ML20062K169: Difference between revisions

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| document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST REPORT
| document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST REPORT
| page count = 18
| page count = 18
| project = TAC:07711, TAC:08404, TAC:7711, TAC:8404
| stage = Other
}}
}}


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Type "A" containment pressure testing.
Type "A" containment pressure testing.
l
l
: 3. C. W. Fay to H. R. Denton letter dated May 2, 1980, committed to
: 3. C. W. Fay to H. R. Denton {{letter dated|date=May 2, 1980|text=letter dated May 2, 1980}}, committed to
:                put the containment isolation signals back on the steam generator blowdown and sample valves but not test them per Appendix J.
:                put the containment isolation signals back on the steam generator blowdown and sample valves but not test them per Appendix J.
  ;        4. Electrical penetrations E58, E20, E22, and E1 were newly installed during Refueling 7 (April - May,1981) . Because of their design, they require a leak test (Type "B") and will be tested regularly henceforth, i
  ;        4. Electrical penetrations E58, E20, E22, and E1 were newly installed during Refueling 7 (April - May,1981) . Because of their design, they require a leak test (Type "B") and will be tested regularly henceforth, i

Latest revision as of 04:57, 1 June 2023

Rept of Reactor Containment Bldg Integrated Leakage Rate Test for Point Beach Unit 2
ML20062K169
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 07/31/1982
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20062K158 List:
References
TAC-07711, TAC-08404, TAC-7711, TAC-8404, NUDOCS 8208170068
Download: ML20062K169 (18)


Text

__

July 1982 REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST FOR POINT BEACH UNIT 2 I. General Data t

A. Owner - Wisconsin Electric Power Company B. Docket Number 301 C. Location - Two Rivers, Wisconsin D. Containment Description - 3\ foot pre-stressed post-tensioned concrete cylinder with k inch welded ASTM A-442 steel liner E. Date Test Was Completed - April 21, 1982 ,

II. Technical Data A. Containment Net Free Volume - 1,000,000 cubic feet B. Design Pressure - 60 psig C. Design Temperature - 286*F D. Calculated Accident Peak Pressure (Pac) - 53 psig

(, ,

E. Calculated Accident Peak Temperature (Tac) - 286*F III. Test Data A. Test Method - absolute B. Data Analysis Technique - mass point C. Test Pressure - 30 psig D. Maximum Allowable Leak Rate (La) - 0.4% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> E. Calculated Leakage Rate at Upper Confidence Limit (UCL) -

0.0715% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. Measured Leak Rate (Lam .0491% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) ,

IV. Verification Test A. Calibrated Leak Superimposed .1530% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 8208170060' 820811 DR ADOCK 050003o3 PDR

i i ,

V. Analysis and Interpretation The third periodic Type "A" Integrated Leakage Rate Test (ILRT) of the Point Beach Nuclear Plant Unit 2 Containment was performed April 18-21, 1982, with satisfactory results. The testing program was conducted in accordance with the requirements of the Point Beach FFDSAR Chapter 15, " Technical Specifications," paragraph 4.4 Containment Tests.

The testing instrumentation system was composed of temperature and humidity readout devices and humidity / sensors different from those used during the preoperational test and previous in-service tests.

The new instrumentation system components were used in order to expedite the data taking process. The test procedure and the data analysis computer program were used in order to expedite the data taking process. The test procedure and the data analysis computer program were provided by Quadrex Corporation. The Type "A" test could have been considered successful and terminated after five hours had there not existed a 12-hour minimum duration commitment with the NRC. To verify the results, an " induced leakage rate" approximately equal to the maximum allowable operational leakage rate was superimposed on the actual leakage rate at 30 psig.

The absolute value of the total measured leakage rate (L,=.0491) was a small fraction of the allowable operational leakage rate

/~ (L ,=.201). The instrument error analysis shows this measurement

\ system to have an accuracy of 1 .0276 percent leakage rate per day at a 95 percent confidence level. The absolute value of the difference between measured leakage from the Type "A" test data and measured leakage from verification test data was .0264 at a 95 percent confidence level.

