ML20031D478

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Reactor Bldg Local Leak Rate Testing Repts for 1979-81
ML20031D478
Person / Time
Site: Crane 
Issue date: 08/08/1981
From: Roxanne Summers
METROPOLITAN EDISON CO.
To:
Shared Package
ML20031D470 List:
References
SP-1303-11.18, NUDOCS 8110130377
Download: ML20031D478 (69)
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Text

_ _

APPENDIX F THREE MILE ISLAND UNIT 1 l

i J

p 1979 REACTOR BUILDING LOCAL LEAK RATE TESTING REPORT SP 1303-11.18 (4/78 - 12/31/79) j I

Prepared t bh- ' -

R. L. Summers Engineer Senior I - Ti1I-l

.', 8110130377 811006

.PDR ADOCK 05000289 P

PDR

INDEX - 1979 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.

ERROR ANALYSIS 6.1 Valves 6.2 Access Hatches 6.3 Penetration Pressurization 7.

REFERENCES 8.

ATTACHMENTS 8.1 Results Evaluation Procedure / Repair Criteria 8.2 Tabulation of Individual Test Results,

REACTOR BUILDING LOCAL LEAK ?AlE TESTING NRC REPORT REFUELING FREQUENCY 1.

PURPOSE 1.1 To provide analysis to the Nuclear Regulatory Commission on the burth periodic type B and type C leakage tests performed on the Three Mile Island Unit I reactor building.

This is in accordance with " Primary Reactor Containment Leakage Testing fur Water Cooled Power Reactor." Appendix J. Part 50, Title 10 Code cf Federal Regulations which required the contents of this summary report to become part of the type A test report along with the details of any other type B and type C testing per-formed since the previous type A test.

(Also requ' ired per tech-nical speci fication 4.4.1.1.8).

Note that from 4/79 to 12/79 the reactor was in long term cold shutdown due to the March 28, 1979, Unit II accident.

2.

SUMMARY

OF WORK ACCOMPLISHED 2.1 Valve Testing / Repairs A total of approximately 74 valve seat and/or packing leak tests were performed between 4/78 and 12/79.

Leakage was high on LR-V2, AH-VlB, CA-V5B and RB-V7.

Repairs were as follows:

a. AH-VlB - Seat Tightened
b. CA-V5B Stem straightened / valve repacked
c. RB-V7

- Seat / disc lapped to reseat

d. IC-V3

- Repacked

c. RB-V2A - Repacked - _ _ _ - - _ _ - _ - _ _ _ _ _ _ _ - _ _

Per the " repair criteria" (see Attachment #1) LR-V2 required corrective action. A valve disc modification was accomplished during 1980 to greatly reduce the leak rate.

A licensee event report (LER#79-06) was submitted to the NRC for high total leakage, as-found, caused mainly by the CA-V5B damage.

2.2 Access Hatch Testing / Repairs 2.2.1 Door Seals SP 1301-11.25 During reactor operation door seals were tested after each use but no more frequently than daily. Weekly door seal leak tests were performed during the cold shutdown portior, of the time period. Occasional seal replacement was performed in response to high leakage although the as-found leakage at no time violated technical specification requi rements.

2.2.2 Overall Hatch Test The following leak tests on each access hatch were per-formed between 4/78 and 12/79. No repairs were initiated as a result of these tests.

Date Personnel 6/78, 12/78, 6/79, 12/79 Emergency 6/78, 12/78, 5/79, 12/79 2.3 Penetration Pressurization SP 1303-11.24 Quartarly readings were recorded on 6/78, 8/78, 12/78, 3/79, 6/79, 9/79 ard 12/79 from the flow rotometers which supply air pressure or nitrogen pressure to reactor building mechanical and electrical._

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penetrations. No penetration leakage problems were noted although flow mater malfunctions required occasional meter repair.

3 METHODS OF TESTING 3.1 Valve Test Methods Testing was performed by use of TMI Unit 1 surveillance procedure SP 1303-11.18 Reactor Building Local Leak Rate Testing.

This pro-cedure gives detailed guidance on the test equipment and methods to be used for each penetration / valve. The following general

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philosophy is contained in the surveillance procedure.

3.1.1 Use air or nitrogen at a pressure differential across the valve greater than Pa (Calculated accident pressure).

55 psig was normally used.

3.1.2 Assure that the pressure is exerted in the accident test direction unless it can be demonstrated that pressurizing in the opposite direction is as consersative. Butterfly valves AH-VlA/lB/lC/lD, and globe valves WDG-V4,.SA-V3 and IA-V20 were tested in the reverse direction.

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

3.1.4-Assure that the test verified 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 condi tions.

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3.1.6 Assure test equipment is calibrated and used in a i

manner consistent with the data accuracy desired.

(Weekly meter standardization was performed to verify meters accurate within + 5% full scale - MP 1430-Y-22).

}

3.1.7 Assure that the fluid blocking system is drained.and vented during tests on the associated containment iso-lation valves to prevent any effects it might have on the test results.

(Most of the F.B. ' system piping is seismic 3) 3.1.8 Assure valves to be tested are closed by the normal method prior to testing.

4 3.1.9 Document as-found conditions (prior to adjustments /

repairs) and as-left conditions.

i 3.1.10 Record test instrument scale readings prior to-doing any data cor rections.

3.1.11 Assure that system drains and vents which could serve as i

containment isolation valves, are closed and capped and tagged after completion of the test program.

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.

3.2 _ Access Hatch Test Met. hods 3.21.

Door Seal Leak Tests-Methud I

Door seal leak tests were performed by use of SP1303-11.25.

This procedure gives detailed guidance on the test equip-ment and methods to be used.

I 4

The door seal tests were performed by. pressurizing' the interspace between the double seals on each door with r,etered air at 55 psig. After stabilization the air rotameter indicates the rate of air input required to maintain the test pressure.

3.2.2 Overall Hatch Leak Test - Overall hatch leak testing was performed by use of TMI Unit 1 Surveillance Pro-cedure SP1303-ll.18 Reactor Building Local Leak _ Rate Testing. This procedure gives detailed guidance on the test equipment and methods to be used.

The overall (integrateo) leak test verifies the integrity of all of the following barriers:

a. Hatch shell/ welds,
b. Rubber door seals,
c. Teflon operating shaft packing,
d. Bulkhead electrical penetrations,
e. Penetration pressurization check valves,
f. Emergency air flange and associated "0" rings on outer
bulkhead,
g. Bulkhead equalizing ball valves and associated mounting flanges /"0" rings.

i l

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

Pressure corrections are made by reference to a barometer.

i 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.,

c.

Pressure Indicators (as follows or similar)

Mfgr. - Ashcroft Model - 1279 - 41" Dial 3

Range 0 - 60 or 0 - 100 psig Accuracy 1 2 psig d.

Pressure Regulator (as follows or similar)

Mfgr. - Union Carbide Co. p.

Modei - UPG 3-75-580 Range 0-100 psi outlet / 0-3000 psi input e.

Calibration rotameters (Set of 3)

Mfgr. - Brooks Inst. Co.

Model - 1114 Full range Range - see items 4.1 Accuracy 11% Fuli Scale 4.2 Access Hatch Test Equipment a.

Precision Pressure Gage (as follows or similar)

Mfgr. - Heise Model - CM Range 0-60 psig Resolution 0.25 psi l

Accuracy 0.1%

b.

Barometer (as follows or similar) i Mfgr. - Pennwalt Model - FA185260A Range 10.8 - 15.5 psia Resolution 0.005 psia l

l Accuracy - 0.1% l

f 3.3 Penetration Pressurization - Method 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 l

to maintain approximately 60 psig in mechanical penetrations and 30 psig in electrical penetration. High meter readings have occasionally occurred but these have oeen attributed to leaks in the many compression fittings in the penetration pressurization i

system or to malfunction of rotameters. Testing was per the guidance in SP 1303-11.24, 4.

TEST EQUIPMENT USED 4.1 Valve Test Equipment (See Figure 1) a.

Rotameters - Sets of 3 i

Mfgr. - Brooks Inst. Co.

Model - 1114 Full View Ranges:

Float Mat'l.

Tube #

Range Pyrex R-2-150 8-1,120 SCCM l

Saphire R-2-15C 100-12,200 SCCM i

Carboloy R-6-15B 1000-142,000 SCCM Accuracy 12A full scale industrial accuracy i

b.

Temperature Indicators (as follows or similar)

Mfgr. - Ashcrof t l

Model - EH or AH - 3" or 5" Dial Range 130 F l

Accuracy 12F i

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4.3 Penetration Pressurization Test Equipment a.

Flow Rotameters - (Permanent System Egiipment)

Mfgr. - Brooks Inst. Co.

Model - 1114 Range 0-10 SCFH at 60 psig air Accuracy

+2% Industrial accuracy 5

SUMMARY

AND INTERPRETATION OF DATA 5.1 Valve Test Results a.

As-Found Leakage - Also see tabulation of Individual results in Attachment #2.

Total Leckage Tech. Spec. Limit

% Tech Spec. Limit

> 229,452 SCCM 104,846 SCCM

>100%

The guidelines in SP 1303-11.18 Enclosure 10 (see attachment #1) were used to determine need to repair individual valves.

NOTE: The total shown above is cumulative by penetration and not the total of all valve leakages, i.e., Only the highest valve leakage on each penetration is counted.

EXAMPLE: Penetration SYZ has three containment isoia-tion 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.

This as found leakage exceeded the technical specification leakage criteria and a Licencee Event Report (LER 79-06) was sub-mitted.

Repairs were performed as needed to regain acceptable leakage.

J b.

S-Left Leakage Total Leakage Tech. Spec. Limit

% Tech. 9pec. Limit 6'.321 SCCN 104,846 SCCM--.

59%

i 5.2 Access Hatch Test Results j

5.2.1 Overall Hatch Leakage.

i Following are the leakages measured in the last half of 1978.

For the 1979 results see the computer tabulation of 1979 leakages in Attachment #2.

4 Date Leak Rate 6/17/78 2047 SCCM PERSONNEL 12/9/78 2708 SCCM 6/2/78 3469 SCCM EMERGENCY 12/8/78 3855 SCCM These leakages were considered to be satisfactory.

5.2.2 Door Seal Leakage Several weekly door seal tests failed the 3 SCFH adminis-trative leakage criteria but there were no violations of any technical Specification leakage limits. Containment l

integrity was not required during this time period.

Door I.

sfactory seals were replaced several times to obta (less t.ian 3 SCFH) re test results. Most of the leakage problems are attributable to excessive test pressure.

(Met Ed received a Tech. Spec. change in 1981 to allow testing at 10 psi.3 per manufacturers recommendation.)

