ML20137F776

Forwards Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Tests for May 1983 - May 1985, Ja Fitzpatrick.... Local Leakage Rate Test Summary Analysis for as-found Containment Condition Also Encl,Per Request

ML20137F776
Person / Time
Site:	FitzPatrick
Issue date:	08/21/1985
From:	Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20137F781	List: ML20137F776 ML20137F793
References
JAFP-85-0675, JAFP-85-675, NUDOCS 8508270080
Download: ML20137F776 (8)

Text

'

JImas A. FitzP: trick Nucliar Pow:r PI:nt PO. Box 41 Lycomeng. New York 13093 315 342.3840 Radford J. Converse

1. > NewYorkPbwer tv Authority August 21, 1985 JAFP 85-0675 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST REPORT JAMES A FITZPATRICK NUCLEAR POWER PLANT DOCKET No. 50-333; OPERATING LICENSE NO DPR-59 The subject summary technical report is submitted in accordance with the requirements of 10 CFR 50 Appendix J paragraph V.B.1.

Also submitted, as requested, is a local leakage rate test summary analysis for the "as found" containment condition during the 1983 and 1985 local leakage rate testing periods.

Gt;4-(L W RADFORD J. CONVERSE RJC:PGS:mac cc:

W. Fernandez D. Lindsey H. Keith W.V. Childs P. Swinburne J. Gray (WPO)

DCC 01

.L 3r i 1

8508270080 850821 PDR ADOCK 05000333 P

PDR

. =.

ATTACHMENT 1

/3 LOCAL LEAKAGE RATE TEST

SUMMARY

ANALYSIS The evaluation of the "as-found" containment leakage conditions requires au analysis of the containment penetrations repaired prior to the May 1985 PCILRT.

A conservative analysis indicates that certain penetrations could potentially impact the "as-found" Type A test results. The details of this analysis are shown on the following pages.

Info rmation for the 1983 and 1985 Local Leakage Rate Tests is also presented.

The following analysis reviews the Local Leakage Rate Test results performed since the February 1982 PCILRT.

This analysis is based on the repairs per-formed on the containment isolation valves and penetrations.

Each penetration is reviewed using the following criteria:

I' 1.

A leakage equivalent to the repair improvement achieved on each valve is calculated.

4 2.

The leakage equivalent is the difference between the "as-found" and the "as-left" LLRT result.

3.

If a repair was not required, a zero leakage equivalent is as-sessed to the valve.

-4.

The Icakage equivalent assessed to a penetration may be reduced due to the safety-related service of the penetration.

Justi-fication for these penetrations is provided.

5.

The net equivalent leakage for the penetration is the lowest of inside or outside valve grouping (e.g., simulates minimum pathway leakage).

6.

The resulting net equivalent leakage is added to the Type A results.

l 7.

If the results of the "as-found" Type A are less than 0.5 percent / day, the test is declared a success.

i 8.

A summary sheet for the outage is included.

l l

i V

2094-1515400-B2 Page 1 of 7

1985 "AS-FOUND" LLRT

SUMMARY

ANALYSIS Penetration No.

Inside Outside Net (SCFD)

Remarks Drywell Stabilizer 270*

(GE-0')

28.0 28.0 X-7B "B" Main Steam Line 0

>1018 0

'X-8 Condensate Drain 826.6 0

0 X-9B Feedwater 0

122.1 0

X-10 Steam to RCIC Turbine 0

26.01 0

X-12 Shutdown Supply to RHR

>1018

>1018 0

See Note 3 X-13A RHR Return 0

0 X-14 RWCU Supply to 61.51 0

0 Recirculation Pumps X-19 Equipment Sump Pump

>1018 0

0 Discharge

-X-21 Service Air

>1018 0

0

(

X-24 Cooling Water Supply 0

0 s

X-25 Drywell-Inerting and

>1018

>1018 See Note 4 CAD and Purge X-71 X-26A Containment Atmos-119.5 119.5 pheric Sampling X-31Ac "A" Recirculation Pump >1018 0

0 Mini-Purge X-31Ad Drywell Inert and 0

0 Purge X-31Bc "B" Recirculation Pump 75.35 0

0 Mini-Purge X-35C TIP Probe 3.17 3.17 X-39A Containment Spray

>101.8 0

See Note 3 X-39B Containment Spray 0

0 See Note 4 X-55B Drywell CAD Inert 0

0 and Purge b) ks 2094-1515400-B2 Page 2 of 7

1985 "AS-FOUND" LLRT

SUMMARY

ANALYSIS (Continued)

Penetration No.

Inside Outside Net (SCFD)

Remarks

(}

X-59 Drywell CAD Inert 101.8 101.8 and Purge X-61 Breathing Air 0

124.49 0

X-66 "A" Drywell Cooler 0

0 Assembly Return X-100B Elect 0.427 0.427 X-104C Elect 1.018 1.018 X-106A Elect 0.948 0.948 X-111B Elect 0.2805 0.2805 X-200A Torus Access 0.1521 0.1521 X-202G Vacuum Breaker 0.210 0.210 X-203A 02 Analyzer Sample 0

0 X-205 Drywell Inert CAD

>1018

>1018 See Note 4 and Purge rs X-211A Containment Spray

>101.8 0

See Note 3

()

X-211B Containment Spra, 57.55 0

See Note 3 X-212 RCIC Turbine Exhaust 0

0 X-214 HPCI Turbine Exhaust 0.25 0

See Note 6 X-220 Drywell CAD Inert and

>1018 0

See Note 7 and Purge X-221 Condensate from RCIC

>101.8 0

See Note 5 Turbine b

r.)

