ML20154L010

Reactor Containment Bldg Integrated Leak Rate Test, Final Rept

ML20154L010
Person / Time
Site:	Grand Gulf
Issue date:	11/30/1985
From:	BECHTEL GROUP, INC.
To:
Shared Package
ML20154L003	List: AECM-86-0039, Forwards Reactor Containment Bldg Integrated Leak Rate Test Final Rept,Per 10CFR50,App J.Maint Schedule for Type a Tests Requested.Summary of Corrective Actions for Cause of Test Failure Also Encl.Fee Paid ML20154L010
References
SU-088A, SU-88A, TAC-60862, NUDOCS 8603110372
Download: ML20154L010 (67)

Text

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i Mississippi Power & '

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l GRAND GULF i NUCLEAR STAYlON ,

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UNIT 1 ,

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Primary Reactor Containment  ;

i Integrated Leakage '

Rate Test Final Report November 1985  :

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I NISSISSIPPI POWER AND LICHT COWANY i

CRAND CULF NUCLEAR STATION  ;

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t REACTOR CONTA!!# TENT SUILDING IlffECRATED LEARACE RATE TEST f i

FINAL REP 0fff l l

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f Prepared by Bechtel Powr Corporation San Francisco, CA November 198S .

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TABLE OF C0fffEhTS 1

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Secttons No. of Pagea

1.0 INTRODUCTION

1-1 to 1-1 2.0 MSULTS

SUMMARY

2-1 to 2-1 3.0 CNRONOLOGY 3-1 to 3-2 4.0 MTN0DOLOGY 4-1 to 4-5 5.0 TEST DATA AND M SULTS ANALYSIS 5-1 to 5-2 5

6.0 MFEMMCES 6-1 to 6-1 Appendice s A. Description of Bechtel ILRT Computer Program A-1 to A-11

5. Instrument Error Analysis (ISC) 3-1 to 3-1 C. Local Leakage Rate Test Data C-1 t o C-6 D. Summary of Major Modifications and Component D-1 t o D-2 Replacement s E. Summary Report of Type A, 3, and C Test s Which E-1 t o E-4 Failed to Meet 10CFR50, Appendix J, Acceptance Criteria i

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SU-048a $I

1.0 INTRODUCTION

m The first periodic Integrated Leakage Rate Test (ILRT) on the Grand Culf

('- ') Nuclear Station Unit I reactor containment building was performed on November 3-4, 1985. The test was conducted to demonstrate that leakage f rom the containment system at the design loss of coolant accident pressure does not exceed the maximum allowed by the Technical Specif1-cation (Ref. 6.1) . The ILRT was conducted in accordarre with a mechanical surveillance procedure (Ref. 6.2) which conformed to the general testing requirements established in Appendix J to 10CFR50 (Ref. 6.3), ANSI N45.4-1972 (Ref. 6.6), ANSI /ANS 56.8-1981 (Ref. 6.4) and Bechtel Topical Report BN-TOP-1 (Ref. 6.5).

The balance of this report presents test results, describes test eve nt s and methodology and lists the data necessary to support the stated re sult s. The ensuing material is organized into the following sections.

o Section 2, Results Summary, lists the leakage rates determined during the test and the acceptance criteria.

o Section 3 Chronology, describes the activities performed in support of the test.

o Section 4, Nethodology, describes test methods and inst rumentation.

o Section 5, Test Data and Results Analysis, discusses the data acquired to establish the results and presents an analysis of the results.

1 is ,/ o Section 6. References, lists the documents cited in the body of the repo rt .

o The Appendices contain a description of the ILRT computer program and tabular listings of all supporting data.

SU-088a 1-1

2.0 RESULTS

SUMMARY

,9 k ,) Containment pressurization was completed at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on November 3, 1985. Temperature stabilization criteria were met by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.

However, initially calculated leakage was outside the acceptance limit a nd the start of the formal test was delayed until the leakage source (main steam lines C and D isolation valves and spare standby liquid control isolation valves) had been found and isolated. The formal test commenced at 0545 hotra on November 4 and was completed at 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />. Results of the 8.5-hour test, which confirmed an acceptable leakage rate, are tabulated below.

Calculation Mass Point Total Time

• Method Ca lcula t ed 95% UCL Ca lc ula t ed 95% UCL Calculated 0.137 wt.%/ day 0.141 wt.%/ day 0.129 wt.%/ day 0.183 vt.%/ day Rate Additions (per Section 5) 0.004 wt.%/ day 0.004 vt.%/ day 0.004 wt.%/ day 0.004 wt.%/ day Net Rate 0.3 41 wt.%/ day 0.145 wt.%/ day 0.133 wt. % / day 0.18 7 wt. Z /d ay Accep tanc e Limit 0.328 wt .%/ day 0.328 wt.%/ day 0.328 wt.2/ day 0.328 wt.2/ day i The supplemental test calibrated leakage was imposed immediately following

' the 1415 hour0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> data point. The supplemental test commenced at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, following the required one hour stabilization period, and was completed at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />. Results of the 4.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> supplemental test, which confirmed the correctness of the leakage rate calculational method, are tabulated below.

Calculation Method Mass Point Total Time Upper Acceptance Limit 0.684 wt.%/ day 0.675 wt.!/ day l

Calculated Rate 0.543 wt.%/ day 0.555 wt.%/ day Lower Acceptance Limit 0.465 wt.%/ day 0.457 wt.%/ day

• Additional Total Time results based on trend values and the corresponding acceptance criteria, which were satisfied, are presented in Section 5.

