ML12233A666

NRC Staff Pre-Filed Hearing Exhibit NRC000152, Indian Point Nuclear Generating Unit 2 - NRC Inspection Report 05000247/2012008, Dated April 19, 2012

ML12233A666
Person / Time
Site:	Indian Point
Issue date:	04/19/2012
From:	Conte R J Engineering Region 1 Branch 1
To:	Ventosa J Entergy Nuclear Operations
SECY RAS
References
RAS 23327, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 IR-12-008
Download: ML12233A666 (15)

See also: IR 05000247/2012008

Text

UNITED STATES NUCLEAR REGULATORY

COTTIM ISSION REGION I 475 ALLENDALE

ROADKING OF PRUSSIA. PENNSYLVANIA

19406.1415

Apri'l L9, 20L2Mr. John Ventosa. Site Vice PresidentEntergy Nuclear

Operations, lnc.Indian Point Energy

Center 450 Broadway, GSBP.O. Box 249

Buchanan, NY 1051 1-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT

2 - NRC INSPECTION

REPORT 05000247t2012008

Dear Mr. Ventosa:On March 8,2012, the U.S. Nuclear Regulatory

Commission (NRC) completed

an inspection

at the lndian Point Nuclear

Generating

Unit 2. The enclosed report documents

the results of the inspection, which were discussed on

March 8,2012, with Mr. John Curry and members

of your staff.This inspection

was an examination of

license renewal activities

under Temporary

Instruction (Tl) 2516/001, Review of License RenewalActivities.

The inspection

was directed toward thoseactivities and

facilities accessible during

the refueling

outage. The inspection also reviewed thecompletion of

commitments made during

the renewed license application

process andcompliance with the Commission's

rules and regulations

and the conditions

of your operating license. Within these areas, the inspection

involved examination

of selected procedures

and representative

records, observations

of activities, and interviews

with personnel.

On the basis of the samples selected

for review, there

were no findings of significance

identified

during this inspection.

The NRC staff identified

two instances of commitments

which could notbe considered completed at this

time. Given the scheduled completion

of September

28,2013, for these commitments, we will incorporate

a followup review as a

part of our planned team inspection

in this area prior to September 28,2013, to

verify completion along with thecompletion of other commitments.

In accordance

with 10 CFR 2.390 of the NRC's "Rules

of Practice," a copy of

this letter and

its enclosure

will be available electronically

for public inspection

in the NRC Public Document

Room or from the Publicly Available

Records (PARS) component

of NRC's document system Agencywide

Document Access and Management System (ADAMS). ADAMS is accessible

from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic

Reading Room).Sincerelv, ,e"/^JyffiRichard J. Conte, Chief Engineering

Branchl Division of Reactor Safety

Mr. John Ventosa Site Vice President Entergy Nuclear Operations, Inc.Indian Point Energy Center 450 Broadway, GSB Buchanan, NY 1051 1-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING

UNIT 2 - NRC INSPECTION

REPORT 0500024712012008

Dear Mr. Ventosa: On March 8,2012, the U.S. Nuclear Regulatory

Commission (NRC) completed

an inspection

at the Indian Point Nuclear Generating

Unit 2. The enclosed report documents

the results of the inspection, which were discussed

on March 8, 2012, with Mr. John Curry and members of your staff.This inspection

was an examination

of license renewal activities

under Temporary

Instruction (Tl) 2516/001, Review of License RenewalActivities.

The inspection

was directed toward those activities

and facilities

accessible

during the refueling

outage. The inspection

also reviewed the completion

of commitments

made during the renewed license application

process and compliance

with the Commission's

rules and regulations

and the conditions

of your operating license. Within these areas, the inspection

involved examination

of selected procedures

and representative

records, observations

of activities, and interviews

with personnel.

On the basis of the samples selected for review, there were no findings of significance

identified

during this inspection.

The NRC staff identified

two instances

of commitments

which could not be considered

completed

at this time. Given the scheduled

completion

of September

28,2013, for these commitments, we will incorporale

a followup review as a part of our planned team inspection

in this area prior to September

28,2013, to verify completion

along with the completion

of other commitments.