The elapsed times, the least squares leakage rate, the 95% con-fidence level rate, total time leakage rate, and the total leakage are tabulated below: ,

r Tabulation of Calculated Parameters Test 30 psig CILRT 30 psig verification Time 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 6k hours Least Squares L a= .0491%/ day L ** = .2053%/ day L ' = .0555%/ day e m Leakage Rate 95% Confidence = .0715%/ day = .2476%/ day = .0979%/ day Leakage Rate i

Total Time = .0738%/ day = .1530%/ day = .0038%/ day leakage Rate Total Leakage .0369% .0398% = .0010%

    • This column represents leakage rates based upon the leakage measured during the verification added to the induced leakage rate of .1498%/ day.

VI. Summary of Events A. General Due to the test configuration of the containment, eleven penetra-tions were not subjected to the 30 psig Type "A" test pressure.

These eleven penetrations, justification, and Type "C" test results are identified below:

Penetration Justification Type "C" Results CVCS Supply Line In use to control primary 46 seca

(#26) system pressure CVCS Letdown Line In use to control primary 5 sccm

(#10) system pressure RCP "A" Seal Injection Maintain flow of clean 2 seem Line (#29A) water through RCP seals RCP "B" Seal Injection Maintain flow of clean 1 scem Line #29B) water through RCP seals RCP Seal Return (#11) Maintain ilow path for 23 seem seal leakage Service Air Line Modified to allow for 125,000 secm l

(#33C) containment depressurization (9 secm)

Containment Pressure Modified to provide a 1 scem2 Sensing Line (#31A) pressure point for Type "A" test purposes Auxiliary Charging Proper venting of line is I seem Line (#32C) not possible when seal injection lines are in use.

Reactor Makeup Proper venting of line is not I seem Water Line (#30C) possible without securing entire reactor makeup water header, which would affect Unit 1.

l Containment Pressure Isolated to allow for 8 scem2 Sensing Line (#32A) system modification "A" Steam Generator Isolated due to leakage 1,368 seem 2 i Blowdown Line (#51) l 1

Prior to modifying this penetration to perform the test, the leakage was measured at 125,000 secm. The valve was subsequently repaired prior to the performance of the Type "A" test. The Type "C" retest resulted in a leakage of 9 seca.

l 2 Type "C" leakage tests were performed prior to Type "A" test to assure "as found" leakage.

Th2 total Type "C" leskaga w:s 126,462 secs or 0.1468%/dr.y. After the repairs, the total Type "C" leakage was 1,471 seca or 0.0017%/ day.

Therefore, the "as found" adjusted leakage was 0.0491%/ day +

0.1468%/ day or 0.1959%/ day. The "as left" adjusted leakage was 0.0491%/ day + 0.0017%/ day or 0.0508%/ day.

i

Enclosure 1 Sheet No. 1 ,

TYPE "B" TESTS PERFORMED BETWEEN REFUELINGS TS-10 Lower Personnel Hatch 06-07-78 1,260 cc/ min  !

TS-10 Upper Personnel Hatch 06-08-78 8,000 cc/ min i TS-10 Lower Personnel Hatch 12-08-78 2,830 cc/ min TS-10 Upper Personnel Hatch 12-19-78 70 cc/ min TS-10 Lower Personnel Hatch 04-07-79 5,000 cc/ min TS-10 Upper Personnel Hatch 06-06-79 1,100 cc/ min TS-10 Lower Personnel Hatch 06-07-79 4,000 cc/ min ,

TS-10 Upper Personnel Hatch 08-04-79 1,676 cc/ min TS-10 Upper Personnel Hatch 12-04-79 75 cc/ min TS-10 Lower Personnel Hatch 12-05-79 36,000 cc/ min

  • TS-10 Lower Personnel Hatch 12-06-79 <2,000 cc/ min TS-10 Upper Personnel Hatch 06-03-80 620 cc/ min TS-10 Lower Personnel Hatch 06-04-80 1,175 cc/ min TS-10 Lower Personnel Hatch 12-31-80 159 cc/ min TS-10 Upper Personnel Hatch 01-10-81 164 cc/ min TS-10 Lower Personnel Hatch 05-30-81 388 cc/ min TS-10 Upper Personnel Hatch 05-30-81 1,308 cc/ min I

TS-10 Lower Personnel Hatch 11-05-81 1,098 cc/ min TS-10 Upper Personnel Hatch 11-05-81 500 cc/ min

  • Retest after maintenance.

