Text

Reactor Containment Integrated Leak Rate Test,Vermont Yankee Nuclear Power Station
	ML20102A593
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	07/08/1992
From:	Buteau B, Cappuccio G, Trask T; VERMONT YANKEE NUCLEAR POWER CORP.
To:	;
Shared Package
ML20102A590	List: ML20102A589; ML20102A593;
References
	NUDOCS 9207270135
	Download: ML20102A593 (61)
	v • d • e

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.o-1 REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST Vermont Yankee Nuclear Power Station Vermont Yankee Nuclear Power Corporation Docket No. 50-271 License No. DPR-28 July 1992 Test Coordinator:

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C. 'frask Senior Mechanical Engineer Approved By:

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,G. C dnical Engineering and Construction Supervisor B. R.~ mmh 7 a 1%

i BQteau i 8 Engineering Director 9207270135 920721 PDR -ADOCK 05000271 P

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Table of Contents.

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Section Paae I.;

Introduction....................................

1 i

II.

Type A Test Summary.............................

4

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A.-

Preparation.................................

5 B.

Pressurization..............................

8 C.

Stabilization...............................

9 D.

24 Hour ILRT................................ 10 E.

Verification Test 11 F.

Test Corrections 13 G.

Reported "As-Left" ILRT Results 16 III. Type B and C Testing Summary...................

17 A.

Types of Tests Performed.................... 18 B.

Valves That Exceeded Acceptance Criteria 19 C.

Sum Total Type B and Type C Leakage......... 27 D ; -- Additional Leakage Rate Testing Performed 28 IV. ' Analysis and Interpretation..................... 29 A.

Assessment of-As-Found State of Containment 29 B.

Summary of Corrective Actions Planned 31 V.

References.......................................

32 VI.

Attachments

-A.

Stabilization Phase Data and. Plots B.

24 Hour ILRT. Data and Plots C.

Verification Phase Data and Plots D.' Type B Test Results

~

E.

Type C Test Results i

4

4 I.

Introduction In accordance with 10 CFR 50, Appendix J, Section V.B.3, this report provides information pertinent to the activities related to the preparation, test performance, and reporting of the 1992 Vermont Yankee Primary Containment Integrated Leakage Rate Test (Type A ILRT).

In addition, results and evaluations related to the Vermont Yankee Local Leakage Rate Testing (Type B&C LLRT) performed since 1989 are provided.

Both the Type A ILRT and Type B&C LLRT are performed to demonstrate that leakage through both the primary containment and those systems and components penetrating the primary containment do not exceed the allowable leakage rates specified in the Vermont Yankee Technical Specifications and 10 CFR 50, Appendix J.

Paragraphs III.B.3 and III.C.3 of 10 CFR 50, Appendix J

~

state that the combined leakage rate for all pentrations and valves subject to Type B and C tests shall be less than 0.60 La.

The Vermont Yankee Technical Specifications also state that the leakage from any one isolation valve shall not exceed 5 percent of Ltm (Total Measured Leakage Rate) and that the leakage from any one main steam line isolation valve shall not exceed 11.5 sof/hr at 24 psig.

These supplemental, single valve leakage surveillance limits provide added assurance, beyond the Page 1 of 32

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requirementslof 10_CFR 50, Appendix J, that_ valves receive the proper-attention and maintenance before excessive leakage occurs.-

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Section II of.this report, s.; titled " Type A Test Summary,"

contains data and results necessary to demonstrate containment atmosphere stabilization, acceptable leakage rate, and successful-

verification test.

The plots and data tables provided in Appendices A through C provide a visual history of the containment atmospherir conditions beginning with-the start of l

the stabilization phase and ending with the completion of the verification test.

Highlights of activities and events which occurred-both prior to and during the Type A ILRT and the verification test are also provided in Section II.

Section III of this report, entitled " Type B and C Testing Summary," contains data-and results from-Type B&C LLRT performed since 1989.

Also included are evaluations of those valves that did not meet the acceptance criteria specified in the Vermont Yankee. Technical Specifications and discussions of additional l

.LLRT that was performed.

Further data is provided in Appendices j

I

-D and-E.

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i Page 2 of 32

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Section IV of this report, entitled " Analysis and I

r Interpretation," providos an ovaluation of the as-found state of

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the primary containment sydtom and a summary of the correctivo I

actions planned with respect to both the Type A ILRT and the Type l

i B&O LLRT, as required.

Section V of this rorbrt lists the documents referenced for the conduct of the Type A ILRT and the Type B&c LLRT.

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l II.

Tyra A Toot Summary During the 1992 Refueling Outage (March 7 to April 21, 1992)

Vermont Yankee performed a successful Type A ILRT of the primary containment system, including the required verification tort.

The results of the previous Type A ILRT were filed with the USNRC in July 1989 (Reference (E)).

The successful 1992 Type A ILRT and verification test were performed according to the requirements of the Vermont Yankee Technical Specifications and 10 CFR 50, Appendix J.

The Type A ILRT was performed using the Absolute Method as described in ANSI N45.4-1972, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors".

Leakage rate was calculated using the Mass Point Method as described in ANSI /ANS 56.8-1987, " Containment System Leakage Testing nequirementa".

The verification test was performed using Appendix C of ANSI N45.4-1972.

The instruments usod for data collection met the applicable requirements of ANSI

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N45.4-1972.

In accordance with 10 CFR 50 Appendix J, the acceptance criteria for the Type A ILRT is 0.75 La or 0.6 wt%/ day.

Page 4 of 32 l

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A.

Preparation Prior to the start of primary containment proacurization on April 15, 1992, Vermont Yankee test und maintenance personnel woro engaged in activition ro)ated to primary i

containmont leakage.

Primary containment leakago was identified through Type B&C LLRT and reduced by ropairs to those systems and components having excessive leakage.

Plant modifications waro also performed both to

'ico primary containment leakage and to aid in futurs

-sting.

Further discussion is provided in Section III and Appendicos D and E of this report.

Pre-pressurization activities also included

1) Review and revision of the Type A ILRT test procedure,

3) Calibration and operability checks of the Type A ILRT instrumentation, and

3) Revision, verification and validation of the Type A ILRT computer programs.

The Type A ILRT test procedure was reviewed and revised tot

1) Ensure the inclusion et the current requirements of-the Vermont Yankee Technical Specifications and FSAR, 10 CFR 50fAppendix J, and ANSI N45.4-1972, Pago 5 of 32

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2) Reflect changes in plant design since the last Type A ILRT, and

3) Reflect lessons earned from previous Type A ILRTs performed both at Vermont Yankee and other utilities.

The Type A ILRT computer programs were revised, verified and validated to reficct changes in the plant process computer system since the last Type A ILRT and to ensure that the computer programs are technically correct and function as required.

Preparation of the primary containment for the Type A ILRT included:

1) Performance of a general inspection of the accessible interior and exterior surfaces of the primary containment structures and components.

No evidence of structural deterioration which could affect primary containment structural integrity or leak tightness was iL discovered,

2) Closure of the primary containment isolation valves by normal operation.

No preliminary exercising or adjastments was allowed,

3) Venting of those portions of fluid systems that are part of the reactor fluid pressure oundary and are open directly to the primary containment atmosphere under post-accident conditions, Page 6 of 32

4) Draining of those portions of fluid systems to the extent necessary to expose tho isolation valves, and

5) Removal or venting of pressurized tanks and accumulators.

9 Page 7 of 32

.....-.-.- J

B. Pressurisation Primary containment pressurization for the Typo A ILRT commenced on April 15, 1992 at 1423 hours0.0165 days 0.395 hours 0.00235 weeks 5.414515e-4 months .

Pressurization proconded at a rate which did not excoud the procedural limit of 7 psi /hr.

Two air compressors with a total rating of 2100 scfm woro used along with fan driven aftercoolers and desiccant air dryers.

Flow control valves were manually throttled as required to maintain backpressure and flowrato.

The aftercooler fans woro operated as required to control air compressor dischargo temperaturo.

primary containment inspections woro perfo.~cd at 5, is and 30 psig to attempt to locato any excessivo primary containment leakage, llo significant leaks were idantified.

Prossurization continued until the primary containment pressure test pressure of 59.2 psia ( 120.54 in hg abs) was reached.

Pressurization was completed on April 16, 1992 at 0014 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months .

The elapsed time for the pressurization _ phase was 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and 51 minutes.

l Pago 8 of 32 L

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C.

