ML18038B120

Reactor Containment ILRT Browns Ferry Nuclear Plant Unit 2 Conducted 941105-07, Test Rept

ML18038B120
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Site:	Browns Ferry
Issue date:	01/25/1995
From:	Clarke K, Kimberly Green TENNESSEE VALLEY AUTHORITY
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Reactor Containment Building Integrated Leak Rate Test Browns Ferry Nuclear Plant Unit 2 Conducted November 5-7, 1994 Test Report Prepared by:

Reviewed by:

Approved by:

Date Approved:

~7 zs/q5 Submitted to:

'Ihe United States Nuclear Regulatory Commission Pursuant to Facility Operating Licensing

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SECTION TITLE TABLE OF CONTESTS PAGE 1.0 2.0 3.0 3.1 3.2 4.0 5.0 5.1

SUMMARY

TEST PURPOSE AND RESULTS est Purpose..

T Test Results.

CONDUCT OF TEST S AND CALCULATIONS.

Test Equipment Sensor Location.

.2

.2

.2

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.10 10 10 5.3 5.4 6.0 6.1 6.2 6.3 Computer-Based Data Acquisition and Data Reduction...10 Containment Model..

ANALYSIS OF TEST DATA..

Instrument Assessment Discussion of Graphical and Tabular Results..........11 Discussion of Agreement (Verification Test)..........12 6.4 7.0 Discussion of "As Found" Leak Rate Exceeding Technical. Specifications..

CONCLUSIONS..

APPENDICES 12 13 A.

B.

C.

D.

E.

F.

G H.I ~J.

K.

L.

Stabilization Phase Graphs and Tabular Data.....14 CILRT Test Phase Graphs.

..................27 CILRT Test Phase Tabular Data..

39 Verification Test Phase Graphs.

50 Verification Test Phase Tabular Data............62 Verification Analysis Summary..

...67 Penetrations Not Vented During the CILRT........68 Ccmputer System Block Diagram....

69 Compartment Parameters and Instrument Locations. 72 Instrument Specif ications 80 Water Level Readings.

81 Summary of Local Leak Rate Tests

......82

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INTRODUCfION This report contains the summary technical analysis of the Reactor Building Containment Integrated Leak Rate Test (CILRT) conducted on Browns Ferry Nuclear Plant (BFN) Unit 2 November 5-7, 1994.

As prescribed in BFN Technical Specification 4.7.A.2, the leakage of air from the boundary forming the reactor building primary containment is limited to 2.0 percent by weight of the containment air mass per day at a pressure of P49.6 psig.

This test was conducted in accordance with the requirements of Title 10, Code of Federal Regulations (CFR), Part 50, Appendix J, which is implemented by BFN Surveillance Instruction (SI) 2-SI-4.7.A.2.a-f.

The American National Standard for Containment Testing, ANSI 45.4-1972, the proposed American Nuclear Society Standard for Containment Testing, ANS 56.8, and the procedure outlined in Bechtel's Topical Report, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants" (BN-TOP-1, Revision 1), provided guidance for the procedure implemented by the SI.

BFN Unit 2 is a 3,293-megawatt thermal, boiling water reactor employing a steel pressure suppression containment.

The Final Safety Analysis Report defines the calculated peak accident pressure, P to be 49.6 psig.

The reactor containment building is divided into two major compartments-the drywell, enclosing the reactor and the forced recirculation system, and a pressure suppression pool chamber.

These two compartments are connected by blowdown pipes that terminate below the suppression pool level.

Vacuum breakers are provided to ensure that the suppression chamber is never pressurized with respect to the drywell. For the performance of this CILRT, these vacuum breakers were mechanically locked open to ensure pressure equalization between the drywell and the suppression chamber.

This report outlines the objectives, principal events, special equipment, and analysis of the test results for the CILRT completed on November 7, 1994, on BFN Unit 2. In addition, a summary of local leak rate tests conducted since the previous CILRT is included in Appendix L.

SUMMARY

A CILRT was conducted on BFN Unit 2 November 5-7, 1994, in preparation for return to power operation.

The CILRT was successfully completed in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 10 minutes and included 50 data samples.

The calculated Total Time Leak Rate (TTLR) was 0.33203 percent of containment air mass per day (% /day). The associated reportable "As Found" 95 percent upper confidence limit (UCL), which includes the type B and C leakage for testable penetrations in service at the time of the CILRT, the difference between the "As Found" minimum and the "As Left" minimum path leakage rates for tests performed in

conjunction with the Unit 2, cycle 7 refueling outage, and compensation for water level changes not accounted for by the CILRT computer system was 5.2332 % /day.

The "As Left" 95 percent UCL value of 0.37699 % /day includes the type B and C leakage for testable penetrations in service during the CILRT and compensation for water level changes not accounted for by the CILRT computer system.

The "As Found" Mass Leak Rate (MLR) for the CILRT was 0.33944 % /day.

The associated reportable "As Found" 95 percent upper UCL was 5.2062 % /day, and the reportable "As Left" 95 percent UCL was 0.35001 % /day.

These values reflect the adjustment provisions as described for TTLR.

3.0 TEST PURPOSE AND RESULTS 3.1 TEST PURPOSE The primary objective of the CILRT was to demonstrate the continuing leak-tight integrity of the Unit 2 reactor containment for return to power operation.

For BFN Unit 2, the leak-tight integrity is defined in Technical Specifications to be that the leakage of air from containment is not to exceed 1.5 % /day at peak accident pressure, P,.

3.2 TEST RESULTS The following table presents the test results with appropriate adjustments in leak rates as indicated by the notations.

Evaluation of the Instrument Selection Guide and statistical analysis of proposed Regulatory Guide MS-021-5 are also presented.

Additional tabular data on the CILRT and verification test results are presented in Appendices C and E.

The Total Time Leak Rate results, required by BN-TOP-1, Revision 1, for short duration tests, represent only 25.1 percent of the allowable 1.5 percent of containment air mass, as described under Technical Specification 4.7.A.2.

Agreement as prescribed by BN-TOP-1 between the CILRT and the verification test was 9.67 percent, which is well within the + 25 percent L, Required by Technical Specifications.

During the stabilization period, the primary containment was tested for unidentified leakage with a soap solution using Technical instruction 2-TI-173.

Leakage was identified at several instrument tubing compression fittings on panels 2-25-57, 2-25-306, and 2-25-307, which are tested as part of the CILRT boundary.

The magnitude of these leakage paths was insufficient to preclude the successful performance of the CILRT, so the locations of these leaks were noted in 2-TI-173, and repairs were deferred until after completion of the CILRT and verification

tests.

These repairs were subsequently performed before primary containment was depressurized.

Since no convenient provisions for locally quantifying these leaks existed, no adjustment was made in the CILRT results to reflect the improvement realized by these repairs.

The leak-tight integrity of BFN Unit 2 was accurately measured and recorded by a computer-based instrumentation and data acquisition system.

The acquisition system provided reliable, immediate calculations of the test data, thereby allowing test engineers to continuously monitor all instrumentation and test parameters.

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Table of CILRT and Verification Test Results TTLR = Total Time Leak Rate MLR = Mass Leak Rate Post Test ISG 0 0655315 percent per day (using instrument repeatability)

(25 percent L, = 0,5 percent per day)

As Found TTLR MLR Calculated 0.332030 % /day 0.339439 % /day W'ith 95% UCL 5.233189 % /day OX2) 5 206214 % /day onst As Left Calculated 0 341530 % /day 0.348939 % /day CILRT Test Duration 8

Hours 10 Minutes CILRT Number of Samples 50 CILRT Sample Span 212 to 261 lf/'ith 95% UCL 0.376989 % /day 0350014% /day

'erification Test TTLR Agreement 9.50 MLR Agreement 8.93 Verification Test Duration 4

Hours 10 Minutes Verification Number of Samples 26 Verification Sample Span 270 to 295 Extended ANSI Statistical Analysis for CILRT (satisfaction of equations 1.1 or 1.2 and 2.1 is required)

Equation 1.1 2.8790 <

1 Not Satisfied 1.2 0.0532 <

1 Satisfied 2.1 5.2424 >

1 Satisfied (1) Reflects leakage savings of 4.8562 percent per day.

See Appendix L for calculation.

(2) Reflects leakage of systems in service during the CILRT of 0.0095 percent per day.

See Appendix G for calculation.

(3)

See Appendix F for agreement calculations.

~

CONDUCT OF TEST Prior to the start of the CILRT, local leak rate tests (LLRT) were conducted on the containment closures (hatches with resilient seals, bellows, and electrical penetrations) in accordance with surveillance instructions 2-SI-4.7.A.2.g-l and 2-SI-4.7.A.2.g-2 (series).

LLRTs were conducted on valves forming the boundary of the primary containment in accordance with surveillance instructions 2-SI-4.7.A.2.g-3 (series),

with all valves meeting satisfactory leakage requirements prior to the performance of the CILRT.

The Residual Heat Removal (RHR) and the Core Spray (CS) safety systems were aligned to allow exposure to the CILRT test pressure.

Water levels in the reactor vessel and the pressure suppression chamber were monitored for unexpected or unusual changes during the test sequence, but were not intentionally controlled with makeup or letdown (See Appendix K). The levels were allowed to change in response to possible internal system leakage (i.e., leakage from the reactor vessel to the pressure suppression chamber via safety system piping) or possible external system leakage (i.e., from primary containment via the RHR and CS external piping). This test configuration provides a means to reflect any water leakage from these systems external to the primary containment boundary (via displacement) in the CILRT measured leak rate.

This CILRT was the first to be performed on a Browns Ferry unit with the reactor vessel head installed and torqued.

Previous, tests had been performed with the vessel head in place but not torqued due to high value of the vessel minimum nil ductility temperature (100'F for Unit 2). Prior to beginning the test sequence, the Reactor Coolant System (RCS) temperature was stabilized at 155'F to ensure that the reactor vessel head flange temperature was maintained above 100'F.

This RCS temperature resulted in an air temperature of approximately 112'F in the drywell regions above and immediately below the vessel flange.

Although the maximum permissible exposure temperature for temperature sensors used with the CILRT measuring and data acquisition system is 390'F, the normal measuring range is 0-114'F.

Five sensors were specially modified and calibrated to allow temperature measurements up to 130'F.

Three of these five modified sensors were intended to be installed in the drywell area above the vessel head flange in anticipation of elevated temperatures.

The two remaining modified sensors were intended to serve as spares ifneeded.

Three modified sensors were installed above the vessel head flange and were verified to be functioning properly.

The two spare modified sensors were then installed in the area below the drywell bulkhead (just below the vessel flange).

Pressurization of the primary containment was planned to be accomplished in approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Pressurization began at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> on November 5, 1994.

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The temperature in the drywell immediately began increasing dramatically, causing the temperature immediately below the drywell bulkhead to approach 114'F. The pressurization rate was reduced significantly to slow the rate of temperature rise, and the Operations Department began decreasing the RCS temperature from 155'F to 133'F.

These combined actions resulted the ability to maintain the temperatures within the calibrated range of the temperature sensors (one standard range temperature sensor did momentarily exceed 114'F, but quickly fell back into range).

Due to the elevated temperatures, pressurization of primary containment required 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and 40 minutes and was completed at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />.

The required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stabilization was begun on November 6 at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, following completion of the isolation of penetration X-48 and venting of the pressurization line, and completed at 0551 hours0.00638 days <br />0.153 hours <br />9.11045e-4 weeks <br />2.096555e-4 months <br /> (see Appendix A for stabilization phase acceptance criteria).

Evaluation of the containment environment parameters indicated that although temperatures in the drywell compartment were substantially higher than had been experienced in previous BFN tests (due to the higher RCS moderator and reactor vessel flange temperatures),

the temperature distribution was comparable to that of past tests.

The overall containment conditions were relatively stable from the beginning of the stabilization phase.

This was attributed, in part, to the slow pressurization rate which reduced the effects of ingassing.

Another identifiable contributing factor was the containment ventilation configuration (no forced ventilation, which reduced spot heat sources due to blower operation).

At 0601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br />, the CILRT test phase was initiated..The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 10 minute, 50 samples test proceeded uneventfully, with conditions remaining stable and water levels remaining essentially constant.

The CILRT test phase was concluded at 1411 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.368855e-4 months <br /> in accordance with BN-TOP-1, Revision 1.

The linearity of the CILRT was confirmed by statistical evaluation as described in proposed Regulatory Guide MS-021-5.

Subsequent to the conclusion of the CILRT test phase, a leak of 1140 SCFH (approximately Lg was imposed on the primary containment.

The primary containment was allowed to stabilize for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after introduction of this leak before beginning the verification test.

The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 10 minute verification test was initiated at 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> on November 6 and was completed at 1951 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.423555e-4 months <br />.

No perturbations occurred during this period, and the required agreement between this test and the CILRT was attained immediately.

The following gives a chronological listing of events associated with the CILRT.

Date and Time 11/5/94 0700 Event Completed temperature survey of drywell compartment with elevated vessel flange temperature (173'F) and RCS temperature (155'F) to confirm validity of previous temperature survey.

11/5/94 1030 11/5/94 1230 Completed 2-TI-173, Step 7.6, Primary Containment Inspection Completed pretest briefings with Operations and all personnel associated with test.

11/5/94 1355 11/5/94 1423 Began pressurization of primary containment at 9.4 psi/hour.

Temperature in the upper region approaching calibration limitof some temperature sensors.

Reduced pressurization rate slightly to reduce temperature rise.

11/5/94 1449 Reduced pressurization rate to slow containment temperature increase.

Rate now 8.4 psi/hour. Containment pressure is 8.0psig.

11/5/94 1500 11/5/94 1535 Briefed oncoming Operations shift.

Reduced pressurization rate again to slow containment temperature rise.

11/5/94 1710 Pressurization rate has been adjusted several times in attempts to slow/stop temperature rise. Only moderate success has been realized. Containment pressure now at 22.0 psig. Requested a

decrease in the RCS moderator temperature to assist in reducing the containment temperatures in the upper portion of the drywell.

Technical Support Manager is talking with Operations.

11/5/94 1740 Operations Supervisor-On-Shift (SOS) has agreed to reduce the RCS temperature 15 to 20 degrees.

The Plant Manager has concurred.

11/5/94 1905 Primary CILRT data acquisition computer crashed due to overheating (Pentieum 66 computer). Switched to backup computer and added additional cooling.

