ML19347C734

Unit 1 Reactor Containment Bldg Integrated Leak Rate Test - Oct 1980

ML19347C734
Person / Time
Site:	Prairie Island
Issue date:	10/31/1980
From:	Haugland P NORTHERN STATES POWER CO.
To:
Shared Package
ML19347C733	List: ML19347C732 ML19347C734
References
NUDOCS 8101050267
Download: ML19347C734 (32)

Text

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NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I REACTOR CONTALNMENT BUILDING INTEGRATED LEAK RATE TEST OCTOBER, 1980 1

Prepared By: D.L. Haugland, P.E.

Prairie Island Nuclear Generating Plant e

f M

40

1 m.

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I 1

Reactor Containment Building Integrated Leak Rate Test TABLE OF CONTENTS Page 1.0

SUMMARY

............................................................ 1 2.0 D ES IGN INFO RMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.1 Containment Vessel Design..................................... 1 2.2 ILRT Instrumentation System................................... 1 2.3 ILRT Pressurization System.................................... 2 2.4 Computer System............................................... 2 3.0 P RE TEST CONS ID E RATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.1 ILRT Instrumeitation System................................... 2 3.2 Venting & Draining Criteria................................... 3 3.3 Local Leak Rate Test Program.................................. 4 3.4 Containment Inspection........................................ 5 4.0 CONDUCT OF TYPE A TEST............................................. 5 4.1 Acceptance Criteria for Type A Test........................... 5 4.2 Type A Test Recuced Time Criteria............................. 6 4.3 Acceptance Criteria for Verification Test..................... 8 4.4 ILRT & Verification Test Results and Conclusions.............. 9 .

4.5 Abnormal Conditions During Test............................... 9 5.0 SPECIAL TESTING.................................................... 10 5.1 Shield Building Testing....................................... 10 5.2 Auxiliary Building Testing.................................... 10 5.3 Containment Ventilation Penetration Testing................... 11 5.4 Containment Airlock Volumetric Testing........................ 11

6.0 REFERENCES

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TABLE OF CONTENTS (Cont'd) 1 i

LIST OF FIGURES Page ,

Figure 1 - Containment Atmosphere - ILRT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 i Figure 2 - Containment Atmosphere - Verification Tes t . . . . . . . . . . . . . . . . . . 13 1

Figure 3 - Least Squares Leak Rate - ILRT.............................. 14

, Figure 4 - Least Squares Leak Rate - Verification Test................. 15 j

s

) Appendix A - Type B & C Test Results - 1978 Refueling Outage i Appendix B - Type B & C Test Results - 1979 Refueling Outage Appendix C - Type B & C Test Results - 1980 Refueling Outage Appendix D - Summary Technical Report on Type B & C Tests Failing to Meet Acceptance Criteria Since Last Type A Test i

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1 J 1.

SUMMARY

J The periodic Integrated Leak Rate Test (ILRT) of Prairie Island Unit 1 containment was completed October 9, 1980. The testing program was per-formed in accordance with Technical Specification 4.4.A which, in turn, references requirements of 10CFR 50, Appendix J and ANSI N45.4-1972. Addi-tionally, ANS N274, Draft 3-July, 1979, was used as a guide.

The test was performed at reduced pressure, Pt, equal to 23 psig. The test instrumentation used is as described in Reference 6.1. All instru-mentation was calibrated traceable to National Bureau of Standards just .

prior to the ILRT. As a final verification, a superimposed known leak was induced and a composite leak rate measured.

ANSI-N45.4-1972 permits a reduced time ILRT "if it can be demonstrated I to the satisfaction of those responsible for the acceptance of the con-tainment structure that the leakage rate can be accurately determined during l a shorter test period, the agreed upon shorter period may be used." Prior NRC approval was obtained and a reduced time test was performed. The test, subject tc conditions of Reference 6.3, lasted 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and 20 minutes l with a follow up verification test of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

For a reduced pressure te.st, Ltm as determined during preoperational testing (see Reference 6.1) is 0.11569 we %/ day. The 1980 ILRT on Unit 1 contain- .

ment yielded a least squares curve fit of 0.0435 we %/ day and a correspond-ing 95% upper confidence level of 0.0806 wt %/ day.

I 2.0 DESIGN INFORMATION 2.1 Containment Vessel Design Information The design parameters of the Unit 1 containment vessel have been l described in Reference 6.1. A design change involving re-route of Safety Injection lines necessitated changing penetration location .

in the Shield Building. The re-route was performed according to Prairie Island Design Change 80Y127.

2.2 ILRT Instrumentation System In addition to instrumentation described in Reference 6.1, a back up flow meter was purchased and installed for the verification test:

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Instrument number F1-3 Purchase Order Number M-39525 Manufacturer Fischer & Porter Co.