SU-088a 2-1

3.0 CHRONOLOGY O

O Test prerequisites specified in Ref. 6.2, including the containment exterior and interior inspections mandated in Ref. 6.3, were completed by November 3, 1985. No evidence of structural deterioration was found during the containment inspection. Completion of prerequisites, containment systems status and inspection results are documented in the Official' Test Copy of Ref. 6.2, which is maintained as a part of permanent plant records. Containment pressurization commenced at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on November 3, and was stopped at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on the same day when containment pressure had reached 12.25 psig, which is 0.75 psig above the minimum test pressure of 11.5 psig. Pressurizing equipment consisted of air compressors with an aggregate capacity of approximately 6,000 SCFM, aftercooler/ moisture separators and a refrigerated air dryer. This equipment maintained an almost constant pressurization rate of about 1.5 psi /hr. Containment fan coolers were run during pressurization to minimize temperature stratificaion. Cooling water was run through the fan cooler coils to control containment air temperature. Fan coolers and cooling water were shut off immediately following the completion of pressurization. Containment lights had been previously turned off.

Temperature stabilization criteria specified in Ref. 6.2 were met by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, four hours following the completion of pressurization. Calcula-tions performed using data recorded during the stabilization period

+ indicated a stable leakage rate of about 0.7 wt.%/ day, which was more than twice the 0.328 wt.%/ day allowable. Data recorded over the next few hours confirmed this initially calculated rate. Leak search teams examined 211 (N /"')

s containment penetrations and identified significant leakage at the open vents outboard of main steam isolation valves QlB21F028C and QlB21F028D.

A possibly significant leak was identified at the open vent outboard of isolation valve Q1C41F150 in the spare standby liquid control line passing through penetration 61. These leakages were reduced to negl!gible values by shutting the vents.* This corrective action was completed at 0104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> on November 4.

During the stabilization and subsequent leak search periods, reactor water level had dropped to 65 inches and required makeup. Level was restored'to 84 inches by an injection starting at 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> and ending at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />. Calculations performed using data recorded following the reactor makeup indicated that leakage had been reduced to an acceptable level.

When this reduction had been confirmed using data recorded over. a three-hour period, a formal test start was declared at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />.

Calculations usind data recorded during the first 8. hours of test (the minimum acceptable test duration) showed a stable and acceptable leakage rate. It was intended to end the primary test and initiate the imposed leak for the supplemental test at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />. However, due to a delay in receiving the release authorization from Health Physics, the imposed leak

• Additions to the calculated leakage rate are required by the resulting

- (--) non-standard valve lineups. These are discussed in Section 5.

SU-088a 3-1

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was not initiated until af ter 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />. The primary test was extended for the additional half hour so that its end would coincide with the start (t}j of the supplemental test. The one-hour stabilization period for the supplemental test ended at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> and the supplemental test itself was concluded at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> (giving it a duration of 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> which is half the duration of the primary test).

The pressure at the end of the supplemental test was 12.1 psig. . Duri ng the entire test period, pressure was between 12.25 psig and 12.1 psig, well within the 11.5 to 13.5 psig acceptable range.

The containment was depressurized following the supplemental test and plant systems aligned for the ILRT were restored, as required, to conditions required for the support of subsequent outage activities.

Depressurization and restoration are documented in the Official Test Copy of the procedure (Ref. 6.2).

Various items of data needed to support or supplement the ILRT were recorded at regular intervsl

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. .530 1104 TIME HOURS 1945 1104 i START TIME DATE END TIME DATE FICURE 5.8 l

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6.0 REFERENCES

6.1 Grand Gulf Nuclear Station, Unit 1. Technical Specification 3/4.6.1.

6.2 Grand Gulf Nuclear Station, Surveillance Procedure 06-ME-1M10-0-0002, Contairunent Integrated Leak Rate Test, Revision 20.

6.3 Code of Federal Regulations, Title 10, Part 50, Appendix J - Primary Reactor Contalment Leakage Testing for Water Cooled Power Reactors.

6.4 ANSI /ANS-56.8-1981, Contaiment System Leakage Testing Requirements.

6.5 Bechtel Topical Report BN-TOP-1, Revision 1 Testing Criteria for Integrated Leakage Rate Testing of Primary Contairunent Structures for Nuclear Power Plant s.

6.6 ANSI N45.4 - 1972, Leakage Rate Testing of Containment St ructures for Nuclear Reactors.

O SU-088a 6-1

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APPENDIX A i ,

l Description of Bechtel ILRT Computer Program j 1.

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i APPENDIX A i

l v DESCRIPTION OF BECHIEL ILRT COMPUTER PROGRAM A. Program and Report Description i I

i 1. The Bechtel ILRT computer program is used to determine the inte-

. grated leakage rate of a nuclear primary containment structure.  ;

The program is used to compute leakage rate based on input values of time, free air volume, containment atmosphere total pressure, 1 drybulb temperature, and dewpoint temperature (water vapor pressure).

Isakage rate is computed using the Absolute Method as defined in ANSI /ANS 56.8-1981, " Containment System Leakage Testing Requirements" and BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants".

The program is designed to allow the' user to evaluate containment .

leakage rate test results at the jobsite during containment le akage  !

testing. Current leakage rate values may be obtained at any time

during the testing period using one of two computational methods, i yielding three dif ferent report printouts.  !

2. In the first printout, the Total Time Report, leakage rate is com-  !

! puted from initial values of free air volume, containment atmosphere  :'

i drybulb temperature and partial pressure of dry air, the latest

} values of the same parameters, and elapsed time. These individually j computed leakage rates are statistically averaged using linear re-gression by the method of least squares. The Total Time Method is the computational technique upon which the short duration test criteria'of BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Contairusent Structures for Nuclear

, Power Plant " are based.