11/5/94 1947 11/5/94 1950 Containment pressure at 34.5 psig.

Agreement with CILRT pressure monitors and control room pressure monitors verified at 35 psig in containment.

11/5/94 2205 Placed CRD system in service to raise reactor vessel water level to 90 inches.

11/5/94 2227 Addition of cold water decreasing moderator temperature (currently -125'F). Containment pressure at 44.99 psig.

11/5/94 2340 Reactor vessel level at 90 inches. CRD system shutdown and isolated.

11/6/94 0035 11/6/94 0106 11/6/94 0130 11/6/94 0132 11/6/94 0135 Increased containment pressurization rate.

Containment pressure at 49.7 psig. Shut down one compressor.

Containment pressure at 50.55 psig.

PSC head tank overflowing. Operations investigating.

Stopped pressurization.

Containment at 50.7 psig (target is 50.4-51.2 psig).

11/6/94 0145 11/6/94 0152 Began Containment Stabilization.

Operations isolated Core Spray valves 2-FCV-75-57 and 2-FCV-75-58 to stop PSC head tank overflow. These are containment isolation valves that are locally tested and that should have been shown closed in the test procedure.

11/6/94 0256 Conducted pre-inspection briefing with system engineers prior to beginning inspection for unidentified leakage per 2-TI-173.

11/6/94 0333 Water leak reported at bay 11 on top of torus. Leak had been previously reported and identified as water coming from outside and through a block valve on the Reactor Building Closed Cooling Water system (RBCCW) seeping out an open test vent.

This seepage was analyzed and determined not to impact venting of the RBCCW line.

11/6/94 0444 Performed leakage tests on shaft seals on Core Spray Pumps A and B and inspected 2-FCV-75-57 bonnet and packing for

leakage as required by 2-TI-173.

11/6/94 0500 Leakage found on instrument tubing joints in three locations.

Leakage inspected and determined to be acceptable for performance of CILRT. These leaks will be repaired following the CILRT test sequence while pressure is still on containment.

(These leaks are not locally testable).

11/6/94 0551 Completed Containment Stabilization phase. Temperature Criteria met.

11/6/94 0601 11/6/94 1411 Started CILRT test phase at sample 212.

Completed CILRT test phase at sample 261. Test duration was 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 10 minutes. All BN-TOP-1, Revision 1, criteria met.

11/6/94 1440 11/6/94 1541 Established an imposed leakage of 1140 scfh on containment.

Completed required stabilization period with imposed leak.

Began Verification test phase.

11/6/94 1951 Completed Verification test phase. Verification test duration was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 10 minutes. Agreement criteria satisfied.

11/6/94 2000

. Notified Instrument Maintenance department to repair leaks found on instrument tubing during performance of 2-TI-173.

11/6/94 2055 Temporary mechanical valve'stops used to provide positive control of depressurization path valve positions installed in ventilation valves 2-FCV-64 -29 and 2 FCV-64-30.

11/6/94 2201 11/7/94 0535 Leak repairs completed. Began depressurization.

Containment depressurization completed.

5.0 MEASUREMENTS AND CALCULATIONS 5.1 Test E ui ment Appendix J lists the range, accuracy, and repeatability of the special test equipment used in the Unit 2, cycle 7 CILRT. Test instrumentation received pre/post test calibration checks.

The test instruments were calibrated by the TVA Central Laboratories with standards traceable to the National Bureau of Standards.

One redundant pressure gauge installed in the Torus compartment (TVAI.D.

Number E21317) was found to be out-of-tolerance during the post-test calibration check.

This gauge was deleted from the test data base, and test results were recalculated after adjusting the volume weight of the redundant pressure gauge to compensate for the deleted gauge.

5.2 Sensor Location Appendix I lists the volumetric weighting factor for each temperature and relative humidity sensor based on the two-compartment model used for this test.

The associated figures indicate sensor locations.

The pressure sensors were divided so that two sensors measured each compartment through penetrations X-25 and X-205. Utilizing two sensors per compartment allows removal of any one mal-functioning pressure gauge during the test while continuing to accurately monitor containment pressure.

As discussed in paragraph 5.1, one Torus compartment gauge was removed from the-test data base as a result of the post-test calibration check without compromising the test results.

An additional pressure gauge measured barometric pressure at the test station.

5.3 Com uter-Based Data Ac uisition and Data Reduction The test data measured by the special test instrumentation during the BFN Unit 2 CILRT was automatically scanned and collected by a PC computer system and then reduced.

The computer produced immediate statistical and graphical results of the containment test parameters, including temperature, pressure, vapor

pressure, mass, MLR, and TTLR plots.

These calculated results were reported automatically to the test director as data was collected.

Appendix H depicts the functional relationship between the special test instrumentation and the PC computer system.

All calculations performed by the computer system were in conformance with the procedures outlined in ANS 56.8, ANSI 45.2-1972, and/or Bechtel Topical report BN-TOP-1, Revision 1.

Software used by the PC was purchased from Duke Engineering Company.

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Source listing for all computer programs are on file with the Plant Operating Systems group in Chattanooga, Tennessee.

Additional software Commercial Dedication, Software Description, and User's manuals are located in the BFN Technical Support organization.

5.4 Containment Model A two-compartment model was used to represent the Unit 2 containment.

The first compartment was the drywell which was subdivided into five segments.

A constant volume mode was used with a volume of 164,170.2 ft'epresenting the drywell volume.

Twenty-nine temperature, 7 relative humidity, and two pressure instruments were used to determine the ambient conditions in the drywell.

The second compartment was the pressure suppression chamber (torus).

Due to the uniformity of atmospheric conditions in the torus, this compartment consisted of only one segment.

Again, a constant volume mode was used, amounting to 136,629.5 ft'. Six temperature, 3 relative humidity, and 2 pressure instruments were used in the torus compartment.

6.1 t

6.0 ANALYSIS OF TEST DATA Instrument Assessment The total complement of instruments for both the drywell and torus was 35 temperature, 10 relative humidity, 4 containment pressure, and one flow instrument.

In addition, 1 pressure and one temperature instrument was used to monitor atmospheric conditions.

No instruments, 'other than the pressure gauge discussed in paragraph 5.1, were lost or malfunctioned during the entire test interval.

6.2 Discussion of Gra hical and Tabular Results for the CILRT and Verification Phases The CILRT and verification test phases were markedly uneventful.

The CILRT was completed in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 10 minutes with 50 samples collected.

The

measured, measured mean, calculated, and delta calculated leak rates were all converging.

The extrapolated value of the leak rate was 0.352522 percent per day.

The verification test was also without incident.

26 samples were taken after allowing the verification imposed flow to stabilize for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The verification test was concluded in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 10 minutes and agreement was satisfactory.

During the CILRT phase and the verification test phase the water levels in the reactor vessel and torus were allowed to fluctuate without make-up to either vessel.

The reactor vessel level decreased slightly (10 inches during the combined CILRT and verification test periods) while the torus level increased slightly (- 0.2 inches during the same period) indicating that no measurable leakage was occurring out of the RHR and CS systems.

(See Appendix K for water tabular data) 6.3 Discussion of a reement Verification'Test Since this test was conducted in accordance with BN-TOP-I,Revision 1, the verification flow was allowed to stabilize for approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to starting the verification phase of testing.

The verification test ran 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 10 minutes, which is approximately one-half of the CILRT duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 10 minutes.

The verification test summary is contained in Appendix F.

Agreement between the verification test and CILRT test results was attained immediately and held constant throughout the verification test.

This phase was completed in the minimum time required by BN-TOP-1 criteria.

6.4 Discussion of "As Found" Leak Rate Exceedin Technical S ecifications Application of "leakage savings" per IE Notice 85-71 resulted in a technical failure of the CILRT before the test was performed.

A single penetration leakage path (X Heating and Ventilation system drywell discharge) was responsible for this failure. During performance of LLRT's, isolation valves 2-FCV-64-29 (inboard isolation valve) and 2-FCV-64-30 (outboard isolation valve) were discovered to be leaking 1046.75 SCFH and 1161.60 scfli, respectively.

This resulted in a minimum path leakage which singlehandedly exceeded the Technical Specification leakage limit for the CILRT of approximately 820 SCFH (0.75 Lg.

During disassembly of these valves following the leakage failure, products of corrosion were noted to be present on the valve seats in sufficient quantity to interfere with seating of the valves.

This condition is being addressed on BFPER940910.

FCV 64-29 and 30 were new replacement valves installed during the Unit 2, cycle 5 refueling outage.

These valves, along with the remaining similar system 64 valves that have been recently replaced, were satisfactorily retested prior to CILRT performance and again just prior to unit startup.

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Future leakage performance of the Heating and Ventilation System isolation valves will be monitored through the LLRT program. Any future failures that occur will be addressed through the plant corrective action program.

Since the LLRT program is performed at least once per operating cycle and is component specific, it will more readily determine significant component problems which may occur than would performance of additional CILRT's.

7.0 CONCLUSION

S The reactor containment building integrated leak rate test performed on BFN Unit 2, cycle 7, recorded a calculated TTLR of 0.332030 percent of containment air mass per day, which clearly demonstrates the leak-tight integrity of Unit 2.

The total 95 percent UCL "As found" of 5.233189 percent per day exceeded the limitof 1.5 percent of containment air mass per day as prescribed under BFN Technical Specifications due to LLRT "leakage savings" contributions.

The total 95 percent UCL "AS Left" of 0.376989 percent per day was less than 25 percent of that allowed by Technical Specifications.

The cause of the As Found excessive "leakage savings" is being addressed through the local leak rate test program.

TVA concludes that conditions which caused the leakage to exceed the leakage limit set forth in the technical specifications can best be addressed through local leak rate testing.

TVA therefore proposes to continue with the normal CILRT testing schedule.

The next CILRT is scheduled to be performed during the Unit 2, cycle 9 refueling outage which is currently scheduled for March, 1998.

The technique of multicompartment modeling coupled with a computer-based data acquisition system yielded immediate results that accurately measured and displayed the Unit 2 containment leak rate.

13

e

APPENDIX A Stabilization Phase Graphs and Tabular Data Contents:

Temperature stabilization criteria - samples 184 to 211 P~ae Total Containment Mass Drywell Mass Torus Mass Drywell Average Pressure Torus Average Pressure Drywell Average Temperature Torus Average Temperature Drywell Average Vapor Pressure Torus Average Vapor Pressure Containment Calculated Values 15 16 17 18 19 20 21 22 23 24 Tabular Data - Review Temperature Stabilization Criteria 26 14

0

94550 Containment Mass Browns Ferry Nuclear Plant Unit 2 94540 94530 94520 94510 94500 94490 94480 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

51100 Drywell Mass Browns Ferry Nuclear Plant Unit 2 51000 50900 50800 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 4.0

43610 Torus Mass Browns Ferry Nuclear Plant Unit 2 43600 43590 43580 b

43570

- m 43560 43550 43540 43530 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5

65.10 Drywell Average Pressure Browns Ferry Nuclear Plant Vnit 2 65.00 p

~

s I

a 64.SO 64.80 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5

65.10 Torus Average Pressure Browns Ferry Nuclear Plant Unit 2 65.00 P

s I

a 64.90 64.80 0.0 0.5 1.0

. 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

100.10 Drywell Average Temperature Browns Ferry Nuclear Pfant Unit 2 100.00 99.90 99.80 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

87.0 Torus Average Temperature Browns Ferry Nuclear Plant Unit 2 86.0 85.0 84.0 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

0.640 Drywell Average Vapor Pressure Brovrns Ferry Nuclear Plant, Unit 2 0.630 0.620 p

S I

a 0.610 0.600 0.590 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5

0.540 Torus Average Vapor Pressure Browns Ferry Nuc ear plant Unit 2 0.530 P

S I

a 0.520 0.510 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

0 L

1

&pl rE i)

STABILIZA.'IIONPHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 Page1 of 2 RDG TIME MASS TEMP VAPOR PRESSURE PRESS 184 01:45:05 Drywell TOI'LIS TOTAL 51012.68 43534.70 94547.38 100.069 86.750 0.5932 65.0310 0.5364 65.0408 185 01:50:05 186 01:59:05 Drywell TOI'LIS TOTAL Dryweil Torus TOTAL 51005.34 43541.38 94546.73 50993.78 43550.58 94544.37 100.034 86.565 100.003 86.337 0.5937 0.5359 0.5965 0.5338 65.0183 65.0284 65.0029 65.0129 187 02:08:06 Drywell TOI'LIS TOTAL 50985.27 43555.17 94540.45 99.978 0.5993 86.182 0.5344 64.9921 65.0020 188 02:17:06 189 02:26:06 190 02:35:07 191 02:44:07 192 02:53:07 Dryweil TOI'LIS TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell TorLls TOTAL Drywell TOI'LIS TOTAL 50978.17 43558.82 94536.99 50971.77 43561.57 94533.34 50966.82 43564.17 94530.99 50960.90 43566.58 94527.48 50956.92 43569.52 94526.44 99.967 86.060 99.953 85.962 99.934 85.877 99.933 85.798 99.910 85.720 0.6007 0.5348 0.6030 0.5348 0.6049 0.5343 0.6062 0.5338 0.6080 0.5329 64.9833 64.9934 64.9759 64.9859 64.9693 64.9792 64.9631 64.9730 64.9572 64.9672 193 03:02:07 194 03:11:08 Drywell Torus TOTAL Drywell Torus TOTAL 50950.12 43571.50 94521.62 50946.24 43574.16 94520.40 99.921 0.6098 85.653 0.5322 99.908 0.6109 85.583 0.5313 64.9517 64.9616 64.9464 64.9563 195 03:20:08 Drywell TorLls TOTAL 50941.35 43577.06 94518.41 99.904 85.512 0.6124 0.5303 64.9412 64.9511 196 03:29:08 Drywell TOI'LIS TOTAL 50936.13 43579.25 94515.39 99.903 0.6141 85A50 0.5294 64.9363 64.9462 197 03:38:09 198 03:47:09 Drywell TOI'LIS TOTAL Drywell TOI'LIS TOTAL 24 50932.16 43581.65 94513.81 50928.01 43583.90 94511.90 99.894 85.388 99.891 85.328 0.6153 0.5285 0.6162 0.5275 64.9314 64.9415 64.9267 64.9368

(". t~

l

STABILIZATIONPHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 PQQB 20f 2 RDC TlME MASS TEMP VAPOR PRESSURE PRESS 199 03:56:09 200 04:05:10 201 04'.14:10 202 04:23:10 203 04'32:10 204 04:41:11 205 04:51:11 206 05:01:11 Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAI.

