Text

Final Pilgrim Nuclear Power Station Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept
	ML20056E222
Person / Time
Site:	Pilgrim
Issue date:	05/19/1993
From:	; GENERAL PHYSICS CORP.
To:	;
Shared Package
ML20056E173	List: BECO-93-102, Forwards Final Pilgrim Nuclear Power Station Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept, for 930519; ML20056E222;
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l IlOSTON EDISON COMPANY O- Pilerim Nuclear Station Unit 1 l

l REACTOR CONTAINMENT BUILDING l 1NTEGRATED LEAKAGE RATE TEST -

l FINAL REPORT l

l O DOCKET NO. 50-293 OPERATING LICENSE NO. DPR-35 May 19,1993 GENERAL PilYSICS CORPORATION G P-R-643011 9308200327 930813 PDR ADOCK 05000293 p PDR .

r TABLE OF CONTENTS

1. INTRODUCTION .. . . . . 1 i

11. TEST SYNOPSIS . . 2 A. Pre-pressurization Activities .. . . .. 2 B. ILRT Test Summary Time-Line .. . . . . 3 C. Containment Pressurization . . . 3 D. Containment Atmosphere Stabilization . . . 4 E ILRT Test Period . . 4 i F. Veritication Test . . . 5 111. TFST DATA SUN 1 MARY 6 A. Plant Intonnation ... 6 g B. Technical Data 6 C. Test Results - Type A Test . . . 6 4

D. Test Results - Types B and C Tests . . . S ,

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E Integrated Leakage Rate Measurement System ... . 8 i F. Information Retained at Plant .. .. .. 10 IV. ANAINSIS AND INTERPRETATION . . . 12 A. Type B&C Penalties .. . . 12 i

B. Volume Change Corrections .. . . 13 C. Reported "As Left" ILR1 Results . . . .. 13 D. leakage Savings . .. . 13 j E. "As Found" Evaluation of the Containment . .... . 15 I

i V. REFERENCES . .... . 16 i

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TABLE OF CONTENTS ,

CONTINUED i i

APPENDICES Appendix A STAlllLIZATION PilASE DATA AND PLOTS Appendix B ILRT TEST DATA AND PLOTS j Appendix C VERIFICATION PilASE DATA AND PI_OTS

Appendix D INSTRUMENT SELECTION GUIDE CALCULATIONS Appendix E SENSOR LOCATIONS Appendix F DESCRil'l~ ION OF GENERAL PilYSICS ILRT COMPUTER PROGRAM !

Appendix G RFO 9 LOCAL LEAKAGE RATE TEST SUMMARIES l Appendix 11 1991/1992 LOCAL LEAK RATE TEST DATA i Appendix I 2301-74 FAILURE ANALYSIS TEAM REPORT I

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1. INTRODUCTION The Reactor Containment Building Integrated 12akage Rate " Type A" Test is performed to demonstrate that leakage through the primary reactor containment systems and components penetrating primary containment do not exceed the allowable leakage rates specified in the Plant Technical Specifications.

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

The section of this report entitled Test Synopsis "Section 11" presents the highlights of activities and events which occurred prior to and during the ILRT.

Test Data Summary "Section 111" contains data and results necessary to demonstrate containment atmosphere stabilization, acceptable leakage rate, and successful verification test. In adJition, plots provided in Appendices B and C supply a visual history of containment atmospheric conditions beginning with the eight-hour test period and ending with the veritication test.

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

Section V lists the documents referenced for the conduct of the ILRT.

The successful periodic Type A and verification tests were performed according to the l requirements of the Pilgrim Nuclear Power Station, Technical Specifications and 10CFR50, Appendix J. The test method utilized is the Absolute Method described in l ANSI /ANS 56.8-1987, " Containment System Leakage Testing Requirements". Leakage rate was calculated using formulas from BN-TOP-1, Revision I,1972, (Total Time Analysis technique) during the Type A and verification tests. Formuhis from ANSI /ANS 4 56.8-1987 (Ma's Point Analysis) were run concurrently for informational purposes only. g i Type A and verification test durations were conducted according to the criteria of Pilgrim !

Nuclear Power Station, Plant Technical Specifications. !

i The test results are reported in accordance with the requirements of 10CFR50, Appendix J.Section V.B.3. :

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!!. TFST SYNOPSIS l

Prior to containment pressunzation on May 18,1993, Pilgrim Nucicar Power Station site l test and maintenance personnel were engaged in activities related to containment leakage, Containment leakage was identified through the Type B and C local leakage rate testing ,

programs and teduced by repairs to those systems and containment components having l excessive leakage.

The following discussion highlights some of the most significant activities encountered l during test preparation and execution and presents these items in a chronological order. !

A. Pre-pressurization Activities l Pre-pressurization activities included: Completing all Type B and Type C testing;

] Type A test procedure review; final ILRT instrumentation operability checks: final l ILRT computer program modifications; containment subvolume weighing factor ;

- calculation checks and sensor failure analysis. A few of these items are discussed ;

1 below to present pertinent information that impacted on Type A Test activities.

The Type A test procedure review was conducted to ensure that all references to

Plant Technical Specifications; 10CFR50, Appendix J; BN-TOP-1, Rev.1,1972; ANSI /ANS 56.S-1987; and the FSAR were accurate and current. l l

A containment area temperature survey was conducted in 1987 to verify proper ;

i sensor placement for the proposed test ventilation as required by ANSI N45.4-1972 paragraph 7.4 and ANSI /ANS 56.8 paragraph 5.5.1. The results of this 1

survey were used to validate the ILRT measurement system sensors. ;

i Final ILRT instrumentation operability checks were performed to ensure that all l instrumentation was operating correctly. An in-situ check, as specified in ANSl/ANS 56.8-1987, Section 4.2.3.1, was conducted to verify that all ILRT

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instrumentation was working correctly. Calibration records for all ILRT i l measurement system component calibrations,in-situ loop checks, and for all field

! standards used are retained at the plant. j l

lecal leakage rate testing at Pilgrim Nuclear Power Station were completed prior l to the start of the ILRT. The results of this program are summarized in Appendix l

G, " local Leakaec Test Summaries" l l

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i B. ILRT Test Summary Time-Line Phase Time Frame - Duration' ;

Pressurization From: 1506 on 5/18/93 11.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l To: 0213 on 5/19/93 !

Stabilization From: 0215 on 5/19/93 4.00 hours0 days 0 hours 0 weeks 0 months l To: 0615 on 5/19/93 !

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lloid Test From: 0615 on 5/19/93 8.00 hours0 days 0 hours 0 weeks 0 months !

To: 1415 on 5/19/93 1.cak Stab. From: 1630 on 5/19/93 1.00 hour0 days 0 hours 0 weeks 0 months Verit. Test To: 1730 on 5/19/93 Veritication From: 1730 on 5/19/93 5.00 hours0 days 0 hours 0 weeks 0 months !

Test To: 2230 on 5/19/93 i Depress (includes From: 2245 on 5/19/93 18.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

performance of To: 1700 on 5/20/93 l' drywell to toms vacuum break.er !eak {

rate test )

i C. Containment Pressurization i l

Containment pressurization started at 1506, on May 18, 1993 using two j compressors with a total rating of 2400 scfm. Pressurization proceeded at a rate I which did not exceed the procedural limit of 8 psi /hr. Compressor discharge l valves were manually throttled to maintain backpressure and flowrate. Aftercooler j cooling water flow was manually throttled to maintain compressor air discharge ;

temperature. No fans were running in the containment during the ILRT itself or -i verification test. {

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I At 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on May 18,1993, a 15 psig containment walkdown was performed to identify any potential leaking penetrations. No significant leakage was ;

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i Containment test pressure of 61.2058 psia was reached at 0213 hours0.00247 days 0.0592 hours 3.521825e-4 weeks 8.10465e-5 months on May 19, 1993 and the compressors secured. j I

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D. Containment Atmosphere Stabilization l l

Stabilization was commenced at 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months on May 19,1993. i By 0615 on May 19,1993, the stabilization criteria of BN-TOP-1, Rev.1, and j i ANSI 56.8-1987, section 5.3.1.6 were met and the contained air mass had j stabilized. l I

c E. ILRT Test Period

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Subsequent to meeting the temperature stabilization criteria, leakage rate analysis ;

began at 0615 on May 19,1993. ;

By 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months (sesen hours into a planned eight hour BN-TOP-1 test), the l measured total time and mass point leakage rates had stabilized at approximately ;

O.128% wt./ day. j

? i l At approximately 1328 hours0.0154 days 0.369 hours 0.0022 weeks 5.05304e-4 months , the plant experienced a loss of offsite power. All- !

ILRT instrumentation was connected to an uninterruptible power supply and j continued to function. However, containment isolation valves AO-5035A and AO- l 5036A, which were open to provide communication between the drywell and j torus, closed, in addition, the loss of offsite power caused a loss of shutdown !

cooling flow which created changes in reactor vessel level and temperature. !

i Minor fluctuations occurred in the ILRT data from 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months until 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months . l At 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months , after eight hours of ILRT data, the calculated total time leakage i rate was 0.1289% wt./ day and the mass point leakage rate was 0.1331% wt./ day. i As the plant was still recovering from the loss of offsite power, the verification j

test was not started and ILRT data collection continued. From 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months until j approximately 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months , a significant increase in containment mass resulted i from changes in reactor vessel level due to re-establishing shutdown cooling flow. !

f By 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months , containment mass data confirmed that the plant had recovered l from the loss of offsite power and operations had stabilized reactor vessel level L and temperature. (Refer to Mass Plot in Appendix B). During the stabilization j and hold test periods, the instrumentation was continuously monitored. ;

Since the data from 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months until 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months was significantly disturbed by j plant recovery operations, the ILRT was considered successfully completed at l' 1415 on May 19,1993. This represents an eight (8) hour test and the containment leakage rate data met all the requirements of BN-TOP-1, Rev.1 necessary to end i the hold test in less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The maximum allowable leakage rate (L,) for -l the primary containment is 1.0% wt./ day of contained air mass at peak test [

pressure. The mass point and total time analysis were run concurrently on the l General Physics ILRT Data Management Computer Program. The leakage rate ;

results are as follow:

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Total Time Analysis Mass Point Analysis

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

Calculated Isakage Rate From Regression Line 0.1289 0.1331 95% Upper Confidence Limit 0.2158* 0.1405*

20 Point Mean Leakage 0.1573 Doe:, not include penalties for nonstandard alignments and water level t changes. i F. Verincation Test A successful verification How test was conducted following the ILRT. At 1630, a leakage of 7.54 sefm was imposed an the primary containment and allowed to stabilize for one hour. The verification test phase started at 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on May ,

19,1993 and was completed at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months on the same day. The 7.54 sefm leak l imposed (L,,) on the existing measured leakage was slightly larger than L,(1.0 % l wt.! day) at 1.0106% wt./ day. The results stabilized (as shown on the graph !

contained in Appendix C) within the i 25% L, acceptance criteria and are {

summarized below: i

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Total Time Analysis Mass Point Analysis :

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

lxakage Rate (L ,,j 0.1289 0.1331 i t

imposed lxak (L,,) 1.0106 1.0106 l lewer limit:

L,. + L,,,, - 0.25 L, 0.8895 0.8937 i i

Composite Ixakage (L) 1.0934 1.0966

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Upper limit: !

L, + L,,, 4 0.25 L, 1.3895 1.3937 i i

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III. TEST DATA

SUMMARY

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A. Plant Information Owner Boston Edison Company

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Plant Pilgrim Nuclear Station Unit 1 -i I

Location Plymouth, Massachusetts .

Containment Type BWR Mark I i 4

NSSS Supplier, Type General Electric BWR 4 .

Date Test Completed May 19,1993 l

] i B. Technical Data .

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, 1. Containment l

Net Free Air Volume 263,520 cu. ft.

2. Design Pressure, P 56 psig i

3. Design Temperature, T 281F l i

4. Calculated Peak 45 psig .

Accident Pressure, P, l

5. Containment ILRT 60-120"F i Avg. Temp. Limits j

6. Calculat :d Peak 281*F Accident Temperature f C. Test Results - Type A Test :

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1. Test Method Absolute l i

l 2. Test Pressure 46.3 psig I

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Integrated Leakage Rate Total Time Analysis (Calculated per BN-TOP-1) 1 9 3.

Test Results:

a. Calculated Leakage Rate, from regression i line. L,, 0.1289 wt.%/ day i

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b. Upper 95Fo Confidence Limit 0.2158 wt.%/dav l

4. Integrated leakage Rate Mass Point Analysis Test Results (Presented for .

. information only): l l

a. Calculated Leakage J

, Rate, from regression l j line, L., 0.1331 wt.%/ day l 1

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b. Upper 95% Confidence j j- Limit 0.1405 wt.co/ day ;

i 5. Maximum Allowable - 1.000 wt.%/ day j Leakage Rate, L, j

6. ILRT Acceptance Criteria 0.750 wt.%/ day (75% of L,) l

7. Veritication Test imposed 7.54 scfm l i lxakace Rate (L ) (1.0106 wt.%/ day) i l

i 8. Verification Test Total Time Analysis Results and Limits :

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a. Upper Limit 1.3895 wt.G! day '

{ ( L + L,,,,, + 0.25 L,)

l l b. Verification Test 1.0934 wt.%/ day !

] Total Time Results !

, c. Lower Limit 0.8895 wt.%/ day j l (L + L ,,, - 0.25 L,) ;

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--...,_,-----._e_ , ,,,,,y._. , . , , . . , _, . . _ . _.,,.,.,_.,,y___,,,_m.. _ , . ., , , _ , _ . , . . - . , _ _ , . . . . . . . . _ , . _ . - - - - - . .

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9 Veri 0 cation Test Mass Point Analysis Results and Limits (Presented for information only) .j

a. Upper Limit 1.3937 wt.%/ day (L,,, + L, + 0.25 L ) j 1 ;

b. Verification Test 1.0966 wt5/ day Mass Point Results

c. Iwwer Limit 0.8937 wt&/ day :

(L,, + L,,, - 0.25 L,) l

10. Report Printouts The Repon Printouts of the Type A and verification test calculations are }

provided for the Mass Point and Total Time Analysis (Appendices B and i C). Stabilization data is also provided (Appendix A).

D. Test Results - Types B and C Tests j

A summary of local leakage rate test results since the last ILRT in August 1991 are provided in Appendices G and H. A failure analysis team report for valve 2301-74 is provided in Appendix 1.

E. Integrated Leakage Rate Measurement System

1. Absolute Pressure (2 Sensors) ,

J Type Paroscientific Precision Pressure t

Range 0-100 psia l

! Accuracy 1 0010 psia l i

Repeatability 0.010 psia ;

Sensitivity 0.0005 psi j 1

Resolution 0.0001 psi i Calibration Date 4/29/93 Instrument Numbers: CCGPC24210, CCGPC28778 8

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2. Drybulb Temperature (18 Sensors)

I 1 i i-- Type 100 ohm platinum RTDs i Calibrated Range 60-110*F .

. J Accuracy 1 05"F .

Repeatability 1 0.l*F .

i Sensitivity 0.001*F j Resolution 0.001"F i Calibration Date 4/18/93 1

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3. Dewpoint Temperature (10 Sensors) I 1 Type Foxboro Lithium Chloride Deweels i Calibrated Range 37.5-100*F 2

Accuracy 1.5"F

. Repeatability 0.5"F I Sensitivity 0.5"F Resolution 0.001"F

, Calibration Date 4/20/93 I

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. 4. Veri 6 cation Flow (1 Channel plus 1 Spare) 4 i Flow Meter Datametrics Thermal Mass Flowmeters e

Range O to 15 scfm Accuracy 11% FS Sensitivity .1 % FS Repeatability .01% FS Calibration Date 12/29/92 O

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p'yw g Ny - -7.-- -w 1-'gyy- y-r-w 'm-* -

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5. Data Acquisition System t

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i Type Fluke Model 2285B !

Drybulb Signal Conditioning / Readout

) 1) Repeatability: 1 0.001"F i 2) Resolution: 0.001"F i

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, Dewpoint Signal Conditioning / Readout 9 .

1) Repeatability: 10.001"F ;

2) Resolution: 0.001"F

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j Calibration Date 4/27/93

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5. Overall Instrumentation Selection Guide (ISG) Value frem ANSI /ANS- ,

56.S-1987 based on ILRT instrumentation configuration at end of ILRT ;

and an eight hour test = 0.0567% wt./ day (see Appendix . D for calculations). !

i l 6. Sensor Locations and Volume Fractions ;

. I i Appendix E, Sensor Locations contains descriptions of the sensor locations ;

i as installed for the 1993 ILRT. t i

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4 F. Information Retained at Plant I

The following information is available for review at the facility. ;

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1. Access controls th:t were established to limit ingress to containment j during testing. ;

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j 2. A listing of all containment penetrations, including the total number oflike j

! penetrations, penetration size, and function. j

- i j 3. A listing of normal operating instrumentation used for the leakage rate test. j i

1 i 4. A system lineup (at time of test), showing required valve positions and i

! status of piping systems.

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l 5. A continuous, sequential log of events from initial survey of containment l

! to restoration of all tested systems.

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6. Documentation of instrumentation calibrations and standards. j

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

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8. The working copy of test procedure that includes signature sign-off of .

procedural steps. ,

9. The procedure and all data that verifies completion of penetrations and valve testing (B&C-type tests), including as-found leak rates, corrective action taken, and final leak rate.

10. Computer printouts of Integrated Leakage Rate Test Data and automated ;

data accumulation along with summary description of computer program. ,

11. The Quality Assurance surveillance checklist that was used to monitor ILRT with proper sign-offs.

12. A listing of all test exceptions including changes in containment system ;

boundaries instituted by licensee to conclude successful testing.

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13. A review of confidence limits of test results with accompanying computer i printouts where applicable. ;

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14. Description of method ofleakage rate verification ofinstrument measuring ;

system (superimposed leakage), with calibration information of flowmeters along with calculations that were used to measure the verification leakage l rate (Appendix C).

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15. Plot presenting ILRT data obtained during the test (Appendix B). l

16. The P&lDs of pertinent systems.

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i IV. ANAINSIS AND INTERPRETATION f The upper 95% confidence limit (UCL) Total Time and Mass Point leakage rates calculated during the ILRT were less than the test acceptance criteria of 0.75 L,(0.750

% w1Jday). Corrections for penetration paths not exposed to the ILRT pressure and for I changes in the net free volume due to changes in containment water levels must be l considered for addition to the calculated results of the ILRT.

i A. Type B&C Penalties The following cortections must be added for valves / penetrations which were not in their normal post-accident condition: ,

l Penetration Description Irakage (SLM) ?

i 9A Feedwater (including RCIC and RWCU) 0.005 9B Feedwater (including 11PCI) 0.025 l 12 Residual Heat Removal (Shutdown Cooling) 0.399 ;

t 14 Reactor Water Clean-Up 0.387 j i

23 Reactor Building Closed Cooling Water Supply 0.005 24 Reactor Building Closed Cooling Water Supply 0.004 40Aa Jet Pump Sensing - Post Accident Sampling 0.006 40Dc Jet Pump Sensing - Post Accident Sampling 0.006 41A Recire Sampling 0.005 46A Reactor Recire Seal 0.986 46B Reactor Recire Seal 3.818 47 ILRT Instmmentation 0.066 47 ILRT Instrumentation 0.066 223 HPCI Turbine Exhaust 0.014 223 11PCI Turbine Exhaust 0.095 228G Post Accident Sampling 0.195 22811 Post Accident Sampling 0.004 leakage Summation 6.086 The LLRT results based on the above equate to a Type B and C penalty addition of0.0288 %wt./ day.