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3. The second printout is the Mass Point Report and is based on the 1 Mass Point Analysis Technique described in ANSI /ANS 56.8-1981, I

" Containment System Leakage Testing Requirements." The mass of dry j sir in the containment is computed at each data point (time) using

, the Equation of State, from current values of containment atmosphere l drybulb temperature and partial pressure of dry air. Contained mass i is " plotted" versus time and a regression line is fit to the data -

I using the method of least squares. Imakage rate is determined from '

j the statistically derived slope and intercept of the regression line.

I 4 The third printout, the Trend Report, is a summary of leakage rate l l values based on Total time and Mass Point computations presented J

as a function of number of data points and elapsed time (test dura-  :

tion). The Trend Report provides all leakage rate values required '

for comparision to the acceptance criteria of BN-TOP-1 for conduct '

of a short duration test.

i 7 5. The progree is written in a high level language and is designed for use on a micro-computer with direct data input from the data acquisition system. Brief descriptions of program use, formulae i DN-103 g.g

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l used for leakage rate computations , and program logic are provided Q in the following paragraphs.

D B. Explanation of Program

1. The Bechtel ILRT comp.ater program is written. for use by experi-enced ILRT personnel, to determine containment inteersted leakage rates based on the Absolute Method described in ANSI /ANS 56.8-1981 and BN-TOP-1.

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

a. Number of contairunent atmosphere drybulb temperature sensors, dewpoint temperature (water vapor pressure) sensors and pressure gages to be used in leakage rate computations for the specific test

b. Volume fractions assigned to each of the above sensors

c. Calibration data for above sensors

d. Tes t title

e. Test pressure

f. Maximum allowable leakage rate at test pressure

3. Data received from the data acquistion system during the test, and used to compute leakage rates :

a. Time and date

b. Containment atmosphere drybulb temperatures

c. Containment staosphere pressure (s)

d. Containment atmosphere dewpoint tempe ra tures

e. Containment free air volume.

4 Af ter all data at a given time are received , a Summary of Measured Data report (refer to " Program Logic," Paragraph D. " Data" option command) is printed.

5. If drybulb and dewpoint temperature sensors should f ail during the test, the data from the sensor (s) are not used. The volume frac-tions for the remaining sensors are 'recomputed and reloaded into the program for use in ensuing leakage rate computations.

O DH-103 A-2

C. Leakare Rate Formulae

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't) 1. Computation using the Total Time Method:

a. Measured leakage rate, from data:

PV1 i = W 1RT1 (1)

PVi i = WiRTi - (:)

2400 (W1-W) i li "

(3)

Solving for W1 and Wi and substituting equations (1) and (2) into (3) yields:

2400 / TPVh 1ii Lg = l 1- l (4) ati ( TPVi1i) where, W,Wi 1 = Weight of contained = ass of dry air at times ti and ti respectively, lbs.

-T1 , Ti = Containment atmosphere drybulb te=perature at times

ti and ti respectively, 'R.

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P,Pi 1 = Partial pressure of the dry air component of the con-tainment atmosphere at times ti and ti respectively, psia.

V,Vi 1 = Containment free air volume at times t iandtgresgec-tively, (constant or variable during the test), ft .

ti, tg = Time at let and ith data points respectively, hours.

att = Elapsed time from ti to ti, hours.

R = Specific gas constant for air = $3.35 ft.lbf/lbm.*R.

Li = Measured leakage rate computed during time interval ti to ti, we.%/ day.

In order to reduce truncation error, the computer program uses the following equivalent formulation:

-2400(aW)i Li= l ati( W /

1 n

U DH-103 A-3

where, Le AWi Wi-W1 W1 W1 api AVi APi aVi ATg

+ + -

P1 V1 PV1i T1 y ,AT t Ti api =Pi-P1 AVi=Vi-V1 STi=Ti-T1

b. Calculated leakage rate from regression analysis, I = a + b ats (5) where:

L = Calculated leakage rate, wt.%/ day, as determined f rom the regression

'line.

a = (ILt - bIatg)/N (6)

N( Li ati) - (ILi )(Iott)

N(IatgA ) - (Iatg)2 N = Number of data points N

I=I i=1

c. Calculated leakage rate at the 95% confidence level.

I95 = a + b atN + S (8)

I where:

E95 = calculated leakage rate at the 95% confidence level, wt.%/ day, at elapsed time atN*

O U DH-103 44

For.atN < 2' p)

C S = to.025;N-2 [(ILt 2

- a:Lt - brLi ati)/(N-2)]II2 x [1'+ 1,+ (at3-E)2/ (9a)

T N (Iat g2 _ (g3ti)2f3)jl/2 where, to.02! N-2 = 1.95996 + 2.37226 + 2.82250 ;

N-2 (N-2)-

For atN 12' S_ = to.025;N-2 [(ILg 2 - arLt - btt gati)/(N-2)]1/2 x (1,+(at3 - E)2/ (9b)

L N (ratt 2 _ gg et)2f3);1/2 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 where , to.025;N-2 =

(N-2)2 + 1.2209(N-2) - 1.5162 I= t Calculated leakage rate computed using equation (5) at total elapsed time att, %/ day.

_ Iati at =

N O- 2. Computation using the Mass Point Method

a. Contained mass of dry air from data:

T (10) whe re A11' symbols are as previously defined.

b. Calculated leakage rate from regression analysis, W = a + b at b

E = -2400 - (11) a where L = Calculated leakage rate, wt.%/ day, as determined f rom the regression line.

