ML20236H378

App I TMI-1 1987 Reactor Bldg Local Leak Rate Testing Rept, Updated-871009, for 861104-870318

ML20236H378
Person / Time
Site:	Three Mile Island
Issue date:	10/09/1987
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20236G524	List: ML20236G521 ML20236H378
References
NUDOCS 8711040093
Download: ML20236H378 (22)

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t APPENDIX I l

THREE MILE ISLAND UNIT 1 j i '

1987 REACTOR BUILDING LOCAL LEAK RATE TESTING REPORT UPDATED - OCTOBER 9, 1987 I SP 1303-11.18

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11/4/06 to 3/10/87 1

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INDEI - 198_7 R. B. LOCAL LEAK RATE TESTING REPORT

1. PURPOSE

2.

SUMMARY

OF WORK ACCOMPLISHED 2.1 Valve Testing / Repairs 2.2 Access Hatches 2.3 Penetration Pressurization

3. METHODS OF TESTING 3.1 Valves 3.2 Access Hatches 3.3 Penetration Pressurization

4. TEST EQUIPMENT USED 4.1 Valves 4.2 Access Hatches 4.3 Penetration Pressurization

5.

SUMMARY

AND INTERPRETATION OF DATA 5.1 Valves 5.2 Access Hatches 5.3 Penetration Pressurization

6. EBROR ANALYSIS 6.1 Valves 6.2 Access Hatches 1

6.3 Penetration Pressurization

7. REFERENCES

8. ATTACHMENTS 8.1 Results Evaluation Procedure / Repair Criteria 8.2 Tabulation of Individual Test Repales 72.0 0111U l

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REACTOR BUILDING LOCAL LEAK RATE TESTING' REPORT 1987 REFUELING FREQUENCY

1. PURPOSE 1.1 To provido analysis to the Nuclear Regulatory Commission on the tenth periodic type B and type C loakage tests performed on the Three Mile Island Unit 1 Reactor Building.

This is in accordance with " Reactor Containment Leakage Testing for Water Cooled Power Reactors". Appendix J, Part 50, Title 10 Codo of Federal Regulations which required the contents of this summary report to becomo part of the Type A test report along with the details of any other typo B and type C testing performed since the previous type A test (also required per technical specification 4.4.1.1.8).

TMI Unit I restarted October 3, 1985 af ter a prolonged shutdown which began March 28, 1979 (TMI Unit II accident). For this round of leak rate testing the plant was shutdown for the 6R Refueling Outage. Testing began on November 4, 1986 and was still in progress at the time the original report was submitted (02-09-87; Record No.

5211-87-2030). This report has been updated to reflect the As-Left testing data at the completion of the 6R Refueling Outage (03-18-87).

2.

SUMMARY

OF WORK ACCOMPLISHED 2.1 Valve Testing / Repairs Appendix J Type B and C leak tents woro performod on the components i as listed in TMI Unit 1 Technical Specification 4.4.1. In addition l the following components woro leak tested though not yet listed in  :

the Technical Specification.  ;

l 1. HM-V1A/B, 2A/B, 3A/B, 4A/B - New System

2. NI-V26.  ;

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3. PP-V101/102/133/134 i

Ropairs were initiated on the following components due to higher '

than desirable leakage, j

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1. IC-V3 replaced with a new valvo - upgrado  !

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2. IC-V4 replaced with a now valvo - upgrado i'

3. AH-V1A - Seat leakago

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4. AH-VID - Seat leakago 73.0

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5. Penet 211 - Test connection' cap leak - replaced improper 1 fitting (doublo / tubing connector as-found rather than the l single connector desired. Resulted in pipe threads mating '

with tubing threads with resultant thread leakage).

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6. MU-V2A - Packing leakage l

7. PP-V101/102/133/134 - Seat leakago l l

8. CA-VSA/B - Seat leakago

9. LR-V1/10 - Seat leakago Additional leak tests woro performed on the following components:

1. CA-V1/2/J/13 - Modified packing configuration-

2. FTT East /FTT West - Rotested af ter refueling

3. MU-V2A/28 - Modified packing configuration l

4. PENET. 104/210/211 - Rotested after refueling

5. HR-2A/B/4A/B - Associated flanged service connections tested before being opened and after being closed.

2.2 Access Hatch Testing / Repairs l

2.2.1 Door Seals SP 1303-11.25 (Ref. 7.6) ,

l Door seal leak tests are performed as required by Technical I

, Specification 4.4.1.2.5. All of the tests satisfied the

! surveillance procedure administrative acceptance criteria.