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B. Volume Change Corrections The tollowing corrections are made for any liquid level changes which resulted in an decrease in the net free volume of the containment:

Containment Volume Momtored Level Change Volume Change Reactor Vessel + 6.799 inches /8 hours - 204.52 cu. ft./ day Torus + 0.0160 inch /8 hours - 37.63 cu. ft./ day Equipment Drain Sump +697 gallons /66 hours - 33.88 cu. ft./ day l

Floor Drain Sump D 0 l Total Volume Change - 276.03 cu. ft./ day Based on the volumes monitored, the containment net free volume decreased during the ILRT by 276.03 ft' This is equivalent to a leakage rate of 0.1047

%'dav which will be added to the ILRT results.

l l C. Reponed "As lx"t" ILRT Results l !

l The results of the ILRT to be reported including all corrections are: l l

Total Time Analysis Mass Point Analysis l

("h wt./ day) (G wt./ day) j i

95% UCL Leakage Rate 0.2158 0.1405 Volume Correction 0.1047 0.1047 l

Type C Penalty Addition 0.0288 0.0288 "As Left" leakage Rate 0.3493 0.2740 j

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l The "as left" Total Time and Mass Point 95% UCL leakage rates are less than the test acceptance criteria value of 0.75 L, (0.750 % wt./ day). l D. leakage Savings ;

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1 The following corrections must be added for valves / penetrations which were j i repaired and/or adjusted prior to the ILRT: ;

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I Niin. Path Niin. Path Leakage Pen. As Found As Left Savings t i

N o. Description (SLN1) (SLNI) (SLN1) l Drywell Head 0.059 0.010 0.049 i Equipment flatch 0.006 0.004 0.002 l

6 CRD 11atch 0.003 0.003 0 16A Core Sprav 0.001 0.003 0

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23 RBCCW Supply 0.070 0.005- 0.065 ;

25 Drywell Exhaust 0.748 0.177 0.571 ,

35A TIP 0.092 0.073 0.019 i 35B TlP 0.092 0.073 0.019 35C TIP 0.044 0.683 0 l

1 35D TIP 0.044 0.683 0 l 39A RilR Containment Spray 0.123 0.006 0.117 j 1

41 Recire Pump Sample 0.005 0.002 0.003 i q

i 51A RHR Injection 0.222 0.385 0 I

52 IIPCI Steam Supply 0.036 0.036 0 i

53 RCIC Steam Exhaust 0.028 0.002 0.026 j a

j 200B Torus Hatch North 0.021 0.110 0 :

211A RHR to Torus 0.153 0.023 0.130 l i

223 HPCI Exhaust Inboard Flange 0.002 0.002 0 j j

223 IIPCI Exhaust Outboard Flange 0 002 0.002 0 ;

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, 'l l 223 HPCI Exhaust 1.778 0.137 1.641 ;

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"6 RCIC Exhaust inboard Flange 0.001 0.001 0 :

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225 RCIC Exhaust Outboard Flange 0.001 0.001 0 l leakage Summation 2.642

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I The LLRT results based on the above equate to a Type B and C leakage savings j addition of 0.0125 %wt./ day. ;

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j E. "As Found" Evaluation of the Containment l t

The results of the ILRT to be reported including all corrections for repair and/or

adjustments are: ).

k Total Time Analysis Mass Point Analysis l i (% wt./ day) (% wt.! day) j i

A i "As-Left" UCL lxakace Rate 0.3493 0.2740 l j leakage Savings 0.0125 0.0125 l l "As-Found" Leakace Rate 0.3618 0.2865 1 !

The "as found" Total Time and Mass Point 95% UCL leakage rates are less than i

the test acceptance criteria of 0.75 L, (0.750 % wt./ day). j i

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h 4 i V. REFERENCES i

i A. Pilgrim Nuclear Power Station. FSAR.

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' B. Pilgrim Nuclear Power Station, Technical Specifications.

i l C. Pilgrim Nuclear Power Station, Procedure 8.7.1.4.2 Rev.10, Integrated Leakage ;

Rate Test Surveillance Procedure. !

I D. Code of Federal Regulations, Title 10, Part 50, Appendix J. Primary Reactor l Containment leakage Testing for Water Cooled Power Reactors.

E ANSI /ANS 56.8-1987, Containment System leakage Testing Requirements. .

1 F. Bechtel Topical Repon BN-TOP-1, Test,ag Criteria for Integrated Leakage Rate '!

Testing of Primary Containment Structures for Nuclear Power Plants, Revision 1, i

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197' ;

i G. /CiSI N45A-1971, leakage-Rate Testing of Containment Structures for Nuclear i Roactors i

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I Appendix A STABILIZATION PIIASE DATA l i

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l STABLIZATION MODE TIME : 0615 !

OPTIONS MODE

SUMMARY

l 1 - MANUAL DATA ENTRY #~OF DATA POINTS = 17 2- PARAMATER GRAPils MODE DURATION (IN llRS) = 4.00 l 3 - SENSOR PLOTS TOT TIME MEASURED LEAK = 0.2185 l 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK = 0.1048 )

5 - ANSI STABILIZATION CRITERIA TOT TIME 95% UCL = 0.3816 :

MASS PT LEAK = 0.I738 -!

6 - DN-TOP-I STAH. CRITERIA 7 - ANSI CRITERIA PRINTOUT MASS PT 95% UCL = 0.2007 8 - BN-TOP-1 CRITERIA PRINTOUT l 9 - REPRINT CURRENT DATA POINT !

P - PASS WORD MENU !

O - FLASil OFF j ANSI TEMPERATURE STABLIZATION CRITERIA MET i UN-TOP TEMPERATURE STABLIZATION CRITERIA MET l POINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT )

l J

AVG TEMP: 74.788/ -0.042 AVG PRESS: 60.687/ -0.006 :

MASS: 80765.72/ -1.242 AVG DEW PRESS: 0.3677/-0.0007 [

TOTAL PRESS: 61.055/ -0.006 l i

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O STABLE MODE PILGRIM NCCLEAR POWER STATION UNIT I Page 1 STABILIZATION SDIMARY UNIT 1 ANSI 56.8 BN-TOP-1 TIME TEMP 1 HR 4 HR DIFF BN1 BN2 0.00 75.842 0.0000 0.0000 0.0000 0.0000 0.0000 0.2a ,5.719 0.0000 0.0000 0.0000 0.0000 0.0000 0.50 75.617 0.0000 0.0000 0.0000 0.0000 0.0000 0.75 75.529 0.0000 0.0000 0.0000 0.0000 0.0000 1.00 75.452 0.3901 0.0000 0.0000 0.0000 0.0000 1.25 75.381 0.3382 0.0000 0.0000 0.0000 0.0000 1.50 75.308 0.3083 0.0000 0.0000 0.0000 0.0000 1.75 75.243 0.2856 0.0000 0.0000 0.0000 0.0000 2.00 75.187 0.2645 0.0000 0.0000 -0.3273 0.0000 2.25 75.130 0.2505 0.0000 0.0000 -0.2944 0.1317 2.50 75.074 0.2340 0.0000 0.0000 -0.2711 0.0929 2.75 75.022 0.2212 0.0000 0.0000 -0.2534 0.0710 3.00 74.971 0.2160 0.0000 0.0000 -0.2402 0.0527 3.25 74.921 0.2092 0.0000 0.0000 -0.2299 0.0414 3.50 74.875 0.1992 0.0000 0.0000 -0.2166 0.0531 3.75 74.830 0.1923 0.0000 0.0000 -0.2068 0.0392

() 4.00 74.788 0.1839 0.2636 -0.0798 -0.1999 0.0274 O

l l

i STABLE MODE 1

PILGitIM NL'CLEAlf POWEft STATION LINIT 1 Page 1

]

l LEAKAGE ItATE SI:MMARY IJNIT I TOTAL TIME MASS POINT l

) DATE TlME TTLM LMCALC 1CL LAM LCL )

1 l

l 139 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 t 139 0.25 0.9639 0.0000 0.0000 0.0000 0.0000 139 0.50 0.7523 0.7523 0.0000 0.7538 1.7970

139 0.75 0.5298 0.5316 0.5749 0.5310 0.9404 i 139 1.00 0.4527 0.4113 0.6805 0.4254 0.6631

I 139 1.25 0.4100 0.3403 0.6398 0.3689 0.5262 l 139 1.50 0.3599 0.2835 0.5761 0.3207 0.4397 139 1.75 0.3444 0.2487 0.5483 0.2949 0.3852 t 139 2.00 0.3181 0.2200 0.5186 0.2724 0.3450 i 139 2.25 0.3041 0.1991 0.4975 0.2564 0.3157 :

139 2.50 0.2855 0.1809 0.4765 0.2412 0.2915 !

a 139 2.75 0.2497 0.1586 0.4457 0.2191 0.2665

! 139 3.00 0.2481 0.1437 0.4277 0.2065 0.2484 ;

i 139 3.25 0.2367 0.1308 0.4122 0.1952 0.2326 :

139 3.50 0.2274 0.1199 0.3990 0.1861 0.2196 l 139 3.75 0.2233 0.1115 0.3893 0.1793 0.2093 1 139 4.00 0.2185 0.1048 0.3816 0.1738 0.2007 l 5 !

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i STABLE MODE Page 1 AVERAGE DATA VALUES j DATE TIME RTD DEW PT. VAP PRESS TOT PRESS MASS 4

139 0.00 75.842 70.787 0.373 61.202 80795.14 139 0.25 75.719 70.839 0.373 61.183 80787.03 ;

139 0 50 75.617 70.923 0.375 61.169 80782.48 139 0.75 75.529 70.887 0.374 61.158 80781.77 '

139 1.00 75.452 70.880 0.374 61.147 80779.90 139 1.25 75.381 70.838 0.373 61.137 80777.88 1

139 1.50 75.308 70.829 0.373 61.128 80776.97 139 1.75 75.243 70.847 0.374 61.120 80774.85 139 2.00 75.187 70.791 0.373 61.112 80773.73 139 2.25 75.130 70.742 0.372 61.103 80772.12 139 2.50 75.074 70.704 0.372 61.096 80771.12 139 2.75 75.022 70.557 0.370 61.089 80772.03 139 3.00 74.971 70.590 0.370 61.082 80770.09 4

139 3.25 74.921 70.509 0.369 61.074 80769.24 i i 139 3.50 74.875 70.477 0.369 61.068 80768.35 l 139 3.75 74.830 70.441 0.368 61.062 80766.96 l 139 4.00 74.788 70.383 0.368 61.055 80765.72 t

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DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 03:45 a Pressure Instruments in PSIA j channel pressure channel pressure

_______ ________ _-_____ ________ 3 i

1 +61.1119 2 +61.1279 i

RTDs in degrees F i channel temp. channel temp. channel temp. l 1 +81.485 2 +81.683 3 +82.448

4 +84.513 5 +78.462 6 +78.338 i 7 +77.508 8 +78.444 9 +77.265 10 +76.557 11 +74.686 12 +74.668 l 13 +72.972 14 +72.704 15 +75.466 ;

16 +73.574 17 +74.820 18 +73.696 i Dew Cell temperatures in degrees F

___________-_-___________-____--_-_-______--___-_-_____________-_ t channel cell temp channel cell temp :

1 +75.205 2 +76.577 '

3 +70.685 4 +71.414 5 +70.050 6 +66.906 l 7 +71.370 8 +71.259 '

9 +69.307 10 +71.088 AVERAGE TEMPERATURE = +75.3084 DEG. F ;

AVERAGE PRESSURE = +61.1283 PSIA MASS = +80776.97 LBM :

AVG DEW POINT TEMP = +70.8286 DEG. F i AVG VAPOR PRESSURE = +0.3733 PSIA 1

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PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE i DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 04:00 Pressure Instruments in PSIA channel pressure channel pressure 1 +61.1027 2 +61.1196 RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.452 2 +81.646 3 +82.404 4 +84.457 5 +78.432 6 +78.296 7 +77.447 8 +78.385 9 +77.220 10 +76.547 11 +74.655 12 +74.619 ,

13 +72.897 14 +72.646 15 +75.445 4 16 +73.483 17 +74.747 18 +73.606 .

t 1

Dew Cell temperatures in degrees F d

channel cell temp channel cell temp 1 +75.140 2 +76.541 3 +70.634 4 +71.160 +

5 +69.918 6 +66.979 7 +71.973 8 +71.750 i

. 9 +69.242 10 +71.080 l

i AVERAGE TEMPERATURE = +75.2433 DEG. F AVERAGE PRESSURE = +61.1196 PSIA MASS = +80774.85 LBM ,

AVG DEW POINT TEMP = +70.8466. DEG. F i AVG VAPOR PRESSURE = +0.3735 PSIA j 1

l

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PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 04:15 Pressure Instruments in PSIA channel pressure channel pressure l 1 +61.0953 2 +61.1112 i

l RTDs in degrees F l

_________________________________________________________________ i channel temp. channel temp. channel temp.

l 2 +81.620 +82.359 I 1 +81.420 3 4 +84.421 5 +78.413 6 +78.261 7 +77.397 8 +78.329 9 +77.159 10 +76.522 11 +74.643 12 +74.583 13 +72.837 14 +72.591 15 +75.408 l 16 +73.411 17 +74.676 18 +73.528 l l

l Dew Cell temperatures in degrees F i

channel cell temp channel cell temp :

t 1 +75.120 2 +76.548 3 +70.590 4 +70.967 5 +69.882 6 +66.842 7 +71.740 8 +71.176 9 +69.317 10 +71.114 t

AVERAGE TEMPERATURE = +75.1875 DEG. F AVERAGE PRESSURE = +61.1117 PSIA MASS = +80773.73 LBM AVG DEW POINT TEMP = +70.7905 DEG. F AVG VAPOR PRESSURE = +0.3728 PSIA .

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PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE l DATA POINT

SUMMARY

SHEET DATE : 139 I TIME : 04:30 i

_---__-___----____--_____----__________----_-__----_-_----_--_--- l Pressure Instruments in PSIA l channel pressure !

channel pressure 1 +61.0874 2 +61.1024 1 l

l RTDs in degrees F channel temp. channel temp. channel temp. j 1 +81.385 2 +81.593 3 +82.314.

4 +84.344 5 +78.383 6 +78.231 7 +77.340 8 +78.290 9 +77.107 10 +76.503 11 +74.611 12 +74.536 .

13 +72.782 14 +72.534 15 +75.372 16 +73.340 17 +74.606 18 +73.449 i Dew Cell temperatures in degrees F l

_--_____------_----__-__-_----______--_____---_-_-------____--___ i channel cell temp channel cell temp 1 +75.048 2 +76.487 3 +70.496 4 +70.848 5 +69.887 6 +66.702 )

7 +71.779 8 +71.155 l 9 +69.215 10 +71.070 j i

i AVERAGE TEMPERATURE = +75.1300 DEG. F AVERAGE PRESSURE = +61.1033 PSIA MASS = +80772.12 LBM ;

AVG DEW POINT TEMP = +70.7419 DEG. F AVG VAPOR PRESSURE = +0.3722 PSIA t

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PILGRIM NUCLEAR POWER STATION 1 ,

INTEGRATED LEAK RATE TEST TEST MODE : STABLE -

DATA POINT

SUMMARY

SHEET DATE : 139 i TIME : 04:45 i t

Pressure Instruments in PSIA channel pressure channel pressure j 1 +61.0794 2 +61.0953 ;

i RTDs in degrees F l-channel temp. channel temp. channel temp.

1 +81.353 2 +81.552 3 +82.270 i 4 +84.300 5 +78.361 6 +78.202 7 +77.293 8 +78.229 9 +77.053 i 10 +76.481 11 +74.587 12 +74.494

13 +72.709 14 +72.487 15 +75.339 16 +73.265 17 +74.543 18 +73.380 i

i Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +75.112 2 +76.488 !

3 +70.481 4 +71.010 ,

5 +69.788 6 +66.630 7 +71.584 8 +70.996 ;

9 +69.255 10 +71.103 ,

1 AVERAGE TEMPERATURE = +75.0744 DEG. F

+61.0958 AVERAGE PRESSURE = PSIA

) MASS = +80771.12 LBM AVG DEW POINT TEMP = +70.7041- DEG. F AVG VAPOR PRESSURE = +0.3717 PSIA i

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PILGRIM NUCLEAR POWER STATION 1 ;

INTEGRATED LEAK RATE TEST TEST MODE : STABLE !

DATA POINT

SUMMARY

SHEET DATE : 139 l TIME : 05:00 !

_________________________________________________________________ j Pressure Instruments in PSIA !

i channel pressure channel pressure l

1 +61.0724 2 +61.0881 ,

t i

b-RTDs in degrees F ;

channel temp. channel temp. channel temp. ;

1 +81.323 2 +81.516 3 +82.235 4 +84.257 5 +78.335 6 +78.192 7 +77.242 8 +78.179 9 +76.995 i 10 +76.464 11 +74.572 12 +74.449 i l

13 +72.665 14 +72.435 15 +75.310 ;

16 +73.185 17 +74.478 18 +73.318 !

Dew Cell temperatures in degrees F '

channel cell temp channel cell temp I 1 +75.055 2 +76.400 ,

3 +70.448 4 +70.891 I 5 +69.741 6 +66.602 '

7 +71.016 8 +70.989 ;

9 +69.028 10 +71.024 l t

+75.0221 AVERAGE TEMPERATURE = DEG. F AVERAGE PRESSURE = +61.0887 PSIA MASS = +80772.03 LBM :

AVG DEW POINT TEMP = +70.5570 DEG. F !

AVG VAPOR PRESSURE = +0.3699 PSIA i 6

F i

l 1

1

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 05:15 Pressure Instruments in PSIA channel pressure channel pressure :

1 +61.0655 2 +61.0814 i l

RTDs in degrees F !

t channel temp. channel temp. channel temp. .

1 +81.287 2 +81.478 3 +82.183 l 4 +84.214 5 +78.315 6 +78.169 i 7 +77.193 8 +78.131 9 +76.963 !

11 +74.550 12 74.413 ;

10 +76.447 13 +72.608 14 +72.381 15 +75.270 :i 16 +73.124 17 +74.412 18 +73.257 ;

i i

Dew Cell temperatures in degrees F ,

channel cell temp channel cell temp 1 +74.919 2 +76.365 l 3 +70.377 4 +70.825 5 +69.736 6 +66.600 l 7 +71.295 8 +70.988 9 +69.074 10 +71.072 i t

i AVERAGE TEMPERATURE = +74.9715 DEG. F ;

AVERAGE PRESSURE = +61.0819 PSIA !

MASS = +80770.09 LBM !

AVG DEW POINT TEMP = +70.5896 DEG. F :

AVG VAPOR PRESSURE = +0.3703 PSIA !

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PILGRIM NUCLEAR POWER STATION 1 i INTEGRATED LEAK RATE TEST TEST MODE : STABLE !

DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 05:30 i i

t I

-Pressure Instruments in PSIA channel pressure channel pressure j 3

1 +61.0588 2 +61.0733 :

i I

l RTDs in degrees F :

I -----------------------------------------------------------------

l channel temp. channel temp. channel temp. <

r l

1 +81.254 2 +81.438 3 +82.133 ;

4 +84.135 5 +78.284 6 +78.155 l 7 +77.141 8 +78.088 9 +76.917 ;

l 10 +76.437 11 +74.529 12 +74.371 i l

I 13 +72.549 14 +72.331 15 +75.222 !

16 +73.051 17 +74.362 18 +73.198 I

l l ----------------------------------------------------------------- l Dew Cell temperatures in degrees F l l channel cell temp channel cell temp ,

1 +74.969 2 +76.285 I 3 +70.325 4 +70.806 l l 5 +69.769 6 +66.527 i 7 +71.011 8 +70.968 9 +68.958 10 +70.964 [

1 l

I i

AVERAGE TEMPERATURE = +74.9208 DEG. F l i AVERAGE PRESSURE = +61.0745 PSIA :

l MASS = +80769.24 LBM }

l AVG DEW POINT TEMP = +70.5091 DEG. F !

l AVG VAPOR PRESSURE = +0.3693 PSIA i

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i PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE j DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 05:45 l

(

Pressure Instruments in PSIA f channel pressure channel pressure l i

1 +61.0525 2 +61.0671 i i _________________________________________________________________ {

I RTDs in degrees F temp. I channel temp. channel temp. channel 1 +81.221 2 +81.408 3 +82.088 4 +84.088 5 +78.265 6 +78.132 !

7 +77.103 8 +78.045 9 +76.869 !

10 +76.414 11 +74.516 12 +74.337 '

13 +72.499 14 +72.285 15 +75.204 16 +72.985 17 +74.305 18 +73.141 ;

Dew Cell temperatures in degrees F l channel cell temp channel cell temp

_______ _________ _______ _________ j 1 +74.891 2 +76.295 !

3 +70.338 4 +70.643 !

5 +69.808 6 +66.480 7 +70.805 8 +70.983 9 +68.971 10 +70.977 +

t I

AVERAGE TEMPERATURE = +74.8752 DEG. F AVERAGE PRESSURE = +61.0682 PSIA MASS = +30768.35 LBM AVG DEW POINT TEMP = +70.4768 DEG. F I AVG VAPOR PRESSURE = +0.3689 PSIA l

l

, PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE 1 DATA POINT

SUMMARY

SHEET DATE : 139 ,

TIME : 06:00 i

i Pressure Instruments in PSIA channel pressure channel pressure 1 +61.0460 2 +61.0603 .

9 RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.187 2 +81.382 3 +82.048 4 +84.028 5 +78.245 6 +78.110 7 +77.055 8 +78.006 9 +76.831 10 +76.399 11 +74.491 12 +74.293 t 13 +72 454 14 +72.243 15 +75.187 16 +72.922 17 +74.252 18 -+73.087 W

Dew Cell temperatures in degrees F channel cell temp channel call temp 3

1 +74.938 2 +76.159 .

3 +70.227 4 +70.790 l 5 +69.598 6 +66.370 7 +71.126 8 +70.839 e 1

9 +68.890 10 +70.901 :

l 3

AVERAGE TEMPERATURE = +74.8298 DEG. F !

