i APPENDIX Il ILRT TEST DATA AND PLOTS l

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SUMMARY

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TOTAL TfME/ MASS POINT UNIT # 3

, DN!E TN iTLH LHCALC SL LAM L95

- , % , .m . ... .... .. ...__. . .. ..------- . . .... ...

im f'? 0.0000 0.0000 0.0000 0.0000 0.0000 ,

'[; E9 e.s5 0.3932 0.0000 0.0000 0.0000 0,0000 310 0.50 0.2223 0.2223 0.0000 0.2209 1.0630 310 0.75 0.2380 0.2069 0.9452 0.2190 0.3486 r

310- 1.00 0.1867 0.1695 0.4623 0.1808 0.2597 310 1.25 0.1725 0.14't 1 0.3523 0.1610 0.2140 310 1.50 0.1707 0.1367 0.3120 0.1537 0.1901  !

310 1.Yb 0.1713 0.1327 0.2935 0.1528 0.1790 310 2.00 0.1631 0.2280 0.2762 0.1496 0.1698 310 2.58 0.1498 0.1C86 0.2581 0.1408 0.1570 310 2.75 0.1505 0.1161 0.2536 0.1383 0.1514 310 3.00 0.1417 0.1134 0.2421 0.1329 0.1447  !

310 3.05 0.1393 0.1178 0.2365 0.1995 0.1403 ,

310- 3.25 0.1404 0.1148 0.2279 0.1277 0.1373 310 3.53 0.1549 0.1132 0.2253 0.1314 0.1408 310 3.75 0.1467 0.1129 0.2221 0.1321 0.1403 310 4.00 0.1399 0.1104 0.2167 0.1307 .0.1381  :

r

-310 4.27 0.1419 0.1088 0.2130 0.1305 -0.1371 310 4.50 0.1492 0.1100 0.2131 0.1326 0.1389 .

'310 4.75 0.1483 0.1107 0.2126 0.1341 0,1399 310 5.00 0.1408' O.1102 0.2102 0.1336 0.1389 310 5.25 0.1409 0.1099 0.2082 0.1330 0.1379 310 5.50 0.1384 0.1094 0.2060 0.1324 0.1369 310 5.75 0.1336 0.1084 0.2030 0.1308 0.1353 310- 6.00 0.1328 0.1075 0.2004 0.1293 0.1336 L 310, 6.25 'O.1362 0.1073 0.1989 0.1291 0.1331 L

e TOTAL TIME / MASS PO!!1T UllIT W 3  ;

DATE TIME TTLM LHCALO SL LAM L95 310 6.50 0.1429 0.1082 0.1991 0.1302 0.1341' i

310 6.75 0.1416 0.1090 0.1989 0.1311 0.1347  ;

310- 7.00 0.1366 0.1090 0.1973 0.1308 0.1342 ,

310 7.25 0.1366 0.1091 0.1968 0.1305 0.1337 f 310 7.50 0.1403 0.1097 0.1966 0.1312 0.1342- -

310 7.75 0.1367 0.1099 0.1957 0.1312 0.1340 310 8.00 0.1362 0.1100 0.1949 0.1309 0.1336

• 310 8.25. 0.1362 0.1102 0.1941 0.1308 0.1333 310 8.50 0.1368 0.1105 0.1935 0.1300 0.1332 310 8.75 0.1336 0.1104 0.1925 0.1302 0.1325 310 9.00 0.1357 0.1100 0.1919 0.1303 0.1324 310 9.25 0.1331. 0.1100 0.1909 0.1298 0.1319 310- 9.50- 0.1288 0.1101 0.1895 0.1290 0.1312 310 9.'75 0.1310 0.1099 0.1885 0.1284 0.1305  :

310 10.00 0.1331 0.1100 0.1878 0.1282 0.1302 310 10.25 0.1347 0.1103 .0.1874 0.1283 0.1302 310 10.50 0.1257 0.1097 0.1860 0.1272 0.1293

-310 10.75 0.1307 0.1096 0.1852 0.1268 0,1289,  ;

310. 11.00 '0.1274 0.1093 0.1841 0.1262 0.1283 310- 11.26 0.1273 0.1090 0.1831 0.1266 0.1277 310 11.50 0.1250 0.1086 0.1819 0.1249 0.12h0 '

&W- 11,75 0.1262 0.1083 0.1809 0.1244 0.1265 310 12.00. 0.1242 0.1079 0.1798 0.1236 0.1257

~

3101 12.25 0.1228' O.1074 0.1786 0.1228 0.1250.:

'310 12.50 0.1240 0.1071 0.1777 0.1224 0.1245 310 12.75 0.1218 0.1066 0.1766 0.1214 0.1236 [

t TOTAL T8ME/ MASS P0111T UllIT : 3 l

'DATE TIME TTLM LMCALC SL LAM L95 c 310 13.00 0.1241 0.1064 0.1757 0.1209 0.1231 310 13.25 0.1238 0.1062 0.1750 0.1206 0.1227 310 L'.50 0,1208 0.1057 0.1739 0.1199 0.1220 0.1195 310 13.75 0.1228 0.1055 0.1732 0.1010 310 14.00 0.1209 0.1052 0.1723 0.1191 0.1211 310 14.25 0.1211 0.1049 0.1715 0.1187 0.1207 310 14.50 0.1205 0.1045 0.1707 0.1181 0.1201 310 14.75 0.1187 0.1041 0.1697 0.1176 0.1196 310 15.00 0.1187 0.1038 0.1689 0.1170 0.1101 310 15.25 0.1166 0.1033 0.1679 0.1164 0.1184 310 15.50 0.1159 0.1028 0.1670 0.1156 0.1177 ,

310 15.75 0.1162 0.1024 0.1661 0.1151 0.1173 310 16.00 0.1118 0.1018 0.1649 0.1142 0.1165 310 16.25 0.1158 " 0.1014 0.1641 0.1137 0.1150 310 16.50 0.1153 0.1010 0.1633 0.1131 0.1154 -

310 16.75 0.1096 0.1003 0.1622 0.1122 0.1146 310 17.00, 0.1137 0.0999 0.1613 0.1117 0.1140 310 17.25 0.1107 0.0994 0.1604 0.1110 0.1134 310 17.50 0.1100 0.0988 0.1594 0.1103 0.1127 310 17.75 0.1111 0.0904 0.1586 0.1096 0.1120 3fp 18.00 0.1118 0.0980 0.1578 0.1092 0.1116 313 18.25 0.1097 0.0975 0.1570 0.1086 0.1109 311 18.50 0.1101 0.0971 0.1562 0.1081 0.1105 311 18.75 0.1103 0.0967 0.1554 0.1077 0.1100 311 19.00 0.1084 0.0963 0.1546 0.1070 0.1094 311 19.25 0.1069 0.0958 0.1538 0.1064 0.1086 l

l

TOTAL TIME / MASS POINT UNIT # 3 DATE TIME TTLM LMCALO SL LAH L95 311 19.50 0.1057 0.0952 0.1529 0.1057 0.1081 311 19.75 0.1068 0.0948 -0.1521 0.1052 0.1076 311 20.00 0.1001 0.0943 0.1513 0.1046 0.1070 311 20.25 0.1040 0.0938 0.1505 0.1040 0.1064 311- 120.50 0.1035 0 0933 0.1490 0.1033 0.1058 311 20.75 0.1050 0.0928 0.1489 0.1029 0.1053