In accordance

with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure

will be available

electronically

for public inspection

in the NRC Public Document Room or from the Publicly Available

Records (PARS) component

of NRC's document system Agencyride

Document Access and Management

System (ADAMS). ADAMS is accessible

from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic

Reading Room).Sincerely,/RN Richard J. Conte, Chief Engineering

Branchl Division of Reactor Safety DOCUMENT NAME: G:\DRS\Engineering

Branch 1\-- Meyer\lndian

Pt 71003\lR 2012-08 lP Rev 2.docx 104315 ADAMS ACCESSION

NUMBER: ML12 g suNst Review fl Non-Sensitive

n Sensitive V!Publicly Available Non-Publicly

Available OFFICE RI/DRS RI/DRP RI/DRS NAME GMeyer/RJC

for MGray RConte DATE 4t11t12 4t19t12 4t19t12 RECORD COPY

J. Ventosa Docket No. 50-247 License No. DPR-26 Enclosure:

NRC f nspection

Report 05000247 12012008 cc w/enclosure:

Distribution

via ListServ

J. Ventosa 3 Distribution

Mencl: (via E-mail)W. Dean, RA D. Lew. DRA J. Trapp, DRP C. Miller, DRS (R{ORAMATL

RESOURCE)(RIORAMAlL

RESOURCE)(RIDRPMAIL

Resource)(RI DRSMArL RESOURCE)J. Clifford, DRP (RlDRPMail

Resource)P. Wilson, DRS (R,lDRSMAIL

RESOURCE)M. McCoppin, Rl OEDO M. Gray, DRP B. Bickett, DRP S. McCarver, DRP M. Jennerich, DRP M. Catts, SRI A. Ayegbusi, Rl D. Hochmuth, AA RidsNrrPMlndianPoint

Resource RidsNrrDorlLpll

-1 Resource ROPreport

Resource D. Bearde, DRS T. Lupold, DRS R. Conte, DRS G. Meyer, DRS

U.S. NUCLEAR REGULATORY

COMMISSION

REGION I Docket: 50-247 License: DPR-26 Report: 0500024712012008

Licensee:

Entergy Nuclear Northeast (Entergy)Facility:

lndian Point Nuclear Generating

Unit 2 Location:

Buchanan, NY Dates: March 5-8,2012 Inspectors:

G. Meyer, Senior Reactor Inspector, Division of Reactor Safety M. Modes, Senior Reactor Inspector, Division of Reactor Safety Accompanied

By: K, Green, Senior Project Manager, Division of License Renewal W. Holston, Senior Technical

Reviewer, Division of License Renewal Approved By: Richard J. Conte, Chief Engineering

Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS lR 0500024712012008i

0310512012 - 0310812012;

Indian Point Nuclear Generating

Unit 2;Review of License Renewal Activities.

The report covers a one week inspection

of the implementation

of license renewal activities

during the Indian Point Unit 2 refueling

outage, lt was conducted

by two region based engineering

inspectors

under Temporary

Instruction

2516/001.

No findings were identified.

The inspectors

determined

that Entergy actions on four commitments (Commitments

28,29,34, and 36) were complete and met regulatory

expectations

as reflected

in the staff's safety evaluation

report. lnspection

of two commitments (Commitments

2 and 3) concluded

that additional

inspection

was needed.Enclosure

4.a.4042 Report Details oTHER ACTTVTTTES (OA)Other - License Renewal Activities (Tl 2516/001 )lnspection

Scope This inspection

was performed

by two NRC Region I based inspectors

to evaluate the license renewal activities

at the Indian Point Nuclear Generating

Unit 2 in accordance

with Temporary

Instruction (Tl) 25161001.

As noted in this Tl: "This procedure

was written to allow for timely verification

by NRC inspectors

that the applicant

has made sufficient

progress in implementing

its license renewal commitments

before entering its post-4O-year

license period and to allow documentation

of these inspection

activities

while the operating

license is being considered

for renewal." This phase of the inspection

is "to be completed

during the outage preceding

the beginning

of the period of extended operations

for the purpose of observing

or verifying

commitments

of tests or other activities

that require containment

entries or access to rooms that would normally be posted as a high-radiation

area or higher when the reactor is operating." The inspectors

performed

in-plant observations

of license renewal related activities

and sampled Entergy actions on commitments.

