ML20137F793

Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Tests for May 1983 - May 1985, Ja Fitzpatrick Nuclear Power Plant

ML20137F793
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Site:	FitzPatrick
Issue date:	05/31/1985
From:	STONE & WEBSTER ENGINEERING CORP.
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O REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST TYPES A, B, AND C PERIODIC TESTS FOR MAY 1983 TO MAY 1985 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 O

4 Prepared by Stone & Webster Engineering Corporation Boston, Massachusetts O

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- TABLE OF CONTENTS Section Title Page LIST OF ATTACHMENTS iii REFERENCES v 1 PURPOSE 1-1 2

SUMMARY

2-1 2.1 TYPE A TEST 2-1 2.1.1 Test Summary 2-1 2.1.2 Conclusion 2-2 2.2 LOCAL LEAKAGE RATE TESTS (TYPES B AND C) 2-3 3 TYPE A TEST 3.1-1 3.1 EDITED LOG OF EVENTS 3.1-1 3.2 GENERAL TEST DESCRIPTION 3.2-1 3.2.1 Prerequisites 3.2-1

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( 3.2.2 3.2.3 Equipment and Instrumentation Data Acquisition System 3.2-1 3.2-2 3.2.4 Data Resolution System 3.2-2 3.3 TEST RESULTS 3.3-1 3.3.1 Presentation of Test Results 3.3-1 3.3.2 60 psia PCILRT Results 3.3-2 3.3.3 Supplemental Test Results 3.3-2 4 LOCAL LEAKAGE RATE TESTS (TYPES B AND C) 4-1

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j LIST OF ATTACHMENTS O Title Attachment r

2.1A Graph 1 - Total Mass vs. Time i

3.2A Site Meteorology 3.2B Temporary Piping Leakage Rate Analyzer (LRA) System No. 16-1 3.2C Permanent Piping Leakage Rate Analyzer (LRA) System No. 16-1 3.2D Instrumentation 3.2E LRA System No. 16-1, PCILRT Temperature Detector Locations 3.2F LRA System No. 16-1, PCILRT Moisture Detector Locations 3.2G Temporary Piping Superimposed Leakage Verification Test (CAD)

System No. 27 3.3A Primary Containment Integrated Leakage Rate Test (PCILRT) -

Input Variables, from 1630 on 5-13-85 to 1630 on 5-14-85.

3.3B Primary Containment Integrated Leakage Rate Test (PCILRT) -

Absolute Test Method, Mass Point Analysis Test Results, s

from 1630 on 5-13-85 to 1630 on 5-14-85.

3.3C Primary Containment Integrated Leakage Rate Test (PCILRT) -

Initialization and Control Variables, from 1630 on 5-13-85 to 1630 on 5-14-85.

3.3D Type C Penetration Leakage to be Added to Cal'culated PCILRT Leakage P..te 3.3E Graph 2 - Primary Containment Leakage Rate and UCL vs. Time 3.3F Graph 3 - Primary Containment Air Mass vs. Time 3.3G Superimposed Leakage Verification Test - Input Variables, from 1730 on 5-14-85 to 2130 on 5-14-85.

3.3H Superimposed Leakage Verification Test - Absolute Test Method, Mass Point Analysis Test Results, from 1730 on 5-14-85 to 2130 on 5-14-85.

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LIST OF ATTACHMENTS (Cont.)

Attachment Title 4A 1985 Types B and C Data Summary 4B 1983 Types B and C Data Summary 4C 1983/1985 Primary Containment Boundary Modifications O

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^ l REFERENCES l

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1. 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing For  !

Water-Cooled Power Reactors, October 22, 1980. '

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2. F-ST-39F, Type "A" Test (60 PSIA) Primary Containment Integrated Leak l Rate Test.

3. ANSI N45.4, American National Standard Leakage - Rate Testing of Containment Structures For Nuclear Reactors, March 16, 1972.

4. ANSI /ANS-56.8, Containment System Leakage Testing Requirements, February 19, 19811 I

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This document used only as a guideline and any reference to said document in (n) w/

no way implies compliance,

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( SECTION 1 kJ PURPOSE The purpose of this report is to present a description and analysis of the May 1985 Periodic Type A Primary Containment Integrated Leakage Rate Test (PCILRT) and a summary of the last two periodic Type B and C tests conducted since May 1983 at the James A. FitzPatrick Nuclear Power Plant (JAFNPP).

JAFNPP is owned and operated by the New York Power Authority (NYPA).

Stone & Webster Engineering Corporation (SWEC) provided engineering consul-ta!; ion services to NYPA during the performance of this test.

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

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SECTION 2 G

SUMMARY

2.1 Type A Test 2.1.1 Test Summary On May 13, 1985, pressurization was started at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />. A fairly constant rate of 6.8 psig per hour was established. Equipment problems with 16-FCV-101 (see Attachment 3.2C) interrupted primary containment pressurization at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />. Flow was reestablished through bypass valve LRA-3 at 0620 hocr- with a fairly constant rate of 7.0 psig per hour. At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, 16-FCV-101 was placed back in service with a fairly constant pressurization rate of 4.2 psig per hour being maintained throughout the remainder of the pressurization period.

Primary containment pressurization was secured at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on May 13, 1985, with a peak instantaneous pressure of 60.33 psia. During the pressurization period both drywell vent fans (68-FN-4D and 68-FN-2D) tripped on high current overload. At approximately 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, the average hourly drywell and torus temperature satisfied the procedural thermal stabilization criterion.

An extensive investigation of all penetration areas was conducted. This search revealed minor packing leaks on several valves, the most significant

[,) on 27-A0V-101B.

A./

During the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test period from 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 13, 1985 to 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 14, 1985, a steady mass increase of about 7.2 lba per hour was observed (Attachment 2.1A) . This mass increase was initially attributed to the difference in torus water and air temperatures, but was later attributed to an increasing torus water level of approximately 5 gpm and an increasing drywell equipment sump water level of approximately 0.5 gpm.

With the calculated mass adjusted for the torus water inleakage, a stable mass loss of about 7.1 lbm per hour was observed. This rate was below the procedural acceptance criteria rate of 0.375%/ day (13 lba per hour).

The Type A PCILRT was successfully completed at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 14, 1985 with a total Type A leakage of 0.281214%/ day. A superimposed leakage verification test was successfully completed from 1730 to 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on May 14, 1985.

In accordance with the U S. Nuclear Regul.atory Commission's (USNRC) request, an investigation of certain pathways was conducted in order to identify the {

source of torus water inleakages For exuple the condensate transfer supply

(" Keep Full") to the Residual Heat Removal (RHR) System was isolated. Also, 10-RV-41B was gagged since it was suspected to be leaking (warm tail pipe) (

back to the torus. The containment mam and the torus water level rate of change were monitored dcing this invest gation. No significant change in the torus water level ideakage rate was detected during the inve s tiga tiott.

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Drywell equipment sump cooling water was also isolated prior to the test y/ since it was suspected that it had been leaking into the Drywell Equipment Sump. This also did not prove to be a water inleakage source, as the level still increased during the Type A test (see Section 3.3.2.d for the correction).

Depressurization of the primary containment began at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on May 15, 1985 with a drywell pressure of about 60.2 psia and was completed at 0845 ,

hours. I 2.1.2 Conclusion

a. The calculated air mass, when adjusted for the torus water inleakage, results in a leakage rate well within the procedural acceptance criteria. Although the source of the torus water inleakage could not be identified, it was the cause of the increasing air mass. As shown in Attachment 2.1A, the water level rate of increase was uniform throughout the Type A test period.

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2096-1515400-B2 2-2 M A.

i 2.2 LOCAL LEAKAGE RATE TESTS (Types B and C)

The Local Leakage Rate Tests (LLRTs) of containment isolation valves and other primary containment penetrations were performed by the methods de-scribed in the plant surveillance procedure No. F-ST-39B, " Type 'B' and 'C' LLRT of Containment Penetrations."

Data for the two surveillance periods (1983 and 1985) of LLRTs performed since the last Type A Test in accordance with Appendix J, 10CFR50, Para-graph V.B., is summarized in Section 4 of this report.

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SECTION 3 TYPE A TEST 3.1 EDITED LOG OF EVENTS This log was edited from the Official PCILRT Log of Events, Shift Supervisor's Log, Nuclear Control Room Operator's Log, and Auxiliary Operator C's Log.

May 10, 1985 At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, the valve lineups were started for the PCILRT.

May-11, 1985 At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, used 06-LI-94C instead of 06-LI-94B as control room reat'or vessel level indicator backup.

May 12, 1985 At 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, commenced processing torus water in order to meet 0.0 to -1.5 in.

At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, successfully completed the local leakage rate test on the drywell head.

At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, the primary containment inspection was completed.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, observed a drywell equipment sump inleakage of approximately 0.5 gpm. Isolated drywell sump cooler and drywell cooler "A" to determine if the drywell sump cooler was the source of leakage.

l At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />, successfully completed the local leakage rate test on the l~ personnel hatch.

May 13, 1985 At 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, completed all PCILRT prerequisites.

3 At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, commenced primary containment pressurization in accordance i with surveillance procedure No. F-ST-39F entitled " Type A Test (60 psia)

Primary Containment Integrated Leak Rate Test."

At 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />, 16-FCV-101 closed.

.At 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />, opened bypass valve LRA-3.

At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, 16-FCV-101 placed back in service.

At 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, drywell vent fan 68-FN-4D tripped on high current overload.

At 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />, drywell vent fan 68-FN-2D tripped on high current overload.

s 2096-1515400-B2 3.1-1

At 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, isolated " Keep Full" to standby loop of RHR (A side). Torus b

O water level pumped down from -0.72 to -1.03.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />, with the drywell pressure at 60.3 psia (instantaueous computer reading), the pressurization equipment was isolated and secured.

The minimum 4-hour stabilization period began.

At 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, extensive search for leakage paths completed. This search revealed minor packing leaks on several valves, the most significant on 27-A0V-101B.

At 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />, pumped down drywell equipment sump.

At 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, the temperature stabilization criterion was satisfied and the PCILRT was started.

6 May 14, 1985 At 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, investigated all possible sources of inleakage to the drywell. None were found.

At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, torus water level increased 0.90 in. in 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.

At 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, the PCILRT test period was completed, and preparation for the superimposed leakage verification test began.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the superimposed leakage verification test stabilization

~5 period was initiated with an imposed leakage of approximately 5375 SCFD.

At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, began the superimposed leakage verification test period.

At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, the superimposed leakage verification test was completed.

At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, gagged 10-RV-41B to determine if this was the source of torus water inleakage.