2094-1515400-B2 Page 3 of 7

1985 "AS-FOUND" LLRT

SUMMARY

ANALYSIS (continued)

NOTES:

1.

The resulting net equivalent leakage of

>2291.51 SCFD or

>0.208774 percent / day indicates that the plant allowable leakage rate limit of 0.5 percent / day may have been e::ceeded.

2.

Greater than represents the largest leakage measuring equipment used for the 1985 LLRT program.

3.

The RHR system restores and maintains the coolant inventory in the reactor vessel so that the core is adequately cooled after a LOCA.

The RHR system also provides containment cooling so that condensation of the steam resulting from the blowdown due to the design basis LOCA is ensured.

The RHR system valves, piping, and components L.: been designed as essentially a leaktight system, (seismic, safety-related).

During plant operations periodic inspections are performed. Reference JAFNPP FSAR Section 4.8, RHR system.

4.

Each penetration is tested by pressurizing between valves (e.g., valves in series and/or parallel). No attempt to quantify whether the leakage path is through the inboard or outboard valve (s) is required by the LLRT procedure.

5.

The RCIC system provides adequate core cooling.

The RCIC system valves, piping, and components have been designed as essentially a leaktight system (seismic, safety-related).

During plant operations periodic inspections are performed.

Reference JAFNPP FSAR Section 4.7, RCIC system.

6.

The HPCI system provides adequate core cooling.

Exhaust steam from the HPCI system turbine is discharged to the suppression pool.

The HPCI systera valves, piping, and components have been designed as essentially a leaktight system (seismic, safety-related).

During plant operations periodic inspections are performed.

Reference JAFNPP FSAR Section 6.4.1, HPCI system and Section 6.6, Inspection and Testing.

7.

There are three parallel-paths with two isolation valves per path.

Each path is tested by pressurizing between the valves.

One of the three paths uhibited excessive leakage on the "As-Found" LLRT; however, only the inboard isolation valve was repaired.

O 2094-1515400-B2 Page 4 of 7

~ 1983 "AS-FOUND" LLRT

SUMMARY

ANALYSIS Penetration No.

Inside Outside Net (SCFD)

Remarks J

X-7B "B" Main Steam Line 20.36 914.164 20.36 L

X-7D "D" Main Steam Line

>1018 0

0 X-9A Feedwater

>1018

>1018

>1018 X-9B Feedwater

>1018 31018

>1018 X-11 Steam to HPCI' Turbine 0

>1018 0

r X-12 Shutdown Supply to RHR 0

>1018 0

X-19 Equipment Sump Pump

>1018

>1018

>1018 Discharge F

X-21 Service Air

>1018 0

0 X-22 Instrument Air

>1018 0

0 X-24 Cooling Water Supply

>1018

>1018

. (

X-25 Drywell Inerting and

>1018

>1018-See Note 3 1

, CAD and Purge X-71

.X-26A Containment Atmospheric -

0 0

Sampling i

X-31Ac "A" Recirculation

>1018 Pump Mini Purge

.,>1018

>1018

'X-31Ad Drywell Inert and 0

0 i

.z Purge X-36 CRD Return

~68.5978

>1018 68.5978 I

X-39A Containment Spray 0

0 ISee Note 3

\\

X-39B Containment Spray 0

0 See' Note 3 X-41 Recirculation Loop

>1018 0

0

, Sample X-h2 Standby Liquid Control 0

4.942 0'

X-59 Drysell CAD Inert

>1018

>1018

\\

and Purge X-61 Breathing Air 400.074 112.83 112.83 p\\

2094-1515400-B2 Page 5 of 7 m

1983 "AS-FOUND" LLRT

SUMMARY

ANALYSIS (Continued)

Penetration No.

Inside Outside Net (SCFD)

Remarks

• N X-68 "B" Recirculation Pump 526.0525 0 See Note 4 4

MTR Cooling Return X-205 Dryw 11 Inert CAD and 278.6775 278.6775 See Note 3 l

Purge i

X-212 RCIC Turbine Exhaust

>1018 0

See Note 5 X-214 HPCI Turbine Exhaust

>1018 0

See Note 6 X-220 Drywell CAD

• Inert and

>1018

>1018 See Note 3 Purge X-221 Condensate from RCIC

>1018 0

See Note 5 Turbine t

I 1

r A

t i

r l

l k

l 4

O 2094-1515400-B2 Page 6 of 7

..s 1983 "AS-FOUND" LLRT

SUMMARY

ANALYSIS (continued)

NOTES:

1.

The resulting net equivalent leakage of

>8624.47 SCFD or

>0.785757 percent / day indicates that the plant allowable leakage rate limit of 0.5 percent / day was exceeded.

2.

Greater than 1018 SCFD represents the largest leakage measuring equipment used for the 1983 LLRT program.

3.

Each penetration is tested by pressurizing between valves (e.g., valves in series and/or parallel). No attempt to quantify whether the leakage path is through,the inboard or outboard valve (s) is required by the LLRT procedure.

4.

Emergency Service Water (ESW) from the Recirculation Pump MTR.

5.

The RCIC system provides adequate core cooling.

The RCIC system valves, piping, and components have been designed as essentially a leaktight system, (seismic, safety-related).

During plant operations periodic inspections are performed.

Reference JAFNPP FSAR Section 4.7, RCIC system.

6.

The HPCI system provides adequate core cooling.

Exhaust steam from the O

HPCI system turbius is discharged to the suppression pool.

The HPCI system valves, piping, and components have been designed as essentially a leaktight system, (seismic, safety-related).

During plant operations periodic inspections are performed.

Reference JAFNPP FSAR Section 6.4.1, HPCI system and Section 6.6, Inspection and Testing.

t.*

O