Stabilisation ANSI H45.4-1972, Section 7.6, states that " leakage-rate tests should not be started until ossential temperaturo equilibrium has been attained."

To quantity this statomont, the stabilization criteria established in ANSI /ANS 56.8-1987, Section 5.3.1.3, was used.

ANS1/ANS 56.8-1987, Section 5.3.1.3, states that "the latest rate of change of the containment atmosphoro volumo weighted absoluto drybulb temperature, averaged over the last hour, does not deviato by more than 0.5 'F/hr(0.3 "C/hr) from the average rate of chango of the containment atmosphoro voluno weighted absoluto drybulb temperature, averaged over the last four hours," or:

T' - T' * * - (T - T.1) s, 0. 5* F/ h r e

e The stabilization period commenced on April 16, 1992 at 0043 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months .

Satisfactory stabilization was achieved on April 16, 1992 at 0453 hours0.00524 days 0.126 hours 7.490079e-4 weeks 1.723665e-4 months , with the results of the above equation being 0.055 "F/hr for the drywell and 0.128 'F/hr for the wetwoll.

The clapsed time for the stabilization phase was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 10 minutos.

Page 9 of 32 l

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D.

24 llour ILRT Subsequent to meeting the ternperature stabilization criteria, the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months IL'n commenced on April 16, 1992 at 0504 hours0.00583 days 0.14 hours 8.333333e-4 weeks 1.91772e-4 months .

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT was successfully completed on April 17, 1992 at 0514 hours0.00595 days 0.143 hours 8.498677e-4 weeks 1.95577e-4 months .

The primary containment leakage rato results were as follows:

Calculated Leakage Rate from regression lino 0.1119 wt%/ day 95% Upper Confidenco Limit 0.1172 wtt/ day *

Does not include penalties for nonstandard alignments and water level changes.

These corrections are provided in Section II.F of this report.

Page 10 of 32

I i

E. Verification Test i

i In accordance with Appendix C of ANSI N45.4-1972, Vermont Yenkee uses the superimposed leak method for the verification test.

In this method, a known leakage rate (Lo), equal to 75 to 125 percent of La, is imposed on the primary containmant through a calibrated flow meter.

The composite leakage rate, equal to the sum of the Icakage rate af ter the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT (Lam) and the superimposed leak (Lo),

i 1s then compared with the composite Icatage rate determined i

i by the Type A ILRT computer programs (Lc).

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l Satisfactory verification is achieved ift (Lo + Lam - 0.25 La) $ Lc $ (Lo 4 Lam + 0.25 La) l On April 17,-1992 at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months , a leakage rate of 5.51 scfm was imposed on the primary containment and allcwed to stabilize.-__The 5.51 sofm Icak imposed (Lo) was equivalent to 100 percent of La.

The verification test commenced on April 17, 1992 at 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months .

Satisfactory verification was achieved.on April 17, g

1992-at 1005 hours0.0116 days 0.279 hours 0.00166 weeks 3.824025e-4 months , with the results stabilizing to within the acceptance criteria of 75 to 125 percent of La.

A summary is provided on the following page:

Page 11 of 32

4 Leakage Rate at etid of Type A ILRT (Lam) 0.1119 wt%/ day imposed Leak (Lo) 0.798 wt%/ day Lower limit:

Lo + Lam - 0.25 La 0.7099 wt%/ day Composite Leakage (Lc) 0.9574 wt%/ day Upper limit:

Lo + Lam + 0.25 La 1.1099 wt%/ day Based on obtaining a composite leakage rate (Lc) between the upper and loser limits, the 1992 Vermont Yankee Verification Test was successful.

The elapsed time for the Verification Test was 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 10 ninutes.

s Page 12 of 32 C--___

F. Test Correotions Several corrections must be considered for addition to the calculated results of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT.

1, Type B&C Penalties Corrections are required for containment valves / penetrations that were not in the normal post accident position during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT.

The total correction, based on Minimum Pathway Leakage for the penetrations, was 0.0290 wt%/ day.

The listing is provided on the following page:

Page 13 of 32

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Minimum Pathway-Leakage Ponetration Descript12D (1bm/hr)

X - 9A "A" Feedwater Line 0.007 X - 9B "B" Feedwater_Line 0.015 X - 14 Reactor Water Cleanup 0.002 Suction X - 22 Containment Air 0.012 X - 47 Compressor Suction J-

'and Discharge X - 26 Containment Purge 0.002 X

__205 Makeup X --31F Reactor Recirc Pump 0.125 Seal Purge X - 32F Reactor Recirc Pump 0.228 Seal-Purge X - 35A Tip Purge 0.002 X - 41 Reactor Recirc Sample 0.034 X - SOA-C Hfh Monitors 0.478 X - 209D Total correction

=

0.903 This equates ~to an addition of 0.0290 wt%/ day

=

Page 14 of 32

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2)' Volume Change Correctionn i

corrections are required for any liquid lovel changes during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT which resulted in a change in the not free volume of the primary containmontt calculated Correction Description (vt1/ day 1 RPV Volume Chango 0.0121 Equipment Drain Sump Volume Change 0.0030 Floor Drain Sump Volume Change 0.0013 Total correction =

0.0164 Corrections in the net free volume of the primary containment resulting from changes in Torus water volumo are automatically calculated by the Type A ILRT computer programn during the cource of tho-test.

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Reported "As-Left" ILRT Results The results of the Type A ILRT to be reported, including all corrections are:

95% Uppor Confidenco Limit 0.1172 wt%/ day Total Type B&C Penaltico 0.0290 wt%/ day-Total Volume Change Corroctions 0.0164 wt%/dwy "As-Left" Type A ILRT Lankago Rato 0.1626 ut%/ day Type A ILRT Acceptance Criteria (0.75 La) 0.6 wt%/ day Based on obtaining a final "An-Loft" leakage rato loss than the acceptanco criteria, the 1992 Vermont Yankoo Type A ILRT was successful.

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t III. Type D and C Testing Summary since the completion of the previous Type A ILRT in March of 1989, Type B&C LLRT was performed on primary containment penetrations and valves.

This testing was performed during both the 1990 Refueling Outago ( August to October 1990) and the 1992 Refueling Outage.

Required non-outage testing was also performed as necessary.

As discussed in Section I of this report, Paragraphs III.B.3 and III.C.3 of 10 CFR 50, Appendix J state that the combined leakage rate for all pentrations and valves subject to Type B and C tests shall be less than 0.60 La.

The Vermont Yankoo Technical Specifications also state that the leakage from any one isolation valve shall not exceed 5 percent of Ltm and that the leakage from any one main steam-line isolation valve shall not exceed 11.5 sof/hr at 24 poig.

These supplemental, single valve leakage surveillance limits provide added assurance, beyond the requirements of 10 CFR 50, Appendix J, that valves recolve the proper attention and raaintenance before excessive leakage cccurs.

Vermont Yankee calculates the sum total Type B and C Icakage rato using the Maximum Pathway Leakage method with single valve failure assumed for all applicable penetrations.

The results of this calculation are presented in Section III.C of this report.

Page 17 of 32 o

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A.

Types of Tests Performed Type B leak tests were performed on containment penetrations utilizing gasketed seals prior to opening to determine the as-found leakage rates.

After each containnent penetration was closed, a Type B leak test was again performed to provide as-left data.

A summary of the Type B tests that were performed during the 1990 and 1992 Refueling Outages is provided in Attachment D.

Type c leak tests were performed on all containment isolation valves both prior to and after any outage maintenance to provide both as+found and as-left data.

A summary of the Type c tests that were performed during the 1990 and 1992 Refueling Outages is provided in Attachment E.

s Page 18 of 32

D.

Valves That Exceeded Acceptance criteria The following is a summary of the valves that failed to meet the Vermont Yankee Technical Specifications acceptance critoria of 5 percent of Ltm (0.522 Lbm/hr at 44 psig) for any single valve.

For each valve an oveluation of the root cause and a summary of the Vermont Yankee action plan to address the failure is provided.

This information supplements the information provided in LERs 90-12, 90-12, Supplement 1, and 92-010.

Specific leakage rates are provided in Attachment E.

