ML20071K114

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Proposed Tech Spec Changes Re Local Leakage Tests for Valves IC-VI6,VI8 & NS-VII in Type C Testing Program & Newly Installed Hydrogen Recombiner Valves
ML20071K114
Person / Time
Site: Crane 
Issue date: 04/21/1982
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20071K067 List:
References
NUDOCS 8204270469
Download: ML20071K114 (3)
v • d • e


Text

.

4 detection tests.

Sufficient data and analysis shall be included to show that a stabilized leak rate was attained and to identify all significant required correction factors such as those associated with humidity and barometric pressure, and all significant errors such as those associated with instrumentation sensitivities and data scatter.

This report shall be titled Reactor Containment Building Integrated Leak Rate Test and shall be submitted to the AEC within 3 months of the test.

4.4.1.2 Local Leakage Rate Tests 4.4.1.2.1 Scope of Testing The local leak rate shall be measured for the following components a.

using a type "B" test as defined in 10 CFR 50, Appendix J.

1.

Personnel air lock door gaskets and other seals.

2.

Emergency air lock door gaskets and other seals.

3.

The resilient seals on the equipment hatch and fuel transfer tube blind flanges 4.

Blind flanges on penetration No. 414 (L.R. Pressure Sensing) 5.

Reactor Building Purge valves (AH-V1A, B, C and D) 6.

Blind flanges on both ends of pipe through the following penetrations:

I 6.1 No. 104 (S/G drains) 6.6 No. 241 (Incore Inst. Transfer Tube) 6.2 No. 105 (S/G cleaning) 6.7 No. 415 (L.R. Test Bleed Line) 6.3 No. 106 (S/G cleaning) 6.8 No. 416 (L.R. Test Bleed Line) 6.4 No. 210 (S/G annulus drains)

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6.5 No. 211 (S/G annulus drains) b.

The local leak rate shall be measured for the following isolation valves using a type "C" test as defined in 10 CFR 50, Appendix J.

1.

CA-V1, 2, 3, 13 (Primary Sampling)

CA-V189,192 (reclaimed Water)

CA-V4A, 4B, 5A, 5B (Secondary Sampling) 2.

CF-V2A, 2B, 12A, 12B, 19A, 19B, 20A, 20B (Core Flsod) 3.

CM-V1, 2, 3, 4 (Containment Monitoring) 4.

DH-V64, 69 (Decay Heat) 5.

HP-V1, 6 (Hydrogen Purge) 6.

HR-2A, 2B, 4A, 4B, 22A, 22B, 23A, 23B (Hydrogen Recombiner) 7.

IA-V6, 20 (Instrument Air) 8.'

IC-V2, 3, 4, 6,16,18 (Intermediate Cooling) 4-32 8204.270469

-9.

LR-V1, 4, 5, 6, 10, 49 (Leak Rate Test) 10.

MU-V2A, 2B, 3, 18, 20, 25,.26, 116 (Make up and Purification) 11.

NI-V27 (Nitrogen) 12.

NS-V4, 11, 15, 35 (Nuclear Services Closed Cooling) 13.

RB-V2A, 7 (R.B. Industrial Cooling System) 14.

SA-V2, 3 (Service Air) 15.

SF-V23 (Spent Fuel Cooling) 16.

WDG-V3, 4 (Waste Gas Header) 17.

WDL-V303, 304 (Waste Disposal Liquid) f 18.

WDL-V534, 535 (R.B. Sump Gravity Drains) l 4.4.1.2.2 Conduct of Tests Local leak rate tests shall be perfo med paeumatically at a pressure a.

of not less than P, with the following exception:

The access hatch door seal test sha 1 no mally be perfo med a: 10 psig and the tes: every l

six months specified in 4.4.1.2.5.b shall be perfc =ed a: a pressure not less than P.

3 b.

Acceptable methods of testing are haloger gas detection, pressure-decay, I

pneumatic flow measurement or equivalen:.

c.

The pressure for a valve test shall be applied in the same direction as that when the valve vould be required to perform its safety function unless it can be determined that the direction will provide equivalent or more conserva.:ive results, d.

Valves to be tested shall be closed by no =al operation and without any preliminary exercising or adjustments.

4.4.1.2.3 Acceptance Criteria The combined leakage from all items listed in 4.4.1.2.1 shall not exceed.6 L, (the maximum allowable leakage rate at P )-

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c Tha mini =us test pressure of 27 5 psis for the periodic. int:rgrated 1sakaar rate test is nufficiently high to provide an accurate measurtm:nt of tb2 i

)L leakage rate and it duplicates the pre-operational leakage rate test at the reduced pressure. The specification provides a relationship for relating the measured leakage of air at the reduced pressure to the potential leakage of 55 psis. The minimu= of 2L hours was specified for the integrated leakage rate test to help stabilize conditions and thus i= prove accuracy and to better evaluate data scatter. The frequency of the periodic integrated leakage rate test is heyed to the refueling schedule for the reactor, because these tests can best be performed during refueling' shutdowns.

The specified frequency of periodi integrated leakage rate tests is based on three major considerations.

First is the low probability of leaks in the liner, because of conformance of the complete containment to a 0.10 percent leakage rate at 55 psig during pre-operational testing and the absence of any significant stresses in the liner during reactor operation.

Second is the more frequent testing, at design pressure, of those portions of the containment envelope that are most likely to develop leaks during reactor operation, and the low value (0.06 percent) of leakage that is specified as acceptable from penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that an important part of the structural integrity of the containment is maintained.

More frequent testing of various penetrations is specified as these locations are more susceptible to leakage than the reactor building liner due tc the mechanical closure involved.

The basis for specifying a tetal leakage rate of 0.06 percent frot those penetrations and isolation valves is that more than one-half of the leakage rate vill be from these sources.

d allowable integrate Valve Operatility tests are specified :: assure pre;er :1:sure er cpening ef the reacter building istiatien valves :: previde fer is:1stien er functiening Of Engineered Safety yestures systens.

Talves vil; be strekei

the positien required te Palfill their safe;y function unless it is established that such testing is net practical durin: enerati:n. valves :ha; cannet be full-stroke te sted vill be part-stroke testei during Operation e #

-strche tested during ee :t ner=C re^aeling shutdev.

eriodic surveillance cf the air 1cch interlo:P systers is specified :: assure S

ocntinued cperatility and preclude inr;t: es where :ne er be:b deers are in-When an air 10 k is inoperatie and centainren; advertently left ope r..

integrity is required, local supervisien Of airlee? : eratien is specified.

a'a ren ce (1) FSAR. Section 5 A:eni=en: Sc.

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