. Model 10 A 1815 Range 0 - 4.47 SCFM Calibration 0.8 - 4.4 SCFM air @ 85'F

] Accuracy i 1% of Rated Flow 2.3 ILRT Pressurization System The pressurization syctem is as described in Reference 6.1. One

! modification has been added; a six inch gate valve was installed in the pressurization spool piece to enable containment depressur-

. ization into the auxiliary building. This allows air release to atmosphere via the Aux. Building Ventilation System through a con-tinuous radiation monitoring system.

i 2.4 ' Computer System The computer system, except for insertion of current instrument cali-bration correction factors, is as described in Reference 6.1.

3.0 PRE-TEST CONSIDERATIONS 3.1 ILRT Instrumentation All instrumentation utilized during the test was shipped to vendors l with NSP approved Quality Assurance programs. These instruments,

[ all calibrated within six months prior to the test, have calibration certification traceable to the National Bureau of Standards.

Sensor calibration correction factors along with system calibration

. factors were summed and a composite correction factor was entered in the computer program for each instrument.

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The containment fire detection system was modified by temporarily installing 12 photoelectric fire detectors in place of the existing I ionization type. This was done to avoid spurrious fire alarms during pressurization. No fire alarms were received during the duration of the test.

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I Containment pressure was monitored by Control Room personnel by l 1eaving one of the containment pressure signal channels in service.

The remaining five channels were defeated by opening the test jack j switches in the analog protection racks.

1 j 3.2 Venting and Draining Criteria The following criteria was used to determine the ILRT valve lineup:

a. From 10CFR50 Appendix J:

(1) "Those portions of the fluid systems that are part of the reactor cooling pressure boundary and are open directly

• to the containment atmosphere under post-accident conditions

! and become an extension of the boundary of the containment I shall be opened or vented to the containment atmosphere j prior to and during the test.

t I (2) " Portions of closed systems inside containment that penetrate containment and rupture as a result of a loss of ecolant 4 accident shall be vented to the containment atmosphere.

(3) "All vented systems shall be drained of water or other fluids j to the extent necessary to assure exposure of the system containment isolation valves to containment air test pressure

. and to assure they will be subjected to the post-accident '

i differential pressure. , ,

I (4) " Systems that are required to maintain the plant in a safe

! condition during the test shall be operable in their normal mode, and need not be vented.

t l (5) " Systems that are normally filled with water and operating under post-accident conditions, such as the containment heat removal system, need not be vented." .

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b. Other Criteria:

(1) All isolation valves which shut automatically on a safeguards - -

signal, which are shut manually as a part of the post-accident safeguards sequency, or which are normally shut during power operation (except venting lineups) shall be shut during the ILRT.

(2) Lines penetrating containment are to be vented.to the outside atmosphere, if they are normally or potentially vented during i

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power operation or if they could be vented after some phase of the safeguards sequence. Normally closed systems outside of the containment shall also be vented unless they are Seismic Class 1.

c. Pressure vessels inside containment vented to containment atmos-phere during the ILRT:

(1) RCS via Pressurizer vent (2) Reactor Coolant Drain Tank (3) Pressurizer Relief Tank (4) Power Operated Relief Valves Accumulators (2 trains)

(5) No. 11 & 12 SI Accumulators (6) No. 11 & 12 Steam Generator Snubber Accumulators

d. Electrical penetration venting All of the electrical penetrations, including those on the airlocks, were depressurized to 10 t 5 psig prior to the ILRT. Any penetra-tion indicating greater than 15 psig would require investigation.

During the ILRT, none were observed to be greater than 15 psig.

3.3 Local Leak Rate Testing Program The local leak rate test program was performed during each refueling outage as required by 10CFR50, Appendix J and Prairie Isladd Technical ,

Specification 4.4.A. A summary of these results are presented in Appendices A, B & C. The 1980 results reflect the as lef t conditions for the 1980 Unit 1 type A test. Those local leak rate tests failing to meet acceptance criteria are discussed in Appendix D.

The acceptance criteria for type B, C & H tests are as follows:

a. If the total leakage of all local leakage testing exceeds 60% of La , repairs and retests shall be performed to reduce leakage below that value.

b. . Total leakage past isolation valves in systems in the Aux-iliary Building Special Ventilation Zone (ABSVZ) shall be less than 0.1wt%/ day at P a*

c. Total leakage past isolation valves in systems exterior to ,

both the ABSVZ and Shield Building shall be less than 0.01 wt%/ day at P,,

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d. Airlock leakage shall be less than 256 SCCM for door seals and 409 SCCM for inner volume tests.