2.2.2 Overall Hatch Test (Ref 7.5)

Somiannual integrated type leak tests 9are performed as required by Technical Specification 4.4.1.2.5. All of the tests satisfied the surveillance procedure acceptanco criteria.

2.3 Penetration Pressurization SP 1303-11.24 (Ref 7.5)

Quarterly readings are recorded from the flow rotameters which supply air pressure or nitrogon pressure to reactor building mechanical and electrical ponotrations as required by Technical Specification 4.4.1.2.5. No penetration leakage problems were noted although flowmotor malfunctions required motor repair.

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3. MITHODS OF TESTING 3.1 Valve Test Methods i

. l Testing was performed by use of TMI Unit i surveillance procedure SP l 1303-11.18 koactor Building Local Leak Rate Testing. This procedure gives detailed guidance on the test equipment and methods to be used .

I for each penetration / valve. The following general philosophy is I contained in the surveillance procedure.

3.1.1 Use air or nitrogen at a pressure differential across the valve greater than p (50.6 - calculated accident pressure). 55 psig nitrogen was normally used.

1 3.1.2 Assure that the pressure is exerted in the accident test )

direction unless it can be demonstrated that pressurizing in j the opposite direction is as conservative. Butterfly valves  !

AH-V1B/1C, and globe valves WDG-V4, DH-V64, SA-V3, and IA-V20 l were tested in the revers 6 direction.

3.1.3 Assure that the test volume is drained of liquid so that air or nitrogen test pressura is against valve seats.

3.1.4 Assure that the test verifies valve packing integrity in those cases where the packing would be an.R. B. leakage boundary.

3.1.5 Assure adequate time period for stabilization of test I conditions.

3.1.6 Assure test equipment is calibrated and used in a manner consistent with the data accuracy desired (weekly meter standardization was performed during the test program to verify meters accurate within i 4% full scale (Ref. 1.1).

3.1.7 Assure valves to be tested are closed by the normal method prior to testing.

3.1.8 Document as-found conditions (prior to adjustments / repairs) and as-left conditions.

3.1.9 Record test instrument 3g dg readings prior to doing any data corrections.

3.1.10 Assure that system drains and vents which could serve as containment isolation valves, are closed and capped and tagged after completion of the test program. l l

A training program prior to the refueling outage was  !

performed to help assure that the above philosophy was understood by the personnel involved in the testing.

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3.2 Access Hatch Test Methods 3.2.1 Door Seal Leak Tests-Method Door seal leak tests were performed by use of SP 1303-11.25 (Ref. 7.6). This procedure gives detailed guidance on the  !

test equipment and methods to be used.

The door seal tests are performed by pressurizing the interspace between the double seals on each door with metered ]

air at the manufacturers recommended test pressure of 10 pois. After stabilization the air rotameter indicates the rate of air input required to maintain the test pressure. ]

3.2.2 overall Match Leak Test -- Semi-annual overall hatch leak testing was performed by use of TNI Unit 1 Surveillance j Procedure SP 1303-11.18 Reactor Building Local Leak Rate Testing. This procedure gives detailed guidance on the test equipment and methods to be used.- The overall integrated leak test verifies the integrity of all of the following barriers:

a. Hatch shell/ welds,

b. Bubber door seals,

c. Teflon operating shaft packing, l l

d. Bulkhead electrical penetrations,

e. Penetration pressurization check valves,

f. Emergency air flange and associated "0" rings on outer bulkhead,

s. Bulkhead equalizing ball valves and associated mounting flanges /"0" rings.

The overall leak test is performed by pressurizing the hatch to greater than calculated accident pressure and observing the rate of pressure drop on a high accuracy (Heise) pressure gase.

Pressure corrections are made by reference to a barometer.