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s 5.3 Penetration Pressurization Leakage Leakage Rates Date Mechanical Electrical 6/3/78 2.8 SCFH 1 SCFH 8/29/78 20 SCFH 0.9 SCFH 1

12/11/78 0 SCFH 0.6 SCFH 3/17/79 34 SCFH 0.5 SCFH 6/12/79 28 SCFH 025 SCFH 9/11/79 1.5 SCFH 1.5 SCFH 1

12/12/79 9.5 SCFH 0.4 SCFH The test results revealed no penetration leakage problems.

6.

ERdOR ANALYSIS l

- 6.1 Valve Testing Errers (For purge valves see section 6.2)

The flow meters used in the field have normal industrial accuracies i

of + 2% full scale in the 10-100% (15-150 mm) scale range.

Prior

)

to use mm versus sccm graphs were developed for each meter by 10 point comparisons with simi'ar factory calibrated (1% full scale) rotameters.

During the leak test program weekly 3 point standardi--

zations were performed on the field rotameters to verify continued accuracy. The acceptance criteria for these standardizations was a variance of r.o more than 5% from the calibration graphs.

Scale readings on the leak rate procedure (SP1303-ll.18) data sheets were evaluated and corrected using the methods in Attach-ment #1. Approximately 10% coahervative bias was introduced into the results by assuming 15 mm (10% of scale) as the minimum i

scale. Half of the test results actually showed a lower scale i

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reading. More involved error corrections were not considered desirable since neither the as-found or the as-left total leakage was close to the acceptance criteria.

6.2 Access Hatch and Purge Valve Te_ ting Errors The measured pressure drops were corrected by adding the minimum scale increment of the gage used for both the heise gage and the barometer. This conservatively corrected for the resolution cad j

. repeatability errors. Gages used were recently calibrated. A minimum one hour temperature / pressure stabilization pericd was

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used prior to each pressure drop test.

The access hatches and l

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purge valves are not instrumented to allow temperature enrrections.

6.3 Penetration Pressurization Testing Errors These test results are used fo. information only and do not count i

toward the total leakage limit for Technical Specification con-a fo rmance.

The meters, installed permanently in the system, have I-

+2% full-scale industrial accuracy.

7.

REFERENCES t

7.1 1430-Y22 Standardization of Flow Rotometers (Rev 0) l 7.2 SP 1303-11.18 Reactor Building Local Leak Rate Testing (Rev 14) 7.3 Three Mile Island Unit 1 Technical Specification 4.4.1 3

7.4 TMI Surveillance File (for Data Sheets) 7.5 SP 1303-11.24 R.B. Local Leakage Penetration Pressurization (Rev 0) 7.6 SP 1303-11.25 R.B. Local Leakage Access Hatch Door Seals (Rev 3) 4 l

7.7 LER 79-06 Licencee Event Report to NRC !

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ATTACHMENTS i

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ATTACHMENT 1

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RESULTS EVALUATION PROCEDURE (SP1303-11.18 Enclosure 9 & 10) i i

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R.B. LOCAL LEAK 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 pas.ing, fluid black check valve, or gasket leWage was evident the supply rotameter results will be used unitss this non-seat leakage wcs measured reliably and documented.

FOR USE OF SUPPLY FOR USE OF VENT ROTAMETER DATA:

ROTAMETER DATA:

Procedure:

procedure:

a) Record supply meter reading in (1) a) Record vent meter reading in (1) below.*

below*. Also identify the meter used by tube # in (8) below and b) Record downstream verification meter the metering pressurt. in(9).

reading in (2) below. Also identify the respective meters e;ed in (8) be-b) Convert meter units to SCCM units low and the metering pressure in (9).

using latest lab meter calibra-tion curve. Enter in (3) below.

c) Convert meter units to SCCM units using latest lab meter calibraton curve.

c) Correct results for temperature.

Enter in (3) below.

Enter supply teaperature..in (4) d) Correct results fog temperature.

Enter below.

vent temptrature ( F) in (C below.

Calculate and enter in (7) below.

then Calculate and enter in '.) below e) If measurcments of any other significant leakage paths (fluid block check valve, packi1g) are being claimed enter corrected flow (SCCM) in (6) below.

  • If meter scale reading was less than 15mm (minimum scale) use 15mm in calculations.

(MM)

(SCCM) f 533

) convert (

(1)

(2)

(3)_

)

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+ 460 =

SCCM

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+

(4)

(5)

(8) (Iden'tify meters used)

+

SCCM (6) 0 (9) (Meter Pressures

= ClV Leau ge SCCM (7) _ _ _ _ _ _ _

1 REPAIR CRITERIA DETERMINING NEED TO REPAIR VALVES The target criteria throughout this surveillancr procedure are intended strictly as in6i:ations of commonly attainable leakage rates. The engineering staff has also assigned " maximum" leakages for valves 6" or larger in accordance with ASME 3ection XI.

1974 Edition thru summer 1975 Addenda.

(See below)

Valve repairs will be performed for one of two reasons:

1.

POTENTIAL SIGNIFICANT REDUCTION IN THE TOTAL LEAKAGE RATE.

Tiie potential for reduction should be apparent by comparing the "as found" leakage with the target criteria.

The total must not exceed 104,846 SCCM as set by Appendix J-10CFR50 and should be less than 60,000 SCCM (for reasonable margin between refuelings).

2.

VIOLATION 00 LEAKAGE LIMITS SET BY lSME SECTION XI 6" valves and smaller - maximum 10,000 SCCM (Set by Engineering Staff) 8" valves - maximum 15,000 SCCM (Set by Engineering Staff)

Larger than 8" - maximum 20,000 SCCM (Set by Engineering Staff ASME Criteria:

For valves 6" and larger, if an as-found leakage rate exceeds the rate determined by the previous test by an amount trit reduces the margin be-tween measured leakage rate and the maximum permissible rate (above) by 50 Percent or more corrective action shall be taken.

Exe.1pl e :

a. 8" valve - maximum 15,000 SCCM
b. previous leakage 8,000 SCCM
c. last test 11,000 SCCM

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leakage change 11000 - 8000 43 Percent (acceptable)

=

original margin 15000 - 8000 When tests show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible by more than 10 Percent the valve shall be replaced or repaired and retested to demonstrate satis-factory operation before being returned to service.

1. _ _ _ _ _

g (APPENDIX F)

ATTACHMENT II DATA 1979 TYPE B & C REACTOR BUILDING LEAK RATE TESTING

THREE MILE ISLAWD NUCLEAR PLANT UNIT i RB LOCAL LEAN RATE TESTING RESULTS-UPDATE SP1303-11.10 1979

~

~I TEtt TAG DESC SIZES OPER ASFOUND ASLEFT ASLTDATE

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AH-VIA/B BFLY 48 P/MO 3705.001 8073 3/15/79 2

AH-VIC/D DFLY 48 MO/P 8698 6006 3/14/79 3

CA-Vi GLOBE 1

MO 45 45 2/27/79 i

4 CA-V2 GATE i

P 3135 3135 2/27/79 5

CA-V3 GLOBE i

MO 74 74 2/27/79 4

6 CA-V4A GLOBE i

MO 45 45 2/23/79 7

C(-V4B GLOBE i

MO 110 itC 2/23/79 O

CA-VSA GATE i

P 53 53 2/23/79 9

CA-V5B GATE i

P 144000.001 339 3/2/79 10 CA-Vl3 GLOBE i

MO 69 69 2/27/79 11

~CA-V189 GATE 2

P 45 45 2/19/79 l

12 CA-Vi92 LFT CHK 2

N/A

.01

.01 NOTEST 13 0

0 0

14 0

0 0

15 CF-V2A GLOBE i

MO 57 57 3/23/79 l

16 CF-V2B GLOBE i

MO 65 65 3/23/79 17 CF-V12A LFT CHK~

1 N/A 45 45 3/23/79 10 CF-V12B LFT CHK 1

N/A 894 894 3/23/79 19 CF-V19A GATE i

P 983 983 3/23/79 i

20 CF-Vi?B GATE i

P 18 18 3/23/79 l

21 CF-V20A GATE i

P 171 171 3/23/79 22 CF-V20B GATE i

P 608 608 3/23/79 23 CM-Vi BALL 1

P 45 45 2/27/79 24 CM-V2 DALL i

P 45 45 2/27/79 25 Crl-V3 BALL i

P 45 45 2/27/79 26' CM-V4 BALL 1

P 45 45

-2/27/79 27 DH-V64 GLOBE 2

HW 16 16 2/21/79 28 DH=J69 STOP CHK 2

HW 53 53 2/21/79 29 0

0 0

30 FTTEAST FLANGE 30 N/A 45 45 3/14/79 31 FTTWEST FLANGE 30 N/A 75 75 3/14/79 32 HP-Vi GATE 6

HW-1287 1287 2/19/79 33 HP-V6 GATE 6

HW 3655 3655 2/19/79 34 HR-V2A/B GLOBE 2

HW

.01

.01 NOVALVE 35 HR-V4A/B GLOBE 2

HW

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.Li NOVALVE 36 HRV22A/D GLODE 2

S

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.01 NOVALUE 37 0

0 0

38 HR-V23A GLOBE 2

S

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.01 NOVALVE 39 HR-V23B GLOBE 2

S

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.01 NOVALVE 40 IA-V6/20 GLOBE 2

HW 45 45 2/14/79

~~41 IC-V2 GATE 6

MD 2242 2242 2/22/79 I

42 IC-V3 GATE 6

P 5872 4136 2/26/79 -

ITEM TAG DESC SIZES OPER ASFOUND ASLEFT ASLTDATE

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43 IC-V4 GATE 6

P 45 45 2/22/79 44 IC-V6

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P 45 45 3/ * '79

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HW 160 160 3/2/79

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49 LR-V5 GLOBE 2

HW 910 910 2/12/79 50 LR-V6 GLOBE 2

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52 MU-V2A GLOBE 2.5 MO 16 16 2/19/79 53 MU-V2B GLOBE 2.5 MO 45 45 2/19/79 54'-MU-V3' GATE

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55 HU-V18 GATE E.5 P

635 635 2/16/79 56 HU-V2O GATE 4

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---^

58 MU-V26 GATE 6

P 45 45 2/21/79 59 MU-V116 PIST CHK 1.5 N/A 9105 9105 2/20/79 j

60~~ NI-V27

~~

1' HW

~

. 01 " ~ ~ ~ '

~.01 NOTEST ~~

~

~~ ~ ~~

l 61 NS-V4 GATE 1.5 N/A 45 45 3/1/79 62 NS-V15 GATE O

MO 45 45 3/1/79

_..g _..NSLV35 GATE ~~~~

~'~8'