Drywell Torus TOTAL Drywell Tol'Lls TOTAL Drywell Torus TOTAI.

Drywell Tol'Lls TOTAL 50924.03 43586.32 94510.35 50919.43 43588.24 94507.67 50914.39 43589.94 94504.34 50910.59 43592.19 94502.78 50906.92 43594.50 94501.42 50902.21 43596.27 94498.48 50897.58 43598.41 94495.99 50894.01 43600.55 94494.56 99.884 85.268 99.885 85.213 99.890 85.160" 99.886 85.105 99.880 85.050 99.882 85.000 i 99.886 84.943 99.879 84.888 0.6175 64.9222 0.5266 64.9324 0.6189 64.9178 0.5259 64.9280 0.6199 64.9131 0.525'l 64.9234 0.6212 64.9091 0.5243 64.9194 0.6224 64.9050 0.5233 64.9154 0.6239 64.9008 0.5226 64.9114 0.6252 64.8966 0.5218 64.9070 0.6260 64.8922 0.5209 64.9028 207 05:11:12 Drywell Torus TOTAL 50890.01 99.876 43602.68 84.833 94492.69 0.6272 64.8879 0.5200 64.8985 208 05:21:12 209 05:31:12 210 05:41:13 211 05:51:13 Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL 50886.09 43604.59 94490.68 50881.48 43606.49 94487.97 50876.64 43608.33 94484.97 50873.48 43609.67 94483.15 99.871 84.782 99.876 84.730 99.880 84.680 99.874 84.635 0.6286 64.8839 0.5192 64.8944 0.6297 64.8797 0.5185 64.8904 0.6312 64.8757 0.5177 64.8864 0.6319 64.87'f6 0.5170 64.8824

STABKIZATIONPHASE

'I Mass Point Temperature Stabilization Browns Ferry Nuclear Plant Unit 2 Containment page1 of1 TIME HOURS 01:45 01:50 01:59 02:08 02:17 02:26 02:35 02:44 02:53 03:02 03:11 03:20 03:29 03:38 03:47 03:56 04:05 04:14 04:23 04:32 04:41 04:51 05:01 05:11 05:21 05:31 05:41 05:51 TEMP 94.019 93.916 93.795 93.711 93.650 93.598 93.549 93.512 93.464 93.440 93.401 93.367 93.338 93.305 93.276 93.245 93.221 93.199 93.172 93.144 93.122 93.098 93.070 93.043 93.017 92.996 92.976 92.952 Q3 AVE. DT OVER LAST4 HOURS ITt

- Tt-4I

'F/HR 0.240 Q4 AVE. DT OVER LAST HOUR IT<

Tt 1 I

'F/HR 0.146

'F/HR 0.094 Q4 2

APPENDIXB CILRl'est Phase Graphs (samples 212 to 261)

Contents:

Containment Total Time Leak Rate S UCL Containment Mass Point Leak Rate 8c UCL Total Containment Mass Drywell Mass Torus Mass Drywell Average Pressure Torus Average Pressure Drywell Average Temperature Torus Average Temperature Drywell Average Vapor Pressure Torus Average Vapor Pressure 28 29 30 31 32 33 34 35 36 37 38 27

Calculated Total Time Leak 8 Total Time Leak at UCL Browns Ferry Nuclear Plant Unit 2 Calculated Total Time Leak Total Time Leak at UCL 1.4 1.3 1.0 I

0.8 a

Y 0.6 0.5 1I'I g \\

g

\\

\\

g

'V I

0.3 0.2 0.0 I

I I

I I

I I

I I

I I

I I

I 4'ime - Hours

1 6 Mass Point Leak Mass Point Leak & Mass Point Leak at UGL Brains Ferry Nuclear Plant Unit 2 Mass Point Leak at UCL 1.4 1.3 1.0 I

d 0.8 a

V 0.6 0.5 0.3 0.2 0.0 0

I IlIIII I I I I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I 4

Time - Hours

f 0

94500 Containment Mass Browns Ferry Nuclear Plant Unit 2 I

b 94400 94300 4

Time - Hours

F

%900 Drywell Mass Brains Ferry Nuclear Plant Unit 2 I

b 50800 m

50700 0

4 Time - Hours

43650 Torus Mass Browns Ferry Nuclear Plant Unit 2 43640 I

b 43630 Al 43620 43610 0

3 4

Time - Hours

64.90 Drywe1l Average Pressure Browns Ferry Nuclear Plant Unit 2 P

64.80 a

64.70 0

4 Time - Hours

64.90 Torus Average Pressure Browns Ferry Nuclear Plant Unit 2 p

64.80 a

64.70 0

Time - Hours

99.940 Drywell Average Temperature

.Browns Ferry Nuclear pfant Unit 2 99.930 99.920 99.910 99.900 99.890 99.880 99.870 4

Time - Hours

85:0 Torus Average Temperature Browns Ferry Nuclear Plant Unit 2 0

84.0 83.0 4

Time - Hours

0.670 Drywell Average Vapor Pressure Browns Ferry Nuclear Plant Unit 2 0.660 P

0.650 a

0.640 0.630 0

4 Time - Hours

0.520 Torus Average Vapor Pressure Browns Ferry Nucfear plant Unit 2 0.510 oo p

s I

a 0.500 0.4SO 0

4 Time - Hours 5

APPENDIX C CILRTTest Phase Tabular Data (samples 212 to 261)

Contents:

CILRTTotal Time Leak Rate Analysis CILRTMass Point Leak Rate Analysis BN-TOP-1 Termination Criteria CILRT Mass Point Termination Criteria CILRT Containment Calculated Values 40 42 45 46 39

Cl12G'EST PHASE

'I Total Time Leak Rate Analysis Browns Ferry Nuclear Plant Unit 2 Page1 of 2 RDG TIME (MINUTES)

MEASURED LEAK CALCULATEDLEAK UCL LEAK(WT (WT %/DAY)

(WT %/DAY)

%/DAY) 212 213 214 215 216 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 0.00 10.02 20.02 30.02 40.03 50.03 60.03 70.05 8O.O5 90.05 100.07 110.07 120.07 130.08 140.08 150.08 160.10 170.10 180.10 IS0.12 200.12 210.12 220.13 230.13 240.13 250.15 260.15 270.15 280.17 290.17 300.17 310.18 320.18 330.18 340.20 350.20 360.20 370.22 380.22 390.22 400.23 410.23 420.23 430.25 440.25 450.25 0.458526 0.385613 0.362623 0.334821 0.359156 0.344319 0.349079 0.357192 0.355690 0.351606 0.345147 0.343902 0.337263 0.337908 0.338089 0.340121 0.342959 0.339833 0.341028 0.341850 0.339511 0.334061 0.339687 0.340584 0.335713 0.340314 0.334607 0.339605 0.340238 0.340027 0.339457 0.338449 0.342732 0.341013 0.340598 0.343589 0.340266 0.340671 0.337478 0.340547 0.339322 0.341795 0.342372 0.340812 0.341658 0.385613 0.354302 0.326264 0.330244 0.325738 0.326187 0.330477 0.333171 0.333925 0.332660 0.331560 0.329068 0.32746?

0.326383 0.326090 0.326570 0.326407 0.326575 0.326937 0.326884 0.325961 0.326138 0.326473 0.326063 0.326412 0.325948 0.326244 0.326616 0.326944 0.327185 0.327303 0.327923 0.328303 0.328618 0.329236 0.329464 0.329726 0.329660 0.329905 0.330025 0.330372 0.330750 0.330971 0.331255 0.551746 0.417481 0A47587 0.425035 0.418178 0.419574 0.417398 0.412687 0.405986 0.400510 0.393923 0.389115 0.385443 0.383193 0.382265 0.380514 0.379378 0.378619 0.377349 0.375032 0.374289 0.373826 0.372396 0.372064 0.370673 0.370358 0.370178 0.369958 0.369642 0.369181 0.369450 0.369386 0.369247 0.369552 0.369321 0.369153 0.368577 0.368423 0.368119 0.368132 0.368199 0.368063 0.368022 40

CILRTTEST PHASE Total Time Leak Rate Analysis Browns Ferry Nuclear Plant Unit 2 Page 2 of 2 RDG TIME (MINUTES)

MEASURED LEAK CALCULATEDLEAK UCL LEAK(WT (WT %/DAY)

(WT %/DAY)

%/DAY) 258 259 260 261 460.27 470.27 480.27 490.28 0.339810 0.341330 0.342227 0.340231 0.331368 0.331606 0.331905 0.332030 0.367768 0.367687 0.367698 0.367489

~;

ClIRTTEST PHASE Mass Point Leak Rate Analysis Browns Ferry Nuclear Plant Unit 2 Page1 of 2 RDG TIME (MINUTES)

NORM. MASS MEASURED LEAK UCL LEAK(WT (WT %/DAY)

%/DAY) 212 213 214 215 216 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 0.00 10.02 20.02 30.02 40.03 50.03 60.03 70.05 80.05 90.05 100.0?

110.07 120.07 130.08 140.08 150.08 160.10 170.10 180.10 190.12 200.12 210.12 220.13 230.13 240.13 250.15 260.15 270.15 280.17 290.17 300.17 310.18 320.18 330.18 340.20 350.20 360.20 370.22 380.22 390.22 400.23 410.23 420.23 430.25 440.25 450.25 1.000000 0.999968 0.999946 0.999924 0.999907 0.999875 0.999856 0.999830 0.999801 0.999778 0.999756 0.999736 0.999713 0.999695 0.999671 0.999648 0.999622 0.999595 0.999575 0.999550 0.999525 0.999505 0.999489 0.999457 0.999432 0.999417 0.999385 0.999372 0.999339 0.999314 0.999291 0.999269 0.999247 0.999214 0.999194 0.999172 0.999141 0.999125 0.999100 0.999085 0.999053 0.999033 0.999003 0.998977 0.998958 0.998932 0.458526 0.385634 0.357636 0.330782 0.341072 0.337147 0.338887 0.344704 0.347609 0.347705 0.345178 0.343158 0.339443 0.337199 0.335774 0.335479 0.336199 0.335933 0.336120 0.336535 0.336327 0.334901 0.335088 0.335475 0.334782 0.335189 0.334414 0.334755 0.335182 0.335524 0.335731 0.335750 0.336491 0.336865 0.337132 0.337833 0.337954 0.338126 0.337827 0.337996 0.337984 0.338307 0.338673 0.338805 0.339031 0.746106 0.430710 0.380495 0.373146 0.359067 0.354762 0.358278 0.358686 0.356621 0.352975 0.350015 0.346412 0.343621

, 0.341544 0.340552 0.340747 0.339995 0.339768 0.339851 0.339341 0.337990 0.337919 0.338102 0.337298 0.337549 0.336731 0.336935 0.337257 0.337491 0.337584 0.337489 0.338280 0.338589 0.338780 0.339534 0.339569 0.339666 0.339317 0.339422 0.339341 0.339638 0.339992 0.340071 0.340261 42

0

CERT TEST PHASE Mass Point Leak Rate Analysis Browns Ferry Nuclear Plant Unit 2 Page 2 of 2 RDC TIME (MINUTES)

NORIVI. MASS MEASURED LEAK UCL LEAK(WT (WT %/DAY)

%/DAY) 258 259 260 261 460.27 470.27 480.27 490.28 0.998914 0.998885 0.998859 0.998842 0.339011 0.339177 0.339435 0.339439 0.340188 0.340317 0.340555 0.340514 43

CKRrTEST PHASE BN-TOP-1 Termination Criteria Browns Ferry Nuclear Plant Unit 2 Page1 of1 BN-TOP-1 Termination Criteria Evaluation for Reading ¹ 261

1. The Trend Report based on Total Time calculations shall indicate that the magnitude ofthe calculated leak rate is tending to stabilize at a value less than the maximum allowable leak rate (<.75La).

Required Value: 1.500000 %/day Actual Value: 0.332030 %/day

{Note: The magnitude of the calculated teak rate may be increasing slightly as it tends to stabilize.

In this case the average rate of increase of the calculated leak rate shall be determined from the accumulated data over the last five hours or last twenty data points, whichever provides the most points. Using this average rate, the calculated leak rate can then be linearly extrapolated to the 24th hour data point.

Ifthis extrapolated value of the calculated leak rate exceeds 75% ofthe maximum allowable leak rate (La) then the leak rate test is continued.)

Required Value: 1.500000 %/day Actual Value: 0.352522 %/day

2. The end of test upper 95% confidence limitfor the calculated leak rate based on Total Time calculations. shall, be less than the maximum allowable leak rate (<.75La)..

Required Value: 1'.500000%/day 'ctual Value: 0.367489%/day

3. The mean ofthe measured leak rates based on Total Time calculations over the last five hours of test or last twenty data points, whichever provides the most data, shall be less than the maximum allowable leak rate {<.75La).