Minimum test duration is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stabilization period.

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3.3 penetration pressurization - Msthod

! Quarterly readings were taken on the flow rotameters which are permanently installed in the penetration pressurization system.

These readings represent the air / nitrogen makeup rate required to .i maintain approximately 60 psis in mechanical penetrations and 30  !

pois in electrical penetrations. High meter readings have l occasionally occurred but these have been attributed to leaks in the I compression fittings in the penetration pressurization system or to l malfunctioning (stuck) rotameters. Testing was per plant surveillance procedure SP 1303-11.24 (Ref. 7.5). i I

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4. TEST EQUIPMENT USED ,

4.1 Valve Test Equipment (See Figure 1)

a. Rotameters - Sets of 3 l Mfge. - Brooks Inst. Co.

Model - 1}14 Full View i t i r' Ranges: ', ,

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1 /, l Float Mat'1. Tube No. ,;janae ,r

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Pyrer R-2-15D' 8-1.120 SCCM /

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l Sacchire R-2-150' 100-12.200 SCCM (

I Carboloy R-6-153 1,000-142,000 SCCM )

Accuracy t 2% full scale industrial accuracy h

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b. Temperature Indicators (as follows or similar)

Mfge. - Ashcroft j J i Model - RH or AH / 3" orl5" Dial Range - 30 0 -130 0F e N

. e' Accuracy - 0 2F

c. Pressure Indicators (as follows or similar)

Mfge. - Ashcroft .

Model - 1279 1/2" Dial ,

t Range 60 or 0-100 psis s Accuracy - t 2 pois ,-

d. Pressure Regulator (as follows or similar) q.

, h Kfgr. - Union Carbide Corp.

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Model - UPG 3-75-580

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Range 100 psi ou*aut / 0-3000'p si input ', j

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e. Calibration Rotameters (Set of 2)

Mf5r. - Brooks Inst. Co.

Models - 1110-05K2B1Z49, 1110-08K281206 t

, i Ranges 16,000 SCCH, 3 600-234,000'SCCM a / i' Repeatability - t 1/4% cf instan,taneous

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Accuracy - t 1% instantaneous f/ { ,

f. Flow rate Calibrator ,/ j

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Mfge. - Brooks Inst < Co.  ;

Model - 1056A Rante O to 2,400 SCCM Accuracy - 0.2% of indicated voluna < /

4.2 Accese Hatch Test Eauipment 4

a. Precision Pressure Gage (ad follows or similar) ,

Mfge. - Heise Model - CM -

Range - 0.60 psig Resolution - 0.25 pois 1

Accuracy - 0.1%

b. Baronetse (as follows or similar) 1 Mfge. - Pennwalt Model - FA185260A '

Range - 10.8 - 15,5 psia j i

Resolution - 0.005 psia i

Accuracy - 0.1% , /. j l

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l 4.3 Penetration Pressurization Test Eauipment 1 i

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a. Flow Rctameters - (Permanent System Equipment)

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Model - 1114

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Range 10 SCFH at 60 psia air i ,

Accuracy - t 2% Industrial accuracy

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5.

SUMMARY

AND INTERPRETATION OF DATA 5.1 Valve Test Results As-Found/As-Lef t Leakage to this date - Also see tabulation of individual results in Attachment #2.

Total Leakage Tech. Spec. Limit  % Tech. Spec. Limit As-Found MAXPATH >162,105 SCCM 104,846 SCCM >100%

As-Left MAXPATH 29,906 SCCM 104,846 SCCM <30%

NOTE: The total shown above is " maximum pathway" and not the total of all valvo leakages. i.e., Only the highest valvo leakage on each penetration is counted. This number is labeled as.

"MAXPATH" on the tabulation of results.in Attachment 2.

EXAMPLE: Penetration XYZ has three containment isolation valves inside the reactor building in parallel and one outside. The leakage from the three inside totals 500 SCCM and the outside valve is 1000 SCCM. The penetration leakage is counted as 1,000 SCCM not 1,500 SCCM.

5.2 Access Hatch Test Results 5.2.1 Overall Hatch Leakage - SP 1303-11.18 (Ref. 7.2) - See the computer tabulation of 1987 leak rates in Attachment II.