Containment Containment Isolation Ecn_eir_a_t i on

_Va1ye Des _gr_1pilqn T.c_pt Period o

1990 Outage:

X-98 FDW-96A Reactor Feedwater X-25 PCAC-6B Drywell Atmospheric Control Exhaust 1992 Outage:

X-9B FDW-28B Reactor Feedwater X-18 LRW-83 Drywell Floor Drain X-31F CRD-413A Recirc Pump Seal Purge X-32F CRD-413B Recirc Pump Seal Purge Page 19 of 32

d X-9B. FDW-96A:

During the 1990 Refueling Outage, the outboard Feedwater isolation valve, FDW-96A, was tested.

The leakage rate could not be measured with available on-site testing equipment.

The valve wt disassembled and physical abrasion of the ciastomeric seat was observed.

The physical abrasion was determined to be caused by low flow conditions which exist during Feedwater system steirtup and during refueling outages and cold shutdowns when only Reactor Water Cleanup and Control Rod Drive return flow is present in the Feedwater system.

The root cause was determined to be the failure by the manufacturer, in the denign of the valve, to anticipato the potential adverse c

affects of low flow conditions.

To resolve this concern, the clastomeric seats were removed from all four (4) Anchor Darling feeJwater check valves, FDW-28A/B, FDW-96A and FDW-27A.

The resulting stellite to stellite seating surface is not as susceptible to wear due to the low flow condition and, based upon information from 4

other plants who have experience with similar valves in similar installations, is not expected to be a concern.

Page 20 of 3?

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-Vermont Yankoo has experienced failurce of thib valvo in the past and has aggrousively pursued ways, along with the i

industry, to improve the foodwater check valvo leak I

tightness.

These improvements have included previous repair of misalignments and grinding of the seats.

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To. improve the rollability of both punotrations X-9A and X-9B, Vermont Yankoo replaced the inboard check valves, FDW-28A/B, with now check valves during the 1990 Refueling Outage.

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rollowing the above maintenanco and installations, valvos

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FDW-96A and FDW-28A/B were successfully leak go rato tested.

~L X-35, PCAC-6Bt During the 1990 Refueling Outage, the Primary Containment Atmospheric control (PCAC) system exhaust line was--tested.

The PCAc exhaust i~s comprised of six valvos testod as a group.

The leakage rate c uld no; bo measured with 1

available on-site tenting equipment.

valve PCAc-6B was.

disassembled and failure of the clastomoric seat was observed.

Page 21 of 32

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The root cause of the failure was determined to be a tear in the elastomeric seat caused by excessive flexing of the seat.

The compression gasket that compresses the seat material was found to be misaligned.

This allowed the disc to flex the seat material more than is intended, causing the seat to tear.

Valve PCAC-6B in regularly cycled during operation for surveillance testing.

The root cause of the compression gasket misalignment is believed to be the maintenance performed on the valve during thn 1989 Refueling Outage.

In 1989, the clastomeric seat was replaced due to excessive leakage resulting from a torn seat.

The root cause of this torn seat was determined to be normal wear.

The seat had been in service for 12 years, 1l rom 1977 to 1989 Fo.' lowing the above maintenance, valve PCAC-6B was s'ccessfully leakage rate tested.

To address continuing concerns with the performance of the PCAC valves, Vermont Yankee has developed a preventive maintenance schedule for replacing the seats.

Included in the preventive maintenance instructions will be steps to ensure the proper alignment of the compression gasket.

Page 22 of 32 am

e X-9B. FDW-20B:

During the 1992 Refueling Outaca, the inboard Fondwater isolation valve, FDW-2SB, was tested.

The leakage rate could not be measured with available oa-site testir.g o

equipment.

The valve was disassembled and the disc was found to be stuck in the f'111y open position.

The-root cause of the failure was determined to be a manufacturing defect.

Excess material was present in the valve-body casting which caused-the disc to etick in the fully open position.

The-valve was repaired by removing the excess material and proper clearances and valve operation were assured.

The remaining three (3) Anchor Darling feedwater check valves, FDW-27A, FDW-28A and FDW-96A, were also inspected for this same defect.

Valves FDW-27A and FDW-96A, the outboard isolation valves for penetrations X-9A/B, were found not to have the defect.

Valve FDW-28A, the inboard isolation valve for penetration X-9A, was found to have the defect.

The disc could be manually made to stick in the g

fully open position even though the valve had successfully passed leakage rate testing and was not found stuck open.

The valve was also repaired by removing the excess material and proper clearances and valve operation was assured.

Page 23 of 32 4-

4 Following the above maintenanco and inspections, valvos FDW-27A, FDW-28A/B and FDW-36A were successfully leakage rato l

tested.

Based on similar concerns noted with Anchor Darling check i

valves (Reference (I)), Vermont Yankoo '.as rnvised our purchase specifications to explicitly require free travol of the-valvo disc over the entire range of motion and has increased vendor surveillance of Anchor Darling fabrication and inspection activities.

X-18, LHW-81t' During the 1992 Refueling Outage, the outboard isolation valve for the drywell' floor drain sump line, LRW-83, was tested.

The as-found leakage rate was 0.990 lbm/hr and determined to be caused by valvo wear and a failure to properly seat,.both resulting from equipment age._

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As a besult of excessive leakage rates observed for the-LRW valves in both.1989 and 1990, Vermont Yankeo undertook additional action to improve the reliability of penetrations X-18.and-X-19.

This resulted in the replacement of valves LRW-82,

-83,.-94, and -95 during the'1992 Refueling Outage.

Following1 installation,-valves LRW-82,

-83,

-94,-and -95 were successfully leakage rate tested.

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i X-31F and 32F. pRD-413A/_B:

l During the 1992 Refueling Outage, the inboard isolation j

check valves for the reactor recirculation coal purgo lincts, CRD-413A and -413B, were tested.

The as-found leakage rates i

were 0.788 lbm/hr for CRD-413A and 0.873 lbm/hr for CRD-l 413B.

The valves were disassembled and teflon tape was found within valve CRD-413B, preventing proper seating.

The root cause of ths presence of the teflon tape was determined to be incorrect use of teflon tapo-during the installation of the ranctor recirculation seal purgo linos.

Disassembly and li.spection of the threaded joints in the lines identiflod excessive toflon tape.

The tapo extended into the process stroam whero system flow could erodo the tape and allow pieces to foul the downstream surfaces and

. valves.

The joints were properly taped and the valves

. cleaned and inspected.

Following this maintenanco, valves CRD-413A and -413B were successfully leakago rato tested.

Tho'une of exec.aive teflon tapo is considered to be an isolated incident for the following reasons:

Page 25 of 32

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1) The installation was-performed by a contractor, and i

2) The installation of teflon tape by-Vermont Yankoo personnel is properly controlled by an existing

-i guidelino.

To prevent reoccurronco, Vermont Yankoo will revise our installation procedures to ensure the proper installation of teflon tape.

These procedures are used by both contractor and Vermont Yankee personnel.

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Page 26 of 32

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C.

Sun Total Type B knd Type C Leakage The Vermont Yankee Technical Specifications and 10 CFR 50, Appendix J require the sum total Tvoe B (penetrationn) and Type C (valves) leakage rate to be less than or equal to 0.6 La prior to startup from a Refueling Outage (0.6 La equals 14.75 lbm/hr).

Vermont Yankee calculates the sum total Type B and C leakage rate using the Maximum Pathway Leakage method with single active failure assumed for all applicable penetrations.

The results of the calculations for the as-left sum totals for the 1990 and 1992 Refueling Outages are presented below, along with the Minimum Pathway Leakago Rates:

Sum Total Sum Total Maximum Pathway Minimum Pathway Test Period Leakane (1bm/hr)

Leakage _J1bm/hr) 1990 Outage:

6.951 4.879 1992 Outage:

8.907 3.866 Based on obtaining final "As-Left" leakage rates less than the acceptance criteria, the 1990 and 1992 Refueling Outage.

Type B&C LLRTs were successful.

Page 27 of 32

4 I

D.

Additional Leakage Rate Testing Performed The following leakage rate tests were performed between the 1990 and 1992 Refueling Outages:

Pen.

Test Measured Leakago No.