-311 21.00- 0.1040 0.0924 0.1481 0.1024 0.1048 311 21.25 0.1026 0.0919 0.1473 0.1018 0.1042 311 21.50- 0.1031' O.0914 0.1408 0.1012 0.1037 311 21,75 0.1043 0.0911 0.1459 0.1008 0.1032 311 22.00 - 0.1026 0.0906 0.1452 0.1003 0.1027 311 22.25 0.1005 0.0901 0.1444 0.0998 0.1022 311 22.50 0.1010 0.0897 0.1437 0.0993- 0.1017

311 22.75 - 0.1008 0.0893 0.1430 0.0988 0.1012 311- 23.00 0.1004- 0.0888 0.1423 0.0903 0.1007 311- 23.25 0.1009- 0.0885 -0.1417 0.0979 0.1002 311 23.50 ' 0.0994 0.0880 0.1410 0.0973 0.0997

~311 23.75 0.0985 0.0876 0.1403 0.0968 0.0992-

'311 24.00 0.0968 0.0871 0.0958 0.09G2 0.0986

• -.~.,,_,n -

.,,_U,-

,v y . . -i.--

. AVG. DATA VALUES UNIT # 3 o^1E _ _ _ _ _I!"E _ _ _ _ _ !!!!_ _ _ _ _L'111_ _ _ _ _ BI1!!_ ___

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APPENDIX C  ;

VERIFICATION TEST DATA AND PLOPS f

i i

l 1

i

-- . - - - - - - ,_ _ - - _ . _ . __1

VERITICAT!CN MCDE TIHE: 0945

. OPTIONS: TEST

SUMMARY

i - MANUAL DATA ENTRY # OF DATA POINTS : 10 2 -

PARAMETER GRAPH'1 MODE DURATION (IN HOURS) : 4.25 3 -

02NSCR PL370 TOT TIME MEASURED LEAK : 0.03??

4 -

TREND ANALYSIC TOT TIME CALCULATED LEAK : 0.0020 S -

REPRINT CURf:ENT DATA PT HASS PT LEAK : 0.2810 S -

SENSCR DIFFERENT! ALS IMPOSED LEAK : 0.2000 TOT TIME UPPER LINIT : 0.3879 P -

PASS UCRD MENU TOT TIME LOWER LIMIT : 0.2020 MASS PT UPPER LIMIT : 0.3970 SELECTED OFTION : HASS PT LOWER LIMIT : 0.2720 TOT TIME VEfIFICATIDH CRITERIA HAS NOT BEEN HET MASS PT VERIFICATICN CRITERIA HAS BEEN HET POINT SUPMARY: CLARENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP- 70.010/ -0.007 AVG PRESS: 08.297 / -0.000 HASS: 6S7103.63/ -21.750 AVG DEW PRESS: 0.4000/ -0.0002 TOTAL PRESS: 60.897 / -0.00?

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AVO. D41A VALUCS UNII U 3 DATC TIME T(!) P(l) Di(1) VP(l) MASU(!)

311 0.00 77.069 6P.352 0.000 0.401 607461.19 311 0.25 77.066 60.349 0.000 0.401 607432.30 311 0.32 77.067 60.340 0.000 0.401 607420.19

?ll 0.50 77.056 60.346 0.000 0.401 607410.06 311 0.75  ??.030 60.242 0.000 0.401 60 7 39 2. St, 311 1.00 77.031 60.339 0.003 0.401 607372.06 311 1.25 77.023 60.334 0.000 0.402 607340.75 311 1.50 77.014 60.331 0.000 0.401 607321.30 311 1.75 77.003 60.329 0.000 0.401 607306.63 311 2.00 76.906 60.32b 0.000 0.401 607296.94 311 2.25 76.902 60.323 0.000 0.400 607273.01 311 2.50 76.969 60.320 0.000 0.400 607260.56 311 2.7B 76.962 60.316 0.000 0.401 607220.25 311 3.00 76.956 60.313 0.000 0.400 607213.06 311 3.25 76.945 60.310 0.000 0.400 607195.94 311 3.30 76.931 (0.306 0.000 0.400 607174.75 311 3.75 76.929 68.304 0.000 0.400 607149.01 311 4.00 76.920 60.100 0.000 0.400 607125.30 311 4 . .' S 76.913 60.297 0.000 0.400 607103.63

i i 0-MASS POINT UNIT C J l

DATE TIME LAM L95 311 0.00_ 0.0000 0.0000 311 0.25 0.0000 0.0000 311 0.32 0.4304 0.7072 311 0.50 0.3672 0.5005 311 0.75 0.3145 0.3907 311 1.00 0.2967 0.3450 311' 1.25 0.3115 0.3460 311 1.50 0.3132 0.3370 311 1.75 0.3040 0.3240 311 2.00 0.~903- 0.3111 311 2.25 0.2044 0.3010 311- 2.50 0.2772 0.2932 311 2.75- 0.2700 0.2922 311 -3.00 0.2779 0.2092 311 3.25 0.2764 0.2062 311 3.50 0.2760 0.2045

-311 3.75' O.2770 0.2045 311 '4.00 0.2799 -0.2057 311- 4.25 -0.2010 0.2073

~

e Al'I'ENDIX D INSTRUMENT SELECrlON GUIDE CAlrUIA110N

l l

INS'IRUMFNI' Sell!C110N 0U1D11 CAICUIWi1ON  !

Page 1 of 2

{

- A. TEST PARAMlITERS  !

i la = 0.25%/ day {

P = 68.6 psia f

-T a 538' R l T 4, = 74.4' F  ;

t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />  !

H. INSTRUMENT PARAMETERS  !

.I

1. Total Absolute Pressure  !

No of Sensors = 2 l

F,ange: 0 100 psia j Sensor sensitivity error (E): 0.005 psla j Measurement system error (c): [

Res.olution: 0.0001 psia i Repeatability: 0.005 psia l

c = + /. ((0.0001)' +- (0,005)')'/3 -

e = +/. 0.005001 psia j ep= +/. ((0.005)8 + (0.005001)2)'/2 /(2)'/2 ep = +/. 0.005001 psia  ;

3

2. Water Vapor Pressure i No. of Sensors = 10 -!

Sensor sensitivity error (E): 0,l* F t Measurement system error (e):

Resolution: ~ 0.01' F 1- ,

Repeatability: 0.04" F

-- e ' = + /. ((0.01)' + (0.04)2)'/2 c = + /.' O.04 l' F. a At a dewpoint of 74.4' F, the equivalent water vapor pressure change (as

. determined from steam tables) is 0.0142 psla/" F.