O DH-103 g_3

a = (IWi -bu tt)/N (12)

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( N(IW g atg) - ( Ng )( Utg)

b. =

, , (13)

N(U tg-) - (U tg)*

att = Total elapsed time at time of i th data point, hours N = Number of data' points Wg = Contained mass of dry air at ich data point, 1be, as computed from equation (10).

N I=I i=1 In order to reduce truncation error, the computer program uses the following equivalent formulation:

AWg b a= Wg 1 + (I IAtg)/N W~ 1 W1 .

O aWg AWg N (I Atg) - I Iac g Wi Wi b= W N(Dtg2 ) _ (gggi)2 AWg

'where, is as previously defined.

W1

c. Calculated leakage rate at the 95* confidence level.

-2400 b5= (b - s b) (14) a where:

I93 = Calculated leakage rate at the 95* confidence level, wt.2/ day.

DH-103 A-6 w_.___________________._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ . _ . . _ . _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ .

1/2 SN sb* "0 025;N-2 (.M tg d - (u tg) W (15)

-where, to.025;N-2 , 1.6449(N-2)2 + 3.5283 (N-2)2 + 0.85602 (N-2)2 + 1.2209 (N-2) - 1.5162

'I(Wg - (a + b atg)]I N-2 a

rg -

=W,g - I(awg/W g )2 . ggg3g i1fw )j2fg .

N-2

[I(AWg /W g ) a tt - I(awg/W U2 1 )(u tg)/N]2

• d I(a tt ) - (I act)d/N _

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l ,fm D. Program Logic l (v) l 1. The Bechtel 11JtT computer program logic flow is controlled by a set i

of user options. The user options and a brief description of their associated f unction are presented below.

l OPTION COMMAND FUNCTION l Af ter starting the program execution, the user either l enters the name of the file containing previously I

entered data or initializes a new data file.

DATA Enables user to enter raw data. When the system

, requests values of time, volume, temperature, pressure l and vapor pressure, the user enters the appropriate l data. Af ter completing the data entry, a summary is printed out. The 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 Summary Report of time, data, average temperature, partial pressure of dry air, and water vapor pressure is printed.

TREND A Trend Report is printed.

O I h TOTAL A Total Time Report is printed.

MASS A Mass Point Report is printed.

TEP.M Enables user to sign-of f temporarily or permanently.

All data is saved on a file for restarting.

CORR Enables user to correct previously entered data.

LIST A Summary Data Report is printed.

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! READ Enables the computer to receive the next set of data l

from the data acquisition system directly.

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

DELETE Enables user to delete a data point.

INSERT Enables user to reinstate a previously deleted data point.

VOLFRA Enables user to change volume f ractions.

O DH-103 A-8 I

OPTION

[} v COSNAND FUNCTION TIME Enables the user to specify the time interval for a report or plot.

VERT Enables the user to input imposed leakage rate and calculated ILRT leakage rates at start of verification test.

E. COMPUTER REPCRT AND DATA PRINTOUT MASS POINT REPORT The Mass Point Repott presents leakage rate data (wt%/ day) as deter-mined by the Mass Point Method. The " Calculated Leakage Rate" is the value determined from the regression analysis. The "Containnent Air Mass" values are the masses of dry air in the containment (ibm).

These air masses, determined from the Equation of State, are used in the regression analysis.

TOTAL TIME RIPORT The Total Time Report presents data leakage rate (wt%/ day) as deter-mined by the Total Time Method. The " Calculated Leakage Rate" is the g value deter =ined from the regression analysis. The " Measured Leakage I,

Rates" are the leakage rate valuas determined using Total Time calcu-lations. These values of leakage rate are used in the regression analysis.

TREND REPORT The Trend Report presents leakage rates as determined by the Mass Point and Total Time methods in percent of the initial contained mass of dry air per day (wt%/ day), versus elapsed time (hours) and number of data points.

SUMMARY

DATA REPORT The Summary Data report presents the actual data used to calculate leakage rates by the various methods described in the " Computer Program" section of this report. The six column headings are TIME, DATE, TEMP, PRISSURE, VPRS, and VOLUME and contain data defined as follows:

1. TIME: Time in 24-hour notations (hours and minutes).

2. DATE Calendar date (month and day).

3. TEMP: Containment weighted-average drybulb temperature in absolute units, degrees Rankine (*R).

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DH-103 A-9 e

4. PRESSURE: Partial pressure of the dry air component of the con-tainment atmosphere in absolute units (psia).

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

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

F.

SUMMARY

OF MEASURED DATA AND

SUMMARY

OF CORRECTED DATA The Summary of Measured Data presents the individual containment atmosphere drybulb temperatures, dewpoint temperatures, absolute total pressure and free air volume measured at the time and date.

1. TEMP 1 through TEMP N are the drybulb temperatures, where N = No. of RTD's. The values in the right-hand column are temperatures ('F) as read from the data acquisition system (DAS).

The values in the left-hand column are the corrected temperatures expressed in absolute units (*R).

. PRES 1 through PRES N are the total pressures, absolute, where N = No.

of pressure sensors. The right-hand value. in parentheses, is a number in counts as read f rom the DAS. This count value is converted to a value in psia by the computer via the instrument's calibration table, counts versus psia. The left-hand column is the absolute total pressure, psia.

3. VPRS 1 throueh VPRS N are the dewpoint temperatures (water vapor pressures), where N = No. of dewpoint sensors. The values in the right-hand column are temperatures (*F) as read f rom the DAS. The values in the lefthand column are the water vapor pressures (psia) f rom the steam tables for saturated steam corre-sponding to the dewpoint (saturation) temperatures in the center column.