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May 15, 1985 At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the packing on 27-A0V-101B was adjusted. The PCILRT, the l verification test, and the torus water inleakage investigation were

-documented as complete. The depressurization of the primary containment was started. I l At 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, depressurization of the primary containment was completed. i I

2096-1515400-B2 3.1-2 m

p 3.2 GENERAL TEST DESCRIPTION 3.2.1 Prerequisites In accordance with the James A. FitzPatrick PCILRT Procedure F-ST-39F (Reference 2), the following is a listing of the pertinent prerequisites completed and documented prior to primary containment pressurization:

a. Site meteorological data recorded at least three days prior to and during the performance of the PCILRT (Attachment 3.2A).

b. All required test instrumentation cleaned, calibrated within 6 months of the test, and placed in service.

e. All required Types B and C leakage rate testing completed.

d. Satis factory inspection of accessible interior and exterior surfaces of the primary containment structures and components completed.

e. Temporary air compressors and test skid ready for use as the pressurization source.

f. Two drywell ventilation fans adjusted for continuous operation at test pressure (45 psig), and their associated dampers blocked in the open position.

g. All computer software used for test calculations tested and operational.

h. Valves lined up and tagged in accordance with the Valve Line-Up List,

i. Water levels recorded for the suppression pool, reactor vessel, drywell equipment sump, and drywell floor drain sump.

J. Controlled Work Area Plan in effect.

k. An Official Log of Events located in the Control Room and main-tained by the Test Director.

3.2.2 Equipment and Instrumentation Pressurization of the primary containment was achieved by the utilization of a temporary system consisting of two parallel compressor trains. Each train consisted of two air compressors which were manifolded through an in-line water cooled heat exchanger and refrigerant air dryer (Attachment 3.2B).

The discharge of the temporary system was routed to the primary containment via the drywell spray portion of the RHR System (Attachment 3.2C). The

-system included adequate instrumentation and valving to maintain proper monitoring and control of the compressed air quality throughout the pressurization sequence. The total capacity of the pressurization system

, was 3,600 cubic feet per minute.

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2096-1515400-B2 3.2-1

The various containment parameters required to calculate containment leakage

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during the test were monitored by the leakage monitoring system instrumenta-tion. The instrumentation consisted of multiple resistance temperature detectors (RTDs), moisture detectors (dewcells), and absolute pressure quartz manometers for both the drywell and torus. Pertinent data for the test instrumentation is listed in Attachment 3.2D. The general locations of the temperature and moisture sensors, including applicable test zones, are shown in Attachments 3.2E and 3.2F.

A mass flow meter was used to perform the superimposed leakage verification test (Attachment 3.2G). All test instrumentation with the exception of that used for the superimposed leakage verification test was monitored by the plant process computer for data acquisition.

3.2.3 Data Acquisition System The James A. FitzPatrick plant process computer system (PPCS) performs reactor core calculations and provides the plant operator with current core operating data. The PPCS also scans, calculates, stores, logs, and alarms information which has been collected for the plant operation.

The PPCS analog scan package reads all the analog inputs in a pre-estab-lished manner, converts these readings into engineering units, and then stores these values into predefined locations for use by the plant operators and by the ' plant application programs.

For the PCILRT, the function of the PPCS is to provide and transmit at five

( minute intervals sufficient sensor and zone pair information for input to a remote AT&T 3B2/300 computer (PCILRT computer) PCILRT calculation program.

The PPCS PCILRT sensor program converts binary-coded decimal digital in-formation from each manometer to an analog value.

For the PCILRT, the plant computer monitored the following instrumentation:

Type Scan Rate (sec) 18 RTDs 60 6 Dewcells 60 4 Absolute Manometers 60 3.2.4 Data Resolution System Periodically, during the PCILRT test period, leakage rate trends were moni-tored from data obtained from the plant process computer. The PCILRT l

computer program converts the dewcell equilibrium temperature to dewpoint temperature, and calculates a zone pair average (see Attachment 3.2E and i 3.2F). This data along with the instantaneous sensor values and the difference between the two averaged sensor values for each zone are logged on the utility typer every 10 minutes.

l After the appropriate data had been acquired and averaged utilizing the PCILRT computer system, the results were inputted for leakage rate calcula-tions, utilizing the Absolute Method of Mass Point Anal'1 sis.

2096-1515400-B2 3.2-2

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

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.m Absolute Method of Mass Point Analysis N -

The Absolute Method of Mass Point Analysis consists of calculating air masses within the containment structure over the test period from pressure, temperature, and dewpoint observations made during the PCILRT. The air masses are computed using the ideal gas law as follows:

Mass = l'44V(P-Pv) ( 9' RT where:

M = air mass, lbm P = total pressure, psia Pv = average vapor pressure, psia R '= 53.35 ft-lbf/lba R (for air)

T = average containment temperature, R V = containment free volume, ft3 There are two containments: torus (suppression chamber) and drywell. The masses for each containment are computed separately and added together.

The leakage rate is then determined by plotting the total air mass as a function of time, using a least-squares fit to determine the slope, A = dM/

dT. The leakage rate is expressed as a percentage of the air mass lost in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or symbolically:

Leakage Rate = A/B(-2400) (Eq.2) where A is the slope of the least-squares curve and B is the y-intercept.

The sign convention is such that the leakage out. of containment is positive and the units are in percent / day.

A 95 percent confidence interval is calculated using a Students T distribu-tion. The sum of the leakage rate and the 95 percent confidence interval is the upper confidence limit (UCL). The measured leakage rate may be de-scribed as 95 percent accurate to within the value of the UCL.

2096-1515400-B2 3.2-3

O O O ATTACHMENT 3.2A SITE METE 0E0 LOGY Temperature Barometric Wind Dew Point Reactor Bldg.

Ambient, Pressure, Velocity, Wind Temperature Temperature Date Time *F in. Hg sph Direction *F *F 5/9/85 1500 64.3 29.87 7.0 232.9* (SW) 21.2 68 2300 65.3 29.79 8.1 183.3 35.0 75 5/10/85 0700 65.2 29.75 11.2 197.6 38.6 73 1500 62.8 29.71 12.4 244.8 21.4 69 2300 71.0 29.72 10.3 224.9 19.4 78 5/11/85 0700 65.0 29.77 6.1 206.8 23.7 70 1500 69.7 29.78 3.4 34.2 21.4 72 2300 68.5 29.73 4.1 95.7 15.4 74 5/12/85 0700 66.8 29.71 7.9 134.5 16.6 71 1500 65.4 29.66 3.4 285.4 57.7 72 2300 N/A N/A N/A N/A N/A 72 5/13/85 0330 - Start Pressurization 0400 N/A N/A N/A N/A N/A N/A 0500 N/A N/A N/A N/A N/A N/A 0600 N/A N/A N/A N/A N/A N/A 0700 N/A N/A N/A N/A N/A 70 0800 70.5 29.64 9.3 228.4 22.6 N/A 0900 69.2 29.65 12.8 240.0 15.3 N/A 1000 62.7 29.66 14.0 247.1 14.5 N/A i 1100 54.6 29.67 12.1 251.7 22.0 N/A 1200 53.0 29.66 13.2 247.8 26.1 N/A 2096-1515400-B2 Page 1 of 2

O O O; ATTACHMENT 3.2A (Cont)

Temperature _ Barometric Wind Dew Point Reactor Bldg.

Ambient,. Pressure, Velocity, Wind Temperature Temperature Date Time *F in. Ha sph Direction 'F *F 5/13/85 1300 52.2 29.67 12.6 '250.4 24.0 N/A 1400 56.0 29.67 13.6 257.9 22.0 N/A 1500 56.9 29.67 12.3 247.2 27.5 69 1600 57.9 29.67 13.3 247.7 25.1 68 1630 - Start PCILRT 1700 56.0- 29.66 12.6 249.4 22.0 70 1800 54.5 29.67 12.4 249.7 18.8 69 1900 53.6 29.67 13.1 248.3 17.1 70 2000 52.6 29.68 12.6 247.5 16.0 70 2100 52.1 29.70 12.9 247.5 16.7 70 2200. 51.3 29.70 11.2 260,1 21.4 70 2300 52.7 29.71 10.2 241.7 26.9 70 2400 52.1 .29.73 12.0 242.5 22.8 70 5/14/85 0100 50.5 29.75 11.2 242.8 21.1 70 0200 48.7 29.75 10.0 252.6 19.5 70 0300 49.7 29.75 6.8 239.2 18.1 70 0400 50.4 29.74 5.3 228.5 16.3 69 0500 49.9 29.76 7.5 238.3 16.3 69 0600 48.6 29.77 9.0 241.9 16.2 69 0700 48.8 29.80 9.0 243.2 15.2 69 0800 49.0 29.82 11.0 246.0 13.3 69 0900 47.7 29.83 10.8 288.5 13.1 69 1000 47.5 29.85 9.9 333.5 N/A 70 1100 46.8 29.86 9.9 348.5 N/A 70 1200 47.1 29.87 5.2 357.1 N/A 69 1300 N/A N/A N/A N/A N/A 69 1400 N/A N/A N/A N/A N/A 69 1500 52.6 29.89 5.0 303.3 45.5 69 1600 53.7 29.89 5.4 6.4 45.6 69 1630 - Complete PCILRT NOTE: '

N/A - Site Meteorology Data Computer Inoperable.  ;

2096-1515400-B2 Page 2 of 2

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( PT T 105 RTD 702 l16 i f Y

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" 18 RHR-52A RHR-528 10 MOV 10 MOV SIA 31 8 10 MOV RHR 5)A 268 IOMOV .

26A X39A X398 RHR-RHR-748 A 7488

~

49A g NOTE:

ALL MANUAL VALVES ARE PREFIXED WITH LRA, WHICH IS LEAK RATE ATTACHMENT 3.2C ANALYZER SYSTEM NQ 16-1, EXCEPT PERMANENT PIPING LEAK RATE i AS NOTED.