I l

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{

_,v - -- , - . , , . . - - --

c Enclosure 1 Sheet No. 2 TYPE "C" TESTS PERFORMED BETWEEN REFUELINGS Leakage ORT # Penetration Date Title (sccm) 62 V1 04-20-78 Purge Exhaust 0 63 V2 04-21-78 Purge Supply 1 62 V1 08-18-78 Purge Exhaust 160 63 V2 08-18-78 Purge Supply 190 62 V1 10-25-78 Purge Exhaust 620 63 V2 10-25-78 Purge Supply 360 62 V1 12-19-78 Purge Exhaust 125 62 V1 07-19-79 Purge Exhaust 1,782 63 V2 07-19-79 Purge Supply 32 62 V1 03-12-80 Purge Exhaust 740 63 V2 03-12-80 Purge Supply 850 Y* - - . - . .-

REFUELING CONTAIllMEtIT PEteETPRTIC24 Enclosure 2 LEAKAGE RECORD Sheet No. 1 Refueling Refueling Refueling Refueling UNIT # 2 March - flarch - March - March -

DATE 1978-1979 TYPE "C" TESTS April, April, April, April, 1978, As 1978, 1979, As 1979,

, Found Leakage Found Irakage Leakage, After Leakage, After ORT PENETRA- scem Repair, scem Repair, NO. TION TITLE seem seem 25 9 RCDT Pump Suction Line (Enter highest test) 28 NA 37 NA 26 10 Letdown Line O NA 20 NA 27 11 RCP Seal Water Return Line 3 NA 200 NA 28 12A DI Water Line 0 HA 1 NA 29 12B Test Connection 0 NA 18 NA 30 12C RCDT and PRT Vent (Add test together) 3 NA 145,134 369 31 14A Nitrogen Supply to PRT 3 NA 20 NA 32 14C Nitrogen Supply to the Accumulators 388 NA 807 NA 33 25C PACVS Return Line 9 NA 40 NA 34 26 Charging Line Check Valve 3 NA 30 NA 35 28A Not Leg Sample 98 NA 6,000 3

36 28B Pressurizer Liquid Space Sample 170 NA 296 NA 1

37 28C Pressurizer Steam Space Sample O NA 10 NA 38 39 29A Seal Injection Supply RCP "A" 9 NA 4 NA 40 29B Seal Injection Supply RCP "B" O NA 4 NA 41 30A Test Connection 7 NA 60 NA ,

OPS-27 (03-78)

REFUELING CO23 TAIT 04ENT PENFc?ATION Enclosure 2 LEAKAGE RECORD Sheet Mo. 2 Refueling Refueling Refueling Refueling UNIT # 2 April - April - April - April -

DATE 1980-1981 TYPE "C" TESTS May, 1980 May, 1980 May, 1981 May, 1981 .

I t As Found Leakage As Found Icakage Leakage, After Irakage, After i

scem Repair, scem Repair, ORT PENETRA- sccm seem NO. TION TITLE 25 9 RCDT Pump Suction Line (Enter highest test) 40 NA 36 NA 26 10 Intdown Line 15 NA 55 NA 27 11 RCP Seal Water heturn Line 17 flA 0 NA 28 12A DI Water Line O NA 0 NA 29 12B Test Connection 0 NA 3 NA

. 30 12C RCDT and PRT Vent (Add tests together) 0 NA 544 NA 31 14A Nitrogen Supply to PRT 0 NA 8 NA 32 14C Nitrogen Supply to the Accumulators 102 7 42,000 8 33 25C PACVS Return Line O NA 8 NA 34 26 Charging Line Check Valve 20 NA 6 NA 35 28A flot Leg Sample O NA 2 NA 36 28B Pressurizer Liquid Space Sample 17 NA 1 NA 37 28C Pressurizer Steam Space Sample 10 NA 0 NA 38 _ , , _ , , _ , , , . , , , _ __ ____ _ _ _ _ , _ _ _ _ _ _ _ __