AVERAGE PRESSURE = +61.0616 PSIA ,

MASS = +80766.96 LBM 3 AVG DEW POINT TEMP = +70.4413 DEG. F i AVG VAPOR PRESSURE = +0.3684 PSIA 1

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i PILGR1M NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : STABLE DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 06:15 i i

i i

Pressure Instruments in PSIA !

.i _________________________________________________________________

channel pressure channel pressure l 1 +61.0394 2 +61.0540 l 9

j RTDs in degrees F j i _________________________________________________________________

i- channel temp. channel temp. channel temp. ;

I 1 +81.152 2 +81.341 3 482.001 i 4 +83.982 5 +78.234 6 +78.098 !

7 +77.021 8 +77.965 9 +76.799 i

10 +76.382 11 +74.474 12 +74.261 l j 13 +72.406 14 +72.199 15 +75.144 ;

16 +72.863 17 +74.207 18 +73.036 !

l 4

i Dew Cell temperatures in degrees F j channel cell temp channel cell temp !

[

1 +74.831 2 +76.207 -i 3 +70.230 4 +70.686

5 +69.700 6 +66.431 ;

7 +70.577 8 +70.915 9 +68.865 10 +70.902 .

3 I

f AVERAGE TEMPERATURE = +74.7876 DEG. F i 4

AVERAGE PRESSURE = +61.0551 PSIA :

MASS = +80765.72 LBM l AVG DEW POINT TEMP = +70.3832 DEG. F !

AVG VAPOR PRESSURE = +0.3677 PSIA 1

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. . _ . _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ . _ ~ . _ . _ . . _ . . . _ . . = . _ . . _ _ _ . . _ . ._ . . _ . _ .

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Appendix B l O

4 ILRT TEST DATA AND PLOTS

i i

1 l

i TEST MODE PLEASE SELECT THE OPTION YOU WISH TO USE: TEST DATA 1415 1 -

MANUAL DATA ENTRY # OF DATA POINTS = 33 '

2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 8.00 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 0.1525 :

4 -

TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.1289 5 -

REPRINT CURRENT DATA PT TOT TIME 95% UCL = 0.2158 l 6 -

SENSOR DIFFERENTIALS MASS POINT LEAK = 0.1331 '

MASS POINT 95% UCL = 0.1405 75% La = .75 '

P -

PASS WORD MENU MASS = 80724.67 ,

4 SELECTED OPTION = f POINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 73.941 / -0.031 AVG PRESS: 60.561 / -0.003 MASS: 80724.67 / +0.469 AVG DEW PRESS: 0.3609 / -0.0011 TOTAL PRESS: 60.921 / -0.004 O

t t

l f

i 0

I

() i e

_ . _ . _ _ _ _ _ _ _ _ _ . . . _ . . _ _ = _ _ _ _ . _ .. . . _ . _ _ _ . - _

TEST MODE !

Page 1 l i

l I

AVERAGE DATA VALUES !

DATE TIME RTD DIM PT. VAP PRESS TOT PRESS MASS {

139 0.00 74.788 70.383 0.368 61.055 80765.72 139 0.25 74.747 70.345 0.367 61.050 80765.17 !

139 0.50 74.713 70.460 0.369 61.043 80759.93 139 0.75 74.679 70.395 0.368 61.038 80759.21 'l 139 1.00 74.G47 70.373 0.368 61.033 80757.22 !

139 1.25 74.612 70.423 0.368 61.028 80754.95 :

139 1.50 74.575 70.311 0.367 61.022 80754.66 !

139 1.75 74.541 70.325 0.367 61.017 80752.79 l 139 2.00 74.511 70.278- 0.366 61.012 80751.51 139 2.25 74.483 70.249 0.366 61.008 80750.61 139 2.50 74.452 70.252 0.366 61.002 80748.23 139 2.75 74.423 70.204 0.365 60.998 80747.76 l 139 3.00 74.394 70.243 0.366 60.994 80745.91 l 139 3.25 74.366 70.215 0.366 60.989 80744.82 !

139 3.50 74.341 70.194 0.365 60.985 80743.09 {'

139 3.75 74.310 70.209 0.366 60.981 80742.66 139 4.00 74.285 70.131 0.365 60.977- 80742.26 139 4.25 74.259 70.138 0.365 60.974 80741.70 139 4.50 74.236 i 70.121 0.364 60.971 80741.34 i 139 4.75 74.217 70.069 0.364 60.967 80740.26 !

139 5.00 74.193 70.076 0.164 60.964 80739.71 !

139 5.25 74.173 70.040 0.363 60.961 80739.11 j 139 5.50 74.153 70.003 0.363 60.958 80738.71 l 139 5.75 74.135 69.976 0.363 60.955 80737.27 !

139 6.00 74.114 69.97G 0.363 60.952 80737.63 139 6.25 74.094 69.961 0.362 60.949 80736.10 !

139 6.50 74.081 69.912 0.362 60.946 80735.30 139 6.75 74.060 69.899 0.362 60.942 80733.39 ;

139 7.00 74.045 69.884 0.361 60.939 80732.06 I 139 7.25 74.026 69.981 0.363 60.936 80729.49 139 7.50 74.003 69.900 0.362 60.931 80726.62 l 139 7.75 73.972 69.930 0.362 60.926 80724.20 l 139 8.00 73.941 69.840 0.361 60.921 80724.67 l

l l

1 l

l J

i i

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TEST MODE ,

PILGRIM NUCLEAR POWER STATION UNIT 1 Page 1 ,

i i

1.EAKAGE RATE TREND

SUMMARY

UNIT 1 !

TOTAL TIME MASS PCINT i

DATE TIME TTLM LMCALC CHANGE LAM CHANGE !

i 139 0.25 0.0645 0.0000 0.0000 0.0000 0.0000 l 139 0.50 0.3442 0.3442 0.3442 0.3430 0.3430 139 0.75 0.2576 0.3187 -0.0255 0.2949 -0.0480 !

139 1.00 0.2524 0.3013 -0.0174 0.2734 -0.0215 139 1.25 0.2560 0.2932 -0.0081 0.2666 -0.0068 ,

139 1.50 0.2191 0.2682 -0.0250 0.2389 -0.0277 i 139 1.75 0.2195 0.2533 -0.0149 0.2271 -0.0118 139 2.00 0.2111 0.2402 -0.0131 0.2157 -0.0114 !

139 2.25 0.1995 0.2269 -0.0132 0.2046 -0.0111 139 2.50 0.2078 0.2207 -0.0063 0.2020 -0.0026 139 2.75 0.1940 0.2118 -0.0089 0.1945 -0.0075 139 3.00 0.1962 0.2060 -0.0058 0.1909 -0.0036 139 3.25 0.1910 0.2002 -0.0058 0.1872 -0.0037 ;

139 3.50 0.1921 0.1961 -0.0041 0.1850 -0.0022 ;

139 3.75 0.1827 0.1907 -0.0054 0.1807 -0.0042 i O 139 139 139 4.00 4.25 4.50 0.1743 0.1679 0.1609 0.1846 0.1783 0.1718

-0.0061

-0.0063

-0.0065 0.1749 0.1692 0.1633

-0.0058

-0.0057

-0.0059 i

l 139 4.75 0.1593 0.1662 -0.0056 0.1582 -0.0052 !

139 5.00 0.1546 0.1608 -0.0055 0.1534 -0.0048 i 139 5.25 0.1506 0.1556 -0.0052 0.1486 -0.0048 i 139 5.50 0.1459 0.1504 -0.0052 0.1440 -0.0046 !

139 5.75 0.1470 0.1463 -0.0042 0.1406 -0.0034 139 6.00 0.1391 0.1415 -0.0047 0.1362 -0.0043 139 6.25 0.1408 0.1377 -0.0038 0.1332 -0.0030 139 6.50 0.1391 0.1343 -0.0035 0.1304 -0.0029 139 6.75 0.1423 0.1318 -0.0025 0.1291 -0.0013 139 7.00 0.1429 0.1297 -0.0021 0.1282 -0.0009 139 7.25 0.1485 0.1286 -0.0010 0.1286 0.0004 139 7.50 0.1549 0.1286 -0.0000 0.1300 0.0014 139 7.75 0.1592 0.1291 0.0005 0.1323 0.0023 139 8.00 0.1525 0.1289 -0.0003 0.1331 0.0009 O

._ _= __ .. ~=.__- - _- - .. .-

I l

TEST MODE O PILGRIM NUCLEAR POiER STATION UNIT 1 Page 1 1.EAKAGE RATE

SUMMARY

UNIT 1 TOTAL TIME MASS POINT l DATE TIME TTLM LMCALC UCL LAM UCL .

t 139 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 l 139 0.25 0.0645 0.0000 0.0000 0.0000 0.0000 -

139 0.50 0.3442 0.3442 0.0000 0.3430 1.7213 i 139 0.75 0.2576 0.3187 1.7673 0.2949 0.5231 l 139 1.00 0.2524 0.3013 0.9195 0.2734 0.3828 l 139 1.25 0.2560 0.2932 0.7044 0.2666 0.3319 139 1.50 0.2191 0.2682 0.6003 0.2389 0.2929 139 1.75 0.2195 0.2533 0.5324 0.2271 0.2685 139 2.00 0.2111 0.2402 0.4838 0.2157 0.2491 139 2.25 0.1995 0.2269 0.4453 0.2046 0.2335 i 139 2.50 0.2078 0.2207 0.4184 0.2020 0.2254 1 139 2.75 0.1940 0.2118 0.3939 0.1945 0.2152 i 139 3.00 0.1962 0.2060 0.3749 0.1909 0.2086 i 139 3.25 0.1910 0.2002 0.3583 0.1872 0.2028 ;

139 3.50 0.1921 0.1961 0.3450 0.1850 0.1985 ;

139 3.75 0.1827 0.1907 0.3318 0.1807 0.1933 I O 139 139 139 4.00 4.25 4.50 0.1743 0.1679 0.1609 0.1846 0.1783 0.1718 0.3190 0.3070 0.2954 0.1749 0.1692 0.1633 0.1874 0.1817 0.1760 l

l 139 4.75 0.1593 0.1662 0.2851 0.1582 0.1706 139 5.00 0.1546 0.1608 0.2755 0.1534 0.1656 ,

139 5.25 0.1506 0.1556 0.2664 0.1486 0.1606 139 5.50 0.1459 0.1504 0.2578 0.1440 0.1558 139 5.75 0.1470 0.1463 0.2504 0.1406 0.1519 ,

139 6.00 0.1391 0.1415 0.2427 0.1362 0.1475 l 139 6.25 0.1408 0.1377 0.2362 0.1332 0.1440 i 139 6.50 0.1391 0.1343 0.2303 0.1304 0.1407 139 6.75 0.1423 0.1318 0.2255 0.1291 0.1387 139 7.00 0.1429 0.1297 0.2215 0.1282 0.1372 i 139 7.25 0.1485 0.1286 0.2188 n.1286 0.1370 l 139 7.50 0.1549 0.1286 0.2176 0.1300 0.1380 !

139 7.75 0.1592 0.1291 0.2173 0.1323 0.1401 139 8.00 0.1525 0.1289 0.2158 0.1331 0.1405 1

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PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST !

DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 06:15 I

Pressure Instruments in PSIA ;

channel pressure channel pressure

_______ ________ _______ ________ j 1 +61.0394 2 +61.0540 .

t

_________________________________________________________________ i RTDs in degrees F channel temp. channel temp. channel temp. l 1 +81.152 2 +81.341 3 +82.001 4 +83.982 5 +78.234 6 +78.098 l' 7 +77.021 8 +77.965 9 +76.799 10 +76.382 11 +74.474 12 +74.261 l 13 +72.406 14 +72.199 15 +75.144 !

16 +72.863 17 +74.207 18 +73.036 ,

t Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +74.831 2 +76.207 i 3 +70.230 4 +70.686 I 5 +69.700 6 +66.431 7 +70.577 8 +70.915 9 +68.865 10 +70.902 i

i AVERAGE TEMPERATURE = +74.7876 DEG. F l AVERAGE PRESSURE = +61.0551 PSIA l MASS = +80765.72 LBM l AVG DEW POINT TEMP = +70.3832 DEG. F i AVG VAPOR PRESSURE = +0.3677 PSIA '

I a

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139

' TIME : 06:30 ;

Pressure Instruments in PSIA ;

channel pressure channel pressure ,

1 +61.0338 2 +61.0487 ;

I RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.120 2 +81.316 3 +81.953 '

4 +83.924 5 +78.216 6 +78.074 7 +76.983 8 +77.927 9 +76.766 10 +76.372 11 +74.451 12 +74.229 -

I 13 +72.364 14 +72.150 15 +75.121 16 +72.818 17 +74.162 18 +72.979 i s i Dew Cell temperatures in degrees F channel cell temp channel cell temp ;

1 +74.795 2 +76.154 !

3 +70.218 4 +70.681 i 5 +69.592 6 +66.241 .

, 7 +70.653 8 +70.817 l 9 +68.860 10 +70.853 i

l AVERAGE TEMPERATURE = +74.7474 DEG. F

, AVERAGE PRESSURE = +61.0497 PSIA ,

MASS = +80765.17 LBM AVG DEW POINT TEMP = +70.3454 DEG. F

~

AVG VAPOR PRESSURE = +0.3672 PSIA j 1

I 1

i I

i y -

'ri9 w +e - -

PILGRIM NUCLEAR POWER STATION 1 l INTEGRATED LEAK RATE TEST TEST MODE : TEST [

DATA POINT

SUMMARY

SHEET DATE : 139 )

TIME : 06:45 ;

r i

r Pressure Instruments in PSIA

_________________________________________________________________ i channel pressure channel pressure I

1 +61.0272 2 +61.0425 r

RTDs in degrees F channel temp. channel temp. channel temp. ,

1 +81.086 2 +81.288 3 +81.907 4 +83.871 5 +78.211 6 +78.053- ;

+76.738

~

7 +76.938 8 +77.877 9 10 +76.352 11 +74.438 12 +74.197 13 +72.321 14 +72.104 15 +75.093 16 +72.793 17 +74.122 18 +72.938 .

Dew Cell temperatures in degrees F -

channel cell temp channel cell temp i l

1 +74.875 2 +76.181 3 +70.201 4 +70.668 5 +69.823 6 +66.358 ,

7 +71.046 8 +70.859 l 9 +68.944 10 +70.923 AVERAGE TEMPERATURE = +74.7131 DEG. F AVERAGE PRESSURE = +61.0433 PSIA MASS = +80759.93 LBM AVG DEW POINT TEMP = +70.4596 DEG. F AVG VAPOR PRESSURE = +0.3687 PSIA 1

l l

I 1

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I

i PILGRIM NUCLEAR POWER STATION 1 r INTEGRATED LEAK RATE TEST TEST MODE : TEST t DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 07:00 !

i Pressure Instruments in PSIA ;

channel pressure channel pressure 1 +61.0220 2 +61.0373 :

1

+

i RTDs in degrees F j channel temp. channel temp. channel temp. '

1 +81.053 2 +81.261 3 +81.859 4 +83.809 5 +78.200 6 +78.029 4

7 +76.912 8 +77.843 9 +76.702 ,

10 +76.340 11 +74.424 12 +74.166 !

13 +72.289 14 +72.058 15 +75.091 >

16 +72.751 17 +74.077 18 +72.895 ;

i i

Dew Cell temperatures in degrees F !

channel cell temp channel cell temp ;

i _______ _________ _______ _________

j 1 +74.822 2 +76.054 i 3 +70.152 4 +70.657 ,

, 5 +69.744 6 +66.404 !

7 +70.977 8 +70.809 i 9 +68.839 10 +70.845 i

. \

a !

2 l AVERAGE TEMPERATURE = +74.6792 DEG. F i AVERAGE PRESSURE = +61.0381 PSIA I i MASS = +80759.21 LBM !

AVG DEW POINT TEMP = +70.3952 DEG. F AVG VAPOR PRESSURF -

40-3678 PSIA I J

i I

)

- PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 07:15 l t

Pressure Instruments in PSIA U

channel pressure channel pressure 1 +61.0163 2 +61.0321 t 1

RTDs in degrees F channel temp. channel temp. channel temp. '

1 +81.011 2 +81.236 3 +81.817 :

4 +83.748 5 +78.188 6 +78.020 !

7 +76.869 8 +77.802 9 +76.686 10 +76.322 11 +74.404 12 +74.134 13 +72.255 14 +72.025 15 +75.065 16 +72.718 17 +74.049 18 +72.854 Dew Cell temperatures in degrees F channel cell temp channel cell temp g

1 +74.740 2 +75.978 l 3 +70.107 4 +70.578 1 5 +69.869 6 +66.253 7 +70.751 8 +70.917 9 +68.868 10 +70.778 AVERAGE TEMPERATURE = +74.6468 DEG. F AVERAGE PRESSURE = +61.0326 PSIA

- MASS = +80757.22 LBM AVG DEW POINT TEMP = +70.3731 DEG. F AVG VAPOR PRESSURE = +0.3676 PSIA 3

j 1

i

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l

PILGRIM NUCLEAR POWER STATION 1 l INTEGRATED LEAK RATE TEST TEST MODE : TEST 4 DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 07:30 l 5

Pressure Instruments in PSIA ,

t t

channel pressure channel pressure -i i

i 1 +61.0116 2 +61.0267 !

i RTDs in degrees F

_________________________________________________________________ j channel temp. channel temp. channel temp. ;

4 1 +80.968 2 +81.202 3 +81.761 !

4 4 +83.700 5 +78.184 6 +77.999 !

] 7 +76.837 8 +77.772 9 +76.659 l 10 +76.307 11 +74.393 12 +74.106 '

13 +72.209 14 +71.992 15 +75.043 16 +72.675 17 +74.005 18 +72.812 l l

l l

_________________________________________________________________ i Dew Cell temperatures in degrees F ;

channel cell temp channel cell temp l 1 +74.743 2 +76.031 3 +70.103 4 +70.639 5 +69.996 6 +66.251 I 7 +71.081 8 +70.840 9 +68.850 10 +70.778 l

\

d AVERAGE TEMPERATURE = +74.6118 DEG. F .

AVERAGE PRESSURE = +61.0276 PSIA !

MASS = +80754.95 LBM '

l AVG DEW POINT TEMP = +70.4232 DEG. F AVG VAPOR PRESSURE = +0.3682 PSIA

.i

, e

I PILGRIM NUCLEAR POWER STATION 1 ;

INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 ,

TIME : 07:45 L

Pressure Instruments in PSIA channel pressure channel pressure 1 +61.0061 2 +61.0206 RTDs in degrees F !

i channel temp. channel temp. channel temp.

1 +80.938 2 +81.150 3 +81.717 4 +83.654 5 +78.170 6 +77.985 7 +76.811 8 +77.741 9 +76.625 10 +76.297 11 +74.371 12 +74.070 13 472.173 14 +71.957 15 +75.023 16 +72.623 17 +73.965 18 +72.766 Dew Cell temperatures in degrees F l

< channel cell temp channel cell temp l 1 +74.686 2 +75.930 !

3 +70.089 4 +70.443

5 +69.869 6 +66.071 7 +70.880 8 +70.809 9 +68.703 10 +70.698 ,

AVERAGE TEMPERATURE = +74.5750 DEG. F AVERAGE PRESSURE = +61.0218 PSIA MASS = +80754.66 LBM AVG DEW POINT TEMP = +70.3111 DEG. F AVG VAPOR PRESSURE = +0.3668 PSIA 4

?

I i

e PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 i TIME : 08:00 I i

Pressure Instruments in PSIA l channel pressure channel pressure 1 +61.0009 2 +61.0157 RTDs in degrees F f

channel temp. channel temp. channel temp. ;

1 +80.903 2 +81.110 3 +81.661 !

4 +83.596 5 +78.156 6 +77.977 ;

7 +76.781 8 +77.709 9 +76.598 .

10 +76.283 11 +74.352 12 +74.045 13 +72.148 14 +71.918 15 +74.982 l 16 +72.580 17 +73.931 18 +72.725 l l

Dew Cell temperatures in degrees F <

, _________________________________________________________________ j channel cell temp channel cell temp l

_______ _________ _______ _________ i 1 +74.670 2 +75.912 1 3 +70.021 4 +70.529 ;

5 +69.849 6 +66.080 ;

7 +70.795 8 +70.958 9 +68.702 10 +70.717 l

! 1 1

i AVERAGE TEMPERATURE = +74.5413 DEG. F l AVERAGE PRESSURE = +61.0167 PSIA i d

MASS = +80752.79 LBM AVG DEW POINT TEMP = +70.3252 DEG. F I AVG VAPOR PRESSURE = +0.3670 PSIA i i

l i

l 4

I

+

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 08:15 Pressure Instruments in PSIA channel pressure channel pressure ,

_______ ________ _______ ________ j 1 +60.9960 2 +61.0107 i 1

RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.856 2 +81.081 3 +81.603 )

4 +83.528 5 +78.151 6 +77.963 )

7 +76.754 8 +77.677 9 +76.572 !