'MO

'45

~~45 ~~

3/1/79~ ~ ~ ~ "

- ~ ~'

64 PENETiO4 BLK FLG 2

N/A 45 45 3/22/79 65 PENET105 BLK FLG 10 N/A 45 45 2/14/79

'66 PENET106~ BLK~FLG'

~~

4'

'N/A~'

~45 -

' ^ 45'

^2/14/79~

~ ~ ~ ~ ~ ~ ~

67 PENET2io BLK FLG 2

N/A 45 45 3/17/79 68 PENET2ii BLK FLG 2

N/A 45 45 3/17/79

~ 69 ~ ~ ~ PENET241~ BLK /LG~

~ ~ 18 ~ ~

~N/A'~

~

'45

~~

~ ~4 5 '

3/17/79-~

~ ^

70 RB-V2A CalE 8

MO 3093 4100 3/1/79 71 RB-V7 GATE 8

MD 25450 1033 3/79

~72~

SA-V2/3 GLOBE 2

~ HW '

' 45~

45 2/14/7" ~

~ - - '

73

-SF-V23 GATE 8

HW 45 45 2/21/79 74 WDG-V3/4 GL/GA 2

M0/P 544 544 2/28/79

- 7 7 WDL-V303 ~ GLOBE ^

~

~4

~MO'

~

44-4 4 ~~

2/28/79~

~ ~ ~

~ -

76 WDL-V304 GATE 4

D 45 45 2/28/79 77 WDL-V534 GATE 8

P 45 45 3/13/79 78 WDL-V535~ GATE

'0

~P-

~'

~4 5 -

~

45'

~3/13/79 79 EQPFLG FLANGE 216 N/A 45 45 3/9/79 80 PERACCES MISC.

96 N/A 2179 2179 4/2/79 "8f

~

~

~

~

96--~

~~~

991 ~~ ~ 991 ~~

12/22/N'

~

62 EMEACCES MISC 96 N/A 754 754 5/31/79 83 96 3855 3855 12/8/79 ITEM TAG TARGET ASFOUND ASLEFT

~*w**

          • x**'

--~ - -

84 TOTAL 64549 235129.072 67998.07 85 PENTOTAL 53598 229878.032 62747.03 06

~ACC~ CRIT ~ ~23975

~104846'

~

104846

~ ' '

~

~~~

' ' ~~

-ie,

.w..

.--in-....-

r.,-vg

_-a.m._

LRTERMS - TERMINOLOGY U5FD IN COMPUTER PROGRAM FOR LOCAL LEAK

--RATE TESTING RESULTS.

-- 1 )-

.1- (ALONE) OR ANY 0THER-NUMBER-0THER-THAN ZERO--

IN THE FIRST DECIMAL PLACE HEANS TEST SCHEDULED.

2)

.01 -(ALONE) MEANS NO DATA AVAILABLE FOR YEAR OR TEST DELAYED.

(E.G. VALVE NOT INSTALLED YET OR NOT IN PREVIOUS -

TESTING SCOPE) 3)

.001 - (OR ANY NUMBER OTHER THAN ZERO IN THE THIRD DECIMAL PLACE) AFTER.A LEAK.

RATE (I.E. 59500.001) MEANS ACTUAL LEAK RATE GREATER THAN MEASURED / RECORDED VALUE.

~ 4) TARGET. ADMINISTRATIVE LEAKAGE LIMIT BASED ON TESTING.

EXPERIENCE.

COMPLETE EXPLANATION GIVEN IN SP1303-ti.18.

5).ASFD__ - LEAK RATE (SCCM)..IN THE AS-FOUND VALVE CONDITION.

BEFORE ANY REPAIRS OR ADJUSTMENTS. FOR THE DESIGNATED YEAR.

._-6)-ASLT__

LEAK RATE (SCCM) ATTAINED AFTER.ANY_ ADJUSTMENTS / REPAIRS.

7) SIZES - PIPE DIAMETER (INCHES) FOR VA'_VE/ PENETRATION.
0) RUNTOTAL-RUNNING TOTAL. THIS IS THE LIST OF LEAKAGES WHICH IS USED FOR DETERMINATION-OF REPORTABILITY.

A NEW.

ASFD LEAKAGE REPLACES THE PREVIOUS YEARS ASLT LEAKAGE.

RETEST RESULTS ARE NOT INCLUDED UNTIL AFTER DETERMINING REPORTADILITY.

9) SCHED-SCHEDULED DATE FOR TEST
10) ASLTDAlE-DATE OF LAST ACCEPTABLE TEST RESULTS

_. 11) RETEST 1/2/ETC-LEAF RATE (SCCM) FOR RETEST AFTER REPAIRS AND/OR ADJUSTMENTS.

12) ITEM-REFERENCE NUMBEi CORRESPONDING TO THE POSITION IN A DATA ARRAY OF ANY DATA FOR A PARTICULAR VALVE.

I.E.

DESC(2) CORRESPONDS TO TAG (2) WHICH IS AH-ViC/iD AND TO ITEM (2).

.13) DESC - DESCRIPTION OF. VALVE OR PENETRATIOW.

14) OPER - TYPE OF VALVE OPERATOR (ACTUATOR)

HW= HANDWHEEL ONLY MO= MOTOR AND HANDWHEEL P=

PISTON (SOME OF THESE HAVE HW A'S0)

S=

SOLENOID ACTUATED ONLY N/A=NO ACTUATOR (E.G. CHECK. VALVE) 15 NOTEST - THE TECH SoEC SCOPE DID NOT REQUIRE THIS

' 'f,L V E TO BE TESTED DURING THIS YEAR 16 NOVALVE-THIS VALVE WAS INSTALLED DURING A LATER REFUELING PERIOD.

W

APPENDIX G THREE MILE ISLAND UNIT 1 I

l I

I i

1980 REACTOR BUILDING LOCAL LEAK RATE TESTING REPORT SP 1303-11.18 (1/80 -.i/80)

I t

I i

I h-f Prepared b R. L. Summers Engineer Senior I - TMI-1 l

f

INDEX - 1980 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 i

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 i

5.3 Penetration Pressurization i

6. ERROR ANALYSIS 6.1 Valves 6.2 Access Hatches 6.3 Penetration Pressurization
7. REFERENCES l
8. ATTACHMENTS 8.1 Results Evaluation Procedure / Repair Criteria 8.2 Tabulation of Individual Test Results

_1

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

1980 - REFUELING FREQUENCY 1.

PURPOSE 1.1 To provide analysis to the Nuclear Regulatory Commission on the fifth periodic type B and type C leakage tests performed on the Three Mile Island Unit I reactor building.

This is in accordance with " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors". Appendix J, Part 50, i

Title 10 Code of Federal Regulations which required the contents of this summary report to become part of the type A test report along with the details of any other type B and type C testing performed since the previous type A test.

(also required per technical specification 4.4.1.1.8).

Note that this testing was performed during i year when the reactor remained in long term cold shutdown. Containment integrity has not been required since the Unit was placed in cold shutdown following the March 28,1979, Unit II accident.

2.

SUMMARY

OF WORK ACCOMPLISHED 2.1 Valve Testing /Pepairs A total of approximately 80 valve seat and/or packing leak tests were t

performed during 1980. The test results showed the need to perfou j

repairs on LR-V2, AH-VlA/B, RB-V7 and WDG-V4 (see Attachment #1 for repair criteria). A licensee event report (LER 80-06) was submitted to the NRC as a result of the overall leakage exceeding the Tech. Spec.

limit even though containment integrity was not required during 1980.

Vaive repairs and retests were not performed until early 1981 except for a disc modification on LR-V2. =

2.2 Access Hatch Testing / Repairs 2.2.1 Door Seals SP 1303-11.25 Weekly door seal leak tests were performed during the current cold shutdown condition. Occasional seal replacement was performed in response to high leakage.

2.2.2 Overall Hatch Test The following leak tests on each access hatch have been performed thus far in 1981.

Repairs were initiated as a result of the 12/27/80 test. This involved tightening fittings.

Date Personnoi 5/80,11/80 Emergency 7/80, 12/80, 1/81 2.3 Penetration Pressurization SP 1303-11.24 Quarterly reaoings were recorded on 3/80, 6/80,10/80 and 12/80 from the flow rotometers which supply air pressure or nitrogen pressure to reactor building mechanical and electrical penetrations. No penetration leakoge problems were noted although flow meter malfunctions required meter repairs.

3.

METHODS OF TESTING 3.1 Valve Test Methods Testing was performed by use of TMI Unit 1 surveillance 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 for each penetration / valve. The following general philosophy is contained in the surveillance procedure.

4 3.1.1 Use air or nitrogen at a pressure differentia's across the valve greater than Pa (Calculated accident pressure). 55 psig was normally used.

3.1.2 Assure that the pressure is exerted in the accident test direction unless it can be demonstrated that pressurizing in the opposite direction is as conservative. Butterfly valves AH-VlA/18/lC/lD, and globe valves WDG-V4, SA-V3 and IA-V20 wer's tested in the reverse direction.

3.1.3 Assure that the test volume is drained of liquid so that air or nitrogen test pressure 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 conditions.

j 3.1. 6 Assure test equipment is calibrated and used in a manner consistent with the data accuracy desired.

(Weekly meter standardization was performed to verify meters accurate within + 5% instantaneous --

3 MP1430-Y-22).

3.1. 7 Assure that the fluid blocking system is drained and vented during tests on the associated containment isolation valves ta prevent any effects it might have on the test results.

(Most of the F.B. system piping is seismic 3).

3.1.8 Assure valvas to be tested are closed by the normal method prior to testing.

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

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

3.1.10 Record test instrument scale readings prior to doing any data corrections.

3.1.11 Assure that system drains and vents which could serve as c'.atainment isolation valves are closed and capped and tagged after completion of the test program.

A training program prior to the refueling outage was performed j

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

3.2 Access Hatch Test Methods 3.2.1 Door Seal Leak Tests-Methods Door Seal leak tests were performed by use of SP 1303-11.25.

i This procedure gives detailed guidance on the test equipment and methods to be used.

i The door seal tests were performed by pressurizing the interspace i

i between the double seals on each door with reiered air at 55 psig.

After stabilization the air rotameter indicates the rate of air input required to maintain the test pressure.

3.2.2 Overall Hatch Leal Test -- Overall hatch leak testing was performcd by use of TMI V'ait 1 Surveillance Procedure SP 1303-11.18 Reactor Building Local Leak Rate Testing. This procedure gives detailed 2

guidance on the test equipment and methods to be used. The i

overall (integrated leak test verifies the integrity of all of the following barriers:

a. Hatch shell/ welds,
b. Rubber door seals, r I
c. Teflon operating shaft packing,
d. Bulkhead electrical penetrations,
e. Penetratie, pressurization chack valves,
f. Emergency air flange and associated "0" rings on outer
bulkhead,
g. Bulkhead equalizing ball valves and associated mounting flanges /"0" rings.