Required Value: 1.500000 %/day Actual Value: 0.340051 %/day

4. Data shall be recorded at approximately equal intervals and in no case at intervals greater than one hour.

Required Intewal: <=1 hr Maximum Actual Interval: 0.17 hr

5. At least twenty (20) data points shall be provided for proper statistical analysis.

Required ¹ Data Points: >>=20 Actual Data Points: 50

6. In no case shall the minimum test duration be less than six (6) hours.

Required Minimum Duration: 6 hr Actual Duration: 8.2 hr

1 IP ~

CKRrTnr pHASE Mass Point Termination Criteria Browns Ferry Nuclear Plant Unit 2 Page% of 1 RDG 212 213 214 215 216 TIME 0.00 10.02 20.02 30.02 40.03 MP UCL

%/clay 0.0000 0.0000 0.7461 0.4307 0.3805 CuAI 11 0.0279 0.9719 8.3822 6.9167 12.4459 10.1047 0.0000 1.0000 2.6485 3.7184 4.6646 Curv 111 Curv 12

'cat 21 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232 233 234 235 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 258 259 260 261 50.03 60.03 70.05 80.05 90.05 100.07 110.07 120.07 130.08 140.08 150.08 160.10 170.10 180.10 190.12 200.12 210.12 220.13 230.13 240.13 250.15 260.15 270.15 280.17 290.17 300.17 310.18 320.18 330.18 340.20 350.20 360.20 370.22 380.22 390.22 400.23 410.23 420.23 430.25 440.25 450.25 460.27 470.27 480.27 490.28 0.3731 0.3591 0.3548 0.3583 0.3587 0.3566 0.3530 0.3500 0.3464 0.3436 0.3415 0.3406 0.3407 0.3400 0.3398 0.3399 0.3393 0.3380 0.3379 0.3381 0.3373 0.3375 0.3367 0.3369 0.3373 0.3375 0.3376 0.3375 0.3383 0.3386 0.3388 0.3395 0.3396 0.3397 0.3393 0.3394 0.3393 0.3396 0.3400 0.3401 0.3403 0.3402 0.3403 0.3406 0.3405 0.0154 0.0513 0.0117 0.0588 0.1797 0.1330 0.0003 0.0577 0.4930 0.9627 1.3022 1.0920 0.4899 0.4816 0.3214 0.1465 0.1745 0.6911 0.4645 0.2157 0.4952 0.2104 0.5746 0.2779 0.0744 0.0064 0.0013 0.0020 0.2093 0.4230 0.6137 1.3264 1.3762 1.5306 0.8136 0.9720 0.8558 1.2933 1.9092 2.0677 2.5129 2.1871 2.5115 3.1760 2.8790

'j.0788 0.9945 0.2916

-0.4650

-0.5571

-0.3514

-0.0129 0.1504 0.3775 0.4222 0.3984 0.3119 0.1914 0.1608 0.1142 0.0681 0.0641 0.1187 0.0873 0.0543 0.0738 0.0445 0.0676 0.0437 0.0211 0.0057

-0.0023

-0.0026

-0.0266

-0.0349

-0.0386

-0.0549

-0.0516

-0.0503

-0.0359

-0.0364

-0.0319

-0.0368

-0.0422

-0.0410

-0.0423

-0.0375

-0.0377

-0.0400

-0.0362 1.5858 1.4585 0.4281 0.6850 0.8222 0.5187 0.0190-0.2213 0.5543 0.6192 0.5838 0.4569 0.2805 0.2356 0.1674 0.0998 0.0940 0.1738 0.1279 0.0795 0.1081 0.0652 0.0989 0.0640 0.0309 0.0083 0.0034 0.0039 0.0390 0.0512 0.0567 0.0805 0.0757 0.0738 0.0526 0.0533 0.0468 0.0540 0.0620 0.0602 0.0622 0.0551 0.0554 0.0587 0.0532 4.7480 5.0370 5.1325 5.0823 5.0783 5.1236 5.2171 5.2912 5.4020 5.4727 5.5192 5.5334 5.5163 5.5239 5.5182 5.5043 5.5061 5.5397 5.5293 5.5129 5.5257 5.5080 5.5217 5.5059 5.4871 5.4707 5.4583 5.4504 5.4233 5.4065 5.3923 5.3667 5.3569 5.3454 5.3462 5.3353 5.3289 5.3139 5.2983 5.2885 5.2764 5.2710 5.2607 5.2482 5.2424 45

CKRF TKSTPHASE.

Containment Calculated Values Browns Ferry Nuclear Plant Unit2-PQQB 1 of 4 RDG TIME MASS TfMP VAPOR PRESSURE PRESS 212 06:01:13 213 06:11:14 214 06:21:14 215 06:31:14 216 06:41:15 217 06:51:15 218 07:01:15 219 07:11:16 220 07:21:16 221 07:31:16 222 07:41:17 223 07:51:17 224

'8:01:17 225 08:11:18 226 08:21:18 Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL 50869.37 43611.37 94480.74 50864.82 43612.91 94477.73 50860.92 43614.76 94475.68 50857.50 43616.10 94473.60 50854.06 43617.89 94471.95 50850.05 43618.90 94468.95 50846.62, 43620.56 94467.18 50843.14 43621.56 94464.70 50839.26 43622.72 94461.98 50835.81 43623.92 94459.73 50832.19 43625.46 94457.66 50828.71 43627.11 94455.82

~ 50825.58 43628.07 94453.65 50823.01 43628.95 94451.96 50819.31 43630.37 94449.68 99.874 84.587 99.881 84.540 99.882 84.492 99.881 84A48 99.876 84.398 99.879 84.358 99.875 84.313 99.875 84.273 99.878 84.233 99.876 84.193 99.879 84.150 99.877 84.105 99.875 84.068 99.870 84.032 99.874 83.990 0.6333 0.5163 0.6342 0.5156 0.6353 0.5148 0.6361 0.5141 0.6370 0.5134 0.6382 0.5128 0.6392 0.5121 0.6399 0.5115 0.6408 0.5110 0.6418 0.5103 0.6426 0.5097 0.6435 0.5091 0.6443

'.5085 0.6447 0.5080 0.6457 0.5074 64.8678 64.8785

. 64.8638 64.8745 64.8601 64.8707 64.8564 64.8669 64.8525 64.8629 64.8488 64.8591 64.8451 64.8555 64.8415 64.8517 64.8378 64.8481 64.8342 64.8445 64.8307 64.8410 64.8271 64.8375 64.8237 64.8340 64.8202 64.8305 64.8169 64.8270

0'

Containment Calculated Values Browns Ferry Nuclear Plant, Unit 2 Page 2 of 4 RDG TIME MASS TEMP VAPOR PRESSURE PRESS 227 08:31:18 228 08:41:19 229 08:5'i:19 230 09:01:19 231 09:11:20 232 09:21:20 233 09:31:20 234 09:41:21 235 09:51:21 236 10:01:21 237 10:11:22 238 10:21:22 239 10:31:22 240 10:41:23 241 10:51:23 Drywell Torlls TOTAL Drywell Tol'LIS TOTAL Drywell Torus TOTAL Drywell Tol'LIS TOTAL Drywell Torus TOTAL Drywell Tol'LIS TOTAL Drywell Tol'LIS TOTAL Drywell Torus TOTAL Drywell Tol'LIS

TOTAl, Drywell Tol'LIS TOTAL Drywell Tol'us TOTAL Drywell Torus TOTAL Drywell TorLls TOTAL Drywell Torlls TOTAL Drywell Tol'LIS TOTAL 47 50816.20 43631.25 94447.45 50812.50 43632.51 94445.01 5OSOS.85 43633.61 94442.47 50806.19 43634.39 94440.58 50802.53 43635.68 94438.20 50799.56 43636.30 94435.86 50796.67 43637.27 94433.94 50794.36 43638.13 94432.49 50790.93 43638.52 94429.45 50787.88 43639.20 94427.08 50785.72 43639.92 94425.64 50782.26 43640.39 94422.65 50780.31 43641.13 94421.43 50776.39 43641.92 94418.31 50773.46 43642.51 94415.97 99.871 0.6465 64.8135 83.957 0.5068 64.8238 99.875 0.6476 64.8104 83.917 0.5062 64.8203 99.883 0.6480 64.8071 83.880 0.5057 64.8171 99.877 0.6487 64.8039 83.847 0.5052 64.8138 99.882 0.6496 64.8006 83.810 0.5046 64.8108 99.885 0.6499 64.7975 83.780 0.5042 64.8077 99.882 0.6508 64.7945 83.745 0.5037 64.8045 99.879 0.6512 64.79'i6 83.713 0.5032 64.8015 99.882 0.6521 64.7885 83.685 0.5027 64.7983 99.885 0.6525 64.7853 83.653 0.5023 64.7951 99.880 0.6529 64.7825 83.623 0.5019 64.7922 99.887 0.6535 64.7796 83.595 0.5014 64.7891 99.878 0.6541 64.7766 83.565 0.5010 64.7862 99.889 0.6549 64.7737 83.533 0.5006 64.7832 99.894 0.6553 64.7709 83.507 0.5001 64.7804

• -6 I

\\

crier msr PHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 PQg930f 4 RDC TIME MASS TEMP VAPOR PRESSURE PRESS 242 11:01:23 243 11:11:24 244 11:21:24 245 11:31:24 246 11:41:25 247 11:51:25 Drywell TorLIs TOTAI.

Drywell Torus TOTAL Drywell TolLIS TOTAL Drywell Torus TOTAL

'rywell Torus TOTAL Drywell TOI'LIS TOTAL 50770.93 43642.84 94413.78 50768.37 43643.28 94411.66 50765.61 43644.03 94409.64 50761.46 43645.04 94406.49 50759.78 43644.84 94404.62 50756.84 43645.64 94402.48 99.893 83.480 99.891 83.453 99.894 83.425 99.909 83.393 99.903 83.375 99.904 83.345 0.6557 0.4997 0.6562 0.4993 0.6567 0.4989 0.6575 0.4984 0.6577 0.4981 0.6585 0.4977 64.7681 64.7774 64.7652 64.7745 64.7625 64.7718 64.7598 64.7690 64.7571 64.7663 64.7543 64.7635 248 12:01:25 Drywell TOI'LIS TOTAL 50753.52 43646.02 94399.54 99.911 0.6592 83.320 0.4975 64.7517 64.7609 249 12:11:26 250 12:21:26 Drywell Torus TOTAL Drywell Torus TOTAL 50751.87 43646.22 94398.09 50749.33 43646.42 94395.76 99.906

'3.298 99.907 83.277 0.6592 0.4971 0.6598 0.4967 64.7491 64.7582 64.7465 64.7556 251 12:31:26 252 12:41:27 Drywell Torus TOTAL Drywell TOI'Us TOTAL 50747.35 43646.99 94394.34 50744.02 43647.30 94391.31 99.904 0.6601 83.252 0.4964 99.914 0.6606 83.230 OA960 64.7440 64.7531 64.7414 64.7506 253 12:51:27 Drywell Torus TOTAL 50742.06 43647.35 94389.41 99.912 83.210 0.6609 0.4958 64.7390 64.7481 254 13:01:27 255 13:11:28 256 13:21:28 Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL 48 50738.76 43647.74 94386.50 50?36.05 43648.04 94384.09 50733.99 43648.31 94382.30 99.925 83.167 0.6621 0.4951 99.925 0.6623 83.147 0.4947 99.920 0.6616 83.188 0.4954 64.7365 64.7457 64.7340 64.7433 64.7317 64.7410

~ ~

0'

CILRTTEST PHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 Page 4 of 4 RDG TIME MASS TEMP VAPOR PRESSURE PRESS 257

'3:31:28 Drywell TOlLIS TOTAL 50731.68 43648.13 94379.81 99.925 83.130 0.6628 0.4945 64.7292 64.7385 258 13:41:29 259 13:51:29 Drywell TOI'LIS TOTAL Drywell TOI'LIS TOTAL 50729.97 43648.16 94378.12 50726.87 43648.55 94375.42 99.925 0.6628 83.113 0.4942 99.929 0.6639 83.092 0.4939 64.7270 64.7363 64.7248 64.7340 260 14:01:29 261 14:11:30 Drywell TOI'LIS TOTAL Drywell TOI'LIS TOTAL 50724.44 43648.46 94372.90 50722.80 43648.50 94371.29 99.933 83.078 99.930 83.060 0.6643 0.4936 0.6645 0.4933 64.7225 64.7320 64.7203 64.7296 49

APPENDIXD Verification Test Phase Gmphs (samples 270 to 295)

Contents:

Containment Total Time Leak Rate with Agreement Limits 51 Containment Mass Point Leak Rate with Agreement Limits 52 Total Containment Mass Drywell Mass Torus Mass Drywell Average Pressure Torus Average Pressure Drywell Average Temperature Torus Average Temperature Drywell Average Vapor Pressure Torus Average Vapor Pressure 53 54 55 56 57 58 59 60 61 50

0 3.5 Calculated Total Time Leak Browns Ferry Nuclear Plant Unit 2 2.3 I

d a

v 1.2 0.0 0.0 0.5 1.0 1.5 2.0

'ime-Hours 2.5 3.0 3.5 4.0

3.5 Mass Point Leak Browns Ferry Nuclear Plant Unit 2 2.3 d

a Y

1.2 0.0 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5

94300 Containment Mass Browns Ferry Nuclear Plant Unit 2 94200 94100 b

m 94000 93900 93800 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

50700 Drywell Mass Browns Ferry Nuclear Plant Unit 2 50600 50500 50400 0.0 0.5 1.0 2.0 Time - Hours 2.5 3.0 3.5 4.0

43700 Torus Mass Browns Ferry Nuclear Plant Unit 2 43600 (A

tA b

m 43500 43400 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

64.70 Dryvrell Average Pressure Browns Ferry Nuclear Plant Unit 2 64.60 P

64.50 i

a 64.40 64.30 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

64.70 Torus Average Pressure Browns Ferry Nuclear Plant Unit 2 64.60 P

64.50 a

64.40 64.30 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

4

100.010 Drywell Average Temperature Browns Ferry Nuclear pfant Unit 2 100.000 99.990 O

99.980 99.970 99.960 99.950 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

82.SO Torus Average Temperature

'Browns Ferry Nuclear Plant Unit 2 82.80 0

F 82.70 82.60 82.50 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

4

0.6760 Drywell Average Vapor Pressure Srowns Ferry Nuclear Plant Unit 2 0.6750 0.6740 0.6730 0.6720 P

S I

a 0.6710 0.6700 0.6690 0.6680 0.6670 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

4 t

4

~ hV

0.4910 Torus Average Yapor Pressure Browns Ferry Nuclear plant Unit 2 0.4900 0.4890 P

0.4880 a

0.4870 0.4860 0.4850 0.0 0.5 1.0 1.5 2.0 Time - Hours 2.5 3.0 3.5 4.0

Verification Test Phase Tabular Data (samples 270 to 295)

Contents:

Verification Total Time Leak Rate Analysis Verification Mass Point Leak Rate Analysis Verification Containment Calculated Values 63 65 62

VERIFICATIONTEST PHASE Total Time Leak Rate Analysis 8rowns Ferry Nuclear Plant Unit 2 Page1 of 1 RDG TIME (MINUTES)

MEASURED LEAK CALCULATEDLEAK UCL LEAK(WT (WT %/DAY)

(WT %/DAY)

%/DAY) 270 271 272 273 274 275 276 277 278 279 280 281 282 283 284 285 286 287 288 289 290 291 292 293 294 295 0.00 10.00 20.02

, 30.02 40.02 50.03 60.03 70.03 80.05 90.05 100.05 110.07 120.07 130.07 140.08 150.08 160.08 170.10 180.10 190.10 200.12 210.12 220.12 230.13 240.13 250.13 2.530679 2.587982 2.571218 2.593086 2.552317 2.555070 2.572566 2.562357 2.555459 2.567240 2.576179 2.577212 2.580120 2.583803 2.566529 2.568720 2.570250 2.565765 2.566230 2.568671 2.561798 2.563884 2.560391 2.554824 2.555320 2.587982 2.583567 2.596312 2.576735 2.567690 2.570517 2.567970 2.563655 2.564751 2.568380 2.571344 2.574356 2.577597 2.575931 2.575075 2.574693 2.573444 2.572489 2.572135 2.570608 2.569661 2.568278 2.566213 2.564499 2.876341 2.705650 2.687264 2.656412 2.643217 2.630944 2.620373 2.616019 2.616052 2.615865 2.616280 2.617391 2.614294 2.611863 2.609971 2.607633 2.605595 2.604120 2.601928 2.60015?