The Summary of Corrected Data presents corrected temperature and pressure values and calculated air mass determined as follows:

1. TEMPERATURE (*R) is the volume weighted average containment steosphere drybulb temperature derived from TEMP 1 through TEMP N.

2. CORRECTED PRESSURE (psla) is the partial ,sressure of the dry air component of the containment atmosphere in absolute units. The volume weighted average containment atmosphere water vapor pressure is subtracted from the volume weighted average total pressure, yielding the partial pressure of the dry air.

3. VAPOR PRESSURE (psia) is the volume weighted average contain-ment atmosphere water vapor pressure, absolute derived f rom VPRS 1 through VPRS N.

O DH-18$ A-10

4. VOLT.HE (cu. ft.) is the containment f ree air volu:se.

5. CONTAINMENT AIR MASS (Ibe) is the calculated mass of dry air in the containment. The mass of dry air is calculated using the containment free air volume and the above TEMPERATURE and CORRRECTED PRESSURE of the dry air.

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APPENDIX D l l

(~N ISG CALCULATION l 1 ,) ........................................................................

( ANSI /ANS 56.8 - 1981 )

CALIBRATION DATA

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

TEMPERATURE (T) 22 0.1000 deg. F 0.0100 deg. F PRESSURE (P) 2 0.0003 paia 0.0003 pais VAPOR PRESS (Pv) 6 0.1000 deg. F 0.0100 dag. F' Length of Test (t) 8.0 hrs Test Pressure (P) 11.5 paig ==> 26.2 paia From Steam Table 0.0124 pai/deg. F (at 70 deg. F)

La 0.4370 wtt/ day INSTRUMENT MEASUREMENT ERRORS

[)

v 2 2 1/2 1/2 eT . ((ET) + (rT) 3 /t# of sensors) e7 0.0214 deg. F 2 2 1/2 1/2 eP = ((EP) + (rP) 3 /tm of sensors) eP = 0.0003 pain 2 2 1/2 1/2 ePv . ((EPv) + (rPv) 3 /t# of sensors) ePv . 0.0005 pais INSTRUMENT SELECTION GUIDE 2 2 2 1/2 ISG . 2400/tt 2(eP/P) + 2(ePv/P) + 2(eT/T) 3 ISG . 0.0194 wt2/ day

) 25% of La 0.1093 wt4/ day

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l-t APPENDIX C Local Leakage Rate Testing Results t i

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APPENDIX C

\j Local Leakage Test Summary Data Type B Test Results Penetration Description Leakaoe, SCC" 1 Equipment Hatch 0 1 11 2 Upper Personnel Lock 116 2 12 3 Lower Personnel Lock 294 2 11 4 rual Transfer Tube 02 11 201 Reactor Protection System 020 202 Low Voltage Power 020 203 Instrumentation 010 204 Instrumentation 010 205 Neutron Monitoring 020 206 Low Voltage Power and Control Ot0 207 Control and Power 020 208 Instrumentation 020 209 Low Voltage Power 020 210 Radiation Monitoring 020 211 Control 010 212 Instrumentation 020 213 Rod Position Indication 010 214 T. I. P. 020 215 6.9 Kv-Reactor Recirculation Pump A 020 f-~g 216 Test Systems and Communications 010

(' ') 217 Low Voltage Power and Control 020 218 Neutron Monitoring 020 219 Instrumentation 020 220 Instrumentation 020 221 Control 020 222 Reactor Protection 010 223 Low Voltage Power and Control 020 224 Instrumentation 010 225 Low Voltage Power 010 226 Control 020 227 Instrumentation 020 228 Instrumentation 020 229 Low Voltage Power and Control 020 230 Reactor Protection 020 231 Instrumentation 020 232 Neutron Monitoring 020 233 Rod Position Indication 020 234 CRD Hydraulic System Power and Control 020 235 Neutron Monitoring 01 0 237 Instrumentation 020 238 Reactor Protection System O10 239 Control 020 240 Instrumentation 020 241 Low Voltage Power and Control 020 2 4.' Low Voltage Power and Control 010 C-1

( APPENDIX C (Cont'd)

Local Leakage Test Summary Data Type B Test Results (Cont'd)

Penetration Description Leakage, SOCM 243 Instrumentation 020 244 Low Voltage Power 020 245 Low Voltago Power and Control 020 246 Radiation Monitoring 020 247 6.9 KV Reactor Recirculation Pump B 020 248 Power 020 249 Control 020

• ISI Inspection Ports 010 TOTAL = 420 2 23

• Twenty-two inspection ports on guard pipes, two ea:h per penetration on eleven penetrations (5-10, 14, 17-19, & 87).

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() APPENDIX C (Cont'd)

Local Leakage Test summary Data Type C Test Results (Pneumatic)

(Maximum Pathway Leakage)

Penetration Description Leakage, SCCM

$ Main steam Line A 7,174 2 100 6 Main steam Line B 30 2 17 7 Main steam Line C 01 16 8 Main steam Line D 588 1 11 9 Feedwater Line A 11,011 2 151 10 feedwater Line B 2,552 1 151 14 RHR shutdown Cooling suction 02 17 17 steam supply to RCIC Turbine and RHR Heat Exchangers 02 17 18 RHR to RPV Head spray 02 19 19 Main steam Drain to Condenser 40119 20 RHR A to LPCI 393 1 26 21 RHR 8 to LPCI 0 2 27 22 RHR C to LPCI 1,472 2 19 24' RHR Pump C Test Return Line To suppression Pool 0 2 20 26 HPCs Pump Discharge to RPV 20 2 19 31 LPCS Pump Discharge to RPV 179 1 16 O- 32' LPCs Pump Test Return Line to suppression Pool 0 2 19 33 CRD Pump Discharge 0 2 16 34 Containment Purge supply 98 2 16 35 Containment Purge Eshaust 49 2 17 36 Plant service Water Return 0 1 11 37 Plant service Water supply 02 16 38 Chilled Water supply 180 1 20 39 Chilled Water Return 02 16 40 ILRT Containment Pressurization /