The overall leak test is performed by pressurizing the hatch l

to greater than calculated accident pressure and observing the rate of pressure drop on a high accuracy (Heise) pressure gage.

4 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 j

period.

3.3 Penetration Pressurization - Method l

Quarterly readings were taken on the flow rotameters which are i

permarpntly installed in the penetration pressurization system. These readings represent the air / nitrogen makeup rate required to maintain approximately 60 psig in mechanical penetrations and 30 psig in electrical penetrations. High meter readings have occasionally occurred but these have been attributed tc leaks in the many compression fittites in ti;e penetration pressurization system or to malfunctioning (stuck) retameters. Testing was per the guidance in SP 1303-11.24.

4.

TEST EQUIPMENT USED 4.1 Valve Test Equipment (See Figure 1) l 6-

--.,-,..,,.,--.,,,,...n.,

,.--.n-.

.n.,

.-.-,,a.

l a.

Rotameters - Sets of 3 Mfgr. - Brooks Inst. Co.

Model - 1114 Full View Ranges:

l Float Mat'l.

Tube #

Range i

Pyrex R-2-15D 8-1,120 SCCM Saphire R-2-15C 100-12,200 SCCM Carboloy R-6-15B 1000-142,000 SCCM Accuracy 12% full scale industrial accuracy b.

Temperature Indicators (as follows or similar)

Mfgr. - Ashcroft i

Model - EH or AH - 3" or 5" Dial a

Range 30 -130 F i

Accuracy 12F c.

Pressure Indicators (as follows or similar)

Mfgr. - Ashcroft Mcdel - 1279 - 41 " Dial 3

Range 0-60 or 0-100 psig l

Accuracy 1 2 psig d.

Pressure Regulator (as follows or similar)

Mfgr. - Union Carbide Corp.

Model - UPG 3-75-580 Range 0-100 psi output / 0-3000 psi input 1

e.

Calibration Rotameters (Set of 2)

Mfgr. - Brooks Inst. Co.

Models - ll10-05K2BlI49, ll10-08K2BlZ06 f

Ranges 20-;t,000 S CM, 3,600-234,600 S CM Repeatability i 1/4% of instantaneous Accuracy 1 1% instantaneous f.

Flow rate Calibrator Mfgr. - Brooks Inst. Co.

Model - 1056A Range 0 to 2,400 SCCM Accuracy 10.2% of indicated volume 4.2 Access Hatch Test Equipment a.

Precision Pressure Gage (as follows or similar)

Mtgr. - Heise Model - CM Range 0-60 psig Resolution 0.25 psig Accuracy 0.1%

b.

Barometer (as follows or cimilar)

Mfgr. - Pennwalt Model - FA18526(9 Range 10.8 - 15.5 psia Resolution 0.005 psia Accuracy 0.1%

4.3 Penetration Pressurization Test Equipment a.

Flow Rotameters - (Permanent System Equipment)

Mfgr. - Brooks Inst. Co.

Model - lil4 i

j

__ _ __. ($ q

{

I l

I l

t I fo E l

lL 1

l, l

i i

Ise"*

l 'f" A Y "<'#

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Ch a;

V'*

5;'$

l l

ctV

  1. p lp NW X e4

'l i

I T

T

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l l

I I

l 8

l I

l I

II vv' r {pg) r;

[ 7 "a' sea u j E

l V

se

, y -I A

i l

oi I

g'b 9 r s w aj

'X

--t

, g_I a l

lm

)

y

- VENT fflG-s y,

y, t_. _ _ __ ___ _ _ __. _ _ _l o

- PRESSURIMTmN RW -

na en>at 4

k b

McTres VALVES Ml<

M VI - Al, Borra Resnaroa Keef Fionr

@ opsy

@ syyns Yt,3}-BAu. VALVF

\\

L" g

J j

Lo R-1-isD Bl=ek &/.es 8-3so scem w-Nu seen g

hp>g y _ _g, yg,,

Mro e-2-in s,.. s.p:n io. - s,so scen 100 - n n o scen

.,o,,,,,,,,.ga r,7y.ag Mg Hisa R-c-irs c.4.1.,

t.o~ - ci, ~ :cen zooo -19.1.~ seen D

Pxt.ssoac ruoienreas TEMP Ivb' CAT 0A S i

g

  • ?

25 ~!2WT *

' fan **Y j

]

o -100 erg e i p.y Acevency l

}

M a vr>

a a

I

Range 0-10 SCFH at 60 psig air Acc9 racy

+ 2% Industrial accuracy 5.

SUMMARY

AND INTERPRETATIO". OF DATA 5.1 Valve Test Results a.

As-Found Leakage - Also see tabulation of individual results in Attachment #2.

Total leakage l Tech. Spec. Limit

% Tech. Spec. Limit

> 205,413 SCCM 104,846 SCCM

> 100%

The guidelines in SP 1303-11.18 Enclosure 10 (See Attachment #1) were used to determine the need to repair valves.

NOTE: The total shown above is cumulative by penetration and not the total of all valve leakares, i.e., Only the highest valve leakage on each penetration is counted.

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.

b.

As-Left Leakage l

Total Leakage Tech. Spec. Limit

% Tech. Spec. Limit

  • 13%

19,311 SCCM 104,846 SCCM

  • Some repairs and retests were delayed till 1981 5.2 Access Hatch Test Results 5.2.1 Overall Hatch Leakage.

Data Leak Rate Personnel 5/18/80 885 SCCM 11/27/80 1056 SCCM l

Emergency 7/5/80 1708 SCCM 12/27/80 9406 SCCM 1/6/81 1188 SCCM

  • 4 i
  • Retest after tightening Fittings.

None of the test results violated Technical Specification requiremerts.

l 5.2.2 Door Seal Leakage Numerous weekly door seal tests failed the 3 SCFH administrative leakage criteria but there were no violations of any Technical Specification leakage limits. Containment integrity was not required during this time period.

Door seals were replaced several times to obtain satisfactory (less than 3 SCFH) retest results.

5.3 Penetration Pressurization Leakage i

Leakage Rates Date Mechanical Electrical 3/18/80 1.6 SCFH 0.5 SCFH 6/12/80 3.2 SCFH 0.6 SCFH 10/3/80 7

SCFH 0

SCFH 12/12/80 13 SCFH 0

SCFH N-> penetration leakage problems were evident from these results.

i

. 1 p-v.a

,-----my..,,

--,wn---pa,w..r-g-m,,,,-wmsy--,,-,-wry,.,--we-wg-me n,

-c w,w-ww~-nogr--------------r-m-.

-e

+

w-w

1 6.

ERROR ANALYSIS 6.1 Valve Testing Errors (For purle valves see section 6.2)

The flow meters used in the field have normal industrial accuracies of i 2% full scale in the 10-100% (15-150 mm) scale range. Pric) to use mm versus sccm graphs were developed for each meter by 10 point calibrations using high accuracy (1.1% instantaneous) lab rotameters.

During the leak test program weekly 3 point standardizations were performed on the field rotameters to verify continued accuracy. The acceptance criteria for these standardizations was a variance of no more than 5% instantaneous from the calibration graphs. When 5% was exceeded the respective meter was recalibrated to develop a new graph.

4 Scale readings on the leak rate procedure (SP 1303-11.18) data sheets were evaluated and corrected using the methods in Attachment #1.

Approximately 10% conservative bias was introduced into the results by assuming 15mm (10% of scale) as the minimum scale. Half of the test results actually showed a lower scale reading. More involved error corrections were not considered desirable as neither the as-found or the as-left total leakage were close to acceptance criteria.

6.2 Access Hatch and Purge Valve Testing Errors The measured pressure drops were corrected by adding"the minimum scale increment of the gage used for both the heise gage and the barometer.

I 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 corrections.

6.3 Penetration Pressurization Testing Errors These test results are used for information only and do not count toward the total leakage limit for Technical Specification conformance.

The neters, installed permanently in the system, have + 2% full scale industrial accuracy.

7.

REFERENCES 7.1 143C-Y22 Standardization of Flow Rotometers (TCN 80-39) 7.2 SP 1303-11.18 Reactor Building Local Leak Rate Testing (Rev.18) 7.3 Three Mile Island Unit 1 Technical Specification 4.4.1 7.4 TMI Surveillance File (for Data Sheets) 7.5 SP 1303-11.24 R.B. Local Leakage Penetration Pressurization (Rev. 0) 7.6 SP 1303-11.25 R.B. Local Leakage Access Hatch Door Seals (Rev. 3) 7.7 LER 80-06 NRC Licensee Event Report 1

(A P P E N D I X G)

AliACHMENTS I

t l

l l

l :

t

j (APPENDIX G)

ATTACHMENT 1 RESULTS EVALUATION PROCEDURE (SP 1303-11.18 Enclosure 9) _

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

FOR USE OF SUPPLY FOR USE OF VENT ROTAMETER DATA:

ROTAMETER DATA:

Procedure:

Procedure:

a) Record supply meter reading in (1) a) Record vent meter reading in (1) below.*

below*. Also identify the meter used by tube # in (8). below and b) Record downstream verification meter the metering pressure in (9).

reading in (2) below. Also identify the respective meters used in (8) be-b) Convert meter units to SCCM units low and the metering pressure in (9).

using latest lab meter calibra-tion curve.

Enter in (3) below.

c) Convert meter units to SCCM units using latest lab meter calibraton curve.

c) Correct results for temperature.

~

Enter in (3) below.

Enter supply temperature;in (4) d) Correct results fo temperature. Enter below.

vent temperature ( F) in (4) below.

Calculate and enter in (7) below.

then.

Calculate and enter in (5) below e) If measurements of any other significant leakage paths (fluid block check valve, packing) are being claimed enter corrected flow (SCCM) in (6) below.

  • If meter scale reading was less than 15mm (minimum scale) use 15mm in calculations.

(MM)

(SCCM)

! 530

) convert (

+

)

X t 460 =

SCCM'

(

+

(1)

(2)

(3)

(4)

(5)

+

_.SCCM (8) (Identify meters used)

(6)

(9) (Meter Pressures

= ClV Leakage SCCM (7).

y,

.._,-m

_y

-._m, y

REPAIR CRITERIA DETERMINING NEED TO REPAIR VALVES The target criteria throughout this surveillance procedure are intended strictly as indications of commonly attainable leakage rates. The engineering staff has also assigned " maximum" leakages for valves 6" or larger in accordance with ASME Section XI.