The bases for the review was the NRC staff's safety evaluation

report (NUREG'1930)

and related licensee letters associated

with licensee renewal regulatory

commitments, including

Letter NL-11-101, dated August 22,2011.Findinss and Observations

No findings were identified.

ln-Plant Observations

The inspectors

observed ongoing activities

and inspected

the general condition

of structures, systems, and components

within the scope of license renewal. The inspectors

performed

reviews in the following

areas, as related to commitments

and aging management

programs (AMPs):. Turbine Building - Flow Accelerated

Corrosion

AMP. Turbine Building - One-Time lnspection

Program (Commitment

19). Station Blackout (SBO)/Appendix

R Diesel Generator (Commitment

34)The inspectors

determined

the general conditions

to be satisfactory

and the Entergy activities

to be in accordance

with facility programs and procedures.

b.b.1 Enclosure

2 b.2 Commitments - Review Complete Commitment

28 - Water Chemistrv

Control - Closed Coolino Water Prooram Commitment

28 provides that Entergy will "Enhance the Water Chemistry

Control-Closed Cooling Water Program to maintain water chemistry

of the lP2 SBO/Appendix

R diesel generator

cooling system per EPRI guidelines" and will "Enhance the Water Chemistry

Control- Closed Cooling Water Program to maintain the lP2 and lP3 security generator

and fire protection

diesel cooling water pH and glycolwithin

limits specified

by EPRI guidelines" by September

28, 2013. The license renewal team inspection (Report 0500024712008006

dated August 1, 2008) had noted that some parameters

were not monitored

for some diesels in existing procedures.

The inspectors

reviewed the implementation

plan, EPRI guidelines, revised chemistry sampling procedures

and acceptance

criteria, and chemistry

results for the SBO/App. R, fire protection, and security diesels.The inspectors

concluded

that Commitment

28 had been completed.

Commitment

29 - Sulfates in the Refuelino

Water Storaqe Tank (RWST)Commitment

29 provides that Entergy will "Enhance the Water Chemistry

Control -Primary and Secondary

Program for lP2 to test sulfates monthly in the RWST with a limit of <150 ppb" by September

28,2013.The inspectors

reviewed the implementation

plan, RWST chemistry

sampling procedure, and RWST chemistry

results lor 2010 and 2011.The inspectors

concluded

that Commitment

29 had been completed.

Commitment

34 - Station Blackout (SBO)/Appendix

R Diesel Generator Commitment

34 provides that "lP2 SBO/Appendix

R diesel generator

will be installed and operational

by April 30, 2008." lnspection

Report 0500024712008006, dated August 1, 2008, documented

the license renewal team inspection

of the lP2 SBO/App. R diesel generator

following

its installation

and operationaltesting.

Inspection

Report 0500024712008003, dated August 13, 2008, documented

the inspection

of the post-modification

testing of this diesel generator.

The inspectors

concluded

that Commitment

34 had previously

been completed.

Commitment

36 - Refuelino

Cavitv Concrete Commitment

36 provides that Entergy will "Perform a one-time inspection

and evaluation

of a sample of potentially

affected lP2 refueling

cavity concrete prior to the period of extended operation.

The sample will be obtained by core boring the refueling

cavity wall in an area that is susceptible

to exposure to borated water leakage. The inspection

will Enclosure

3 include an assessment

of embedded reinforcing

steel. A sample of leakage fluid will be analyzed to determine

the composition

of the fluid." These actions are scheduled

for completion

by September

28,2013. Commitment

36 also addresses

core bores and leakage fluid analysis in the first ten years of the period of extended operation.

During refueling

operations

at Unit 2, leakage through the reactor refuel cavity liner plate had caused the cavity flood-up water to migrate through the concrete walls of the cavity.NRC was concerned

the borated water flowing through the concrete and past the reinforcement

bars could cause an indeterminate

degradation.