10 +76.269 11 +74.333 12 +74.011 1 13 +72.102 14 +71.890 15 +74.953 l 16 +72.559 17 +73.896 18 +72.690 J Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +74.613 2 +75.891 3 . +70.039 4 +70.529 5 +69.877 6 +65.958 7 +70.447 8 +70.941 9 +68.769 10 +70.655 AVERAGE TEMPERATURE = +74.5113 DEG. F AVERAGE PRESSURE = +61.0118 PSIA MASS = +80751.51 LBM AVG DEW POINT TEMP = +70.2785 DEG. F AVG VAPOR PRESSURE := +0.3664 PSIA J

f PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 08:30 r

Pressure Instruments in PSIA channel pressure channel- pressure 1 +60.9917 2 +61.0065 :

RTDs in degrees F t channel temp. channel temp. channel temp.

1 +80.821 2 +81.039 3 +81.554 4 +83.482 5 +78.146 6 +77.952 ;

7 +76.724 8 +77.651 9 +76.542 l 10 +76.252 11 +74.318 12 +73.982 !

13 +72.072 14 +71.856 15 +74.939 16 +72.529 17 +73.863 18 +72.656 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +74.637 2 +75.766 3 +69.969 4 +70.508 5 +69.836 6 +65.926 l 7 +70.922 8 +70.637 ,

9 +68.634 10 +70.630 l

s 1

---_-__-__---_______-___-________---______--___---_____-____--_-- 1 i

l AVERAGE TEMPERATURE = +74.4831 DEG. F AVERAGE PRESSURE = +61.0075 PSIA MASS = +80750.61 LBM AVG DEW POINT TEMP = +70.2486 DEG. F AVG VAPOR PRESSURE = +0.3660 PSIA I

i l

. PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 :

TIME : 08:45 t i

i Pressure Instruments in PSIA 1 channel pressure channel pressure -

t 1 +60.9860 2 +61.0016 ;

i

_________________________________________________________________ j RTDs in degrees F 3

_________________________________________________________________ 3 i

channel temp. channel temp. channel temp. >

1 +80.784 2 +81.012 3 +81.508 ;

4 +83.439 5 +78.134 6 +77.933 !

7 +76.695 8 +77.619 9 +76.522 !

10 +76.247 11 +74.304 12 +73.957 l 13 +72.037 14 +71.825 15 +74.919 !

16 +72.490 17 +73.833 18 +72.612 :

i E

I r

Dew Cell temperatures in degrees F l channel cell temp channel cell temp 1 +74.594 2 +75.788 {

3 +70.000 4 +70.417 !

5 +69.913 6 +66.052 !

7 +70.600 8 +70.756 -

9 +68.743 10 +70.638 i d

I AVERAGE TEMPERATURE = +74.4517 DEG. F

. AVERAGE PRESSURE = +61.0022 PSIA MASS = +80748.23 LBM AVG DEW POINT TEMP = +70.2522 DEG. F AVG VAPOR PRESSURE = +0.3661 PSIA n

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

l i

1 1

PILGRIM NUCLEAR POWER STATION 1 I INTEGRATED LEAK RATE TEST TEST MODE : TEST l DATA POINT

SUMMARY

SHEET DATE : 139 1 TIME : 09:00 !

- i 4

i i

_________________________________________________________________ j j Pressure Instruments in PSIA i

_________________________________________________________________ l channel pressure channel pressure j

, 1 +60.9820 2 +60.9971 I 8

i i

1 s

RTDs in degrees F !

] channel temp. channel temp. channel temp. l 3

1 +80.745 2 +80.959 3 +81.452 l

+78.131 +77.930 4 +83.386 5 6 1 7 +76.673 8 +77.599 9 +76.489 l 10 +76.233 11 +74.280 12 +73.927 l

- 13 +71.999 14 +71.789 15 +74.900 1 16 +72.458 17 +73.797 18 +72.582 i

l _________________________________________________________________ ;

Dew Cell temperatures in degrees F l q _________________________________________________________________ ,

channel cell temp channel cell temp !

1 +74.588 2 +75.708 l 3 +69.962 4 +70.423 !

l 5 +69.754 6 +65.948 !

1 7 +70.618 8 +70.652 i l 9 +68.763 10 +70.582 1

i 1 ;

1 }

l

) !

l AVERAGE TEMPERATURE = +74.4227 DEG. F i AVERAGE PRESSURE = +60.9980 PSIA i

, MASS = +80747.76 LBM 1 l AVG DEW POINT TEMP = +70.2037 DEG. F l AVG VAPOR PRESSURE = +0.3655 PSIA ;

a i

4 4

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i !

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3

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I i

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT SUMHARY SHEET DATE : 139 TIME : 09:15 Pressure Instruments in PSIA channel pressure channel pressure 1 +60.9780 2 +60.9929 RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.712 2 +80.916 3 +81.400 4 483.318 5 +78.117 6 +77.912 7 476.645 8 +77.572 9 +76.456 10 +76.220 11 +74.263 12 +73.895 I 13 +71.969 14 +71.770 15 +74.868 l 16 +72.428 17 +73.769 18 +72.553 i

_________________________________________________________________ j Dew Cell temperatures in degrees F channel cell temp channel cell temp i

_______ _________ _______ _________ j 1 +74.590 2 +75.713 !

3 +69.944 4 +70.378 5 +69.951 6 +65.981 7 +70.408 8 +70.765 9 +68.919 10 +70.606 AVERAGE TEMPERATURE = +74.3944 DEG. F AVERAGE PRESSURE = +60.9939 PSIA MASS = +80745.91 LBM AVG DEW POINT TEMP = +70.2435 DEG. F AVG VAPOR PRESSURE = +0.3659 PSIA i

l l

I

- _ - - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ . _ ._ ._ __-w

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 09:30 ,

Pressure Instruments in PSIA c i

channel pressure channel pressure 1 +60.9737 2 +60.9884 a

RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.674 2 +80.878 3 +81.345 t 4 +83.270 5 +78.110 6 +77.897 )

7 +76.623 8 +77.543 9 +76.435 .

10 +76.209 11 +74.249 12 +73.870 13 +71.941 14 +71.740 15 +74.838 ,

16 +72.400 17 +73.737 18 +72.516

_________________________________________________________________ i Dew Cell temperatures in degrees F

! channel cell temp channel cell temp i 1 +74.585 2 +75.631 '

3 +70.000 4 +70.426 5 +69.834 6 +65.870 i 1 7 +70.561 8 +70.756 '

9 +68.773 10 +70.521 i

AVERAGE TEMPERATURE = +74.3661 DEG. F ;

4 AVERAGE PRESSURE = +60.9895 PSIA ,

1 MASS = +80744.82 LBM AVG DEW POINT TEMP = +70.2146 DEG. F ;

4 l

AVG VAPOR PRESSURE = +0.3656 PSIA n

i.

I J

1 a

i.

5

1 I

P1LGRIM NUCLEAR POKIER STATION 1 i INTEGRATED LEAK RATE TEST TEST MODE : TEST j DATA POINT

SUMMARY

SHEET DATE : 139 l TIME : 09:45 :l k-,

_________________________________________________________________ )

Pressure Instruments in PSIA ;

pressure !

channel pressure channel 1 +60.9690 2 +60.9843 RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.635 2 +80.836 3 +81.296 4 +83.233 5 +78.104 6 +77.882 7 +76.598 8 +77.521 9 +76.405 !

10 +76.196 11 +74.232 12 +73.842 13 +71.914 14 +71.710 15 +74.839 16 +72.371 17 +73.707 18 +72.488 Dew Cell temperatures in degrees F channel cell temp channel cell temp ,

1 +74.535 2 +75.669 i' 3 +69.917 4 +70.347 5 +69.870 6 +65.926 i 7 +70.501 8 +70.581 !

9 +68.909 10 +70.541 ;

_________________________________________________________________ i AVERAGE TEMPERATURE = +74.3410 DEG. F AVERAGE PRESSURE = +60.9851 PSIA MASS = +80743.09 LBM AVG DEW POINT TEMP = +70.1945 DEG. F AVG VAPOR PRESSURE = +0.3653 PSIA ,

i I

i a

I

_ - _ - . .=. -

PILGRIM NUCLEAR POWER STATION 1 ;

i INTEGRATED LEAK RATE TEST TEST MODE : TEST l DATA POINT

SUMMARY

SHEET DATE : 139 [

TIME : 10:00 Pressure Instruments in PSIA l channel pressure channel pressure !

1 +60.9653 2 +60.9807 t

RTDs in degrees F j channel temp. channel temp. channel temp.

1 +80.599 2 +80.807 3 +81.234 4 +83.181 5 +78.093 6 +77.888 !

7 476.581 8 +77.490 9 +76.379 10 +76.187 11 +74.219 12 +73.806 l 13 +71.882 14 +71.677 15 +74.805 16 +72.317 17 +73.678 18 +72.461 i i Dew Cell temperatures in degrees F channel cell temp channel cell temp j

_______ _________ _______ _________ t 1 +74.467 2 +75.594 3 +69.895 4 +70.497 5 +69.947 6 +65.773

7 +70.654 8 +70.600 9 +68.754 10 +70.556 .

.i 1

d, 5 !

n AVERAGE TEMPERATURE = +74.3100 DEG. F l 1 AVERAGE PRESSURE = +60.9814 PSIA MASS = +80742.66 LBM l

, AVG DEW POINT TEMP = +70.2089 DEG. F l AVG VAPOR PRESSURE = +0.3655 PSIA '

a i

l i

rILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST ,

DATA POINT

SUMMARY

SHEET DATE : 139 l

TIME : 10:15 ,

1 J

l Pressure Instruments in PSIA channel pressure channel pressure 1 +60.9612 2 +60.9765 RTDs in degrees F channel temp. channel temp. channel temp.

481.208 1 +80.568 2 +80.771 3 4 +83.118 5 +78.084 6 +77.878 7 +76.566 8 +77.470 9 +76.356 -

10 +76.180 11 +74.197 12 +73.786 !

13 +71.848 14 +71.655 15 +74.783 16 +72.292 17 +73.648 18 +72.429 9

6 Dew Cell temperatures in degrees F j channel cell temp channel cell temp i 1 +74.536 2 +75.626 !

3 +69.849 4 +70.302 l 5 +69.865 6 +65.765 !

7 +70.336 8 +70.672 -

9 +68.743 10 +70.456 i!

i AVERAGE TEMPERATURE = +74.2847 DEG. F AVERAGE PRESSURE = +60.9772 PSIA ;

MASS = +80742.26 LBM t AVG DEW POINT TEMP = +70.1306 DEG. F AVG VAPOR PRESSURE = +0.3645 PSIA l

5 i

k i

i h

r

I 4

PILGRIM NUCLEAR POWER STATION 1 '

INTEGRATED LEAK RATE TEST TEST MODE : TEST 4

DATA POINT

SUMMARY

SHEET DATE : 139 I TIME : 10:30 l l

t

_________________________________________________________________ l

, Pressure Instruments in PSIA '

j _________________________________________________________________ ;

channel pressure channel pressure j 1 +60.9580 2 +60.9732 !

t L

i !

RTDs in degrees F i channel temp. channel temp. channel temp. !

1 +80.553 2 +80.740 3 +81.176 1 4 +83.091 5 +78.080 6 +77.863

]

' +76.535 8 +77.442 9 +76.331 10 +76.167 11 +74.181 12 +73.753 13 +71.831 14 +71.625 15 +74.770 16 +72.259 17 +73.615 18 +72.407 <

1 I

I I

g }

Dew Cell temperatures in degrees F '

channel cell temp channel cell temp i d

1 +74.554 2 +75.594 i 3 +69.876 4 +70.308 l 5 +69.904 6 +65.699 <

i 7 +70.496 8 +70.574 l

9 +68.717 10 +70.459 l t

! l i l I i 4

AVERAGE TEMPERATURE = +74.2590 DEG. F )

i AVERAGE PRESSURE = +60.9740 PSIA l i MASS = +80741.70 LBM .

AVG DEW POINT TEMP = +70.1378 DEG. F I l AVG VAPOR PRESSURE = +0.3646 PSIA I i

i 4

a n

l

i i

i l

l t

i PILGRIM NUCLEAR POWER STATION 1 i INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 10:45 i Pressure Instruments in PSIA channel pressure channel pressure 1 +60.9551 2 +60.9699 RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.534 2 +80.721 3 +81.165 '

4 +83.053 5 +78.062 6 +77.868 '

t 7 +76.517 8 +77.425 9 +76.306

10 +76.152 11 +74.161 12 +73.728 13 +71.794 14 +71.602 15 +74.748 16 +72.238 17 +73.595 18 +72.372 i 4

Dew Cell temperatures in degrees F q _______-_-________-__---_-_----______-__________--_-_---_----____

1 channel cell temp channel cell temp j i

1 +74.534 2 +75.641 '

3 +69.901 4 +70.331 ;

, 5 +69.766 6 +65.570 i 7 +70.501 8 +70.576 9 +68.664 10 +70.502 l

I AVERAGE TEMPERATURE = +74.2359 DEG. F AVERAGE PRESSURE = +60.9709 PSIA MASS = +80741.34 LBM AVG DEW POINT TEMP = +70.1207 DEG. F AVG VAPOR PRESSURE = +0.3644 PSIA a

I 4

1 J

m ,, , - , - - - , .

I i

PILGRIM NUCLEAR POWER STATION 1 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST i DATA POINT

SUMMARY

SHEET DATE : 139 :

TIME : 11:00 .

l l

Pressure Instruments in PSIA channel pressure channel pressure l

_______ ________ _______ ________ l 1 +60.9513 2 +60.9665 J

l

_________________________________________________________________ l RTDs in degrees F l l

channel temp. channel temp. channel temp.

1 +80.517 2 +80.709 3 +81.153 4 +83.052 5 +78.059 6 +77.854 7 +76.497 8 +77.395 9 +76.288 10 +76.150 11 +74.147 12 +73.706 13 +71.772 14 +71.576 15 +74.740 16 +72.222 17 +73.571 18 +72.352 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +74.454 2 +75.655 3 +69.784 4 +70.243 5 +69.723 6 +65.602 7 +70.381 8 +70.653 9 +68.624 10 +70.398 AVERAGE TEMPERATURE = +74.2171 DEG. F AVERAGE PRESSURE = +60.9673 PSIA MASS = +80740.26 LBM AVG DEW POINT TEMP = +70.0691 DEG. F AVG VAPOR PRESSURE = +0.3638 PSIA i

4

PILGRIM NUCLEAR POWER STATION 1 !

INTEGRATED LEAK RATE TEST TEST MODE : TEST l DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 11:15 !

Pressure Instruments in PSIA channel pressure channel pressure 1 +60.9484 2 +60.9632 r RTDs in degrees F channel temp. channel temp. channel temp. >

1 +80.500 2 +80.685 3 +81.138 4 +83.005 5 +78.051 6 +77.847 ,

7 +76.473 8 +77.372 9 +76.263 10 +76.140 11 +74.128 12 +73.675 13 +71.755 14 +71.562 15 +74.722 16 +72.191 17 +73.543 18 +72.325 Dew Cell temperatures in degrees F channel cell temp channel cell temp )

1 +74.408 2 +75.692 4

3 +69.802 4 +70.308 5 +69.778 6 +65.634

7 +70.320 8 +70.664 9 +68.572 10 +70.431 I AVERAGE TEMPERATURE = +74.1926 DEG. F AVERAGE PRESSURE = +60.9642 PSIA MASS = +80739.71 LBM AVG DEW POINT TEMP = +70.0758 DEG. F AVG VAPOR PRESSURE = +0.3639 PSIA 4

^

\

l J

l 1

1 I

l l

I I

i I 1

I i

i w r ,

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 11:30 Pressure Instruments in PSIA channel pressure channel pressure 1 +60.9449 2 +60.9604 RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.491 2 +80.675 3 +81.123 4 +82.964 5 +78.039 6 +77.842 7 +76.457 8 +77.351 9 +76.234 10 +76.133 11 +74.111 12 +73.652 13 +71.727 14 +71.543 15 +74.705 16 +72.171 17 +73.518 18 +72.306 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +74.304 2 +75.684 -

3 +69.756 4 +70.196 .

5 +69.659 6 +65.674 !

7 +70.330 8 +70.621 {

9 +68.619 10 +70.396 P

i i

l AVERAGE TEMPERATURE = +74.1727 DEG. F l AVERAGE PRESSURE = +60.9610 PSIA j MASS = +80739.11 LBM- l AVG DEW POINT TEMP = +70.0404 DEG. F !

AVG VAPOR PRESSURE = +0.3634 PSIA j l

l l

t

P PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST i DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME: 11:45 l Pressure Instruments in PSIA channel pressure channel pressure ,

i 1 +60.9419 2 +60.9574 l

RTDs in degrees F channel temp. channel temp. channel temp. !

1 +80.480 2 +80.669 3 +81.124 I 4 +82.986 5 +78.036 6 +77.832 i 7 +76.439 8 +77.335 9 +76.214 10 +76.122 11 +74.095 12 +73.636 13 +71.698 14 +71.518 15 +74.688 16 +72.145 17 +73.499 18 +72.279 Dew Cell temperatures in degrees F l channel cell temp channel cell temp 1 +74.397 2 +75.717 3 +69.732 4 +70.171 5 +69.646 6 +65.496 7 +70.236 8 +70.589 9 +68.581 10 +70.364 AVERAGE TEMPERATURE = +74.1529 DEG. F AVERAGE PRESSURE = +60.9580 PSIA MASS = +80738.71 LBM AVG DEW POINT TEMP = +70.0034 DEG. F AVG VAPOR PRESSURE = +0.3630 PSIA l l

l i

l

.)

l l-PILGRIM NUCLEAR POWER STATION 1 !

INTEGRATED LEAK RATE TEST TEST MODE : TEST !

I DATA-POINT

SUMMARY

SHEET DATE : 139 i

~

TIME : 12:00 r

l Pressure Instruments in PSIA i

_________________________________________________________________ i channel pressure channel pressure

_______ ________ _______ ________ i 1 +60.9389 2 +60.9535 l RTDs in degrees F !

channel temp. channel temp. channel temp.

1 +80.478 2 +80.660 3 +81.116 4 +82.948 5 +78.036 6 +77.829 7 +76.416 8 +77.309 9 +76.196 10 +76.109 11 +74.087 12 +73.612 .

13 +71.678 14 +71.493 15 +74.679 ;

16 +72.131 17 +73.473 18 +72.261 P

Dew Cell temperatures in degrees F l

channel cell temp channel cell temp 1 +74.400 2 +75.744 l 3 +69.745 4 +70.113 5 +69.641 6 +65.422 i 7 +70.032 8 +70.603 9 +68.600 10 +70.363 :

t AVERAGE TEMPERATURE = +74.1351 DEG. F AVERAGE PRESSURE = +60.9546 PSIA MASS = +80737.27 LBM AVG DEW POINT TEMP = +69.9758 DEG. F AVG VAPOR PRESSURE = +0.3626 PSIA

PILGRIM NUCLEAR POWER STATION 1 f INTEGRATED LEAK RATE TEST TEST MODE : TEST !

DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 12:15 .

i

______________________-______________..._________________________ i Pressure Instruments in PSIA !

_________________________________________________________________ {

channel pressure channel pressure l 1 +60.9363 2 +60.9518 i RTDs in degrees F

_________________________________________________________________ i channel temp. channel temp. channel temp. l 1 +80.469 2 +80.641 3 +81.108 '

4 +82.935 5 +78.029 6 +77.823 7 +76.397 8 +77.292 9 +76.173 '

10 +76.107 11 +74.062 12 +73.590 13 +71.659 14 +71.473 15 +74.657 16 +72.102 17 +73.451 18 +72.238 l

?

I Dew Cell temperatures in degrees F i channel cell temp channel cell temp !

i 1 +74.353 2 +75.745 ;

3 +69.716 4 +70.236 i 5 +69.589 6 +65.344 7 +70.169 8 +70.570 1 9 +68.567 10 +70.329 l t

i AVERAGE TEMPERATURE = +74.1137 DEG. F !

AVERAGE PRESSURE = +60.9524 PSIA ..

MASS = +80737.63 LBM !

AVG DEW POINT TEMP = +69.9764 DEG. F r AVG VAPOR PRESSURE = +0.3626 PSIA !

i k

t l

i 1

i 4

PILGRIM NUCLEAR POWER STATION 1 ,

INTEGRATED LEAK RATE TEST TEST MODE : TEST l DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 12:30 i

- ?