Depressurtration 0 1 11 41 Plant service Air 0 2 16 42 Instrument Air 450 2 12 43 RWCU to Main Condenser 02 16 44 Component Cooling Water supply 01 17 45 Component Cooling Water Return 0 2 17 47 Reactor Recirculation Post Accident sample 40 2 12

• Penetrations 24 and 32 test return lines were extended into the suppression Pool below the minimum drawdown level during the outage.

Hydraulic local leakage test is specified by Tech specss however, pneumatic leakage test results are current, pneumatic testing is conservative, and results are included in Type B and C totals. The next O scheduled leakage tests on these penetrations will be with water.

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l O) i (s APPENDIX C (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)

(Maximum Pathway Leakage) 1 Penetration Description Leakaan, ECTt 49 RWCU Backwash Transfer Pump to Spent Resin Storage Tank 40 1 12 l 50 DW & Containment Equipment Drain Surep l Pumps Discharge to Auxiliary Building Transfer Tank 150 1 12 51 DW & Containment Floor Drain Surp Pumps Discharge to Auxiliary Building Transfer Tank 78 1 11 I 54 Upper Containment Pool to and from Refueling Water Storage Tank 02 11 56 Condensate Makeup to Upper Containment Pool 453 2 11 l 57 Discharge fron ruel Fool Cooling and C. U.

I system to Upper Containment Pool 160 2 17 l 58 Inlet Upper Contairment Pool Skimmer

! Tanks to ruel Pool Cooling and

! C. U. System 02 10 ,

60 Auxiliary Building Floor and Equipment l 0 2 16 I v Drain Return 61 Standby Liquid Control Mixing Tank (Future Use) 30 2 17 65 Containment Normal Vent Supply and Combustible Gas Control 150 2 17 66 Containment Normal Vent and Combustible Gab Control Purge Exhaust 02 17 l 70 Automatic Depressurization System (Instrument Air) 20 2 12 73 RHP Shutdown Helief Valve Discharge to l

l Suppression Pool 0 t 12 l 75 RCIC Pump Turbine Exhaust Vacuum Pelief 151 2 12 76B RHR Shutdown Suction Relief Valve Discharge to suppression Pool 02 12 l

1 81 Reactor Pecirculation Post Accident sample 20 2 12 82 ILRT Drywell Pressurization /

l Depressurization 02 11 83 PWCU Line from Pegenerative Heat Exchanger l to Teodwater 299 2 12 1 04 Drywell and Containment Chemical Waste 02 11 85 Suppression Pool Cleanup peturn 304 t 19 l 86 Dominera11ted Water Supply to containment 01 12 87 PWCU Punp Suetion from Peeirculation Loops 0t li 80 PWCU Pump Discharge to RWCU Heat Exchanger 01 17

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[)V APPENDfX C (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)

(Maximum Pathway Leakage)

Penetration Description Leakace, ECC" 101C Drywell Pressure Instrumentation (Narrow Range) Ot 11 101r Drywell Pr,ssure Instrumentation (Wide Range) 30 2 11 1020 Drywell Pressure Instrumentation (Wide Range) 02 11 103D Containment Pressure Instrumentation (Wide Range) 02 12 i

104D Containment Pressure Instrumentation (Wide Range) 02 12 10$A Containment Hydrogen Analyzer Sample 02 11 106A Drywell Hydrogen Analyzer Sample 02 11 106B Drywell Hydrogen Analyzer Sample Return S2 11 106E Containment Hydrogen Analyzer Sample Return 01 11 107B Containment Hydrogen Analyzer Sample Neturn 02 12 107D Drywell Hydrogen Analyzer Sample 01 12 107E Drywell Hydrogen Analyzer Sample 0 2 11 i 108A containment Hydrogen Analyzer Sample 02 11 Os 109A Drywell - rission Product Monitor Sample 02 11 109B Drywell - Fission Product Monitor Sample Return 02 12 109D Containment Pressure Instrumentation (Harrow Range) 02 12 110A ILRT Instrumentation (Drywell Pressure) 02 11 1 110C ILRT Instrumentation (Verification Flow) 02 11 110F ILRT Instrumentation (Containment Pressure) 02 11 ,

114 Suppression Pool Water Level Instrumentation 0 2 12 116 Suppression Pool Water Level Instrumentation 0 2 12 110 Suppression Pool Water Level Instrumentation 0 2 11 120 Suppression Pool Water Level Instrumentation 0 2 11 TOTAL = 26,734 1 306 I

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~'} APPENDIX C (Cont'd)

(V Local Leakage Test Summary Data Type C Test Results (Hydraulic)

Penetration Description Leakage, M1/ Min 11 RHR Pump A Suction 010 12 RHR Pump B Suction 53 2 1 13 RHR Pump C Suction 02 0 23 RHR A Pump Test Return Line to suppression Pool 020 24* RHR C Pump Test Return Line to Sappression Pool N/A 25 HPCS Pump Suction 020 27 HPCS Test Return Line to Suppression Pool 020 20 RCIC Pump Suetion 020 29 RCIC Turbine Exhaust 17 1 1 30 LPCS Pump Suetion 020 32* LPCS Test Return Line to Suppression Pool N/A 46 RCIC Pump Discharge Minimum Flow Line 011 48 RHR Heat Exchanger B Relief Valve Discharge To Suppression Pool 15711 67 RHR Pump B Test Return Line To Suppression Pool 5311 g-~3