The inspectors

reviewed the test results of concrete cores removed from the lP2 refuel structure

in Engineering

Report No. lP-RPT-11-00002, Assessment

of Concrete Aging From Selected Indian Point Structures, Rev 0, January 10,2011. The originally

specified

concrete strength, per United Engineers

and Constructors

Drawing 9321-01-5-

1, Specification

for Design, Inspection

and Tests of Concrete, High Strength Bolts, Compaction

of Fill and Rock Bearing, was 3000 psi at 28 days. Entergy took seven core samples from the Unit 2 fuel pool structure;

the compression

results were 7,213 psi, 3,202 psi, 5,890 psi,6,294

psi, 8,307 psi, 5,497 psi, and 6,448 psi' Using the guidance of American Concrete Institute, ACI214.4R, the calculated

equivalent

in-structure

compressive

strength was 4,341 psi.Reinforcing

bars were part of three of the concrete samples taken from the Unit 2 fuel pool structure.

The above referenced

report noted there was no visible degradation

of the reinforcing

bars. This observation

compared favorably

with concrete core samples taken from the Unit 1 fuel pool structure, which was wetted by a boric acid solution equivalent

to Unit 2 for approximately

30 years.Nine samples were taken from the core bores for further interrogation

by Petrography

with a Stereo-microscope.

These samples were examined in general accordance

with ASTM C-856-04, Standard Practice for Petrographic

Examination

of Hardened Concrete.

There were observations

of concrete paste discoloration

and cracks noted in the Petrographic

samples taken from the core samples extracted

from the west and south walls of the fuel pool. The discoloration

was attributed

to the differences

in the hydration

of the paste most likely due to exposure to the water through the cracks, and the report concluded

the examined material was of "relatively

good quality." The inspectors

concluded

that Commitment

36 is on track to be completed, b.3 Commitments - Needino Additional

NRC Review Commitment

2 - Boltino Inteqritv

Proqram Commitment

2 provides that Entergy will "Enhance the Bolting lntegrity

Program tor lP2 and lP3 to clarify that actual yield strength is used in selecting

materials

for low susceptibility

to SCC and clarify that prohibition

on use of lubricants

containing

MoSz for bolting" by September

28, 2013. Commitment

2 also states that "The Bolting Integrity Program manages loss of preload and loss of material for all external bolting," Enclosure

4 The inspectors

reviewed the implementation

plan and the revised mechanicalfastener

procedure, which had specific instructions

on bolting regarding

the use of actual yield strength and the prohibition

against molybdenum

disulfide

as a lubricant.

Nonetheless, there was no planned action regarding

the second commitment

statement

regarding

loss of preload and loss of material, despite Commitment

2 being considered

completed

by Entergy. Entergy entered this concern into the license renewal corrective

action system as item LO-LAR-2011-00174, CA-66.The inspectors

concluded

that the specific procedural

instructions

of Commitment

2 had been completed, but that review of any action on the general statement

needed to be reviewed during a subsequent

NRC inspection.

Commitment

3 - Buried Pipinq and Tanks lnspection

Proqram Commitment

3 provides that Entergy will "lmplement

the Buried Piping and Tanks Inspection

Program for lP2 land lP3] as described

in LRA Section 8.1.6" and perform the following:

o "lnclude in the Buried Piping and Tanks lnspection

Program described

in LRA Section 8.1.6 a risk assessment

of the in-scope buried piping and tanks that includes consideration

of the impacts of buried piping or tank leakage and of conditions

affecting

the risk for corrosion.". "Classify

pipe segments and tanks as having a high, medium or low impact of leakage based on the safety class, the hazard posed by fluid contained

in the piping and the impact of leakage on reliable plant operation.". "Determine

corrosion

risk through consideration

of piping or tank material, soil resistivity, drainage, the presence of cathodic protection

and the type of coating." o "Establish

inspection

priority and frequency

for periodic inspections

of the in-scope piping and tanks based on the results of the risk assessment." o "Perform inspection

using inspection

techniques

with demonstrated

effectiveness." The inspectors

reviewed the implementation

plan and Entergy fleet, corporate engineering

and site engineering

procedures.

The inspectors

also reviewed a summary report of inspection

results, cathodic protection

records, and area potential

earth current (APEC) survey results.The inspectors

reviewed the risk assessment, classifications

of leakage impacts, and corrosion

risk categorizations

addressed

in the first three bulleted items above, and found the evaluation

approaches

to be sound and generally

credible.

The inspectors

reviewed the inspection

plan based on these evaluations

to be reasonable

and appropriate.