ANALYZER l LRA SYSTEM NO.16-1 l 1

J.A.FITZPATRICK NUCLEAR POWER PLANT DATE: MAY 13,1985 TO MAY 14,1985

1 ATTACHMENT 3.2D

~k INSTRUMENTATION Weight Computer Instrument Factor Point Range Zone Accuracy A. Temperature 16-1-RTD-101 0.056755 M103 0*-300*F 0 11.0 F 16-1-RTD-120 0.056755 M116 0*-300*F 0 1.0*F 16-1-RTD-102 0.082510 M084 0*-300*F 1 11.0 F 16-1-RTD-119 0.082510 M115 0 -300*F 1 11.0 F 16-1-RTD-103 0.178020 M085 0*-300*F 2 1.0 F 16-1-RTD-104 0.178020 M086 0*-300*F 2 il.0*F 16-1-RTD-105 0.065685 M087 0*-300*F 3 1.0*F 16-1-RTD-106 0.065685 M088 0*-300*F 3 1.0*F 16-1-RTD-107 0.023505 M089 0*-300*F 4 11.0 F 16-1-RTD-108 0.023505 M090 0 -300*F 4 11.0*F 16-1-RTD-109 0.026685 M091 0*-300*F 5 il.0*F 16-1-RTD-117 0.026685 M113 0 -300*F 5 1.0*F 16-1-RTD-110 0.035765 M092 0*-300*F 6 il.0*F 16-1-RTD-111 0.035765 M093 0*-300 F 6 il.0*F 16-1-RTD-112 0.031075 M094 0*-300*F 1.0*F

(

\

16-1-RTD-118 16-1-RTD-113 0.031075 0.500000 M114 M095 0*-300*F 0*-300*F 7

8 7

11.0*F il.0*F 1-RTD-114 0.500000 M102 0*-300*F 8 1.0*F B. Pressure 16-1-PIT-101 0.50 M096 0-100 psia Drywell i0.02%

16-1-PIT-102 0.50 M097 0-100 psia Drywell- i0.02%

16-1-PIT-103 0.50 M098 0-100 psia Torus 10.02%

16-1-PIT-104 0.50 M099 0-100 psia Torus 10.02%

C. Dewpoint 16-1-DC-Al 0.50 7062 38.5*-118.5*F A 11*-2*F 16-1-DC-A2 0.50 T063 38.5 -118.5 F A 11*-2*F 16-1-DC-B1 0.50 T064 38.5*-118.5*F B 11*-2*F 16-1-DC-B2 0.50 T065 38.5*-118.5*F B 11*-2*F 16-1-DC-C1 0.50 T066 38.5*-118.5 F C 11*-2*F 16-1-DC-C2 0.50 T067 38.5*-118.5*F C 1*-2*F D. Superimposed Leakage Verification Test Flow Instrument Mass Flow Meter N/A N/A 0-150 SLPM N/A 12% F.S.

O 2096-1515400-B2 Page 1 of 1

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RTO 100 __ , > \ 200' RTD 117 u 109 l

RTD 180' W$ O'RTD 107 < 108 N 10 ' RTD l > \

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70* RTD EA ll EAVil 120 AREAll RTD 160*/ -

125' RTD RTD 160 103 l14 O UE 101 EL 264' V

1. 'ARE RTDISO AREA D

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AREA Vill RTD 210' 67' RTD EA Vill 11 2 118 30S' RTD 113 NOTE RTD ELEVATIONS AND AZIMUTH POSITIONS ARE APPROXIMATE l

ATTACHMENT 3.2E PCILRT TEMPERATURE DETECTOR I LOCATIONS LRA SYSTEM NO.16-1 J. A. FITZPATRICK NUCLEAR POWER PLANT l

l O DATE: MAY 13,1985 TO MAY I4,1985

270*

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, , NOTE MOISTURE DETECTOR ELEVATIONS AND AZIMUTH POSITIONS ARE APPROXIM ATE. ,

ATTACHMENT 3.2F t PCILRT MOISTURE DETECTOR j LOCATIONS i

LR A SYSTEM NO.16-1 .

• i

. J. A. FITZPATRICK NUCLE.AR POWER PLANT DATE: MAY 13,1985 TO MAY 14,1985 ,

l

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o 27SOV CAD-206 HW 2 TO 27HAZ- 102A I^

$"MO$"EE CAD-718 CAD-r1 TO Ha -0aA z TEMPORARY CONNECTION i r TEST SKID CH)4-AIR DRYERS W

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MOISTURE II i=

KURZ INDICATOR MASS FLOW METER ,

(TY PICAL) l l

l

, ATTACHMENT 3.2G TEMPORARY PIPING SUPERIMPOSED l LEAKAGE VERIFICATION TEST I CAD SYSTEM NO. 27 l J.A.FITZPATRICK NUCLE AR POWER PLANT l DATE: P \Y 13,1985 TO MAY 14,1985 l

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

3.3 TEST RESULTS O['N 3.3.1 Presentation of Test Results The test data for the period of 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 13, 1985 through 1630 on May 14, 1985 were analyzed for the final test results using NYPA's AT&T 3B2/300 PCILRT computer program. The reduced input data and test results obtained by the PCILRT computer program are contained in Attachments 3.3A through 3.3C. Primary containment air mass was adjusted for the continuous torus water inleakage.

Two representative graphs (Attachments 3.3E and 3.3F) are provided showing the following quantities vs time:

1. Primary Containment Leakage Rate and UCL

2. Primary Containment Air Mass The Absolute Test Method - Mass Point Analysis calculated test results are well below the procedural acceptance criteria of 0.375 percent / day. These test results include corrections for water levels and Type C leakage penalties (Section 3.3.2).

The Type A test instrumentation was verified during the supplemental test which used the superimposed leakage verification test method. The calculated test results using the PCILRT computer program were acceptable, .

as shown in Section 3.3.3. The reduced input data and test results obtained

by the PCILRT computer program are contained in Attachments 3.3G and 3.3H.

O 2096-1515400-B2 3.3-1

/~'} 3.3.2 60-psia PCILRT Results v

The 60-psia PCILRT was conducted in accordance with Section VII.3 of surveillance ~ procedure No. F-ST-39F. The results for the PCILRT is shown below.

a .- Lam, leakage rate calculated (percent / day) 0.203447

b. 95 percent confidence level (percent / day) 0.007808

c. UCL, leakage rate with 95 percent confidence level (percent / day) 0.211255

d. Corrections due to water level (percent / day)

Torus (adjusted) 0.000000 Reactor Vessel 0.000692 Drywell Equipment Sump 0.027695 Drywell Floor Sump 0.00000 Total 0.028387

e. Correction for Type C leakage (percent / day)

(See Attachment 3.3D) 0.041572 Total reported Type A leakage rate (percent / day) n N/

f.

1. Results were within the acceptable limits of 0.75 La or 0.375 percent / day.

0.281214 3.3.3 Supplemental Test Results The Supplemental Verification Test was performed using the Superimposed Leakage Verification Test Method in accordance with Section VII.4 of sur-veillance procedure No. F-ST-39F. The results for the superimposed leakage verification test is shown below.

a. Average Flow

i. Average flow in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> = 223.9583 scfh l ao r Lo = 0.489579%/ day

b. Composite Leakage, Lc

- 1. Le = 0.761626%/ day

c. Leakage rate from 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> PCILRT, Lam i

i. Lam = 0.203447%/ day o

i 2096-1515400-B2 3.3-2

l l

d. Lam + Lo - 0.25 La < Le $ Lam + Lo + 0.25 La

i. 0.203447 + 0.489579 - 0.125 = 0.568026 ii. 0.203447 + 0.489579 + 0.125 = 0.818026 0.568026 5 0.761626 5 0.818026 The composite leakage rate is within the limits for the period of 1730 to 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on May.14, 1985.

10 4

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.Y ATTACHMENT 3.3A PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST 4

NYPA JAMES A. FITZPATRICK NUCLEAR POWER PLANT FROM 1630 ON MAY 13, 1985 TO 1630 ON May 14, 1985 INPUT VARIABLES Drywell Torus Time Temp Abs Press Dew Pt Vap Press Temp Abs Press Dew Pt Vap Press Hr Degr Psia Degr Psia Degr Psia Degr Psia 1630 89.274 60.146 75.575 0.438 75.133 60.244 73.424 0.408 1730 89.342 60.142 76.005 0.444 74.790 60.241 73.234 0.405 1830 89.353 60.136 76.316 0.449 74.653 60.235 72.995 0.402 1930 89.398 60.136 76.699 0.455 74.516 60.235 72.804 0.399 2030 89.482 60.136 76.913 0.458 74.242 60.235 72.613 0.397 2130 89.572 60.138 77.201 0.462 74.104 60.238 72.470 0.395 2230 89.556 60,142 77.439 0.466 73.966 60.241 72.326 0.393 2330 89.593 60.144 77.655 0.469 73.966 60.244 72.231 0.391 0030 89.595 60,147 77.822 0.472 73.830 60.245 72.183 0.391 0130 89.619 60.150 77.966 0.474 73.762 60.249 72.040 0.389 0230 89.621 60.155 78.037 0.475 73.693 60.255 71.992 0.388 0330 89.623 60.158 78.110 0.476 73.624 60.258 71.896 0.387 0430 89.626 60.161 78.109 0.476 73.555 60.261 71.896 0.387 0530 89.666 60.168 78.205 0.478 73.555 60.268 71.849 0.386 0630 89.674 60.165 78.133 0.477 73.418 60.267 71.801 0.386 0730 89.655 60.175 78.229 0.478 73.350 60.275 71.801 0.386 0830 89.662 60.183 78.229 0.478 73.350 60.283 71.706 0.385 0930 89.682 60.186 78.181 0.477 73.418 60.286 71.753 0.385 1030 89.654 60.186 78.229 0.478 73.418 60.286 71.706 0.385 1130 89.663 60.200 78.253 0.479 73.418 60.300 71.658 0.384 1230 89.672 60.199 78.205 0.478 73.282 60.299 71.658 0.384 1330 89.612 60.201 78.277 0.479 73.282 60.301 71.658 0.384 1430 89.589 60.204 78.253 0.479 73.350 60.305 71.706 0.385 1530 89.592 60.207 78.229 0.478 73.350 60.308 71.610 0.383 1630 89.586 60.215 78.277 0.479 73.282 60.315 71.658 0.384 2096-1515400-B2 Page 1 of 2

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

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ATTACHMENT 3.3A (Cont) '[

t

' 4 Initialization Drywell - Torus .