Pressure Instruments in PSIA !

channel pressure channel pressure i 1 +60.9333 2 +60.9477 i RTDs in degrees F ,

I i channel temp. channel temp. channel temp.

j _______ _____ _______ _____ _______ _____

1 +80.464 2 +80.644 3 +81.109 '

4 +82.924 5 +78.017 6 +77.822 7 +76.377 8 +77.280 9 +76.154-10 +76.094 11 +74.047 12 +73.565 .

13 +71.631 14 +71.456 15 +74.647 !

16 +72.082 17 +73.427 -

18 +72.211 .

Dew Cell temperatures in degrees F 1_

channel cell temp channel cell temp i 1 +74.416 2 +75.747 3 +69.696 4 +70.184 i 5 +69.628 6 +65.288 !

7 +70.250 8 +70.515 '

, 9 +68.522 10 +70.277 l 1

1 i

i

_________________________________________________________________ i'

. AVERAGE TEMPERATURE = +74.0942 DEG. F l

- AVERAGE PRESSURE = +60.9489 PSIA I MASS = +80736.10 LBM AVG DEW POINT TEMP = +69.9606 DEG. F i AVG VAPOR PRESSURE = +0.3624 PSIA i

e a

i 4

d d

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST j DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 12:45 :

Pressure Instruments in PSIA r

channel pressure channel pressure 1 +60.9303 2 +60.9452 e a

RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.453 2 +80.634 3 +81.106 I 4 +82.909 5 +78.009 6 +77.811 1 7 +76.359 8 +77.261 9 +76.144 :

10 +76.086 11 +74.041 12 +73.548 13 +71.611 14 +71.431 15 +74.641 .

16 +72.079 17 +73.409 18 +72.192 !

Dew Cell temperatures in degrees F channel cell temp channel cell temp ,

1 ,74.307 2 +75.678 3 4 v9.657 4 +70.141 5 +<9.693 6 +65.125 7 +70.201 8 +70.465 9 +68.368 10 +70.268 i

AVERAGE TEMPERATURE = +74.0806 DEG. F AVERAGE PRESSURE = +60.9461 PSIA MASS = +80735.30 LBM AVG DEW POINT TEMP = +69.9119 DEG. F )

AVG VAPOR PRESSURE = +0.3618 PSIA 1

i i

PILGRIM NUCLEAR POWER STATION 1 ,

INTEGRATED LEAK RATE TEST TEST MODE : TEST l DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 13:00 i i

Pressure Instruments in PSIA channel pressure channel pressure !

i 1 +60.9260 2 +60.9416 [

_________________________________________________________________ t RTDs in degrees F channel temp. channel temp. channel temp.

1 +80.448 2 +80.643 3 +81.101 4 +82.890 5 +78.000 6 +77.810 7 +76.339 8 +77.239 9 +76.113

, 10 +76.078 11 +74.025 12 +73.523 13 +71.590 14 +71.416 15 +74.623 16 +72.049 17 +73.388 18 +72.169 i

Dew Cell temperatures in degrees F !

I>

channel cell temp channel cell temp 1 +74.381 2 +75.662 i 3 +69.658 4 +70.141 '

5 +69.672 6 +65.156 l 7 +69.970 8 +70.471 ,

j 9 +68.480 10 +70.256 i

AVERAGE TEMPERATURE = +74.0598 DEG. F AVERAGE PRESSURE = +60.9422 PSIA [

MASS = +80733.39 LBM i I

! AVG DEW POINT TEMP = +69.8988 DEG. F

+0.3617 AVG VAPOR PRESSURE = PSIA i'

e i

6 t

i a

1

i I

l PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 13:15 Pressure Instruments in PSIA ,

channel pressure channel pressure ,

1 +60.9233 2 +60.9386 i

RTDs in degrees F channel temp. channel temp. channel temp 1 +80.442 2 +80.631 3 +81.094 4 +82.942 5 +77.998 6 +77.802 7 +76.321 8 +77.225 9 +76.097

- 10 +76.071 11 +74.010 12 +73.506 13 +71.576 14 +71.403 15 +74.623 16 +72.029 17 +73.373 18 +72.148 i Dew Cell temperatures in degrees F

_________________________________________________________________ 1

- channel cell temp channel cell temp 1 +74.397 2 +75.673 i 3 +69.557 4 +70.111 5 +69.618 6 +65.278 7 +70.028 8 +70.517 ;

9 +68.386 10 +70.257 i 1

4

. AVERAGE TEMPERATURE = +74.0451 DEG. F AVERAGE PRESSURE = +60.9393 PSIA MASS = +80732.06 LBM i AVG DEW POINT TEMP = +69.8838 DEG. F I AVG VAPOR PRESSURE = +0.3615 PSIA l 4

4 4

4 t -- - , - - -r

l i.

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 13:30

_-___-_--_-_-_____---______----__________--____-_________________ \

Pressure Instruments in PSIA i

channel pressure channel pressure 1 +60.9204 2 +60.9357 l l

l RTDs in degrees F '

channel temp. channel temp. channel temp.

1 +80.433 2 +80.633 3 +81.100 l 4 +82.918 5 +77.992 6 +77.795 l 7 +76.304 8 +77.206 9 +76.079 l 10 +76.066 11 +73.995 12 +73.480 13 +71.549 14 +71.381 15 +74.607 16 +72.018 17 +73.343 18 +72.125 l

l Dew Cell temperatures in degrees F channel cell temp channel cell temp i 1 +74.527 2- +76.121 3 +69.602 4 +70.123 i 5 +69.650 6 +65.644 7 +70.011 8 +70.490 9 +68.824 10 +70.257 AVERAGE TEMPERATURE = +74.0259- DEG. F AVERAGE PRESSURE = +60.9364 PSIA !

l MASS = +80729.49 LBM AVG DEW POINT TEMP = +69.9812 DEG. F '

AVG VAPOR PRESSURE = +0.3627 PSIA l

l

PILGRIM NUCLEAR POWER STATION 1 l INTEGRATED LEAK RATE TEST TEST MODE : TEST !

DATA POINT

SUMMARY

SHEET DATE : 139 i TIME : 13:45 ;

Pressure Instruments in PSIA

_________________________________________________________________ i channel pressure channel pressure ;

4 1 +60.9149 2 +60.9297 '

3 RTDs in degrees F ,

channel temp. channel temp. channel temp. i 1 +80.432 2 +80.619 3 +81.100 l 4 +82.910 5 +77.984 6 +77.779 i 7 +76.252 8 +77.172 9 +76.042 i 10 +76.052 11 +73.963 12 +73.461 '

13 +71.514 14 +71.330 15 +74.593 ,

16 +71.991 17 +73.336 18 +72.108 i l

1 i

Dew Cell temperatures in degrees F :

_________________________________________________________________ l channel cell temp channel cell temp 1 +74.467 2 +75.807 !

3 +69.561 4 +70.056 1 I

5 +69.615 6 +65.401 7 +70.337 8 +70.368 9 +68.447 10 +70.173 AVERAGE TEMPERATURE = +74.0032 DEG. F AVERAGE PRESSURE = +60.9307 PSIA MASS = +80726.62 LBM AVG DEW POINT TEMP = +69.8995 DEG. F AVG VAPOR PRESSURE = +0.3617 PSIA i

l l

i j

PILGRIM NUCLEAR POWER STATION 1 ;

INTEGRATED LEAK RATE TEST TEST MODE : TEST DATA POINT

SUMMARY

SHEET DATE : 139 i TIME : 14:00 Pressure Instruments in PSIA channel pressure channel pressure l

_______ ________ f 1 +60.9096 2 +60.9250 RTDs in degrees F >

channel temp. channel temp. channel temp. t 1 480.423 2 +80.612 3 +81.095 4 +82.931 5 +77.973 6 +77.769 :

a 7 +76.187 8 +77.099 9 +75.997 10 +75.040 11 +73.935 12 *73.423

+ !

13 +71.429 14 +71.250 15 +74.562 j 16 +71.974 17 +73.313 18 +72.097 i i

Dew Cell temperatures in degrees F l channel cell temp channel cell temp l J _______ _________ _______ _________

l 1 +74.608 2 +75.869 ;

3 +69.600 4 +70.154 l 5 +69.744 6 +65.317 ;

+70.049 8 +70.499 '

7 9 +68.543 10 +70.170 !

1 >

AVERAGE TEMPERATURE = +73.9718 DEG. F ;

AVERAGE PRESSURE = +60.9257 PSIA i

MASS = +80724.20 LBM i

'~

AVG DEW POINT TEMP = +69.9299 DEG. F :

AVG VAPOR PRESSURE = +0.3621 PSIA l a i r

a w

f

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : TEST ,

DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 14:15 ;

Pressure Instruments in PSIA >

channel pressure channel pressure 1 +60.9056 2 +60.9205 ,

RTDs in degrees F v _________________________________________________________________

channel temp. channel temp. channel temp.

1 +80.423 2 +80.603 3 +81.093 t 4 +82.902 5 +77.948 6 +77.738 7 +76.131 8 +77.026 9 +75.942 10 +76.023 11 +73.902 12 +73.379 13 +71.376 14 +71.173 15 +74.532

+72.086 16 +71.952 17 +73.297 18

_________________________________________________________________ l Dew Cell temperatures in degrees F

_________________________________________________________________ l channel cell temp channel cell temp !

1 +74.692 2 +75.869

, 3 +69.649 4 +70.079 ,

5 +69.583 6 +65.172 7 +69.288 8 +70.590 l 9 +68.586 10 +70.242 :

i i

J 1

AVERAGE TEMPERATURE = +73.9411 DEG. F ;

AVERAGE PRESSURE = +60.9214 PSIA l MASS = +80724.67 LBM AVG DEW POINT TEMP = +69.8396 DEG. F 1 AVG VAPOR PRESSURE = +0.3609 PSIA !

I i

i 4

s w-- ~ - , - w-- -

, . + - - w w

i I

l Appendix C !

VERIFICATION PIIASE DATA AND PLOTS -

i f

I e

s.

F b

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

i VERIFICATION MODE TIME = 2230 OPTIONS: TEST

SUMMARY

O I -

MANUAL DATA ENTRY # OF DATA POINTS = 20 2 -

PARAMETER GRAPHS MODE DURATION (IN HOURS) = 5.00 l 3 -

SENSOR PLOTS TOT TIME MEASURED LEAK = 1.0981 4 -

TREND. ANALYSIS TOT TIME CALCULATED LEAK = 1.0934 5 -

REPRINT CURRENT DATA PT MASS PT LEAK = 1.0966 ;

6 -

SENSOR DIFFERENTIALS IMPOSED LEAK = 1.0106 TOT TIME UPPER LIMIT = 1.3895 P -

PASS WORD MENU TOT TIME LOWER LIMIT =. 0.8895 I MASS PT UPPER LIMIT = 1.3937 i SELECTED OPfl0N = MASS PT LOWER LIMIT = 0.8937 TOT TIME VERIFICATION CRITERIA HAS BEEN MET ,

MASS PT VERIFICATION CRITERI A HAS BEEN MET POINT

SUMMARY

CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT J

AVG TEMP: 73.728/ -0.005 AVG PRESS: 60.388 / -0.008 i MASS: 80526.41/ -9.406 AVG DEW PRESS: 0.3577/ -0.0002 TOTAL PRESS: 60.745 / -0.008

't 4

j W

O i

b VEHF MODE !

Page 1 J

l AVERAGE DATA VALUES DATE TIME RTD DEW PT. VAP PRESS TOT PRESS MASS 139 0.00 73.847 69.662 0.359 60.898 80711.05 139 0.25 73.847 69.646 0.359 60.891 80701.70 139 0.50 73.844 69.688 0.359 60.884 80692.35 139 0.75 73.838 69.678 0.359 60.876 80682.69 139 1.00 73.830 69.668 0.359 60.869 80674.11 l 139 1.25 73.826 69.669 0.359 60.861 80G64.16 139 1.50 73.820 69.628 0.358 60.853 80655.52 139 1.75 73.809 69.624 0.358 60.846 80647.28 139 2.00 73.805 69.656 0.359 60.838 80636.80 i 139 2.25 73.801 69.556 0.357 60.830 80629.13 l 139 2.50 73.798 69.634 0.358 60.823 80618.20 139 3.00 73.784 69.543 0.357 ~60.807 80600.68 139 3.25 73.775 69.561 0.358 60.799 80591.80 l

139 3.50 73.770 69.661 0.359 60.792 80581.08 139 3.75 73.762 69.630 0.358 60.784 80571.77 l 1 139 4.00 73.756 69.577 0.358 60.777 80564.09 {

139 4.25 73.748 69.607 0.358 60.769 80554.40 139 4.50 73.740 69.574 0.358 60.760 80544.55 .

139 4.75 73.733 69.596 0.358 60.753 80535.82 l 139 5.00 73.728 69.579 0.358 60.745 80526.41 l l

I i

l 1

1 3

a J

E 4

J l !

. , - I

VERF MODE PILGRIM NUCLEAR POWER STATION UNIT 1 Page 1 LEAKAGE RATE TREND

SUMMARY

UNIT 1 TOTAL TIME MASS POINT DATE TIME TTLM LMCALC CHANGE LAM CHANGE 139 0.25 1.1127 0.0000 0.0000 0.0000 0.0000 139 0.50 1.1122 1.1122 1.1122 1.1101 1.1101 139 0.75 1.1244 1.1223 0.0101- 1.1233 0.0131 139 1.00 1.0986 1.1075 -0.0148 1.1044 -0.0189 ,

139 1.25 1.1154 1.1110 0.0036 1.1101 0.0057 139 1.50 1.1009 1.1053 -0.0057 1.1039 -0.0063 .-

13P 1.75 1.0836 1.0941- -0.0113 1.0910 -0.0128 139 2.00 1.1040 1.0957 0.0017 1.0952 0.0041 :

139 2.25 1.0827 1.0889 -0.0068 1.0876 -0.0075 139 2.50 1.1046 1.0919 0.0030 1.0927 0.0051 I

. 139 3.00 1 0940 1.0893 -0.0025 1.0918 -0.0009 i 139 3.25 1.0911 1.0884 -0.0010 1.0903 -0.0015 j 139 3.50 1.1043 1.0915 0.0031 1.0948 0.0045 l 139 3.75 1.1045 1.0937 0.0023 1.0977 0.0029 !

j 139 4.00 1.0925 1.0925 -0.0012 1.0959 -0.0018 4

O 139 139 139 4.25 4.50 4.75 1.0961 1.1003 1.0970 1.0924 1.0932 1.0932

-0.0001 0.0008 0.0000 1.0956 1.0966 1.0962

-0.0003 0.0009

-0.0004 139 5.00 1.0981 1.0934 0.0002 1.0966 0.0004 4

l t

1 i

i v

f i

i VERF MODE I P1LGRIM NUCLEAR POWER STATION UNIT 1 Page 1 LEAKAGE RATE

SUMMARY

UNIT 1 ,

TOTAL TIME MASS POINT l

DATE TIME TTLM LMCALC UCL LAM UCL t 139 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 l 139 0.25 1.1127 0.0000 0.0000 0.0000 0.0000 !

139 0.50 1.1122 1.1122 0.0000 1.1101 -1.1263 139 0.75 1.1244 1.1223 1.1732 1.1233 1.1425 '

139 1.00 1.0986 1.1075 1.1679 1.1044 1.1308 139 1.25 1.1154 1.1110 1.1521 1.1101 1.1274 139 1.50 1.1009 1.1053 1.1381 1.1039 1.1178 139 1.75 1.0836 1.0941 1.1274 1.0910 1.1089 139 2.00 1.1040 1.0957 1.1270 1.0952 1.1094 139 2.25 1.0827 1.0889 1.1178 1.0876 1.1016 :

139 2.50 1.1046 1.0919 1.1218 1.0927 1.1053 139 3.00 1.0940 1.0893 1.1179 1.0918 1.1018 i 139 3.25 1.0911 1.0884 1.1147 1.0903 1.0987 !

139 3.50 1.1043 1.0915 1.1185 1.0948 1.1029 i 139 3.75 1.1045 1.0937 1.1206 1.0977 1.1052 l 139 4.00 1.0925 1.0925 1.1179 1.0959 1.1027 l 139 4.25 1.09G1 1.0924 1.1166 1.095G 1.1016 l 139 4.50 1.1003 1.0932 1.1168 1.0966 1.1020 ;

139 4.75 1.0970 1.0932 1.1160 1.0962 1.1010 139 5.00 1.0981 1.0934 1.1155 1.0966 1.1010 I

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1 PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF ;

DATA POINT

SUMMARY

SHEET DATE : 139 :

TIME : 17:30

_________________________________________________________________ i Pressure Instruments in PSIA !

channel pressure channel pressure

_______ ________ _______ ________ i 1 +60.8821 2 +60.8979 RTDs in degrees F i I

channel temp. channel temp. channel temp.

1 +80.956 2 +81.203 3 +81.471 ;

I 4 +83.193 5 +78.340 6 +78.201 7 +76.014 3 +76.950 9 +75.758 :

10 +75.959 11 +73.780 12 +73.169 i 13 +71.237 14 +71.123 15 +74.396 ;

+71.752 +71.933

~

16 17 +73.129 18 i

2 ;

Dew Cell temperatures in degrees F !

1 ( annel cell temp channel cell temp l 1 +73.678 2 +74.382 ,

3 +69.370 4 +69.901 l 5 +69.255 6 +64.247 7 +69.994 8 +70.477 i 9 +68.335 10 +70.013 I

I

, AVERAGE TEMPERATURE = +73.8471 DEG. F i AVERAGE PRESSURE = +60.8984 PSIA MASS = +80711.05 LBM AVG DEW POINT TEMP = +69.6624 DEG. F AVG VAPOR PRESSURE = +0.3588 PSIA I i

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-________--_____?

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 17:45 Pressure Instruments in PSIA channel pressure channel pressure 1 +60.8749 2 +60.8907

+

RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.024 2 +81.296 3 +81.508 4 +83.249 5 +78.379 6 +78.236 7 +76.025 8 +76.953 9 +75.765 ,

10 +75.954 11 +73.774 12 +73.171 .

13 +71.242 14 +71.118 15 +74.396 16 +71.742 17 +73.114 18 +71.922 i

Dew Cell temperatures in degrees F !

t channel cell temp channel cell temp '

1 +73.577 2 +74.210 3 +69.347 4 +70.053 5 +69.321 6 464.314 i' 7 +69.807 8 +70.510 9 +68.277 10 +69.983 AVERAGE TEMPERATURE = +73.8472 DEG. F AVERAGE PRESSURE = +60.8912 PSIA MASS = +80701.70 LBM l AVG DEW POINT TEMP = +69.6461 DEG. F AVG VAPOR PRESSURE = +0.3586 PSIA t

b PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF l DATA POINT

SUMMARY

SHEET DATE : 139 .

TIME : 18:00 ;

i Pressure Instruments ir PSIA :

_______________________._________________________________________ l channel pressure _ channel pressure !

1 +60.8682 2 +60.8836 :

RTDs in degrees F ;

channel temp. channel temp. channel temp. ;

1 4b4.094 2 +81.369 3 +81.553 i 4 +83.282 5 +78.423 6 +78.268 ,

7 +76.023 8 +76.949 9 +75.767 ,

10 +75.952 11 +73.774 12 +73.169 !

17 +71.236 14 +71.120 15 +74.383 i 16 +71.735 17 +73.099 18 +71.902' l t

Dew Cell temperatures in degrees 7 l channel cell temp channel cell temp ;

1 +73.580 2 +74.187 3 +69.343 4 +69.994 5 +69.415 6 +64.225 7 +70.082 8 +70.479 9 +68.325 10 +69.988 :

F AVERAGE TEMPERATURE = +73.8437 DEG. F AVERAGE PRESSURE = +60.8843 PSIA ;

MASS = +80692.35 LBM !

AVG DEW POINT TEMP = 469.6875 DEG. F AVG VAPOR PRESSURE = +0.3591 PSIA t

i I

l t

I i

i l

}

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF l DATA POINT

SUMMARY

SHEET DATE : 139 ,

TIME : 18:15 :

Pressure Instruments in PSIA i channel pressure channel pressure j

__--_-- __--_-__ --_-__- __------ t 1 +60.8602 2 +60.8755 !

RTDs in degrees F ,

channel temp. channel temp. channel tr.mp.

1 -_-_-__ _____ ---____ --_-_ _______ -___.

1 +81.158 2 +81.451 3 +81.589 [

4 +83.317 5 +78.445 6 +78.303 i 7 +76.023 8 +76.944 9 +75.770 i 10 +75.961 11 +73.770 12 +73.165 i 13 +71.233 14 +71.114 15 +74.388 7 1

16 +71.709 17 +73.084 18 +71.885 l 1 i i i l .

Dew Cell temperatures in degrees F channel cell temp channel cell temp ;

1 +73.521 2 +74.021 I 3 +69.373 4 +69.962 !