5.2.2 Door Seal Leakage - SP 1303-11.25 (Ref. 7.6)

None of the door seal leak' tests exceeded the 3 SCFH I administrative leakage limit. Typically the leakage was

<1 SCFH.

5.3 Penetration Pressurization (PP) Leakage - SP 1303-11.24 (Ref. 7.5) l Leakage Rates - SCFH l

l Mechanical Electrical l

Date 12/12/86 21.5 0.0 03/14/87 8.5 0.0 There is no technical specification limit on penetration pressurization system leakage. The system leakage is maintained as low as practical.

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6. ERROR ANALYSIS 6.1 Valve Testina Errors _(For purge valves see Section 6.2)

The flow meters used in the field have normal industrial accuracles of t 2% full scale in the 10-100% (15-150 mm) scale range. Prior to i use, ma versus sc:a graphs were developed for the meters by 10 point calibrations using high accuracy (t 1% instantaneous) lab rotameters. Dur(ng the leak test program, weekly 3 point ,

standardization were performed on the field rotameters to verify continued accuracy. The acceptance criteria for these standardization was a variance of no more than 4% from the calibration graphs. If meters were repaired or the 3 point standardization exceeded the inaccuracy. Limit, a new 10 point calibration was performed. Scale readings on the leak rate procedure (SP 1303-11.18) data sheets were evaluated and corrected using the methods in Attachment 1. Conservative bias was introduced into the results by assuming 15 num (10% of scale) as the minimum scale. Approximately half of the test results actually showed a minimum scale reading. More involved error corrections were not considered meaningful based on the acceptable total leakage as-found and the low total leakage as-left.

6.2 Access Match and Purne Valve Testina Errors-The measured pressure drops were corrected by adding the minimum scale increment of the sage used for'both the heise sage and the barometer. This conservatively corrected for the resolution and repeatability errors, Gages used were recently calibrated. A minimum one hour temperature / pressure stabilization period was used prior to each pressure drop test. The access hatches and purge valves are not instrumented to allow temperature coercetions.

6.3 penetration Pressurization Testina Errors

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These test results are used for information only and do not count )

toward the total leakage limit for Technical specification l' conformance. The meters, installed permanently in the system, have t 2% full scale industrial accuracy.

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7. REFERENCES 7.1 1430-Y-22 Standardization of Flow Rotamotors (Rev. 4) ]

7.2 SP 1303-11.18 Reactor Building Local Leak Rate Testing (Rev. 38) w/TCN 1-86-0179 (RB-V2A/7 Testing). .

7.3 Three Mile Island Unit i Technical Specif'ication 4.4.1 I I

7.4 TMI Surveillance File (for Data sheets) 7.5 SP 1303-11.24 R. B. Local Leakage Penetration Pressurization (Rev. 6) 7.6 SP 1303-11.25 R. B. Local Leakage Access Hatch Door Seals (Rev. 11).

7.7 SP 1303-11.18 Reactor Building Local Leak Rate Testing (Rev. 38) w/TCN 1-87-0021 (PP-V101/102/133/134 Testing).

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I ATTAC10ENT 1 RESULTS EVALUATION PROCEDURE (SP 1303-11.18 Enclosure 9)

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Attcchment 1 R. B. LOCAL LEAN RATE TESTING RESULTS EVALUATION The vent rotameter reading will be used if it can be demonstrated by the test data that all significant CIV leakage is being accounted for. If CIV packing, fluid block check valve, or gaaket leakage was evident the supply rotameter results will be used unless this non-seat leakage was measured reliably and documented.

FOR USE OF SUPPLY ROTAMETER DATA: FOR USE OF VENT ROTAMETER DATA:

Proc edure : Proc edure :

a) Record supply meter reading in (1) a) Record vent meter reading in (1) below*. Also identify the meter below.e used by tube # in (8) below and the metering pressure in (9). b) Record downstream verification meter reading in (2) below. Also b) Convert meter units in SCCM units identify the respective meters used using latest lab meter calibration in (8) below and the metering curve. Enter in (3) below. pressure in (9).

c) Correct results for temperature. c) Convert meter units to SCCM units Enter supply temperature in (4) using latest lab meter calibration below, curve. Enter in (3) below.