Abs Press' 60.146 60.244 Vap Press 0.438 0.408-Temp 89.274 75.133

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2096-1515400-B2 Page 2 of 2 9

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l fm ATTACHMENT 3.3B PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST NYPA JAMES A. FITZPATRICK NUCLEAR POWER PLANT FROM 1630 ON MAY 13, 1985 TO 1630 ON MAY 14, 1985 ABSOLUTE TEST METHOD, MASS POINT ANALYSIS TEST RESULTS (Adjusted)

Time Air Mass Air Mass Leakage Rate 95 Pct Conf Hrs Pounds Pounds Pet / Day Pct / Day UCL 0.000 80322.69 80322.69 0.000000 0.000000 0.000000 1.000 80331.16 80316.88 0.000000 0.000000 0.000000 2.000 80329.91 80301.35 .318808 .717293 1.036101 3.000 80332.36 80289.52 .343724 .118156 .461880 4.000 80342.45 80285.33 .305006 .075838 .380844 5.000 80345.13 80273.73 .299885 .045391 .345276 6.000 80358.22 80272.54 .269740 .046376 .316116 7.000 80356.73 80256.77 .273965 .033670 .307635 8.000 80367.02 80252.78 .265623 .027017 .292641 9.000 80374.05 80245.53 .258705 .022421 .281126 10.000 80384,84 80242.04 .247914 .021359 .269273 11.000 80392.48 80235.40 .239785 .019523 .259309 12.000 80401.03 80229.67 .232613 .017963 .250575 13.000 80406.44 80220.80 .229031 .015705 .244735

% 14.000 80413.25 80213.33 .226557 .013749 .240306 x 15.000 80430.96 80216.76 .217646 .015006 .232652 16.000 80441.23 80212.75 .209614 .015481 .225095 17.000 80439.32 80196.56 .208786 .013724 .222510 18.000 80441.17 80184.13 .210759 .012391 .223150 19.000 80460.30 80188.98 .207119 .011696 .218815 20.000 80467.05 80181.45 .204656 .010832 .215489 21.000 80474.53 80174.65 .202790 .009995 .212785 22.000 80476.25 80162.09 .203244 009114 .212358 23.000 80480.70 80152.26 .204498 .008428 .212926 24.000 80495.49 80152.77 .203447 .007808 .211255 l

O 2096-1515400-B2 Page 1 of 1

O O

' ATTACHMENT 3.3C O

PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST NYPA JAMES A. FITZPATRICK NUCLEAR POWER PLANT FROM 1630 ON MAY 13, 1985 TO 1630 ON MAY 14, 1985 -; -

INITIALIZATION AND CONTROL VARIABLES Weighting Factors for Temperature and Dew Point Averaging Zone 0 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Zone 7 Zone 8 Zone A Zone B Zone C 0.11351 0.16502 0.35604 0.13137 0.04701 0.05337 0.07153 0.06215 1.00000 0.50000 0.50000 1.00000 Polynomial Coeffi'cients for Vapor Pressure Conversion

's 0.919818D-14 0.172223D-10 0.105015D-08' O.349876D-06 0.179585D-04 0.112199D-02 0.211397D-01 STUDENT'S T CONSTANTS 1.95996 2.37226 2.82250 2096A-1515400-B2 Page 1 of 1

ATTACHMENT 3.3D TYPE C PENETRATION LEAKAGE TO BE ADDED TO CALCULATED PCILRT LEAKAGE RATE

1. Penetrations to be penalized from initial valve line-up .(see Types B and C data):

Leakage Penetration Description (SCFD)

X-9A "A" Feedwater Line 184.20 X-9B "B" Feedwater Line 221.40 X-14 RWCU Supply 13.54 X-23 Drywell Cooling Equipment 30.44 X-24 Drywell Cooling Equipment 6.71 Total (percent / day) 0.041572

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2096-1515400-B2 Page 1 of I

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a O O O ATTACHMENT 3.3G PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST SUPERIMPOSED LEAKAGE VERIFICATION TEST NYPA JAMES A. FITZPATRICK NUCLEAR POWER PLANT FROM 1730 ON MAY 14, 1985 TO 2130 ON MAY 14, 1985 Input Variables Drywell Torus Time Temp Abs Press Dew Pt Vap Press Temp Abs Press Dew Pt Vap Press Hr Degr Psia Degr Psia y De Psia Degr Psia 1730 89.601 60.191 78.253 0.479 73.282 60.292 71.658 0.384 1750 89.554 60.186 78.276 0.479 73.350 60.286 71.610 0.383 1810 89.582 60.186 78.277 0.479 73.282 60.286 71.610 0.383 1830 89.627 60.182 78.253 0.479 73.213 60.283 71.610 0.383 1850 89.607 60.179 78.301 0.479 73.350 60.281 71.658 0.384 1910 89.592 60.177 78.276 0.479 73.282 60.278 71.610 0.383 1930 89.592 60.174 78.277 0.479 73.350 60.274 71.610 0.383 1950 89.600 60.171 78.325 0.480 73.282 60.272 71.610 0.383 2010 89.570 60.168 78.420 0.481 73.282 60.269 71.610 0.383 2030 89.613 60.165 78.276 0.479 73.213 60.265 71.610 0.383 2050 89.634 60.166 78.253 0.479 73.282 60.268 71.658 0.384

! 2110 39.626 60.163 78.348 0.480 73.350 60.264 71.658 0.384 2130 89.655 60.160 78.325 0.480 73.282 60.260 71.610 0.383 i

Initialization Drywell Torus f

Abs Press 60.191 60.292 Vap Press 0.479 0.384

Temp 89.601 73.282 i

Volume 154476 115800 t

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i 2096-1515400-B2 Page 1 of 1

' ATTACHMENT 3.3H PRIMARY CONTAINMENT INTEGRATED LEAKAGE RATE TEST

'O SUPERIMPOSED LEAKAGE VERIFICATION TEST NYPA JAMES A. FITZPATRICK NUCLEAR POWER PLANT IROM 1730 ON MAY 14,1985 TO 2130 ON May 14,1985 ABSOLUTE TEST METHOD, MASS POINT ANALYSIS TEST RESULTS (Adjusted)

Air Mass Air Mass Leakage Rate 95 Pct Conf Time Pct / Day UCL Pounds Pounds Pct / Day Hrs 0.000000 0.000000 0.000000 0.000 80462.26 80462.26 0.000000 80450.30 0.000000 0.000000 0.333 80455.06 2.540316 80446.68 .6970P4 1.843232 0.667 80456.20 .953763 80438.69 .665140 .288623 1.000 80452.97 1.059477 80422.50 .815458 .244019 1.333 80441.54 .919553 80421.15 .759181 .160372 1.667 80444.95 .915145 80406.46 .798572 .116573 2.000 80435.02 .872098 80401.24 .787368 .084730 2.333 80434.56 .839532 80393.83 .773855 .065677 2.667 80431.91 .807971 80388.46 .750980 .056990 3.000 80431.30 .789847 80378.90 .743252 .046595 3.333 80426.50 .798333 80365.22 .757283 .041050 3.667 80417.58 .796296 80358.16 .761626 .034670 4.000 80415.28 O

O 2096-1515400-B2 Page 1 of 1

SECTION 4

(

N LOCAL LEAKAGE RATE TESTS (TYPES B AND C)

Attachments 4A and 4B, which follow, summarize the LLRT data which has been  !

obtained from periodic testing performed since the February 1982 Type A '

Test. Pre-repaired data is provided for surveillance testing performed in 1985 and 1983. Values listed in both summaries are individual valve measurecents, unless otherwise noted. Each penetration's leakage rate can be obtained form site reference material. These LLRTs were performed using

" volumetric" leakage measuring equipment with a maximum range of 1,018 SCFD.

No attempt to establish the actual leakage rate was made when the calibrated range of the test instrumentation was exceeded.

The acceptance criteria for Types B and C testing are in accordance with 10CFR50, Appendix J. The combined "as-left" leakage rate for all penetrations and valves subject to Types B and C tests shall be less than 0.6 La. The LLRTs performed in 1983 and 1985 were well below the acceptance criteria.

r The data contained in this section are summarized below:

Attachment No. Title 4A 1985 LLRT Data (10-Year Plant Inservice Inspection) 4B 1983 LLRT Data (Refueling Outage) 4C Primary Containment Boundary Modifications 2096B-1515400-82 4-1 I

l O

t O ATTACHMENT 4A l 1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA l

Type Equipment / Valves Pre-Repair Post nepair Penetration Ho. Test Tested Leakage (sef/ day) Leakage (scf/ day) Repair / Notes Drywell Stabilizer 0* (E-90*) B "O" rings 0.188 0.188 45' (2-135*) B "O" rings 0.181 0.181 90* (E-180*) B "O" rings 0.133 0.133 l

135' (E-225*) B "O" rings 0.154 0.154 180* (E-270*) B "O" rings 0.252 0.252 i 225' (E-315*) B "O" rings 0.417 0.417 ,

l 270* (E-0*) B "O" rings 28.0 <0.102 270*

315* (E-45*) B "O" rings 0.155 0.155 Dry Well Head B "O" rings 0.2886 0.2886 X-1A Equipment and Emergency B "O" rings 7.89 7.89 Escape Hatch X-1B Equipment Hatch B "O" rings 0.1404 0.1404 X-2A Personnel Access Hatch B "O" rings 91.387 91.387 X-4 Drywell Head Manhole B "O" rings 0.2886 0.2886 X-6 CRD Removal Hatch B "O" rings <0.102 <0.102 X-7A "A" Main Steam Line C 29-AOV-80A(IPC) 0.298 0.298 29-AOV-86A(OPC) (Combined) (Combined)

X-7B "B" Main Steam Line C 29-AOV-80B(IPC) >1018 16.13 A0V-86B 29-AOV-86B(OPC) (Combined) (Combined)

X-7C "C" Main Steam Line C 29-AOV-80C(IPC) 0.102 0.102 29-AOV-86C(OPC) (Combined) (Combined) 2096C-1515400-B2 Page 1 of 13 i . . -

,s - -l O._ Ou .

ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA ~

Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakate (sef/ day) Leakage (sef/ day) Repair / Notes X-7D "D" Main Steam Line C 29-A0V-80D(IPC) 0.141 0.141 29-A0V-86D(OPC) (Combined) (Combined)

X-8 Condensate Drain C 29-MOV-74(IPC) 826.6 <0.102 MOV-74 ground 29-MOV-77(OPC) 16.69 16.69 bonnet nating surfaces and replaced gasket.

X-9A Feedwater C 34-FWS-28A(IPC) 0.520 (FWS-28A) 0.520 (FWS-28A) 13-MOV-21(OPC) 184.2 (MOV-21) 184.2 (MOV-21) 34-NRV-111A(OPC) (NRV-111A) (NRV-Illa)

RWC-62(OPC) 17.9 (RWC-62) 17.9 (RWC-62)

X-9B Feedwater C 34-FWS-28B(IPC) 0.674 (FW9-28B) 0.674 (FWS-28B) NRV-1118 23-MOV-19(OPC) 343.5 (MOV-19) 221.4 (MOV-19) machined disc 34-NRV-111B(OPC) (NRV-111B) (NRV-111B) and seat.

Replaced internals and adjusted valve.

X-10 Steam to RCIC Turbine C 13-MOV-16(IPC) >0.102 <0.102 MOV-15 lapped 13-MOV-15(OPC) 30.4 4.39 disc and seat and body /

bonnet tightened.