I 3.4 Containment Inspection 4

A general inspection of the accessible interior and exterior surfaces of the containment and components was performed prior to 3

the ILRT as required by 10CFR50, Appendix J, Section V. There was no evidence found of structural degradation.

Additionally, the inspection revealed no pressurized containers, -

fire hazards or containment wall growth interferences. There were no wet surfaces exposed to containment atmosphere and the general -

cleanliness was very good.

i j The annulus area was also inspected for wall growth interferences; none were found.

4.0 CONDUCT OF ILRT I

• 4.1 Acceptance Criteria of Tvpe A Test _

The measured leak rate, Ltm, at reduced pressure Pt. shall not exceed the maximum allowable leak rate, Lt. as follows:

Le = 0.25 if < 0.7 Lt = 0.25 if ' > 0.7 ,

For an acceptable ILRT, the measured leak rate, Ltm, shall be less than 0.75 Lt.

1 Based upon preoperational test data (reference 6.1):

Les = 0.0087 wt%/ day Lam = 0.0141 wt%/ day Therefore, Ltm 0.0087

= 0.617

• Lam 0.0141 Since 0.617,< 0.7, Lt = 0.25 wt%/ day or Lt = 0.25 we%/ day (0.617) = 0.15423 wt%/ day Then Ltm shall be less than 0.75 (0.15423) = 0.11567 wt%/ day.

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i 4.2 Typs A Tent Reductd Timi Criteria

, ANSI 45.4-1972 allows a reduced time test "if it can be demonstrated to the satisfaction of those responsible for the acceptance of the containment structure that the leakage rate can be accurately deter-mined during a shorter test, the agreed-upon shorter period may be used."

Additionally, the conditions of Reference 6.3 were imposed:

a) "In no case shall the minimun test duration be less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (The 1980 Unit 1 ILRT duration was 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and j 20 minutes). t

. b) "At least 20 sets of data points at approximately equal time f intervals and in no case at intervals greater than one hour (33 sets of data were collected at 20 minute intervals).

c) "The end-of-test calculated leak rate based on total time calculations shall be less than 0.75 La (or Le for reduced pressure test) at the upper 95% confidence limit (the Prairie '

l Island Unit 1 end-of-test calculated leak rate based upon mass plot technique, at the upper 95% confidence level was 0.0806 wt%/ day or 0.52 Lt).

d) "A four hour stabilization period will be required and the contain-i ment atmosphere will be considered stabilized when the change i in weighted average air temperature averaged over an hour does not deviate by more than 0.5*R/ hour from the average race of change of temperature measured from the previous four hours (after a four hour stabilization period, the Prairie Island Unit 1 temperature deviation was 0.279'R/ hour).

e) "The test will not be concluded with an increasing calculated

, leak rate (the Unit 1 containment ILRT was concluded with a decreasing calculated least squares leak rate).

f) "The figure of merit for the instrument system shall never exceed 0.25 La (or 0.25 Lt for the reduced pressure test)

at the start and end of the test."

! NOTE: Lt as determined during Unit 1 preoperational testing was determined to be 0.15425 wt%/ day (see Reference 6.1). Therefore, the figure of merit (FOM) shall be less than 0.25 (0.15425 wt%/ day) =

0.0356wt%/ day.

1 FOM SAMPLE CALCULATIONS Prairie Island Unit 1 Test Parameters:

Beginning End Pt, Containment test pressure = 38.737 psia 38.657 psia T, Containment temperature = 83.992*F 83.056*F Tdp, Containment dew point = 63.215'F 62.565'F ,

t, Test duration 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

• 10 hr, 20 min.

Lt, Maximum allowable leak rate = 0.15425 wt%/ day .

E, Error in sensitivity of sensor c, Error in measurement system, excluding sensor (resolution and repeatability).

e, Error associated with the measurement of change of a given parameter.

• Test duration at the beginning of the test is assumed to be eight hours, the minimum time requirement.

Pressure Error, beginning of test.

Number of sensors = 2 Range = zero - 100 psia ,

Ep = 0.0003% full scale cp = 0.001% full scale ep = + (*N =

(0.000003)(100)12 + [(0.00001)(100)]2 rWo. of Inst. /2 ep = 0.0007382 psi Water vapor Pressure Error, beginning of test .