2.598160 2.595841 2.593696 63

vane max TEST PHASE Mass Point Leak Rate Analysis Browns Ferry Nuclear, Plant Unit 2 Page1 of 1 RDG TIME (MINUTES)

NORM. MASS MEASURED LEAK UCL LEAK(WT (WT %/DAY)

%/DAY) 270 271 272 273 274 275 276 277 278 279 280 281 282 283 284 285 286 287 288 289 290 291 292 293 294 295 0.00 10.00 20.02

., 30.02 40.02 50.03 60.03 70.03 80.05 90.05 100.05 110.07 120.07 130.07 140.08 150.08 160.08 170.10 180.10 190.10 200.12 210.12 220.12 230.13 240.13 250.13 1.000000 0.999824 0.999640 0.999464 0.999279 0.999113 0.998935 0.998749 0.998576 0.998402 0.998216 0.998031 0.997851 0.997670-0.997486 0.997325 0.997144 0.996964 0.996791 0.996612 0.996430 0.996262 0.996081 0.995908 0.995740 0.995561 2.530679 2.587995 2.578628 2.592760 2.567725 2.558909 2.565116 2.563068 2.558602 2.561375 2.566981 2.571080 2.574911 2.578819 2.575832 2.574287 2.573561 2.571716 2.570413 2.570027 2.568012 2.566910 2.565228 2.562643 2.560650 2.870827 2.624954 2.621529 2.602939 2.584584 2.584844 2.578134 2.571337 2.572038 2.577536 2.580889 2.584133 2.587705 2.584137 2.581743 2.580199 2.577916 2.576125 2.575193 2.573108 2.571679 2.569899 2.567638 2.565656

I

VER1FICATIONTEST PHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 Page1 of 2 RDC TIME MASS TEMP VAPOR PRESSURE PRESS 270 15:41:33 271 15:51:33 272 16:01:34 273 16 11:34 274 16:21:34 275 16:31:35 276 16:41:35 277 16:51:35 278 17:01:36 279 17:11:36 280 17:21:36 281 17:31:37 282 17:41:37 283 17:51:37 284 18:01:38 Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell TorUs TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Tol'US TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Torus TOTAL Drywell Tol'US TOTAL 65 50650.09 43606.73 94256.82 50640.57 43599.69 94240.26 50630.17 43592.74 94222.91 50620.65 43585.65 94206.30 50609.61 43579.29 94188.90 50600 A8 43572.76 94173.23 50590.63 43565.79 94156.42 50580.15 43558.74 94138.89 50570.72 43551.84 94122.56 50561.03 43545.16 94106.19 50550.58 43538.11 94088.69 50539.80 43531.42 94071.22 50529.99 43524.28 94054.27 50519.69 43517.47 94037.16 50509.73 43510.17 94019.90 99.954 82.878 99.953 82.867 99.961 82.852 99.956 82.838 99.969 82.820 99.964 82.803 99.967 82.790 99.973 82.778 99.973 82.763 99.971 82.748 99.979 82.737 99.988 82.720 99.989 82.710 99.998 82.695 100.000 82.687 0.6679 64.6347 0.4906 64.6439 0.6681 64.6226 0.4904 64.6320 0.6683 64.6106 0.4902 64.6198 0.6687 64.5984 0.4900 64.6076 0.6691 64.5865 0.4897 64.5958 0.6692 64.5745 0.4895 64.5840 0.6695 64.5627 0 4893 64.5720 0.6702 64.5508 0.4892 64.5601 0.6701 64.5387 0.4890 64.5480 0.6705 64.5267 0.4888 64.5362 0.6710 64.5150 0.4886 64.5243 0.6717 64.5030 0.4885 64.5123 0.6720 64.4911 0.4883 64.5005 0.6720 64.4791 0.488'I 64.4885 0.6724 64.4672 0.4880 64.4767

VE<RIFICA'IIONTEST PHASE Containment Calculated Values Browns Ferry Nuclear Plant Unit 2 Page 2of 2 RDG TIME MASS TEMP VAPOR PRESSURE PRESS 285 18:11:38 286 18:21:38 Drywell Tol'us TOTAL Drywell Torus TOTAL 50501.03 43503.66 94004.69 50490.81 43496.85 93987.66 99.991 0.6725 82.667 0.4879 99.997 0.6730 82.653 OA877 64.4552 64.4646 64.4435 64.4528 287 18:31:39 Drywell Torus TOTAL 50480.97 43489.67 93970.65 99.997 82.643 0.6734 0.4876 64.4315 64.4410 288 18:41:39 289 18:51:39 Drywell Torus TOTAL Drywell Torus TOTAL 50471.10 43483.25 93954.35 50461.52 43475.98 93937.50 99.996 0.6741 64.4196 82.625 0.4873 64.4291 99.998 0.6742 64.4078 82.617 0.4872 64.4173 290 19:01:40 Drywell Torus TOTAL 50451.37 43468.98 93920.35 100.002 0.6746 82.605 0.4869 64.3959 64.4054 291 19:11:40 292 19:21:40 Drywell Torus TOTAL Drywell Torus TOTAI.

50442.44 43462.05 93904.49 50432.13 43455.29 93887.42 99.997 82.593 100.005 82.578 0.6744 OA867 0.6746 0.4865 64.3838 64.3936 64.3719 64.3817 293 19:31:41 294 19:41:41 295 19:51:41 Drywell Torus TOTAL Drywell Tol'us TOTAL Drywell Torus TOTAL 50422.84 43448.29 93871.13 50413.22 43442.03 93855.25 50403.45 43435.00 93838.44 99.998 0.6752 82.568 0.4864 99.996 0.6755 82.550 0.4861 99.999 0.6757 82.538 0.4860 64.3600 64.3701 64.3479 64.3584 64.3361 64.3466 66

Verification Analysis Smrnnary TTLRreported during Verification Test ('/today):

MLRreported during Verification Test (A'day):

2.564499 2.560650 TILRreported during CILRT (/a/day):

MLRreported during CILRT ('/a/day):

0.332030 0.339439 Imposed Leak (0/@day) 2.042523 IVRmmum Allowable Leak Rate (/a/day) 2.000000 TILRAgreement:

MLRAgreement 9.50 %

8.93 %

67

0

APPENDIX G Penetntions Not Vented During the CILRT (in service or available forservice)

Penetration Hu@zr X-12 X-42 Residual Heat Removal Shutdown Cooling suction Standby Liquid Control Leak Rate iud%

1.4813 0.2980 Percent per Day 0.0027 0.0005 X-18 X-19 X-9B Floor &, Equipment 0.0000 Sump Drain Floor &, Equipment 0.6697 Sump Drain "B" Feedwater, 2.1557 Reactor Water Cleanup Return, Control Rod Drive Return, Reactor Core Injection Cooling 0.0000 0.0012 0.0039 X-14 Reactor Water Cleanup Suction Total Leakage 0.6766 5.2813 0.0012 0.0095 68

Computer System Block Diagram (Typical) 69

4 IL G

Computer System Block Diagram (Typical)

JB 5945 IHSIDE COHTAItltfEtlT JB 5942 OUTSIDE COtlTAItltiEtlT

~ ~ 4

~

~

TEtfPORARY JUtlCTIOH BOX 220 OHtfS StfART SEHSOR St fART SEtlSOR REPEATER/

REPEATER/

REPEATER/

REPEATER/

REPEATER/

COtmERTER COHUERTER COtPTERTER COtPJERTER COtPiTERTER REPEATER/

CO HVERTER CHO HSTR A/B SELECTOR BOX CH1 BREAKOUT BOX COH1 RS-232 PORT Cotf2 RS-232 PORT LPT1 PORT PRItfARY COHP UTER COtf1 RS-232 PORT COtf2 BACKUP RS-232 CotfP UTER PORT LPT1 PORT PRESSURE SEHSOR PRESSURE SEtlSOR PRESSURE SEHSOR PRESSURE SEtlSOR PRESSURE SEHSOR REPORT PRIHTER DATA PRIHTER TO SP AThSS THROUGH 2-84-627 U-TUBE tfANOtfETER TO DV ATNOS TflROUGH 2-84-631 0-100 PSXG PRESS GAUGE 70

~ ka r.~

VJ y1

~

I

Computer System BlockDiagnln (Typical)

TElfPORARY JUt JCT IOtJ BOX IHSIDE COHTAItJt fEtJT l&

$j(

JB 5942 OUTSIDE COllTAI1ltfEtJT StfART SEHSOR 1

StfART SENSOR StfART SEHSOR SHART SEWSOR StfART SENSOR 8tfART SENSOR StfART SElJSOR StfART SENSOR SlfART SENSOR SlfART SENSOR SHART SElJSOR SHART SENSOR SHART SEHSOR SHART SElJSOR StfART SENSOR Sl;iART SENSOR StfART SENSOR SlfART SEHSOR 220 OHtfS StfART SEHSOR SHART SEllSOR SlfART SEtJSOR 220 OHtf8 SlfART SENSOR StfART SElJSOR SlfART SEllSOR 220 OHtfS SlfART SENSOR StfART SEt JSOR SlfART SENSOR 220 OHtf8 SlfART SENSOR SHART SEtJSOR SliART SEtlSOR 220 OHtfS i~()

Yg

~i)

APP~IXI Compartment Pamneters and Instwment Locations 72

BBBMPMBBMBMTP~

Tempentme (35 Instruments)

Segment Hmzhar Segment

&luna~

Initial Number of Instrument Ill!Ill Bll Drywell (TS 1-29)

I II III IV V

8,300.87 50,332.38 64,058.92 33,378.15 8,099.86 0.050563 0.038323 0.048775 0.022590 0.016446 Torus (TS 30-35)

IX 136,629.53 0.166667 Relative Humidity (10 Instruments)

Drywell (HS 1-7)

VI(I+II) 58,633.25 III 64,058.92 VII(IVXV) 41,478.01 0.119045 0.195099 0.126326 Torus (HS 8-10)

IX 136,629.53 0.333333 Press'4 Instruments)

Drywell (PS 1-2)

Torus (PS 3-4)

IX 136,629.53 VIII 164,170.18 0.500000 0.500000 73

Compufment Volume Weights Containment Drywell Torus Volume 164,170.18 136,629.53 Volumetric K~ight 0.545779 0.454221 Total Containment 300,799.71 1.000000 HS/IS Associations HS 1

HS2 HS 3 HS4 HS 5 HS 6 HS 7 HS 8 HS 9 HS 10 TS 1

TS7 TS 14 TS 17 TS 21 TS 26 TS 29 TS 30 TS 32 TS 34 74

D~ell Instmnlnt Locations po 1800 r r r

.,",~.".g.J;Ma,~:j a) 'QJ.~Q '~ksai<

4~ +>...,

cxgX E d2S'rr A2 04 r r 0'LAN

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rrr J J r r r r rrr J

J r

r J 'Q 45 r r r

r r J rrrr rrrrr rr rrrrrrrrr rrrrrrr rrr

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.. Drywell Instnanent Locations c:4 pc~

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'4/A AIRLOCK Q4'4 OA PLAN - EL.

563'8

TOnm IiptSfrument LOCafiOaS 180'S EL.

AZ.

HS-9 EL.

540'

~

AZ.

125 "~J

/

J J

r Jrr rr J rr Jr rrrr/rrr/r ~

rr/r rrrr/J 32

~ r r Jrrr

////

540>125'S-33 EL.

540'Z.190' J

J /

'll,

'll, P'/r

///

/ J' r HS-10 EL.

540'Z.

260'rrrr r

r TS-34 EL.

540'Z.

260O TS-31

/ /

EL.'540'w w

w AZ 55O

/ rrr r

J/r J rrr

/ / lV

/

HS-0 EL.

540'Z10'rr Q.

r r J J /

TS-35 EL.

540'Z.305' r

rrr

//rr

/rrr r r r Jrr J

r/rr/r JJ rr/rrr rrrr/J rrrrrrrrr/r T$ 3Q EL.

540'Z.

10'o TORUS 79

APPENDIXJ INS'IRUMWTSPI<XXHCATIONS Measured PRGBILee:

Containment Temperature Containment Temperature Containment Relative Humidity Containment Pressure Veri6cation Flow Atmospheric Temperature Atmospheric Pressure Manufacturer Graftel Model No. 9202 LT Gravel Model No. 9202 GmRel Model No. 9203 Paroscientific Model No. 760-100A Teledyne-Hastings Mass Flow Meter Model AHL-25 Graftel Model No. 9202 LT Paroscientific Model No. 760-100A Number 30 10 ci tn Range:

0-114'F Accuracy:

+0.24'F Repeatability:

0.01'F

-Range:

32-130'F Accuracy:

+0.24'F Repeatability:

0.01'F Range:

17-100% RH Accuracy:

~+'F dewpoint Repeatability:

0.1'F Range:

0-100 psia Accuracy:

+0.015% F.S.

Repeatability: +0.005% F.S.

Range:

0-25 SCFM Accuracy:

~+% F.S.

Repeatability

+0.5% F.S.

Range:

0-114'F Accuracy:

+0.24'F Repeatability:

0.01'F Range:

0-100 psia Accuracy:

+0.015% F.S.

Repeatability: +0.005% F.S.