-.---.n-._,w,'.,

y- --

,.,,,,,+g.-w -,w,,-w-__-3', ,--ry---.*3.-n-., ,p-- ,p- rw--w,---,,--w---wm-,wp.,y .y.,.9.,,.,..,..,%- ,,yy..-%. y w,,. p. +y-, i %,-v

0 l' age 2 of 2 i

E = +/ 0.1 F (0.0142 psla/ F)

E = +/ 0.00142 psia e = + /. 0.04l' F (0.0142 psla/" F) c = + /. 0.(XX)58 psia ey a +/. ((0.00142)8 + (0.(XX)58)2)3/2 /(10)i/2 e = 4 /. 0.(XX)48 psia n

3. Temperature No. of Sensors = 24 Sensor sensitivity error (E): 0.01" F Measurement system error (c):

Resolution: 0.01" F Repeatability: 0.054" F e = + /- ((0.01)' + (0.054)2)'/3 e = /. 0.055' F = +/ 0.055' R cr = + /- ((0.01)2 + (0.055)2)l/2 /(24)'/3 c r = + / 0.01l' R

4. Instrumentation Selection Guide Formula ISO =- +/. 2400/t (2(ep /P)3 +2(ep /P)2 +2(eifI')2)'/2 ISG = +/-(2400/24)(2(0.005001/68.6)2 + 2(0.(XXM8/68.6)8

+ 2(0.0ll/538)2)i/2 ISO = +/ 0.0108 %/ day '

1 l

I k .~ s,.

l l

t l

APPENDIX E GENERAL FilYSICS ILRT COMPUTER PROGRAM DESCRii'FlON t

t

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. I DESCRIFi1ON OF GENERAL PilYSICS ILRT COMPUIIIR PROGRAM LThe following paragraphs describe the various features and attributes of the Generai  !

- Physics ILRT _ Computer Program and uc- process used to certify it for each

- application.

REDUNDANCY -i

~

The General Physics ILRT team was equipped with two fully operational IBM

-compatible microcomputers during the ILRT-and for on site data reduction and - ,

analysis. The computer software and hardware interfaced directly with the ILRT Measurement System Data Acquisition System (Fluke 2285H). -;

l

- ,Two computers were brcught on site for 100% redundancy, as each computer and its. software is capable of independently performing the ILRT. The General Physics ILRT Computer Software is also capable of accepting manual input of raw sensor t

data and performing all required sensor data conversions if the data logger nould cease to function. : Each computer was equipped with back-up disks in the unlikely event of a disk'" crash."  !

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SECURrrY The General Physics ILRT Computer Program is written in OUICK BASIC. QUICK BASIC is a high level programming language which combines programming case with user oriented command functions to create an easy to use and understand program.

In order to increase speed of operation the program was then compiled into an executable command file. Compiling was accomplished using the Oulck Basic Compiler. In addition to execution speed, this had the added benefit of makinb the program more secure as compiled programs cannot be edited or changed. The program requires a password to change modes of operation, start times, or enter the data editing routine to safeguard the integrity of the raw data files.

FEATURES The program itself is designed to be a menu driven program consisting of five separate, menu driven operating modes. These are the:

1 Pressurization Mode 4. Verification Mode

2. Stabilization Mode 5. Depressurization Mode 3.. Test Mode l

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. . - .. - _ ~ . .- - - - - - . - - _ - - -_ . - _

These modes also correspond to the phases of the ILRT, Menu driven means that the user is presented with a list of options that the program can perform and from which the user can choose It allows for interactive information exchange between the user and the computer and preunts invalid information or user mistakes from crashing the program. Program organization consists of a master menu which controls access to the seven operating modes chained to the individual menus which control these modes. The data processing, information disby capabilities and function of each mode is as follows:

1. Pressurization Mode: All data reduction, graphic displays of average temperature, dewpoint, and corrected pressure.

2. Stabilization Mode: All data reduction, automatic comparison of data against ANSI 56.8 and UN TOP.1 temperature stabilization criteria, notification when criteria is met, graphic displays of average temperature, dewpoint, and corrected pressure.

3. Test Mode: All data reduction, calculation of leakage rates using mass point, tor 1 time and point-to-point analysis techniques, display of trend report information required by BN-TOP-1, graphic display of average temperature, dewpoint, pressure and mass, as well as graphic display of mass point measured leakage,95% UCL; total time measured and calculated leakage and the total time leakage rate at the 95% UCL (as calculated by BN-TOP 1),

including a superimposed acceptance criteria line).

4. Verification Test Mode: With input of imposed leakage in SCFM automatically calculates and displays on graph and trend report the acceptance criteria band, plus all graphics displays available in test mode,

5. Depressurization Mode: All data and graphics capabilities of Pressurization Mode.

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Other reduedon and analysis capabilities of the General Physics ILRT computer 3

program include:

1. Containment total pressure conversion from counts to psia (if required), and averaging.

2. Containment drybulb temperature weighted averaging and conversion to absolute units.

3. Containment dewpoint temperature weighted averaging (conversion from Foxboro dewcell element temperature to dewpoint temperature if required) and conversion to partial pressure of water vapor (psia).

4, Data storage of ILRT measurement system inputs for each data point.

5. Weight (mass) point calculations using the ideal gas law.

6. Automated Data Acquisition and/or Manual Data Entry.

7. _ Sensor performance and deviation information for sensor failure criteria, graphic display ofindividual sensor performance for selected operating mode.

8. Calculation of ISO formula at beginning of test; acceptance criteria based on

! number of sensors remaining and actual test duration.

9. Computer System Error Functions automatically checks for error in incoming data, printer or disk drive faults.

'4

- The computer program used by General Physics has been previously certified for six tests at the San Onofre Nuclear Generating Station and over a dozen other ILRTs.

The initial certification required verification of the program through hand calculations and an independent review by Bechtel Power Corporation.

After modification for the Crystal River Unit 3 ILRT was completed, a calibration set of raw data was used to verify the program calculations prior to usage.

Additionally, once the computer was linked to the data acquisition system and a complete data stream was available, the input function of each mode of the program was verified by comparing the data acquisition system output to the computer

, printout data point summary. A data set of known values were manually entered h.

verify proper calculation of average temperatures and relative humidities using the installed volume weighting fractions.

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l APPENDIX F LOCAL LEAKAGE RATE TEST SUMMARIES

LEAK RATE TESTING

SUMMARY

DATE DESCRIPTION AS FOUND TOTAL AS LEFT TOTAL OF TYPE B & C 0F TYPE B & C (secm) (sccm) 10/30/87 RF 6 "As left" ------ 26,930.1 5/26/89 RCP Outage 58,290.8 40,076.7 6/13/89 Purge Valve Testing 40,076.7 37,583.7 6/30/89 As Found Purge Valve 36,962.6 ------

Testing 7/10/89 As left Purge Valve ------ 37,417.7 Testing 8/28/89 As Found Purge Valve 37,628.7 ------

Testing 10/2/89 As left Purge Valve ------ 37,672.7 Testing 11/16/89 Personnel Air Lock 35,112.7 35,112.7 Testing 2/21/90 As Found & As Loft 36,176.7 35,348.7 Purge Valve Testing 6/14/90 RF 7 Testing 50,839.94 38',998.46 10/19/90 As Found & As left 38,920.46 39,204.46 i Purge Valve Testing 12/17/90 As Found & As Left 27,681.46 28,071.46 Purge _ Valve and Personnel Air-Lock Testing 1/28/91 Update Total for 28,464.43 28,464.43

-Addition of Electrical Penetrationt 4 1

6/10/91 Personnel Air Lock 28,822.43 28,822.43 Testing 1

11/15/91 BM Outage Testing 45,699.57 46,958.27 11/19/91 Post Maintenance 46,958.27 46,348.27

( Testing of Personnel l

Air Lock i

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LEAK RATE TESTING TBENDtNG PROGRAM Page 2 FOR FLORfDA PCM/ER CORPOPATION - CRYSTAL RfVER UNIT 3 (2ND INTERVAL)