Number of sensors = 6 Range 30*-80'F dew point Epy = 0.5'F c py =

/[0.25%(50)]2 + [0.25%(50)]2

( _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

(4.2 cont'd)

(f cont'd) c py = 0.1768'F

• pv = /(Epy)4 + (c,,,) 2 ,

/(0.5)2 + (0.18)2

/No. of Inst. [f epy = 0.217'F dew point from steam tables at a dew point of 63.215 1 0.217'F, e

py

= 0.002728 psi Temperature Error, beginning of test Number of sensors = 24 Et = 0 et = 0.02*F et =  !(Et)2 + (et)2 ,

/ 0.02

/No. of Inst 6 et = 0.00408 *R FOM = 1 400 2

+

2 pv 2 ,2 1/2 g

For beginning of test conditions:

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2 0.00408 2' 1/2 2400 2(0.0007382) +

OM = 1

• 2(U.00221T 8 ,

\ 38.737 / \38.737 / 459.69+83.992 .

FOM = 1 0.02505 wt%/ day

. For end of test conditions:

- FOM = 0.01939 wt%/ day 4.3 Acceptance Criteria for Verification Test The verification test results are acceptable if the composite leak, L eis equal to the measured leak rate, Ltm, plus the induced leak rate, Lo, within .25 Lt, or:

Le= Lem + Lo 1 0.25 Lt

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4.4 ILRT & Verification Test Results and Conclusions Data was collected at 20 minute intervals and entered into i the computer. The least squares leak rate, Ltm, at the final 4^

data point af ter 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and 20 minutes of data collection l vas 0.0435 wt%/ day with a corresponding upper 95 percent confi-dance level of 0.0806 wt%/ day (see Figure 3). Ltm was 0.24 Lt or 37.6 percent of maximum allowable. 0.75 Lt. I l

t

The upper 95 percent confidence level of 0.0806 wt%/ day was i "

! 0.52 Lt or 69 percent of maximum allowable, 0.75 Lt. This com-

! plies with item c) of 4.2, ILRT Reduced Time Criteria. l 1 -

j A superimposed leak rate Lo of 1.2 CFM equal to 0.04904 wt%/ day was initiated for the supplemental test. Data points were again

!,. collected at 20 minute intervals (see Figure 4) and, at the final

! data point after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of data collection, the measured composite leak race was 0.0839 wt%/ day with a corresponding upper 95 per-i cent confidence level of 0.1242 wt%/ day.

The measured composite leak rate,eL , equal to Ltm + Lo fell within 0.056 Lt; acceptance band is t 0.25 Lt.

The containment atmosphere conditions remained very stable for the duration of the test (see Figures 14 & 2). The maximum dew point variation was 1.256*F about an average of-62.735'F and .

resulted in a 0.01859 psi vapor correction.

l The containment temperature decreased 0.936*F during the ILRT.

This decrease was very uniform with respect to time indicating that diurnal changes had no apparent affect on containment tem-perature.

During the conduct of the ILRT, the containment pressure decreased .

0.100 psi over 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and 20 minutes.

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. 4.5 Abnormal Conditions During Test z

During heatup checklists following depressurization, it was found that three penetrations were not vented inside contain-ment during the ILRT. The three penetrations were

.1) Penetra--

tion 2, Nitrogen supply to Pressurizer Relief Tank, 2)-Penatra-  ;

tion 11, Letdown, and 3) Penetration 45, Reactor Makeup Water to the Pressurizer Relief Tank.

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From the 1980 Local Leak Rate Results, Penetrations 2 and 11 were left with zero leakage rate prior to the ILRT, ie., at least one valve in the penetration had zero leakage. Therefore, had these penetrations been vented, it would have had zero contribu-tion to the overall leak rate.

Penetration 45 would have leaked approximately 0.2 sec/ min. This converts to 0.000003134 wt%/ day and should be added to the overall leak rate of 0.0435 wt%/ day. However, this added leakage rate is insignificant and can be dropped from the calculations. It should be noted that these calculations are based on P, of 46 psig.

The apparent reason for this oversight was personnel misunderstanding procedure venting requirements. Precautions will be made to avoid these misunderstandings in future type A tests.

5.0 SPECIAL TESTING 5.1 Shield Building Testing Section IV, paragraph B of 10CFR50, Appendix J, "Special Testing Requirements" and Technical Specification 4.4.A.7 require. testing of multiple barrier containments. Unit 1 Shield Building is functionally tested at quarterly intervals according to NSP Surveillance Procedure SP 1073. The Shield Building is functionally tested when each redundant train of the special ventilation system is tested to determine if it meets drawdown performance computed for the test condition with 75% of the Shield Building

inleakage specified in Technical Specification Figure TS 4.4.1.-

l None of these quarterly tests on Unit 1 Shield Building has l

I failed to meet acceptance criteria due to Shield Building degrada-tion.