Calculate and enter in (7) below, d) Correct results for temperature.

Enter vent temperature (OF) in (4) below.

then Calculate and enter in (5) below e) If measurements of any other significant leakage paths (fluid

• If meter scale reading wat less ' block check valve, packing) are than 15 mm (minimum scale) use being claimed enter corrected flow 15 mm in calculations. (SCCM) in (6) below.

(MH) (SCCM) 530

( + )C'8'*I8( + )x + 460 = SCCM (1) (2) (3) (4) (5) I

+ SCC t  !

(8) (Identify meters used) (6)

@ = CIV Leakage SCCM I (9) (Macer Pressures) (7) 87.0 0111U

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ATTACHMENT 2 l 1

DATA 1987 TYPE C REACTOR BUILDING LEAX RATE TESTING l

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• LOCAL LEAX RATE TEST RE5t.7 TS THREE MILE ISLAND UNIT I REACTOR SUILDZNG 1987 1987 1987 1987 1987 1987 1987 1987 RESULTS GIVEN IN STD. CUBIC CENTIMETERS PER MINUTE (SCCM)

NO TAG DESC OPER SIZE ASFOUND ASLEFT COMT387 DATE ese enemones messeeen vessee een seemmessee eenesesse sessense enesee..

1 AH-VIA/3 3 FLY P/MO 49 .01 546 ASFD86 3/16/87 j 2 2ND 48 .gi .01 j 3 3RD 48 .31 *01 l 4 4TH 48 .91 .01 5 AH-V1C/D 3 FLY M0/P 48 .61 2750 ASFD86 3/16/87 6 2N3 48 .41 .01 7 3RD 48 .61 .01 8 4TH 48 .41 .01 9

it 11 CA-Vi GLOSE MO 71 65 12 CA-Y2 GATE P 1 OK 3/13/87 1 1132 65 HIGH 3/13/87 13 CA-V3 GLOBE MO 71 52 14 CA-V44 GLOM MO i 1 OK 3/14/87 71 71 15 CA-V43 GLOBE MO i 98 OK 12/3/86 98 OK 12/3/86 16 CA-VSA GATE P 1 4487 243 17 CA-V53 GATE P 4947 HIGH 3/10/87 1 250 HIGH 3/10/87 10 CA-V13 GLOM MO 1 71 52 19 CA-V189 GATE P. 2 1389 OK 3/14/87 1389 HIGH 12/ /86 29 CA-V192 LFT CHN N/A 2 71 71 LOW 21 12/1/86 l 22 23 CF-V2A GLOBE MO i 4e 40 OK 11/21/86 24 CF-Y23 GLOM MO i 38 38 OK ii/22/86 25 CF-V124 LFT CHN N/A i 13 13 OK 26 CF-V123 11/25/86 LFT CHN N/A i 88 88 OK 11/25/86 )

27 CF-V19A GATE P 1 1396 1306 HIGH 28 CF-V193 GATE 11/26/86 P 32 32 29 CF-V20A GATE P 1

OK 11/25/86 1 347 367 OK 11/22/86 '

30 CF-V243 GATE P 1 38 38 31 CM-Vi BALL P OK 11/22/86 I 1 75 75 OK 12/9/86 32 CM-V2 BALL P 1 319 319 HIGH 33 CM-V3 BALL P 12/9/86  !

1 75 75 OK 12/9/86 34 CM-V4 BALL P 75 75 35 DH-V44 GLOSE HW 1

2 OK 12/9/86 39 39 OK 1/6/87 36 DHaV69 STOP CMC HW 2 44 46 OK 37 1/6/87 38 39 FTTEAST FLANGE N/A 38 145 338 OK 40 FTTWEST 3/4/87 FLANGE N/A 34 52 353 OK 3/4/87 )

41 HMeV1A GLOSE f .5  :

75 75 OK 12/6/86 42 HMeViB GLOM S .5 75 75 i

43 HM-V2A GLOM S .5 75 OK 12/6/86 'l 75 OK 12/6/86 1 44 HM-V2B GLOM J .5 75 75 OK 45 HM-V34 12/6/86 GLOSE I .5 75 75 OK 12/6/86 44 HM-V3B GLCM J .5 75 75 OK 47 HM-V44 12/6/86 GLOBE K .5 75 75 OK 12/6/86 j