1974 Edition thru summer 1975 Addenda.

(See below)

Valve repairs will be performed for one of two reasons:

1.

POTENTIAL SIGNIFICANT REDUCTION IN THE TOTAL LEAKAGE RATE.

The potential for reduction should be apparent by comparing the "as found" leakage with the target criteria. The total must not exceed 104,846 SCCM as set by Appendix J-10CFR50 and should be less than 60,000 SCCM (for reasonable cargin between refuelings).

2.

VIOLATION OF LEAKAGE LIMITS SET BY ASME SECTION XI

~

6" valves and smaller - maximum 10,000 SCCM (Set by Engineering Staff) 8" valves - maximum 15,000 SCCM (Set by Engineering Staff)

Larger than 8" - maximum 20,000 SCCM (Set by Engineering Staff ASME Criteria:

For valves 6" and larger, if an as-found leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin be-tween measured leakage rate and the maximum permissible rate (above) by 50 Percent or more corrective action shall be taken.

Example:

a. 8" valve - maxinium 15,000 SCCM
b. previous leakage 8,000 SCCM
c. last test 11,000 SCCM s.

r leakage change 11000 - 8000 43 Percent (acceptable)

=

original margin 15000 - 8000 When tests show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will e'xceed the maximum permissible by more than 10'Perc.nt the valve shall be replaced or repaired and retested to demonstrate satis-factory operation before being returned to service.

e j

9 e,

(APPENDIX G)

ATTACHMENT 2 DATA 1980 TYPE B & C REACTOR BUILDING LOCAL LEAK RATE TESTING

THREE Mi' E ISLAND NUCLEAR PLANT UNIT 1 RB LOCAL._EAK_ RATE-. TESTING RESULTS-UPDATE SP1303-ti.18 198 O

' ITEh TAG DESC SIZES OPER ASFOUND ASLEFT ASLTDATE

                • . ********. ****t
        • . ******x**

i AH-VIA/B BFLY 18 P/MO 18936

.01 SEE 1981

.4-ViC/D BFLY 48 M0/P

.01

.01 SEE 1981 2

^

_3 CA vL

._ GLOBE..

.1 Hu _

42 42 5/13/80 4

CA-V2 GATE i

P 937 937 5/13/80 5

CA-V3 GLOBE i

MO 99 99 5/13/80 d

CA-V4A GLOBE __. _.

-.i.

MO.

50-50.

_3/27/80_ _

7 CA-V4B GLOBE i

MO 50 50 3/27/80 8

CA-V5A GATE

,P 63 63 3/27/80 9.

CA-V5B GATE _

t

.~P

_ i45 1 4 5.- _

.3/27/FM 10 CA-V13 GLOBE i

MO 115 115 5/13/60 11 CA-V189 GATE 2

P 1557 1557 4/2/80 12 CA-Vi92._-.LFT.CHK

.2-

-N/A_

. 01 - -_ _

.01_ NOTEST 13 O

O O

14 0

0 0

1 15 CF-V2A... GLOBE _.

_ _i _.. MO

-_i15

_115

_4/22/80 16 CF-V2B GLOBE i

MO 40 40 4/23/80 17 CF-V12A LFT CHN 1

N/A iii iii 4/28/80 4

u 18.

.CF-V12B _ LFT.CHK _ __ 1.

N/A 91.

. _ 9.1 4/28/80.

19 CF-Vi9A GATE 1

P 22i 221 4/28/80 20 CF-V19B GATE i

P 42 42

.)/28/80

.21 -

_CF-V20A..

GATE

.i P _

226

. 226._

4/22/BO_.

22 CF-VZOD.

GATE 1

P 1T 135 4/23/80 23 CM-Vi BALL i

P 5A 50 3/18/80 l

24

~CM-V2_-_

BALL-.

1.

P.

59 _

50

_3/18/80_.

25 CM-V3 BALL i

P 50 50 3/18/80 26 CM-V4 B t.L t.

1 P

50 50 3/18/80 27_

.DH-V64-J LDE. _

2 HW _

24.

- _ _ _24. __ _5/6/80..

20 DH=V/ 9 ST ? CHK 2

HW 162 162 5/1/80 29 0

0 0

_ 3 0 _... F T T E r S T -

FLANGE--

_ 30 __N/A

. 50_

30.

_3/12/80 -

31 FTTWEST FLANGE 30 N/A 169 169 3/12/80 32 HP-Vi GATE 6

HW 1099 1099 3/14/80

-33, HP_-V6-GATE. _

.6 HW.

.1994

_19.94._

. 3 /.14 /80 _ _ _

34 HR-V2A/B GLOBE 2

HW

.01

.01 NOVALVE 35 HR-V4A/B GLOBE 2

HW

.01

.Gi NOVALVE 36-_.HRV22A/B_ GLOBE

.2.

S

. 01.

. 01.NOVALVE.

37 0

0 0

39 HR-V23A GLOBE 2

S

.01

.01 NOVALVE 39 HR-V23B.

GLOBE _

2 S.

.01

_-m01.

NOVALVE 40 IA-V6/20 GLODF 2

HW ii2 ii2 3/6/80 41 IC-V2 GATE 6

MO 40 40 4/18/80

_._4 2.

.IC-V3

. GATE ~

6

.P 3779.

3779_

4/18/80 l

,-,n,-.

---.-.n,-------

- - -. -. - - - ~ - - -

ITEM TAG.

DESC SIZES OPER ASFOUND ASLEFT ASLTDATE

-43

..I C-V4 -. -

-GATE ~ --

-- - P- -

40

-40

- 4/17/80---

44 IC-V6 OATE 3

. P 40 40 4/17/80 45-LR-Vi GATE 6

HW 50 50 3/7/80

.. _.46 - LR-V2 - -

G ATE = - - -

6

.-- - H W --

-5655 - -

--613 - - -4/8/80 47 LR-V3 GATE 6

HW 168 168 3/7/80 48 LR '14 GLOBE

.75 HW 50 50 3/7/80 4 47.

-LR-,J.

-GLOBE _.

2

..HW 50 50 3/7/80 50 LR-V6 GLOBE 2

HW 112 112 3/7/80 51 LR-V49 GATE 6

HW 40 40 4/10/80

' 52-

-MU-V2A-

-GLOBE--

- 2.5 -- M O -

171 -

- -. i71- - -- 2/18/81- -

53 MU-V2B GLOBE 2.S MO 61 61 2/18/81 54 MU-V3 GATE 2.5 P

38 38 2/18/81

-55

-MU-ViB GATE

-2.5-P-

50-50 - - 2/1i/81- -

56 MU-V20 GATE 4

P 67

~67 5/9/80 57 MU-V25 GLOBE 4

- MO 87 87 5/7/80 MU-V24 GATE. _ -

6. -

R.

41

. 41_- - 5/8/80. -.

~_

59 MU-Vii6 PIST CHK 1.5 N/A 2972 2972 5/9/80 60 MI-V27 i

HW 01 01 NOTEST i. 61.

NS-V4.

- GATE

.1. 5

- N/A 325.--.-

325 _

_ 5/.9/80.

62 NS-Vi5 GATE 8

MO 842 842 4/29/80 63 NS-V35 GATE 8

MO 673 673 4/29/80

! -64 _ PENET104.-BLK FLG_

E2 _--N/A 50

. 30.

_ 3/11/80..

l 65 PENETiO5 BLK FLG 10 N/A 50 50 3/11/80 66 PENETiO6 BLK FLG 4

N/A 50 50 3/11/80

.67

- PENET210 -PLK FLG_---

2 _.

N/A 50

.50~

3/.ii/80_ _ _ __ _.. -.

6U PENEr21i BLK FLG 2

N/A 50 50 3/1)/80 60 PENET241 LLK FLG 18 N/A 205 205 5/1,/80

_ _. 70-RB-V2A-

- GATE.-

-_- 8. -- -. MO. - - -

358 358..

~ 3/26/80--.-

! 71 RD-V7 GATE 8

MO 105176.001 01 SEE 1981

( 72 SA-V2/3 GLOBE 2

HW 50 50 2/9/81

-. SF-V23.- - GATE 8

- HW 64 _.. - _

64

__4/3/80-~.

i 74 WDG-V3/4 GL/GA 2

MO/P 48730 01 SEE.1981-75 WDL-V303 GLOBE 4

MO 59 59 2/23/01 76 WDL-U304_ GATE.-.

- -.4_.

- D 59- - -- _ _ - 5 9_ - _ 2/2 4 / 81 -.

77 WDL-V334 GA TE 8

P 59 59 2/26/81 78 WDL-V535 GATE 8

P 59 59 2/26/81

~79 EQPFLG.

FLANGE

. _.216.

N/A-59- - - - _ 5 9- -

- 3/4/81- ~ -

.00 PERACCES MISC.

96-N/A 885 885 5/18/80-81 94 1056 1056 11/27/80

. 82 _-EMEACCES. MISC

.96.

N/A-i708

-. _.-i708._

.7/"i/ 80..

83 96 9406 1188 1/ /81

. ~.

ITEM TAG TARGET ASFOUND ASLEFT-

      • +****

uB4

- TOTAL-64549--.210319 0E!

24217.11-85 PENTOTAL 53598 206950.041 20848.07 j

86 ACC CRIT 23975 104846 104846 a

4m s

m

-w-'mem m wee.-e=y-.wy--y.yiw.e,yg.9-.wv,,--'P-'-tM-rwveo m yy v--y,--(wygvw. m.w ww--

v-yw-1r--vre,-.y y. y-ng w ee e yy yr,yw-ww,e-yy-

. ww w. wt-9ey-'-'e'fw-wm=+.gi-gw*pzr---9mwy'er---'e v + w.g wms r

~

e

.._s LRTERMS - TERMINOLOGY USED IN COMPUTER PROGRAM FCR LOCAL LEAK

._ RAT E.. TESTING RESULTS,. -_. - _

-.1) _

_.1 - ( ALONE L OR _ ANY.. 0THER NUMBER OTHER..THAN._ZERO _ _.-. _ _.._ _ _ _ _ _ _. _. _ -

IN THE FIRST DECIMAL PLACE MEANS TEST SCHEDULED.

2) 01 -(ALONE) MEANS NO DATA AVAILABLE FOR YEAR OR TEST DELAYED.

_ _.(E.G.

VALVE NOT. INSTALLED YET_OR.NOT IN_ PREVIOUS.. -. _ _

TESTING SCOPE)

. 3):

.001 - (OR ANY NUMBER OTHER THAN ZERO IN THE

. THIRD _ der rt1AL PLACEL AFTER _A_ LEAK RATE (I.