DAtg

[Leacriotion Q1.2n/hE)

X-2 10-22-90 Personnel Airlota 1.6 X-13B 11-07-90 RHR-66 0.031 X-2 12-28-90 Personnel Airlock O.966 X-2 3-15-91 Personnel Airlock 1.21 X-2 3-18-91 Personnel Airlock 1.3 X-2 3-19-91 Personnel Airlock 1.41 X-2 4-24-91 Personnel Airlock 1.14 X-2 4-27-91 Personnel Airlock 1.07 X-2 4-29-91 Personnel Airlock 1.119 X-2 5-01-91 Personnel Airlock 1.03 X-2 6-20-91 Personnel Airlock 0.582 X-2 9-06-91 "arsonnel Airlock 1.04 X-6 9-06-91 CRD Removal 0.0 X-2 9-14-91 Personnel Airlock 1,71 X-6 9-14-91 CRD Removal 0.0 X-2 9-16-91 Personnel Airlock O.162 X-35E 10-07-91 TIP Ball Valve No. 3 0.001 X-2 12-26-91 Personnel Airlock O.971 2-19-92

'A' H202 Monitor 1.632 2-26-92

'B' H202 Monitor 0.648 Page 28 of 32

l

-l IV.

Analysis and Interpretation

-All testing performed during the period covered in this report satisfied the requiremonte f Vermont Yankco Technical Specifications and 10 CFR 50, Appendix J.

Due to the succes. of the 1992 Type A ILRT and Type-B&C LLRT, coupled with the corrective actions discu.ssed in Section IV.B of this report, Vermont Yankee plans to perform the next l

s Type li ILRT during the 1995 Ref ueling Outage.

A. Assessment of the As-Found State of Containment Integrated Leak Rate tasts are performed on the Primary Containment System to ensure that the leakage rate is within allowable limits.

Many utilities, including Vermont Yankee, perform this test at the end of Refueling Outages, following repairs or adjustments to the Primary containment boundary.

To assess the As-Found state of the Primary Containment, Type B&C ILRT data is used to-determine the Minimum Pathway

' Leakage Savings.

Leakage Savings is realized when containment penetrations or valve repairs or adjustments result: in. a-lower minimum pathway leakage than that measured prior to~the repairs or adjustments.

The Leakage Savings is determined as follows:

Page 29 of 32

_. ~. _

_.., _, ~

1) The post-repair minimum pathway leakage is compared to the pre-repair minimum pathway leakage.

If the post repair minimum pathway leakage is smaller, a leakage savings has been realized foi that penetration,

2) If the post-repair minimum pathway leakage is equal to or greater than tne pre-repair minimum pathway leakage, no lankage savinga has been realized 'or that penetration, and no contribution is made by that penetration to the As-Found correction.

The results of the As-Found State of the Primary Containment to be reported, including all corrections are:

"As-Left" Typo A ILRT 0.1626 wt%/ day Leakage Rate at 95% Upper Confidence Limit Leakage Savings 0.0524 wt%/ day "As-Found" Leakage 0.2150 wt%/ day Rate at 95% Upper Confidence Limit 1

Type A ILRT Acceptance Criteria (0.75 La) 0.6 wt%/ day 6

Based on obtaining a final "As-Found" leakage rate less than the acceptance criteria, it is concluded that had the 1992 Type A ILRT been performed at the start of the Refueling Outage the acceptance criteria would have been met.

Page 30 of 32

)

4-9 B.

Summary of Corrective Actionfs Planned

~The following is a-summary of the corrective actions currently planned for implementation prior to or during the 1993 Refueling Outage.

1) To address continuing concerns with the performance of the PCAC valves, Verront Yankee has developed a preventive maintenance schedule for replacing the seats.

Included in the preventive maintenance instructions will be steps to ensure the proper alignment of the compression gasket.

2) Based on the revot cause analysis performed for the presence of teflon-tape in the recirculation seal purge lines and valves CRD-413A and -413B, Vermont Yankee will revise our installation procedures to ensure the prcjer installation of teflon tape.

These procedures e s used-by both contractor and Vermont Yankee personnel.

.y Page 31 of 32

?

V.

References

'A) License No. DPR-28 (Docket No. 50-271)

B) Code of Federal-Regulations, Title 10, Part 50, Appendix J,

" Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors".

C) ANSI N45.4-1972, " Leakage-Rate Testing of Cu*ainment

' Structures for Nuclear Reactors".

D) ANSI /ANS 56.8-1987, " Containment System Leakage Testing Requirements".

A

'E) Letter, VYNPC to USS7C. " Primary Containment Leak Rate Test Report," dated Ju'y 7 1989.

F) Report Slo ~ccurr sca No. LER 90-12, VYV 90-281, dated October 3,

1990.

G) Reportable Occurrence No. LER 90-12, Supplement 1, VYV 90-320, dated October 24, 1990.

H) Reportable Occurrence No. LER 92-010, dated April 7, 1992.

I) Letter,-VYNPC to USNRC, "10 CFR 21.21 Notification Regarding Anchor Darling Swing Check Valves," BVY 92-49, dated April 29, 1992.

J) Vermont Yankee: Analysis / Calculation No.92-007, " Calculation of Required Corrections for the 1992 Type A Test," dated 6'une 24, 1992.

K) Vermont Yankee Analysis / Calculation No. 92'008,

" Determination'of the As-Found State of the Primary Containment for the 1992 Type A Test," dated June 24, 1992.

.0 Page 32 of 32

_. c o

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. ;y Fb 4

_'k _- -

1 APPENDIX A-n, 2,.y STABILIZATION PHASE DATA AND PLOTS

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a.:.

._k' 4

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e

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,-w-.

u u- - -

1992 Primary Containment Leakage Rate Data Sheet (Stabilization Phase)

Drywell Torus Temperature Temperature 1

(F)

Date Time I

C050 C060 16-Apr-92 00:31:22.8 78.485 68.232 16-Apr-92 00:43:37.4 78.397 67.935 16-Apr-92 00:53:35.6 78.382 67.810 16-Apr-92 01:03:35.6 78.348 67.638 16-Apr-92 01:13:35.6 78.310 67.598 16-Apr-92 01 23:35.6 78.271 67.450 16-Apr 92 01:33:35.6 78.252 67.415 16-Apr-92 01:43:35.6 78.220 67.321 16-Apr 92 0113:35.6 78.182 67.283 h

16-Apr-92 02:03:35.6 78.145 67.111 16-Apr-92 02:13:35.6 78.142 67.077 16-Apr-92 02:23:35.6 78.121 67.050 16-Apr-92 02:33:35.6 78.114 67.013 16-Apr-92 02:43:35.6 78.096 66.923 16-Apr-92 02:53:35.6 78.071 66.860 16-Apr-92 03:03:35.8 78.049 66.883 16-Apr-92 03:13:35.6 78.008 66.816 16-Apr-92 03:23:35.6 78.009 66.765 16-Apr-92 03:33:35.6 77.996 66.700 16-Apr-92 03:43:35.6 77.977 66.691 16-Apr-92 03:53:35.6 77.929 66.615 16-Apr-92 04:03:35.6 77.938 66.601 16-Apr-92 04:13:35.6 77.901 66.514 16-Apr-92 04:23:35.6 77.899 66.514 16-Apr-92 04:33:35.6 77.858 66.483 16-Apr-92 04:43:35.6 77.850 66.363 16-Apr-92 04:53:35.6 77.851 66.387 e

.i A.-

.' b

'85 VERMONTYANKEE

1992 44 PSIG'ILRT

' Stabilization Phase Drywell and Torus.

-Temperature n. Time.

80-g Cn b

2

{

C050:'Drywell WTD AVG Temperature 5

75-m GQ.

EW I-70-CM0: Torus WTD AVG Temperature.

~

65 !

i 0-0.5 1

1.5 -

2

. 2.5 3

3.5 4..

Elapsed Time.(hrs)l

l t.

APPENDIX B 24 HOliR ILRT DATA AND PLOTS N

1992 l' rim ry Conttimn ni f.,c:k:g3 luto intn Stoct (241 tour Tcst l'hasa) 4 Regression 95% Upper Containment Containment Line Leakage Confidence Mass Pressure Rate Limit (lbm)

(in. IIg.)