TYPE C LLRT tvaNes, flanges) INBOARD ISOLATION VALVES (Leakage in seem) OUTBOARD ISOLATION VALVES (Leak in ocem) , PENETRATION PATH LEAKAGE (ecom)

PENETRATION SYSTEM . VALVE # LEAKAGE ACTION STATUS VALVE # LEAKAGE ACOON STATUS AS ' AS 1 ACTUAL AS AS 'VALUE AS AS VALUE FOUND LEFT DATE FOUND / LEFT FOUND./ LEFT VALUE VALUE I

113 AIR HANDUNG A HV-1C 2250.0 2500 PASS AHV-1D 2250 525 Mis 113 AIR HANDUNG - AHV-1C 1400 0 2500 PASS AHV-1D 1460 2r27/89 116 RB LEAK RATE LRV-45 41.0 41.0 3192 PASS LfW46 221.0 221.0 1596 PASS 221 221 ta%91 116 Ru LEAK RATE LRV-45 2.0 20 3192 PASS LRV-46 69 4 69 4 1596 PASS 69 69 377/90 116 RB LEAK PATE LRV-45 20.0 20.0 3192 PA5S LRV-46 2950 295 0 1596 PASS 295 295 ~3/15/83 117 DEM!N WATER WN-162 4788 PASS DWV-160 258.0 700.0 4788 PASS 258 700 11/1/91 117 DEMIN WATER DWV-162 2.0 2.0 4788 PASS DWV-160 1882 1882 4786 PASS 188 188 4/3/90 117 DEM:N WATER DWV-162 6570.0 2190 0 4788 FAIL DWV 160 537.0 281.0 4788 PASS 6570 2190 3/3G1!!9 121 RB LEAK RATE LRV-50 331.0 331.0 12768 PASS 121 RB LEAK RATE LFN-36 324.0 3240 12768 PASS 121 RB LEAK RATE LRV-90 128.7 128 7 4788 PASS 121 RB LEAK RATE LRV-89 124.1 124.1 4788 PASS 460 460 3"27/90 121 RB LEAK RATE LRV-50 116.0 1160 12768 PASS 1 21 RB LEAK RATE LRV-36 134.9 134.9 12768 PASS 121 RB LEAK RATE LRV-90 117.6 117.6 4788 PASS 121 RB LEAK RATE LRV-89 118.6 178 6 4788 PASS 254 254 3/1539 122 RB LEAK PATE LRV-88 4768 PASS 122 RB LEAK RATE LRV-87 15 0 117.6 4788 PASS 15 118 11/11.91 122 PS LEAK RATE LRV-88 20 0 20 0 4788 PASS 122 RB LEAK RATE LRV-87 20 0 20 0 4788 PASS 20 20 3/26/90 122 RB LEAK RATE LRV-88 42.6 42.6 4788 PASS 122 RB LEAK RATE LRV47 51.6 51 6 4788 PASS 52 52 3/15,%9 123 CORE FLOOD CFV-20 3820.0 3740 1596 FA!L CFV,28 13 0 13.0 1596 PASS 3820 374 3G1/30 123 CORE FLOOD CFV-20 1587.0 1587.0 1596 PASS CFV-28 41.4 41.4 1S96 PASS 1587 1587 3/14,Tt9 124 CORE FLOOD CFV-17 336.0 1890 1596 PASS CFV-27 20 0 $0.0 1596 PASS 336- 189 3/21/90

LEAK RATE TESTING TRENDING PROGRAM Page 3 FOR FLORfDA POWER CORPORATION - CRYSTAL Ar/ER UNIT 3 (2ND INTERVAQ TVPE C LLRT (valves, flanges) . INBOARD ISOLATK)N VALVES (Leakage in secm) , OUTBOARD ISOLATION VALVES (Leakage in secm) PENE BATKyd PATH LEAKAGE (scem)

- PENETRATION SYSTEM VALVE # . LEAKAGE: ACTION STATUS VALVE # . LEAKAGE ACTION STATUS AS AS ACTUAL AS . AS . VALUE. AS AS VALUE FOUND .; -LEFT DATE FOUND / LEFT FOUND / LEFT VALUE VALUE 124 CORE FLOOD CFV-17 202.0 202.0 1596 PASS CFV-27 . 20 0 20.0 1596 PASS 202 202 3/14/09 125 RB LEAK RATE LRV-94 665.0 665.0 4788 PASS 125 RB LEAK RATE LRV-93 655.0 655.0 4788 PASS 125 RB LEAK RATE LRV-92 87.0 87.0 4788 PASS 125 RB LEAK RATE LRV-91 ti5.0 65 0 4788 PASS 752 752 3/28,9 0 125 RB LEAK RATE LRV-94 1536.0 1536.0 4788 PASS 125 RB LEAK RATE LR/-93 1575.0 1575.0 4788 PASS 125 RB LEA.K RATE LRV-92 286.0 2860 4788 PASS 125 RB LEAK RATE LRV-91 285.0 2850 4788 PASS 1861 1861 3/1 5199 202 RB LEAK RATE LAV-44 69 6 1089.0 3192 PASS 70 1089 11/11/91 202 RB LEAK RATE LRV-44 202 20 2 3192 PASS 20 20 3/24,90 202 R8 LEAK RATE LRV 44 20.0 20.0 3192 PASS 20 20 3/15/89 206 INDUST. COOUNG CN-41 82.0 82.0 39Q0 PASS 82 82 3f23,90 206 INDUST. COOUNG CN-41 300.0 300.0 3990 PASS 300 300 3/1/89 207 INDUST. COOUNG CN-40 15.0 150 3990 PASS 15 15 3MT/90 207 INDUS'. COOUNG CN4 20 0 20 0 3990 PASS 20 20 3/1/89 305 RB LEAK RATE LFN-70 20 6 20 6 9576 PASS LRV-72 27.7 27.7 9576 PASS 26 2B 129/89 IE3L RB LEAK RATE LRV-73 47.5 47.5 9576 PASS LRV-71 52.5 52.5 957G PASS 52 52 3/30/89 ID6W CONT MONITORNG WSV-32 21.0 21.0 798 PASS WSV-33 19.4 19.4 798 PASS 306W CONT MON! TOR:NG WSV-28 18.3 183 798 PASS WSV-29 14.5 14.5 798 PASS 303W CONT MONITORING WSV-26 14.9 14.9 798 PASS WSV-27 14.8 14 6 798 PASS 54 54 3/28,9 0 4

IE3W CONT MONITORING WSV-32 20.0 20.0 798 PASS WSV-33 20.0 20.0 798 PASS 306W CONT MONITORING WSV-28 20.0 20 0 798 PASS M,T/ 29 20 0 20.0 798 PASS 3C3W CONT MONITOR!NG WSV-26 20.0 20.0 798 PASS WSV 27 20.0 20.0 798 PASS 60 6L 3/17/89

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Page 4 LEA *( RATE TESTING TRENDING PROGRAM FOR FLOR!DA POWER CORPORATON - CRYSTAL Rr/ER UNIT 3 (2ND INTERVAL)

INBOARD ISCLATON VALVES (Leakage b seem) OUTBOARD ISOLAMN VALVES (Leakage in occm) PENETRATON TYPE C LLRT (vahres, f!anges)