59500.061) MEANS ACTUAL LEAK RATE GREATER HAN MEASURED / RECORDED VALUE.

_A LIARGET-ADMINIS IR ATIVE. LEAKAGE LIMIT _.. BASED. ON_ JESTING _ _ _. _.._

EXPERIENCE.

COMPLETE EXPLANATION GIVEN IN spi 303-fi.18.

. _ _..5) ASFD__

LEAK RATE _(SCCM LIN_THE_AS-FOUND VALVE _ CONDITION.._ _ _ _.. _ _._. _ _

BEFORE ANY REPAIRS OR ADJUSTMENTS. FOR THE DESIGNATED YEAR.

, _ _ 6). ASLT _. -. LEAK RATE. (SCCM L ATTAINED AETER_ ANY ADJUSTMENTS / REPAIRS._ _ _.. __._ __

7) SIZES - PIPE DIAMETER (INCHES) FOR VALVE / PENETRATION.
8) RUNTOTAL-RUNNING TOTAL. THIS IS THE LIST OF LEAKAGES WHICH IS_USED FOR_ DETERMINATION _0F_.REPORTABILITY.._.A NEW _ _

ASFD LEAKAGE REPLACES THE PREVIOUS YEARS ASLT LEA'< AGE.

RETEST RESULTS ARE NOT INCLUDED UNTIL AFTER

._ -_ -~_. DETERMINING REPORTABILITY-.._ _._ _ _ __ _ _._._ _.___ ____

9) SCHED-SCHEDULED DATE FOR TEST
10) ASLTDATE-DATE OF.LAST ACCEPTABLE TEST RESULTS

_ _ _ _. _11.LRETEST1/2/ETCr _ LEAK _ RATE _(SCCMLFOR RETEST-AETER REPAIRS ___ ____ _ _ __.

AND/OR ADJLISTMENTS.

12) ITEM-REFERENCE NUMBER CORRESPONDING TO THE POSITION IN A DATA. ARRAY.OE_ANY_ DATA..FOR A PARTICULAR-.. VALVE._ _. _...-_., __ _ _ _..

I.E.

DESC(2) CORRESPONDS TO TAG (2) WHICH IS AH-ViC/iD AND TO ITEM (2).

__13).DESC - DESCRIP. TION 0F_ VALVE ~OR PENETRATION. _ -_ _-_.__ _ ___ _... -. _-. - _ _ _

14) OPER - TYPE OF VALVE OPERATOR (ACTUATOR)'

HW= HANDWHEEL ONLY M0=. MOTOR.AND_ HANDWHEEL._ _ _. _.. _ _._ _.._

P=

PISTON (SOME OF THESE HAVE.HW ALSO)

S=~

SOLENDID ACTUATED ONLY

._. _ _N/A=ND_ ACTUATOR..(E.G.~ CHECK VALVE;.

15 NOTEST - THE TECH SPEC SCOPE DID NOT REQUIRE THIS VALVE TO BE TESTED DURING THIS YEAR

-- 16 NOVALVE-THIS.. VALVE _WAS. INSTALLED.DURING_A LATER.

REFUELING PERIOD.

.~

.._w I

.-.94.-.,--,,-y

-wv.

,y--.__-.-

,-,v.,,

.,,..,7,,-.....,.,.,w.

- -y

-.,.,n

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

.,,w..-

.-.o.,

APPENDIX H THREE MILE ISLAND UNIT 1 1981 REACTOR BUILDING LOCAL LEAK RATE TESTING REPORT SP 1303-11.18 (1/1/81 - 8/8/81 )

,77 Pry.sred b 6

t_

R. L. Summers Engineer Senior I - TM1-1

l INDEX - 1981 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. ERROR ANALYSIS 6.1 Valves 6.2 Access Hatches 6.3 Peretration Pressurization
7. REFERENCES
8. ATTACHMENTS 8.1 Results Evaluation Procedure / Repair Criteria

.)

8.2 Tabulation of Individual Test Results -

REACTOR BUILDING LOCAL LEAK RATE TESTING NRC REPORT 1981 REFUELING FREQUENCY 1.

PURPOSE 1.1 To provide analysis to the Nuclear Regulatory Commission on the sixth periodic type B and type C leakage tests performed on the Three Mile Island Unit I reactor building.

This is in accordance with " Primary R?nctor Containment Leakage Testing for Water Cooled Power Reactors". Appendix J, Part 50, Title 10 Code of Federal Regulations which required the contents of this summary report to become part of the type A test report along with the details of any other type B and type C testing performed since the previous type A test.

(also required per technical specification 4.4.1.1.3).

Note that most of this testing was performed as a preliminary to the 1981 R.B. Integrated Leak Rate Test. Containment integrity has not been required during the two years, since the Unit was placed in cold shutdown following the March 28, 1979, Unit II accident. Satisfactory local and integrated leak rate testing was a prerequisite to the pending l

Unit I startup.

2.

SUMMARY

OF WORK ACCOMPLISHED 2.1 Valve Testing / Repairs A total of approximately 78 valve seat and/or packing leak tests were performed between 2/18/81 and 8/8/81. No repairs were initiat' s

a result of the 1981 as-found results.

(Note that repairs on WDG-V4, RB-V7, AH-VlA, AH-VIC and AH-VlD, were accomplished in response to the 1

1 1975 and/or 1980 testing, and the 1981 as-found results represent post-maintenance test results on these valves.)

Valve repairs completed in 1981:

a.

AH-V1A/lC/lD -- new rubber seats l

l b.

AH-V1A/lD -- bearing inspection and/o* replacement l

c.

WDG-V4 -- new disc d.

RB-V7 -- new type gate valve and actuator installed 2.2 Access Hatch Testing / Repairs 2.2.1 Door Seals SP 1303-11.25 Weekly door seal leak tests were performed during the current cold shutdown condition until issuance of a new technical specification which eliminated the need for these. 0cco-ional seal replacement was performed in response to high leakage although the as-found leakage at no time violated technical specification requirements.

The installation proced: ire for door seals was changed to require RTV silicone sealant to be used under the rubber door seals to keep them from popping out under high (55 psig) test pressure.

2.2.2 Overall Hatch Test The following leak tests on each access hatch have been performed thus far in 1981. No repairs were initiated as a result of these tests.

Date Personnel 6/81 Emergency 1/ 81, 5/ 81 _ _____ _ _-___-___

2.3 Penetration Pressurization SP 1303-11.24 Quarterly readings were recorded on 3'81 and 6/81 from the flow rotometers which supply air pressuco or nitrogen pressure to reactor building mechanical and electrical penetrations. No penetration leakage problems were noted although flow meter malfunctions required meter repair.

3.

METHODS OF TESTING 3.1 Valve Test Methods Testing was performed by use of TMI Unit 1 surveillance 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 for each penetration / valve. The following general philosophy is contained in the surveillance procedure.

3.1.1 Use air or nitrogen at a pressure differential across the valve greater than Pa (Calculated accident pressure).

55 psig was normally used.

3.1.2 Assure that the pressure is exerted in the accident test direction unless it can be demonstrated that pressurizing in the opposite direction is as conservative.

Butterfly valves AH-Vl A/lB/lr/lD, and globe valves WDG-V4, SA-V3 and I A-V20 vere tested in the reverse direction.

3.1. 3 Assure that the test volume is drained of liquid so that air or nitrogen test pressure 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..

i

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

.,,. ~,, _,

...m

3.1.5 Assure adequate time period for stabilization of test 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 to verify meters accurate within + 4% full scale.--

MP 1430-Y-22).

2 1.7 Assure that the fit.id blocking system is drained and vented dt. ring tests on the associated containment isolation valves to prevent any effects it might have on the test results.

(Most of the F.B.

system piping is seismic 3).

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

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

3.1.10 Record test instrument scale readings prior to doing any data correct'ons.

3.1.11 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.

A training program prior to the refueling outage was performed to help assure that the at,cve philosophy was understood by the personnel involved in the testing.

3.2 Access Hatch Test Mathods 3.2.1 Door Seal Leak Tests-Method Door seal leak tests were performed by use of SP 1303-11.25.

This procedure givas detailed guidance on the test equipmer.t and methods to be used.

The door seal tests are now performed by pressurizing the interspact > ~ tween the double seals on each door witp metered air at manut acturers recommended test pressure of 10 psig.

(Until recently the technical specifications required these tests to be done at greater than calculated accident pressure.)

After stabilization the air rotameter indicates the rate of air input required to maintain the test pre 3sure.

3.2.2 Overall Hatch Leak Test -- Overall hatch leak testing was performed by use of TMI Unit 1 Surveillance Procedure SP 1303-11.18 Reactor Building Local Leak Rate Testing. This procedure gives oczailed 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. Rubber door seals,
c. Teflon operating shaft packing,
d. Bulkhead electrical penetrations,
e. Pee,etration pressurization check valves.
f. Emergency air flange and associated "0" rings on outer bul khead,
g. Bulkhead equalizing ball valves and associated.nounting flanges /

"0" rings.

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

l 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.

3.3 Penetration Pressurization - Method Quarterly readings were taken on the flow rotameters which are permanently installed in the penetration pressurization system. These j

readings represent tl e air / nitrogen makeup _ rate required to maintain 1

approximately 60 psig in mechanical penetrations and 30 psig in l

electrical penetrations. High meter readings have occasionally occurred but these have been attributed to leaks in the many compression fittings in the penetration pressurization system or to malfunctioning 3

(stuck) rotameters. Testing was per the guidance in SP 1303-11.24.

4.

TEST EQUIPMENT USED 4.1 Valve Test Equipment (See Figure 1)

a. Rotameters - Sets of 3 Mfgr. - Ev 'oks Inst. Co.

Model - 1114 Full View l

Ranges:

i Float Mat'l.

Tube #

Range Pyrex R-2-15D 8-1,120 SCCM-Saphire R-2-15C

. 100-12,200 SCCM Carboloy R-6-15B 1,000-142,000 SCCM Accuracy + 2% full scale industrial accuracy i

)

i

b. Temperature indicators (as follows or similar)

Mfgr. - Ashcroft Model - EH or AH / 3" or 5" Dial :

i

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

,_.,._,r_. -.. -,,-,.,-,,.

,,,._4___..-r~.-w-__._,

,y--.-

w._,

,-m,

<,,.,.y

1 i

j Range 30 -130 F i

l Accuracy

+2F

c. Pressure Indicators (as follows or similar)

Mfgr. - Ashcroft Model - 1279 - 4h" Dial 4

i-Range 0-60 or 0-100 psig Accuracy i 2 psig

d. Pressure Regulator (as follows or similar)

Mfgr. - Union Carbide Corp.