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5.2 Auxiliary Building Testing Technical Specification 4.4.A.7 requires retesting of the j' Auxiliary Building Special Ventilation Zone (ABSVZ) . . Leak

[ tightness of the ABSVZ is verified at quarterly intervals when each redundant train is run to determine if:it can produce an acceptable vacuum in the zone within six minutes with.an opening in the boundary of-at least ten square feet.

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None of these tests have failed to meet the acceptance criteria due to zone boundary degradation.

i 5.3 Containment Ventilation Penetrations Testing i Penetrations 25A & 3. Containment Purge Exhaust & Supply and j Penetrations 423 & 43A, Containment In-Service Purge Supply

& Exhaust, were tested between refuelings as indicated as a j corrective action in Reportable Occurrence 75-45. A preven-tive maintenance program requiring increased seat replacement frequency has resulted in no unacceptable tests on Unic 1 con-tainment ventilation penetrations.

5.4 containment Airlock Volumetric Testing The Unit 1 Personnel and maintenance airlocks are tested at

, Pa at six month intervals according to Technical Specification 4.4.A.2. All of these tests were found acceptable with the exception of the test performsd on 4-29-80. A summary is con-l tained in Appendix D.

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6.0 REFERENCES

6.1 Unit 41 Reactor Containment Building Integrated Leak Rate Test _,

July, 1973.

Transmitted by letter dated October 4, 1973, from Mr. L.0. Mayer, NSP to Mr. J.F. O' Leary, Directorate of Licensing. USAEC.

6.2 Supplement No. 1 to Unit 1 Reactor Containment Building Integrated

! Leak Rate Test - July, 1973.

6.3 Monticello Nuclear Generating Plant Inspection Report No.

50-263/79-18, Item 7. .

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APPENDIX A Type B and C Test Results - 1978 Refueling Outage Each penetration is tested according to Surveillance Procedure 1072 and Technical Specification Table 4.4-1. Type H tests are normally performed using air, thus no water / air conversion factor is used. In cases where water is used for the type H test, a water / air conversion ratio of 1.0/68.55 is used.

Pen. Test As Left No. Penetration Type Inside Outside Max.

1 Pressure Relief Tank C -

0 0 Sample to GA 4 Primary Vent Header C -

0 0 5 ' Reactor Coolant Drain C -

0 0 Tank Pump Discharge 11 Letdown Line C 0 0 0 12 Charging Line H 0 950.7 950.7 13A No. 11 RCP Seal Water H 0 0 0 Supply 13B No. 12 RCP Seal Water H 1370 275 1350 Supply 14 RCP Seal Water Return H 0 0 0 -

15 Pressurizer Stm Sample C 0 42 42 16 Pressurizer Liquid Smpl C 65 0 65 i

17 Loop B Hot Leg Sample C 3050[0] 0 0 18 Fuel Transfer Tube B 0 0 0

- 19 Service Air B 0 0 0 21 Reactor Coolant Drain C 0 0 0 Tank Gas to GA 22 Cntmt Air Sample In C 0 0 0 23 Cntmt Air Sample Out C 0 0 0 A-1 g 7 -yq-e- -

-9ew- -r-w yy --- . r

-m__m__7 y--,yyy.g- -g--,,y_.g.,7,r-Cs -rFe'<P--%-g-w-f "-- 9 e- # "*-- = W'-

ABSVZ PENETRATIONS Measured Leakage-SCCM Pen. Test As Le f t No. Penetration Type In_ side Outside Max.

25A Catst Purge Exhaust C - - 85,941[270](Note 1) 25B Catmt Purge Supply C - -

745(Note 1) 26 Cntat Sump "A" Disch C -

0 0 27 ILRT Pressure B 0 0 0 C-1 Instrument .

27 ILRT Pressure B 0 0 0 C-1 Instrument -

28A Cold Leg Safety H -

68.5 68.5 Injection 28B Hot Leg Safety H -

0 0 Inj ection 29A Internal Containment H -

0 0 Spray 29B Internal Containment H -

0 0 Spray 30A Containment Sump B H -

47.5 47.5 Suction Line 30B Containment Sump B H -

14.5 14.5 -

Suction Line 35 Safety Injection & H - -

- (Note 2)

Accumulator Test Line 42B In Service Purge C - -

150 (Note 1)

Supply 42C Containment Heating B 1100[0] 108[0] O Steam .

42F Containment Heating B 4450[0] 0 0 Condensate -

42F Containment Heating B 0 0 0 Condensatet 43A In Service Purge C - -

0 (Note 1)

Exhaust 44 ILRT Pressurization B 0 0 0 45 Reactor Make Up to C 0 74 74 Pressurizer Relief Tank A-2

ABS 7Z PENETRATIONS Measured Leakage-SCCM Pen. Test As Left No. Penetration Type Inside Outside Max.

