ML20248E874

VEPCO North Anna Power Station Unit 1 Jul 1989 Reactor Containment Integrated Leakage Rate Test

ML20248E874
Person / Time
Site:	North Anna
Issue date:	10/02/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
References
89-694, NUDOCS 8910060079
Download: ML20248E874 (84)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY q RICIIMOND, VIRGINIA 23261 October 2, 1989 U.S. Nuclear Regulatory Commission Serial No.89-694 Attention: Document Control Desk NL/JBL Washington, D.C.- 20555 Docket No. 50-338 License No. NPF-4 Gentlemen:

VIRGINIA ELECTEIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST

SUMMARY

TECHNICAL REPORT SUBMITTAL in accordance with 10 CFR 50, Appendix J, Paragraph V.B., Virginia Electric and Power Company submits the summary technical report entitled " Reactor Containment Building Integrated Leak Rate Test" concerning the most recent Type A, B, and C1ests for North Anna Unit 1.

Very truly yours,

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. L. Stewart enior Vice President - Power Attachment cc: U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. J. L. Caldwell NRC Senior Resident inspector North Anna Power Station 1

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Sectionn di" rq) iSection;1:- Introduction.

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. Seetion .-2 : ' Summary l Section'.3: : General and Technical rata-

'Section'4: ' Acceptance Criteriai

.'Section'5: Test Instrumentation >

o Section 6: ' Test Procedure 4

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Section 7: . Analysis.Metho'dsi

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ISection 8:~ Test Results.

Section 9: ' Local Leakage Rate Testing Section-10: References-1-

Appendices

-' Appendix: A: ' Computer Printouts

' Appendix B: Data Analysis ~Information Appendix,C: Graphs L:-

.-Appendix:D: Local Leakage Rate Testing Summary Appendix E: Local Leakage. Rate-Testing Failure Summary l

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X6 > 'SECTION 1

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INTRODUCTION u

. .. 'This report. has . been . prepared r.o provide a description and an' analysic. of ' the July .

I 1989' containment integrated leakage rate test (ILRT)' performed on ' Virginia ElectricL and' g . ' Power Company's (VEPCO's) North Anna Power Station, Unit 1 and to provide a summary of.the

local leakage rate tests,(LLRTs) performed on the Unit 1 ' containment ' penetrations since 4 thellast. Unit'.1 ILRT which was performed in September 1984.

Bechtel . Power Corporation (Containment Test Group) provided engineering consultation services to .VEPCO during the performance of the July 1989 Unit 1 ILRT.

This report is submitted as required by 10CFR50, Appendix J, Section V.B.

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SECTION 2 p

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SUMMARY

2.1 JULY 1989 CONTAINMENT INTEGRATED LEAKAGE RATE TEST (ILRT)

The final containment walkdown and penetration preparations were completed by 1315 on 06/29/89.

Pressurization began at 1324 on 6/29/89. During the pressurization, extensive leak checks were performed by visually inspecting potential leak paths such as the mechanical penetration area, the electrical penetration area, the personnel air lock, and the main steam lines. Leakage was found into the containment personnel air lock and through penetration 38, the containment sump pump discharge line. No other ,

significant leakage paths were discovered.

Pressurization was secured at 0056 on 06/30/89 at a containment pressure of 44.49 psig. The average containment dew point was unusually high and the individual dew point readings varied greatly between the containment dome and the containment baserent. The unusual dew points were due primarily to a Reactor Coolant system (RCS) leak. The cooling water supply to the containment recirculation air fans was changed from Service Water to the colder Chilled Water to reduce the high average containment dewpoint at 0700 on 07/01/89. The converging of the dewpoints and the decrease in average dewpoint due to the change in recirculation air fan cooling water supply cauced the containment pressure to decrease substantially. To increase the containment pressure and to add mass to containment, air was added from 1745 to 1813 on 07/01/89. The new containment pressure was 44.58 psig.

Because the dewpoints varied widely as a functicn of containment location and were transitory the indicated leakage rate was high. The indicated dew points from

(#') the five containment dew neint sensors eventually converged, and stabilization

\> requirements were met at 2345'on 07/01/89.

The ILRT portion of the procedure was successfully completed at 2345 on 07/02/89.

The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95% UCL mass point leakage rate was 0.026 weight %/24 hours.

The verification test was initiated at 0030 on 07/03/89. Because of the failure i of the lcminar flow elements used and the tripping of "A" containment air rceirculation fan, which upset the stability of the containment atmosphere, the verification test was reinitiated at 2330 on 07/03/89. The verification test was successfully completed at 0330 on 07/04/89 with a measured mass point composite leakage rate of 0.124 wt %/24 hrs, which was within the allowable range of 0.084 wt

%/24 hrs to 0.134 wt %/24 hrs. The containment was subsequently depressurized without incident.

2.2 LOCAL LEAKAGF RATE 'IESTS (LLRTs)

The local leakage rate tests (LLETs) of the containment isolatten valves and primary containment penetrations have been conducted since the performance of the last Unit 1 ILRT performed in September 1984 aa required by 10CFR50, Appendix J and the Station's Unit 1 Technical Specifications using appropriate Station procedures.

In accordance with 10CFR50, Appendix J Section V.B, the data for the Unit 1 LLRTs performed since September 1984 are summarized in Appendices D and E of this report.

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'SECTION 3'

'H CENERAL~AND TECHNICAL DATA

., l3.1'. GENERAL DATA

- 3.1.1 Owner: Virginia' Electric and Power Company Plant Name: North' Anna Power' Station Unit: ~

1' 1 1

- 3.1.2 Docket No.: 50-338 3.'1.3 Plant: Location: South' shore of Lake Anna Louisa' County, Virginia

- 3.1.4l' Containment

Description:

Reinforced concrete, steel lined,-

Operating at subatmospheric pressure 3.1~.S ILRT Completion Date: ' July'4, 1989 g

3.2 TECHNICAL DATA-0 3.2.1' Containment Net Free Velume:- 1.825 x 10 cubic feet

3. 2.1' Design Pressure: 45.0 psig 3.2.3 Design. Temperature: 280 *F 3.2.4 Calculated LOCA Peak Preasure: 44.1 psig 3.2.5 Calculated LOCA Peak Temperature: 280 'F

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'SECTION 4

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- ACCEPTANCE CRITERIA

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4.1 ILRT'-

4.1.1- Test Method: . Absolute Method

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'4.1.2 Data Analysis' Technique: 24 Hour Test Duration using the Mass Point Data Analysis Method:

4.1.3 Test Pressure: . _

44.1 psig - 45.0 psig.

4.1.4 Maximum Allowable Leakage 0.1 weight %/24 hours (304.4 SCFH)

. Rate:

4.1.5- Maximum Unit 1 Technical 0.075 we %/24 hours Specification Leikage Rate:

-4.2 VERIFICATION TEST

-4.2.1 Superimposed Leakage. 0.075 wt%/24 hrs - 0.125 wt%/24 hrs Rate Range:-

4.2.2 Required Agreement for. +/ .0.025 wt %/24 hours Composite Leakage. Rate:

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SECTION 5 L

- TEST INSTRUMENTATION

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5.1 INSTRUMENTATION SELECTION GUIDE (ISG) FORMULA. CALCULATION RESULTS i- -

' Appendix B provides the calculations of the ISG at the ILRT conditions..

T 5.2 MEASUREMENT' SYSTEM COMPONENT. DESCRIPTION For the -ILRT, eighteen resistance ~ temperature detectors (RTDs). 5 moisture temperature detectors (MTDs), and 2 absolute manometers were used.

In addition to the above instrumentation,.-two laminar flow elements were initially used for the verification test. .The flow elements were subsequently replaced with two rotameters.

-5.3 P?RFORMANCE OF INSTRUME'TATION -

All of the test instrumentation performed as required during the ILRT and 'the verification test- with the exception of the laminar flov elements. There were no other instrumentation failures.

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SECTION 6 p)

TEST PROCEDURE 6.1 INITIAL CONDITIONS FOR TESTING In accordance with the Dorth Anna Power Station Unit 1 ILRT procedurce, 1-PT-61.1 and 1-PT-61.1 A-L, the following initial conditions vere met and documented prior to commencing containment pressurization. The following is not an all inclusive listing of the precedural initlai conditions.

6.1.1 In accordance with 10CFR50, Appendix J.Section V.A. a general inspectior of the accessible interior and exterior surfaces of the containment structure was satisfactorily performed. I 6.1.2 All test instrumentation was calibrated within six monthn of the test.

6.1.3 All required system valve line-ups were conipleted, including the venting of possible pressurization sources.

6.1.4 All required local leakage rate testing was completed and reviewed by the Test Director, 6.1.5 A leak check of the absolute side of the leakane monitoring system was successfully completed.

6.1.6 The computers were operational and programmed for the ILLT.

6.1.7 A containment walkdown was performed to ensure ao pressurization sources were present in containment.

6.1.8 The containment air recirculation cyscem was operationo and maintaining ,

stable containment atmospheric conditions, 6.1 9 The official log of events was established.

6.1.10 Site meteorological data was recorded during the performance of the test.

6.2 PRESSURIZATION PHASE Pressurization of the containment was achieved by the use of seven diesel driven air compressors. Compressed air was piped through two aftercoolers in parallel and then through a refrigerant air dryer. Adequate instrumentation and controls were installed to maintain control of the compressed. air quality during the pressurization phase. The total capacity of the pressurization system was slightly in excess of 10,000 cubic feet per minute. Pressurization was initiated at 1324 on 06/29/89 and was secured at 0056 on 06/30/89 at a containment pressure of 44.49 psig.

Containment pressure was subocquently noted to be decreasing at a more rapid than expected rate. During pressurization, the pressure in the containment personnel air lock had been noted to be increasing, indicating leakage through the inner door of the air lock. Leakage was also observed through penetration 38, the containment sump pump discharge line. The containment personnel air lock was pressurized to 43 psig (approx. 1 pai below test pressure) to minimize effect on the calculated leakage rate due to the known inner door leak. A comprehensive search was made to identify additional leaks. No other significant leaks were identified. Due to the continued high indicated leakage rate and the absense of any significant leakage paths, the seals on the outer door of the personnel air lock wete lubricated, in accordance with normal maintenance practices. to identify possible leakage and/or to prevent leakage from occurring. No change in the indicated leakage rate was observed subsequent to the greasing of the containment personnel air lock outer door seals.

From results of the extensive leak checks, it was determined that the high indicated leakage rate was due to the elevated average dew point und the variance in r'

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the dew points between the containment dome and the containment basement. At 0700 on 07/01/89 the cooling water supply to the containtaent air recirculation fans was 6-  ; changed from Service Water to the colder Chilled Water to reduce the high containment 3

dew point which had resulted from a Reactor Coolant system (RCS) leak. As a result, the containment pressure dropped. Air was added from 1745 to 1813 on 07/01/89 to raise containment pressure to 44.58 psig. Subsequent to the additional pressurization, a new stabilization period was entered.

6.3 ILRT PHASE The various containment parameters were monitored by the Leakage Monitoring (LM) system instrumentation. The instrumentation consisted c,f eighteen resistance temperature detectors (RTDs). 5 moisture temperature detectors (MTDs), .and two absolute manometers.

It was determined that the previously high indicated leakege rate was caused by a substantial . dif ference in local dewpoints within the containment as evidenced by the variance in dew point readings. A complication to the variance in the dew points is that the locations and weighting of the containment temperature and dewpoint sensors do not appear to provide an accurate containment atmosphere model with such a variance in dew point readings. As containment atmospheric conditions became more stable, the dew points in the containment dome and the containment basement began 'to converge.

Homogeneous equilibrium conditions compensated for model inaccuracies. Stabilization requirements were met and the ILRT started at 2345 on 07/01/89.

I The ILRT portion of the procedure continued until 2345 on 07/02/89. During the l ten, ting period, the Chemistry department obtained a Residual Heat Removal (RHR) sample l which required the purging of 1.5 gallons from the RCS. This change in volume is insignificant. The levels of tanks and vessels located inside containment were ,

monitored hourly during the testing portion with no significant differences noted l except reduction in pressurizer level and increase in containment sump level. The ,

pressurizer level decrease was expected due to the the known RCS leak. A calculation i has been performed which verifies that that there was no resultant change in containtnent free volume. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 95% UCL mass point leakage rate was 0.026 weight

%/24 hours.