80

Water Level Readings CERT Test Phase Reactor Vessel gI 3='>4 Suppression Chamber glc6HQ Drywell Floor Dm~ump Drywell Equipment Dca~mup 0600 0700 0800 0900 1000 1100 1200 1300 1400 84 83 83 82 80 79 79 78 77

-2.5

-2.5

-2.5

-2.5

-2.4

-2.4

-2.5

-2.5

-2.4 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 15.0 15.0 15.0 15.2 15.5 15.5 15.2 15.2 15.2 Verification Test Phase Reactor Vessel Q ~)

Suppression Chamber QJR%69 Drywell Floor Dra~mp Drywell Equipment Dra~ump 1500 1600 1700 1800 1900 2000 75 73 72 72 71 70

-2.4

-2.4

-2.4

-2.4

-2.3

-2.3 11.0 11.0 11.0 11.0 11.0 11.0 15.2 15.2 15.2 15.2 15.2 15.2

APPENDIX L Summary of Local Leak Rate Tests Introduction Appendix J to 10 CFR 50 and BFN Technical Specifications (TS) require that the total leakage from all penetrations subject to type B and C testing be less than 0.60 L, for return to power operations.

In addition, TS 4.7.A.2.i.requires that the main steam isolation valve leakage be less than 11.5 SCFH, and TS 4.7.A.2.g requires water-tested valves in the water seal system to provide a leakage limiting boundary which will ensure 30-day maintenance of the seal system inventory.

TS 4.7.A.2.g also requires that water-tested valves in seismic Class I lines be tested and reported but not included in the leakage total. In the following listing, leak rates are given in SCFH for air/nitrogen-tested components, and in CFH for water-tested components.

Water-tested valves in the seal system are denoted by "W" after the description,and water-tested valves in seismic Class I lines are denoted by "W/S". Valves which do not have these designations are air-tested valves.

Summaru These tests were conducted during the period from the cycle 5 CILRT until the cycle 7 CILRT. Testing was performed in accordance with plant-approved Surveillance Instructions 2-SI-4.7.A.2.g-l through 2-SI-4.7.A.2.i.3/1.d.2, which are on file at the plant site.

The Cycle 6 and Cycle 7 refueling outage totals are summarized below.

Individual component tests and leak rates are also listed.

Leakage through the Ventilation System (system 64) primary containment isolation valves (measured by LLRTs prior to the CILRT) caused the "leakage savings" total to exceed L, and, when added to the Unit 2, cycle 7 CILRT, resulted in a reportable As-Found test failure.

The original butterfly isolation valves in the ventilation system had a history of leakage and were replaced with new butterfly valves of a different design during the cycle 5 and cycle 6 refueling outages.

After failing the initial cycle 7 LLRTs, these valves were disassembled and inspected. Debris from products of corrosion from inside the ventilation lines was found on the seating surfaces in sufficient quantity to prevent the valves from fully seating. This condition is being addressed through BFPER940910.

The drywell/drywell head flange gasket surface is fitted with double 0-rings to provide a testable seal configuration.

The machined 0-ring grooves are 1 inch in width while the seals are 5/8-inch in diameter.

A small amount of RTV silicon rubber sealant is used to hold the 0-rings in place during head positioning when the head is installed.

When the drywell head was removed for refueling operations during the cycle 7 outage, it was discovered that an apparent excessive amount of RTV sealant had been applied when the head was replaced at 82

the end of the cycle 6 refueling outage.

This excess had overflowed into the LLRT test volume between the two 0-rings and virtually filled the space, resulting in an inability to apply air pressure to the entire circumference of the sealing surfaces.

This resulted in an inadequate LLRT on the flange leak path.

This problem was identified and addressed on BFPER940847 and LER 93-011-00. The maintenance instruction used for installing the drywell head was revised to require the use of a special tool which positions RTV sealant as it is applied and ensures that the amount is not excessive.

In addition, the analysis of this condition performed by TVA concluded that containment integrity had been maintained throughout the operational period since this event occurred.

Unit 2 Cycle 6 As Found

~Max.Path As Left

[Max,P~ath T.S. Limit TypeB 2 C Total Leak Rate (SCFH) 6625.4013 160.1642 655.9 (60/o L,)

Seal System Total Leak Rate 5.0200 4.8523 28.65 Unit 2 Cycle 7 As Found As Left

~Max.Path

[Min. P~ath

~Max.Path M~in.Path T.S. Limit Type B &C Total Leak Rate (SCFH) 8425.5583 2708.2897 153.9838 58.9088'55.9 (60/o Lg Seal System Total Leak Rate (CFH) 4.3439 2.9598 28.65 U2C7 Leakage Savings = 2708.2897 - 58.9088 = 2649.3088 SCFH or 4.8562 %/Day (As Found (As Left min.path) min. path) 83

Type B Testing Smmnary X-7A X-7B X-7C X-7D X-8 Personnel Airlock MS Line A Inboard Bellows MS Line A Outboard Bellows'S Line B Inboard Bellows MS Line B Outboard Bellows MS Line C Inboard Bellows MS Line C Outboard Bellows MS line D Inboard Bellows MS Line D Outboard Bellows MS Drain Line Inboard Bellows MS drain Line Outboard Bellows 40.4101 32.6290 31.5233 36.0586 23.3070 27.7611 24.2910 26.2297 0.0003 0.0003 0.0002 0.0001 0.0007 0.0000 0.0006 0.0000 0.0002 0.0000 0.0014 0.0005 0.0003 0.0008 0.0009 0.0006 0.0004 0.0001 0.0006 0.0004 01/29/93 05/23/93 05/24/93 05/31/93 11/16/93 05/18/94 09/30/94 11/05/94 03/25/93 10/14/94 03/25/93 10/14/94 02/19/93 10/14/94 02/19/93 10/14/94 04/02/93 10/15/94 04/01/93 10/14/94 04/02/93 10/14/94 04/01/93 10/15/94 02/19/93 10/14/94 02/19/93 10/14/94

0 I

A Feedwater Line Inboard Bellows 0.0002 0.0002 03/27/93 10/14/94 AFeedwater Line Outboard Bellows B Feedwater Line Inboard Bellows B Feedwater Line Outboard Bellows RCIC Steam Supply Inboard Bellows RCIC Steam Supply Outboard Bellows HPCI Steam Supply Inboard Bellows

,HPCI Steam Supply Outboard Bellows RHR SDC Suction Inboard Bellows RHR SDC Suction Outboard Bellows RHR LPCI Inboard Bellows RHR LPCI Outboard Bellows 0.0008 0.0005 0.0002 0.0004 0.0007 0.0003 0.0001 0.0002 0.0000 0.0001 0.0003 0.0001 0.0002 0.0001 0.0001 0.0003 0.0003 0.0003 0.0004 0.0002 0.0002 0.0004 03/26/93 10/14/94 03/26/93 10/14/94 03/25/93 10/14/94 04/02/93 10/13/94 04/02/93 10/13/94 03/20/93 10/18/94 03/21/93 10/18/94 02/18/93 10/15/94 02/18/93 10/15/94 02/18/93 10/15/94 02/18/93 10/15/94 RHR LPCI Inboard Bellows RHR LPCI Outboard Bellows 0.0330 0.0316 0.0003 0.0004 02/19/93 10/15/94 02/18/93 10/15/94 85

X-14 X-14 X-16A X-16B RWCU Suction Inboard Bellows RWCU Suction Outboard Bellows CS Injection Inboard Bellows CS Injection Outboard Bellows CS Injection Inboard Bellows CS Injection Outboard Bellows 0.0008 0.0004 0.0015 0.0004 0.0005 0.0004 0.0004 0.0000 0.0002 0.0000 0.0013 0.0000 0.0002 0.0000 02/21/93 04/22/93 10/14/94 02/21/93 04/22/93 10/14/94 02/23/93 10/14/94 02/23/93 10/14/94 02/23/93 10/14/94 02/23/93 10/14/94 X-100A INC Electrical Penetration X-100B Neutron monitor Electrical Penetration X-100C Neutron monitor Electrical Penetration X-100D Neutron monitor Electrical Penetration X-100E Neutron monitor Electrical Penetration X-100F Neutron monitor Electrical Penetration X-100G Neutron monitor Electrical Penetration 0.0000 0.0084 0.0000 0.0390 0.0252 0.0243 0.0571 0.0152 0.0476 0.0183 0.0381 0.0152 0.0395 0.0769 02/09/93 09/08/94 02/08/93 09/08/94 02/15/93 09/15/94 02/15/93 09/14/94 02/15/93 09/14/94 02/15/93 09/15/94 02/08/93 09/09/94 86

X-101A RCP POWER Electrical Penetration X-101B RCP POWER Electrical Penetration 0.0234 0.0525 0.0477 0.0625 02/13/94 10/09/94 02/13/93 10/09/94 X-101C RCP POWER Electrical Penetration X-101D RCP POWER Electrical Penetration 0.0597 0.0393 0.0606 0.0266 02/17/93 10/10/94 02/17/93 10/10/94 X-102 X-103 Thermocouple Electrical Penetration CRD Pos. Ind. Electrical Penetration 0.0715 0.0774 0.1110 0.0547 02/08/93 09/12/94 02/15/93 09/13/94 X-104A INC Electrical Penetration X-104B CRD Pos. Ind. Electrical Penetration X-104C Neutron Monitor Electrical Penetration X-104D Ihermocouple Electrical Penetration X-104E IAC Electrical Penetration X-104F 18'cC Electrical Penetration X-105A Power Electrical Penetration 0.0267 0.0131 0.0667 0.0491 0.0855 0.0327 0.0944 0.0612 0.0011 0.0005 0.0004 0.0004 0.9681 0.0094 0.0097 02/09/93 09/09/94 02/09/93 09/09/94 02/09/93 09/12/94 02/15/93 09/15/94 02/15/93 09/15/94 02/15/93 09/16/94 02/17.93 03/20/93 10/31/94 87

X-105B RCP POWER Electrical Penetration X-105C RCP POWER Electrical Penetration X-105D Power Electrical Penetration X-106A CRD Pos. Ind. Electrical Penetration X-106B Neutron Monitor Electrical Penetration X-107A Neutron Monitor Electrical Penetration X-107B Neutron Monitor Electrical Penetration X-108A Power Electrical Penetration X-108B CRD Pos. Ind. Electrical Penetration 0.0318 0.0312 0.0398 0.0157 0.0004 0.0003 0.0774 0.0771 0.0396 0.0000 0.0557 0.0007 0.0412 0.0123 0.0003 0.0015 0.0661 0.0704 02/13/93 10/09/94 02/17/93 10/10/94 02/08/93 09/12/94 02/08/93 09/06/94 02/08/93 09/07/94 02/09/93 09/07/94 02/09/93 09/07/94 02/09/93 10/09/94 02/15/93 09/13/94 X-109 CRD Pos. Ind. Electrical Penetration 0.0337 0.0327 02/08/93 09/08/94 X-110A Power Electrical Penetration X-110B CRD Pos. Ind. Electrical Penetration 0.0265 0.0398 0.0628 0.0609 02/08/93 10/09/94 02/15/93 09/13/94 X-219 PSC Vacuum Breaker Electrical Penetration 0.0846 0.0833 02/17/93 09/19/94 88

X-1A X-1B X-6 X-35A X-35B X-35C X-35D X-35E Equipment Hatch Equipment Hatch DW Head Access Hatch CRD Hatch TIP Indexer Flange TIP Indexer Flange TIP Indexer Flange TIP Indexer Flange TIP Indexer Flange 0.0085 0.0069 0.0052 25.5656 0.0020 0.0067 0.0578 0.0026 0.0081 0.0027 0.0043 0.0002 0.0001 0.0000 0.0001 0.0001 0.0001 0.0000 0.0001 0.0001 0.0000 0.0001 0.0001 0.0000 0.0001 0.0001 0.0000 0.0001 0.0001 0.0000 0.0001 0.0001 01/30/93 05/16/93 05/31/93 10/02/94 11/03/94 11/09/94 01/30/93 05/03/93 10/02/94 11/03/94 11/09/94 02/08/93 10/23/94 01/30/93 04/05/93 10/06/94 11/01/94 02/07/93 10/18/94 10/25/94 02/07/93 10/18/94 10/25/94 02/07/93 10/18/94 10/25/94 02/07/93 10/18/94 10/25/94 02/07/93 10/18/94 10/25/94 89

- X-35F TIP Indexer Purge Flange X-35G Spare 0.0000 0.0001 0.0001 0.0000 0.0001 0.0001 02/07/93 10/18/94 10/25/94 02/07/93 10/18/94 10/25/94 X-47 Power Operations Test Flange 0.0004 0.0001 02/21/93 10/14/94 X-200A Torus Access Hatch 0.0002 0.0002 0.0002 0.0002 01/29/93 05/23/93 10/03/94 11/05/94 X-200B Torus Access Hatch X-223 Torus Access Hatch Drywell Head 0.0000 0.0000 0.0002 0.0002 0.0002 0.0000 0.0001 0.0001 0.0239 0.0036 0.0049 0.0513 01/29/93 04/15/93 10/06/94 11/05/94 11/10/94 01/29/93 10/18/94 10/26/94 01/29/93 05/15/93 10/01/94 11/04/94 N/A N/A Shear Lug @O'zmith Shear Lug @45'zmith Shear Lug @90'zmith 0.0002 13.8143 0.0001 0.0001 0.0001 0.0000 0.0001 02/18/93 10/16/94 11/01/94 02/18/93 10/16/94 02/18/93

. 10/16/94 90

Shear LugI135'zmith Shear Lug @ 180'zmith 0.0001 02/18/93 0.0001 10/16/94 0.0004 02/18/93 0.0004 10/16/94 Shear Lug 225'zmith 0.0022 0.0001 0.0001 02/19/93 05/08/93 10/16/94 Shear Lug @270'zmith Shear Lug 315'zmith 0.0004 02/19/93 0.0003 10/16/94 0.0008 02/19/93 0.0011 10/15/94 91

'type C Testing Surmnary ZeeleeQfiQQ X-7A 2-FCV-1-14/15 "A"Main Steam Line MSIVs 3.1612 16.4183 9.9435 QQ~e~td 01/31/93 10/03/94 10/06/94 X-78 X-7C 2-FCV-1-26/27 "8" Main Steam Line MSIVs 2-FCV-1-37/38 "C" Main Steam Line MSIVS 17.2122 24.5701 8.0246 7.0726 1320.2634 1409.3449 8.9169 0.0000 01/31/93 02/05/93 02/07/93 10/03/94 01/31/93 02/02/93 05/08/93 10/02/94 2-FCV-1-37 "C" Main Steam Line I.B. MSIV 1317.9368 6.5903 04/01/93 05/08/93 X-7D X-8 2-FCV-1-38 "C" Main Steam Line O.B. MSIV 2-FCV-1-51/52 "D" Main Steam Line MSIVs 2-FCV-1-55/56 Main Steam Drain Isolation Valves 2.3266 1.2067 60.5745 1.6253 151.3793 0.0000 29.5965 0.0000 04/01/93 01/31/93 10/02/94 11/02/94 01/31/93 03/11/93 10/04/94 10/30/94 X-9A 2-CKV-3-558 "A"Feedwater O.B. Isolation Valve 2-CKV-3-554 "A"Feedwater I.B. Isolation Valve 2-FCV-73-45 HPCI Tie-in to "A"Feedwater O.B. Isolation Valve 0.9254 3.6064 0.0000 0.0000 362.8166 1.2221 5.6388 02/15/93 10/08/94 02/15/93 10/08/94 02/16/93 04/10/93 10/08/94 92

P~ UQ X-9B 2-CKV-3-572 "B" Feedwater0.B.