5 +69.337 6 +64.112 i 7 .b.144 8 +70.454 9 +68.379 10 +69.967 l l \

r AVERAGE TEMPERATURE = +73.8377 DEG. F AVERAGE PRESSURE = +60.8762 PSIA MASS = +80682.69 LBM AVG DEW POINT TEMP = +69.6777 DEG. F AVG VAPOR PRESSURE = +0.3590 PSIA ;

m.. - , - -

i PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF ,

DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 18:30 Pressure Instruments in PSIA !

channel pressure channel pressure !

1 +60.8528 2 +60.8680 t 4 ;

d _________________________________________________________________ ,

RTDs in degrees F i

_________________________________________________________________ j 9 channel temp. channel temp. channel temp. l

1 +81.209 2 +81.447 3 +81.631 4 +83.347 5 +78.471 6 +78.332 t 7 +76.028 8 +76.939 9 +75.774 !

10 +75.952 11 +73.757 12 +73.160 l 13 +71.224 14 +71.114 15 +74.377 l a 16 +71.684 17 +73.069 18 +71.869 i Dew Cell temperatures in degrees F a .

channel. cell temp channel cell temp

^

2 1 +73.562 2 +74.015 3 +69.441 4 +70.139 d

5 +69.238 6 +64.424 ;

7 +70.090 8 +70.359 ;

. 9 +68.306 10 +69.984 i

i AVERAGE TEMPERATURE = +73.8298 DEG. F i

] AVERAGE PRESSURE = +60.8688 PSIA MASS = +80674.11 LBM i

! AVG DEW POINT TEMP = +69.6682 DEG. F l AVG VAPOR PRESSURE = +0.3588 PSIA t 4 ,

h f

l l

1 5

d s

a 4

l j

1 PILGRIM NUCLEAR POWER STATION 1 l INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 18:45 i Pressure Instruments in PSIA l l

channel pressure channel pressure l

1 +60.8449 2 +60.8602 RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.261 2 +81.539 3 +81.658 4 +83.365 5 +78.501 6 +78.350 7 +76.020 8 +76.945 9 +75.775

- 10 +75.950 11 +73.752 12 +73.158 13 +71.217 14 +71.112 15 +74.371 16 +71.677 17 +73.058 18 +71.855 1

_____________________________________________________-__-________ i Dew Cell temperatures in degrees F J channel cell temp channel cell temp 1 +73.515 2 +74.051 3 +69.458 4 +69.994 5 +69.190 6 +64.232 7 +69.992 8 +70.517 9 +68.417 10 +69.957 AVERAGE TEMPERATURE = +73.8262 DEG. F AVERAGE PRESSURE = +60.8609 PSIA MASS = +80664.16 LBM AVG DEW POINT TEMP = +69.6693 DEG. F AVG VAPOR PRESSURE = +0.3588 PSIA 4

) e 1

d

~ _ _ _ ..

t PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF -

DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 19:00 .

t Pressure Instruments in PSIA

_________________________________________________________________ i channel pressure channel pressure 1 +60.8370 2 +60.8526 t

RTDs in degrees F

_________________________________________________________________ l channel temp. channel temp. channel temp.

1 +81.292 2 +81.569 3 +81.692 ,

4 +83.353 5 +78.507 6 +78.369 l 7 +76.030 8 +76.940 9 +75.772 '

10 +75.950 11 +73.744 12 +73.156 2

13 +71.212 14 +71.106 15 +74.369 16 +71.656 17 +73.048 18 +71.839 i Dew Cell temperatures in degrees F {

channel cell temp channel cell temp i 1 +73.417 2 +73.882 !

3 +69.451 4 +69.902 .

5 +69.218 6 +64.201 4

7 +69.985 8 +70.384 9 +68.407 10 +69.926 '

)

l 1

1 AVERAGE TEMPERATURE = +73.8196 DEG. F AVERAGE PRESSURE = +60.8532 PSIA MASS = +80655.52 LBM AVG DEW POINT TEMP = +69.6277 DEG. F ,

AVG VAPOR PRESSURE = +0.3583 PSIA i l

i

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 l TIME : 19:15 !

I l

Pressure Instruments in PSIA channel pressure channel pressure 1 +60.8295 2 +60.8452 I

i

-_____-___----___---________--____-_--_------___----_---_______-_ i RTDs in degrees F channel temp. channel temp. channel temp.

]

1 +81.324 2 +81.612 3 +81.697 '

4 +83.367 5 +78.526 6 +78.380 7 476.020 8 +76.938 9 +75.774 10 +75.949 11 +73.736 12 +73.146 13 +71.204 14 +71.103 15 +74.354 l 16 +71.630 17 +73.028 18 +71.826 i i

e Dew Cell temperatures in degrees F

\

channel cell temp channel cell temp 1 +73.462 2 +73.970 i 3 +69.443 4 +70.107 5 +69.146 6 +64.204 7 +70.183 8 +70.349 9 +68.167 10 +69.935 ,

1 AVERAGE TEMPERATURE = +73.8087 DEG. F -

AVERAGE PRESSURE = +60.8457 PSIA MASS = +80647.28 LBM AVG DEW POINT TEMP = +69.6239 DEG. F ,

AVG VAPOR PRESSURE = +0.3583 PSIA ,

k f

t

PILGRIM NUCLEAR POWER STATION 1 :

INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 19:30 Pressure Instruments in PSIA channel pressure channel pressure !

1 +60.8219 2 +60.8371 :

RTDs in degrees F channel temp. channel temp. channel temp. l 1 +81.350 2 +81.621 3 +81.713 ,

4 +83.401 5 +78.541 6 +78.404 7 +76.026 8 +76.937 9 +75.772 l 10 +75.951 11 +73.728 12 +73.149 13 +71.199 14 +71.097 15 +74.363 16 +71.622 17 +73.011 18 +71.817 r

j Dew Cell temperatures in degrees F channel cell temp channel cell temp l 1 +73.536 2 +73.948 3 +69.477 4 +70.063 i 5 +69.090 6 +64.164 ;

7 +70.254 8 +70.431 9 +68.255 10 +69.961 AVERAGE TEMPERATURE = +73.8053 DEG. F AVERAGE PRESSURE = +60.8379 PSIA MASS = +80636.80 LBM !

AVG DEW POINT TEMP = +69.6558 DEG. F AVG VAPOR PRESSURE = +0.3587 PSIA !

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l 1

.l 2

i PILGRIM NUCLEAR POWER STATION 1 l INTEGRATED LEAK RATE TEST TEST MODE : VERF ;

DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 19:45 i

Pressure Instruments in PSIA l channel pressure channel pressure ,

1 +60.8143 2 +60.8297 i RTDs in degrees F l r channel temp. channel temp. channel temp.

l 1 +81.368 2 +81.656 3 +81.727 4 +83.424 5 +78.556 6 +78.408 7 +76.022 8 +76.930 9 +75.763 10 +75.953 11 +73.721 12 +73.143 l 13 +71.189 14 +71.087 15 +74.364 '

16 +71.622 17 +73.001 18 +71.804 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +73.435 2 +73.897 i 3 +69.408 4 +69.979 5 +69.039 6 +64.086 7 +70.005 8 +70.332 9 +68.149 10 +69.908

-__________---_______-_-____--_-__--_-____________--__----__-_-__ i I

I AVERAGE TEMPERATURE = +73.8008 DEG. F !

AVERAGE PRESSURE = +60.8304 PSIA MASS = +80629.13 LBM AVG DEW POINT TEMP = +69.5560 DEG. F AVG VAPOR PRESSURE = +0.3575 PSIA l

i

PILGRIM NUCLEAR POWER STATION 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 20:00 I

l Pressure Instruments in PSIA channel pressure channel pressure ;

1 +60.8065 2 +60.8223 !

t RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.387 2 +81.679 3 +81.739 4 +83.405 5 +78.580 6 +78.413 7 +76.020 8 +76.927 9 +75.771 10 +75.945 11 +73.705 12 +73.142 13 +71.192 14 +71.082 15 +74.369 16 +71.625 17 +72.991 18 +71.791 Dew Cell temperatures in degrees F <

channel cell temp channel cell temp 1 +73.350 2 +73.717 3 +69.466 4 +70.145 5 +69.117 6 +64.070 7 +70.146 8 +70.485 9 +68.221 10 +69.904 i AVERAGE TEMPERATURE = +73.7977 DEG. F l AVERAGE PRESSURE = +60.8228 PSIA MASS = +80618.20 LBM j AVG DEW POINT TEMP = +69.6336 DEG. F AVG VAPOR PRESSURE = +0.3584 PSIA l

l l

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l l

i l

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1

Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 20:30 Pressure Instruments in PSIA channel pressure channel pressure 1 +60.8065 2 +60.7907 RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.422 2 +81.719 3 +81.756 4 +83.398 5 +78.600 6 +78.441 7 +76.023 8 +76.925 9 +75.771 1 10 +75.949 11 +73.699 12 +73.139 !

13 471.178 14 +71.078 15 +74.346 16 +71.588 17 +72.965 18 +71.770 ,

Dew Cell temperatures in degrees F channel cell temp channel cell temp

~ -----__ --------- _--_--_ ------_ -

1 +73.279 2 +73.717 3 +69.442 4 +70.094 5 +69.072 6 +64.114 '

7 +70.156 8 +70.152 9 +68.118 10 +69.842 f

t AVERAGE TEMPERATURE = +73.7839 DEG. F AVERAGE PRESSURE = +60.8070 PSIA MASS = +80600.68 LBM AVG DEW POINT TEMP = +69.5429 DEG. F AVG VAPOR PRESSURE = +0.3573 PSIA

__ . _ _ _ . . _ . . _ - - _ _ _ ._ __ _ . _ = . . _

\

l Pilgrim Nuclear Power Plant 1 l INTEGRATED LEAK RATE TEST TEST MODE : VERF )

DATA POINT

SUMMARY

SHEET DATE : 139 l TIME : 20:45 ,

i

_________________________________________________________________ i Pressure Instruments in PSIA )

channel pressure channel pressure 1 +60.7985 2 +60.7837 i

RTDs in degrees F ,

channel temp. channel temp. channel temp.

1 +81.435 2 +81.732 3 +81.772 ;

4 +83.361 5 +78.611 6 +78.441 7 +76.020 8 +76.909 9 +75.775 >

10 +75.946 11 +73.689 12 +73.135 ;

13 +71.172 14 +71.070 15 +74.348 16 +71.572 17 +72.950 18 +71.756 I

I Dew Cell temperatures in degrees F q channel cell temp channel cell temp l 1 +73.519 2 +73.706 3 +69.463 4 +69.957 s 5 +69.064 6 +64.238 7 +70.228 8 +70.146 9 +68.201 10 +69.837 .

AVERAGE TEMPERATURE = +73.7746 DEG. F AVERAGE PRESSURE = +60.7995 PSIA MASS = +80591.80 LBM ;

AVG DEW POINT TEMP = +69.5606 DEG. F ,

AVG VAPOR PRESSURE = +0.3575 PSIA 6

t

?

F

Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF 4 DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 21:00 s

Pressure Instruments in PSIA f channel pressure channel pressure l 1 +60.7916 2 +60.7759 1

RTDs in degrees F ,

channel temp. channel temp. channel temp.

1 +81.453 2 +81.753 3 +81.765 4 +83.380 5 +78.625 6 +78.453 !

7 +76.018 8 +76.914 9 +75.771 !

10 +75.943 11 +73.679 12 +73.130 -

13 +71.167 14 +71.060 15 +74.347 :

16 +71.566 17 +72.942 18 +71.741 i

t Dew Cell temperatures in degrees F ;

channel cell temp channel cell temp l

+73.448 1 2 +73.725 3 +69.544 4 +70.101 .

5 +69.098 6 +64.205 :

7 +70.408 8 +70.388 9 +68.255 10 +69.883 1 i

i AVERAGE TEMPERATURE = +73.7698 DEG. F AVERAGE PRESSURE = +60.7921 PSIA MASS = +80581.08 LBM AVG DEW POINT TEMP = +69.6613 DEG. F ,

AVG VAPOR PRESSURE = +0.3588 PSIA l l

l 1

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t Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 TIME : 21:15 Pressure Instruments in PSIA _

l channel pressure channel pressure '

1 +60.7832 2 +60.7678 RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.463 2 +81.767 3 +81.768 4 +83.423 5 +78.632 6 +78.466 7 +76.017 8 +76.900 9 +75.778 10 +75.942 11 +73.684 12 +73.124 13 +71.161 14 +71.056 15 +74.337 16 +71.546 17 +72.925 18 +71.734 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +73.318 2 +73.728 3 +69.497 4 +70.053 5 +69.109 6 +64.351 7 +70.338 8 +70.406 9 +68.163 10 +69.856 AVERAGE TEMPERATURE = +73.7620 DEG. F AVERAGE PRESSURE = +60.7839 PSIA MASS = +80571.77 LBM AVG DEW POINT TEMP = +69.6302 DEG. F AVG VAPOR PRESSURE = +0.3584 PSIA

Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 ;

TIME : 21:30 i

l Pressure Instruments in PSIA f channel pressure channel pressure f 1 +60.7762 2 +60.7607 !

I t

i RTDs in degrees F f channel temp. channel temp. channel temp.

1 +81.476 2 +81.785 3 +81.785 l 4 +83.387 5 +78.649 6 +78.469 i +76.900 9 +75.776 7 +76.020 8 !

10 +75.941 11 +73.669 12 +73.126 1 13 +71.155 14 +71.053 15 +74.334 ,

16 +71.533 17 +72.915 18 +71.724

}

_________________________________________________________________ i Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +73.396 2 +73.716 3 +69.499 4 +70.062 5 +69.025 6 +64.279 7 +70.411 8 +70.236 9 +68.035 10 +69.824 AVERAGE TEMPERATURE = +73.7562 DEG. F AVERAGE PRESSURE = +60.7768 PSIA l

MASS = +80564.09 LBM AVG DEW POINT TEMP = +69.5770 DEG. F AVG VAPOR PRESSURE = +0.3577 PSIA 1

I 3

. = - - .- . . -- .

Pil' grim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 -

TIME : 21:45 I

Pressure Instruments in PSIA i channel pressure channel pressure i

1 +60.7685 2 +60.7528 i

RTDs in degrees F channel temp. channel temp. channel temp. l 1 +81.483 2 +81.793 3 +81.782 4 +83.388 5 +78.656 6 +78.478 ;

7 +76.011 8 +76.884 9 +75.774 j 10 +75.943 11 +73.663 12 +73.120 >

13 +71.150 14 +71.049 15 +74.327 16 +71.522 17 +72.907 18 +71.711 Dew Cell temperatures in degrees F l channel cell temp channel cell temp 1 +73.356 2 +73.753 '

3 +69.458 4 +70.030 ,

5 +69.108 6 +64.311 7 +70.459 8 +70.136 9 +68.223 10 +69.850 t AVERAGE TEMPERATURE = +73.7484 DEG. F AVERAGE PRESSURE = +60.7690 PSIA MASS = +80554.40 LBM AVG DEW POINT TEMP = +69.6066 DEG. F AVG VAPOR PRESSURE = +0.3581 PSIA

i Pilgrim Nuclear Power Plant 1 I INTEGRATED LEAK RATE TEST TEST MODE : VERF l DATA POINT

SUMMARY

SHEET DATE : 139 !

TIME : 22:00 l

l Pressure Instruments in PSIA i

channel pressure channel pressure i

1 +60.7596 2 +60.7442 -

i RTDs in degrees F channel temp. channel temp. channel temp.

1 +81.492 2 +81.791 3 +81.772 ,

4 +83.391 5 +78.669 6 +78.489 7 +76.003 8 +76.884 9 +75.767-10 +75.938 11 +73.645 12 +73.113 ,

13 +71.145 14 +71.041 15 +74.327 16 +71.508 17 +72.895 18 +71.697 i l

Dew Cell temperatures in degrees F

_________________________________________________________________ t channel cell temp channel cell temp 1 +73.570 2 +73.595 [

3 +69.440 4 +70.050 i 5 +69.062 6 +64.193 7 +70.382 8 +70.235 9 +68.094 10 +69.793 AVERAGE TEMPERATURE = +73.7398 DEG. F AVERAGE PRESSURE = +60.7603 PSIA MASS = +80544.55 LBM AVG DEW POINT TEMP = +69.5742 DEG. F AVG VAPOR PRESSURE = +0.3577 PSIA f

s 4

Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF DATA POINT

SUMMARY

SHEET DATE : 139 {

TIME : 22:15 i 7

Pressure Instruments in PSIA channel pressure channel pressure 1 +60.7527 2 +60.7371 f

_________________________________________________________________ t RTDs in degrees F channel temp. channel temp. channel temp. l 1 +81.501 2 +81.806 3 +81.774 4 +83.363 5 +78.681 6 +78.493 7 +75.996 8 +76.888 9 +75.756 10 +75.933 11 +73.634 12 +73.110 13 +71.139 14 +71.042 15 +74.317 16 +71.502 17 +72.882 18 +71.686 Dew Cell temperatures in degrees F channel cell temp channel cell temp 1 +73.486 2 +73.468 3 +69.484 4 +70.071 '

5 +69.105 6 +64.043 7 +70.361 8 +70.278 9 +68.207 10 +69.782 ,

l l

i l

1 AVERAGE TEMPERATURE = +73.7334 DEG. F AVERAGE PRESSURE = +60.7533 PSIA MASS = +80535.82 LBM AVG DEW POINT TEMP = +69.5965 DEG. F I AVG VAPOR PRESSURE = +0.3580 PSIA

i Pilgrim Nuclear Power Plant 1 INTEGRATED LEAK RATE TEST TEST MODE : VERF l DATA POINT

SUMMARY

SHEET DATE : 139 '

TIME : 22:30

- i i

Pressure Instruments in PSIA i channel pressure channel pressure 1 +60.7449 2 +60.7292 l 1

i RTDs in degrees F channel temp. channel temp. channel temp. 1 1 +81.502 2 +81.828 3 +81.767 l

4 +83.385 5 +78.687 6 +78.499 7 +75.995 8 +76.882 9 +75.741 l 10 +75.934 11 +73.625 12 +73.109 13 +71.145 14 +71.037 15 +74.319 16 +71.489 17 +72.873 18 +71.676 l l

Dew Cell temperatures in degrees F

_________________________________________________________________ i I

channel cell temp channel cell temp I 1 +73.506 2 +73.529 3 +69.399 4 +70.001 i 5 +69.083 6 +64.172 l 7 +70.358 8 +70.265 j 9 +68.179 10 +69.792 i

l i

l l

l AVERAGE TEMPERATURE = +73.7282 DEG. F -

AVERAGE PRESSURE = +60.7454 PSIA l MASS = +80526.41 LBM l AVG DEW POINT TEMP = +69.5794 DEG. F l AVG VAPOR PRESSURE = +0.3577 PSIA l<

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Appendix D '

INSTRUMENT SELECTION GUIDE CALCULATIONS !

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Page 1 of 5 i

INSTRUMENTATION SELECTION GUIDE CALCULATION l

A. Instrument Specifications

1. Total, Absolute Pressure

a. Paroscientific Precision Pressure Gages .

b. No. of sensors used in calculation: 2 i

c. Range: 0-100 psia (direct reading)

d. Accuracy: 0.010 psia

e. Sensitivity: 0.0005 psia -

i

f. Repeatability: 0.01 psia i

g. Resolution: 0.0001 psi 5

2. Water Vapor Pressure

a. Foxboro Lithium Chloride Dewcels !

b. No. of sensors: 10

c. Calibrated range: 37.5 - 100*F ,

d. Accuracy: 1.5'F

e. Sensitivity: 0.5"F

f. Repeatability: 0.5'F

3. Drybulb Temperature .

t

a. 100 ohm platinum RTDs

b. No. of sensors: 18 r

c. Calibrated range: 60 - 110*F

d. Accuracy: 0.5*F

e. Sensitivity: 0.001*F ,

f. Repeatability: 0.1*F I

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Page 2 of 5 j l

4. Data Acquisition System l

a. Fluke Model 2285 i

b. Drybulb Signal Conditioning / Readout

< i Repeatability: + 0.001*F 1)

2) Resolution: 0.001*F

c. Dewpoint Signal Conditioning / Readout j.

1) Repeatability: i 0.001*F :

2) Resolution: 0.001*F 5 '

B. Instrument and Measurement System Errors .

1. Definitions j

\

l a. e= the error associated with the measurement of change in a given l i parameter. l r

I b. E= the error associated with the sensitivity of the sensor. j

c. t= the error associated with the measurement system readout and ,

j signal conditioning (excludes sensor), including resolution and !