39 29A Seal Injection Supply RCP "A" 22 NA 10 NA 40 29B Seal Injection Supply RCP "B" 20 NA 9 NA 1

41 30A Test Connection 19 NA 0 NA OPS-27 (0 3-7B)

RETJELING COR NI rei .NT PE'IE* RATION Enclosure 2 LEAKAGE RECORD Sheet No. 3 Refueling Refueling Refueling Refueling UNIT # 2 March - March - March - March -

DATE 1978-1979 TYPE "C" TESTS April, April, Acril, April, .

1978, As 1978, 1979, As 1979, Found Icahage Found Icakage Leakage, After Leakage, After ORT PENETRA- sccm Repair, scem Repair, NO. TION TITLE seqm scem 42 30C neactor Makeup Water Supply (Enter highest test) 9 NA 1 NA

, 43 31B Containment sample Line (Enter highest test) 9 NA 0 NA 44 31C PACVS Vent Line (Enter highest test) 20 NA 0 NA 9

45 46 32C Auxiliary Charging Line O NA 1 NA 47 33A Instrument Air Supply 3047 (Enter highest test) 108 NA 154 NA 48 33B Instrument Air Supply 3048 (Enter highest test) 56 NA 3 NA 49 33C Service Air Supply 16 NA 950 NA

. (Add tests 14 NA 55 NA 50 34A sample Line PRT to Gas Analyzer together) ~

III p 51 34C "A" SG Sample Line 8 NA n 52 34B "B" SG Sample Line 21 NA NA NA (Enter highest 53 34D Sample Line RCDT to Gas Analyzer 0 NA 10 NA sd

(

54 50 "B" SG Blowdown, 2045 5,000 10 NA NA 55 51 "A" SG Blowdown, 2042 33,000 1,688 NA NA 56 52 lleating Steam Supply 1,485 NA 9 NA 57 53 Condensate Return from Containment 1,029 NA 5 NA 58 56 Containment Test Connection 44 NA 3 NA

_ . _ . . . 1 ---

OPS-21 (03-78)

PEFUELING CONTAINf!ENT PEMTRATION Enclosure 2 LEAKAGE RECORD Sheet No. 4.

Refueling Refueling Refueling Refueling UNIT # 2 April - April - April - April -

DATE 1980-1981 TYPE "C" TESTS May, 1980 May, 1980 May, 1981 May, 1981 ,

As Found Leakage As Found Leakage Leakage, After Irakage, After scem Repair, sccm Repair, ORT PENETRA- seem scem NO. TION TITLE 42 30C Reactor Makeup Water Supply (Enter highest test) 20 NA 12 NA 43 31B Containment Sample Line (Enter highest test) 1 NA 24 NA 44 31C PACVS Vent Line (Enter highest test) 3 NA 13 NA 45 46 32C Auxiliary Charging Line 5 NA 588 NA 47 33A Instrument Air Supply 3047 (Enter highest test) 115 NA 124 NA 48 33B Instrument Air Supply 3048 (Enter highest test) 49 NA 225 NA 49 33C Service Air Supply 0 NA 42 NA t 50 34A Sample Line PRT to Gas Analyzer (Add tests 6 NA 0 NA together) 51 34C "A" SG Sample Line NA NA NA NA 52 34B "B" SG Sample Line ( '( }NA NA

' NA NA

" ' 9 53 34D Sample Line RCDT to Gas Analyzer 5 NA 0 NA

. test) 54 50 "B" SG Blowdown, 2045 NA NA NA NA 55 51 "A" SG Blowdown, 2042

( '(

'NA NA

'( 'NA NA 56 52 Ileating Steam Supply 799 260 89 NA 57 53 Condensate Return from Containment 69 NA 352 NA 58 56 Containment Test Connection 20 NA 28 NA UPS-27 (03-78)

REFUELING CONTAIt;"':NT PEEETMsTIC33 .