(wi%/ day)

Date Time CMASS M006 LAM UCL 16 Apr-92 05.04:10.9 74929.0 120.038 16-Apr-92 05:14:09.6 74925.1 120.022 16-Apr-92 05:24.09.6 74940.7 120.030

-1.1243 8.1267 16-Apr 92 05:34:09.6 74928.6 120.015

-0.2767 1.7475 16-Apr-92 05:44:09.6 74933.8 120.008

-0.2518 0.6842 16-Apr-92 05:54:09.6 74923.9 119.985 0.0631 0.7398 16-Apr-92 06:04:09.6 74932.1 120.000 0.0R 0 0.4582 16-Apr-92 06:14:09.6 74927.2 119.973 0.0522 0.3867 16-Apr-92 06:24:09.6 74934.3 119.993

-0.0179 0.2461 16-Apr-92 06:34:09.6 74917.7 119.955 0.1214 0.3765 16-Apr-92 06:44:09.6 74929.3 119.978 0.0905 0.2984 16-Apr-92 06:54:09f 74926.5 119.962 0.0899 0.2610 16-Apr-92 07:04:09.6 74930.4 119.962 0.0619 0.2080 16-Arr-92 07:14:09.6 74918.0 119.932 0.1106 0.2445 16-Api-92 07:24:09.6 74922.1 119.932 0.1198 0.2354 16-Apr-92 07:34:09.6 74921.4 119.925 0.1262 0.2270 16-Apr-92 07:44:09.6 74922.8 119.932 0.1229 0.~2115 16-Apr-92 07:54:09.6 74921.7 119.917 0.1222 0.2005 16-Apr-92 08:04:09.6 74913.6 119.902 0.1443 0.2175 16-Apr-92 03:14:09.6 74913.9 119.902 0.1575 0.2245 16-Apr-92 08:24:09.6 74914 3 119.902 0.1642 0.2250 16-Apr-92 08:34:09.6 74906.0 119.880 0.1862 0.2456 16-Apr-92 08:44:09.6 74911.8 119.887 0.1889 0.2430 16-Apr-92 08:54:09.6 74901.9 119.865 0.2080 0.2610 16-Apr-92 09:04:09.6 74916.9 119.880 0.1944 0.2449 16-Apr-92 09:14:09.6 74924.3 119.880 0.1699 0.2223 16-Apr-92 09:24:09.6 74913.9 119.857 0.1649 0.2137 16-Apr-92 09:34:09.6 74914.5 119.850 0.1589 0.2045 16-Apr-92 09:44:09.6 74911.2 119.842 0.1573 0.1997 16-Apr-92 09:54:09.6 74899.0 119,813 0.1701 0.2116 16-Apr-92 10:04:09.6 74902.3 119.813 0.1757 0.2149 16-Apr-92 10:14:09.6 74905.1 119.813 0.1763 0.2130

1992 Primnry Containment Leakage Reto D:te Sheet (24 Hour Test Phase) a Regression 95% Upper Containment Containment Line Leakage Confidence Mass Pressure Rate Limit (Ibm)

(in. Ilg.)

(wt%/ day)

Date Time-CMASS M006 LAM UCL 16 Apr 92 10:24:09.6 74912.5 119.820 0.1683 0.2035 16-Apr-92 10:34:09.6 74888.3 119.783 0.1841 0.2208 16-Apr 10:44:09.6 74904.1 119,798 0.1821 0.2167 16-Ap.92 10:54:09.6 74909.6 119.805 0.1748 0.2082 16-Apr-92 11:04:09.6 74886.4 119.775 0.1869 0.2206 16-Apr-92 11:14:09.6 74899.5 119.783 0.1863 0.2182 16-Apr-92 11:24:09.6 74901.3 119.783 0.1837 0.2140 16-Apr 92 11:34:09.6 74904.9 119.790 0.1782 0.2075 16-Apr-92 11:44:09.6 74887.7 119.745 0.1844 0.2129 16-Apr-92 11:54:09.6 74897.2 119.760 0.1831 0.2103 16-Apr-92 12:04:09.6 74892.9 119.752 0.1840 0.2099 16-Apr-92 12:14:09.6 74897.9 119.760 0.1814 0.2062 16-Apr-92 12:24:09.6 74894.1 119.752 0.1806 0.2043 16-Apr-92

_12:34:09.6 74893.7 119.737 0.1797 0.2024 16-Apr-92 12:44:09.6 74894.7 119.745 0.1779 0.1996 16 Apr-92 12:54:09.6 74899.1 119.737 0.1736 0.1949 16-Apr-92 13:04:09.6 74883.7 119.715 0.1768 0.1974 16-Apr-92 13:14:09.6 74891.9 119.715 0.1754 0.1952 16-Apr-92 13:24:09.6 74890.2 119.723 0.1745 0.1936 16-Apr-92 13:34:09.6 74884.5 119.707 0.1757 0.1941 16-Apr-92 13:44:09.6 74890.4 119.707 0.1741 0.1918 16-Apr-92 13:54:09.6 74897.5 119.723 0.1695 0.1871 16-Apr 14:04:09.6 74884.5 119.707 0.1699 0.1869 16-Apr 92 14:14:09.6 74880.6 119.692 0.1714 0.1878 16-Apr-92 14:24:09.6 74871.6 119.685 0.1756 0.1919 16-Apr-92 14:34:09.6 74876.8 119.685 0.1772 0.1931 16-Apr-92 14:44:09.6 74869.3 119.670 0.1809 0.1966 16-Apr-92 14:54:09.6 74879.4 119.685 0.1807 0.1959 16-Apr-92 15:04:09.6 74878.1 119.678 0.1807 0.1954 16-Apr-92 15:14:09.6 74873.3 119.663 0.1818 0.1960 16-Apr-92 15:24:09.6 74877.7 119.663 0.1812 0.1950 16-Apr-92 15:34:09.6 74871.5 119.655 0.1822 l

0.1956

1992 Prim ry Containment Leckege Rate D:ta Sheet (24 Ilour Test Phase)

Regression 95% Upper Coniainment Containment Line Leakage Confidence Mass Pressure Rate Limit (lbm)

(in. Hg.)

(wt%/ day)

Date Time CMASS M006 LAM UCL 16-Apr-92 15:44:09.6 74876.5 119.663 0,1815 0.1945 16-Apr-92 15:54:09.6 74886.0 119.670 0.1781 0.1911 16-Apr-92 16:04:09.6 74887.7 119.670 0.1744 0.1875 16-Apr-92 16:14:09.6 74881.1 119.655 0.1724 0.1852 16-A pr-92 16:24:09.6 74872.2 119.640 0.1724 0.1849 16-Apr-92 16:34:09.6 74878.9 119.640 0.1707 0.1830 16-Apr-92 16:44:09.6 74874.5 119.640 0.1699 0.1819 16-Apr-92 16:54:09.6 74863.6 119.625 0.1714 0.1831 16 Apr 92 17:04:09.6 74878.2 119.640 0.1695 0.1810 16-Apr-92 17:14:09.6 74865.1 119.625 0.1702 0.1814 16-Apr-92 17:24:09.6 74867.8 119.625 0.1702 0.1811 16-Apr-92 17:34:09.6 74873.8 119.625 0.1688 0.1795 16-Apr-92 17:44:09.6 74879.1 119.633 0.1663 0.1770 16-Apr-92 17:54:09.6 74861.8 119.610 0.1671 0.1776 16-Apr-92 18:04:09.6 74892.5 119.625 0.1621 0.1734 16 Apr-92 18:14:09.6 74877.2 119.595 0.1600 0.1712 16-Apr-92 18:24:09.6 74880.7 119.602 0.1573 0.1685 16-Apr-92 18:34:09.6 74877.8 119.595 0.1552 0.1663 16-Apr-92 18:44:09.6 74884.8 119.602 0.1519 0.1632 16-Apr-92 18:54:09.6 74880.0 119.602 0.1495 0.1607 16-Apr 92 19:04:09.6 74874.0 119.573 0.1480 0.1591 16-Apr-92 19:14:09.6 74879.1.

119.588 0.1458 0.1569 16-Apr-92 19:24:09.6 74871.8 119.580 0.1447 0.1556 16-Apr-9' 19:34:09.6 74878.6 119.580 0.1426 0.1534 16-Apr-92 19:44:09.6 74881.6 119.580 0.1401 0.1509 16.Apr-92 19:54:09.6 74873.9 119.565 0.1387 0.1493 16-Apr-92 20:04:09.6 74881.9 119.580 0.1362 0.1469 16-Apr-92 20:14:09.6 74882.2 119.573 0.1337 0.1445 16-Apr-92 20:24:09.6 74880.7 119.573 0.1315 0.1422 16-Apr-92 20:34:09.6 74871.4 119.565 0.1306 0.1411 l

16-Apr 92 20:44:09.6 74862.4 119.550 0.1307 0.1410 l

16-Apr-92 20:54:09.6 74860.1 119.542 0.1311 0.1411 l

l I

1992 Prim ry Coniainment Leakage Rate Data Shee (24 Hour Test Phase) l I

Regression 95% Upper Containment Containment Line Leakage Confidence Mass Pressure Rate Limit (ibm)

(in. Hg.)