) repeatability.

t 1) Instmmentation errors (e.g., repeatability and resolution) are i 1 t 4 combined using a root-sum-square formula (per ANSI /.ANS 56.8- l I

i 1987, Appendix G). r l 2) In cases where repeatability is tested and specified for both the !

sensor and the readout device, the largest source of error is used to !

j calculate c.

r f

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l Page 3 of 5 {

i C. Instrument Errors

1. Total, Absolute Pressure ;

a. Sensitivity E,= 0.001 psia (per manufacturer spec.) ,

r

b. Resolution and Repeatability l

c, = [(0.0001)2 + (0.01 psia)2)ta j d

=

[1 x 10* + 1 x 10 ]'" l

= 1 [1.0001 x 10"]'8 {

c, = 1 1 x 10-2 psia

c. Measurement System Error l e, = [(Ep)2 , (,p)2)m/[no. of sensors]"

= 1 [(0.0005)2 + (1 x 10 2)2)in/(2)" ;

4 d

= 1[2.5 x 10 + 1 x 10 ]"/1.414 ;

=

[1.0025 x 10"]"/1.414 j e, = 17.081 x 10 psia !

O 2. Drybulb Temperature j

a. Sensitivity Er = i 0.001*F

b. Resolution and Repeatability ,

or= 1 [(0.001)2 + (0.1)2)m

= i [1 x 104 + 1 X 10 2)m

= i[1 X 10 )m 2 j i

er = 10.100*F

c. Measurement System Error e=

r [(Er)2 + (c7)2)m/(no. of sensors)"

= 1 [(0.001)2 , (9,3)2)m/(18)" <

2

= 1 [1 x 104 + 1 x 10 )m/4.243 l f

=

i [1 x 10]"/4.243 l

! er= 10.0236*F l O :

i P

--_.r , _ . _ _ , ,m , - - , .

Page 4 of 5 i l !

t

3. Water Vapor Pressure !

a. Sensitivity ;

Ey= 0.5"F j

b. Resolution and Repeatability !

cy = [(.001*F)2 , (0.5)2]t"

=

1 [1 x 10*F + .25]'"

= l

[.25] "

ry = 0.5'F !

c. At 75 F dewpoint, water vapor pressure change /"F is 0.0143 psia /'F l

d. Measurement System Error l ey = 1 [(E y)2 # (e p)2)in/(no. of sensors)'"

= 1 [(.5)2 + (.5)2]"/(10)'" f

= 1 [0.5]'"/3.162 l

= 0.2236*F x 0.0143 psia /"F ey = 13.13 x 10~' psia ,

D. Instrumentation Selection Guide Formula (24 hr. Test)

[

?

= 1100 [2(1.157 x 10')2 + 2(5.114 x 10-5)2 + 2(4.333 x 10-3)2)tn ,

=

100 [2(1.339 x 10*) + 2(2.615 x 10*) + 2(1.877 x 10*)]'"

= 4 100[2.678 x 10 + 5.230 x 104 + 3.754 x 10*]'"

=

4 100 [3.576 x 10 ]'"

d

= 1100 [1.891 x 10 ]

ISG = 0.0189%/ day O

i Page 5 of 5 i

E. ISG at 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s: !

24 d ISG = 1 3 1.891 x 10 ]

d

=

300 [1.891 x 10 ] -

ISG = 0.0567%/ day F. ISG Acceptance Criteria :

1. ISG must be s 25% L, :

1

2. 25% (1% wt/ day) = .25%/ day

^

3. ISO = 0.0189% 5 0 25%/ day

, for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months :

4 1 4. ISG = 0.0567% 5 25%/ 0 day

~

d for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months i

5 l

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Appendix E l i

SENSOR LOCATIONS O

i r

I a

1 O

i

~ ELEVATICN AZiWUTH g,, .C 6'- 3 3/4 " l O 9; IE*C $go

//'ZO$E /

/A x

- EL. 9 3'- 3 -3/4 '

I l

l N NN , i ZONEE' N < '\

ZCNEB N TE-0330I . e l EL. 81 1/4 g -

M N ,- j 0* /

/ N V 3,s e d, f / s N f /N TE-B . l

,'/ N N // l

'/ s s, f TE-F , /,' N N /

/ 60' f' N N /'# 27C* l

//'/ s' N b/ l

/ / /

s N r CNEC' ,ZCNE C EL. 50'- 6"

% O

=

TE-Gl0 TE-J '2 1,' &s ZON E ,0^

x .__s_ "9 "

A ZONE D 5\ .. x - TE- 1 < l80' EL. It'- 6*

i 22' -- Z CN -TE-L 2CS'

[(f7/f TE-M q, , ,

12' // e- I / // f/ E L. !6* - 10" l

'(

125' MAD $UN { l TE- q

/ ,,

sssh\\sk'ZCNE Fe ICNE 'ZCNE

{ as m N.