Enclosure 2 LEAKAGE RECORD Sheet No. 5 Refueling Refueling Refueling Refueling UNIT # 2 !4 arch - March - March - March -

DATE 1978-1979 TYPE "C" TESTS April, April, April, April, .

1978, As 1978, 1979, As 1979, Found Leakage Found Leakage icakage, After Isakage, After ORT PENETRA- scem Repair, sccm Repair, NO. TIOtl TITLE __

scem Eccm 59 54 P14A Spray Pump Discharge Check Valve 1 NA 0 NA 60 55 P14B Spray Pump Discharge Check Valve 300 NA 220 NA 61 71 Sump "A" Drain to A'axiliary Building 0 NA 4 NA 62 V1 Purge Supply 18 NA 385 NA 63 V2 Purge Exhaust 0 NA 18 NA 64 X1 Rll/R12 Suction Supply (Enter highest test) 1,')2 8 NA 53 NA 65 X2 Ril/R12 Discharge Return (Enter highest test) 78 NA 220,000 0 66 31A Pressure Test of . -945 and 946 'O NA 'NA NA 67 19 & 20 CCW to and from excess letdown IIEX og h) 30 NA 4 NA 68 15 & 17 CCW to and from "A" RCP (Add tests together) 2 NA 1,260 NA 69 16 & 18 CCW to and from "B" RCP (Add tests together) 4 NA 586 NA

_ . . . .. . . _ . _ - . . _ _ . . _ . . . . ....a.- . - . . _ . . . . _. . . - . .

END OF TYPE "C" TESTS OPS-27 (03-78)

REFUELING CONTAIPMENT PENETRATION Enclosure 2 L.iAKAGE RECORD Sheet P40. 6 Refueling Refueling Refueling Refueling UNIT # 2 April - April - April - April -

DATE 1980-1981 TYPE "C" TESTS May, 1980 May, 1980 May, 1981 May, 1981 .

As Found Leakage As Found Leakage Irakage, After Icakage, After scem Repair, scem Repair, ORT PENETRA- sccm scem NO. TION TITLE 59 54 P14A Spray Pump Discharge Check Valve 57 NA 106 35 60 55 P14B Spray Pump Discharge Check Valve 183 NA 175 392 61 71 Sump "A" Dra'n i to Auxiliary Building 0 NA 0 NA 62 V1 Purge Supplh 344 NA 408 NA 63 V2 Purge Exhaust 62 NA 250 NA 64 X1 Rll/R12 Suctich Supply (Enter highest test) 277 NA 265 NA 65 X2 Rll/R12 Discharg'e Return (Enter highest test) 191,000 0 275 NA 66 31A Pressure Test of PT-945 and 946 85 NA 16 NA 67

^ 347 NA 8 NA 19 & 20 CCW to and from excess letdown IIEX together) 68 15 & 17 CCW to and from "A" RCP (Add tests together) 62 NA 517 NA 69 16 & 18 CCW to and from "B" FCP (Add tests together) 559 .NA 959 NA END OF TYPE "C" TESTS OPS-27 (03-78) .

REFUELING COi1TAINMrMT PENE.? <ATION - Enclosure 2

  • LEAKAGE RECORD Sheet No. 7 kefueling Refueling Refueling Refueling UNIT # 2 March - March - March - March -

DATE 1978-1979 TYPE "B" TESTS April, April, April, April, .

1978, As 1978, 1979, As 1979, Pound Leakage Found Leakage wakage, After Leakage, After ORT PENETRA-  :;cc m Repair, scem Repair, NO. TIOti TITLE Scem sccm No 12 Fuel Transfer Tube Flange O NA 1 NA No 13 Equipment Hatch Flange 15 NA 0 NA Number ._. - _ . . . . . . - . . - - . - - - - - - - . _ . - -- -. - - - - - - - - - - -

70 71 72 73

, 74 P-50, 51' 75 M hanical Penetration Test 48 NA 0 NA 52 & 53 76 P-58 Mechanical Penetration Test 9 NA 95 NA 77 P-57 Mechan: cal Penetration Test 8 NA 215 NA 78 P-69 & 70 MPT (Sump "A" & "B" Drain Lines) 0 NA 26 NA

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

79 Number MPT (Fuel Transfer Tube Penetration) 0 NA 11 NA 80 P-13' 27 g Mechanical Penetration Test 3 NA 23 NA P-37,- . - - .38 -----.