6.4 VERIFICATION PHASE The verification test was initiated a t' 0030 on 07/03/89. A 45 minute delay '

between the ILRT and the verification test existed due to difficulties obtaining leaktight connections in the superimposed flow tubing. Two laminar flow elements were I connected in parallel to that either could be used to measure the superimposed flow rate. The calculated composite leakage was indicating low. At 0554 on 07/03/89, the "A" containment air recirculation fan tripped. After the resultant transient, the calculated composite leakage was again indicating low. At 1230 on 07/03/89, a rotameter was used to check the laminar flow element. The rctameter reading was approximately 33% of the laminar flow element reading. The laminar flow elements were subsequently found to contain water. The verification test was reinitiated at 1445 on 07/03/09 using two rotameters in parallel. The calculated composite leakage rate was indicating high. A couple factors contributed to the high calculated composite O rase 2 ef 3 Section 6

t leakage rate. The containment atmosphere was continuing to recover from the transient caused by the tripping of the "A" containment recirculation fan. Also, the es backpressure .due to tubing on the discharge of the rotameter could not be accurately

('_) determined, and therefore, an accurate flow rate correction factor could not be determined.

Due to these difficulties, the verification test was reinitialized after resolving the problems described above. The final verification test was started at 2330 on 07/03/89 with the rotameters discharging directly -to atmosphere. The verification test was completed at 0330 on 07/04/89 with a measured mass point composite leakage rate of 0.124 wt %/24 hrs, which was within the allowable range of

.0.084 wt %/24 hrs to 0.134 wt %/24 hrs, l 6.5 DEPRESSURlZATION PHASE The containment was depressurized through a T-connection and ball valve installed in the temporary pressurization piping. The post containment walkdown revealed no significant deficiencies.

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l SECTION 7

- ANALYSIS METHODS Y/;

7.1 DATA ACQUISITION SYSTEM The data acquisition system used for the ILRT and the verification test, with exception of the rotameters, was the Unit 1 Westinghouse Prodae P250 plant computer.

Monitoring of the rotameters during the verification test was accomplished by local observation of the rotameters to ensure a constant flow rate.

The instantaneous P250 data was inputted at fifteen minute intervals to a personcl computer and processed by the Bechtel Power Corporation's ILRT computer program. This program verifies the validity of the data, weights the RTD and MTD readings, and performs the necessary leakage rate calculations. The inputting of data continued from the start of pressurization until the end of the verification test.

Instantaneous values of the ILRT instruments were printed at 15 minute intervals during the test period using the P250 digital trend functica on the operator's console.

7.2 ABSOLUTE METHOD OF MAS 5 POINT ANALYSIF The absolute method of mass point analysis consists of calculating air masses within the containment structure over the test peried using pressure, temperature, and air moisture inputs. The air masses are corruted using the ideal gas law as follows:

M= 144V (P-Py )

,-s nJ RT where: M = containment air mass, lbm P = total containment pressure, paia P = containment vapor pressure, psia R = universal gas constant for air, 53.35 ft-lbf /lb,-R T = average containment temperature, R 6 3 V = containment volume, 1.825 x 10 ft ,

The leakage rate is then determined by plotting the containment air mass as a function of time, using a least squares fit to determine the slope.

A 95-percent confidence interval is calculated using a Student's t distribution.

The sum of the leakage rate and the 95-percent confidence interval is the UCL.

Appendix B provides further description of the program.

7.3 STATISTICAL EVALUATION Appendices A and B provide the necessary information for the statistical evaluation of the data.

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SECTION 8 fl - TEST RESULTS Q.)

8.1 ILRT Measured Leakage Rate: 0.024 weight %/24 hours UCL: 0.026 weight %/24 hours As Found ._ _.

As Left Leakage Savings: 0.034 wt %/24 hrs 0.002 wt %/24 hrs Type C Penalties: 0.003 wt %/24 hrs 0.003 vt %/24 hrs Total Reported Leakage: 0.063 wt %/24 hrs 0.031 wt %/24 hrs 3.1.1 Leakage Savings Description The leakage savings for the As Found ILRT is the difference in the minimum pathway leakage (MPL) from the prenaintenance Type C values recorded at the start of the 1989 Unit 1 outage and MPL from the Type C values recorded after maintenance and prior to the Unit 1 July 1989 ILRT. The leakage savings for the As Left ILRT is the difference in the MPL from the Type C values recorded at the time of the Unit 1 July 1989 ILRT and the MPL from the Type C values recorded after post ILRT maintenance and prior to the July 1989 Unit 1 Cycle 8 start-up.

A discussion of the personne3 air lock leakage savings is warranted to clarify the reported values. Prior to the ILRT, the most recent recorded Type B leakage for the air lock was 10.0 SCFH. The minimum pathway leakage for this value is 5.0 SCFH.

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'-- In order to appropriately account for the pressurizing of the air lock to 43 psig for the ILRT and for the gressing of the outer door seals, the "As Found" leakage savings is to be taken ar 5.0 SCFH. Although the pressurizing of the personnel air lock had no effect on the ILRT levkage and no change in leakage rate was observed after the greasing of the cuter door seals, it is assumed that these events caused the air lock minimum pathway leakage to go to 0 SCFH. Therefore, the recorded "As Found" leakage savings is 5.0 SCFH.

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ILRT As Found Leakage Savings Dutage As ILRT Leakage

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Penetration Number Found MPL (SCFH)

MPL (SCFH)

Savings (SCFH) 24 0.15 0 0.15 40 3.5 0 3.5 67 1.8 0 1.8 71 0.7 0 0.7 79 27.53 4.6 22.93 80 2.34 0 2.34 81 3.3 0 3.3 82 7.7 0 7.7 83 14.0 0 14.0 84 2.34 0 2.34 85 15.0 0 15.0 36 7.7 0 7.7 90 0.50 0.475 0.025 113 17.0 0.3 16.7 Equipment 0.7 0 0.7 Hatch Personnel 5.0 0 5.0 Air Lock Electrical 2.915 2.645 0.27 r Penetrations k_ Total Leakage Savings: 104.16 SCFH ILRT As Left Leakage Savings ILRT Outage As Leakage Penetration MPL Left MPL Savings Number (SCFH) (SCFH) (SCFH) 38 0 0.53 0.53 80 0 2.34 2.34 Personnel 0 3.15 3.15 Air Lock Total Leakage Savings: 6.02 SCFH

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= Calculation; of. As' Found Leakage Savings: 104.16'SCFH x 0.1 wt %/24 hrs.-

lp L'd L-  ; ~

304.4 SCFH

= O.034~wt %/24 hrs

Calculation of Ae Left Leakage Savings: _6.02-SCFH x 0.1'wt %/24 hrs 304.4-SCFH

= 0.002 wt %/24' hrs-8.1.2  : Type C: Penalties Description A minimum pathway leakage (MPL) Type C penalty was applied 'for all. containment.'

piping penetrations whose containment isolation valves were.not' exposed to the ILRT-pressure. . The listing of the applicable pene': rations . and the associated MPLs are-given below..

Penetration MPL (SCFH) Penetration- MPL (SCFH) 1 0 56D 0 2' O 57A 0-

'O 4 60 0 5 0. 61 0

.7 0' 62 0 8 0 63- 0 9 0 64 0

h 10 0 66~ 'O sb/' 11- 0 67 0 -I 12 .0 70 0 13 0 71 0 14- 0 79 4.6 15- 0 80' 0 16 0 81 0

17. 0 82 0 18 0 83 0 19 0 84 0 20 0 85 0 22 0 86 0 24 0 92 0 25 0.05 93 0 26 0.875 94 0.5 27 1.0 97A 0 28 0 97B 0 31 0 97C 0 1

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' Penetration! ' MPL~' (SCFH) - Penetration MPL-(SCFH) 4 39 -) 0- 98A 0

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0 103.

98B- 0 0

46~ ~0 a105B 0 e.' SSD- .0 '105C 0-

-56A~ 0 105D 0 f; 156By ,0 109- 0 NT- 56C 0.25 113 -0.3 114 0

'Totalr .7.575 SCFH-s Calculation'.of. Type C Penalties: 7.575'SCFH' 'x'O.1 wt %/24 hrs-304.4 SCFH-

= 0.003 wt'%/24h'rs

.'.2 8 VERIFICATION TFST--

The' calculated superimposed leakage rate (Lg) was

'4.33 scfm x 60 min /hr x 0.1 we %/24 hrs = 0.0853.wt %/24. hrs.

304.4 SCFH

'The measured. leakage rate.(L,,) was 0.024 wt'%/24 hrs.

The limits for the composite leakage rate (L )c ""#**

'L~ + L .+ 0.25L' = 0.084 wt %/24 hrs L*"

+-L" - 0.25L*, = 0.134 wt %/24 hrs.

The measured' composite leakage' rate'(Lc ) was 0.124 wt %/24 hrs.

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SECTION 9 1

LOCAL LEAKAGE RATE TESTING 0-l I

Appendix D contains a summcry of all of the LLRTs performed on Unit I components since the last Unit 1 ILRT which was prformed in September 1984.

Appendix E contains information on all of the LLRTs performed on Unit I components since September 1984 that had leakages greater *.he 0.60L,.

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SECTION 10

- REFERENCES

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G 10.1 North Anna Power Statior;, Unit 1, Periodic Test procedures:

1-PT- 61.1 Reactor Containment Integrated Leak Rate Test 1-PT-61.1A Containment Structural Inspection 1-PT-61.1B ILRT Instrumentation Set-up and Calibration PT-61.1C Cooling Water Hookups for ILRT Air Pressurization Equipment 1-PT-61.1D Leak Check of Absolute Side of LM System 1-PT-61.1F Leak Check of Steam Generators 1-PT-61.1G Checkout of ILRT Air Pr ,urization Equipment 1-PT-61.1H ILRT Penetration Valve Lineups 1-PT-61.11 Secondary System Instrumentation Integrity for ILRT 1-PT-61.1J Venting of Containment for ILRT 1-PT-61.1K Mechanical ILRT Set-up of Containment Equipment 1-PT-61.1L Flooding and Venting of ILRT Containment Piping Penetrations 10.2 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled' Power Reactors 10.3 ANSI N45.4-1972, American National Standard, Leakage Rate Testing of Containment Structures for Nuclear Reactors 10.4 ANSI 56.8-1987. American National Standard, Containment System leakage Testing Requirements 10.5 Bechtel Power Corporation, Bechtel ILRT Program, Version 4.0, 10/14/88

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' APPENDIX A COMPUTER PRINTOUTS O

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NORTH ANNA POWER STATION - UNIT'l-

SUMMARY

. DATA

'ALMAX~ =- .100 VOLUME = 1825000~.

VRATET = .104- VRATEM :. 109 TIME DATE TEMP PRESSURE. VPRS' VOLUMEL . AIRMASS-

'1815 701 546.201 58.7708' .4243 1825000.0 .530029.5 L ~1830 .701 546.170 58.7595 .4235. 1825000.0 529957.9 1845701' 546.110 58.7514 .4249 1825000.0 529942.9 1900 701 '546.083 58.7481 .4237l 1P25000.0- 529939.3-1915 .701 1546.'060 58~.7452 .4233 1825000.0 529934.6

, 1930 701' 546.0351 58.7437- .4224- 1825000.0. 529945.4-1945 701 546.022 58.7408 .4235' 1825000.0 '529933.1-2000' 701- 546.011 58.7405 .4221- 1825000.0 529940.7'

.2015 701 545.981- 58.7397. .4213' 1825000.0 529962.7 2030- 701 545.970 58.7403 .4194 1825000.0 529978.8

2045 701- 545.976 58.7388 .4199 1825000.0 !529959.9 2100 -701. .545.963 58.7386- .4194 1825000.0 529969.9 'i 2115 '701 545.973- 58.7369 .4203 L1825000.0 529945.6 2130 701 545.973 58.7364 .4204 1825000.0. 529941.1

.2145~ 701 545;966- '58.7368' .4196 '1825000.0 .529950.0 2200 701 545.962 58.7362 .4197 1825000.0 529949.3 2215. 701. 545.939 58.7359 .4196 '1825000.0 529969.0.