"W E L. 9'- 2 l

/ ngN s 3ss -

f

.m s

~~~

g s% l

[7 ' $1,,')E'sDys j [ t I !

I I TE-N 7, g 15, I

/ h I

~

\ f ZONE J k ZONE J '

% ,/ %s /

T PROFILE VIEW

[TE-S120* TE-0h NOTES:

1. ZONE BOUNDARtES ARE APPROX!WATE, REFERENCE PNPS CALC. No. US-009.

2. INSTRUWENT ELEVATION AND AZiWUTH POSITIONS ARE APPR0xlWATE.

ILRT RESISTANCE TEMPERATURE O DETECTOR LOCATIONS PILGRIM NUCLEAR POWER STATION-UNIT No.1

, ELEVATION E L .10 6' 3 /4 '

ME-A C' A b4'

/r/ - ME-B :

j a: 180* t

/

Q//[/ /[ / '

EL. 8 t'-6-1/4"

\

s sN N :

\

N -

N N -

N N s sN N: 4 S

( E L.1 O*- 6" ;

ME-D h 43' l N

ZONE 2 NNN\

> x h

\ ZONE 2

\\NNN z'o-E L. 31'- 6" I / ' 22' 22' / / ---- W E - E i ME F ,, i , w/ // , ,,f / <

20s*

[ /' ZCNE 4 [! '

O T

/0 4

/ //g' ~ ME Kgana l

' 2CNE 3 / ['[/ZONE 3 l/

p f~ / /,5 ,' // (k // // 0 % EL.9'-2' h/ ,'} d>

f $,'!' t ~t' \

k I l L ME-G k I 2CNE5 180 ZCNE 5 w

%su-

[ME-J 120*

PROFILE VIEW ME- H NOTES:

1. ZCNE BOUNDARIES ARE APPRCK!W ATE, REFERENCE PNPS CALC. No. WB -009. I

2. INSTRUMENT ELEVATION AND AZlWUTH PCSITIONS ARE APPROXIWATE. .

ILRT DEWPOINT TEMPERATURE SENSOR LOCATIONS PILGRIM NUCLEAR POWER STATION-UNIT No.1

. i

SENSOR LOCATIONS AND VOLUME FRACTIONS VOLUME AZIMUTH WEIGHTING O SENSOR NUMBER LOCATION ELEV.

(FEET) (DEGREES) FACTOR i TE-A DREVELL 87 0 0.014678 TE-B DRYWELL 84 180 0.014678 ,

4 TE-C DRYWELL 91 50 0.009113 TE-D DRUVELL 91 330 0.009113 TE-E DRUVELL 60 270 0.025920 TE-F DRUVELL 60 90 0.025921 TE-G DRUVELL 39 270 0.069702 TE-H DRYWELL 39 90 0.069703 TE-J DRUVELL 32 0 0.005330 TE-K DRYWELL 28 180 0.005330 1 :

. TE-L DRUVELL 22 205 0.071493 S

TE-M DRUVELL 22 45 0.071494 TE-N DRYWELL 14 270 0.056466 TE-O DRYWELL 15 0 0.020245 TE-P DRYWELL 12 125 0.056467 i

TE-Q TORUS 0 0.158115 TE-R TORUS 240 0.158116

TE-S TORUS 120 0.158116 i ME-A DRYWELL 94 0 0.023791 ME-B DRYWELL 94 180 0.023792 ME-C DRYWELL 39 270 0.095622 ME-D DRUVELL 39 90 0.095623 ME-E DRYWELL 22 205 0.127960 i

ME-F DRUVELL 15 180 0.030905 ME-G DRYWELL 22 45 0.127960 ME-H TORUS 0 0.158115

ME-J TORUS 120 0.158116 ME-K TORUS 240 0.158116

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l Appendix F I

A j DESCRIPTION OF GENERAL PIIYSICS ILRT COMPUTER PROGRAM i :

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i

DESCRIPTION OF GENERAL PHYSICS '

ILRT COMPUTER PROGRAh!

4 O 4 The fallowing paragraphs describe the various features and attributes of the General Physics

! ILRT Data Management computer program and the process used to cenify it each application.

I ,

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

microcomputers during the ILRT for on site data reduction and analysis. The computer i

software and hardware irectfaced directly with the Fluke Model 2285B Data Acquisition System for the test. ]

I Two computers were brought on site for 100% redundancy, as each computer and its software '

was capable of independently performing the ILRT. The General Physics ILRT Data Management Software is also capable of accepting manual input of raw sensor data and )

performing all required sensor data conversions if the data logger would cease to function. l The program installed on each computer was designed to write to the hard drive and the back-up disk in the "A" drive to protect against the unlikely event of a disk " crash."

The General Physics ILRT Data Management Computer Program is written in IBM's BASIC l and Microsoft's Quick Basic 4.5. BASIC is a high level programming language which

. combines programming ease with user oriented command functions to create an easy to use '

and understand program. In order to increase its speed of operation the program was then compiled into an executable command Sle. Compiling was accomplished using the Microsoft's Quick Basic 4.5 Compiler. In addition to execution speed, this had the added benefit of making the program more secure, as compiled programs cannot be edited or j

changed. j

~i SECURITY l

In addition to execution speed, compiling has the added benefit of making the program more secure as compiled programs cannot be edited or changed. Also, as the program does not j need to be attended to operate, a password is required to change modes of operation, stan I times or to enter the data editing routine. The data editing routine itself is purposely designed !

to be extremely user un-friendly and implementable only by the GP programmers as General l Physics believes that the integrity of the raw data files is paramount. ;

FEATURES 4

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

1. Pressurization Mode

2. Stabilization Mode

3. Test Mode

4. Verification Mode O 5. Depressurization Mode These modes correspond to the phases of the ILRT. Menu driven means that the user is presented with a list of options that the program can perform and from which the user can choose. It allows for interactive information exchange between the user and the computer and prevents invalid information or user mistakes from crashing the program. Program organization consists of a master menu which controls access to the five operating modes chained to the individual menus which control these modes. The data processing, information display capabilities and function of each mode is as follows:

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

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

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

including a superimposed acceptance criteria line).

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

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

Other reduction and analysis capabilities of the General Physics ILRT computer program include:

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

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

3. Containment dewpoint temperature weighted averaging and conversion to partial pressure of water vapor (psia).

I

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

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

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

Sensor performance and deviation information for sensor failure criteria, l 7.

graphic display of individual sensor performance for selected operating mode.

8. Calculation of ISG formula at beginning of test; acceptance criteria based on number of sensors remaining and actual test duration.

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

COMPUTER PROGRAM CERTIFICATION The computer program used by General Physics and has been previously certified for six tests at the San Onofre Nuclear Generating Station and over a dozen other ILRT's. ;

The initial certification required verification of the program through hand calculations and an {'

independent review by Bechtel Power Corporation. After certification was completed a calibration set of raw data was established from the data which is used to verify performance of the program pnor to usage. ;

O l

Additionally, a hand calculated data set was entered into the program to further verify l performance, as configured for the ILRT. Acceptable agreement was obtained between the hand calculated results and the computer results, within the limits of truncation and round-off error.

Once the computer was linked to the data acquisition device and a complete data stream was available, the input function of each mode of the program was verified by comparing the data logger's output to the computer's printed data point summary.

General Physics also provided printouts of the installed constants for the test such as:

1. Volume Fractions for ILRT Measurement System Sensors

2. Installed Calibration Constants The microcomputer hardware and software remains the property of General Physics. General Physics supplied Boston Edison Company with certification documents for the ILRT microcomputer software for the ILRT in accordance with paragraph 4.2 of General Physics Corporation's CLRT Project Procedures Manual and the Purchase Order requirements.

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Appendix G ,

d RFO 9 LOCAL LEAKAGE TEST SUS 151 ARIES l 4

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l 1993 LOCAL LEAK RATE

SUMMARY

TYPE B DOUBLE GASKETED SEALS '

i AS FOUND AS LEFT l PEN. LEAKAGE LEAKAGE !

No. DESCRil"rION (SLM) (SLM) COMMENT NA GIBS MANWAY 0",45 ^,90',13 5' O.088 0.088 N/A GIBS MANWAY i 180*,225',270',315" 0.006 0.00G !

NA DRYWELL IIEAD 0.059 0.010 1 EQUIPMENT llATCil 0.00G 0.005 2 AIRLOCK INNER SEAL 0.022 0.004 AIRLOCK OUTER SEAL 0.005 0.005 4 DRYWELL IIEAD ACCESS IIATCll 0.115 0.115 G CRD REMOVAL IIATCil 0.003 0.003 25 AO 5044A INLIOARD FLANGE 0.002 0.002 AO-5044B INBOARD FLANGE 0.014 0.014 AO-5044B OUTBOARD FLANGE 0.001 0.001 20 AO-5035B INBOARD FLANGE 0.003 0.003 AO-5035A INBOARD FLANGE 0.003 0.003 AO-5035A OUTBOARD l FLANGE 0.002 0.002

, 35A 35B TIP DRIVE FLANGES 0.032 0.032 35C (4 INNER) 35D 35A ,

35B TIP DRIVE FLANGES 0.008 0.00E l 35C (4 OUTER) 351) 35E TIP NgPURGE 0.005 0.005 43 DRYWELL TEST CONNECTION FLANGE 0.003 0.003 47 ILRT TEST CONNECTION FLANGE 0.009 0.009 a

200A TORUS ACCESS IIATCH - EAST 0.013 0.003 l l

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

1993 LOCAL LEAK RATE SUMMAltY TYPE B DOUBLE GASKETED SEALS AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE NO. DESCRIPTION 'SLM) (SLM) COMMENT 200B TORUS ACCESS liATCII - NORT11 0.021 0.111 l 1

205 AO-5036B INBOARD FLANGE 0.003 0.003 1 l

AO-503GA INBOARD FIANGE 0.002 0.002 i AO-5036A OUTBOARD FLANGE 0.003 0.003 ,

223 IIPCI STEAM TO TORUS INBOARD FLANGE & 0.004 0.020 l

, OUTBOARD FIANGE f 2301-74 INBOARD &

OUTBOARD FLANGE 0.002 0.002 I 225 1301-64 INBOARD &

OUTBOARD FLANGE 0.003 0.003 l RCIC STEAM TO TORUS l INBOARD FLANGE & 0.002 0.002 OUTBOARD FIANGE 227 AO-5040A INBOARD & ;

OUTBOARD FLANGE 0.004 0.004 AO-5040B INBOARD & l OliTBOARD FLANGE 0.004 0.004 227A X-212A SEAT FLANGE 0.004 0.004 ,

227B X-212B SEAT FLANGE 0.004 0.004 4

227 AO-5012A INBOARD 3

FIANGE 0.003 0.003 >

A0-5042A INBOARD & .

OUTBOARD FLANGE 0.004 0.004 AO-5025 INBOARD

FLANGE 0.003 0.003 230 TORUS TEST !

CONNECTION FLANGE 0.003 0.003 j i i 1

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1993 LOCAL LEAK RATE

SUMMARY

TYPE B TESTABLE PENETRATIONS

~

AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE ;

NO. DESCRIPTION (SLM) (SLM) COMMENT 2 AIRLOCK INTEGRATED 0.317 5.14 7A MAIN STEAM & RCIC 53 STEAM TO TURBINE 0.042 0.042 7B MA1N STEAM (2) 0.091 0.091 .

7C l 7D MAlN STEAM & MAIN 8 STEAM DRAIN 0.003 0.003 9A FEEDWATER (2) 0.029 0.029 9B 12 RIIR SUCTION FROM RECIRC 0.726 0.726 51A RIIR RETURN TO RECIRC 0.004 0.004 l 14 CLEANUP SUPPLY TESTED !'

J IGA CORE SPRAY 0.003 0.003 TOGETIIER 1GB CORE SPRAY 0.005 0.005 17 RX VESSEL IIEAD SPRAY 0.487 0.487 ,

51B RllR RETURN TO 0.005 0.005 RECIRC

] 201G VENT LINE 0.004 0.004 j 52 IIPCI STEAM TO !

. TURBINE 0.014 0.014 :

20111 VENT LINE 0.005 0.005 ,

i 100C,D !

NEUTRON MONITORING (4)

- 102A,103 ELECTRICAL (3) 0.108 0.108 A,X-105B CRD POSITION (3) 104G 11'J ,

100A NEUTRON MONITORING I i 0.046 101NB ELECTRICAL (2) 0.04G 104D E F CRD POSITION (3) 100E NEUTRON MONITORING i 102B 103 ELECTRICAL (3) 0.028 0.028 l B,105A CRD POSITION l a 104B i

, 104A-C CRD POSITION (2) 0.026 0.026 !

100B NEUTRON MONITORING 0.077 0.077 10GB DRYWELL IIUMIDITY

i 1993 LOCAL LEAK RATE SU51 MARY TYPE B TESTABLE PENETRATIONS AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE :

NO. DESCRIIrrION (SLM) (SLM) COMMENT 101C ELECTRICAL 0.02G 0.026 201A VENT LINE 0.002 0.002 201B VENT LINE 0.004 0.004 201C VENT LINE 0.011 0.011 201D VENT LINE 0.013 0.013 201E VENT LINE 0.003 0.003 201F VENT LINE 0.006 0.006 202A ELECTRICAL 0.188 0.188 202B ELECTRICAL 0.019 0.019 4

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1993 LOCAL LEAK RATE

SUMMARY

'IYPE C TESTS i

AS FOUND AS LEFT [

PEN. LEAKAGE LEAKAGE NO. DESCRIPTION (SLM) (SLM) COMMENT 7A MAIN STEAM AO-203-1A 3.331 3.331 ,

AO-203-2A 1.793 1.793 7B MAIN STEAM AO-203-1 B 0.550 0.550 AO-203-2 B 0.550 0.550 $

7C MAIN STEAM i AO-203-1C G.295 G.295 .

AO-203-2C 2.494 2.494 I 7D MAIN STEAM ,

AO-203-1 D 0.542 0.542 AO-203-2D 1.884 1.884 S MAIN STEAM DRAIN I i

MO-220-1 1.90G 1.90G M O-220-2 1.906 1.90G 9A FEEDWATER

) 6-58A 0.058 0.058 G-62A 0.001 0.001 TESTED WITil MO-1301-49 1 l

+

RWCU RETURN MO-1201-80 0.003 0.003 RCIC DISCHARGE MO-1301-49 TESTED WITI{ G-62A 9B FEEDWATER G-58B 0.025 0.025 G-62B 0.205 0.205 TESTED WITII MO-2301-8 IIPCI DISCIIARGE MO-2301-8 TESTED WITH G-62B 12 RIIR SUCTION FROM RECIRC MO-1001-47 0.399 0.399 MO-1001-50 0.925 0.925 14 RWCUINLET MO-1201-2 0.774 0.774 MO-1201-5 15E 11000 ANALYZER "B" 3V-5065-35B 0.011 0.011 SV-50G5-31B 0.005 0.005 16A CORE SPRAY TO REACTOR TESTED IN MO-1400-24A 0.002 0.006 PARALLEL MO-1400-25A

q 1993 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS AS FOUND AS LEFf !

PEN. LEAKAGE LEAKAGE !

N O. DESCRIP'flON (SLM) (SLM) COMMENT ;

16B CORE SPRAY TO REACTOR TESTED IN MO-1400-24B 2.250 2.250 PARALLEL -

MO-1400-25B ,

18 DRYWELL FLOOR DRAIN j AO-7017A 3.010 3.010 AO-7017B 3.318 3.318 19 DRYWELL EQUIP-MENT DRAIN AO-7011 A 0.024 0.024 AO-7011 B 1.323 1.323 ,

22 INSTRUMENT AIR ,

TO DRYWELL 31-CK 167 1.483 1.483 23 RBCCW SUPPLY 30-CK-432 0.070 0.005 24 RBCCW RETURN MO-4002 0.004 0.004 2

25 DRYWELL PURGE

EXIIAUST AO-5044A 0.062 0.062 TESTED IN PARALLEL l AO-5044B l DRYWELL VENT EXHAUST i l AO-5043A 1.496 0.354 TESTED IN PARALLEL :

AO-5043B l 1 'l POST ACCIDENT l

PURGE & VENT l

.SV-5082A 0.002 0.002 TESTED IN PARALLEL I SV-5081 B l POST ACCIDENT PURGE & VENT I

SV-5081A 0.002 0.002 TESTED IN PARALLEL SV-5082 B 28 DRYWELL PURGE INLET AO-5035A AO-5035B 1.815 1.815 TESTED IN PARALLEL AO-5033B POST ACCIDENT TESTED IN PURGE & VENT PARALLEL SV-5085A 0.076 0.076 SV-5085B

1993 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS AS FOUND AS LEFT '!

PEN. LEAKAGE LEAKAGE l NO. DESCRIPTION (SLM) (SLM) COMMENT l 26 POST ACCIDENT TESTED IN l PURGE & VENT PARALLEL i SV-508GA 0.036 0.03G l SV-5086B i DRYWELL MAKEUP TESTED IN GAS PARALLEL 9-CK-340 0.081 0.081 DRYWELL MAKEUP GAS AO-5u33A 0.524 0.524 29E Iloo nANALYZER "A"

~ ~SV-5065 37A 2.230 2.230 SV-5065-33A 0.326 0.32G 32A C-19 RETURN !

TO DRYWELL i CV-50G5-91 0.13G 0.13G !

CV-5065-92 0.077 0.077 {

35A TIP BALL VALVE 4 ,

45-300D 0.092 0.073 [

35B TIP BALL VALVE 3 TESTED WITH 45-300D 45-300C l 35C TIP BALL VALVE 1 .

45-300A 0.044 0.683 !

C.3 D TIP BALL VALVE 2 TESTED WITH 45-300A l 45-300B 35E TIP No PURGE

CITECK 0.005 0.005 39A CONTAINMENT ;

SPRAY MO-1001-23A 0.24G 0.012 TESTED IN PARALLEL i MO-1001-2GA >

39B CONTAINMENT SPRAY MO-1001-23B 3.558 3.558 TESTED IN PARALLEL ]

4 MO.1001-2GB 40Aa JET PUMP SENSING LINE PASS SV-5065-G3 0.006 0.006 i SV-5065-64 0.010 0.010 40De JET PUMP SENSING LINE PASS SV-5065-85 0.473 0.473 SV-5065-SG 0.002 0.002

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1993 LOCAL LEAK RATE

SUMMARY

l TYPE C TESTS j l

AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE l NO. DESCRIPTION (SLM) (SLM) COMMENT i 41 RECIRC PUMP B DISCll SAMPLE AO-220-44 0.003 0.003 AO-220-45 0.090 0.090 42 STANDBY LIQUID CONTROL 1101-1G 0.013 0.013 ,

43 DRYWELL TEST -

CONNECTION 45-110-106 0.050 0.050 ,

4GA RECIRC PUMP ,

SEAL 2G2-F013A 1.211 1.211 l

262-FO17A 0.986 0.986 4GB RECIRC PUMP ;

SEAL l 262-F013 B 3.963 3.963 l

262-F017B 3.818 3.818 4GF 119 90 ANALYZER

~"A* RETURN SV-5065-26A 0.077 0.077 !

SV-5065-24A 0.011 0.011 ,

47 DRYWELL TEST 45-HO-102 0.144 0.144 TESTED IN PARALLEL 45-110-104 ,

45-110-103 0.132 0.132 TESTED IN PARALLEL ,

45-110-105 ?

50Ad II 900ANALYZER "B"

~ BV-5065-13B 0.154 0.154 SV-5065-20B ,

51A RHR VESSEL RETURN '

MO-1001-28A 0.474 0.525 MO-1001-29A 0.222 0.385 51B RIIR VESSEL RETURN MO-1001-28B 0.780 0.780 ,

MO-1001-29B 2.425 2.425 i

52 HPCI STEAM ;

TO TURBINE MO-2301-4 0.072 0.042 TESTED IN PARALLEL ;

MO-2301-5 :

I

1993 LOCAL LEAK RATE

SUMMARY

l TYPE C TESTS ;

AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE NO. DESCRIPTION (SLM) (SLM) COMMENT 53 RCIC STEAM TO TURBINE MO-1301-16 0.055 0.003 TESTED IN PARALLEL MO-1301-17 10 gab 110 00 ANALYZER "A" -

~ 3V-5065-14A 0.033 0.033 SV-50G5-21 A 0.033 0.033 205 TORUS MAKEUP GAS 0-CK-341 0.248 0.248 AO-5033-C 0.226 0.226 .

POST ACCIDENT PURGE & VENT SV-5087A 0.232 0.232 TESTED IN PARALLEL SV-5087B l POST ACCIDENT PURGE & VENT l SV-5088A 0.230 0.230 TESTED IN PARALLEL j SV-50 SRB r '

TORUS PURGE INLET (X-205) l AO-503GA 1.340 1.340 TESTED IN PARALLEL i AO-503GB 211A RHR TO TORUS SPRAY l MO-1001-34A 0.306 0.046 TESTED IN PARALLEL l MO-1001-37A i 211B RilR TO TORUS SPRAY MO-1001-34B 0.078 0.078 TESTED IN PARALLEL MO-1001-37B 219 HPCI VACUUM BREAKER MO-2301-33 0.747 0.747 MO-2301-34 0.476 0.476 223 HPCIEXHAUST 2301-74 SEE APP. I 0.137 REPAIRED / MODIFIED STOP CHECK POPPET 2301-45 1.778 2301-218 0.095 l

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1993 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS AS FOUND AS LEFT PEN. LEAKAGE LEAKAGE NO. DESCRHTION (SLM) (SLM) COMMENT 223 CV-90G8A 0.031 0.015 AS FOUND TESTED IN CV-90GSB PARALLEL CV-90G8B 0.012 AS LEFT TESTED SEPARATELY (NEW VALVES) i 227A TORUS VACUUM BREAKERS AO-5040A 0.057 0.057 TESTED IN PARALLEL l X-212A 227B TORUS VACUUM BREAKEILS AO-5040B 0.004 0.004 TESTED IN PARALLEL X-212 B 227 TORUS EXilAUST l VALVE BYPASS l AO-5041A 0.310 0.310 TESTED IN PARALLEL AO-5041B

> TORUS MAIN EXilAUST & DIRECT '

VENT AO-5042A AO-5042B 0.G12 0.612 TESTED IN PARALLEL AO-5025 J POST ACCIDENT PURGE & VENT -

SV-5084A 0.274 0.274 TESTED IN PARALLEL :

SV-5083B POST ACCIDENT PURGE & VENT SV-5083A 0.094 0.094 TESTED IN PARALLEL SV-5084B 22SC 110 0 9 ANALYZER "B"

~ 3V-5065-15B 0.008 0.008 !

SV-5065-22B 0.034 0.034 22SE AIR TO TORUS

, VACUUM BREAKERS CV-5046 2.338 2.338 31-CK-434 0.830 0.830 22SG GAS SAMPLE RETURN-PASE SV-50G5 77 0.402 0.402 SV-50G5-78 0.195 0.195 t

1993 LOCAL LEAK RATE

SUMMARY

TYPE C TESTS

[ PEN.

AS FOUND LEAKAGE AS LEFT LEAKAGE :

NO. DESCRII"rION (SLM) (SLM) COMMENT 22811 GAS SAMPLE RETURN-PASS SV-50G5-71 0.004 0.004 SV-50G5 72 0.020 0.020 22&J 1I~9 09 ANALYZER "A"

$V-5065-11A 0.010 0,010 SV-5065-18A 0.051 0.051 22SK 1I0~0 0ANALYZER "B"

~ RETURN '

SV-50G5-25B 0.503 0.503 SV-5065-27B 0.464 0.464 1

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

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. APPENDIX II i i

1991/1992 LOCAL LEAK RATE TEST DATA j

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t 1991/1992 LOCAL LEAK RATE TEST DATA LEAKAGE NOTES EQUIPMENT / (SLM)

PEN TYPE VALVE DATE i NO. DESCRIITION TEST TESTED TESTED 1 EQUIPMENT B DOUBLE 0.014/10-31-91 IIATCil 0-RING 0.009/11-4-91 l t

2 AIRLOCK B DOUBLE TESTED 25 !

INNER SEAL O-RING TIMES :

FROM 7-23-91 !

THRU 12-23-92 !

LEAKAGE l RANGED FROM !

0.003 TO 0.215 l (NO FAILURES) l AIRLOCK B DOUBLE TESTED 2G ;

OUTER SEAL O-RING TIMES j FROM 7-23-91 THRU 12-23-95

, LEAKAGE RANGED FROM 0.003 TO 0.019 (ONE FAILURE) ,

AIRLOCK B 2.140/7-25-91 .

INTEGRATED 0.090/8-10-91 i

TEST 0.755/10-31-91 3.040/11 18-91 3.110/11-19-91 0.355/3-26-92 ,

I 0.618/4 13-92 0.3G0/10-23-92 3.300/11-21-92 ,

0.256/12-16-92 8 MAIN STEAM C MO-220-1 0.870/10-28-92 DRAIN 1.430/11-5-92 ;

9A FEEDWATER C G-58A 0.062/10-26-92 G-62A 0.062/10-26-92 RCIC DISCH C MO-1301-49 0.062/10-26-92 0.460/11-3 92 {

1-DB FEEDWATER C G-58B 0.054/10-26-92 '

6-62B 0.151/10-26-92 WITH 6-62B HPCI DISCH C MO-2301-8 0.159/11-19-92 BETWEEN [

SEATS i 1GB CORE SPRAY C MO-1400-24B 1.225/11-2-92 TESTED IN TO REACTOR MO-1400-25B 0.958/11-16-92 PARALLEL i 39B CONTAINMENT C MO-1001-23B 5.040/11-2-92 TESTED IN SPRAY MO-1001-26B 0.179/11-19-92 PARALLEL ,

SIB RilR VESSEL C MO-1001-28B 0.080/11-2-92 RETURN 0.05G/11 18-92 i

I 1991/1992 LOCAL LEAK ltATE TEST DATA :

LEAKAGE NOTES EQUIPMENT / (SLM)

PEN TYPE VALVE DATE NO. DESCRIITION TEST TESTED TESTED 53 RCIC STEAM C MO-1301-16 TESTED IN TO TURBINE MO-1301-17 PARALLEL 0.099/3-27-92 MO-1301-1G MANUALLY >

CLOSED & ,

GAGGED :

AFTER I TEST VOLUME t WOULD NOT I PRESSURIZE ;

0.120'4-4-92 t 0.050/10-28-92 0.117/11-20 92 211B RilR TO TORUS C MO-1001-34B 0.034/11-2-92 TESTED IN '

SPRAY MO-1001-37B 0.GG0/11-18.'92 PARALLEL i I

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1 APPENDIX I ,

2301-74 FAILURE ANALYSIS TEAM REPORT e i

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. i FAILURE ANALYSIS TEAM :

O 2301-74 VALVE i

R. O'Neil1 Y cc: N. Desmond G. Choquette N J. Bellefeuille W. Grieves t G. James 6 G. Dyckman T. Satterf eld (A/D)

M. Cowell A/D) L. Mcdonald i D. Heardf,inop(O'81 P. Mander !

G. McCarthy ,

M. McC1ellan 1 i

Problem

Description:

The 2301-74, HPCI Torus Discharge Valve (Turbine i Exhaust Stop Check Valve), failed its RFO-09 LLRT.

1 Valve Data: 23-CK-2301-74 HPCI Torus Discharge Valve; 20", 150#, ;

Y Globe Stop Check Valve, soft seat; manufactured by Anchor / Darling.

Valve History:

. O 1984 - Installed i 1987 (RF0-07) - LLRT failed (see TCH 88-20)

9/1988 - LLRT passed j 4/1990 - LLRT passed ;

5/1991 (RF0-08) - LLRT failed (see MSED 91-181) 4/1993 - LLRT failed .

i As Found Conditions (RFO-09): l

! General:

I 1) Valve seat, body and disc seats all found in generally good condition and within manufacturer's tolerances. l

2) Disc not centered (radially) in bore.

3) Disc vertical position was not equi-distant from top flange !

(cocked within bore). l

4) Soft seat was chipped at the 2 o' clock position - matching a I

nick on the seat ring (not considered a contributing cause). !

l Specifics: (

1) Anchor / Darling Component Inspection & Repair Report ,

(Attachment 1A & IB)

2) Anchor / Darling Initial Poppett & Valve as Found Measurements l O 3) and Drawings (Attachments 2A thru 2D)

Anchor / Darling Follow-up Poppett Detail Measurements and Drawing (Attachment 3) l'

m__ _. .. . _ _ __

Immediate Actions Taken: Initiated PR93.0235, no other immediate actions O were necessary as the plant was in cold shutdown.

Root and Contributing Cause:

The direct cause of the LLRT failure is improper disc seating and alignment.

This has been attributed to less than optimum valve design for the conditions the valve is normally operated. Valve installation and maintenance have been adequate. The failure was caused by the interaction of several design parameters and valve disc as-found condition, rather than from the affect of only one condition. Parameters contributing to the improper valve seating are: shortened disc height to width ratio, disc skirt guides to body bore tolerances, distortion of the disc upper guide skirt, disc and valve geometry that results in a low center of gravity (CG), excessive resilient seat projection, and low closing force. Failure to optimize valve design to compensate for the interaction of each of these parameters and the uniqueness of design is the root cause. 5 Each contributing cause is listed below along with a brief discussion and recommended corrective action (as necessary).

1) Disc height is limited due to the location and orientation of the valve.

The piping where the valve is installed is very close to the ceiling of O the HPCI quadrant. This minimizes vertical space above the valve for disassembly and/or valve top works. This reduced vertical clearance is one of the limiting design factors which led to the use of an angle lift check and also limited the available stroke and therefore overall length of the check valve disc subassembly. The valve manufacturer has indicated that without vertical space limitations the preferred disc guide separation height should be equal to the disc width. For the 2301-74, an approx.18" diameter disc, that would result in an 18" disc guide height. The actual guide height is approx. 9" as set by design.

This ' shortened' disc allows for greater angular rotation at the seats ;

and therefore more cocking of the valve within the valve body bore, for a given tolerance in diametrical dimensions.

Lengthening the disc guide separation to the maximum extent possible within the constraints of the current valve body is required.

2) Disc subassembly misalignment was not prevented by internal valve tolerances. Less than optimum internal tolerances are a contributing ,

cause. Internal valve tolerances should be optimized to ensure proper disc subassembly alignment.

, 3) Distortion of the disc subassembly allowed cocking within the guides by effectively reducing the disc guide separation height. Thermal and ;

mechanical distortion are the contributing failure mechanisms.

Thermal distortion can be limited by providing greater mass or limiting thin cross-sections in the upper disc skirt subassembly and center pipe.

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Mechanical distortion could be caused by hydrodynamic transients which O would have placed high loads on the disc subassembly possibly leading to skirt distortion. The HPCI exhaust line has a history of these i transients. The last documented transient occurred on 5/18/85 (well after 2301-74 installation) and is described in NED 85-527. This transient was attributed to water induction from the torus into the HPCI turbine exhaust line after a turbine start, trip and an auto restart.

The resulting waterhammer resulted in damage to snubbers on the HPCI exhaust line. Future transients have been mitigated by design changes which included installation of vacuum breakers to prevent water induction (PDC 85-59).

Additionally, mechanical distortion could have been caused by improper disc handling during shipment, installation or subsequent handling during maintenance. Typically receipt inspection would not be detailed enough to identify this type of problem. Mechanical distortion through waterhammer has been prevented by installation of PDC 85-59. Distortion caused by improper disc handling, if it occurred, is considered to have been an isolated occurrence.

4) The disc's center of gravity is approx. 4" above the bottom or seating end of the disc. This Y angle lift check causes the disc to travel in a plane approx. 45 degrees from vertical. Because of this angle of travel and the low center of gravity a rotational force acts upon the disc encouraging cocking (i.e., the CG's vertical component always leads the lower guide and disc seat during closing of the disc).

Lengthening the disc guide height and increasing the upper skirt mass will cause the center of gravity to move further up the disc assembly as !

compared to the as found disc. This will lessen the rotational force that encourages disc cocking.

5) Excessive soft seat projection was determined to be a contributing factor. F&MR 91-198 was written 05/31/91 to document that subsequent to t machining the disc hard seat the soft seat projection exceeded the value !

specified by the vendor and contained in PNPS drawing M132C-4. The root cause analysis completed for this problem concluded, based on the vendor's (Anchor / Darling) input, that the soft seat projection was adequate for one cycle. Soft seat projection should be decreased. !

6) Securing steam to the HPCI turbine results in cycling of the 2301-45 and 2301-74 valves as exhaust steam pressure reduces to torus pressure. !

Review of EPIC traces of turbine exhaust pressure and interviews with i the System Engineer have indicated such. Therefore, the last stroke that the 2301-74 experiences is most likely the result of relieving

trapped pressure between the 45 and 74 valves and is more of a ' burp' than a full stroke. This results in a low disc closing force. The valve manufacturer has indicated that the valve as designed would be i expected to close properly if closed from a fully open position which results in a larger closing force. Combining all of the other disc factors with this low closing force allowed the disc to cock and prevented the disc from finding the body seat properly.

i The ' burping' of the 2301-74 valve is considered normal system '

O interaction arrd no actions are recommended to modify system operations.

Implementation of the above disc modifications will provide adequate compensatien for this mode of valve operation.

The 2301-74 valve was built for this special application. The design issues are unique to this system and application and therefore no other corrective actions are planned.

Anchor / Darling analysis of the condition can be found in Attachment 4A thru l 4E. ,

Actions Necessary to Prevent Recurrence:

1) Provide a new disc subassembly that has the following design characteristics:

(Action - D. Heard)

A) Maximize the disc subassembly guide length within the constraints of the existing valve body and bonnet.

B) As built guide diameter to results and .026 .035 in. diametral clearance between existing valve body guides and disc guides.

C) Increased disc guide edge radius to 1/4R (reduce chance of edge catching.

D) Increase disc stem hole diameter.

Decreased resilient seat projection.

O E)

F) Increased resistance to disc distortion for the area of the disc upper guide skirt.

2) Develop PDC to install the new disc.

(Action - J. Gerety)

Contingencies:

i l 1) Save old disc subassembly (Action - D. Heard) H Pursue use-as-is justification. (Action - NED) .

2) Develop FRN to modify old disc subassembly (Action - G. Choquette)

A) Raise the disc skirt on the center pipe so that the inside of the skirt is flush with the top of the pipe. ,

B) Reduce '.he clearance between the disc guide and body bore by ;

applying additional hardfacing to the disc OD and remachine. The as found diametral clearance will be decreased from .049 .057 to ,

.026 - 0.35 (new design).

C) Increase the radius on the guide edges from 1/8R to 1/4R. (This f O will reduce the chance of edge " catching".)

I 1

D) Decrease the resilient seat (soft seat) pro.iection to .020 - 0.25.

O (This will improve the seal life and provide continuous seal contact at initial closure.)

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1. 10 CFR 50.73 Evaluation recuired? '/Yes No.

A. If Yes, is 10 CFR 50.73 reporting applicable? Yes

/ No N/A S. If I.A is Yes, identify the applicable 10 CFR 50.73 subpart(s): LIIfT C. If I.A is yes, identify the applicable LER number: Idlk D.

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Compliance,:Di(Asion Engineer /Date l

1. Reviewed By:

Comp (1ance Division R

[h/ 26ff]

ewer /Dats i 3.05-01 Rev. 3 l

i l

l l

NP2110MX MAINTENANCE REQUEST FILE (1 OF 5 ) 05/06/93

+ NP2100DG NEXT PAGE 1 15:20:51

ORIGINATING SECTION ----------------- -----------

v # 19103911 00 TYPE UNIT 1 DATE 8/20/91 NUC CLASS (S/N) S PRI 3 ESR/4 TAG LOC STATUS A2 INITIALS GB RE!MRKS ACTIVE WORK TYPE P SUB TYPE TP IN

, SYSTEM LOADED DATE 8/20/91 TIME 20:41:12 LEAD MR # SUPPORT N EQUIPMENT INFORMATION -----------------------

EQUIPMENT ID 23-CK-2301-74 DESC HPCI TORUS DISCHG VLV SYS 23 TRAIN Q/NON-Q Q LOCATION -4' PWT / OPS N TRENDING N l

- SYSTEM RSP ENGINEER ,

PROBLEM / WORK REQUESTED ----------------------

REPLACE SOFT SEAT ON HPCI TURB EXHAUST STOP CHECK VALVE CK-2 '

301-74 WIT H NEW SMALLER DIAMETER SOFT SEAT TO PREVENT PINCH ING OF THE SEAT. REMOVED FROM MCO 9 AND ADDED TO RFO 9 PER T CONT Y INITIATOR D. FERRARO DATE OPS RV NWE DATE 8/20/91 WPT RECEIVED DATE 8/20/91 DATE WORK REQD

CROSS REFERENCES --------------------------

CONTROL # WRT # REFERENCE DOC # PR91.0198.01 SEC CONT IND SFTY PHONE PDC /FRN#

REJECT CODE RESP PERSON DATE {

ENTER DATA OR. COMPLETE TRANSACTION PF: 11-TEXT 13-HELP 14-ALIAS 15-EXIT 16-COMMIT 17-DTL 18-QUIT 20-LIST r

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