The inspectors

reviewed a sample of inspection

records, which showed that inspections

had involved direct visual inspection, followed by external ultrasonic

test (UT) inspections

in some cases, and were thorough and appropriate.

The inspectors

noted two concerns.

First, site engineering

procedure

SEP-UlP-IPEC

stated that guided wave inspection

was an acceptable

indirect inspection

technique.

Enclosure

5 The inspectors

noted that while guided wave inspection

was a credible method to inform other inspections, it did not meet the "demonstrated

effectiveness" standard and was not suitable for inspection

by itself. There was no evidence that guided wave inspection

had been solely used to accept inspected

piping or tanks, but the procedure

merited clarification

on the use of guided wave inspection.

Second, Entergy fleet procedure EN-DC-343

listed the affected Unit 2 underground

systems in Attachment

9.2, but omitted the river water, circulating

water, and containment

isolation

support systems.There was no immediate

impact on the inspection

plan given that these actions were not in effect without a renewed license. However, Entergy will review this matter and they entered these two concerns into the license renewal corrective

action system as item LO-LAR-201

1 -001 7 4, CA-67 .Given the preliminary

progress on Commitment

3, the inspectors

determined

that additional

inspection

was merited on the clarification

of the use of guided wave inspection, coverage of omitted underground

systems, and subsequently

completed inspections.

b.4 Annual Updates 10 CFR 54.21(b) requires each year following

submittal

of the license renewal application

and at least three months before scheduled

completion

of the NRC review, an amendment

to the renewal application

be submitted

that identifies

any change to the current licensing

basis (CLB) of the facility that materially

affects the contents of the license renewal application, including

the Updated Final Safety Analysis Report (UFSAR) supplement.

The inspectors

selected a sample from annual update submittals

for review.Amendment

8 to the application

transmitted

by a letter (NL-09-060)

dated May 15, 2009.This amendment

was a result of a review of documents

affecting

the current license basis during the period May 1, 2008 through March 1, 2009, since the prior annual update amendment.

The review concluded

that sections of the application

were affected by changes to the current licensing

basis. For example, during this period, the Indian Point 3 Security Dieselwas

replaced, affecting

Section 3.3.2.1.15

and Table 3.3.3-15-lP3 of the application.

This example illustrated

Entergy Nuclear Operations, Inc. compliance

with 10 CFR 54.21(b).Summarv No findings were identified

and general conditions

in the plant areas observed were satisfactory.

The inspectors

determined

that Entergy actions on four commitments (Commitments

28, 29,34, and 36) were complete and met regulatory

expectations

as reflected

in the staff's safety evaluation

report. Inspection

of two commitments (Commitments

2 and 3) concluded

that additional

inspection

was needed. Further NRC inspection

of Unit 2 commitments, including

Commitments

2 and 3, is planned prior to the scheduled

completion

date of September

28,2013.Enclosure

6 4OAO Exit Meetino The inspectors

presented

the inspection

results to Mr. John Curry, License Renewal Project Manager, and other members of the staff on March 8, 2012. The inspectors

confirmed

that no proprietary

materialwas

examined during the inspection.

ATTACHMENT:

SUPPLEMENTAL

INFORMATION

Enclosure

A-1 ATTACHMENT

SUPPLEMENTAL

INFORMATION

KEY POINTS OF CONTACT Licensee Personnel J. Curry, License RenewalTeam

Project Manager N. Azevedo, Supervisor, Supervisor

Engineering

Programs C. Caputo, License RenewalTeam

G. Dahl, Licensing

Engineer R. Drake, System Engineer J. Flagg, License Renewal Team D. Lach, License Renewal Team LIST OF DOCUMENTS

REVIEWED General NUREG-1930, Safety Evaluation

Report Related to the License Renewal of Indian Point Nuclear Generating

Unit Nos. 2 and 3, November 2009 NUREG-1930, Safety Evaluation

Report Related to the License Renewal of Indian Point Nuclear Generating

Unit Nos. 2 and 3, Supplement

1, August 30, 2011 Entergy Letter NL-1 1-101 , Clarification

for Request for Additional

Information (RAl), dated August 22,2011 In-plant Observations

One-Time Inspection

Matrix (draft)One-Time Inspection

Form 169473-01 One-Time lnspection

Form 51 282477 -01 WO 00255920, FAC UT of heater drain piping WO 00255936, FAC UT of reheater drain piping Commitment