( j 69 Refueling Water Transfer Pump Suction

! From Suppression Pool 020 71A LPCS Relief Valve Discharge to Suppression Pool 010 71B RHR "C" Relief Valve Discharge to Suppression Pool and Post-Accident Sample Return 010 77 RHR Heat Exchanger A Relief Valve Discharge to Suppression Pool 01 1 89 Standby Service Water Supply A 010 90 Standby Service Water Return A 020 91 Standby Service Water Supply B 020 92 Standby Service Water Return D 010 113 Suppression Pool Water Level Instrumentation 0 1 0 115 Suppression Pool Water Level Instrumentation 0 2 0 117 Suppression Pool Water Level Instrumentation 0 1 0 119 Suppression Pool Water Level Instrumentatiot. 0 1 0 TOTAL = 280 1 2.4 l

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• Penetration 24 and 32 test return line were extended into the Suppression Pool below the minimum drawdown level during the outage.

I Hydraulic local leakage test is specified by Tech. Specs.# however, pneumatic leakage test results are current, pneumatic testing is conservative, and results are included in Type B and C totals. The next

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scheduled leakage tests on these penetrations will be with water.

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J APPENDIX D 4

SUMMARY

OF MAJOR MODIFICATION 3 i AND COMPONENT REPI.ACEMENTS i

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,m APPENDIX D Summary of Major Modifications And Component Replacements

1. Carbon steel' instrument air piping and valves through Penetration 70 were replaced with stainless steel components to prevent corrosion particles from contaminating the air supply to the Automatic Depressurization System. The following Type C tests were performed:

Component Date Leakage (SCCM)

Penetration 70 pipe seal 6-6-83 0 Weld to containment wall Valve Q1PS3F006 9-8-83 40 Valve Q1P53F003 9-9-83 10 Valve Q1P53F043- 9-9-83 0

2. The carbon steel disk in Feedwater (Penetration 10) outboard isolation check valve OlB21F032B was replaced with a stainless steel disk due to concerns about fracture toughness. At the time the work was completed, Type C testing of the feedwater check valves was not required by the GGNS local leak rate testing

/' N program. Work completed on 5-4-84.

3. A motor-operated 6-inch gate valve (01E12F394) was welded into the RPV head spray line to replace check valve QlE51F066 as the inboard containment isolation valve on Penetration 17, due to the difficulty of performing Type C tests on Q1E51F066. The modification changed the containment isolation boundary so that 1-inch drain valve QlE12F344, which was previously a containment isolation valve, is now outside the containment isolation boundary. After the new gate valve was connected electrically and stroke tested, a Type C test on 10-22-85 indicated no leakage.

4. The plugs on feedwater inboard isolation plug-check valves Q1B21F010A (Penetration 9) and Q1B21F010B (Penetration 10) were replaced with plugs with resilient seating surfaces to enable the valves to pass Type C tests. Prior to the replacements, the test volumes could not be pressurized to Type C test pressure. Type C tests performed after the. replacements were as follows:

Component Date Leakage (SCCM)

Q1B21F010A 10-27-85 59 Q1B21F010B 10-25-85 814

5. Residual Heat Removal Loop C (Penetration 24) and Low Pressure Core o

o D-1

(> APPENDIX D (cont'd)

Summary of Major Modifications And Component Replacements (cont'd)

Spray (Penetration 32) pump test return pipes were extended down into the Suppression Pool to below the minimum drawdown level by welding spoolpieces (approximately 18 inches long) to each pipe.

No Type B or C tests were performed because the previous Type B and C tests on the isolation valves are current. The penetrations now meet the requirements 10CFR50, Appendix J, Paragraph III.C.3 for valves sealed with fluid; hence, the next local leak rate tests of the isolation valves will be with water. Work was completed on Penetration 24 on 11-14-85 and on Penetration 32 on 11-25-85.

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J APPENDIX E

SUMMARY

REPORT OF TYPE A, B, AND C TESTS WHICH FAILED TO MEET 10CFR50, APPENDIX J ACCEPTANCE CRITERIA O

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y APPENDIX E

' Summary Report Of Type A, B, And C Tests Which Failed To Meet 10CFR50, Appendix J, Acceptance Criteria INTRODUCTION: This summary report provides details of Type B and C tests which failed to meet the acceptance criteria of 10CFR50, Appendix J, Paragraphs III.B.3 and III.C.3. The details of the Type A test which failed to meet the acceptance requirements of 10CFR50, Appendix J, Paragraph III. A.S. (b) . (2) , are described in the summary report to which this report is appended.

DISCUSSION: The following summary table provides details of Type B and C tests which were considered to have failed to meet the acceptance criteria of 10CFR50, Appendix J, Paragraphs III.B.3 and III.C.3. In each case, the actual leakage'resulting from the test could not be measured.

The Type B test was conducted with a bubble column test apparatus which provides only two results: No leakage (no bubbles in the bubble column) or test failure (bubbles observed). While it is probable that the leakage would have been very low if it had been measured-with a rotometer, this was not dones therefore, the leakage was conservatively considered infinite.