(wt%/ day)

Date Time CMASS M006 LAM UCL 16-Apr-92 21:04:09.6 74874.6 119.558 0.1295 0.1395 16-Apr-92 21:14:09.6 74865.5 119.535 0.1291 0.1389 16-Apr-92 21:24:09.6 74870.9 119.550 0.1280 0.1377 16-Apr-92 21:34:09.6 74873.1 119.558 0.1266 0.1362 16-Apr-92 21:44:09.6 74866.6 119.542 0.1260 0.1354 16-Apr-92 21:54:09.6 74862.1 119.535 0.1258 0.1350 16-Apr-92 22:04:09.6 74868.8 119.542 0.1249 0.1339 16-Apr-92 22:14:09.6 74860.0 119.527 0.1248 0.1337 16-Apr-92 22:24:09.6 74853.9 119.512 0.1253 0.1341 16-Apr-92 22:34:09.6 74867.8 119.527 0.1244 0.1330 16-Apr-92 22:44:09.6 74867.4 119.520 0.1234 0.1319 16-Apr-92 22:54:09.6 74865.5 119.520 0.1226 0.1310 16-Apr-92 23:04:09.6 74869.4 119.527 0.1215 0.1297 16-Apr-92

'23:14:09.6 74866.1 119.520 0.1206 0.1288 16-Apr-92 23:24:09.6 74866.1 119.520 0.1197 0.1278 16-Apr 92 23:34:09.6 74854.5 119.497 0.1199 0.1278 16-Apr-92 23:44:09.6 74853.3 119.490 0.1201 0.1279 16-Apr-92 23:54:09.6 74863.6 119.505 0.1194 0.1270 17-Apr-92 00:04:09.6 74866.5 119.512 0.1183 0.1260 17-Apr-92 00:14:09.6 74867.6 119.505 0.1172 0.1248 17-Apr-92 00:24:10.0 74853.2 119,490 0.1173 0.1247 17-Apr-92 00:34:09.6 74844.2 119.475 0.1181 0.1254 17-Apr-92 00:44:09.6 74855.8 119.482 0.1178 0.1251 17-Apr-92 00:54:09.6 4

74849.6 119.475 0.1180 0.1252 17-Apr-92 01:04:10.3 74854.7 119.475 0.1178 0.1248 17-Apr-92 01:14:09.6 74859.9 119.482 0.1171 0.1240 17-Apr-92 01:24:09.6 74857.5 119.475 0.1166 0.1234 17-Apr-92 01:34:09.6 74856.3 119.467 0.1162 0.1229 17-Apr-92 01:44:09.6 74867.6 119.482 0.1149 0.1216 17-Apr-92 01:54:09.6 74850.2 119.452 0.1148 0.1215 17-Apr-92 02:04:09.6 74850.7 119.452 0.1147 0.1212 17-Apr-92 02:14:09.6 74853.9 119.452 l

0.1144 0.1208 i

h

1992 Primary Containnnat I caka itet Date Sheet (24 !!aur Tcst l'hase) f Regression 957c Upper Containment Containment Line Leakage Confidence Mass Pressure Rate Limit j

(lbm)

(in. Hg;)

(wi%/ day)

(w1G/ day)

Date Time CMASS M006_

LAM UCL 17 Apr 92 02:24:09.6 74853.7 119.452 0.1140 0.1203 17-Apr-92 02:34:09.6 '

74863.0 119.467 0.1130 0.1193 17-Apr 92 02:44:09.6 74851.6 119.445 0.1127 0.1189 17 Apr-92 02:54:09.6 74833.7 119.415 0.1136 0.1198 17-Apr-92 03:04:09.6 74657.6 119.438 0.1129 0.1190 17-Apr-92 03:14:09.6 74857.0 119.445 0.1122 0.1182 17-Apr-92 03:24:09.6 74858.2 119.438 0.1114 0.1174 17-Apr-92 03:34:09.6 74851.6 119.430 0.1110 0.1170 17-Apr-92 03:44:09.6 74835.1 119.400 0.1116 0.1175 17-Apr-92 03:54:09.6 74852.3 119.415 0.1111 0.1170 17-Apr-92 04:04:09.6 74838.4 119.400 0.1115 0.1172 17-Apr-92 04:14:09.6 1 74847.0 119.408 0.1112 0.1169 17-Apr-92 04:24:09.6 74834.2 119.385 0.1117 0.1173 17-Apr-92 04:34:09.6 74849.1 119.408 0.1113 0.1169 17-Apr 92 04:44:09.6 74839.2 119.385 0.1114 0.1169 17-Apr-92 04:54:09.6 74833.6 119.378 0.1118 0.1173 17-Apr-92 05:04:09.6 74842.9 119.393 0.1117 0.1170 17-Apr-92 05:14:09.6 74835.3 119.378 0.1119 0.1172 l

C

p__

. ~.

3..-

=:

1

-::y,

r u

4 75.10 i VERMONT YANKEE 1-- +

1992 44 PSIG ILRT 75.05-24 Hour ILRT Phase Containment Mass -

versus Time y

75.00-

.cc G

m

'74.95-

<2 G,

B3m j

E! ' 74.90-O b

M 74.85-(

3m 0

74.80-74.75-l

)

74.70 i

i i

i 0

4 8

'12 16 20

.24 Elapsed Time (hrs) i k

i-

.c 4 n

' $_',. y;.

A

.g.

120.1:

~

a VERMONT-YANKEE:-

^

1992 44 PSIGILRTM-l 120.0-s, 24 Hour:ILRT Phase?

i ',

s.

Containment Pressure 3

S versus' Time o

Z 119.9-4 t

e

.c m:

a e

- 8 '119.8-

-l l2 v

2 5!

119.7-wo i

A l

5 119.6-a

'm

'E w

i 8

119.5-U 119.4-i i

119.3 i

i i

n 0

.4 8

12

- 16 20 24 Elapsed Time.(hrs) i e

s

.y'.'

y-w e-+.-

_g.,sq

s

+

~

'f

~^'

i

,s.

/.i. :

1.2

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i j.

VERMONT YANKEEj w

1992 44.PSIG. ILRT -

1.0-24 Hour ILRT Phase Conte.inment Leakage-g vetsusTimeE 0.8-

.a-0.75 LA

~

/

E 0.6.:

w o

~.

W oao3 0.4-UCL i

m o

a 5

02-s e

j o

g

~

8 0.0--

U a

LAM

-0.2-

)

ii

-0,4 i

i i

i 0

4~

8 12 16

.20:

24

\\

.. Elapsed Time (hrs) i 1

)

I n,.

p>,

1 7

,a

.. i -

j.,.

r a

J 3

1 1

APPENDIX C VERIFICATION PIIASE DATA AND PLOTS

.,t

' (

a-

+

v e

r

1, 1992 Primary Containment Leakage Rate Data Sheet (Verification Phase)

Containment Containment Leakage Mass

. (wt%/ day)

(Ibm)

Date Time LAM CMASS 17 Apr-92 01:54:09.6 0.1148 74850.2 17-Apr-92 02:04:09.6 0.1147 74850.7 17-Apr-92 02:14:09.6 0.1144 74853.9 17 Apr-92 02:24:09 6 0.1140 74853.7 17-Apr-92 02:34:09.6 0.1130 74863.0 17-Apr-92

-02:44:09.6 0.1127 74851.6 17-Apr-92 '

02:54:09.6 0.1136 74833.7 17-Apr-92 03:04:09.6 0.1129 74857.6 17-Apr-92 03:14:09.6 0.1122 74857.0 17-Apr-92 03:24:09.6 0.1114 74858.2 17-Apr 03:34:09.6 0.1110 74851.6 Apr-92 03:44:09.6 0.1116 74835.1 17-Apr-92 03:54:09.6 0.1111 74852.3 17-Apr-92 04:04:09.6 0.1115 74838.4 17 Apr 04:14:09.6 0.1112 74847.0 17-Apr-92 04:24:09.6 0.1117 74834.2 17-Apr-92