48 HM-V4B GLOBE 3 .5 75 75 OK 49 HP-Vi 12/6/86 i GATE HW 6 75 75 OK SS HP-V4 GATE HW 12/9/86 5 6 75 75 51 HR-V2A/S GLOSE OK 12/9/86 HW 2 66 86 OK 12/10/86 52 HR-V4A/S GLOM HW 2 273 76 OK 12/10/96 l 53 HRV22A/S GLOBE S 2 74 76 OK 12/10/86 54 HR-V234 GLOBE 3 2 74 76 55 HR-V23B GLOBE 3 OK 12/10/86 2 74 76 OK 12/10/86 56 89.0 l

LOCAL LEAK RATE TEST RESL1TS THREE M1LE ISLAND UNIT 1 REACTOR BUZLDZNG 1987 1987 1987 1987 1987 1987 1987 1987 RESULTS GlyEN IN STD. CUBIC CENTIMETERS PER MINUTE (SCCM)

NO RAG DESC OPER SIZE ASF QUND ASLEFT COMTS87 'DATE

• • • ensanoen essensen meeson ese menemmenee messeswee messenee sensesse 57 58 IA-V4/24 GLOM HW 2 52 52 OK 12/5/84 59 IC-V2 GATE NO 4 194 194 OK 11/12/86 44 IC-V3 GATE P 4 18544 44 NEWVALVE 2/3/87 41 IC-V4 GATE P 4 71 42 NEWVALVE t/24/87 62 IC-V4 GATE P 3 47 47 OK 11/17/84 63 IC= Vie CHECK N/A 4 141 141 OK 11/17/86 44 IC-V10 CHECK N/A 4 71 71 OK i1/11/86 45 LR-Vt/10 GATE HW 4 1904 76 OK 12/5/86 44 LR-V4 GLOM HW .75 52 52 OK 12/5/86 l

67 LR-V5 GLOBE HW 2 52 52 OK 12/5/06 68 LA-V4 GLOM HW 2 52 52 OK t2/5/86 49 LR-V49 GATE MW 4 76 74 OK 12/5/86 74 71 72 MU-V2A GLOM MO 2.5 52874 65 PACKING 3/7/87 73 MU-V2B GLOBE NO 2.5 72 106 OK 3/7/87 74 MU-V3 GATE P 2.5 66 66 OK 3/6/87 75 MU-V10 GATE P 2.5 334 334 OK 12/8/04 74 MU-V24 GATE P 4 44 44 OK 11/15/86 77 MU-V25 GLOBE MO 4 88 88 OK 11/24/04 78 MU-V24 GATE P 4 88 80 OK 1i/24/86 79 MU-Vite PIST CHK N/A 1.5 1319 1319 OK 11/15/86 84 81 NI-V24 GLOSE HW 1 71 71 OK 12/2/86 82 NI-V27 GLOM HW 1 71 71 OK 12/2/86 83 NS-V4 GATE . MO 1.5 421 621 OK 11/20/86 84 NS-Vit CHECK N/A 8 1814 1814 OK 11/19/86 85 NS-V15 GATE MO 8 1442 1642 OK 11/19/86 86 NS-V35 GATE MO 8 7407 495 HIGH 12/19/86 87 88 89 PENET194 BLK FLG N/A 2 71 71 OK 3/14/87 90 PENET195 BLK FLG N/A to 45 45 OK l