All of the Type C tests which failed were due to inability to pressurize the test volune to the required test pressure of 11.5 psig. The leakages were beyond the makeup capability of a 3/4-inch or 1-inch I. D. hose supplying air at approximately 90 psig to 110 psig. Due to the inability to pressurize the volumes as required to measure the leakages, each of the leakages was assumed to be infinite.

In each case where infinite leakage was determined, action was taken immediately to correct the problem and another Type B or C test was performed to verity that the corrective action was sufficient. The measured leakages were added to the combined Type B and C test totals. It should be noted that the combined Type B and C test totals at Grand Gulf have been determined conservatively by adding together the leakages from all of the components which are Type B or C tested. This method provides a significantly higher combined leakage than the Maximum Pathway Leakage method which is recommended in ANSI /ANS 56.8-1981.

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j t TYPE D AND C TEST IICH FAILED TO MFET \ -

10CFR50, APPENDIX J, ACCEPTANCE CRITERIA RETEST DATA COMPONENT COMPONENT DATE OF DESCRIPTION OF DESCRIPTION OF TYPE OF DATE MEASURED NUMBER DESCRIPTION TEST FAILURE FAILURE CORRECTIVE ACTION TEST OF TEST LEAKAGE (SCCM)

QlE12F041C 12" Swing Check 1-20-84 Test Volume could Lapped Seats C 1-23-84 0 Valve not be pressurized for Type C test QlE12D003C Orifice plate 1-20-84 Bubbles Detected Replaced orifice B 2-8-84 0 with double-O- during Type B plate and 0-rings ring seals on Test 18" line Q1G36F101 4" Air operated 12-1-84 Test volume could Replaced disk C 12-5-84 0 Gate Valve not be pressurized for Type C test Q1E12F028A 18" Motor 2-20-85 Test volume could Adjusted valve C 2-20-85 1688 operated not be pressurized closing torque Gate Valve for Type C test switch setting Q1E12F064C 4" Motor 3-7-85 Test volume could Replaced wedge C 3-8-85 0 operated Gate not be pressurized disk Valve for Type C test during retest for electrical work Q1B21F028D 28" Air operated 2-21-85 Test volume could Replaced poppet C 3-9-85 0 globe Valve not be pressurized with Poppet for Type C test QlE12F064C 4" Motor 10-24-85 Test volume could Adjusted valve C 10-24-85 0 operated Gate not be pressurized closing torque Valve for Type C test switch setting Q1B21F010B 24" Plug Check 10-19-85 Test volume could Replaced plug C 10-25-85 814 Valve not be pressurized with modified for Type C test plug having resilient seat QlB21F010A 24" Plug Check 10-17-85 Test volume could Replaced plug C 10-27-85 59 Valve not be pressurized with modified for Type C test plug having resilient seat E-2

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7 TYPE D AND C TESTS'\. CH FAILED TO MEET /

10CFR50, APPENDIX J, ACCEPTANCE CRITERIA RETEST DATA COMPONENT COMPONENT DATE OF DESCRIPTION OF DESCRIPTION OF TYF.= OF DATE MEASURED NUMBER DESCRIPTION TEST FAILURE FAILURE CORRECTIVE ACTION TECT OF TEST LEAKAGE (SCCM)

Q1E51F076 1" Motor 10-29-85 Test volume could Repacked valve C 11-2-85. 101 operated not be pressurized Globe Valve for Type C test due to packing leak Q1B21F022C 28" Air 11-3-E5 Leakage from vent Valves were C 11-7-85 4987 Q1B21F028C operated noted during Type determined to (Combined Globe Valves A test preparation. have been slow- Leakage) with Poppets 11-7-85 Test volume between closed prior to valves could not be Type A. test.

pressurized for valves were Type C test. opened and then fast-closed.

Q1B21F022D 28" Air- 11-3-85 Leakage from vent Valves were C 11-8-85 588 Q1B21F028D operated Globe noted during Type determined to have (Q1B21F022D valves with A test preparation. been slow-closed only)

Poppets 11-7-85 Test volume between prior to Type A Q1R21F022D and test. Valves were F028D could not be opened and then pressurized for fast-closed.

Type C test.

Q1B21F028D 28" Air 11-7-85 Test volume could Replaced stem and C 12-15-85 436 Operated not be pressurized lapped seat.

Globe Valve after Q1B21F022D with Poppet and F028D were opened and fast-closed.

Q1C41F151 2" Manual 11-3-85 Leakage from vent Cleaned valve C 11-17-85 29 Stop- noted during Type internals, lapped check Valve A test preparation. seat and disk.

11-7-85 Test volume could not be pressurized for Type C test.

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TYPE B AND C TEST IICH FAILED TO MEET '\ _

10CF R57, APPENDIX J, ACCEPTANCE CRITERI A RETEST DATA DATE OF DESCRIPTION OF DESCRIPTION OF TYPE OF DATE MEASURED COMPONENT COMPONENT TEST FAILURE FAILURE CORRECTIVE ACTION TEST OF TEST LEAKAGE (SCCM)

NUM'ER DESCRIPTION 12" Swing 11-8-85 Leakage of 10,000 Relapped disk and C 11-21-85 1472 Q1E12F041C Check Valve seem measured seat during Type C test.

11-17-85 After initial lapping, test volume could not be pressurized for Type C retest.

11-3-85 Leakage from vent Closed valve C 11-7-85 65 Q1C41F150 3" Manual Gate Valve noted during Type using valve A test preparation. wrench.

Also, noted stem Valve was very position indicated hard to close.

valve not fully Disassembled C 11-29-85 30 closed. valve, cleaned 11-7-85 Test volume could and lubricated not be pressurized stem and for Type C test. reassembled.

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