X-11 Steam to HPCI Turbine C 23-MOV-15(IPC) 14.04 14.04 23-MOV-16(OPC) (Combined) (Combined) 23-MOV-60(OPC)

X-12 Shutdown Supply to RHR C 10-MOV-17(IPC) >1018 26.72 MOV-17 lapped 10-MOV-18(OPC) >1018 23.82 disc and seat replaced MOV-18 new installation 2096C-1515400-B2 'Page 2 of 13

O O O ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakane (scf/ day) Repair / Notes X-13A RHR Return C 10-MOV-27A(OPC) >1018 81.74 NOV-27A repacked 10-MOV-25A(OPC) 5.53 40.92 MOV-25A repacked X-13B.RER Return C 10-MOV-27B(OPC) 73.9 73.9 10-MOV-25B(OPC) 119.6 119.6 X-14 RWCU Supply to Recirculation C 12-MOV-15(IPC) 71.26 (NOV-15) 9.75 (MOV-15) MOV-15 machined Pumps 12-MOV-18(OPC) 13.54 (MOV-18) 13.54 (MOV-18) stem and wedge.

12-MOV-80(OPC) (MOV-80) (MOV-80) Lapped wedge and seat. Replaced gasket and packing.

X-16A Core Spray Pump Discharge C 14-MOV-11A(OPC) 0.102 0.102 14-MOV-12A(OPC) 0.231 0.231 X-l'B Core Spray Pump Discharge C 14-MOV-11B(OPC) 0.178 0.178 14-MOV-12B(OPC) 0.102 0.102 X-17 RPV Head Spray C 10-MOV-32(IPC) 0.855 0.855 10-MOV-33(OPC) 15.06 15.06 X-18 Floor Sump Pump Discharge C 20-MOV-82(IPC) 1.74 1.74 20-AOV-83(OPC) 19.95 19.95 X-19 Equipment Sump Pump Discharge C 20-MOV-94(IPC) >1018 18.9 MOV-94 cleaned 20-MOV-95(OPC) 269.0 1.53 se.at and disc.

RDW-98A repacked lapped seat.

X-21 Service Air C 39-SAS-10(IPC)* >1018 15.6 SAS-10 lapped 39-SAS-9(OPC) 4.63 4.63 disc and seat, cleaned, new gasket.

2096C-1515400-B2 Page 3 of 13

O O O ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA 9

• Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (sef/ day) Repair / Notes X-22 Instrument Air C IAS-22(IPC) 0.242 0.242 IAS-21(OPC) 0.102 0.102 IAS-23(OPC) 0.102 0.102 X-23 Cooling Water Supply C 46-ESW-16B(OPC) <0.102 3.48 ESW-16B disas-15-RBC-24A(OPC) <0.102 <0.102 sembled for dry-well cooling'.

15-A0V-130A(OPC) 30.44 30.44 X-24 Cooling Water Supply C 46-ESW-16A(OPC) 65.05 6.71 ESW-16A lapped 15-RBC-24B(OPC) <0.102 <0.102 disc and seat 15-A0V-130B(OPC) 13.89 13.89 and cleaned valve internals.

X-25 Drywell Inerting and C 27-A0V-111(OPC) <0.102 (A0V-111) <0.102 (A0V-111)

CAD and Purge X-71 27-A0V-112(OPC) (A0V-112) (A0V-112) CV-68 lapped 27-A0V-131A(OPC) >1018 (A0V-131A) 9.37 (A0V-131A) seat and CV-68(OPC) (CV-68) (CV-68) replaced disc, 27-A0V-131B(OPC) 6.36 (A0V-131B) 6.36 (A0V-131B) spring, and CV-69(OPC) (CV-69) (CV-69) gasket.

A0V-131A re-placed plug, stem, seat, and repacked.

X-26A Containment Atmospheric Sampling C 27-SOV-119F1(OPC) 0.25 0.25 SOV-120A cleaned 27-SOV-119F2(OPC) 0.102 0.102 replaced disc 27-SOV-120A(OPC) 21.3 <0.102 spring, body 27-SOV-120B(OPC) 41.1 <0.102 o-ring, piston 27-SOV-120El(OPC) 0.102 0.102 ring.

2096C-1515400-B2 Page 4 of 13

ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (scf/ day) Repair / Notes 27-SOV-120E2(OPS) 0.102 0.102 SOV-120B cleaned 27-SOV-122A(OPC) >1018 0.102 replaced disc 27-SOV-122B(OPC) 98.2 <0.102 spring, body 27-SOV-122El(OPC) 1.67 1.67 o-ring, piston 27-SOV-122E2(OPC) 0.386 0.386 ring.

27-SOV-121A(OPC) 4.38 4.38 SOV-122A cleaned 0.119 replaced disc 27-SOV-121B(OPC) 33.8 spring, body o-ring, piston ring.

SOV-122B SOV-121B cleaned replaced disc spring, body o-ring, piston ring.

X-26A, X-26B Containment Vent and Purge C 27-AOV-113(OPC) 7.35 (A0V-113) 7.35 (A0V-113) 27-AOV-114(OPC) (A0V-114) (A0V-114) 27-MOV-113(OPC) 0.179 (MOV-113) 0.179 (MOV-113) 27-MOV-122(OPC) (MOV-122) (MOV-122) .

X-31Ac "A" Recirculation Pump Mini-Purge C 02-RWR-13A(IPC) >1018 (RWR-13A) 2.8 (RWR-13A) RWR-13A lapped 02-RWR-14A(IPC) (RWR-14A) (RWR-14A) disc and seat.

02-RWR-40A(OPC) 11.2 (RWR-40A) 11.2 (RWR-40A) Cleaned valve (RWR-14A) (RWR-14A) internals and replaced spring and gasket.

X-31Ad Drywell Inert and Purge C 27-SOV-135A(OPC) 2.85 11.04 SOV-135A 27-SOV-135B(OPC) 328.3 11.4 SOV-135B new plunger assembly viton disc, piston ring, body o-ring.

2096C-15154CO-B2 Page 5 of 13

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ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (scf/ day) Repair / Notes X-31Be "B" Recirculation Pump Mini-Purge C 02-RWR-13B(IPC) 79.9 (RWR-13B) 4.55 (RWR-13B) RWR-14B re-02-RWR-14B(IPC) (RWR-14B) (RWR-13B) placed internals 02-RWR-40B(OPC) 7.48 (RWR-40B) 7.48 (RWR-40B) RWR-13B lapped (RWR-14B) (RWR-14B) disc and seat.

Cleaned valve internals and replaced disc, spring, and

. gasket.

X-35A TIP Probe C/B Ball Valve (OPC) 0.347 0.488 X-35A disassen-

"O" ring (OPC) 0.102 0.282 bled for main-tenance.

X-35B TIP Probe C/B Ball Valve (OPC) 0.79 2.5 X-35B disassea-

"O" ring (OPC) 0.102 0.116 bled for main-tenance.

X-35C TIP Probe C/B Ball Valve (OPC) 3.17 <0.102 X-35C disassen-

"O" ring (OPC) 0.102 0.228 bled for main-tenance. Ball valve replaced.

X-35D TIP Probe C/B Ball Valve (OPC) 0.401 0.79 X-35D disassen-

"O" ring (OPC) 0.102 2.74 bled for main-tenance.

X-35E TIP Purge C/B TP-1 (OPC) 0.435 0.435 "O" ring (OPC) 0.102 0.102 X-39A Containment Spray C 10-MOV-26A(OPC) >101.8 42.1 MOV-26A lapped 10-MOV-31A(OPC) (Combined) (Combiner) wedge and seat.

2096C-1515400-B2 Page 6 of 13 1 -. - - _

O O O ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakane (sef/ day) Leakane (scf/ day) Repair / Notes RHR-52A(OPC) Replaced gasket and packing MOV-31A lapped wedge and seat, polished stem, repacked.

X-39B Containment Spray C 10-MOV-26B(OPC) 136.9 41.3 MOV-26B lapped 10-MOV-31B(OPC) (Combined) (Combined) disc and seat RHR-52B(OPC) and replaced gasket.

X-41 Recirculation Loop Sample C 02-A0V-39(IPC) 0.266 (AOV-39) 0.266 (AOV-39)

RWR-255(IPC) (RWR-255) (RWR-255) 02-AOV-40(OPC) 0.109 (AOV-40) 0.109 (AOV-40)

(RWR-255) (RWR-255)

X-42 Standby Liquid Control C 11-SLC-17(IPC) 0.447 0.447 11-SLC-16(OPC) 0.987 0.987 X-45 Leak Rate Analyzer C 16-1-AOV-101A(OPC) 0.3415 (AOV-101A) 0.3415 (A0V-101A) 16-1-AOV-101B(OPC) (AOV-101B) (A0V-101B)

LRA-20(OPC) <0.102 (LRA-20) <0.102 (LRA-20)

LRA-21(OPC) (LRA-21) (LRA-21)

X-55B Drywell CAD Inert and Purge C 27-SOV-125A(OPC) 1.068 1.068 27-SOV-125B 27-SOV-125B(OPC) >1018 0.364 installed new valve.

X-58B CAD System C 27-SOV-122F1(OPC) 0.251 0.251 27-SOV-122F2(OPC) 0.1694 0.1694 X-58C CAD System C 27-SOV-120F1(OPC) 0.786 0.786 27-SOV-120F2(OPC) 0.1501 0.1501 2096C-1515400-B2 Page 7 of 13

O O O ATTACBENT 4A (Cont.)

1985 IDCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (sef/ day) Repair / Notes X-58D CAD System C 27-SOV-123F1(OPC) <0.102 <0.102 27-SOV-123F2(OPC) <0.102 <0.102 X-59 Drywell CAD Inert and Purge C 27-SOV-123A(OPC) 101.8 X-59; SOV-123A, 27-SOV-123B(OPC) 357.0 123B line cut 27-SOV-123El(OPC) 0.102 0.102 and capped.

27-SOV-123E2(OPC) 0.923 0.923 X-61 Breathing Air C BAS-5(IPC) 16.38 16.38 BAS-4 lapped BAS-4(OPC) 125.21 0.72 disc and seat.

X-62 Drysell Cooling Return C RBC-26B(OPC) 2.55' 2.55 15-AOV-131B(OPC) 1.41 1.41 X-63 "B" Recirculation Pump C 15-RBC-21A(OPC) 0.127 0.127 MTR Coolier Supply 46-ESW-15B(OPC) 33.64 33.64 15-AOV-132A(OPC) 2.9 2.9 X-64 "A" Recirculation Pump C 15-RBC-22A(OPC) 6.7 6.7 NTR Cooling Return 15-AOV-133A(OPC) 0.81 0.81 X-65 Equipment Drain C 15-RBC-33(OPC) 4.95 4.95 Pump Cooler Return 15-AOV-134A(OPC) 6.3 6.3 X-66 "A" Drywell Cooler C 15-RBC-26A(OPC) -207.0 9.0 RBC-26A, lapped Assembly Return 15-AOV-131A(OPC) 9.92 9.92 seat, disc, repacked.