PATH LEAKAGE (seema VALVE # LEAKAGE ACTON STATUS AS AS ACTUAL VALVE # LEAKAGE ACTON STATUS PEMETPATION SYSTEM AS AS ' VALUE FOUND LEFT DATE AS AS VALUE FOUND / LEFT VALUE VALUE FOUND / LEFT MSV-146 420 0 420 0 6384 PASS 420 420 10nS91 314 MAIN STEAM MSV-146 12050 0 2100.0 6384 FAtl 12050 2100 171/90 314 MA!N STEAM 0384 PASS 1606 1606 3,% t9 MSV-146 1606.0 1606.0 314 MA!N STEAM WS%4 73 3 73.3 1596 PASS 97 91 A'590 CONT MONITORING WSV-3 91.3 91.3 1596 PASS 315 WS%4 20.0 20.0 1596 PASS 20 20 3/17/89 CONT MONfTOR;NG WSW3 20 0 20.0 1596 PASS 315 PASS 1030 1030 1008,91 MSV-114 1030.0 1030 0 2394 316 MA!N STEAM

?AS%114 50 50 2394 PASS 5 5 3*22/90 316 MAJN STEAM MSV-114 20.0 20 0 2394 PASS 20 20 19.B9 316 MAIN STEAM NGV41 750 0 750 0 2394 PASS 750 750 32G90 317 NfTROGEN 362.0 362.0 2394 PASS 362 362 3/17139 NGV41 317 NITROGEN l

VSW128 20 0 20 0 6384 PASS 20 20 10/19,91

)

318 MAIN STEAM  !

i MSV-128 20 0 20 0 6384 PASS 20 20 3'2G90 318 MA!N STEAM PASS 20 20 3 , % 18 9 MS%128 20 0 20 0 6384 318 MIAN STEAM 20 0 20.0 2394 PASS 20 20 10/18/91 MSV-132 320 MAJN STEAM MSV-132 1015.0 1015.0 2394 PASS 1015 1015 323/90 i 320 MA!N STEAM 312.0 312.0 2394 PASS 312 312 39/B9 MS%132 320 MAfN STEAM .

649 0 790 0 3192 PASG 649 790 11/1/91 -l DHV-93 3192 PASS DHV-91 329 DECAY HEAT l PASS DH W91 20 0 20 0 3192 PASS 20 20 3E90 20.0 3192 329 DECAY HEAT DH%93 20 0 l 2.0 20 0 3192 PASS 20 20 4/3 B9 DHV-93 20 0 20 0 3192 PASS DHW91 329 DECAY HEAT PASS 24 24 4/5,90 7.8 1506 PASS WSV4 23.9 23 9 1596 332 CONT MONITORING WS%5 7.8 l 1596 FASS WSV4 20.0 20 0 1596 PASS 20 20 3/17f7 l 332 CONT MON!TORING WS%5 20 0 20 0 1

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, LEAK RATE TESTING TRENDING PROGRAM Page 5 '

FOR FLOR!DA POWER CORPORATION - CRYSTAL RIVER UN:T3 (2ND INTERVAQ TYPE C LLRT (valves, flanges) INBOARD ISOLATION VALVES (Leakage in secm) OUTBOARD ISOLATION VALVES (Leakage in seem) ~ PENETRATION l PATH LEAKAGE (socm}

PENETT4AT10N SYSTEM VALVE # ' LEAKAGE ~ . ACTION STATUS VALVE # . L8:AKAGE ACTION STATUS AS 'AS ACTUAL AS . .

AS .VALUE AS AS VALUE FObHD LEFT DATE FOUND / LEFT FOUND / LEFT VALUE VALUE' 333 MAKE UP MUV-40 2200 20,0 3900 PASS MUV-49 1976.0 1976.0 3990 PASS 333 MAKE UP MUV41 2340.0 1860.0 3990 PASS 333 MAKE UP HUV-505 353.0 - 23.8 4788 PASS 2913 1976 574f30 l 333 MAKE UP MUV-40 160.0 175 3 3900 PASS MUV-49 274.0 902 3990 PASS 333 MAKE UP MUV-41 100.0 256.0 3990 PASS 333- MAKE UP MUV-505 1857,0 1857.0 4788 PASS 2117 2288 5/1G159 339 WASTE DtSPOSAL WDV-3 1825 0 1178.0 6384 PASS WDV-4 152.4 152.4 6384 PASS 1825 1178 6/7/90 339 WASTE O!SPOSAL WDV-3 2190.0 2190.0 6384 PASS WDV-4 680.0 680.0 6384 PASS 2190 2190 3,71/89 347 SPENT FUEL SFV-18 15960 PASS SFV-19 13 6 13 6 15960 PASS 14 14 3,78,90 347 SPENT FUEL SFV-18 62.7 62 7 15960 PASS SFV-19 83.7 83.7 15960 PASS 84 84 3/11/89 349 WASTE DISPOSAL WDV40 227.0 1083.0 3192 PASS WDV41 2340 2340 3192 PASS 234 1083 5/9,90 i

349 WASTE DISPOSAL WDV40 20 0 20 0 3192 PASS WDV41 20 0 20.0 3192 PASS 20 20 3 71/89 350 CORE FLOOD CFV-18 275.0 325.0 1596 PASS CFV-26 172.0 172.0 1S96 PASS 275 325 1 71/90 350 CORE FLOOD CFV-18 649.0 6490 1596 PASS CFV.26 1762 1762 1596 PASS 649 649 3'14K$9 351 CORE FLOOD CFV-15 413.0 548.0 1596 PASS CFV?3 431.0 431.0 2394 PASS 351 CORE FLOOD CFV-16 145.3 70 6 1596 PASS 558 619 3,71/90 351 CORE FLOOD CFV-15 20.0 20.0 1596 PASS JV-23 20 0 20.0 2394 PASS 351 CORE FLOOD CFV-16 20 0 20.0 1596 PASS 40 40 3/11/89 ,

352 CORE FLOOD CFV-11 435 0 20.0 1596 PASS CFV-42 640.0 20.0 1596 PASS 352 CORE rLOOD CFV-12 740 0 20.0 1596 PASS 1175 40 37G90 352 CORE FLOOD CFV-11 20.0 20 0 1596 PASS CFV-42 20.0 20 0 1596 PASS 352 CORE FLOOD CFV-12 20.0 - 20 O 1596 PASS 40 40 3/11/59 354 WASTE DtSPOSAL WDV-406 1130 0 237.0 2394 PASS WDV-405 1172.0 227.0 2394 PASS 1172 237 575,90 354 WASTE DtSPOSAL WDV-406 1574.0 1574.0 2394 PASS. WDV-405 749.0 749.0 2394 PASS 1574 1574 370rv3

LEAK R?<TE TESTING TRENDING PROGRAM Page 6 FOR FLORfDA POWER CORPORATION - CRYSTAL RVER UNfT 3 (2ND INTERVAL)

TYPE C LLRT (valves, flanges) INBOARD ISOLATION VALVES (Leak age in secm) OUTBOARD ISOLATION VALVES Aleef age in seem) PENETRATION '

. PATH LEAKAGE j (secm)

PENETRATION SYSTEM VALVE # LEAKAGE ' ACTON STATUS VALVE # LEAKAGE. ACmON  ; STATUS LAS AS ACTUAL AS' AS VALUE- AS  : AS 'VALUE FOUND .LEFT DATE ,