Isolation Valve 2-CKV-3-568 "B" Feedwater I.B. Isolation Valve 2-CKV-69-579 Reactor Water Clean-up Return Tie-in To "B" Feedwater O.B.

Isolation Valve 2-CKV-69-630'eactor Water Clean-up Return Tie-in To "B" Feedwater O.B.

Isolation Valve Laak3hta 25.0184 23.0911 543.3536 6.7528 13.7605 1.0332 890.3141 5.5734 14.6396 2388.3014 0.9306 DahZmfad 02/21/93 10/08/94 02/21/93 04/30/93 05/20/93 10/08/94 02/21/93 04/30/93 06/20/93 10/08/94 10/08/94 2-FCV-71-40 RCIC Tie-in to "B" Feedwater O.B.

Isolation Valve 0.0000 0.0000 0.1919 02/21/93 04/30/93 10/08/94 X-10 X-11 2-CKV-85-576 CRD Return Tie-in to "B" Feedwater O.B. Isolation Valve 2-FCV-71-2/3 RCIC Steam Supply Isolation Valves 2-FCV-73-2/3 HPCI Steam Supply Isolation Valves

/81 0.0000 10.8808 458.5798 0.6017 2.2511 0.7063 0.9248 2.2992 0.0380 0.3683 02/21/93 10/08/94 02/03/93 04/01/93 10/06/94 11/03/94 02/04/93 04/28/93 10/06/94 11/03/94 X-12 2-FCV-74-47 RHR Shutdown Cooling Suction I.B.

Isolation Valve 0.8064 0.0000 1.4813 02/10/93 04/03/93 10/14/94 1 New designated isolation valve replaced 2-CKV-69-579 and 2-CKV-85-576 during cycle 7 refueling outage 93

,P 0

X-12 (cont.)

2-FCV-74-48 RHR Shutdown Cooling Suction O.B.

0.3068 Isolation Valve 15.5056 5.8715 02/10/93 04/13/93 10/14/94 2-CKV-74-661/ RHR Shutdown Cooling Suction 662 Bypass Isolation Valve X-13A 2-FCV-74-53 RHRLoop 1 LPCI O.B. Isolation Valve (W/S) 2-FCV-74-54 RHR Loop 1 LPCI I.B. Isolation Valve (W/S)

X-13B 2-FCV-74-67 RHR Loop 2 LPCI O.B. Isolation Valve (W/S) 2-FCV-74-68 RHR Loop 2 LPCI I.B. Isolation Valve (W/S) 12.9857 36.5673 0.1456 1.0048 0.4637 0.0056 0.3656 0.0113 8.3362 1.5677 1.7673 0.0081 0.0225 0.0028 0.0513 0.1008 0.3713 0.2367 02/10/93 03/29/93 04/03/93 10/14/94 10/18/94 02/10/93 04/1 1/93 10/20/94 02/10/93 04/11/93 10/20/94 02/10/93 04/04/93 05/20/93 10/02/94 02/10/93 04/04/93 10/02/94 X-14 2-FCV-69-1 Reactor Water Cleanup I.B.

Isolation Valve 0.0000 0.0000 0.7153 02/21/93 04/21/93 10/12/94 2-FCV-69-2 Reactor Water Cleanup O.B.

Isolation Valve X-16A 2-FCV-75-'25 CS Loop 1 Injection O.B. Isolation Valve (W/S) 0.0000 0.0000 0.6766 0.0028 0.0028 0.0000 0.0225 02/21/93 04/21/93 10/12/94 02/12/93 04/14/93 10/22/94 11/01/94 94

0 l

~ '

2-FCV-75-26 CS Loop 1 Injection I.B. Isolation Valve (W/S)

X-16B 2-FCV-75-53 CS Loop 2 Injection O.B. Isolation Valve (W/S) 2-FCV-75-54 CS Loop 2 Injection I.B. Isolation Valve (W/S) 17.3571 0.0478 0.0563 0.0378 0.0279 0.0864 0.0468 45.5483 30.7575 02/12/93 04/14/93 10/22/94 02/12/93 03/07/93 10/02/94 02/12/93 10/02/94 10/16/94 X-18 X-19 X-20 X-21 X-22 2-FCV-77-2A Drywell Floor Drain Sump I.B.

Isolation Valve 2-FCV-77-2B Drywell Floor Drain Sump O.B.

Isolation Valve 2-FCV-77-15A Drywell Equipment Sump Drain I.B.

Isolation Valve 2-FCV-77-15A Drywell Equipment Drain Sump O.B.

Isolation Valve 2-ISV-2-1192 Demin. Water I.B. Isolation Valve 2-CKV-2-1383 Demin. Water O.B. Isolation Valve 2-CKV-33-785 Service AirI.B. Isolation Valve 2-ISV-33-1070 Service AirO.B. Isolation Valve 2-CKV-32-336 Control AirI.B. Isolation Valve 0.0585 0.0000 0.0585 0.0000 0.0000 0.6697 1.5173 1.4989 17.0862 1.3776 0.7816 0.0000 0.0000 1.6648 0.3385 0.5508 0.4266 0.8424 0.5083 3.2280 4.4875 0.5401 02/03/93 10/11/94 02/03/93 10/1 1/94 02/03/93 10/11/94 02/03/93 10/11/94 02/07/93 03/06/93 03/08/93 10/06/94 02/07/93 10/06/94 10/18/94 02/07/93 02/07/93 10/18/94 02/15/93 10/1 1/94 10/25/94 10/26/94 95

I 0

X-22 (cont.)

X-23 X-24 2-CKV-32-2163 Control AirO.B. Isolation Valve 2-CKV-84-617 Containment Atmosphere Dilution Tie-in to Control Air 2-FSV-84-49/'ontainment Atmosphere Dilution 686 Tie-in to Control Air 2-FCV-70-47 Reactor Building Closed Cooling Water Isolation Valve 2-CKV-70-506 Reactor Building Closed Cooling Water Isolation Valve 0.5878 1.1799 0.8870 0.2860 1.9969 0.0000 0.3816 0.0000 0.0000 0.0000 0.0000 0.1800 02/15/93 10/11/94 10/25/94 02/15/93 04/19/93 05/07/93 10/11/94 02/14/93 04/15/93 10/06/94 02/14/93 10/06/94 X-25 2-FCV-64-18 Flange Ventilation Supply Isolation Valve I.B. Flange 0.6537 0.0000 0.0001 0.0000 0.0000 02/01/93 03/27/93 10/02/94 11/17/94 11/30/94 X-25 X-25 X-25 2-FCV-76-18 Drywell Inerting Supply Flange Isolation Valve I.B. Flange 2-FSV-84-8A CAD I.B. Isolation Valve 2-CKV-84-600 CAD O.B. Isolation Valve 2-FSV-84-8D CAD I.B. Isolation Valve 0.0447 0.0000 0.0001 332.7828 0.0000 398.3538 0.0964 0.1319 0.0445 0.0749 237.0962 0.0000 0.0904 01/31/93 04/09/93 10/17/94 02/01/93 04/29/93 10/05/94 11/01/94 02/01/93 04/29/93 10/05/94 02/01/93 04/29/93 10/05/94 1 Valves replaced 2-CKV-84-617 during Cycle 6 refueling outage 96

X-25 (cont.)

2-CKV-84-602 CAD O.B. Isolation Valve 0.0000 0.0000 0.0357 02/01/93 04/29/93 10/05/94 X-25/

2-FCV-64-17/

Ventilation Supply Isolation 205 18/19/76-24 Valves X-25/

2-FCV-76-17/

Containment Inerting Supply 205 18/19 Isolation Valves 154.0453 4.8841 2809.2329 3.4781 4.7960 3.7453 2.5352 1.9711 02/01/93 04/04/93 10/02/94 11/17/94 11/30/94 01/31/93 04/09/93 10/17/94 X-26 X-26

. X-26/

231 X-27F X-27F 2-FCV-64-29 Ventilation Exhaust Isolation Flange Valve I.B. Flange 2-FCV-64-31 Ventilation Exhaust Isolation Flange Valve I.B. Flange 2-FCV-64-29/

Ventilation Exhaust Isolation 30/32/33/84-19 Valves 2-FSV-76-49 H,O~ Sampling I.B. Isolation Valve (Analyzer A, Drywell Sample) 2-FSV-76-50 Hzg Sampling O.B. Isolation Valve (Analyzer A, Drywell Sample) 0.0000 0.0000 0.0000 0.0000 0.0000 0.0001 1553.6940 7.1790 2261.2839 8.6670 0.0000 0.1218 0.0000 0.1115 02/02/93 04/09/93 10/05/94 10/28/94 02/02/93 10/10/94 02/02/93 04/09/93 10/05/94 10/28/94 02/05/93 10/18/94 02/05/93 10/18/94 X-35A 2-FCV-94-501 TIP Isolation Valve X-35B 2-FCV-94-502 TIP Isolation Valve X-35C 2-FCV-94-503 TIP Isolation Valve 0.0000 0.0000 0.0000 0.2649 0.0000 0.0000 02/07/93 10/16/94 02/07/93 10/16/94 02/07/93 10/16/94 97

0

X-35D 2-FCV-94-504 TIP Isolation Valve X-35E 2-FCV-94-505 TIP Isolation Valve X-35F 2-CKV-76-653 TIP Nitrogen Purge Isolation Valve 0.0000 0.0000 0.0000 0.0000 0.3618 0.0000 02/07/93 10/16/94 02/07/93 10/16/94 02/07/93 10/17/94 X-37C 2-CKV-68-508 CRD Seal Water to RCP "A"I.B.

Isolation Valves 2-CKV-68-550 CRD Seal Water to RCP "A" O.B.

Isolation Valves 0.0000 0.0000 0.0000 0.0000 02/14/93 10/03/94 02/14/93 10/03/94 X-38C 2-CKV-68-523 CRD Seal Water to RCP "B" I.B.

Isolation Valves 2-CKV-68-555 CRD Seal Water to RCP "B" O.B.

Isolation Valves X-39A 2-FCV-74-74 RHR Loop 2 Containment Spray O.B. Isolation Valve (W/S) 2-FCV-74-75 RHR Loop 2 Containment Spray I.B. Isolation Valve (W/S)

X-39B 2-FCV-74-60 RHR Loop 1 Containment Spray O.B. Isolation Valve (W/S) 2-FCV-74-61 RHR Loop 1 Containment Spray I.B. Isolation Valve (W/S)

X-40B-B 2-FSV-43-70 Post-Accident Sampling Isolation Valve 0.0000 0.0000 0.0000 0.0000 0.0211 0.5231 0.1996 0.0253 0.0281 0.0956 0.0197 1.2756 1.1739 0.0029 0,0084 1.3204 0.1946 5.2063 0.0324 02/14/93 10/03/94 02/14/93 10/03/94 02/1 1/93 10/04/94 10/20/94 02/11/93 10/04/94 10/20/94 02/12.93 10/21/94 10/30/94 02/12/93 10/21/94 02/06/93 04/23/93 10/09/94 10/21/94 98

X-41 2-FCV-43-13 RCP Sample I.B. Isolation Valve 0.0000 0.0000 02/17/93 10/11/94 X-42 X-48 2-FCV-43-14 RCP Sample O.B. Isolation Valve 2-CKV-63-525 Standby Liquid Control I.B.

Isolation Valve 2-CKV-63-526 Standby Liquid Control O.B Isolation Valve 2-FCV-32-62/63 Drywell Control AirSuction Isolation Valves 0.0000 0.0000 0.0000 0.2980 1.3010 0.5366 1.5705 1.1658 02/17/93 10/11/94 02/13/93 10/14/94 02/13/93.

10/14/94 02/14/93 10/10/94 X-50A/D 2-FSV-90-254A/'adiation Monitoring Suction 254B/255 Isolation Valves 2-FSV-90-254A Radiation Monitoring Suction I.B. Isolation Valve 2-FSV-90-254B. Radiation Monitoring Suction I.B. Isolation Valve 2-FSV-90-255 Radiation Monitoring Suction O.B. Isolation Valve X-50B 2-CKV-32-2516 Control AirI.B. Isolation Valve 2-CKV-32-2521 Control AirO.B. Isolation Valve 0.0551 0.0000 0.0514 0.0000 0.1619 0.1350 0.1225 0.0000 0.0000 0.0000 0.0327 02/05/93 04/20/93 10/09/94 04/20/93 10/09/94 04/20/93 10/09/94 02/16/93 10/10/94 02/16/93 10/10/94 2-CKV-84-680 Containment Atmosphere Dilution 0.0000 Tie-in to Control Air 02/16/93 1 Valves replaced with new valves during Cycle 6 refueling outage 99

'I P

0 t

2ggg~t X-50B 2-FSV-84-48/'ontainment Atmosphere Dilution (cont.)