-2230 701- 545.981 58.7325' .4225 -1825000.0 529898.2-2245 701 545.987 58.7330 .4219 1825000.0 529896.2 2300 701 545.980 58.7328 .4219 1825000.0 529901.6.

2315 701-- 545.977 58.7335' .4210' 1825000.0 529909.8 Q- '

2330 701'. 545.962 58.7316 .4225 1825000.0 529907.9

'2345 701 545.973 58.7334 .4205 1825000.0 529913.6-l Page 1 of 6 Appendix

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NORTH ANNA POWER STATION - UNIT 1 (7

SUMMARY

DATA u)

ALMAX = .100 VOLUME = 1825000.

VRATET = .104 VRATEM = .109 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS 2345 701 545.973 58.7334 .4205 1825000.0 529913.6 0 702 545.969 58.7332 .4206 1825000.0 529914.6 15 702 545.973 58.7322 .4214 1825000.0 529903.1 30 702 545.974 58.7341 .4192 1825000.0 529919.4 45 702 540.002 58.7320 .4210 1825000.0 529873.3 100 702 545.989 58.7332 .4200 1825000.0 529896.3 115 702 545.986 58.7325 .4206 1825000.0 529892.8 130 702 545.989 58.7332 .4198 1825000.0 529895.6 145 702 546.006 58.7331 .4196 1E25000.0 529878.1 200 702 546.023 58.7318 .4206 1825000.0 529850.5 215 702 545.983 58.7290 .4180 1825000.0 529864.5 239 702 545.939 58.7262 .4185 1825000.0 52999?. 8 245 702 545.931 58.7238 .4194 1825000.0 529868.0 300 702 545.924 58.7225 .4197 1825000.0 529862.8 315 702 545.921 56.7221 .4192 1625000.0 529862.8 330 702 645.907 58.7212 .4193 1825000.0 529867.2 345 702 545.914 58.7209 .4187 1825000.0 529858.6 400 702 545.917 58.7212 .4177 1825000.0 529857.8 415 702 545.913 58.7197 .4184 1825000.0 529847.9 430 702 545.914 58.7196 .4178 1825000.0 529845.9

(')

445 702 500 702 545.897 545.907 58.7182 58.7193

.4188

.4169 1825000.0 1825000.0 529850.4 529849.7 515 702 545.902 58.7176 .4179 1825000.0 529839.3 530 702 545.877 58.7194 .4157 1825000.0 529880.5 545 702 545.888 58.7174 .4173 1825000.0 529851.7 600 702 545.888 58.7177 .4163 1825000.0 529854.4 615 702 545.888 58.7161 .4174 1825000.0 529839.9 630 702 545.887 58.7172 .4159 1825000.0 529851.1 S45 702 545.902 58.71S8 .4166 1825000.0 529823.4 700 702 545.891 58.7173 .4150 1825000.0 529847.3 715 702 545.896 58.7191 .4127 1825000.0 529858.5 730 702 545.873 58.7171 .4141 1825000.0 529863.4 745 702 545.695 58.7162 .4147 1825000.0 529833.6 800 702 545.898 58.7146 .4157 1825000.0 529816.4 815 702 545.899 58.7158 .4140 1825000.0 529826.3 830 702 545.871 5d.7154 .4140 1825000.0 529850.7 845 702 545.848 58.7140 .4148 1825000.0 529859.8 900 702 545.888 58.7120 .4164 1825000.0 529802.6 i 915 702 545.838 58.7164 .4128 1825000.0 529882.3 L 930 702 545.886 58.7143 .4137 1825000.0 529825.6 945 702 545.863 58.7144 .4131 1825000.0 529848.6 1000 702 545.881 58.7126 .4148 1825000.0 529814.6 1015 702 545.864 58.7133 .4136 1825000.0 529838.2 1030 702 545.865 58.7122 .4143 1825000.0 529826.9 1045 702 545.876 58.7129 .4133 1825000.0 529822.6

<~ 1100 702 545.855 58.7124 .4134 1825000.0 529838.6

(_) 1115 702 545.857 58.7089 .4167 1825000.0 529804.4

. 1130 702 545.844 58.7115 .4138 1825000,0 529841.3 l 1145 702 546.842 58.7136 .4113 1825000.0 529862.0

[ Page 2 of 6 Appendix A

~7 E _ _ _ _ _ _ _ _ _ _

NORTH ANNA POWER STATION - UNIT 1

~

SUMMARY

DATA ALMAX = .300 VOLUME = 1825000.

VRATET = .104 VRATEM = .109 TIME DATF TEMP PRESSURE VPRS VOLUME AIRMASS 1200 702 545.840 58.7124 .4123 1825000.0 529853.1 1215 702 545.860 58.7096 .4150 1825000.0 529807.8 1200 702 545.855 58.7124 .4119 1825000.0 529838.6 1308 702 545.845 58.7071 .4164 1825000.0 529800.9 1315 702 545.846 58.7067 .4166 1825000.0 529795.6 1330 702 545.828 58.7086 .4143 1825000.0 529830.1

.1345 702 545.831 58.7103 .4125 1825000.0 529842.5 1400 702 545.914 58.7054 .4172 1825000.0 529717.8 1415 702 545.840 58.7070 .4152 1825000.0 529804.3 1430 702 545.824 58.7087 .4132 1825000.0 529834.8 1445 702 545.843 58.7089 .4127 1825000.0 529818.3 1600 702 545.850 58.7083 .4133 1825000.0 529806.1 1515 702 545.848 58.7066 .4150 1825000.0 529792.2 1530 702 545.844 58.7054 .4157 1825000.0 529785.8 1545 702 545.825 58.7084 .4129 1825000.0 529831.6 1600 702 545.846 58.7064 .4150 1825000.0 529792.4 1615 702 545.831 58.7056 .4160 1825000.0 529800.4 1630 702 545.846 58.7072' .4147 1825000.0 529800.1 1645 702 545.844 58.7083 .4137 1825000.0 529812.3 1700 702 545.843 58.7092 .4128 1825000.0 529821.6 1715 702 545.852 58.7077 .4145 1825000.0 529798.4

(]) 1730 702 545.856 58.7078 .4146 1825000.0 529796.4 1745 702 545.854 58.7080 .4147 1825000.0 529799.6 1800 702 545.851 58.7087 .4138 1825000.0 529808.6 l 1815 702 545.864 58.7090 .4133 1825000.0 529799.7 1830 702 545.850 58.7070 .4155 1825000.0 529793.8 1845 702 545.858 58.7092 .4133 1825000.0 529806.9 1900 702 545.876 58.7055 .4167 1825000.0 529756.6 1915 702 545.862 58.7084 .4139 1825000.0 529795.3 1930 702 545.876 58.7059 .4162 1825000.0 529759.9 1945 702 545.873 58.7074 .4148 1825000.0 529775.3 2000 702 545.883 58.7073 .4147 1825000.0 529765.2 2015 702 545.851 58.7060 .4162 1825000.0 529784.3 2030 702 545,857 58.7068 .4157 1825000.0 529785.3 2045 702 545.850 58.7065 .4160 1825000.0 529782.3 2100 702 545.888 58.7079 .4146 1825000.0 529765.9 2115 702 545.851 58.7091 .4131 1825000.0 529812.3 2130 702 545.873 58.7061 .4163 1825000,0 529764.0 i 2145 702 545.891 58.7067 .4159 1825000.0 529752.6 2200 702 545.881 58.7077 .4152 1825000.0 529771.4 2215 702 545.882 58.7047 .4181 1825000.0 529742.6 2230 702 545.874 58.7076 .4153 1825000.0 529776.7  !

2245 702 545.869 58.7063 .4167 1825000.0 529769.9 2300 702 545.890 58.7076 .4160 1825000.0 529761.1 2315 702 545.879 58.7099 .4140 1825000.0 529792.4 2330 702 545.872 58.7084 .4154 1825000.0 529786.1

(~)3

(_ 2345 702 545.891 58.7084 .4158 1825000.0 529766.8 Page 3 of 6 Appendix ,A

t NORTH ANNA POWER STATION - UNIT 1

(

SUMMARY

DATA ALMAX = .100 VOLUME = 1825000.

VRATET = .104 VRATEM = .109 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS 0 703 545.896 58.7106 .4140 1825000.0 529782.1 15 703 545.911 58.7091 .4154 1825000.0 529754.6 30 703 545.917 58.7074 .4169 1825000.0 529733.7 45 703 545.919 58.7094 .4151 1825000.,0 529749.3 100 703 545.927 58.7071 .4178 1825000.0 529720.6 115 703 545.934 58.7082 .4168 1825000.0 529723.3 130 703 545.929 58.7088 .4157 1825000.0 529734.3 145 703 545.937 58.7067 .4178 1825000.0 529707.9 200 703 545.929 58.7082 .4164 1825000.0 529728.5 215 703 545.943 58.7077 .4169 1825000.0 529710.5 .

230 703 545.987 58.7094 .4151 1825000.0 529683.9 l 245 703 54L.965 58.7119 .4126 1825000.0 529727.7 300 703 54f.958 58.7056 .4191 1825000.0 529676.5 315 703 545.945 58.7098 .4149 1825000.0 529727.3 330 703 545.983 58.7084 .4162 182500040 529678.5 345 703 545.996 58.7082 .4164 1825000.0 529663.5 400 703 545.985 58.7076 .4170 1825000.0 529668.3 415 703 545.989 58.7075' .4171 1825000.0 529663.8 430 703 545.976 58.7107 .4136 1825000.0 529705.0 445 703 545.997 58.7054 .4187 1825000.0 529637.5 f~)

500 703 545.987 58.7098 .4146 1825000.0 529687.0 515 703 546.021 58.7081 .4164 1825000.0 529638.4 530 703 546.006 58.7099 .4144 1825000.0 529669.6 545 703 545.997 58.7074 .4168 1825000.0 529655.3 600 703 545.911 58.7001 .4120 1825000.0 529672.6 615 703 545.832 58.6892 .4138 1825000.0 529651.4 630 703 545.852 58.6821 .4161 1825000.0 529567.5 645 703 545.836 58.6812 .4134 1825000.0 529575.3 700 703 545.828 58.6773 .4140 1825000.0 529547.7 715 703 545.797 58.6763 .4123 1825000.0 529569.3 i 730 703 545.827 58.6716 .4143 1825000.0 529497.6 i 745 703 545.815 58.6711 .4122 1825000.0 529504.5 800 703 545.808 58.6679 .4131 1825000.0 529482.8 815 703 545.796 58.6650 .4135 1825000.0 529467.8 830 703 546.746 58.6658 .4105 1825000.0 529524.2 845 703 545.762 58.6620 .4123 1825000.0 529474.3 900 703 545.719 58.6608 .4117 1825000.G 529504.7 915 703 545.724 58.6581 .4125 1825000.0 529475.1 j 930 703 545.721 58.6563 .4126 1825000.0 529462.1 '

945 703 545.718 58.6560 .4113 1825000.0 529462.6 1000 703 545.696 58.6533 .4126 1825000.0 529459.1 l 58.6536 529474.6 1015 703 545.683 .41D7 1825000.0 1030 703 545.678 58.6521 .4107 1826000.0 529466.1 1045 703 545.667 58.6507 .4107 1825000.0 529463.7 1100 703 545.660 58.6496 .4103 1825000.0 529461.0 r~ 1115 703 545.652 58.6481 .4106 1825000.0 529454.9

( 1130 703 545.649 58.6466 .4104 1325000.0 529444.0 1145 703 545.626 58.6460 .4097 1825000.0 529461.1 Page 4 of 6 Appendix A

NORTH ANNA POWER STATION - UNIT 1

SUMMARY

DATA

(~)'

n-ALMAX = .100 VOLUME = 1825000.