FOUND / LEFT FOUND / LEFT VALUE .VALUE-355 NfTROGEN NGV42 1670.0 1670.0 2394 PASS 1670 1670 3/2G90 355 NITROGEN NGV42 877.0 877 0 2394 PASS 877 877 3/17/89 356 CONT MONfTORNG WSV-1 16.0 16.0 1596 PASS WSV-2 15 4 15.4 1596 PASS 356 CONT MONITORtNG WSV44 16.1 16.1 798 PASS WSV-35 15.7 15.7 796 PASS 356 CONT MON!TORING WSV40 16 0 16.0 798 PASS WSV-31 15 6 15_6 798 PASS 356 CONT MONITORING WSV-38 15.7 15.7 798 PASS WSV49 15.8 15 8 798 PASS 64 64 3*26,90 356 CONT MONfTORING WSV-1 20.0 20.0 1596 PASS WSV-2 20.0 20.0 1596 PASS 356 CONT MONITORNG WSV44 20.0 20.0 798 PASS WSV-35 20.0 20.0 798 PASS 356 CONT MONITOR NG WSV-30 20.0 20.0 798 PASS WSV-31 20.0 20 0 798 PASS 3' 6 CONT MONITORING WSV-38 20.0 20.0 798 PASS WSV-39 20.0 20.0 798 PASS 80 80 3/16r%9 357 AIR HANDUNG AHV-1 B 978.0 710.0 2550 PASS AHV-1 A 978 710 11/13,91 357 A4R HANDUNG AHV-1 B 8660 978.0 2550 PASS AHV-1 A 866 973 11 A)4,91 357 AIR HANDUNG AHV-1 B 1317.0 2550 PASS AHV-1 A 1317 12/1&"J0 357 AJR HANDUNG AHV-1B 914.0 2550 PASS AH/-1A 914 12/12,90 357 AIR HANDUNG AHV-1B 1003.0 1031fs 2550 PASS AR/-1A 1003 1031 10/12,90 357 AIR HANDLING AHV-1 B 775.0 850.0 2550 PASS AHV-1 A 775 850 ' 6/1G90 357 AIR HANDUNG AHV-1B 8190 797.0 2500 PASS AHV-1 A 819 797 9f29/B9 357 AIR HANDLING AHV-1B 11430 2500 PASS AHV1A 1143 9/2/89 357 AtR HANDUNG AHV-1B 819 0 2500 PASS AHV-1 A 819 &27/89 357 AIR HANDUNG AHV-1B 593.0 2500 PASS AHV-1 A 593 7/3,29 357 AIR HANDUNG AHV-19 1 73.9 2500 PASS AHV-1 A 174 679.39 357 A!R HANDUNG AHV-1B 2010.0 938.0 2500 PASS AHV-1 A 2010 938 6/12/89 337 AIR HANDLING AH/-1B 2010.0 2500 PASS AHV-1A 2010 &*25/89 357 AIR HANDUNG AHV-1B 1017.0 2500 PASS AHV-1 A 1017 2127/89

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LEAK RATE TESTING TRENDING PROGRAM Page 7 -

FOR FLORIDA POWER CORPORATION - CRYSTAL RVER UNIT 3 C2ND INTERVAlj

. WPE C LLRT (valves, flanges) OUTBOARD L,0LATION VALVES (Leenage in ocem) l

• IN00ARO ISOLATION VALVES (Leekage in ocem) '

PENETRATION .

PATH LEAKAGE (occm) -

PENETRATION SYSTEM - VALVE # LEAKAGE ~ ' ACTION STATUS VALVE # ; LEAKAGE ACTION ' STATUS 'AS _ AS .. .

ACTUAL -

AS AS'- 'VALUE AS' AS/ . VALUE .. FOUND .LEFT t DATE i FOUNDi/ -LEFT FOUND / :LEFT VALUE- VALUE- '

366 INDUST. COOUNG CN-34 15.0 ' 15.0 3990 ' PASS 15 15 3/23,90 '

E36 INDUST. COOUNG CN-34 100.0 100.0 3990 PASS 100 100 "&299 -

I37 INDUST, COOUNG CNM - 650.0 650 0 3990 PASS- 650 '650 3'23.90 367 tNDUST. COOUNG - CN-35 326D 3260 '3990 PASS 326 326 3,299 ~

372 NTTROGEN NGV42 ' 37.0 37.0 1596 PASS 37 37 3,20,90 372 NfTROGEN NGV-62 167.4 167.4 2394 PASS 167 167 3/17/89 373 CORE FLOOD CFV-19 1472.0 236.0 1596 PASS CFV-25 190.4 190.4 '1596 PASS 1472 236' 3/21/90' 373 CORE FLOOD CFV-19 312.0 312 0 1596 PASS CFV-25 470 0 470.0 1596 ' PASS 470 470 3/1429' 374 WASTE DISPOSAL WDV-94 20.0 885.0 4786 PASS WDV-62 20.0 20.0 4786 PASS 20 885 3,%90 i

374 WASTE DISPOSAL WDV-94 20.0 20.0 4788 ' PASS WDV-62 255.0 2*5.0 4788' PASS 255 '255 3/18/89 '?

376 COtR MONITORING WSV-41 7.3 ' 7.3 796 PASS WSV-40 8.1 8.1 796 PASS I 376 CONT MONITORING WSV42 52 52 795 PASS WSV-43 7.0 7.0 799 PASS 15 15 ' 3/26/90 376 CONT MONITORING WSV-41 20.0 20.0 796 PASS WSV-40 20.0 20 0 798 PASS 376 CONT MONTTORING WSV-42 20,0 20.0 796 PASS WSV-13 20.0 20.0 798 PASS 40 40 3/17!89 '  ;

.t 377 MAKE UP MW-260 1596 PASS MW-253 20.0 20.0 1596 PASS 377 MAKE UP M W-261 1595 PASS 377 MAKE UP MW-259 1596 PASS 377 MAKE UP MW-258 1596 PASS 1451 1451 10/14/91 377 MAKE UP MW-260 146.7 1088.0 1596 PASS MUV-253 564.0 564.0 1596 PASS 377 MAKE UP MUV-2E1 20.0 194.7 1596 PASS 377 MAKE UP MW-259 2.0 20.0 1596 PASS

377 MAKE UP MW-258 122.4 147.8 1596 PASS 564 1451 5/490 377 MAKE UP MW-260 652. 20.0 1596 PA3S MW-253 126.0 126.0 1596 = PASS 377 MAKE UP MW-261 20.0 20.0 1596 PASS 377 MAKE UP MW-259 22.4- 22.4 1596 PASS I 377 MAKE UP MW-258 411.0 411.0 1596 PASS 519 473 3 30# 9

LEAK RATE TESTING TRENDING PROGRAM Page 8 FOR FLOR!DA POWER CORPORATION - CRYSTAL RVER UNIT 3 (2ND INTERVAQ TVPE C LLRT (valves, flanges) : . INBOARC WTON VEVES My b W OUTBOARD ISOLATION VALVES (Leakage b seem) PENETRATION PATH LEAKAGE M

PENETRATION SYSTEM VALVE #- . LEAKAGE ACTON STATUS VALVE # LEAKAGE ACTON STATUS AS AS ACTUR AS ..