48 Low Head Safety H 0 0 0 Injection 49B Demin Water B 0 0 0 51 Fire Protection B 0 0 0 l

EXTERIOR PENETRATIONS Pen. Test As Left No. Penetration Type Inside Outside Max.

2 Pressurizer Relief C 0 0 0 Tank Ny Supply 20 Instrument Air C 7370[683] 5530[465] 683 31 N t Accumulator C 0 0 0 2

42A Post LOCA Hydrogen C 0 0 0 Control Air Supply -

42A Post LOCA Hydrogen C 0 0 0 to GA 50 Post LOCA Hydrogen C 0 0 0 Control Air Supply 50 Post LOCA Hydrogen C 0 0 0 to GA i

. ANNULUS PENEIRATIONS 41A Containment Vacu,3 C 0 360 360 (Note 1)

Breaker 41B Containment Vacuum C 0 124 124 (Note 1)

Breaker 42A Post LOCA Hydrogen C 0 0 0 Air Vent 50 Post LOCA Hydrogen C 0 0 0 Air Vent A-3

' - - - - - - & r - - + eq r -- --up- w w-- - - * -

9 --

- en --

9 e -- -r --i*-- v -

__.____m .. _ _ __ __ - -.

4 ANNULUS PENETRATIONS I Pen. Test As Left No. Penetration Type Inside Outside Max.

6A #11 Steam Line Bellows C -

0 0 6B #12 Steam Line Bellows B -

0 0 i 7A #11 Feedwater Line B -

0 0

Bellows .

t i 73 #12 Feedwater Line B -

0 0 .

Bellows l 8A #11 3 team Generator B -

0 0 -

Blowlown Bellows 1

8B #12 Steam Generator 3 -

0 0

, Blowdown Bellows 9 Residual Heat Out B -

0 0 2

Bellows 10 Residual Heat in l Bellows B -

0 0 11 Letdown Line Bellows B -

115 115 l

18 Fuel Transfer Tube B -

Bellows Equipment Hatch 3 220(225] 225 .

i l Notes: 1) Maximum leakage is the total leakage measured when air is applied to inner space between valves.

2) Penetration 35 is tested in conjunction with penetration 28A & 28B.

~

3) Reference Appendix D for repair summary.

4) Numbers contained in brackets [] are leakage valves measured ,

after repair or hatch replacement.

l l

i A-4 l

APPENDIX B Type B and C Test Results - 1979 Refueling Outage Each penetration is tested according to Surveillance Procedure 1072 and Technical Specification Table 4.4-1. Type H tests are normally performed using air, thus no water / air conversion factor is used. In cases where water is used for the type H test, a water / air conversion ratio of 1.0/68.55 is used.

Pen. Test As Left No. Penetration Type Inside Outside Max.

1 Pressure Relief Tank C -

0 0 Sample to GA 4 Primary Vent Header C -

0 0 5 Reactor Coolant Drain C -

1.0 1.0 Tank Pump Discharge 11 Letdown Line C 0 0 0 12 Charging Line H 1.1 650 650 13A No. 11 RCP Seal Water H 0.4 1.6 1.6 Supply 13B No. 12 RCP Seal Water H 240 , 0.6 240 Supply 14 RCP Seal Water Return H 0 0 0 15 Pressurizer Sem Sample C 0 120 120 16 Pressurizer Liquid Smpl C 160 0 160 17 Loop B Hot Leg Sample C 0.5 0 0.5 18 Fuel Transfer Tube B 32[0] 7 7 19 Service Air B 6.8 0 6.8 21 Reactor Coolant Drain C 0 0 0 Tank Gas to GA 22 Cntat Air Sample In C 0 0 0 23 Cntmt Air Sample Out C 0 0 0 B-1

4 ABSVZ PENETRATIONS Measured Leakage-SCCM Pen. Test As Left No. Penetration Tvpe Inside Outside Max.

25A Catst Purge Exhaust C - -

46 (Note 1) 25B Cntat Purge Supply C - -

29 (Note 1) 26 Cntat Sump "A" Disch C -

0 0 27 ILRT Pressure B 0 0 0 C-1 Instrument 27 ILRT Pressure B 0 0 0 C-1 Instrument .

28A Cold Leg Safety H -

0 0 Inj ection 28B Hot Leg Safety H -

40.8 40.8 Inj ection 29A Internal Containment H -

34.4 34.4 Spray 29B Internal Containment H -

723.8 723.8 Spray 30A Containment Sump B H -

110 110 Suction Line 30B Containment Sump B H - 0 0 .

Suetien Line 35 Safety Injection & H - -

- (Note 2)

Accumulator Test Line 42B In Service Purge C - -

228 (Note 1)

Supply 42C Containment Heating B 5.5 5.5 Steam .