Model - UPG 3-75-583 Range 0-100 psi output / 0-3000 psi input

e. Calibration Rotameters (Set of 2) i.

Mfgr. - Brooks Inst. Co.

Models - 1110-05K2B1249, ll10-08K2B1Z06 Ranges 20-16,000 S CM, 3,600-234,000 S CM 4

l Repeatability + 1/4% of instantaneous i

]

Accuracy

+ 1% instantaneous

f. Flow rate Calibrator i

Mfgr. - Brooks Inst. Co.

Model - 1056A Range 0 to 2,400 SCCM Accuracy

+ 0.2% of indicated volume

{

4.2 Access Hatch Test Equipment

a. Precision Pressure Gage (as follows or similar) l Mfgr. - Heise 1

Model - CM l'.

e m

1 Y

t F ~~ ~~ ~~ ~ J T

l l

f_

1 1!,

i l

Ig+

I I

ll ll l

Sprar#

3pscI##, co rrod ll p3 C l

l

\\

l I't'""*

CSV b

4* ff r-iGMU" 9

\\

j

\\/ p N-fs X

';===%

ll l

r a

l 0

T T ll l

l

)

i N

l l

l f

f ' ' Ifl pg)

E W

i

@,U h l

V5 s#

yp r vs S,ec.o I

i. i i r -i I

a 6 cunss

' o, l

T()

-)

,g

,' {1 ;

a r saramj

e

~ '

-lER<}-

)

- VEN7* fflG-va 4

k Vs Y1 L- _ - _ _ _ _ _ _ ____ _]

~

l 4,

l t1}

- PRESSURI2ATION RIG -

t n.se on,as l

4 4

METas VAL.ves I

~_Ryss? ----.

VI-N OTnf RE6Dt.hTok l?

TU8EW F10AT

@ OfDy

@ 5ffst3 2

LO R-2-15 D Black 0/ ass 8 - 3so Sccn1

.yg.ll2oSccM op b

WO I?-2 -154 Syn. Saykhn 100 - 5,30^ Sc cM 100 -jp '200 SCCP1 V5

-AOwsrnatt sAs tr>'-ss-q q

x.

M t3 HtGt/ g. g.jy.g [,4,f,y g,ooo. g,;.~

  • SccM 2000 -jq,2,o** SccM fy Pxc.ssuer rooienro,a T~EmP D/blCATORS 2 5 ~l; 5'"E~ t' 2 "fAnwgf r-O -100 P sif t ifsoy AccuMAcy GN h*

Range 0.60 psig Resolutfon 0.25 psig Accuracy 0.1 %

b. Barometer (as follows or similar)

Mfgr. - Pernwalt Mooei lA185260A Range 10.8 - 15.5 psia Resolution 0.005 psia Accuracy 0.1%

4.3 Penetrrrion Pressurization Test Equipment

a. Flow Rotameters - (Permanent System Equipment)

Mfgr. - Brooks Inst. Co.

Model - 1114 Range 0-10 SCFH at 60 psig air Accuracy

+ 2% Industrir.) accuracy 5.

SUfEARY AND INTERPRETATION OF DATA 5.1 Valve Test Results

a. As-Found Leakage - Also see tabulation of individual results in Attachment #2.

Total leakage Tech. Spec. Limit

% Tech. Spec. Limit

  • 18,351 SCCM 104,846 SCCM 17%
  • This includes the most recent access hatch leakage.

NOTE: The tet+1 shown above is cumulative by penetration and not the total of all valve leakages.

i.e., Only the highest valve leakage on each penetration is counted.

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.

b. As-Left Leakage Same as the As-Founi results.

5.2 Access Hatch Test Results 5.2.1 Overall Hatch Leakage - See the computer tabulation of 1981 leak rates in Attachment #2. The leakages were considered to be satisfactory.

5.2.2 Door Seal Leakage Numerous weekly door seal tests failed the 3 SCFH administrative leakage criteria but there were no violations of any Technical-Specification leakage limits.

Containment integrity was not required during this time period. Door seals were replaced several times to obtain satisfactory (less than 3 SCFH) retest results.

5.3 Penetration Pressurization Leakage Leakage Rates Date Mechanical Electrical 3/14/81 OSCFH Indeterminate

  • 6/1 9/81 OSCFH 0 SCFH
  • One meter float stuck i

l No penetration leakage problems were evident from these results.

l L

/

6.

ERROR ANALYSIS 6.1 Valve Testing Errors (Fo, purge valves see section 6.2)

The flow meters used in the field have normal industrial accuracies of i 2% full scale in the 10-100% (15-150 mm) scale range.

Prior to use mm versus sccm graphs were developed for each meter by 10 point calibrations using high accuracy (i1% instantaneous) lab rotameters.

During the leak test program weekly 3 point standardizations were performed on the field rotameters to verify continued accuracy.

The acceptance criteria for these standardizations was a variance of no more than 4% from the calibration graphs. The original 10 point calibrations remained valid throughout_the test program.

Scale readings on the leak rate procedure (SP 1303-11.18) data sheets were evaluated and corrected using the methods in Attachment #1.

Approximately 10% conservative bias was introduced into the results by assuming 15mm (10% of scale) as the minimum scale. Half of the test results actually showed a lower scale reading. More involved error corrections were not considered desirable based on the low total leakage.

6.2 Access Hatch and Purge Valve Testing Errors The measured pressure drops were corrected by adding the minimum scale increment of the gage used for both the heise gage and the barometer.

This conservatively corrected for the resolution and repeatability crrors. Gages used were recently calibrated. A mininum one hour temperature / pressure stabilization period was used prior to each oressure drop test. The access hatches and purge valves are not instrumented to allow temperature corrections.

4

(

6.3 Penetration Pressurization Testing Errors J

These test results are used for information only and do not count toward the total leakage limit for Technical Specification conformance.

The meters, installed perr..anently in the system, have + 2% full scale industrial accuracy.

7.

REF'RENCES 7.1 1430-Y22 Standardization of Flow Rotometers (TCN 81-43) 7.2 SP 1303-11.18 Reactor Building Local Leak Rate Testing (Rev.19) 7.3 Three Mile Island Unit 1 Technical Specification 4.4.1 7.4 TMI Surveillance File (for Data Sheets) 3 7.5 SP 1303-11.24 R.B. Local Leakage Penetration Pressurization (Rev. 0) i 7.6 SP 1303-11.25 R.B. Local Leakage Access Hatch Door Seals (Rev. 4) 1

)'

l l

+

l

,qg_,

+

w

(

(A P P E N D I X H)

ATTACHMENTS 1

(APPENDIX H)

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

'R.B.

LOCAL LEAK RATE TESTING RESULTS EVALUATION The vent rotameter reading will be used if it can be demonstrated by the o

test data that all significant CIV leakage is being accounted for.

If CIV packing, fluid block check valve, or gasket leakage was evident the supply rotameter results will be used unless this non-seat leakage was measured reliably and documented.

FOR USE OF SUPPLY FOR USE OF VENT ROTAMETER DATA:

ROTAMETER DATA:

Procedure:

Procedure:

a) Record supply meter reading in (1) a) iu cord vent meter reading in (1) below.*

below*.

Also identify the meter used by tube # in (8) below and b) Record downstream verification meter the' metering pressure in (9).

reading in (2) below. Also identify the respective meters used in (8) be-b) Convert meter units to SCCM units low and the metering pressure in (9).

using latest lab meter calibra-tion curve. Enter in (3) below.

c) Convert meter units to SCCM units using latest lab meter calibraton curve.

c) Correct results for temperature.

Enter in (3) below.

Enter supply temperature in (4) d) Correct results fog temperature. Enter below.

vent temperature ( F) in (4) below.

Calculate and enter in (7) t,elow.

then Calculate and enter in (5) below e) If measurements of any other significant leakage paths (fluid block check valve, packing) are being claimed er.ter corrected flow (SCCM) in (6) below.

  • If meter scale reading was less than 13mm (minimum scale) use 15mm in calculations.

(MM)

(SCCM) f 53,0

) convert (

+

)

X

+ 460 =

SCCM

(

+

(1)

(2)

(3)

(4)

(5)

(8) (Identify meters used)

+

SCCM (6)

(9) (Meter Press'nres

= ClV Leakage SCCM' (7)

REPAIR CRITERTA DETERMINING NEED TO REPAIR VALVES The target criteria throughout this surveillance procedure are intended strictly as indications of commonly attainable leakage rates. The engineering staff has also assigned " maximum" leakages for valves 6" or larger in accordance with ASME Section XI.

1974 Edition thru summer 1975 Addenda.

(See below)

Valve repairs will be performed for one of two reasons:

1.

POTENTIAL SIGNIFICANT REDUCTION IN THE TOTAL LEAKAGE RATE.

The potential for reduction should be apparent by comparing the "as found" leakage with the target criteria.

The total must not exceed 104,846 SCCM as set by Appendix J-10CFR50 and should be less than 60,000 SCCM (for reasonable margin between refuelings).

2.

VIOLATION OF LEAKAGE LIMITS SET BY ASME SECTION XI 6" valves and smaller - maximum 10,000 SCCM (Set by Engineering Staff) 8" valves - maximum 15,000 SCCM (Set by Engineering Staff)

Larger than 8" - maximum 20,000 SCCM (Set by Engineering Staff ASME Criteria:

For valves 6" and larger, if an as-found leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin be-tween measured leakage rate and the maximum permissible rate (above) by 50 Percent or more corrective action shall be taken.

Example:

a. 8" valve - maximum 15,000 SCCM
b. previous leakage 8,000 SCCM
c. last test 11,000 SCCM 6.

c w

e--

  • 17 tm,,

~ -, - -

7-leakaae change 11000 - 8000 43 Percent (acceptable)

=

=

original margin 15000 - 8000 When tests show a leakage rate increasing with time, and a projection

[

based on three or more tests indicates tha'. the leakage rate of the next scheduled test will exceed the maximum permissible by more than 10 Percent the valve shall be replaced or repaired and retested to demonstrate satis-factory operation before being returned te service.

i 0

0 e.

J

^

(APPENDIX H)

ATTACHMENT 2 DATA 1981 TYPE C REACTOR BUILDING LEAK RATE TESTING i

}

r l

l l I i

THREE MILE ISLAND NUCLEAR PLANT UNIT i

.RB. LOCAL LEAK RATE. TESTIriG RESULTS UPDATE _

SP1303-il.18

~

1981 ITEM TAG DESC SIZES OPER ASFOUNL ASLEFT ASLTDATE 1

AH-VIA/B BFLY 40 P/MG 1755 1755 6/18/81 l

2 Ari "i C/D BFLY 48 N0/P 585 585 6/12/81

.- -__3.