X-67 "A" Recirculation Pump C 15-RBC-21B(OPC) 0.102 0.102 NTR Cooling Supply 46-ESW-15B(OPC) 0.102 0.102 15-AOV-132B(OPC) 0.324 0.324 X-68 "B" Recirculation Pump C 15-RBC-22B(OPC) 3.72 3.72 MTR Cooling Return ~ 15-AOV-133B(OPC) 0.835 0.835 2096C-1515400-B2 Page 8 of 13

ATTACIMENT 4A (Cont.)

1985 IDCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakate (sef/ day) Leakate (sef/ day) Repair / Notes X-100A Elect B "O" rings 0.525 0.525 X-1008 Elcet B "O" rings 0.554 0.127 X-100B Elect.

X-100C Elect B "O" rings 0.242 0.242 X-100D Elect B "O" rings 0.639 0.639 X-100F Elect B "O" rings 0.2692 0.2692 X-100G Elect B "O" rings 0.102 0.102 X-100K Elect B "O" rings <0.102 <0.102 X-101A Elect B "O" rings 0.303 0.303 X-1018 Elect B "O" 0.453 rings. 0.453 X 101C Elect B "O" rings 0.239 0.239 X-101D Elect B "O" rings 0.171 0.171 X-101E Elect B "O" rings 0.401 0.401 X-101F Elect B "O" rings 0.1119 0.1119 X-103A Elect B "O" rings 0.102 O.102 X-103B Elect B "O" rings 0.102 0.102 X-104C Elect B "O" rings 1.018 0.102 X-104C Elect.

X-104D Elect B "O" rings 0.102 0.102 2096C-1515400-82 Page 9 of 13

O O O ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakate (scf/ day) Leakage (sef/ day) Repair / Notes X-IC4E Elect B "O" rings 0.776 0.776 X-106A Elect B "O" rings 0.948 0.102 X-106A Elect.

X-106B Elect B "O" rings 0.5614 0.5614 X-107 Elect B "O" rings 0.102 0.102 X-108 Elect B "O" rings 0.207 0.207 X-109 Elect B "O" rings 0.489 0.489 X-110C Elect ,

B "O" rings 0.1628 0.1628 X-110D Elect B "O" rings 0.1409 0.1409 X-111B Elect B "O" rings 0.4591 0.1786 X-111B Elect.

X-200A Torus Access B "O" rings 0.1521 0.102 X-200A X-2008 Torus Access B "O" rings 0.3949 0.3949 X-200C Torus Access B "O" rings 0.332 0.332 X-202BG Vacuum Breaker C 27-A0V-101B(OPC) <0.102 (A0V-101B) <0.102 (AOV-101B)

VB-7(OPC) (VB-7) (VB-7) 27-AOV-101A(OPC) 4.79 (AOV-101A) 4.79 (AOV-101A)

VB-6(OPC) (VB-6) (VB-6)

X-202F Vacuum Breaker B "O" ring (VB-1) 0.285 0.285 X-222G Vacuum Breaker B "O" ring (VB-2) 0.210 0.102 VB-2 X-222H Vacuum Breaker B "O" ring (VB-3) 0.1369 0.1369 20%C-1515400-B2 Page 10 of 13

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b V b ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA i

l Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (sef/ day) , Repair / Notes l

X-2 2I Vacuum Breaker B "O" ring (VB-4) 0.1328 0.1328 l

X-202J Vacuum Breaker B "O" ring (VB-5) 0.2397 0.2397 I X-203A 02 Analyzer Sample C 27-SOV-119A(OPC) 16.03 0.284 SOV-119A cleaned l 27-SOV-119B(OPC) 0.1817 6.1817 new disc spring, 27-SOV-119El(OPC) 2.81 2.81 body o-ring and 27-SOV-119E2(OPC) 0.1129 0.1129 piston ring.

X-203B O2 Analyzer Sample C 27-SOV-124A(OPC) 7.5 7.5 27-SOV-124B(OPC) 0.228 0.228 27-SOV-124El(OPC) 0.171 0.171 27-SOV-124E2(OPC) 0.35 0.35 27-SOV-124F1(OPC) 0.115 0.115 27-SOV-124F2(OPC) 0.378 0.378 X-205 Drywell Inert CAD and Purge C 27-A0V-117(OPC) >1018 (A0V-117) 0.338 (AOV-117) A3V-117, 118 27-AOV-118(OPC) (A0V-118) (A0V-118) cleaned valve 27-MOV-117(OPC) 0.33 (MOV-117) 0.33 (MOV-117) anf installed 27-MOV-123(OPC) (MOV-123) (MOV-123) new T" ring and "0" ring X-211A Containment Spray C 10-MOV-34A(OPC) >101.8 4.16 MOV-10-MOV-38A(OPC) (Combined) (Combined) 10-MOV-39A(OPC)

X-211B Containment Spray C 10-MOV-34B(OPC) 153.7 96.15 MOV-39B ground 10-MOV-38B(OPC) (Combined) (Combined) seat and disc.

10-MOV-39B(OPC) Cleaned valve internals and replaced gasket.

2096C-1515400-B2 Page 11 of 13

l ATTACHMENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA

. Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Ten. Tested Leakage (sef/ day) Leakage (sef/ day) Repair / Notes X-212 RCIC Turbine Exhaust C RCIC'-04(OPC) >1018 38.17 RCIC-04 lapped RCIC-05(OPC) >1018 52.93 seat.

13-MOV-130(OPC) 0.2 0.2 RCIC-03 lapped wedge and seat.

X-214 HPCI Turbine Exhaust C 23-HPI-12(OPC) 96.6 96.35 HPI-65 cleaned,

. new gasket.

23-HPI-65(OPC) >1018 8S.51 HPI-11 Cleaned ground seat, new gasket X-217 HPCI Turbine Exhaust Vent C 23-MOV-59(OPC) 9.45 9.55 MOV-59 23-HPI-403(OPC) (Combined) (Combined) repacked.

23-HPI-402(OPC)

X-218 Leak Rate Analyzer C LRA-13(OPC) 0.203 (LRA-13) 0.203 (LRA-13)

LRA-14(OPC) (LRA-14) (LRA-14)

A0V-102A(OPC) 5.3 (A0V-102A) 5.3 (AOV-102A)

A0V-102B(OPC) (A0V-102B) (A0V-102B)

X-220 Drywell CAD Inert and Purge C 27-A0V-132A(OPC) 4.3 (A0V-132A) 4.3 (A0V-132A)

CV-67(OPC) (CV-67) (CV-67) 27-A0V-132B(OPC) 0.116 (A0V-132B) 0.116 (A0V-132B)

CV-70(OPC) (CV-70) (CV-70) 27-A0V-115(OPC) >1018 (A0V-115) 1.84 (A0V-115) A0V-116 replaced 27-A0V-116(OPC) (A0V-116) (A0V-116)' operator pin.

X-221 Condensate from RCIC Turbine C 13-RCIC-07(OPC) >101.8 23.41 RCIC-07 lapped 13-RCIC-08(OPC) >101.8 5.27 piston and seat, installed new spring and gasket, and repacked valve.

2096C-1515400-B2 Page 12 of 13

V ATTACIDENT 4A (Cont.)

1985 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair .

Penetration No. Test Tested Leakate (scf/ day) Leakate (sef/ day) Repair / Notes RCIC-08 lapped seat and re-placed gasket.

X-231A Elect B "0" rings 0.597 0.597 2096C-1515400-B2 Page 13 of 13

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O O ATTACIDENT 4B 1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakane (sef/ day) Leakate (sef/ day) Repair / Notes Drywell Stabilizer 0* (E-90*) B "O" rings 0.5003 0.5003 45' (2-135*) B "O" rings 0.6153 0.6153 90* (E-180*) B "O" rings 0.401 0.401 135* (E-225') E "O" rings 0.3206 0.3206 180* (M -270*) B "0" rings 0.5156 0.5156 225' (E-315*) B "0" rings 0.539 0.539 273* (E-0*) B "O" rings 0.6036 0.6036 315' (E-45*) B "O" rings 0.6153 0.6153 Dry Well Head B "O" rings 0.102 0.102 X-1A Equipment and Emergency B "O" rings 1.593 1.593 Escape Hatch X-1B Equipment htch B "O" rings 0.2229 0.2229 X-2A Personnel Access Hatch B "O" rings 42.25 42.25 X-4 Drywell Head h ahole B "0" rings 0.2682 0.2682 X-6 CRD Removal Hatch B "O" rings 0.2957 0.2957 X-7A "A" hin Steam Line C 29-AOV-80A(IPC) 14.761 14.761 29-AOV-86A(OPC) (Combined) (Combined)

X-75 "B" h in Steam Line C 29-AOV-80B(IPC) 20.36 <0.102 29-A0V-86B(OPC) 914.164 <0.102 X-7C "C" h in Steam Line C 29-A0V-80C(IPC) 18.4258 18.4258 29-A0V-86C(OPC) (Combined) (Combined) 2096D-1515400-B2 Page 1 of 11

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l ATTACHMENT 4B (Cont.)

1983 IDCAL LEAKAGE RATE TEST PENETRATION DATA l

Type Equipment / Valves Pre-kepair Post-Repair Penetration No. Test Tested Leakage (scf/ day) Leakage (sef/ day) Repair / Notes X-7D "D" Maia Steam Line C 29-A0V-80D(IPC) >1018 112.489 j 29-A0V-86D(OPC) <0.102 <0.102 l l

X-S Condensate Drain C 29-MOV-74(IPC) 2.825 2.825 29-MOV-77(OPC) 5.0034 5.0034 X-9A Feedwater C 34-IVS-28A(IPC) >1018(IVS-28A) 12.826(IVS-28A) IVS-28A cleaned valve, ground seat, and replaced l disc.

13-MOV-21(OPC) >1018(MOV-21) 147.61(MOV-21) NRV-111A cleaned valve, ground seat and disc, i 34-NRV-111A(OPC) (NRV-111A) (NRV-111A) cleaned operator shaft and cylinder, and replaced l RWC-62(OPC) (RWC-62) tRWC-62) 0-ring and gasket.  ;

X-95 Feedwater C 34-IVS-28B(IPC) >1018(IVS-28B) 6.275(IVS-28B) TVS-28B cleaned valve, ground seat, and replaced 23-MOV-19(OPC) >1018(MOV-19) 32.525)(MOV-19) disc.

34-NRV-111B(OPC) (NRV-1118) (NRV-1118)

X-10 Steam to RCIC Turbine C 13-MOV-16(IPC) <0.102 <0.102 13-MOV-15(OPC) 5.1205 5.1205 X-11 Steam to HPCI Turbine C 23-MOV-15(IPC) >1018 3.0947 MOV-16 repacked valve l 23-MOV-16(OPC) (Combined) (Combined) 23-MOV-60(OPC)

X-12 Shutdown Supply to RER C 10-MOV-17(IPC) 191.893 191.893 MOV-18 replaced wedge, ground seats.