42F Containment Heating B 0 0 Condensate -

42F Containment Heating B 0.1 0.1 Condensater 43A In Service Purge C - - 222 (Note,1)

Exhaust 44 ILRT Pressurization B 5.3 0 5.3 45 Reactor Make Up to C 3250 0.7 3250 Pressurizer Relief Tank B-2

--y e -,gw--r -yi5 -- g-. .

.e e y , e->- t, . - .n4+

ABSVZ PENETRATIONS Measured Leakage-SCCM Pen. Test As Left No. Penetration Type Inside Outside Max.

48 Low Head Safety H 120 -

120 Injection 49B Demin Water B 0 0 0 51 Fire Protection B 0 12 12 i

EXTERIOR PENETRATIONS Pen. Test As Left No. Penetration Type Inside Outside Max.

2 Pressurizer, Relief C 0 54[8] 8 Tank Ny Supply 20 Instrument Air C 378 255 378 31 N to Accumulator C -

155 155 2

42A Post LOCA Hydrogen C 2.0 6.2 6.2 Control Air Supply 42A Post LOCA Hydrogen C 0 0 0 to GA 50 Post LOCA Hydrogen C 7.5 8.0 8.0 Control Air Supply

. 50 Post LOCA Hydrogen C 0 0 0 to GA 4

ANNULUS PENETRATIONS 41A Containment Vacuum C 3.4 242 242 (Note 1)

Breaker 41B Containment Vacuum C 6.5 260 260 (Note 1)

Breaker 42A Post LOCA Hydrogen C 0 0 0 Air Vent 50 Post LOCA Hydrogen C 0 0 0 Air Vent .

ANNULUS PENETRt.TIONS Pen. Test As Left No. Penetration Type Inside Outside Max.

6A #11 Steam Line Bellows C -

5 5 6B #12 Steam Line Bellows B -

0 0 7A #11 Feedwater Line B -

5 5 Bellows 73 #12 Feedwater Line B -

0 0 Bellows 8A #11 Steam Generator B - 8.8 8.8 ,

Blowdown Bellows 8B #12 Steam Generator 3 -

0 0 Blowdown Bellows 9 Residual Heat Out B -

8.1 8.1 Bellows 10 Residual Heat in -

12.4 12.4 Bellows B 11 Letdown Line Bellows B -

121 121 18 Fuel Transfer Tube B -

2 2 Bellows Equipment Hatch B 15 -

15 .

Notes: 1) Maximum leakage is the total leakage measured when air is applied to inner space between valves.

2) Penetration 35 is tested in conjunction with penetration 28A & 28B.

3) Reference Appendix D for repair summary. -

4) Numbers contained in brackets () are leakage valves measured -

after repair or hatch replacement.

B-4

APPENDIX C Type B and C Test Results - 1980 Refueling Outage Each penetration is tested according to Surveillance Procedure 1072 and Technical Specification Table 4.4-1. Type H tests are normally performed using air, thus no water / air conversion facior is used. In cases where water is used for the type H test, a water / air conversion ratio of 1.0/68.55 is used.

Pen. Test As Left No. Penetration h Inside Outside Max.

1 Pressure Relief Tank C -

0.8 0.8 Sample to GA 4 Primary Vent Header C - 0 0 5 Reactor Coolant Drain C - 0 0 Tank Pump Discharge 11 Letdown Line C 0 0 C 12 Charging Line H 0.4 900 900 13A No. 11 RCP Seal Water H 0 150 150 Supply 13B No. 12 RCP Seal Water H 1325(900] 300 900 Supply 14 RCP Seal Water Return H 0 205 205 -

15 Pressurizer Sem Sample C 19.8 0 19.8 16 Pressurizer Liquid Smp1 C 250 1.0 250 17 Loop B Hot Leg Sample C 6.7 1350[655] 655 18 Fuel Transfer Tube B 62 0 62

. 19 Service ir B 0(11.6] 0 11.6 21 Reactor Coolant Drain C 2.8 3.7 3.7 Tank Gas to GA 22 Cntat Air Sample In C 0 0 0 23 Cntat Air Sample Out C 0.3 0.7 0.7 C-1

ABSVZ PENETRATIONS Measured Leakage-SCCM Pen. Test As Lef t No. Penetration Type Inside Outside Max.

25A Cntat Purge Exhaust C - -

1150(3] (Note 1) 25B Catst Purge Supply C - -

1750(40] (Note 1) 26 Cntat Sump "A" Disch C -

0 0 27 ILRT Pressure B 0 2.0[0] 0 C-1 Instrument .