VRATET = .104 VRATEM = .109 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS 1200 703 545.614 58.6453 .4092 1825000.0 529466.2 1215 703 545.639 58.6428 .4103 1825000.0 529419.7 1230 703 545.011 58.6422 .4097 1825000.0 529441.4 1245 7C3 545.598 58.6403 .4103 1925000.0 529437.6 1300 703 545.574 58.8400 .4093 1925000.0 529457.9 1315 703 545.583 58.6362 .4116 1825000.0 529414.6 1345 703 545.558 58.6356 .4098 1825000.0 529433.8 1400 703 545.549 58.6367 .4076 1825000.0 529452.1 2415 703 545.530 58.6348 .4083 1825000.0 529452.8 1430 703 545.532 58.6325 .4093 1825000.0 529430.4 1445 703 545.510 58.6324 .4080 1825000.0 520451.0 1500 703 545.495 58.6307 .4079 1825000.0 529449.9 :

1515 703 545.515 58.6282 .4086 1825000.0 529408.6 ?

1530 703 545.484 58.6263 .4089 1825000.0 529421.6 1545 703 545.465 58.6256 .4078 1825000.0 529433.8 1600 703 545.464 58.6229 .4088 1825000.0 529410.1 1615 703 545.456 58.6217, .4084 1825000.0 529407.3 1630 703 545.476 58.6196 .4089 1825000.0 529368.3 1645 703 545.441 58.6185 .4082 1825030.0 529392.8

~ 1700 703 545.442 58.6166 .4085 18250C0.0 529373.9

(,s) 1715 703 545.414 58.6162 .4073 1825000.0 529398.1 1730 703 545.412 58.6133 .4084 1825000.0 529373.8 1745 703 545.413 58.6107 .4094 1825000.0 529349.5 1800 703 545.395 58.6122 .4063 18250CO.0 529379.9 1815 703 545.378 58.6100 .4067 18250C'0. 0 529377.1 1830 703 545.378 58.6076 .4073 18250CO.0 529355.1 1845 703 545.348 58.6066 .4067 1820000.0 529375.9 1G00 703 545.333 58.6058 .4059 1825000.0 529383.2 1915 703 545.324 56.6037 .4064 1825000.0 529372.2 1930 703 545.343 58.6020 .4067 1325000.0 529339.1 1945 703 545.344 58.6025 .4047 1825000.0 529341.8

! 2000 703 545.315 58.5991 .4066 1825000.0 529339.3 2015 703 545.315 58.5979 .4064 1825000.0 529328.9 2030 703 545.329 58.5955 .4074 1825000.0 529294.1 2045 703 545.308 58.5959 .4055 1825000.0 529317.8 2100 703 545.298 58.5937 .4061 1025000.0 529307.3 2115 703 545.306 58.5915 .4066 1825000.0 529280.1 2130 703 545.277 58.5905 .4063 1825000.0 529298.6 2145 703 545.284 58.5889 .4065 1825000.0 529277.8 2200 703 545.286 58.5868 .4072 1825000.0 529256.9 2215 703 545.255 58.5882 .4045 1825000.0 529298.9 2230 703 545.253 58.5868 .4046 1825000.0 529288.3 2245 703 545.266 58.5818 .4084 1825000.0 529231.5 2300 703 545.273 56.5833 .4056 1825000.0 52?238.6 2315 703 545.252 58.5823 .4054 1825000.0 529248.2 r~s 2330 703 545.229 58.5797 .4068 1825000..O 529248.8

(-) 2345 703 545.217 58.5812 .4042 1825000.0 529272.7 Page 5 of 6 Appendix A

-9

1 L P l

l' >

NORTH ANNA POWER STATION - UNIT 1

SUMMARY

DATA ALMAX = .100 VOLUME = 1825000.

VRATET = .104 'VRATEM-= .109 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS O 704 545.250 58.5787 .4056 1825000.0 529218.9

15. 704 545.230 58.5790 .4044 1825000.0 529240.3 30 704 545'.233 58.5775 .4048 1825000.0 529224.6

-45 704 545.234 58.5768 .4045 1825000.0 529216.3 100- 704- 545.238 58.5745 -.4055 1825000.0 529192.8 115 704 545.215 58.5740 .4051 1825000.0 529209.7-130 704 545.217 58.5738 .4040 1825000.0 529206.7 145 704 545.212 58.5712 .4057 1825000,0 529187.4 200 704 545.188 58.5710 .4049 1825000.0 529209.4 215 704 545.208 58.5703 .4045 1825000.0 529183.3 230 704 545.209 58.5696 .4043 1825000.0 529176.1

.245~ 704 545.214 58.5678 .4051 1825000.0 529155.3 300 704 545.211 58.5662 .4059 1825000.0 529143.5 315- 704- 545.195 58.5676 .4034 1825000.0 529171.5 330 704 545.201 58.5640 .4061 1825000.0 529132.7-O O

Page 6 of 6 Appendix A WCW 'trry j

APPENDIX B DATA ANALYSIS INFORMATION

'( ) SECTION B.1: Containment Temperature Stabilization Criteria SECTION B.2: Instrument Selection Guide (ISG) Calculation SECTION B.3: Description of Bechte Mass Point Analysis: Calculations-SECTION B.4: ILRT Mass Point Data Analysis SECTION B.5: ILRT Data Trend Report SECTION B.6: Verification' Test Mass Point Data Analysis l

l l O l

l l

01 SECTION B.1: Containment Temperature Stabilization Criteria

, I i;

3 LO O

1 ._ NORTH ANNA POWER STATION - UNIT 1 TEMPERATURE STABILIZATION FROM A-STARTING TIME AND DATE OF: 1815 701 1989 TIME- TEMP ANSI BN-TOP-1 MS-021-5 (HOURS) f*R) AVE A T. AVE AT DIFF AVE A T AVE 8T (4 HRS) (1HR) (2 HRS) (2 HRS)

.00 546.201

.25 546.170

.50 546.110

.75 546.083 1.00 546.060 1.25 546.035 1.50. 546.022 1.75 546.011 2.00 545.981 .110* .004*

2.25 545.970 .100* .110*

2.50 545.976 .067* .075*

2.75 545.963 .060* .023* I 3.00 '545.973 .044* .080*

' 3.' 25 545.973 .031*- .031*

~3.50 545.966 .028* .012*

3.75 545.962 .024* .057* l 4.00 545.939 .065 .033 .032* .021* .026*

.047 .008 O' 4.25 4.50 545.981 545.987 .031 .020

.055*

.051*

.005*

.006*

.081*

.044*

4.75- 545.980 .026 .018 .044* .008* .039*

5.00 545.977 .021 .038 .059* .002* .005*

5.25 545.962 .018 .019 .001* .005* .022*

5.50 -545.973 ' .012 .014 .002* .003* 0036*

• INDICATES TEMPERATURE STABILIZATION HAS BEEN SATISFIED l

l l

.h Page 1 of 1 Section B.1 3

1

,t;

. .r f,'

-3 SECTION B.2: Instrument Selection Guide (ISG) Calculation l

O O

ISG CALCULATION

' (']

_\v-( ANSI /ANS 56.8 - 1987 )

r=====================================================================

CALIBRATION DATA SENSOR DISPLAY

1. OF SENSORS SENSITIVITY (E) REPEATABILITY (r)

TEMPERATURE (T) 18 0.0121 deg. F 0.1000 deg. I PRESSURE (P) 2 0.0001 psia 0.0001 psia VAPOR PRESS (Pv) 5 0.0625 deg. F 0.1000 deg. F LENGTH OF TEST (t) 8.00 hrs PRESSURE (P) 58.8C psia TEMPERATURE (T) 540.0 deg. R VAPOR PRESS (PV) 0.01658 psi /deg. F (at 80 deg. F)

La 0.100 wt%/ day

()

INSTRUMENT MEASUREMENT ERRORS 2 2 1/2 1/2 eT = ((ET) + (rT) ) /[# of sensors) eT = 0.02374 deg. F 2 2 1/2 1/2 eP = [(EP) + (rP) ) /[# of sensors]

eP = 0.00010 psia 2 2 1/2 1/2 ePV = ( (EPv) + (rPV) ) /[# of sensors) ePV = 0.00087 psia INSTRUMENT SELECTION GUIDE 2 2 2 1/2 ISG = 2400/t( 2(eP/P) + 2 (ePv/P) + 2(eT/T) ]

ISG = 0.020 wt%/ day

(])

• 25La = 0.025 wt%/ day Page 1 of 1

,,, ,,,,,,,====================== i

== == = = = = == == = == === = = ==

• S e c t ion B . 2 H

_ - - - _ ___ 7 1

.i

, 1

.. l L;, j

.\ '

'(. -

~

SECTION B.'3:. Description of Bechtel Mass Point Analysis Calculations-I p

u O'

OL

l i

g x p-ai OF IEQIIEL IlE NE

, ~

%)

l A. PrtrTram and Report Descriptial 1.

We Bechtel_IIRP computer program is used to determine the integrated leakage rate of a nuclear primary containment structure. The program i is used to coqpute leakage rate based on input values of tim, free  !

air volum, containment atnesphere total pressure, drybulb tarperature, and de4cint tarperature (water vapor pressure).

Leakage rate is computed usirg the Absolute Method as defined in j ANSI /ANS 56.8-1981, " Containment System Isakaga Testing Requirements"  !

and BN40P-1, Rev 1, " Testing Criteria for Integrated Isakage Rate Testing of Primary 021tainment Structures for Nacicar Power Plants".

We program is designed to allow the user to evaluate containment leakage rate test results at the jobsite during containment leakage testirg.

Current leakage rate values may be obtained at any time during the testing period using one of two computational methods, yielding three different report printouts.

2. In the first printout, the 7btal Time Report, leakage rate is canputed fran initial values of free air volume, contairurent atmosphere drybulb temperature and partial pressure of dry air, the latest values of the same p*rameters, and elapsed time. Wese individually emputed leakage rates are statistically averaged using Iq linear regression by the method of least squares. Se ibtal Time s> Method is the certputational technique upon which the short duration test criteria of BN 'IOP-1, Tev 1, " Testing Criteria for Integrated Isakage Rate 7bstirg of Primary containunt Structures for !bclear Power Plant," are based.

3. N re:ond printout is tho Mass Point Report and is based on the Pass Point Analysis Technique described in ANSI /ANS 56.8-1981, "containmnt Systan Isakage Testing Requirements". W mass of dry air in the containnait is caputed at each data point (time) usirg the Equation of State, fran current values of containment atmaghere drybulb tanperature and partial pressure of dry air. Contained mass is " plotted" versus time and a regressi:n line is fit to the data using the method of least squares. Isakage rate is detennined from the statistically derived slope and intercept of the regression line.

4. h third printout, the Trend Report, is a sumary of leakage rate values based on Total Time and Mass Point computations presented as a function of number of data points ard elapsed time (test duration),

h Trend Report provides all leakage rate values required for emparison to the acceptance criteria of IN40P-1 for corduct of a short duration test.

i Page 1 of 12 Section B.3

L

[ 5. We program generates a predictor report based on " Suggested Criteria J

for a Short Duration IIRr", Ted Brown and Louis Estenssoro, Erpceedims of the_first Workshoo on Containment Testim, January 18, 1982. We " predictor" is an estirate of the upper bound l

(~)

V on the change in mass point calculated leakage rate which will occur during the next four hours. We estimte is based on the mass point calculated leakage rates and 95% UCIs during the previous four hours.

6. he program is written in a high level larquage and is designed for use on a micro-computer with direct data input frun the data acquisition system. Brief descriptions of program use, formulae used for leakage rate com itations, and program logic are pratided in the followirg paragraphs.

B. Denlanation of Frhcua

1. Me Bechtel IIRT ocznputer program is written, for use by experienced IIRT personnel, to determine containment integratai leakage rates based on the Absolute Method described in ANSI /ANS 56.8-1981 ard BN 'IDP-1.