AS VALUE AS ,

AS 'VALUE FOUND' LEFT- DATE FOUND.1 .LEFT FOUND / LEFT VALUE- VAWE 425 CHEM. ADDITION CAV-433 32.0 32.0 598 PASS CAV-435 30.0 30.0 598 PASS C25 CHEM. ADDmON CAV-434 . 250.0 250.0 598 PASS CAV436 250.0 250.0 598 PASS 282 282 342,90 G25 CHEM. ADDmON CAV-433 108.6 108.6 538 PASS CAV-435 106.8 106.8 598 PASS 425 CHEM. ADDmON CAV-434 109.9 109.9 598 PASS CAV-436 109.2 *092 598 PASS 21 9 219 3,%S9 427 MA!N STEAM MSV-130 605.0 605 0 4788 PASS 605 605 1C/17,91 G27 IJAd4 STEAM MSV-130 200 0 200.0 4788 PASS 200 200 3/1930 427 MAIN STEAM MSV-130 1062 1082 4788 PASS 106 106 3%29 423 MAIN STEAM MSV-148 1255.0 1255.0 4788 PASS 1255 1255 1W17/91 428 MAIN STEAM MSV-148 345.0 345.0 4788 PASS 345 345 3/19,90 428 MA!N STEAM MSV-148 882_0 882.0 4788 PASS 882 882 3r%B9 430 FIRE SERVICE FSV-262 1400.0 1400.0 6384 PASS FSV-261 1850.0 1850 0 6384 PASS 1850 1850 3,% 90 430 FIRE SERVICE FSV-262 25 4 25.4 6384 PASS FSV-261 40.5 4C.5 6384 PASS 40 40 3*2529 439 CHEM. ADDmON CAV-126 598 PASS CAV-2 760,0 210.0 1596 PASS 439 CHEM. ADDmON CAV-1 558 PASS CAV-431 20 0 20.0 598 PASS 439 CHEM. ADDITON CAV-3 598 PASS CAV-432 20 0 20.0 598 PASS 439 CHEM. ADDmON CAV-429 129.0 129.0 598 PASS 439 CHEM. ADDITON CAV-430 14.0 14.0 590 PASS 800 356 10/17,91 439 CHEM. ADDITON CAV-126 20.0 47.4 598 PASS CAV4 20.0 20.0 1595 PASS 439 CHEM. ADDmON CAV-1 20.0 98.4 598 PASS CAV-431 20 0 20.0 598 PASS C39 CHEM. ADDITON CAV-3 20.0 68.9 598 PASS CAV-432 20.0 20.0 598 PASS 439 CHEM. ADDmON CAV-429 48.0 48.0 598 PASS C39 CHEM. ADDmON CAV-430 260O 260.0 598 PASS 368 521 4/4/90 039 CHEM. ADDmON CAV-126 100.0 20.0 593 PASS CAV2 412 0 412.0 1596 PASS 039 CHEM. ADDITION CAV-1 1878 0 20.0 593 FAIL CAV431 1194 0 580.0 598 FAL 439 CHEM. ADDmON CAV4 2670 0 190.0 598 FAL CAV-432 10200.0 136.0 598 FAIL G39 CHEM. ADDmON CAV-429 100.0 100.0 599 PASS C39 CHEM. ADDITON CAV430 100.0 100.0 598 PASS 11806 1128 4/23/89

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LEAK RATE TESTING TRENUNG PROGRAM Page 1 FOR FLORtDA POWER CORPOPATION - CRYSTAL RNER UNIT 3 (2ND INTERVAQ TYPE B LLRT (Resilient sea's. gaskets, sealar:t compunds, expandable Mr m VALUES bellows and flexible seal assemblies)

PENETRATION DESCRIPTION AS FOUND STATUS _ AS- STATUS TESTTYPE ACCEPTANCE N3M - N LET ACTION VALUE (socm) DATE:

308 FUEL TRANGFER TUBE GASKET - 38 20 PASS 20 PASS PJLK 100 3/1/89 436 FUEL TRANSFER TUBE GASKET - 3A 20 PASS 20 PASS #4LK 100 3/1/89 120 SG CHEMCAL CLEANtNG GAEXETS 48 PASS 48 PASS P4LK 100 35 29 119 SG CHEMICAL CLEANrNG GASKETS 20 PASS 20 PASS INLK 100 T28/89 EHRS EQUIPMENT HATCH RESIUENT SEALS 212 PASS S PASS INLK 500 57329 RAX-2 EOutPMENT HATCH 10240 PASS 10240 PASS INLK fD721 574/89 RAX1 PERSONNEL HATCH 1940 PASS i940 PASS .NLX M 721 576,39 RAX-1 PERSONNFL HATCH 8500 PASS 8500 PASS #4LK 20721 11/1539 RAX-2 EQUIPMENT HATCH 1120 PASS 1120 PASS PJLK 20721 11/16/89 134 LOW VOLTAGE DC INSTRUMENT CONTROL RODS 2 PASS 2 PASS INLK 100 4/18/90 135 RB LIGHTS SMALL AC4)C MOTORS 2 PASS 2 PASS NJ 100 4/1&90 301 CRD POWER SUPPLY 20 PASS 20 PASS INLK 100 4/1&90 302 CRD POWER SUPPLY 20 PASS 20 PASS INLK 100 4/18,90 303 CRD POWER SUPPLY 20 PASS 20 PASS INLK 100 4/18,90 309 VENT FAN 3C 20 PASS 20 PASS '

fNLK 100 4/18,90 127 CMNE/ ELEVATOR POWETt SUPPLY 6 PASS 6 PASS N.K 100 4/19/90 130 MISC. INSTRUMENTATION 6 PASS 6 PASS INLK 100 4/19,90 133 MtSC. INSTRUMENTATION 5 Pt.SS 5 FASS P4LK 100 4/19.90 208 RCP-381 POWER SUPPLY 2 PASS 2 PASS INLK 100 4/19,90 209 RCP-381 POWER SUPPLY' 4 PASS 4 PASS INLK l 100 4/1990 210 RCP482 POWER SUPPLY 4 PASS 4 PASS RJLK 100 4/1990 211 RCP-382 POWER SUPPLY 4 PASS 4 PASS INLK 100 4/19,90

LEAK RATE TESTING TRENDING PROGRAM Py2 FOR FLOR!DA POWER CORPORATION - CRYSTAL RfVER UN!T 3 QND !NTERVAQ TVPE B LLRT (Resilient seals, gaskets, sealant compunds. expandab:e meRED VALUES bellows and flexible seal assembre)

PENETRATON DESCRIPTION ' AS FOUND STATUS . AS- . STATUS TEST TYPE ACCEPTANCE CR:TERIA ' ACTUAL LEFT ACTON VALUE isccm) DATE-212 LOW VOLTAGE DC WSTRUMENT CONTOL RODS - 4 PASS 4 PASS INLK 100 4/1980 213 LOW VOLTAGE DC INSTRUMENT CONTOL RODS 4 PASS 4 PASS INLK - 100 4/19/90 214 LOW VOLTAGE DC INSTRUMENT COtROL RODS .2 PASS 2 PASS INLK 100 4/19/90 215 LOW VOLTAGE DC INSTRUMENT CONTOL FODS 2 PASS 2- PASS INLK 100 4/19,90

.TD7 CRD POWER SUPPLY 20 PASS 20 PASS INLK 100 4/1R90 .