27 ILRT Pressure B 0 4.8[0] O C-1 Instrument

• 28A Cold Leg Safety H -

7840(195] 195 Injection 28B Hot Leg Safety H -

87(1.2] 1.2 Injection 29A Internal Containment H - 0 0 Spray 29B Internal Containment H -

105 105 Spray 30A Containment Sump B H -

2700 2700 Suction Line 30B Containment Sump B H -

1250 1250 Suction Line l

35 Safety Injection & H - -

- (Note 2)

Accumulator Test Line 423 In Service Purge C - -

450 (Note 1)

Supply l

42C Containment Heating B 0

Steam +

42F Containment Heating B - - 0 l '

Condensate 42F Containment Heating B - - 0 Condensatee l

43A In Service Purge C - -

- (Note 1)

Exhaust 44 ILRT Pressurization B 0 0 0 45 Reactor Make Up to C 3700(900] 0.2 900 Pressurizer Relief Tank l

C-2

ABSVZ PENETRATIONS Measured Leakage-SCCM Pen. Test As Left No. Penetration Type Inside Outside Max.

48 Low Head Safety H 1.5 - 1.5 Inj ection 49B Demin Water B 0.4 0 0.4 51 Pfre Protection B C 0 0 EXTERIOR PENETRATIONS Pen. Test As Left No. Penetration Type Inside Outside Max.

2 Pressurizer Relief C 0 0.7 0.7 Tank N SUPPly 2

20 Instrument Air C 350 235 350 31 N t Accumulator C -

0 0 2

42A Post LOCA Hydrogen C 1.0 6.0 6.0 ,

Control Air Supply 42A Post LOCA Hydrogen C 0 0 0 to CA 50 Post LOCA Hydrogen C 1.3 0 1.3 Control Air Supply 50 Post LOCA Hydrogen C 0 0 0 to CA ANNULUS PENETRATIONS .

41A Containment Vacuum C 2.7 750 75 (Note 1)

Breaker 41B Containment Vacuum C 2.9 255 255 (Note.1)

Breaker 42A Post LOCA Hydrogen C 0 0 0 Air Vent 50 Post LOCA Hydrogen C 0 0 0 Air Vent-C-3

_ _. _ _ _ _ _ _ _ . _ _ .___._.. ._ __m . ._ _ . _ _ _ . . _ . _ _ _ _ _ . . - . __. _ _

i l

ANNULUS PENETRATIONS Pen. Test As IA f t j No. Penetration Type Inside Outside Max.

I

,; 6A #11 Steam Line Bellows C -

o o ,

j  !

6B #12 Steam Line Bellows B -

o o  ;

7A #11 Feedwater Line B -

0 0 Bellows

!~

7B #12 Feedwater Line B -

0 0 ,

Bellows 8A #11 Steam Generator B -

9.5 9.5 .

Blowdown Bellows 4

8B #12 Steam Generator 3 -

0 0 Blowdown Bellows j 9 Residual Heat Out B -

0 0 l Bellows ,

10 Residual Heat in j Bellows B -

0 0 11 Letdown Line Bellows B -

12.7 12.7 18 Fuel Transfer Tube B -

0 0

Bellows l

Equipment Hatch B 12.9 -

12.9 ,

i Notes: 1) Maximum leakage is the total leakage measured when air is applied to inner space between valves.

I 2) Penetration 35 is tested in conjunction with penetration 28A & 28B.

i 3) Reference Appendix D for repair summary. *

4) Numbers contained in brackets [] are leakage valves measured ,

after repair or hatch replacement.

l l

l t

l l

c-4

=9 y --,w--. -v+w---- g -yp- ,-- ~ , ---.----w-,-t-,-- - ~. - ,.,.-,,vv- = w -,n- vr 3, e g-w v,-vw- - - -w--- c- e . r y- w,r.,,--,cyr-,4--w-.,- +-4 re-e --+-- v -e---- - --

APPENDIX D

SUMMARY

TECHNICAL REPORT ON TYPE B AND C TESTS FAILING TO MEET ACCEPTANCE CRITERIA SINCE LAST TYPE A TEST A volumetric test of Unit One Contaimnent Maintenance Airlock resulted in a leakage rate of about 600 sec/ min; Technical Specification 4.4.A.5 limits leakage to 409 sec/ min.

Investigation revealed that the leakage was occurring past the inner door gasket seals. The test was aborted and new door gaskets were installed on the inner door.

. A retest resulted in a leakage rate of 8.5 sec/ min.

Since the volumetric test produces a force on the door opposite that of postulated accident, it is unlikely that this leakage rate would have occurred had it been tested from the opposite side.

This event was reported on P-RO-80-15 dated May 13, 1980.

O e

i D-1