683 Tie-in to Control Air X-50C 2-FSV-90-257A/

Radiation Monitoring Return 2578 O.B. Isolation Valve 2-FSV-90-257A Radiation Monitoring Return O.B. Isolation Valve 2-FSV-90-257B Radiation Monitoring Return I.B. Isolation Valve 5.8792 0.0000 0.0000 0.0550 0.8828 0.6642 0.7823 2.2792 0.9157 04/24/93 05/03/93 10/10/94 02/05/93 04/20/93 10/09/94 04/20/93 10/09/94 10/25/94 X-52C 2-FSV-76-59 2-FSV-76-60 X-205 2-FCV-Q-19 H,Q Sampling I.B. Isolation Valve (Analyzer A, Drywell Sample)

H~O~ Sampling O.B. Isolation Valve (Analyzer A, Drywell Sample)

Ventilation Supply Isolation Valve I.B. Flange 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0001 0.0000 0.0000 02/04/93 10/18/94 02/04/93 10/18/94 02/01/93 04/04/93 10/02/94 11/17/94 11/30/94 2-FCV-Q-20/

Reactor Building-to-Torus Vacuum 800 Breaker Isolation Valves 2-FCV-64-20 Reactor Building-to-Torus Vacuum Breaker Isolation Valve I.B. Flange 0.2451 0.0000 0.3672 15.8548 0.0000 0.0000 0.0001 0.0001 02/01/93 04/08/93 10/04/94 11/05/94 02/01/93 04/08/93 10/04/94 11/05/94 1 Valves replaced 2-CKV-84-680 during Cycle 6 refueling outage 2 Valves replaced with new valves during Cycle 6 refueling outage 100

f 4

0 I

. X-205 2-FCV-64-20 Reactor Building-to-Torus Vacuum (cont.)

Breaker Isolation Valve Shaft Seals 52 6000'0/01/93 2-FCV-64-21/

Reactor Building-to-Torus Vacuum 801 Breaker Isolation Valves 2-FCV-64-21 Reactor Building-to-Torus Vacuum Breaker Isolation Valve I.B. Flange 2-FCV-221/222~

Hardened Wetwell Vent Isolation Valves 2-FCV-222'ardened Wetwell Vent I.B.

Isolation Valve Flange 2-FCV-64-31/34 Ventilation Exhaust Isolation Valves

/139/140/84-20 2-FCV-76-19 Torus Inerting Supply Flange Isolation Valve I.B. Flange 2-FSV-84-8B CAD I.B. Isolation Valve 2-CKV-84-601 CAD O.B. Isolation Valve 0.1156 0.6543 0.0000 0.0000 0.0000 0.0001 0.0549 0.0325 0.0000 0.0001 0.4622 0.4571 0.0000 0.0000 0.0000 0.0000 0.0001 218.5788 0.0000 251.9217 0.0000 0.0000 0.0000 0.0000 02/01/93 04/09/93 10/04/94 02/01/93 04/09/93 10/04/94 04/20/93 10/04/94 04/20/93 10/04/94 02/02/93 07/12/93 07/26/93 10/10/94 01/31/93 04/09/93 10/17/94 02/01/93 04/30/93 10/05/94 11/01/94 02/01/93 04/30/93 10/05/94 1 New Valve 2-FCV-64-20 was oriented such that the shaft seals were not in the LLRTboundary.

Leakage shown is maximum calculated value based on shaft-to-valve body clearance. Valve was reoriented during the U2C7 refueling outage.

2 Line and valves added during cycle 6 refueling outage 101

X-205 2-FSV-84-8C CAD I.B. Isolation Valve (cont.)

2-CKV-84-603 CAD O.B. Isolation Valve X-210A 2-CKV-12-738'uxiliary Boiler Tie-in to torus I.B. Isolation Valve (W) 2-CKV-12-741'uxiliary Boiler Tie-in to torus O.B. Isolation Valve (W)

X-210A 2-FCV-71-34 RCIC Minimum Flow I.B.

Isolation Valve (W) 191.4697 0.0000 0.0000 0.0000 0.1058 0.1230 0.0000 0.0000 0.0034 0.0035 0.0000 Dab~4 02/01/93 05/05/93 10/05/94 02/01/93 05/05/93 10/05/94 01/30/93 01/30/93 02/03/93 03/15/93 10/06/94 X-210A X-210B 2-CKV-71-547 RCIC Minimum Flow O.B.

Isolation Valve (W) 2-FCV-73-30 HPCI Minimum Flow I.B. Isolation Valve (W) 0.0035 0.0105 0.0000 0.0000 0.0094 0.0070 02/03/93 10/06/94 02/04/93 03/15/93 10/07/94 11/03/94 2-CKV-73-559 HPCI Minimum Flow O.B. Isolation Valve (W)

X-211A 2-FCV-74-57/

RHR Loop 1 Torus Spray Isolation 58/59 Valves (W/S)

X-211B 2-FCV-74-71/

RHR Loop 2 Torus Spray Isolation 72/73 Valves (W/S) 0.0113 0.0047 0.1044 0.0844

) 45.0000 0.6231 0.7839 1.1854 2.4300 2.3478 02/04/93 10/07/94 02/11/93 04/12/93 10/21/94 11/04/94 02/1 1/93 04/13/93 10/04/94 10/16/94 0

1 Valves removed and line terminated during Cycle 6 refueling outage 102

Rc talh Lgg~4e Qg~e~

X-212 2-HCV-71-14/

RCIC Turbine Exhaust Isolation 580 Valves X-212 2-HCV-71-14 RCIC Turbine Exhaust I.B.

(cont.)

Bonnet Isolation Valve Bonnet Flange 2-HCV-71-14 RCIC Turbine Exhaust I.B.

Packing Isolation Valve Packing X-213B 2-ISV-74-722 Torus Drain Isolation Valve (W) 2-ISV-74-722 Torus Drain Isolation Valve Blind Flange Flange (W)

X-214 2-ISV-73-23/

HPCI Turbine Exhaust Isolation 603 Valves 12.3607 29.1611 13.0016 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0323 0.0225 0.0267 0.0000 80.0366 19.4984 56.1357 19.2173 01/31/93 10/05/94 11/03/94 01/31/93 10/05/94 11/03/94 01/31/93 10/05/94 11/03/94 02/08/93 10/10/94 02/08/93 10/10/94 02/01/93 03/01/93 10/07/94 10/31/94 2-ISV-73-23 Bonnet 2-ISV-73-23 Packing HPCI Turbine Exhaust I.B.

Isolation Valve Bonnet HPCI Turbine Exhaust I.B.

Isolation Valve Packing 0.0000 0.0000 0.0000 9.2177 4.7366 0.0000 0.1889 0.0000 02/01/93 03/01/93 10/07/94 02/01/93 03/01/93 03/08/93 10/07/94 10/31/94 X-218 2-FCV-71-59/

RCIC Turbine Exhaust Vacuum 601 Bonnet Breaker Line Valve Bonnet/Packing

&, Packing 2-CKV-71-597 RCIC Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 02/17/93 10/09/94 02/09/93 04/06/93 09/22/94 10/27/94 0

103

k44 l

Zgg~mtg X-218 2-CKV-71-598 RCIC Turbine Exhaust Vacuum (cont,)

Bonnet Breaker Line Valve Bonnet 2-CKV-71-599 RCIC Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 2-CKV-71-600 RCIC Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet X-220 2-FCV-73-64/

HPCI Turbine Exhaust Vacuum 642 Bonnet Breaker Line Valve Bonnet Ec Packing 2-RFV-73-633 HPCI Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 2-RFV-73-634 HPCI Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 2-RFV-73-635 HPCI Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 2-RFV-73-636 HPCI Turbine Exhaust Vacuum Bonnet Breaker Line Valve Bonnet 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0805 0.0000 02/09/93 04/06/93 09/21/94 02/09/93 04/06/93 09/22/94 02/09/93 04/06/93 09/20/94 02/17/93 10/09/94 02/17/93 09/26/94 11/01/94 02/17/93 09/23/94 10/31/94 02/17/93 09/27/94 10/31/94 02/17/93 09/26/94 11/01/94 X-221 2-.SHV-71-32/

RCIC Vacuum Pump Discharge 592 Isolation Valves (W) 0.0023 0.0000 02/08/93 10/08/94 2-SHV-71-32 Bonnet 0 Packing RCIC Vacuum Pump Discharge I.B. Isolation Valve Bonnet and Packing 0.0000 0.0000 02/08/93 10/08/94 X-222 2-ISV-73-24/

HPCI Turbine Exhaust Drain 609 Isolation Valves 0.0038 0.0000 02/08/93 10/09/94 104

X-222 2-ISV-73-24 (cont.)

Bonnet &,

Packing HPCI Turbine Exhaust Drain I.B.

Isolation Valve Bonnet and Packing 0.0000 0.0000 02/08/93 10/09/94 X-225A 2-FSV-43-28A RHR Sample I.B. Isolation Valve 2-FSV-43-28B RHR Sample O.B. Isolation Valve X-225B 2-FSV-43-29A RHR Sample I.B. Isolation Valve 2-FSV-43-29B RHR Sample O.B. Isolation Valve X-226 2-FCV-73-26 HPCI Torus Suction I.B. Isolation Valve (W) 2-FCV-73-27 HPCI Torus Suction O.B. Isolation Valve (W)

X-227A 2-FCV-71-17 RCIC Torus Suction I.B.

Isolation Valve (W) 2-FCV-71-18 RCIC Torus Suction O.B.

Isolation Valve (W) 2-FCV-75-57/58 CS Torus Drain Isolation Valves (W)

X-229B 2-FSV-76-57 H,O2 SamplingI.B. Isolation Valve (Analyzer A, Sample Return to Torus) 0.0023 0.0020 0.0008 0.0017 0.0000 0.0000 0.0000 0.0000 0.3488 0.1278 0.7841 0.0000 0.0306 0.0281 2.4323 0.9939 0.0228 0.0844 0.6570 0.1224 0.0180 0.0127 0.0081 0.0110 4.5840 1.8000 0.0000 0.0000 02/03/93 10/11/94 02/03/93 10/11/94 02/05/93 10/10/94 02/05/93 10/10/94 02/04/93 03/09/93 10/08/94 02!04/93 03/09/93 03/26/93 10/08/93 11/04/94 02/03/93 04/07/93 10/06/94 11/02/94 02/03/93 04/07/93 10/06/94 10/28/94 02/13/93 11/06/94 02/06/93 10/19/94 105

0*

Lcak3h&

DatcZeMl X-229B (cont.)

2-FSV-76-58 X-229D 2-FSV-76-55 2-FSV-76-56 2-FSV-76-68 X-229J 2-FSV-43-40 2-FSV-43-42 X-229K 2-FSV-76-65 2-FSV-76-66 X-229G 2-FSV-76-67 H~O~ Sampling O.B. Isolation Valve (Analyzer A, Sample Return to Torus)

H>O~ Sampling I.B. Isolation Valve (Analyzer A, Torus Sample)

H~O~ Sampling O.B. Isolation Valve (Analyzer A, Torus Sample)

H~O~ Sampling I.B. Isolation Valve (Analyzer B, Sample Return to Torus)

H~O~ Sampling O.'B. Isolation Valve (Analyzer B, Sample Return to Torus)

Post-Accident Sampling Isolation Valve Post-Accident Sampling Isolation Valve H,Q Sampling I.B. Isolation Valve (Analyzer B, Torus Sample)

H~Q Sampling O.B. Isolation Valve (Analyzer B, Torus Sample) 0.0000 0.0325 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 2.9899 1.7066 0.0606 0.0804 0.1471 0.0461 4.3786 6.5624 0.0000 0.0000 0.0000 0.0000 0.0000 02/06/93 10/19/94 02/06/93 10/19/94 02/06/93 10/19/94 02/06/93 10/19/94 02/06/93 10/19/94 02/06/93 04/18/93 05/06/93 10/13/94 02/06/93 05/06/93 10/13/94 10/26/94 11/03/94 02/06/93 10/19/94 02/06/93 10/19/94 X-231 2-FCV-64-32 Ventilation Exhaust Isolation Valve I.B. Flange 0.0000 0.1713 0.0000 02/02/93 10/05/94 10/28/94 X-231 2-FCV-64-34 Ventilation Exhaust Isolation Valve I.B. Flange 0.0000 0.0001 02/02/93 10/10/94 N/A 2-FSV-43-50 Post-Accident Sampling Isolation Valve (W) 0.0006 0.0015 02/06/93 10/18/94 106

0

2-FSV-43-56 Post-Accident Sampling Isolation Valve (W) 0.0000 0.0015 02/06/94 10/18/94 N/A N/A 2-CKV-74-792 RHRLoop 1 keep fillO.B. Isolation 0.0000 Valve (W) 0.0000 2-CKV-74-804 RHRLoop 1 keep fillI.B. Isolation 13.5000 Valve (W) 0.0000 0.0000 02/12/93 10/04/94 02/12/93 02/24/93 10/04/94 N/A N/A N/A 2-CKV-74-802 RHR Loop 2 keep fillO.B. Isolation Valve (W) 2-CKV-74-803 RHR Loop 2 keep fillI.B. Isolation Valve (W) 2-CKV-75-606 CS Loop 1 keep fillI.B. Isolation Valve (W) 2-CKV-75-607 CS Loop 1 keep fillO.B. Isolation Valve (W) 2-CKV-75-609 CS Loop 2 keep fillI.B. Isolation Valve (W) 2-CKV-75-610 CS Loop 2 keep fillO.B. Isolation Valve (W) 0.0035 0.0128 0.0129 0.0055 0.0023 0.0008 0.0000 0.0045 0.0000 0.7594 0.0098 0.0000 0.7941 0.0120 02/12/93 10/22/94 02/12/93 10/22/94 02/12/93 10/22/94 02/12/93 10/22/94 02/12/93 10/04/94 10/12/94 02/12/93 10/04/94 10/12/94 107

LICENSING TRANSMITTAL TO NRC

SUMMARY

AND CONCURRENCE SHEET A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable commitments are approved for implementation, and supporting documentation for submittal completeness and accuracy has been prepared.

DATE DATE DUE NRC SUBMITTAL PREPARED BY 1

D. E. Masse Name Signature SUBJECT BFN Unit 2 Reactor Containment Buildin Rate Test Does this submittal contain Corrective Action/Commitment2 INDEPENDENT REVIEW 2

Inte rated Leak Yes XX No DATE NAME CONCURRENCE (3)

ORGANIZATION SIGNATURE DATE J.

E. McCarth P.

Salas Site Licensin Licensin Mana er T. D. Shriver NASL Mana er P.

P. Carier H. L. Williams NASL En r Mana er R. J. Moll 0 erations J.

E. Maddox G.

D. Pierce J.

M. Core Maintenance Tech Su Radchem Eu ene Preston Jr.

Plant Mana er J.

R.

Ru ert Cor En ineerin

k 0

0