2 (Boltinq Inteqritv)

lP-RPT-11-LRD03, Review of the Bolting Integrity

AMP for lmplementation, Rev 0 (draft)O-MS-411, Torquing of Mechanical

Fasteners, Rev 3 Enclosure

A-2 Commitment

3 (Buried Pipinq and Tanks lnspection)

lP-RPT-11-LRD07, Review of the Buried Pipe and Tanks Inspection

AMP for lmplementation, Rev 0 (draft)EN-DC-343, Underground

Piping and Tanks Inspection

and Monitoring

Program, Rev 4 CEP-UPT-0100, Underground

Piping and Tanks lnspection

and Monitoring, Rev 0 SEP-UlP-lPEC, Underground

Components

Inspection

Plan, Rev 0 PCA Engineering

Inc, Cathodic Protection

System Maintenance

Record Sheet, AFW Pump Room Annex - Unit 2, PCA Job No. 30493, 2128112 lP-RPT-11-0045, Indian Point Energy Center APEC Survey, 11117111 IPEC Underground

Piping and Tank Program Completed

Buried Pipe lnspections, 1111112 Thielsch Engineering, Laboratory

Testing Data Sheet, 12112111 Photographs

of Nov/Dec 2011 inspections

of lP2 24" SRW lines 409 (16 pictures dated 11123111)

and 408 (24 pictures dated 11123111)lP2-lJT-11-050, UT Erosion Corrosion

Exam - 24 SRW line 409, 12128111 f P2-UT,11-048, UT Erosion Corrosion

Exam - 24 SRW line 408, 1212811, 2 pictures lnspection

Report, lP3 AFWCond Return to CST (8" line 1080), WO 279578-03, 1219111, 4 pictures lnspection

Report, lP3 CST Supply to AFW Pumps (12" line 1070), WO 279578-03, 1219111, 4 pictureslP3-UT-11-076.

UT E/C Examination

lP3 8" line 1080, 12115111lP3-UT-1 1-077, UT E/C Examination

lP3 12" line 1070, 12115111 Commitment

28 (Water Chemistrv - Closed Coolinq)EPRI TR-107396, Closed Cooling Water Chemistry

Guideline, Rev 1lP-RPT-11-LRD41, Review of the Water Chemistry-

Closed Cooling Water AMP for lmplementation, Rev 0 (draft)}-CY-2510, Closed Cooling Water Chemistry

Specifications

and Frequencies, Rev 13 f P2 SBP/App R diesel quarterly

chemistry

results, March 2008 to January 2012 tP2 Fire pump diesel quarterly

chemistry

results, January 2007 to December 201 1 lP2 Security diesel quarterly

chemistry

results, January 2007 to December 2011 Commitment

29 (RWST Sulfates)IP-RPT-11-LRD42, Review of the Water Chemistry - Primary and Secondary

AMP for lmplementation, Rev 0 (draft)2-CY-2625, General Plant Systems Specifications

and Frequencies, Rev 16 lP2 RWST monthly chemistry

results, January 2010 to February 2012 Commitment

36 (Refuelinq

Cavitv Concrete)ER No. lP-RPT-11-00002, Assessment

of Concrete Aging From Selected lndian Point Structures, Rev 0 United Engineers

and Constructors

Drawing 9321-01-5-1, Specification

for Design, Inspection

and Tests of Concrete, High Strength Bolts, Compaction

of Fill and Rock Bearing ASTM C-856-04, Standard Practice for Petrographic

Examination

of Hardened Concrete Enclosure

A-3 LIST OF ACRONYMS ADAMS Agencyruide

Documents

Access and Management

System AMP Aging Management

Program CLB Current Licensing

Basis EPRI Electric Power Research Institute LRA License RenewalApplication

NRC U. S. Nuclear Regulatory

Commission

RFO Refueling

Outage RWST Refueling

Water Storage Tank SBO Station Blackout Tl Temporary

lnstruction

UFSAR Updated Final Safety Analysis Report UT Ultrasonic

Test Enclosure