12/13/86 91 itNETite SLK FLG N/A 4 45 45 O K' 12/13/86 92 L 2ET2tG SLK FLG N/A 2 45 71; OK 3/14/87 i 93 PENET211 SLK FLG N/A 2 18452 71 CAP LEAK 3/14/87 94 PENET241 SLK FLG N/A 18 92 45 OK 12/12/86 95 PP191/02 LFT CHN N/A t/2 37000.001 6142 FAILED 3/10/87 94 PP133/34 LFT CM N/A t/2 3120 5491 HIGH 3/13/87 97 90 99 104 101 RB-V2A GATE NO 8 884 See OK 11/18/84 142 RS-V7 GATE MO 8 4 '4 11/22/86 103 SA-V2/3 GLOBE HW 2 88 88 OK 3/17/87 144 SF-V23 GATE HW 8 42 42 OK 12/4/86 105 WDG-V3/4 GL/GA M0/30L 2 82 82 OK 12/2/96 144 WDL-V343 GLOM MO 4 25 25 OK 1i/24/84 147 WDL-V304 GATE D 4 25 25 OK 11/24/86 108 WDL-V534 GATE P 8 71 71 OK 12/11/84 169 WDL-V535 GATE P 8 71 71 OK 12/11/86*

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111 90.0 L_ _ _____ _ _ _ _ _ _ _ _ _ _ _ _ _

LOCAL LEAK RATE IESE RE5LIIs TRREE M81.E ZSt.AND UNZT 1 REACTOR BUZLD!NG 1987 1987 1987 1987 1987 1987 1987 1987 RESULTS GIVEN IN STD. CUBIC CENTIMETERS PER MINUTE (SCCM) l

)

NO TAG DESC OPER 31ZE I

AKFOUND ASLEFT COMT387 DATE j 112 ESPFLG FLANGE N/A 216 243 77 HIGH i/2/87

)

113 PERACCES MISC. N/A 96 1783 1783 OK 114 2ND N!!C N/A 96 3/i7/87 l )

j 115 EMEACCEJ MISC N/A 96 891 891 OK 114 2ND MISC N/A 96 3/18/87l i 117  !

l 118 119 MIMPATH i 67426.021 23668 FAILED 11/11/8e '

i 129 MAXPATN

• 162105.021 29906 121 ACC CRIT FAILED 3/18/87 194847 104847 i l

i The semiannual and quarterly tests perform.d nearest to the round of refueling frequency testing are added into the "MAXPATH" calculation. For valves in series the valve with highest leakage is used in the ":IAXPATH" calculation, j For valves in parallel or where the inner and outer valves can not be tested separately, the total leakage is used. '

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91.0 l

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LOCFL LEAK RATE TEST RESULTS THREE MILE ISLAND UNIT 1 REACTOR BUILDING Following is the terminology used in the previous computer data:

1) .1 - ( Alone) or any other number other than zero in the first decimal place means test scheduled.

2) .01 - (Alone) means no data available for the year or that the test was ,

delayed. (e.g. valve not installed yet or not in previous testing scopo.) '

3) .001 - (or any number other than zero in the third decimal place) af ter a leak rate (i.e. 59500.001) means actual leak rate was greater than measured / recorded value.

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4) AsFound - leak rate (SCCM) in the As-Found condition before any repairs or adjustments.

5) AsLeft - The leak rate (SCCM) after any adjustments / repairs.

6) Datos - Date of the last acceptable tost results for the item.

7) Desc - Description of the valve or penetration,

8) Oper -- Type of valvo operator (actuator) .

9) Notest - The Tech Spec scopo did not require this valve to be testod during the respectivo year.

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10) Novalvo - This valve was installed during a later refueling outage. i

11) Comments - Cognizant Engineer comments about the results:

A) Failed - Exceeded the plant established leakage rato limit from )

SP 1303-11.18 Enclosure 10 which made repair / adjustment necessary. I B) High/ Low - Subjective judgement of cognizant engineer. Represents the results with respect to the leakage which the type of leakage barrier (e.g. gate valve, globe valvo, check valve, flange, etc.) is considered to be capable of without extraordinary repair / adjustment C) OK - No problems with leakage. ,

l D) Other - E.G. newvalvo, novalvo. notest, repacked seatwork, stembent, etc, ( s e lf-ex planatory ) . l E) CAPLEAK - see para. 2.1.5 PACKING - see para. 2.1.6.

12) Sizo - The nominal pipe sizo for the leakago barrior.

13) ASFD86 - Identifies that the ASFD data to be used for AH-V1A/B & C/D is the last test data reported for 1986; soo Attachment 2 of Appendix H.

92.0 0492C ,

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