10-MOV-18(OPC) >1018 1.99 l

l X-13A RER Return C 10-MOV-27A(OPC) 81.44 81.44 10-MOV-25A(OPC) 124.196 124.196 X-138 RHR Return C 10-MOV-27B(OPC) 81.185 81.185 10-MOV-25B(OPC) 115.54 115.54 2096D-1515400-82 Page 2 of 11

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ATTACHMENT 4B (Cont.)

1983 LOCAL IIAKAGE RATE TEST PEhTTRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakaze (sef/ day) Leakane (sef/ day) Repair / Notes 1-14 RECI: Supply to Recirculation C 12-ft0V-15(IPC) 28.504(ft0V-15) 28.504(Pt0V-15)

Pimps 12-ft0V-18(OPC) 6.342(MOV-18) 6.342(!t0V-18) 12-!s0V-80(OPC) (!!0V-80) (MOV-80)

I-16A Core Spray Pump Discharge C 14-!OV-11A(OPC) <1.02 <1.02 14-!s0V-12A(OPC) 29.165 29.165 I-168 Core Spray Pump Discharge C 1&-ft0V-11B(OPC) 0.1822 0.1822 14-P90V-12B(OPC) 3.3085 3.3085 I-17 RPV Head Spray C 10-f90V-32(IPC) 30.2855 30.2855 10-ft0V-33(OPC) 17.5605 17.5605 I-18 T1oor Sump Pump Discharge C 20-!s0V-82(IPC) 0.803 0.803 20-A0V-83(OPC) 3.28 3.28 I-19 Equipacat Sump Pump C 20-fl0V-94(IPC) >1018 1.04117 110V-94 ground seat, replaced wedge, and repacked Discharge 20-A0V-95(OPC) >1018 0.579 with new rings.

l l I-21 Service Air C 39-SAS-10(IPC) >1018 1.379 SAS-10 cleaned and lapped seat and disc, replaced 39-SAS-9(OPC) <0.102 <0.102 gastet.

SAS-11 inspected valve and lapped seat.

1-22 Instrument Air C 1AS-22(IPC) >1018 21.429 IAS-22 ground and lapped seat, replaced gasket.

IAS-21(OPC) 12.98 12.98 IAS-23(OPC) <0.102 <0.102 1-23 Cooling Water Supply C 46-ESW-16B(OPC) <0.102 <0.102 A0V-130A new installation.

15-RBC-24A(OPC) <0.102 <0.102 15-A0V-130A(OPC) 39.3966 39.3966 I-24 Cooling hater Supply C 46-ESW-16A(OPC) >1018 2.1475 AOV-130B new installation.

15-RBC-24B(OPC) <0.102 <0.102 ESW-16A ground disc and seat, new gasket.

15-A0V-130B(OPC) <0.102 <0.102 2096D-1515400-E2 Page 3 of 11

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ATTACHMENT 4B (Cont.)

1983 IDCAL LEAKAGE RATE TEST PEhTTRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration Ea. Test Tested Leakare (sef/ day) Leakage (sef/ day) Repair / Notes X-25 Drywell Inerting and C 27-A07-111(OPC) >1018(AOV-111) 0.3547(AOV-Ill) AOV-111, 112 cleaned valves, replaced T~ rings CAD and Purge I-71 27-AOV-112(OPC) (A0V-112) (%OV-112) and 0-rings.

27-AOV-131A(OPC) >1018(AOV-131A) 4.983(A0V-131A) CV-68 machined plug seat, replaced spring, CV-6S(OPC) (CV-68) (CV-68) replaced gasket, ground seat.

27-AOV-131B(OPC) 2.5094(A0V-131B) 2.5094(AOV-131B)

CV-69(OPC) (CV-69) (CV-69)

I-26A Containment Atmospheric Sampling C 27-SOV-119F1(OPC) <0.102 <0.102 SOV-119F1,F2 new installation.

27-SOV-119F2(OPC) <0.102 <0.102 27-SOV-120A(OPC) 127.25 (0.102 27-SOV-120B(OPC) 6.8613 6.8613 27-SOV-120El(OPC) <0.102 <0.102 SOV-120E1.E2 new installation.

27-SOV-12CE2(OPC) <0.102 <0.102 27-SOV-122A(OPC) >1018 (0.102 27-SOV-122B(OPC) 2.2294 2.2294 27-SOV-122El(OPC) <0.102 <0.102 SOV-122El,E2 new installation.

27-SOV-122E2(OPC) <0.102 <0.102 27-SOV-121A(OPC) 4.072 4.02 27-SOV-121B(OPC) 9.6557 9.6557 I-2 tut, I-268 Containment Vent and Purge C 27-A0V-113(OPC) 0.2428(AOV-113) 0.2428(AOV-113) 27-A0V-114(OPC) (A0V-114) (A0V-114) 27-MOV-113(OPC) 0.2718(MOV-113) 0.2718(MOV-113) 27-MOV-122(OPC) (MOV-122) (MOV-122)

X-31Ac "A" Recirculation Pump !!ini-Purge C 02-ER-13A(IPC) >1018(RWR-13A) 7.13(RbR-13A) RUR-13A machined plug, lapped plug and seat, 02-Elt-14A(IPC) (hR-14A) (RwR-14A) replaced gasket and spring.

02-Rb1-40A(OPC) >1018(ER-40A) 13.28(RWR-40A)

(RbR-14A) (RbR-14A)

X-31Ad Drywell laert and Purge C 27-SOV-135A(OPC) 8.037 8.037 SOV-1358 cleaned valve, replaced viton plug, seat, 27-SOV-135B(OPC) >1018 26.57 piston rings, e-rings, piston, piston rod, connec-l tion link, plunger assembly, and disc.

209 C-1515400-B2 Page 4 of 11

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ATTACHMENT 4B (Cont.)

i 1983 IDCAL LEAKAGE RAlt TEST PENETRATION DATA t.

i

' Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakate (sef/ day) Leakane (sef/ day) Repair / Notes

! X-31Bc "B" Recirculation Pump Mini-Purge C 02-RWR-13B(IPC) 30.133(RWR-13B) 30.133(RWR-13B) 02-RWR-14B(IPC) (RWR-148) (RWR-14B) 4 02-RWR-40B(OPC) 34.256(RWR-408) 34.256(RWR-40B)

(RWR14B) (RWR-14B) i l X-35A TIP Probe C/B Ball Valve (OPC) 26.824 26.824 "O" ring (OPC) 0.207 0.207 l

X-35E TIP Probe C/B Ball Valve (OPC) 0.964 0.964 l 0.205 "O" ring (OPC) 0.205 X-35C TIP Probe C/B Ball Valve (OPC) 3.346 3.346 "O" ring (OPC) 0.135 0.135 X-35D TIP Probe C/B Ball Valve (OPC) 6.795 6.795 "O" ring (OPC) 0.0208 0.0208 X-35E TIP Purge C/B TP-1 (OPC) 1.006 1.006 "O" ring (OPC) 0.132 0.132 X-36 CRD Return C- CRD-113(IPC) 70.14 1.5422 CRD-110(OPC) >1018 (Combined)

X-39A Containment Spray C 10-MOV-26A(OPC) >1018 1.5779 RHR-52A cut-out valve and replaced with new or.e.

10-MOV-31A(OPC) (Combined) (Combined)

RHR-52A(OPC)

X-39b Containment Spray C 10-MOV-26B(OPC) 533.941 74.212 MOV-26B inspected valve operator, increased torque 10-MOV-31B(OPC) (Combined) (Combined) switch setting, machined rings, replaced wedge and RNR-52B(OPC) rings.

2096D-1515400-B2 Page 5 of 11 f

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ATTACHMENT 4B (Cont.)

1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair

! Penetration No. Test Tested Leakane (scf/ day) Leakane (sef/ day) Repair / Notes X-41 Recirculation Loop Sample C 02-AOV-39(IPC) >1018(A0V-39) 1.481(AOV-39) A0V-39 repacked valve, ground and lapped seat and RWR-255(IPC) (RWR-255) (RWR-255) plug.

02-A0V-40(OPC) 2.036(A0V-40) 2.036(A0V-40)

(RWR-255) (RWR-255)

! X-42 Standby Liquid Control C 11-SLC-17(IPC) 2.652 2.652 SLC-16 replaced gasket, plug, piston, disc, and 11-SLC-16(OPC) 44.792 39.85 . spring.

X-45 Leak Rate Analyzer C 16-1-A0V-101A(OPC) 0.789(A0V-101A) 0.789(A0V-101A)

'16-1-AOV-101B(OPC) (A0V-101B) (A0V-101B)

LRA-20(OPC) 0.1415(LRA-20) 0.1415(LRA-20)

LRA-21(OPC) (LRA-21) (LRA-21) i X-55B Drywell CAD Inert and Purge C 27-SOV-125A(OPC) 0.9625 0.9625 i

27-SOV-125B(OPC) 1.3183 1.3183 l X-58B CAD System C 27-SOV-122F1(OPCJ 4.698 4.698 SOV-122F1 F2 new installation.

27-SOV-122F2(OPC) 0.1669 0.1669 1

1 i X-58C CAD System C 27-SOV-120F1(0PC) 0.3995 0.3995 SOV-120F1.F2 new installation.

27-SOV-120F2(OPC) 0.6542 0.6542 X-58D CAD System C 27-SOV-123F1(OPC) 0.4123 0.4123 SOV-123F1,F2 new installation.

27-SOV-123F2(OPC) 0.2647 0.2647 X-59 Drywell CAD Inert and Purge C 27-SOV-123A(OPC) >1018 5.6499 SOV-123A,B cleaned valves, replaced seats, viton 27-SOV-123B(OPC) >1018 <0.102 discs, springs, piston rings, and 0-rings.

27-SOV-123El(OPC) 2.6977 2.6977 SOV-123E1.E2 new installation.

27-SOV-123E2(OPC) <0.102 <0.102 2096D-1515400-82 Page 6 of 11

Y j ATTACIDfENT 4B (Cont.)

1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Prnitration No. Test Tested Leakage (sef/ day) Leakage (scf/ day) Repair / Notes X-61 Breathing Air C BAS-5(IPC) 413.817 13.743 BAS-5 cleaned valve and polished disc.

BAS-4(OPC) 119.615 6.785 BAS-4 ground disc and seat.

X-62 Drywell Cooling Return C RBC-26B(OPC) 36.85 36.85 A0V-131B new installatior,.

15-A0V-131B(OPC) 13.794 13.794 X-63 "B" Recirculation Pump C 15-RBC-21A(OPC) <0.102 <0.102 A0V-132A new installation.