-04:34:09.6 0.1113 74849.1 17-Apr-92 04:44:09.6 0.1114 74839.2 17-Apr-92 04:54:09.6 0.1118 74833.6 17-Apr-92 05:04:09.6 0.1117 74842.9 17-Apr-92 05:14:09.6 0.1119

~14835.3 17-Apr-92 05:24:09.6 17-Apr-92 05:34:09.6 17-Apr-92 05:44:09.6

.. +

1992 Primary Containment Leakage Rate Data Sheet (Verification Phase)

Containment Containment

+

Leakage Mass (wt%/ day)

(Ibm)

Date Time LAM CMASS 17 Apr-92 05:55:03.3,

74819.0 17 Apr42 06:05:02.3 74811.3 17-Apr-92 06:15:02.3

-0.5197 74824.4 17-Apr-92 06:25:02.3 0.2271 74810.7 17-Apr-92 06:35:02.3 0.6659 74802.0 17-Apr-92 06:45:02.3 0.3690 74813.9

)

17 Apr-92 06:55:02.3 0.5843 74796.4 74187.0 17-Apr-92 07:05:02.3 0.7760 17-Apr-92 07:15:02.3 0.8715 74782.5 17-Apr-92 07:25:02.3 0.7771 74791.6 17-Apr-92 07:35:02.3 u.9605 74760.7 17-Apr-92 07:45:02.3 0.9865 74766.5 17-Apr-92 07:53.02.3 0.9982 74762.0 17-Apr-92 08:05:02.3 I 0.9935 74759.0 17-Apr-92 08:15:02.3 0.9743 74757.2 17-Apr-92 08:25:02.3 0.9574 74753.1 p

17-Apr-92 08:35:02.3 0.94(r2 74749.6 17-Apr-92 08:45:02.3 0.9522 74737.6 17-Apr-92 08:55:02.3 0.9463 74737.4 17-Apr-92 09:05:02.3 0.9469 74730.7 17-Apr-92 09:15:02.3 0.9593 74721.0 17-Apr-92 09:25:02.3 0.9589 74720.3 17-Apr-92 09:35:02.3 0.9569 74716.1 17-Apr-92 09:45:02.3 0.9364 747'21.0 17-Apr-92 09:55:02.3 0.9503 74699.0 17-Apr-92 10:05:02.3 0.9574 74697.0 1

e.

.O M

2 VERMOFT YANKEE 1.8-1992 44 PSIG ILRT Verification Phase 1.6-l Containment Leakage versus Time E

1.4-eE Lo + Lam + 0.25 La '

(

}3 1.2-A 1

1-g e

o 0.8-

{

EP j

0.6 ~I Lo + Lam - 0.25 La '

A E

0.4-u 0

j 0.2-Composite Leakage i

~bo

,k 1

i Lam '

- i

-0.2 -

-0.4-J e

i

-0.6 i

i i

-4

-3

-2

-1 0

2 2

3 4

Elapsed Time (hrs) i I

j

'M.,i A

1. M

+r ab 4-B 6-4-.+--

?

4=W,r4.26-*

4 1=4#B+

M k i 'I.

- i1

- 8

'( _.

- 4 [' "

6.-

.. s Y

APPENDIX D TYPE B TEST RESULTS I -'

4' h.,

T S

i

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4 APPENDIX-D Husmary Test Results for Tvoe-B Testina Page 1-of 5 l

LEAKAGE {LBM/HR)-

1990 1992 PENETRATION NUMBER DESCRIPTION INITIAL RETEST INITIAL RETEST X Personnel Lock O.962 1.790 1.560 1.100 Bellows Seals X-7A Main Steam Line A 0.000 (1)

X-7B Main Steam Line B 0.000 (1)

X-7C Malti-Steam'Line C 0.000 (1)

X-7D Main-Steam Line D 0.000 (1)

X-9A Feedwater A:

0.000 (1)

X-9B-Feedwater B 0.000 (1)

X-11 HPCI f, team-Line 0.000 (1)

X-12' RHR Suction 0.000 (1)

X-13A RHR Return A 0.000 (1)

X-13 B RHR Return B 0.000 (1)

~X-14

. Cleanup Suction 0.000 (1)

X-16A

. Core Spray A 0.000 (1)

X-1GB Core' Spray B 0.000 (1) falectrical Penetrationo i:

100A.

Electrf. cal Penetration 0.001 0.001 100B-Electrical Penetration 0.007 0.037 100C-

' Electrical Penetration 0.001 0.000 100D Electrical Penetration 0.002 0.016 101A Electrical Penetration 0.001 0.035 101C Electrical Penetration 0.000 0.010

l:

['

APPENDIX D

)

Summary Test Results for Tyne B Testina Page.2 of'5 LEAKAGE (LBM/HR) 1990 1992

-PENETRATION NUMBER DESCRIPTION INITIAL RETEST INITIAL RETEST 101D Electrical Penetration 0.000 0.001 102 Electrical Penetration 0.011 0.029 103 Electrical Penetration 0.002 0.002 104A Electrical Penetration 0.001 0.036

-104B Electrical Penetration 0.001 0.000 104C-Electrical Penetration 0.001 0.026 105A Electrical Penetration 0.003 0.039 105B-Electrical Penetration 0.000 0.000 105C-Elsctrical Penetration 0.002 0.001 105D Electrical Penetration 0.008 0.012 214-Electrical Penetration 0.000 0.000 Double Gasketed Seals

'X-1 Equipment Hatch 0.001 0.001 0.000

~

X-3 Drywell Head Flange 0.013 0.003 0.008 X-4 Drywell Head Access 0.000 0.000 0.000 0.001 Hatch

'X Control Rod Drive 0.000 0.000-0.000 0.000 Removal X-35A TIP Penetration Flange 0.000 0.000 X-35B TIP Penetration Flange 0.000 0.000 X-35C.

TIP Penetration flange 0.000 0.000 X-35E TIP Penetration Flange 0.000 0.000 X-200A Torus Access Hatch 0.000 0.000 0.000 0.000 l

4-

[

APPENDIX D

y Summary Test Results for Tvoe D Testing Page=3 of 5 LEAKAGE (LBM/IIR) 1990 1992

,-PENETRATION DESCRIPTION INITIAL RETEST IMITIAL RETEST.

E' NUMBER

'X-200B Torus Access Hatch 0.000 0.000 0.000 0.000 VBC-A Vacuum Breaker Access 0.000 0.000 Cover VBC-B-Vacuum Breaker Access 0.000 0.000 Cover VBC-C Vacuum Breaker Access 0.000 0.000 0.000 Cover-VBC-D Vacuum Breaker-Access-0.000 0.00u 0.000

. Cover VBC-E Vacuum' Breaker Access C.000 0.000 0.000

-Cover VBC-F Vacuum Breaker Access 0.000 0.000 0.000 Cover VBC-G

-Vacuum Breaker Access 0.000 0.000 Cover

.VBC-H Vacuum Breaker Access 0.000 0.000

-Cover s

VBC-I' Vacuum Breaker Access 0.000 0.000

- Cove r -

VBC-J Vacuum Breaker Access 0.000 0.000 Cover VBSL-A Vacuum Breaker Shaft 0.000 0.000 Left

.VB"R-A Vacuum Breaker Shaft 0.000 0.000 Right VBSL-B Vacuum Breaker Shaft 0.000 0.000 Left VBSR-B Vacuum Breaker Shaft 0.000 0.000 Right VBSL-C Vacuum Breaker Shaft 0.000 0.000 0.000 l-Left I'

l L:

APPENDIX D

,y.

Summary Test Results for Tvon B Tesi,iD9 l

Page 4-of 5

{

LEAKAGE (LBM/HR)

. PENETRATION-1990 1992 NUMBER DESCRIPTION INITIAL RETEST INITIAL RETEST VBSR-C:

Vacuum' Breaker Shaft 0.000 0.000 0.000 Right VBSL-D Vacuum Breaker Shaft 0.000 0.000 0.000 Left VBSR-D-Vacuum Breaker ~ Shaft 0.000 0.000 0.000 Right'-

.VBSL-E Vacuum Breaker Shaft 0.000 0.000 0.000 Left VBSR-E

_ Vacuum Breaker Shaft 0.000 0.000 0.000

{

Right VBSL-F

-Vacuum Breaker Shaft 0.000 0.000 0.000 Left-

'VBSR-FL Vacuum Breaker Shaft 0.000 0.000 0.000 Right VBSL-G Vacuum Breaker Shaft 0.000 0.000 Left VBSR-G-Vacuum Breaker Shaft 0.000 0.000 Right VBSL-H; Vacuum Breaker Shaft 0.000 0.000 Left-VBSR-H.