2. Information loaded into the program prior to or at the start of the test:

a. Number of containment atrosphere drybulb ten dewpoint temperature (vater vapor pressure) perature sensors ard senscrs, pressure gages to be used in leakage rate catputations for the specific test

(

b. Volume fractions assigned to each of the above cenrcrs

c. Calibration data for above sensors

d. Test. title

e. Maxinn allowable leakage rate at test pressure

3. Data received from the data acquisition system durirg the test, and used to ccrtpute leakage rates:

a. Tim and date

b. Omtainment atrosphere drybulb temperatures

c. Containment at=csphere pressure (s)

d. Omtainment atmosphere dewpoint temperatures

e. Containment free air volume.

4. After all data at a given time are received, a Sumary of Measured Data report (refer to "Prvgaru Irgic," Paragraph D, " Data" option camard) is printed.

O v

Page 2 of 12 Section B.3 l

I

'5.- If;dr#11b 'and dbwpoint taperature sensors should fa11L durirg the n test, .the data fran the sensor (s) are not used. The volume fractions-O,- ~ for the remainirq sensors are reexputed and reloaded' int 6 the progran for.use in ensuing leakage' rate capitations.

c. Isakaae Rate Fbnm1 Lag

1. Catputations Using the Total Time Method:

a. Measured leakage rate fran data:  ;

PV13=WE' 1 1 (1)

PVii=WEi i .(2) 2 W -(W1-W) i

{3) att W1 solving for % and Wi and substituting equations (1) and (2) _

into (3) yie18s: ,,

, [ t _. b (4) ati ( 'TPVi1i)

W,Wi g = Weight of contained mass of dry air at times ti and ti , r+tively, lbs.

T7 ,' Ti = MM a@ W Wh at times t i and t i, respectively, 'R.

P,Pi 1 = Partial pressure of the dry air +-t of the containment atsi.wAmre at times ti and ti ,

respectively, twia.

V,Vi 1 = contaiment free air volume at times ti and t i, respectively (constant or variable durirg the test), ft .

th data po'ints respectively,.hr.

t,ti t = Time at 1st and i l

ati = Dapsed time fran ti to t i, hr.

R = Specific gas constant for air = 53.35 ft.lbf/lbn.*R.

Li = Measured leakage rata ocuputad during time interval ti to t ,iW.%/ day.

Page 3 of 12 Section B.3

To reduce truncation error, 'da cor,puter program uses the following equivalent for:ulation:

_[bq -2400[aWi3 Li= 3 at t (Wy/

where aWi

= Wi-W1 W1 W1 api AVi A Pi aV1 aTi

+ + -

F3, V1 PV Ty

= 1i ATi T1 4Pi=Pi-P1 ,.

a vi = Vi-V1 ATi=Ti-T1 b.

Calculated leakage rate fran regression analysis:

~

L=a+ bat N (5) wher.

L = calculated leakage rate, wt.t/ day, as determined fran the reejression line.

' 4 a = {I Lg - b Iat i)/N (6) 53b= N(IL at 2) - (IL )(Iat )i i i i (7)

N(Iati ) - (I at )2 i N = Nunbar of data points.

N I= I i=1 c.

95% upper confidence limit on the calculated leakage rate:

UCL = a + b A tN + S-L Page 4 of 12 Section B,3 i r

q

%bere UCL = 95% upper confidence limit wt.%/ day, at elapsed time a tg.

n U.

f For atN < 24 S-

= tsIIIbi - AIL i - b IL a i t )/(N-2)]1/2 i

-[1 + N1 + (atN - at)2/(I A ti2 - (Iat )2/N))1/2 i (9a)

{

Where ts = 1.95996 + 2.37226 + 2.82250 ;

N-2 (N-2)#

For a tN 2 24 S- =t s [(Ebi -AIL i - bI L at i )/(N-2) i J 1/2 (1

N

+ ( a ti- at)2/ (Ioti2 - (It )2/N)) i 1/2 (9b) 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 where t,=

(N-2) 2 + 1.2209 (N-2) ' - 1. 5162 "Li = Calculated leakage rata ocmputed using equation (5) at total elapsed time at ,i %/ day.

at

~

. Iati N

2. Ocupuwc.icn using the Mass Point Method:

a. Contained mass of dry air fran data:

Wi = 144 Pi vi l

Kri (10)

Whern All symbols as previously defined.

Page 5 of 12 Section B.3

1)

b. Calculated leakaga rato from regression analysis, W fa+ bat

- ['N E = -2400 b U' a (11) where i, = calculated leakage rate, wt.%/ day, as determined from the regression line, a =

(IWi - bIat i)/N (12)

N(IWi ati ) -'(IW i)(Iat ).i b = (13) d N(Iati ) - (I at i)*

ati= Total elapsed time at time of ith data point, hr.

N = Number of data points.

Wi

=

Cmtained mass of 4 air at iD data point, Ibm, as cxmputed frcen equation (10).

N-I = I

-i=1 'i O ro reduce truncation error, tu. oc voter program uee tae folicwirq equivalent fornul.ation:'  ;

aWi b -

a = W1 1 + (I -

-Ist i)/N (14)

W1 W1 .

aWi AWi N (I .___ a t ) - I ,, Iati i

W1 W1 b =

wi (15) 2

, N(Iati ) - (I At )2 i ,

f whats is as previously defined.

l.

W1

c. 95% upper confidence limit.

l ~2400 l UCL = - (b - Sb) (16) a Page 6 of 12 D)

Section B.3 i

wh_re -

UCL = 95% upper conf 1,hrne . limit, wt.%/ day.

f~"\ -

Sy3 /2 L(_/

" 4 = t*

[N !ati2 - (I at )2)1/2 i gy7) 1.6449 (N-2)2 + 3.5283 (N-2) + 0.85602 where t, =

(N-2)2 + 1.2209 (N-2) - 1.5162

~

! [wt - (a + b a t t) )2 1/2

, N-2 .

r-

--W1

)l1N-2 I (a wi p t)2 _ g 3g3 wi g 1))2/N -

[ E ( a wiM)ati- 1 I(awiN1)(Iat t)p)2' V2 (18)'

(a tt2) - (I a t i)2g l

d. Predictor:

.. O ,,1 ,, . 1* (2ce 4 (m - 2 s A n La where UCL = 954 upper confidence limit of mass point calculated leakage rate at end of test.

L = Mass point calculated leakage rate at and of test.

r B = Value of linear regression analysis slope of mass point calculated leakage rate vs. time for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of test data.

S A = Linear regression analysis standard deviation of slope.

Ia = Allowable leakage rate.

In tens of elapsed time, a t arti point calculatai leakage rate Iai calculated at the end of yitime interval.

Page 7 of 12 Q.V ,

Section B.3

.f i

. 1

.>, .A- = 2 I Uni - B I at i '

M 4 hr 4 hr

. - (19) h M I-4 hr miati-I4 mi I ati hr 4 hr

.B = (20)

'MIat-i -(I- .at) i 4 hr 4 hr I Mi-AI mi - B I4hr mi a ti 4 hr 4hr (21)

Sg =

2 .(M)

(M-2) [M 4 hr I ati - (I4 hrat i)2)

=

1.mi nass point calculated leakage rate evaluated usirq data up to time a t .

i 4 hr = stmunation over last 4 hotqs of. test data.

N I = I.

N-M+1 M- =

number of data points for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of test.

9 Page 8 of 12 Section B.3 .

f.

D. Prturam Locic -

1. - he Bechtel IIRr corputer program logic flow is controlled by a set fl of u A r options. ne user options and a brief description of their

? 7 associated function are presented below.

[ OPTION COMMAND FUNCTION After startirg the program execution, the user either enters the-nam of the file containirq previously entered data or initialized a new data file.

DATA Enables user to enter raw data. When the system requests valtas of time,. volume, tanperature, pressure and vapor pressure, the user enters the appropriate data. After ocmpleting the data entry, a sumary is printed out. Se user then verifies that the data were entered correctly. If errors are detected, the user will then be given the opportunity to correct the errors. After the user

. verifies that the data were entered correctly, a -

Corrected Data Sumarf Report of time, data, average temperature, partial pressure of dry air, . and water vapor pressure is printed.

TREND A Trend Report is printed.

h 'IUrAL A Total Time Report is printed. -

MASS A Mass Point Report is printed.

TERN Enables user to sign-off temporarily or permanently. All data is saved on a file for y restarting. '

CIRR Enables user to correct previously entered data.

LISP A Sumary Data Report is. printed.

READ Enable the canputer to receive the next set of data from the data Waition system directly.

PIOf Enables user to plot summary data, individual sensor data or air mass versus time.

DEIETE Enables user to delete a data point.

INSERP Enables user to reinstate a previously deleted data point.

VOIR A Enable user to change volume fractions, i

{

'}

Page 9 of 12 Section B.3

• l 1

r ,

r OPTION -

, Cat 99FD FUNCTION 1; ,

PRED A predictor report is printed.

TIME Enable the user to specify the time interval for a report or plot.

g VERF . Enable the user to input LW 1eakage rate and I

calculated IIRP leakage rates at start of verification test.

E. OtInouter Report and Data Printout lass MINr REPORP .

1 h Mass Point Report presents leakage rate data -(wt%/ day) as deter 1nined by the Mass Point Method. . 'Ihe " Calculated Isakage Rate" is the value detendned frun the regression analysis. 'Ihe "Containmer:t Air Mass"

values are the maana i of dry air in the containment . (lben) . 'Ihese air masses, determined frara the Equation of State, are used in the regression analysis.

'IUIAL TIME REREP

'Ibe Total Time Report presents data leakage rata (wt%/ day) as determined by the Total, Time Method. 'Iha " Calculated Laakage Rate" is the value W . determined fraa the regression analysis. 'Iha " Measured Isakage Rates" V are the leakage rate values determined using 'Ibtal Time calculations.

'Ihese values of leakage rate are used in the regression analysis.

TREND REPORP

'Ihe Trend Report presents leakage rates as deteririned by the Mass Point and Total Time methods in perant of the initial-contained mass of dry air per day (wtt/ day), versus elapsed time (hours) and ntanbar of data points.

PREDICICR REPORP

- Ihe predictor K%te presents a predicted upper bound en the change in calculated mass point leakage rate over the next four hours.

StMERf DMA REPORP h Sumary Data report presents the actual data used to calculate

' leakage rates by the various methods described in the corrputer Program" section of.this report. 'Ihe seven coluems are TIME, DME, TEMP, PRESSURE, VPRS, VOIINE, and AIRMASS and contain data defined as follows:.

Page 10 of 12 Section B.3

- 1. TDE

- Tina in 24-hour notation (hours and minutes) .

-- 2. DATE:. Calerdar date (ronth and day).

'  :()'

3. TD@: Containment weightad-average drybulb te".perature in absolute units, degrees Rankine (*R) .

4. PRESSURE: Partial pressure of the dry air cmponent of the containment atmosphere in absolute units (psia).

5. VPRS: Partial pressure of water vapor of the containment atmcsphere in absolute units (psia).

6. VOIIJME: Containment free air volume (cu. ft.).

7. AIRMASS: Calculated dry air mass (1bm).

F. Summary of MeasurM Data and Sunmary of Cbuu,ted Data

'Ihe Summary of Measured Data presents the iniividual containment atnosphere drybulb temperatures, dewpoint temperatures, absolute total pressure and free sir volume measured at the time and date.

1. TD@ 1 through TD@ N are the drybulb temperatures, where N = No. of RID's. 'Ihe values in the right-hand colum are temperatures (*F),

multiplied by 100, as read frtat the data acquisition system (CAS).

'Ihe values in the left-hand colum are the cor4M temperatures expr*"ai in absolute units (*R).

2. PRES 1 throutJh PKSS N are the total pressures, absolute, were N = No.

of pressere sensors. 'Ihe right-hand value, in parentheses, is a number.of counts as read frorn the CAS. This count value is converted to a value in psia by the ocmputer via the instrument's calibration table, ocunts versus psia. Tne left-hand colum is the absolute total pmssure, psia.

3. NPRS 1 through VPRS N are the dewpoint temperatures (water vapor

!. pressures), where N = No. of dewpoint sensors. 'Ihs values in the right-hand colum are temperatures (*F), multiplied by 100 as read from the DAS. 'lhe values in the left-hand colum are the water vapor pressures (poia) frtra the steam tables for saturated stearc corresporxiirq to the dewpoint (saturation) tenparatures in the center coltart. .