36, 40' 81 Mechanical Penetration Test 70 NA 28 NA 48, 45,

  • 44, 46 P-5 & 6, 47 43' 82 Mechanical Penetration Test 0 NA 0 NA 39 35 I 55, 54 -

t _ . - -

OPS-27 (03-78)

RERIELING CON" AINF.tleT PENETRATION Enclosure 2 LEAXAGE RECORD Sheet No. 8 Refueling Refueling Refueling Refueling UNIT # 2 April - April - April - April -

DATE 1980-1981 TYPE "B" TESTS flay , 1980 May, 1980 May, 1981 May, 1981 .

As Found Leakage As Found Leakage Leakage, After Leakage, After

-- - ~~ ~ ~~~~ - --

sccm Repair, secm Repair, ORT PENETRA- sccm scem NO. TION TITLE 12 Fuel Transfer Tube Flange 1 NA 0 NA Number 13 Equipment llatch Flange 60 NA 0 NA Number 70 71 E-58 Electrical Penetration E-58 6 NA 72 E-20 & 22 Electrical Penetrations E-20 & E-22 8 NA 73 El Electrical Penetration El '6 NA 74

___~-- - - . - _ . _ - - --_ - __- -

75 P-50, 51, Mechanical Penetration Test 26 NA 55 NA 52 & 53 76' P-58 Mechanical Penetration Test 38 NA 0 NA 77 P-57 Mechanical Penetration Test 53 NA 45 NA 78 P-69 & 70 MPT (Sump "A" & "B" Drain Lines) 12 NA 39 NA 79 MPT (Fuel Transfer Tube Penetration) 0 NA 0 NA P-13, 27 80 M chanical Penetration Test 0 NA 0 NA 29 P-37, 38 36 40 81 48, 45 chanical Penehadon Test 0 m  % M 44, 46 P-5 & 6 82 ' '

Mechanical Penetration Test 10 NA 26 NA g 5, 55, 54 -

OPS-27 (03-78)

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a Enclosure 2-Sheet No. 11 NOTES: (For "B" & "C" test results) 1

1. Modification E-168, completed April 6, 1978, removed the contain-ment isolation signal from the steam generator blowdown and sample valves; leak testing of these valves is therefore, "No longer re- .

quired under Appendix J." l J

' 2. This leak test is only required during refueling periods following i

Type "A" containment pressure testing.

l

3. C. W. Fay to H. R. Denton letter dated May 2, 1980, committed to
put the containment isolation signals back on the steam generator blowdown and sample valves but not test them per Appendix J.
4. Electrical penetrations E58, E20, E22, and E1 were newly installed during Refueling 7 (April - May,1981) . Because of their design, they require a leak test (Type "B") and will be tested regularly henceforth, i

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Enclosure 3 Sheet No. 1 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING 0.6 La AT STANDARD TEMPERATURE AND PRESSURE ORT #30 (1979)

Check valve (2-1713) nitrogen supply line to the reactor coolant drain tank was discovered leaking at 145,000 secm. Upon disassembly, the valve was found to contain a buildup of foreign material. The valve internals were cleaned and the valve was reassembled. The valve was retested and found to leak at 225 sccm. (Licensee Event Report No. 79-003/0lT-0, 04/19/79)

ORT #65 (1979)

The return check valve to containment, from 2R11 and 2R12 was dis-covered leaking at 220,000 scem. Upon disassembly, the valve was found to contain a buildup of foreign material. The valve internals were cleaned and the valve was reassembled. The valve was retested with no measurable leakage noted. (Licensee Event Report No. 79-003/OlT-0, 04/19/79)

ORT #65 (1980)

The return check valve to containment from 2Rll and 2R12 was dis-covered leaking at 191,000 secm. Upon disassembly, the valve was found to contain a buildup of foreign material. The valve internals were cleaned and the valve was reassembled. The valve was retested with no measurable leakage noted. (Licensee Event Report No. 82-004/01T-0) l

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