308 ES A-B COMTROL CIRCUfT 20 PASS 20 PASS INLK 100 J/19,90 101 PZR HEATER POWER SUPPLY 6 PASS 6 PAS *, INLK 100 AM90 102 PZR HEATER POWER SUPPLY 5 PASS 5 PASS INLK 100 ATQ90 103 PZR HEATER POWER SUPPLY 2 PASS 2 PASS INLK 100 47G90 104 E.S. *B* CON TROL CIRCtES 4 PASS 4 . PASS INLK 100 4/2a90 126 VENT FAN 33 3 PASS 3 PASS INLK 100 ATG90 128 THERMOCOUPLES 2 PASS i PASS INLK 100 4.?Q93 129 MISC, INSTRUMENTATION 2 PASS 2 PASS INLK 100 4/2G90 132 MISC INSTRUMENTATION 5 PASS S PASS INLK 100 42 90 401 RCP-3A2 POWER SUPPLY 2 PASS 2 PASS INLK 100 42 90 R&-3A2 POWER 'MY 4 402 PASS 4 PASS INLK 100 4/20,90 003 RCP-3A1 POWER SUPPLY 6 PASS 6 PASS INLK 100 47G90 l 404 RCP-3A1 POWER SUPPLY 2 PASS 2 PASS INLK 100 4/2Q90 405 INCORE INSMUMENTATON 20 PASS 20 PASS WLK 100 4,7Q90 407 (NCORE & OUT OR CORE INSTRUVENTATON 20 PASS 20 PASS sNLK 100 4/2G90 '

408 tN-CON COAX CABLES 20 PASS 20 PASS INLK 100 470/90 l 409 THERMOCOUPLES 20 PASS 20 PASS INLK 100 AT390

LEAK RATE TESTNG TRENDWG PROGRAM Page 3

' FOR FLOROA POWER COPPORATION - CRYSTAL RVER UNTT 3 (2ND WTERVAL) rr TYPE B LLRT (Resilient seals gaskets, sealant compunds, expandabie m ye bellows and f!axible seal assembres) l PENETRATION DESCRIPTION. AS FOUND STATUS. AS. STATUS TEST TYPE ' ACCEPTANCECRITERIA ACTUAL LEFT- ACTION VALUE (scem) ' DATE 410 ES *A* CONTROL CNa 20 PASS 20 PASS. PEK 100 473,90 411 ES 'A' CONTROL CIRCUlTS 20 PASS 20 PASS INLK 100 4 %90 412 VENT FAN 3A 20 PASS 20 PASS INLK 100 4'2G90 406 ELECTR! CAL PENETRATION 40 PASS 40 PASS INLK 100 A%90 413 THERMOCOUPLES 2 PASS 2 PASS INLK 100 4%90 RAX-1 PERSONNEL HATCH 8500 PASS 1042 PASS INLK 20721 6/12*90 RAX-2 EQ1PMENT HATCH ' ~

1120 ' PASS 12380 PASS INLK 20721 6/13,90 119 SG CHEMICAL CLEAN!N3 GASKETS 62 PASS 20 PASS INLK 100 6/1/90 120 SG CHEMICAL CLEANING GASKETS 87 PASS 27 PASS INLK 100 6/4,90 348 FUEL TRANSFER TUBE GASKET - 3B 15 PASS 20 PASS INLK 100 61590 436 FUEL TRANSFER TUBE GASKET - 3A 7 Pt.SS 20 PASS WLK 100 6/BM)

EHRS EQUIPMENT HATCH RESIDENT SEALS 20 PASS 20 PASS WLK 500 6/12?10 RAX-2 EQU!PMENT HATCH 982 PASS 982 PASS INLK 20721 12t1G90

, RAX-1 PERSONNEL HATCH 1022 PASS 1022 PASS WLK 20721 12t11/90 Rr41 PERSONNEL HATCH 1404 PASS 1404 PASS INLK 20721 6/591 RAX-2 EQU PMENT HATCH 958 PASS 958 PASS INtA 20721 &Sr91 EHAS EQUtPMENT HATCH RES:LtENT SEALS 20 PASS 170 PASS INLK 500 11/A91 348 FUEL TRANSFER TUBE GASKET- 38 20 PASS 20 PASS INLK 100 10/1&91 436 FUEL TRANSFER TUBE GASKET- 3A 20 PASS 20 PASS !NLK 100 10/13/91 119 SG CHEMICAL CLEANING GASKETS  ! 20 PASS 20 PASS INLK 100 10/13,91 120 SG CHEMICAL CLEAN!NG GASKETS 20 PASS 20 PASS INLK 100 10/1191 EHRS EQUIPMENT HATCH RESILIENT SEALS 170 PASS 362 PASS INLK 500 11/13 91

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APPENDIX G SENSOR LOCATIONS AND VOLUME FRACTIONS L

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INSTALLED CONSTANTS O

RTD WEIGHT FACTORS RTD 1 WE!OHT FACTOR = 0.036600 RTD 2 WE!GHT FACTOR = 0.036800 PTD 3 WEIGHT FACTOR = 0.036700 RTD 4 WClGHT FACTOR = 0.013500 RTD 5 WE!GHT FACTOR = 0.050000 RTD 6 WEIGHT FACTOR = 0.050800 RTD 7 WEIGHT FACTOR = 0.050800 RTD 8 WE!GHT FACTOR = 0.016500 RTD 9 WEIGHT FACTOR = 0.054700 RTD 10 WEIGHT FACTOR = 0.054700 RTD 11 WEIGHT FACTOR = 0.063000 RTD 12 WElGHT FACTOR = 0.054700 RTD 13 WEIGHT FACTOR = 0.063700 RTD 14 WEIGHT FACTOR = 0.036100 RTD 15 WEIGHT FACTOR = 0.036100 RTD 16 WEIGHT FACTOR = 0.036200 RTD 17 WEIGHT FACTOR = 0.036100 RTD 18 WEIGHT FACTOR a O.036100 RTD 19 WEIGHT FACTOR = 0.036000 RTD 20 WEIGHT FACTOR = 0.036000 RTD 21 WEIGHT FACTOR = 0.016500 RTD 22 WEIGHT FACTOR = 0.013500 RTD 23 WEIGHT FACTOR = 0.054600 RTD 24 WEIGHT FACTOR = 0.054600 RTD WEIGHTING FACTOR SUM = 1.000000 PRESSURE GAUGE WElGHT FACTORS PRESS. GAUGE 4 1 WEIGHT FACTOR = 0.5000 PRESS. GAUGE # 2 WCIGHT FACTOR = 0.5000 PRESS. GAUGE WEIGHTING FACTOR SUM r 1.0000 DEW CELL WEIGHT FACTORS DEW CELL 1 WEIGHT FACTOR = 0.027000 DEW CELL 2 WEIGHT FACTOR = 0.110300 DEW CELL 3 WEIGHT FACTOR = 0.176400 DEW CELL 4 WEIGHT FACTOR = 0.033000 DEW CELL 5 WEIGHT FACTOR = 0.126700 DEW CELL 6 WEIGHT FACTOR = 0.126700 DEW CELL 7 WEIGHT FACTOR = 0.126600 DEW CELL 6 WEIGHT FACTOR = 0.091100 DEW CELL 9 WEIGHT FACTOR = 0.091100 DEW CELL 10 WEIGHT FACTOR = 0.091100 DEW CELL WE!GHTING FACTOR SUM = 1.000000 CONTAINMENT VOLUME = 2000000 y = 0.25