'Ihe SumnaGr" of Corrected Data presented corrected temperature and pressure values and calculated air mass determined as follows:

1. TDfERA'RJRE ('R) is the volume weicjhted average containment atmosphere drybulb taperature derived from TD91 through TD@ N.

Page 11 of 12 Section B.3

l 2.: CORRECTED PRESSURE (psia) is the partial pressure of the dry air caponent of. the containment abnosphere, absolute. The volume, weighted average containment at:nosphere water vapor pressure is s

subtracted from the volume weighted average total pressure, yielding

- C. . the partial pressure of the dry air.

l l 3. VAIOR PRESSURE (psia) 'is the volume weighted average containment atrWieze water vapor pressure, absolute, derived from VPRS 1 through VPRS N.

4. VOI1HE (cu. ft.) is the containment free air volume.

i

5. CDtfrAINMENT AIR MASS (ibm) is the calculated mass of dry air in the .

containment. The rass of dry air is calculated using the containment' free air volume and the abcne TDiPERATURE and CDRRECTED PRESSI.EE of the dry air.

O O

Page 12 of 12 Section B.3

t t i

~

" SECTION B.4: ILRT Mass Point. Data Analysis LO:

o O-

3 NORTH ANNA POWER STATION - UNIT 1 LEAKAGE RATE'(WEIGHT PERCENT / DAY)

]i MASS POINT ANALYSIS

,O TIME AND DATE AT' START OF TEST: 2345: 701 1989 TEST DURATION: 24.00 HOURS TIME' . TEMP- -PRESSURE CTMT. AIR ' MASS LOSS. AVERAGE MASS h ~ (R) : (PSIA) MASS (LBM), (LBM) LOSS (LBM/HR) t 2345 '545.973 58.7334 529913.6

,, O. 545.969 58.7332 529914.6 -1.1 -4.2 E 15' 545.973' 58.7322. 529903.1- 11.5' 20.9 30 545.974- 58.7341 :529919.4 .-16.2 -7.7 58.7320 529873.3 45- 546.002: 46.2 40.4.

100 545.989 58.7332. 529896.3 -23.1 13.8 115 545.986 58.7325 529392.8 3.5. 13.9 L 130 545.989 58.7332 529895.6 -2.9 10.3 145 '546.006- 58.7331 529878.1 17.5 17.7 200 '546.023 58.7318 529850.5 27.6 28.0 1215 545.983 58.7290 529864.5 -14.0 19.6-230 545.939 58.7262 529881.8 -17.4 11.5

'245 545.931 58.7238 529868.0 13.8 15.2 300 545.924 58.7225 529862.8 5.2 15.6

. 315 545.921 ;58.7221 529862.8 .0 14.5

-330 545.907 -58.7212 529867.2 -4.5 12.4-345, 545.914- 58.7209 529858.6 8.6 13.6' 400 .545.917' 58.7212 529857.8 .8 13.1 1415 545.913 58.7137 529847.9 9.9 14.6 430 545.914 58.7196 529845.9 2.0 .14.3 445 545.897 58.7182 529850.4 -4.6 12.6 500 545.907 58.7193 529849.7 .7 12.2 515 545.902 58.7176 529839.3 10.4 13.5

-530. 545.877 58.7194 529880.5 -41.1 5.8 545 545.888 58.7174 529851.7 28.8 10.3 600' 545.888 58.7177 529854.4 -2.8 9.5 '

615 545.888 58.7161 529839.9 14.6 11.3-630. 545.887 58.7172' 529851.1 -11.2 9.3

, 645 545.902' 58.7158 529823.4 27.6 12.9 700 545.891' 58.7173 529847.3 -23.8 9.1 l 715 545.896 58.7191 529858.5 -11.2 7.3 730 '545.873 58.7171 529863.4 -5.0 6.5 745 545.895 58.7162 529833.6 29.8 10.0 800 545.898 58.7146 529816.4 17.3 11.8 815 545.899 58.7158 529826.3 -9.9 10.3 830 545.871 58.7154 529850.7 -24.4 7.2.

845 545.848 58.7140 529859.8 -9.1 6.0 900 545.888 58.7120 529802.6 57.2 12.0 915 545.838 58.7154 529882.3 -79.7 3.3 930 545.886 58.7143 529825.6 56.8 9.0 945 545.863 58.7144 529848.6 -23.1 6.5 1000 545.881 58.7126 529814.6 34.0 9.7 1015 545.864 58.7133 529838.2 -23.6 7.2 1030 545.865 58.7122 529826.9 11.2 8.1 1045 545.876 58.7129 529822.6 4.3 8.3 1100 545.855 58.7124 529838.6 -16.0 6.7 1115 545.857 529804.4

• ( 1150 545.844

'58.7089 58.7115 529841.3 34.1

-36.9 9.5 6.2 1145 545.842 58.7136 529862.0 -20.7 4.3 1200 545.840 58.7124 529853.1 9.0 4.9 Page 1 of 2-Section B,4 -

p* Mu _ argy

L NORTH ANNA POWER STATION - UNIT 1 LEAKAGE RATE (WEIGHT PERCENT / DAY)

MASS POINT ANALYSIS i

,- . TIME AND DATE AT START OF TEST: 2345 701 1989 i) s TEST DURATION: 24.00 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS AVERAGE MASS (R) (PSIA) MASS (LBM) (LBM) LOSS (LBM/HR) 1215 545.860 58.7096 529807.8 45.2 8.5 1230 545.855 58.7124 529838.6 30.8 5.9 1308 545.845 58.7071 529800.9 37.7 8.4 1315 545.846 58.7067 529795.6 5.3 8.7 1330 545.828 58.7086 529830.1 -34.5 6.1 1345 545.831 58.7103 529842.5 -12.4 5.1 )

1400 545.914 58.7054 529727.8 124.7 13.7  !

1415 545.840 58.7070 529804.3 -86.5 7.5 1430 545.824 58.7087 529834.8 -30.5 5.3 1445 545.843 58.7089 529818.3 16.6 6.4 1500 545.850 58.7083 529806.1 12.1 7.0 1515 545.848 58.7066 529792.2 13.9 7.8 1530 545.844 58.7054 529785.8 6.4 8.1 1545 545.825 58.7084 529831.6 -45.8 5.1 1600 545.846 58.7064 529792.4 39.2 7.5 1615 545.831 58.7056 529800.4 -8.1 6.9 1630 545.846 58.7072 529800.1 .4 6.8 1645 545.844 58.7083 529812.3 -12.2 6.0 1700 545.843 58.7092 529821.6 -9.4 ' 5.3 1715 545.852 58.7077 529798.4 23.2 6.6 1730 545.856 58.7078 529796.4 2.0 6.6 i 1745 545.854 58.7080 529799.6 -3.2 6.3 l 1800 545.851 58.7087 529808.6 -9.0 5.8

{-} 1815 545.864 58.7090 529799.7 8.9 6.2 1830 545.850 58.7070 529793.8 5.8 6.4 1645 545.S58 58.7092 529806.9 -13.1 5.6

) 1900 545.876 58.7055 529756.6 50.3 8.2 1915 545.862 58.7084 529795.3 -38.7 6.1 1930 545.876 58.7059 529759.9 35.5 7.8 i

1945 545.873 58.7074 529775.3 -15.5 6.9 2000 545.883 58.7073 529765.2 10.2 7.3 2015 545.851 58.7060 529784.3 -19.1 6.3 2030 545.857 58.7068 529785.3 -1.0 6.2 2045 545.858 58.7065 529782.3 3.0 6.3 2100 545.888 58.7079 529765.9 16.3 6.9 2115 545.851 58.7091 529812.3 -46.3 4.7 2130 545.873 58.7061 529764.0 48.3 6.9 2145 545.891 58.7067 529752.6 11.4 7.3 2200 545.881 58.7077 529771.4 -18.8 6.4 2215 545.882 58.7047 529742.6 28.8 7.6 2230 545.874 58.7076 529776.7 -34.0 6.0 l 2245 545.869 58.7063 529769.9 6.8 6.2 I 2300 545.890 58.7076 529761.1 8.7 6.6 2315 545.879 58.7099 529792.4 -31.3 5.2 2330 545.872 58.7084 529786.1 6.4 5.4 2345 545.891 58.7084 529766.8 19.3 6.1 FREE AIR VOLUME USED (CU., LT. ) =1825000.0 REGRESSION LINE l

()

INTERCEPT (LBM)

SLOPE (LBM/HR)

= 529888.1

=

=

-5.2

.100 MAXIMUM ALLOWA13LE LEAKAGE RATE

'75% OF MAXIMUM ALLOWABLE LEAKAGE RATE = .075 Page 2 of 2 THE UPPER 95% CONFIDENCE LIMIT = .026 section B.4 THE CALCULATED LEAKAGE RATE = .024 a

.1 SECTION B.5: 'ILRT Data Trend Report O

I

+

a S' , .

i; NORTH: ANNA POWER STATION - UNIT 1 E TREND REPORT

. , TIME AND DATE AT START OF TEST: 2345 .701 1989 NO. END _ TOTAL TIME ANALYSIS -MASS POINT ANALYSIS'

~ PTS TIME MEAS. CALCULATED: UCL-

_______________________.______UCL__ CALCULATED ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ,

2 0 .019~ .019- ~ 99.000 .019 99.000 3 15 .095 .095 99.000' .095' .656 4 30 - .035 .006- .968 .011 .183 5 45 .183. .127 .631- 138 .359 6 100 .063 .108 463 .101 .240 7 ~115 .063 .096 .376 .084 .179 8 130. .046 .081 '319

. .065 .136-9 145 .080 .086 .290 .073 .128:

10 200 . 27 .106 .289 .101 .153 11 215 .089 .106 .273 .100 .142 12 230 .052 .095 .253 .083 .122 13 245. .069 .091- .239 .079 .111-14 300 .071 .089 .228- .076 .104 15 315 -.066 .085 .218 .073 .037-16 330 .050 .080 .207- .067 .089 17 '345 .062 .078 .199 .065 .084 18 400 .060 .075- .191 .063- .080 19 415 .066 .074 .185- .063 .078 20 430 .065 .073' .180 .062 .076 21- 445 .057' .071 .174 .060 .073

._ '22- 500 .055 .068 .169 .058 .070 (3-- 23 515 .061 .067 .165 .058 .069 U 24' 530- .026 .061 .157 .050 .062 25- 545 .047 .058 .152 .048 .060 26 600 .043 .056 .147 .045 .056 27 615 051 .055 .144 .045 .055 2S- 630 .042 .052 .139- .043 .053 29 645 .058 .053 .138 .045 .054 30 700 .041 .051 .134 .043 .052 31 715 .033 .048 .130 .040 .049 32 750 .029 .045 .125 .037'

.045-33 745 .045 .044 .123 .037 .045 34 800 .053 .044 .122 .038 .046 35 815 .047 .044 .120 .038 .046 36 830 .033 .042 .117 .036 .044 37 845 .027 .040 .113 .034 .041 38 900 .054 .040 .113 .036 .043 39 915 .015 .037 .109 .032 .039 40 930 .041 .036 .107 .032 .039-41 945 .029 .035 .105' .030 .037 42 1000 .044 .035 .104 .031- .038-43 1015 .033 .034 .102 .030 .037 44 1030 .037 .033 100 .030 .036 45 1045 .037 .033 .099 .030 .036 46 1100 .030 .032 .097 .029 .035 47 1115 .043 .032 .096 .030 .035 48 1130 .028 .031 .094 .029 .034 49 1145- .019 .029 .092 .027 .032 50 1200 .022 .028 .090 .025 .031

- (} 51 1215 .038 .028 .089 .026 .031 52 1230 .027 .027 .087 .025 .030 53 1308 .038 .026 .086 .026 .031 Page 1 of 2 Section B.5 ~

C%".ijir5p -

. _ _ _ . - _ . - - . - _ - _ _ _ _ - _ - .l

1 l-NORTH ANNA POWER STATION - UNIT 1 l TREND REPORT 1 . ,a .