CA-Vi.

GLOBE _

_ _ 1..

MO.

.4 7 -

. 4 7.

3/1i/81.. __

4 CA-V2 GATE i

P 47 47 3/11/81 5

CA-V3 GLOBE i

MO 47 47 3/11/81

.6 CA-V4A

. GLOBE _

.i MO..

.86.

86

_3/9/81.

7 CA-V4B GLOBE i

MO 47 47 3/10/81 8

CA-V5A GATE i

P 115 115 3/10/81

.9-CA-V5B

. GATE i

P 47.

47

._3/10/81 10 CA-V13 GLOBE i

MO 86 86 3/11/81 11 CA-V189 GATE 2

P 45 45 3/9/81

.12 -.CA-Vi92

__LET CHK. _

.2.

N/A 46

.46 5/16/81 13 0

0 0

14 0

0 0

u-.15_

CF-V2A-GLOBE i

. MO.

46 46 4/8/81.

16 CF-V2B GLOBE i

MO 46 46 4/8/81 17 CF-V12A LFT CHK i

N/A 62 62 4/9/81

- _ 18 -

CF-V12B

.LFT CHK-

.11 N/A 220

_220.

.4/9/81 19 CF-V19A GATE 1

P 46 46 4/9/81 20 CF-Vi9B GATE i

P 46 46 4/9/81 L

.2L CF-V20A GATE i

P 939.

939.

4/8/01 22 CF-V20B GATE i

P 303 303 4/8/81 23 CM-Vi BALL i

P 66 66 4/18/81 24 CM-V2 BALL _

1-

.P 119 119..4/18/81 25 CM-V3 BALL 1

P 66 66 4/18/81 26 CM-V4 BALL i

P 66 46 4/18/81 27.

DH-V64 GLOBE 2

HW 46 46

_ A/28/81 28 DH=V69 STOP CHK 2

liW 2427 2427 4/28/81 29 0

0 0

30

_FTTEAST-FLANGE

.30 N/A 67 67.

5/2.1/81 31 FTTWEST FLANGE 30 N/A 67 67 5/21/81 32 lip-Vi GATE 6

HW 1731 1731 4/23/81 33 lip-V6 GATE

- 6 HW.

2324 2324

.4/23/81 34 HR-V2A/B GLOBE 2

HW 57 57 8/21/81 l

35 HR-V4A/B GLOBE 2

HW 59 59 6/25/81

(-.

36..HRV22A/B-GLOBE 2

.. S 142 1 4 2 --

8/81-f 37 0

0 0

l 38 HR-V23A GLOBE 2

S 290 290 8/81 l.

.39.

HR-V23D.

GLOBE 2

.5 290 290 8/81 l

40 IA-V6/20 GLOEE 2

IfW 57 57 4/12/81 l

41 IC-V2 GATE 6

MD 46 46 3/20/81

!. _ _4 2 IC-V3.

GATE.

.6.

_P 46.

. 4 6.

.3/20/81.

t i

i

_ _ m..

ITEM TAG DESC SIZES OPER ASFOUND ASLEFT ASLTDATE

        • x s**
        • x**
  • x**

43__IC-V4-

-. G ATE - _. __- ~.6 -

P-

_.__.A5.

.45-._

3/13/81 -_.- _

'44 IC-V6 GATE 3

- P 45 45 3/12/81

-45 LR-Vi GATE 6

HW 57 57 4/10/81 l

.. _.-- 4 6. ----._ R ~ V 2 - - G ATE - - - - -. - HW -- - ---268

- - -- 268 -- 4 /10 /81 - -

47 LR-V3 GATE 6

HW 57 57 4/10/81 48 LR-V4 GLP9E

.75 HW 57 57 4/10/81 4 9-LR-V5. -- GLNE. - - -- -.HW-

--- 4/ i O/81 -

50 LR-V6 GLOBE 7

HW 80 80 4/10/81 Si LR-V49 GATE i

HW 47 47 4/15/61 u-52 -- --MU-V2A i - GLOBE 2.5-MO -.--- i 89 189_ 2/i 8/81-._-_.-

53 MU-V2B GLOBE 2.5 MO 52 52 2/18edi 54 MU-V3 GATE 2.5 P

47 47 2/18/81

. -- 5 5. - MU-V 18- - - GATE- - -

-2.5

--P

-. -. -- - ~2/1.1/81 -

56 MU-V2O GATE 4

P

'46 46 4/14/81 57 MU-V25 GLOBE 4

MO~

46 46 4/16/81

~ _ 58 MU-V26-.

-GATE

._ -.. _ 6. - _ P _ - -- - 46.

46_.

4/16/81 59 MU-Vii6 PIST CHK i.5 N/A 245 245 4/28/81 60 NI-V27 i

HW 46 46 5/21/81

. -. _ 61 -

NSrV4 GATE _.

.. i. 5_

-.N/A_

46 _. - --. _ 4 6 - _..

4/21/81-_

62 NS-V15 GATE 8

MO 46 46 4/21/81 63 NS-V35 GATE 8

MO 46

.46 4/21/81

--.64 PENETiO4- -BLK FLG.

--_2-_

_ N/A__

57

_ _ _. 5 7_ _.

6/23/81 _ -- _.-. _ _.

(5 PENETiOS BL K FLG 10 N/A 57 57 4/15/01 66 PENLT106 BLA FLG 4

N/A 57 57 4/15/81

--._67- _ PENET2tO_ BLK.FLG _

2 N/A 57

--__-_.-.57._ _.4/24/81..~.- -- - _

68 PENET2ii BLK FLG 2

N/A 57 57 4/24/81 69 PENET241 DLK FLG 18 N/A 57 57 4/24/81

._-_70_ _._ RB -V2 A.

_ GATE

_8.

MO.

47-A 7.

14/12/81_- -. _

71 RB-V7 GATE 9

MO

'16 86 3/25/81 72 SA-V2/3 GLOBE 2

HW

$2 52 2/9/81

_ 73-SF-V23.- _ GATE.

8

._-HW 46 ~

_.46_

_ 4 /2 '/ 81_ _ -. _. _ -

74 WDG-V3/4 GL/GA 2

MO/P 4783 4783 5/18/81 75 WDL-V303 GLOBE 4

MO 59 59 2/23/81

._ 76

.WDL-V304-G ATE - -- - - - _4-

-.D.

-- --51 51-2 / 24 / 81. ---.

- - -m 77 WDL-V534 GATE G

P 51 51 2/26/81 78 WDL-V535 GATE 8

P 51 51 2/26/81

- ~79 -_EDPFLG --~ FLANGE

.216 N/A - - - -

51-3/4/81- - -

80 PERACCES MISC.

96 N/A 1255 1255 6/7/81 81 96

.01

.01

..EMEACCEI_ MISC-

.96

. N/A

.._.177-

.177~. __5/24/81 __ --

.~. -- !

r 83 96

.01

.01 ITEM TAG TARGET ASFOUND ASLEFT

  • u******

_. 8 4 - -. TOT AL- - - - - 64549- - 212.98.02

. 21298.02.

_ _ ~ -_._

85 PENTOTAL 53598 18351.01 18351.01 86 ACC CRIT 23975 104846 104046 Wee.

--4_.4

+

v-g

.h.-.

m--

-m-

.a,,

.4--

w s

W

.+ -

i i+---e- - -...., --

,,a

.a

~

- - - - =, -

__.LRTERMS - TERMINOLOGY USED IN COMPUTER PROGRAM FOR L OCAL LEAK RATE TESTING RESULTS, i)

.1-(ALUNE) OR ANY OTHER NUMBER OTHER THAN ZERO IN THE FIRST DECIMAL PLACE MEANS TEST SCHEDULED.

2).

-. 01 -(ALONE) MEANS NO DATA AVAILABLE FOR YEAR OR TEST DELAYED.

(E.G. VALVE NOT INSTALLED YET OR NOT IN PREVIOUS TESTING SCOPE) 3)

.001 - (OR ANY. NUMBER OTHER THAN ZERO IN THE THIRD DECIMAL PLACE) AFTER A LEAK RATE (I.E. 59500.001) MEANS ACTUAL LEAK RATE' GREATER THAN. MEASURED / RECORDED VALUE.

4) TARGET-ADMINISTRATIVE LEAKAGE LIMIT BASED ON TESTING EXPERIENCE.

COMPLETE EXPLANATION.GIVEN IN spi 303-ti.18.

5) ASFD__

LEAK RATE (SCCM) IN THE AS-FOUND VALVE CONDITION.

BEFORE ANY REPAIRS OR ADJUSTMENTS. FOR THE DESIGNATED YEAR.

6) ASLT__ - LEAK RATE (SCCM) ATTAINED A'r 'ER ANY ADJUSTMENTS / REPAIRS.
7) SIZES - PIPE DIAMETER (INCHES) FOR VALVE / PENETRATION.

.8) RUNTOTAL-RUNNING TOTAL..THIS IS THE LIST OF LEAKAGES WHICH IS USED FOR DETERMINATION OF REPORTABILITY.

A NEW ASFD LEAKAGE REPLACES THE PREVIOUS YEARS ASLT LEAKAGE.

RETEST RESULTS ARE NOT INCLUDED UNTIL AFTER DETERMINING REFORTABILITY.

9) SCHED-SCHEDULED DATE FOR TEST

.iO) ASLTDATE-DATE OF LAST ACCEPTABLE TEST RESULTS

11) RETESTi/2/ETC-LEAK RATE (SCCM) FDP RETEST AFTER REPAIRS AND/OR ADJUSTMENTS.
12) ITEM-REFERENCE NUMBER CORRESPONDING TO THE POSITION IN A DATA ARRAY OF ANY DATA FOR A PARTICULAR VALVE.

I.E.

DESC(2) CORRESPONDS TO TAG (2) WHICH IS AH-ViC/iD AND TO ITEM (2).

13) DESC - DESCRIPTION OF VALVE OR PENETRATION.
14) OPER - TYF'E OF VALVE OPERATOR (ACTUATOR)

HW= HANDWHEEL ONLY MO= MOTOR AND HANDWHEEL P=

PISTON (SOME OF THESE HAVE HW ALSU)

S=

SOLENOID. ACTUATED ONLY N/A=NO ACTUATOR (E,G. CHECK VALVE) 15 NOTEST - THE TECH SPEC SCOPE DID NOT REQUIRE THIS VALVE TO BE TESTED DURING THIS YEAR 16 NOVALVE-THIS VALVE W/S INSTALLED DURING A LATER REFUELING PERIOD.

_ _ _ _ _ _ _ _ _ - _ - _ _ _ _ -

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