MTR Cooling Supply 46-ESW-15B(OPC) 12.5214 12.5214 15-A0V-132A(OPC) 27.995 27.995 X-64 "A" Recirculation Pump C 15-RBC-22A(OPC) 38.84 38.84 A0V-133A new installation.

MTR Cooling Return 15-A0V-133A(OPC) 4.5351 4.5351 X-65 Equipment Drain C 15-RBC-33(OPC) 2.0156 2.0156 A0V-134A new installation.

Pump Cooler Return 15-A0V-134A(OPC) 2.1174 2.1174 X-66 "A" Drywell Cooler C 15-RBC-26A(OPC) <0.102 <0.102 A0V-131A new installation.

Assembly Return 15-A0V-131A(OPC) 5.446 5.446 X-67 "A" Recirculation Pump C 15-RBC-21B(OPC) <0.102 <0.102 A0V-132B new installation.

MTR Cooling Supply 46-ESW-15A(OPC) <0.102 <0.102 15-A0V-132B(OPC) <0.102 <0.102 X-68 "B" Recirculation Pump C 15-RBC-22B(OPC) 560.41 34.3575 RBC-22B cleaned valve, lapped disc and seat.

MTR Cooling Return 15-A0V-133B(0.') 19.8001 19.8001 A0V-133B new installation.

X-100A Elect B "O" rings <0.102 <0.102 X-100B Elect B "O" rings <0.102 <0.102 X-100C Elect B "O" rings <0.102 <0.102 X-100D Elect B "O" rings 0.2769 0.2769 2096D-1515400-B2 .Page 7 of 11

. .. . ~ . .

ATTACIDfENT 4B (Cont.)

1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves

~

Pre-Repair Post-kepair Penetration No. Test Tested Leakage (scf/ day) Leakage (scf/ day) Repair / Notes X-100F Elect B "O" rings 0.1312 0.1312 X-100G Elect B "O" rings <0.102 <0.102 X-100K Elect B "O" rings <0.102 <0.102 i

X-101A Elect B "0" rings <0.102 <0.102 X-101B Elect B "O" rings <0.102 <0.102 X-101C Elect B "O" rings <0.102 <0.102 X-101D Elect B "O" rings <0.102 <0.102 X-101E Elect B "O" rings <0.102 <0.102 X-101F Elect B "O" rings 0.1273 0.1273 l

X-103A Elect B "O" rings <0.102 <0.102 X-103B Elect B "O" rings <0.102 <0.102 X-104C Elect B "O" rings <0.102 <0.102 f

X-104D Elect B "O" rings <0.102 <0.102 i

X-104E Elect B "O" rings <0.102 <0.102 X-106A Elect B "O" rings 0.5039 0.5039 <

X-106B Elect B "O" rings <0.102 <0.102 X-107 Elect B "O" rings <0.102 <0.102  !

2096D-1515400-B2 Page 8 of 11 e

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m ATTACHMENT 4B (Cont.) ,

1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA s

i Type Equipment / Valves Pre-Repair Post-Repair l Penetration No. Test Tested Leakage (scf/ day) Leakage (sef/ day) Repair / Notes

! X-108 Elect .B "O" rings <0.102 <0.102 4 X-109 Elect B "O" rings <0.102 <0.102

! X-110C Elect B "O" rings <0.102 <0.102 j X-110D Elect B "O" rings <0.102 <0.102 1

i X-111B Elect B "0" rings <0.102 <0.102 a

i X-200A Torus Access B "O" rings 0.3741 0.3741 X-200B Torus Access B "0" rings 0.5415 0.5415 j X-200C Torus Access "O" rings B 0.3837 0.3837 j X-202BG Vacuum Breaker C 27-A0V-101B(OPC) 1.49(A0V-101B) 1.49(AOV-101B) l VB-7(OPC) (VB-7) (VB-7) i 27-AOV-101A(OPC) 2.35(A0V-101A) 2.35(A0V-101A) l i

VB-6(OPC) (VB-6) (VB-6)

X-202F Vacuum Breaker B "O" ring (VB-1) 0.214 0.214 X-202G Vacuum Breaker B "O" ring (VB-2) 0.214 0.214 i

i X-202H Vacuum Breaker B "O" ring (VB-3) 0.216 0.216 X-202I Vacuum Breaker B "0" ring (VB-4) 2.988 2.988 1

j X-202J Vacuum Breaker B "0" ring (VB-5) 0.247 0.247 i

i i

I l

1 2096D-1515400-B2 Page 9 of 11 i

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ATTACHMENT 4B (Cont.)

1983 IDCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair Penetration No. Test Tested Leakage (sef/ day) Leakage (scf/ day) Repair / Notes X-203A 02 Analyzer Sample C 27-SOV-119A(OPC) 3.242 3.242 SO\-119El,E2 new installation.

27-SOV-119B(OPC) 3.7528 3.7528 27-SOV-119El(OPC) 0.779 0.779 27-SOV-119E2(OPC) 2.08 2.08 X-2038 02 Analyzer Sample C 27-SOV-124A(OPC) 13.28 13.28 27-SOV-124B(OPC) 0.2214 0.2214 27-SOV-124El(OPC) 0.6103 0.6103 SOV-124El,E2 new installation.

27-SOV-124E2(OPC) 0.2713 0.2713 27-50V-124F1(OPC) 0.2779 0.2779 SOV-124F1.F2 new installation.

27-SOV-124F2(OPC) 0.6886 0.6886 X-205 Drywell Inert CAD and Purge C 27-A0V-117(OPC) 330.85(A0V-117) 52.1725(A0V-117) A0V-117 replaced T-ring and 0-ring.

27-A0V-118(OPC) (AOV-118) (A0V-118) 21-MOV-117(OPC) 0.2886(MOV-117) 0.2886(MOV-117) 27-MOV-123(OPC) (MOV-123) (MOV-123)

X-211A Containment Spray C 10-MOV-34A(OPC) 107.399 107.399 10 MOV-38A(OPC) (Combined) (Combined) 10-MOV-39A(OPC)

X-211B Containment Spray C 10-MOV-34B(OPC) 53.5468 53.5468 10-MOV-38B(OPC) (Combined) (Combined) 10-MOV-39B(OPC)

>1018 44.7106 RCIC-04 machined back seat surface, seat ring, and X-212 RCIC Turbine Exhaust C RCIC-04(OPC)

RCIC-05(OPC) >1018 44.1812 disc.

13-MOV-130(OPC) 6.885 6.885 X-214 HPCI Turbine Exhaust C 23-HPI-12(OPC) >1018 101.545 HPI-65 cleaned volve, machined and ground back seat 23-HPI-65(OPC) >1018 44.842 surface, seat, disc, disc swing arm, and replaced gaskets.

HPI-12 cleaned valve, machined disc, ground seat, replaced gasket.

2096D-1515400-B2 Page 10 of 11

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D J O ATTACHMENT 4B (Cont.) '

1983 LOCAL LEAKAGE RATE TEST PENETRATION DATA Type Equipment / Valves Pre-Repair Post-Repair P astration No. Test Tested Leakane (scf/ day) Leakage (sef/ day) Repair / Notes X-217 HPCI Turbine Exhaust Vent C 23-MOV-59(OPC) 19.2402 19.2402 23-HPI-403(OPC) (Combined) (Combined) 23-HPI-402(OPC)

X-218 i.e'is Rate Analyzer C IJtA-13(OPC) 0.3177(LRA-13) 0.3277(LRA-13)

IJLA-14(OPC) (LRA-14) (LRA-14)

ADV-102A(OPC) 0.3064(A0V-102A) 0.3064(A0V-102A)

A0V-102B(OPC) (A0V-1028) (A0V-1023)

X-220 Drywell CAD Inert and Purge C 27-A0V-132A(OPC) 2.789(A0V-132A) 2.789(A0V-132A) A0V-115,116 cleaned valves, replaced T-rings and CV-67(OPC) (CV-67) (CV-67) 0-rings.

27-A0V-132B(OPC) 55.1756(A0V-1328) 55.1756(A0V-132B)

CV-70(OPC) (CV-70) (CV-70) 27-A0V-115(OPC) >1018(A0V-115) 4.0618(A0V-115) 27-A0V-116(OPC) (A0V-116) (A0V-116)

X-221 Condensate from RCIC Turbine C 13-RCIC-07(OPC) >1018 2.8605 RCIC-07,08 cleaned valves, ground and lapped plugs.

13-RCIC-08(OPC) >1018 2.7587 seats, pistons, replaced flex gaskets and springs.

X-231A Elect B "O" rings 0.3823 0.3823 2096D-1515400-82 Page 11 of 11

O G

ATTACHMENT 4C PRIMARY CONTAINMENT BOUNDARY MODIFICATIONS The following JAFNPP primary containment boundaries were modified during the 1983 and 1985 outages.

1. Penetrations modified to provide taps for the H2 Monitoring System:

a. X-26A S0V-120E1, SOV-120E2, S0V-119F1, SOV-119F2, S0V-122E1, and SOV-122E2 were tied in. Manual valves (CAD-204, CAD-205, and CAD-206) are open and associated caps removed.

b. X-58B S0V-122F1 and SOV-122F2 were tied in. Manual valve (CAD-214) is open and associated cap removed.

c. X-58C S0V-120F1 and SOV-120F2 were tied in. Manual valve (CAD-215) is open and associated cap removed.

d. X-58D SOV-123F1 and S0V-123F2 were tied in. Manual valve (CAD-216) is open and associated cap removed.

e. X-59 SOV-123E1 and SOV-123E2 were tied in. Manual valve

- (CAD-207) is open and associated cap removed.

/ ,\

\-- f. X-203A SOV-119El and SOV-119E2 were tied in. Manual valve (CAD-201) is open and associated cap removed.

g. X-203B SOV-124E1, S0V-124E2, SOV-124F1, and SOV-124F2 were tied in. Manual valves (CAD-202 and CAD-203) are open and associated caps removed.

2. Reactor Building Cooling Water containment isolation valves added:

a. X-23 A0V-130A was added.

b. X-24 A0V-130B was added,

c. X-62 A0V-131B was added.

d. X-63 A0V-132A was added.

e. X-64 A0V-133A was added.

f. X-65 A0V-134A was added.

g. X-66 A0V-131A was added.

h. X-67 A0V-132B was added.

(/j} j. X-68 A0V-133B was added.

2096E-1515400-B2 Page 1 of 2

ATTACHMENT 4C (Cont.)

PRIMARY CONTAINMENT BOUNDARY MODIFICATIONS

3. MOV-18 was replaced and relocated on Penetration X-12.

4. Penetration X-36 CRD return line was cut and capped.

5. Penetration X-59 line containing valves SOV-123A,B was cut and capped.

O O

2096E-1515400-B2 Page 2 of 2

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