L \_)E TIME AND DATE AT START OF TEST: 2345 701 1989 L

l-NO. END TOTAL TIME ANALYSIS MASS POINT ANALYSIS PTS TIME MEAS. CALCULATED OCL CALCULATED UCL

~5i- 1515---- 525---- 555---- 655----~~~555----- 55i-55 1330 .027 .026 .085 .026 .030 56 1345 .023~ .025 .083 .024 .029 57 1400 .062 .027 .085 .028 .033 58 1415 .034 .026 .085 .028 .033 59 1430 .024 .026 .083 .027 .032 60 1445 .029 .025 .082 .026 .031 61 1500 .032 .025 .081 .026 .031 62 1515 .035 .025 .081 .026 .031 63 1530 .037 .025 .081 .027 .031 64 1545 .023 .024 .079 .026 .030 65 1600 .034 .024 .079 .026 .030 66 1615 .031 .024 .078 .026 .030 67 1630 .031 .024 .078 .026 .030 68 1645 .027 .023 .077 .025 .029 69 1700 .024 .023 .076 .025 .029 70 1715 .030 .023 .075 .025 .028 71 1730 .030 .022 .075 .025 .028 72 1745 .029 .022 .074 .024 .028 73 1800 .026 .022 .073 .024 .028 74 1815 .028 .021 .073 .024 .027 fs 75 1830 .029 .021 .072 .024 .027 1 76 1845 .025 .021 .071 .023 .027 77 1900 .037 .021 .071 .024 .027 78 1915 .027 .021 .071 .024 .027 79 1930 .035 .021 .071 .024 .027 80 1945 .031 .021 .070 .024 .027 81 2000 .033 .021 .070 .025 .028 82 2015 .029 .021 .070 .025 . 027 83 2030 .028 .021 .069 .024 .027 84 2045 .028 .021 .069 .024 .027 85 2100 .031 .021 .069 .024 .027 86 2115 .021 .020 .068 .024 .027 87 2130 .031 .020 .068 .024 .027 88 2145 .033 .020 .067 .024 .027 89 2200 .029 .020 .067 .024 .027 90 2215 .034 020 .067 .025 .027 91 2230 .027 .020 .067 .024 .027 92 2245 .028 020 .066 .024 .027 93 2300 .030 .020 .066 .024 .027 94 2315 .023 .020 .066 .024 .026 96 2330 .024 .020 .065 .024 .026 96 2345 .028 .020 .027 .024 .026 fs Page 2 of 2 Ok*hn

i

o. .t SEC170N B.6: Verification Test Mass Point Data Analysis L

O

' .O P

-^a-------- . - . - _ _ _ _ _ _ _ _ _ _ _ _ _ _

, I j

~

NORTH ANNA POWER STATION - UNIT 1

'(-]i :

~

LEAKAGE RATE (WEIGHT PERCENT / DAY)

-MASS POINT ANALYSIS

' TIME AND DATE AT START OF TEST: 2330 703 1989 TEST DURATION: 4.00 HOURS TIME TEMP. PRESSURE CTMT. AIR MASS LOSS AVERAGE MASS (R) (PSIA) MASS (LBM) (LBM) LOSS (LBM/HR)

---

.w--------------------------------..-------------

2330 545.229 58,5797. 529248.8 2345 545.217 -58.5812 529272.7 -23.9 -95.7 0 545.250 58.5787. 529218.9' 53.7 59.6 15 545.230- 58.5790 529240.3 -21.3 11 4

'30 545.233. 58.5775 529224.6 15.7 24.2 45- 545.234 58.5768 529216.3 8.2 26.0 100 545.238- 58.5745 529192.8, 23.6 37.4 115 545.215 58.5740 529209.7 -16.9 22.4 130 545.217 58.5738 529206.7 2.9 21.0 145 545.212- 58.5712 529187.4 19.3' 27.3 200 545.188 58.5710 529209.4 -22.0 15.7 /

215 545.208 58.5703 529183.3 26.1 23.8 1 230 545.209 58.5G96 529176.1 7.3 24.2 245 545.214 58.5678 529155.3 20.7 28.8 300 '545.211- 58.5662 529143.5 11.8 30.1

'315 545.195 50.5676 529171.5- -28.0 20.6-330 545.201 58.5640 529132.7 38.8 29.0 FREE AIR VOLUME USED (CU. FT.) =1825000.0 REGRESSION LINE INTERCEPT (LBM) = 529254.4 SLDPE (LBM/HR) = -27.4

. VERIFICATION TEST LEAKAGE RATE UPPER LIMIT = .134 VERIFICATION TEST LEAKAGE. RATE LOWER LIMIT = .084 THE CALCULATED LEAKAGE RATE = .124 i

Page 1 of 1 1 Section B.6

.t .:. OL

, '? '

h ,= APPI!lNDIX C . {

$ClE , , ,

x '

d .

4 s CRAPBS k ,_l- r IlM(3.. SECTION C.1:: Containment Air Mass' Plot for' Test Duration l N , '.SECTION C.2:.Regressio'n Line of ILRT Containment Air Mass. _

jf --

SECTION'O.3: TLRT. Mass Point, Leakage Rate'and UCL

r. e.

SECTION C.4:. Regression Line of. Verification Test Containment Air Mass.

-SECTION'C.5: . Verification Test Mass Point Leakage Rate er

+  ?

l ' 9' ;

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1:

1 SECTION C.1: Containment Air Mass Plot for Test Duration l'

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0 0

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0 0

0 0

0 0

0 0

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1 4 7 0 3 6 0 9 8 8 7 6 3 2 2 2 2 2 5 5 5 5 5 5

r :..

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SECTION C.2: Regression Line of ILRT Containment Air Mass j

-l O

I-O

1 l i 0

0 4

2

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^

n 0

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2 2 2 2 2 2

_ 5 5 5 5 5 5

k..

t o a 1

SECTION C.3: ILRT Mass Point Leakage Rate and UCL i .

1 l

10 1

l O

)

Y A

2 D 0 /

Y7  %

A D 5

/E 7 L

%T 3 C -

A 0 U E

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- SECTION C.4: Regression Line of Verification Test Containment Air Mass th '

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0 0 0 0 0 0 0 0 0 0 O 0 5

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_ 9 9 9 9 9

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SECTION C.5: Verification Test Mass Point Leakage Rate l

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S T T T I I I 4 M M M0 I I I7 L E L L T TE R A R ST E R E P W EA P O TD U L N0 O3 I3 T

A CE IM 1 FI

. IT TR IED NVN U E D

- N A3 N 0 OE7 IT TA ARE T T SEA GD RA EK0 WA3 OE3 PL2 ATE NNM 3

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H T TSR RSA OAT NMS 0 0 0 0 0 5 0 5 0 5 2 2

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-1 APPENDIX D: Local Leakage Este Testing Sunmary Section D.1: Type B Testing Summary L .-

f Section D.2: 'lype C Testing Summary

) i, Section D.3: Type B and Type C Instrument Error Analysis f

I G

.- O

1 .'

SECTION D.1. Type B Testing Summary 0-i I

l LO

1 SECTION D.1: Type A Testing Sirmary

~

The following chartu summarize the Type B leakage testing performed on Unit I components from September 1984 to the July 1989 Unit 1 startup. ,

Since September 1984, the Staticn has performed the Type B testing at a pressure range J of 44.0 psig to .45.0 psig. Tha minimum Technical Specification test pressure has been 40.6 psig. A recent change to the Unit 1 Technical Specifications which increased the allowable containment temperature has increased the minimum Type B testing pressure to 44.1 psig. All Type B leakage testing for the Spring 1989 Unit i outage was performed at a pressure range of 44.1 psig to 45.0 psig.

I l

Page 1 of 3

,Section D.1

ps , y.

1

(] ,4 Electrical Penetration Type B Testing Summary

~

g Outage Total Leakage (SCFH)

Fall 1984

~

- 1.551-Winter 1985 1.477

- Spring 1987 0.355 Jn Spring 1989 2.915 2.645 Containment Fuel Transfer Tube Type B Testing Summary

' Until:the Spring 1989 Unit 1. outage, procedural constraints have required that the leakage for the fuel transfer tube be equal to zero. If any leakage-of the fuel transfer. tube was

- discovered, the seal was replaced without measuring the pre-repair leakage. Starting'vith _

- the Spring 1989 Unit'l outage, the as found leakages for the fuel transfer tube are to be recorded. To date, all of the recorded leakages for the fuel. transfer tube havelbeen equal to zero.

O e

Page 2 of 3 Section D.1 s'e i:.._2- - . _ . - - ,

• _ - - . - - - . _ -- - - - - _ . - - ---w _._:_m.m.m_. _m__u _m.--=. _ . _ - - _____.m____:.-.mm__--u___u__-_m.___ u____ _

Containment Air Locks Type B Testing Sununary V Leakages (SCF11) and Test Dates Personnel Air Lock- Equipment Hatch January 1985 0.20 2.80 August 1985 5.50 8.85 January 1986 5.60 3.10 December 1986 11.5 2.60 Dec. ember 1987 8.00 3.30 February 1988 8 65 ----

May 1988 ---- 4.60 June 1988 6.30 =

November 1988 5.00 0.70 lSJune 1989 ----

0 + 0.14 gj -

July 1989 6.30 + 0.14 l

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()\ Page 3 of 3 l

Section D.1 l

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LO

-i SECTION D.2: Type C Testing Summary 1

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r '- - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

SECTION D.2: Type C Testing Summary The following chart summarizes the Type C leakage testing performed on Unit I components from September 1984 to the July 1989 Unit 1 startup. The leakages in the chart represent the maximum' pathway leakages for the penetrations.

Since September 1984, the Station has performed the Type C testing at a pressure range of 44.0 psig to 45.0 psig.. The minimum Technical Specification test pressure has been 40.6 psig. ~ A recent change to the Unit 1 Technical Specifications which increased the ellowable containment temperature has increased the minimum Type C testing pressure to 44.1 psig. All Type C leakage testing for the Spring 1989 Unit 1 outage was performed at a pressu. range of 44.1 psig to 45.0 psig.

,.x

) Page 1 of 7

!. Section D.2 l

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Containment Piping Penetrations Type C Tr ting Summary k(

~

kg IR 5 Leakages' (SCFH)

,-. , ~.3-s,j.

< HPene-

"tration~ Fall 1984 Winter 1985.- Spring 1987 Spring 1989

' Number Outage INTERIM Outage INTERIM Outage INTERIM - Outage 1 b- 0 0.35 0 + 0.07

2. '0, ->257 >257 0 + 0.07

+ 0 0

'4' -O O O O + 0.07

-5 0 0 0 0 + 0.07 7 (*) 0.50 0.35 0 + 0.07 0.35.

8- 0.28 0 0.40 0 + 0.07

'9 >35' >257 0.35 >254

.4.50 1.00 0 + 0.07 10 0 0' 1.00 >254 0 + 0.07 u

m 11 >35 >257 >257 0 + 0.07

', b 0.18 1.50 1.10 12 0- 0 0.30 0 + 0.07 13 0 0 0.20 0 + 0.07 14' 4.60 0 0 0 + 0.07

~

0 15- 0 73.0 0 0 + 0.07

~

1.60 0.35 0 0.07 16 >35 0.50 0.35 0 + 0.07 0

NOTES: 1. For outages the second figure is "As Lef t, when different than "As Found".

2. Leakages not quantified are' indicated by (*).

3. The Fall 1984 outage data is included for reference.

Page 2 of 7 Section D.2 '

. /(l./

Containment Piping Pcnetrctions Typa C T ating Summary (cont)

Leakages (SCFH)

.,c s .