Vacuum Breaker' Shaft 0.000 0.000 Right

.VBSL-I; Vacuum Breaker Shaft 0.000 0.000 Left VBSR-I' Vacuum Breaker Shaft 0.000 0.000 Right-

APPENDIX D:

Summary Test Results for Type B Tefting Page 5 of 5 LEAKAGE (LBM/HR) 1990 1992 q

PENETRATION 1

NUMBER DESCRIPTION INITIAL RETEST INITIAL RETEST VBSL-J-Vacuum Breaker Shaft 0.000 0.000 Left VBSR-J-Vacuum Breaker Shaft 0.000 0.000 Right

-)

SLH-A_

Shear Lug Access Cover 0.000 0.000 SLH-B Shear Lug Access Cover 0.000 0.000 SLH-C Shear Lug Access Cover 0.000 0.000 SLH-D Shear Lug Access Cover 0.000 0.000 SLH-E Shear Lug Access Cover

-0.001 0.004 SLH-F Shear Lug Access cover 0.000 0.000 SLH-G Shear Lug. Access Cover 0.004 0.004 SLH-H Shear Lug Access Cover 0.000 0.000

.X-213A Torus Drain 0.000 0.000 X-213B Torus Drain 0.000 0.000 l-

' NOTES:

(1)

Snoop checked during Type A ILRT.

No significant leakage noted.

p-

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l 1.

4-6 ia#,u

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5 As_L a-8.*Pa 4-

+JB

- - --A-G

-a@as=An

- M V04eA-A 4

44-J.

ea %Gd4e

.A-M-e4 A!

6 4L N4+L&

A-4dwemn,-

n

.6, AA-d--nf-a S

AL F--

-9.

,i? [N'

.: 3 i

4 ~

'. 's I

3 APPENDIX E TYPE C TEST RESULTS 4

a E

a d

1

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L, r

I I

f 1..:

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-pw e-e,-

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+

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e

o APPENDIX E Summary Test Results for Type C Testing Page 1 of 4 LEAKAGE (LBM/HR) 1990 1992 PENETRATION VALVE NUMBER TESTED DESCRIPTION INITIAL RETEST INITIAL RETEST X-7A MSCs0A A Main Steam Line 0.000 0.235 MS86A A Main Steam Line 0.738 0.715 X-7B MS80B B Main Steam Line 0.103 0.202 1

MS86B B Main Steam Line 0.347 0.452 X-7C MS80C C Main Steam Line 0.000 0.001 MS86C C Main Steam Line 0.347 0.393 X-7b MS80D D Main Steam Line 0.000 0.001 1

MS86D D Main Steam Line 0.365 0.483 X-8 MS-74 Main Steam Drain 0.000 0.007 MS-77 Main Steam Drain 0.077 0.182 0.282 X-9A FDW27A Feedwater Check O.237 0.001 0.024 0.378 Valve FDW28A Feedwater Check O.078 0.185 0.007 Valve X-9B FDW28B Feedwater Check 0.011

>14.75 0.015 Valve FDW96A Feedwater Check

>14.75 0.278 0.001 0.096 Valve X-10 RCIC-RCIC' Steam Supply 0.186 0.027 0.000 0.000 15 RC1C Steam Supply 0.313 0.002 0.002 RCIC-16 X-11 HPCI-HFCI Steam Supply 0.000 0.046 0.000 15 HPCI-Reactor Cleanup 0.077 0.077 0.328 0.002 16 X-14 RCU-15 Reactor Cleanup 0.048 0.003 0.007 0.025 RCU-18 Reactor Cleanup 0.011 0.015 0.002 l

\\. --

5 APPENDIX E S_4mmary Test losults f or Tyne C Tgp_t;jng Page 2 of 4 LEAKAGE (LBM/HR)

F0 1992 PENETRATION VALVE NUMBER TESTED DESCRIPTION INITIAL RETEST INITIAL RETEST X-16A CS-12A Core Spray Injection 0.015 0.012 0.002 CS-11A core Spray Injection 0.015 0.012 0.036 X-16B CS-12D Core Spray Injection 0.034 0.001 0.008 CS-11B Col Spray Injection 0.034 0.001 0.024 X-18 LRW-82 Drywell Floor Drain 0.369 0.275 0.400 0.011 LRW-63 Drywell Floor Drain 0.043 0.181 0.990 0.007 X-19=

LRW-94 Drywell Equipment 0.235 0.210 0.002 Drain LR'4-95 Drywell Equipment 0.052 0.079 0.002 D_raLn X-22 CA-89C Cont. Air Compressor 0.001 0.007 0.005 CA-89B Cont. Air C'mpressor 0.001 0.024 IA-103 Instrument Air Valva 0.043 0.024 X-25 SB-6, Containment Exhaust 0.016 0.049 0.138 0.159 7,

6A, (Per (Per (Per (Per 6B, 7A, valve) valve) valve) valve) and 7B X-25 VG-9A CAD Vent 0.001 0.024 0.002 VG-22A CAD Vent 0.151 0.044 X-26 XB-Containment Purge 0.000 0.146 0.104 8,9,10, (Per (Per (Per and 23 valve) valve) valve)

X-26 GB-22B Containment Purge 0.002 0.002 Makeup S0-20 Containment Purge 0.002 0.002 Makeup X-26 NG 13A CAD Injection 0.0025 0.0015 0.002

& 13B NG 11A CAD Injection 0.0015 0.0015 0.002

& 11B l

4i

.f APPENDIX E 33upma ry Test Results for Tyne C Testi_ng Page 3 of 4 LEAKAGE (LDM/HR) 1990 1992 PENETRATION VALVE NUMBER TESTED DESCRIPTION INITIAL RETEST INITIAL RETEST X-26 SD-51 PCAC 0.001 0.002 SB-52 PCAC 0.001 0.001 X-31F CRD-Recirc Pump Seal Purge 0.152 0.788 0.125 413A CRD-Recirc Pump Seal Purge 0.002 0.351 412A X-32F CRD-Recirc Pump Seal Purge 0.124 0.873 0.404 413B CRD-Recirc Pump Seal Purge 0.005 0.228 413B X-35A N/A Tip Purge PNL Check O.001 0.154 N/A Tip Purge Check Valve

0. 0~i 8 0.002 X-35C N/A Tip Ball Valve #1 0.090 0.068 X-35D N/A Tip Ball Valve #2 0.487 0.234 X-35E N/A Tip Ball Valve #3 0.068 0.035 X-41 RV-39 Recirc Sample 0.001 0.034 RV-40 Recire Sample 0.001 0.034 X-47 CA-38A Cont. Air Compressor 0.001 0.002 CA-36 Cont. Air Compressor 0.262 0.238 X-205 NG 12A CAD Injection 0.0005 0.002 0.002

& 12B NG 11A CAD Injection Note (1)

Note (1) 0.002

& 11B Page 4/4 Page 4/4 X-205 SD-11A Vacuum Relief 0.024 0.150 0.623

& 12A (Total)

(Total)

SB-118 Vacuum Relief 0.030 0.352 0.750

& 128 (Total)

(Total)

t APPENDIX P gu,mmary_Tepl rcd 311ta f or Tvne c Teating Pago 4 of 4 n.,

LEAKAGE (LBM/IIR) 1990 1992 PENETRATION VALVE NUMSER TESTED DESCRIPTIOta INITIAL RETEST INITIAL RETEST X-205 SB-22A Containment Purge 0.002 0.002 Hakeup SB-20 Containment Purge (1)

(1)

H&keup S D-2'4 B Containment Purge (1)

(1)

Hakeup X-216 VO 'i6A Rad. Hon. Return 0.003 0.002 VG-76B Rad. Hon. Return 0.001 0.002 X-218 VG-9B CAD Vent 0.006 0.062 i

VG-22B CAD Vent 0.001 0.143 3

X-220 VG 26 CAD Rad. Hora. Suppif

').014 0.001 VG-23 CAD Rad. Hon. Supply 0 015 0.017 D

Noton (1) Reported Under X-26 (2) Could Not Pressurize Valve / Valve Group Utilizi.ng Existing Equipment I

2

\\

_

ML20102A593

Text

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