Pene-tration Fall 1984 Winter 1985 Spring 1987 Spring 1989 Number Outage INTERIM Outage INTERIM Outage INTERIM Outage 17 >35 >257 >257 0 + 0,07 0 0 0 18 0.35 0 35.0 0.35 + 0.07 0

19 0 0.35 0.35 0 (10/87) 0 + 0.07 0.28 0 0 (12/87) 0 (01/88) 20 0 0 0 0 + 0.07 22 0 0 0 0 (09/87) 0 + 0.07 24 2.38 0.30 18.0 0.30 + 0.04 2.75 3.80[0.70 25 0 0 1.00 0.35 + 0.07 26 0.49 1.50 5.00 1.75 + 0.07 O 27 0 0 1.50 2.00 + 0.07 28 >35 68.0 20.0 0 + 0.07 10.9 5.80 0 3! >35 >257 >257 0.20 (10/87) 6.70 + 0.70 2.45 0.50 0.20 1.20 + 0.07 32 2.10 60.0 0.50 0.50 (10/87) 0 + 0.07 0 0.20 33 0 2.25 11.5 3.50 + 0.07 0 0[0.07 34 0 0 0.35 0 + 0.035 38 0.30 3.20 12.0 0 + 0.07 11.2 0 0.55}0.07 l

Page 3 of 7 Section D.2 t]

L________________..___._____.____.___.__.__ _ _ _ _ _ _ . . . _ _ . _ _ _ _ _ _ _ _ _ _ .

l Containment Piping Penetrctio23 Type C T2: ting Sumer.y (cont) -

Leakages (SCFH)

Pene-tration Fall 1984 Winter 1985 Spring 1987 Spring 1989 Number Outage INTERIM Outage INTERIM Outage INTERIM' Outage 39 1.58 16.0 6.00 0 + 0.07 0.15 0 40 5.59 2.50 0.90 10.0 + 0.70 0.85 0 0[0.07 41 0.35 0.60 3.65 0 + 0.07 0

42 0.50 3.80 0.60 0.60 (10/87) 0 + 0.14 0.60 43 >35 0.25 0.40 0 (10/87) 0 + 0.07 0.62 0 44 0 0 0 0 + 0.07 45 0 0 0 0 + 0.07 46 >35 >257 4.80 (01/86) 0 (*)

0.175 0 0 -+ 0.07 O 47 0.40 0.30 1.80 0.70 (10/87) 0 + 0.07 0.70 48 0 0.40 2.10 0 + 0.07 0.40 50 0 0 0.10 0 + 0.07 53 0 10.7 23.5 0 + 0.07 0.93 1.00 0 54 0 0 0 0 + 0.07 _

55D 0 0 0 0 + 0.04 56A 0 0.08 0.08 (02/87) 0 48.7 + 1.44 0.3510.07 Page 4 of 7 p

ul Section D.2

Containment Piping P:netrations Type C Tu ting Sununary (ccnt)

Leakages (SCFH) g3 .

Pene-tration Fall 1984 Winter 1985 Spring 1987 Spring 1989 Number Outage INTERIM Outage INTERIM Outage INTERIM Outage 56B 0.21 0.05 0 1.40 + 0.07 010.07 56c o 0 0 0.35 + 0.07 560 0 0 0 0 + 0.07 57A 0 0 0 0 + 0.04 57B 0 0.60 0 0 + 0.07 57C 0 0.05 0 0 + 0.07 60 0.70 6.00 0 1.30 + 0.07 0}0.07 61 0 0 0 0 (10/87) 0 + 0.07 62 0 15.0 11.4 0.35 (10/87) 0 + 0.07 1.8 0.35 O 63 o o o o co9/87) o + o o7 2.00 64 0 0 0 0 + 0.07 1.50 66 22.0 0.50 12.0 1.40 (10/87) 8.80 + 0.70 11.2 23.0 0[0.07 67 0 0.60 0.80 0 (10/87) 5.20 + 0.70 0 1.80 7 0.04

~

l 70 0 0 0 0 (09/87) 8.00 + 0.70 0.35 0 7 0.07 1

71 9.20 5.90 (08/85) 6.00 0 5.00 (09/87) 1.00 + 0.07 5.90 79 >35 >257 >257 180 + 5.14 1.61 0 0 4.60[0.70 Page 5 of 7 Section D.2

~ ~

' [

["' ..Contaitument Piping- P:n.trctions Type C Tasting Samunary - (cznt)

R; Leakages (SCFH)

^

-Pene-

,tration Fall 1984 Winter 1985 Spring 1987 Spring 1989

, ~ Number Outage INTERIM Outage INTERIM Outage INTERIM Outage ;I 7.34-80' ~0 8.00 28.0 + O.70 0.92 7.00 + 0.70

, 81 8.04 .19.0 9.00 3.30 + 0.07 0 0 0[0.07

, , 82 'O O >257 185 + 5.14 0 0.07}0.07 14.0 + 0.70.

83 0.42 8.00 2.40 0 0 0[0.07 84 1.89 0 0.35 250 + 5.14

, 0 010.07 85' O 31.0 0 15.0 + 0.70 2.80 030.07 86 0 40.0 2.80 17.0 + 0.70 0.75 0 030.07 89 3.50 144.0 >257 1.60 (10/87)- 4.60 + 0.23 1.93 1.90 1.60 0 + 0.23

.90 >35 468 (08/85) 0 10.0 (01/86) 20.0 5.80 (06/87) 1.00 + 0.23 5.00 6.70 (08/85) 7.99 (09/86) 0 16.0 (10/87) 0.80 7 0.04

~

400 (11/85) 3.00 (12/87) 18.0 (12/85) 1.40 (01/88) 7.70 (12/85)

-91 ~>3 5 10.8 (08/85) 24.0 13.6 (01/86) 48.0 6.10 (06/87) 1.00 + 0.23 0 24.0 (11/85) 23.0 (09/86) 0 12.0 (10/87) 1.10 7 0.04

~

31.0 (12/85) 0 (12/87) 2.90 (01/88) 92 0 65.25 0.20 0.80 + 0.07 0

93 0 0.80 0.50 1.50 + 0.07 1.00[0.07 l

Page 6 of 7 Section D 2

Contcinnent' Piping Panetrationa Type C Tacting Samanary (cont)

Leakages -(SCFH) 7

\

p tration . Fall 1984 . Winter 1985 _

Spring 1987 . Spring 1989

. Number. Outage INTERIM- ~0utage INTERIM Outage -INTERIM Outage 94 0: 10.0 2.20 (09/86) 0 0 (06/87) 6.60 + 0.70

~

1.10 1.30 .1.20 (10/87) 1.80 ~

0.07-1.60 (12/87).

0 (02/88) 97A .0 0 0 0 + 0.07 97B 0 0 0 04 0.04 97C 0- 0 0.05 0 2 0.07-98A 0 0 0 1.40 + 0.035 98B 0 0 0.20 O_+ 0.07 100 1.40- 10.0 0 0.75'(10/87) '0 + 0.07 0 0.20 103, 0.50 0 0 0 + 0.07.-

O.

104 0 -0 0 0 (01/88) 0 + 0.07 105A 0 0 0 0 + 0.04 105B -0 0 0 0 (06/88) 0 + 0.07

'105C 0 0.10 0.18 0.18 (10/87) 0 + 0.07 105D 0 0 0.60 0 + 0.07 106 0 0 0 0 + 0.23

~

108 27.3 166 20.0 1.00 (10/87) 0 + 0.07

~

8.45 0.20 0 109 2.38 >257 0.40 0.40 (10/87) 0 + 0.07 0.63 0.20 111 0 0 0 0 + 0.07 113 0 0.10 0 0.40 (10/87) (*)

7.00 + 0.70 114 0 0 3.15 3.15 (10/87) (*)

0 + 0.07

~

O Page 7 of 7 I

Section D.2

= _ _ _ _ _ _ - _ - _ _ - - - _ _ _ - _ _ _ - _ _ _ _

' [h .f, 3-10 SECTION D.3: . Type B and Type C Instrument Error Analysis S

O.

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'SECTION D.3: Type B and Type C Instrument Error Analysis In previous ' Type B and C testing, no formal instrument error analysis was

-performed since the increased-test pressure (44.0 vs. 40.6)' ensured that any additional leakage due to instrument error was incorporated. Starting with the Spring 1989 Unit-1 outage, formal instrument error analyses will be performed for the Type B and C testing results. The Type B testing on the electrical penetrations and the fuel transfer tube are performed using a bubbler rig in which the number of bubbles per unit time are counted. . The conversion from number of bubbles to SCFH is sufficiently conservative so that no additional error penalty needs to be incorporated. As is shown in the charts in Section D.1 and Section D.2, the reported leakages for the air lock Type B tests and the Type C tests reflect the instrument error analyses performed for the Spring 1989 Unit 1 leakage testing results.

Rotometers are calibrated to 12% (of full scale) for the range of 10% to 100%

of full scale. . When a reading of less than 10% but greater than zero is obtained, the reading is recorded as the 10% value.

Sample rotameters, taken from those used for the Unit 1 Type .C Testing, were checked for sensitivity at the 'O' flow indication. Obvious flow indication

. occurred at 1% and less. Based on this sensitivity, an error tolerance of ! 2%

is assigned to 'O' test. readings.

O 1

Page 1 of 1 Section D.3

{[

I APPENDIX E f

LOCAL LEAKAGE RATE TESTING FAILURE

SUMMARY

( ,)

SECTiON E.1: Type B Testing Failure Summary SECTION E.2: Type C Testing Failure Summary

,~

(

V j

I o

O i

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SECTION E.1: Type B Testing Failure Summary O

1 0

i- ,

SECTION E.1: Type B Testing Failure Su==ary O -

'N/\ During the time period of September 1984 to the July 1989 Unit 1 Cycle 8 start-up, there have been no Type B testing failures of equal to or greater than 0.60L,.

Is)  !

I I

1

\

l 1

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's Section E.1 Page 1 of 1 1

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SECTION E.2: Type C Testing failure-Summary i'

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SECTION E.2: Typ2 C Tasting Failure Summary The'ifo11owing chart summarizes the Type. C testing results for the Unit I containment

? isolation valves which have recorded Type C leakages of at 1 east 0.60L a during the time period-from Septembe'r 1984 to the July 1989 Unit.1 start-up.

Pene- Recorded. Work tration Test Leakage Order

. Number Valve # Date (SCFH) Number Description'of Repair'-

'2 1-CC-193 11/29/95 >257 033861 ' Lapped disc.and cleaned seat.

l 05/11/87 >257 059541 Cleaned valve internals.

9~ 1-CC-572 11/16/85 >257 033058 ' Cleaned and lapped disc.

05/08/89 >254 093015 Insta11ed new valve.

10 1-CC-559 05/08/89 >257 093014 Insta11ed new valve.

11 1-CC-546 11/16/85 >257 033059 Lapped disc and repaired seat.

Replaced springs and hinge. pins.

04/26/87 >257 057896 Installed new vlave. Lapped seat and flapper of new valve.

17 1-CC-119 11/17/85 >257 033087 Cleaned valve internals.

04/28/87 >257 057959 Installed new valve. Lapped seat and flapper of new valve.

- O 31 1-HC-14 11/06/85 >257 032757 C1eaned va1 e internate. tav9ed disc and seat.

04/25/87 >257 057882 Cleaned valve internals. Lapped disc and seat.

31 TV-HC-105A 04/25/87 >257 057883 Cleaned valve internals.

-46. 1-CH-330 11/08/85 >257 032760 Replaced plug and spring.

79 MOV-SW-103D 11/06/85 >257 032703 Cleaned and inspected valve.

Replaced disc.

04/24/87 >257 057835 Bench set valve.

82- MOV-SW-103A 04/24/87 >257 057834 Replaced seat ring.

03/28/89 185.04 090684 Cleaned seating surface.

Replaced seat ring.

84 MOV-SW-104C 03/28/89 250.0 090682 Cleaned seating surface.

Rep 1 aced seat ring.

Page 1 of 2 Section E.2

Pc.nt- Recorded Work tration Test Leakage Order Number Valve # Date (SCFH) Number Description of Repair

j, ~

v

) 89 TV-SV-103 05/01/87 >257 058106 Replaced disc and coat.

90 MOV-HV-100C 08/03/85 467.6 028238 Cleaned valve internals.

11/04/85 400.0 032587 Cleaned valve internals.

109 TV-HC-107A 11/06/85 >257 014144 Cleaned valve internals.

A comprehensive engineering study has been initiated to evaluate and recommend corrective actions for Unit I and Unit 2 containment isolation valves which have been identified as having unsatisfactory Type C testing leakage histories.

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Page 2 of 2 i

Section E.2 lllll l

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_ _ _ _ _ _ _ _ _