IR 05000414/1985017

Insp Rept 50-414/85-17 on 850513-17.No Violations or Deviations Noted.Major Areas Inspected:Containment Isolation Valve Test Procedure Review,Test Witnessing & Test Results Evaluation

ML20127M773
Person / Time
Site:	Catawba
Issue date:	05/29/1985
From:	Jape F, Macdonald J, Mathis J, Van Dyne K, Vandyne K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127M760	List: IR 05000414/1985017 ML20127M756
References
50-414-85-17, NUDOCS 8507010350
Download: ML20127M773 (4)

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1. jk RM4 .qy UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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ATLANTA. GEORGI A 30303

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Report No.: 50-414/85-17 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket No.: 50-414 License No.: CPPR-117 Facility Name: Catawba Inspection Conducted: May 3-17, 1985 Inspec ors: I d an ).fu e $ Z9 Y J. L. Mathis "[ Dat 51gned h D 29 K. W. Van Dyne ( Date ' Signed 0 .. , b Ws<~ d,n a fd Sf2Gffr J. B, NacDonal Date Signed Approved by: 4 N F. Jape, Chief, Test Progr8fns 5'ection Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: . This routine, unannounced inspection entailed 110 inspector-hours at the site in the areas of containment isolation valve test procedure review, test witnessing, and test results evaluatio Results: No violations or deviations were identifie DR ADOCK0500gl4 l

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. . REPORT DETAILS Persons Contacted Licensee Employees

• J. W. Hampton, Station Manager G. Bonine, Performance Engineer

• C, L. Hartzell, Licensing and Projects Engineer

• R. A. Jones, Performance Engineer

• P. G. LeRoy, Licensing Engineer R. Scarborough, Performance Engineer Other licensee employees contacted included preoperational test engineers, technicians, and office personne NRC Resident Inspectors P. K. Van Doorn, Senior Resident Inspector

• P. H. Skinner, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were sumarized on May 17, 1985, with those persons indicated in paragraph 1 above. The inspectors described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Preoperational Testing Procedure Review Containment System Integrated Leak Rate Testing (CILRT) Unit 2(70307)

The inspectors reviewed PT/2/A/4200/01C, Containment Isolation Valve Leak Rate Test. The purpose of this test is to measure the leak rates of all containment isolation valves identified per Catawba's Final Safety Analysis Report (FSAR) Table 6.2.4-1 as potential bypass leakage paths. In addition, it will verify that the acceptance criteria of ASME Section XI are me _

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PT/2/A/4200/01C was reviewed to verify the following:

- Valve and penetration list is complete and correc Method of pressurization is specifie Test instruments are calibrate Test medium is air or nitroge Valve seats are drained of water (as appropriate).

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Test conditions are allowed to stabilize prior to recording dat Acceptance criteria are specifie Test pressure results in a pressure differential greater than the definedaccidentpressure(Pa).

No violations or deviations were identified in the areas inspecte . Preoperational Test Witnessing - CILRT Unit 2(70313)

Catawba Nuclear Station's Performance Engineering Group is currently testing containment isolation valves for leakag The procedure, PT/2/A/4200/01C, measures leakages rates of individual containment isolation valves by pressurizing the test volume such that pressure is applied to the valves in the same direction as post accident pressure. The leakage rate is determined by measuring the flow rate of dry air required to maintain test pressure. The isolation valve with the highest leak rate is considered the penetration's leak rate. PT/2/A/4200/01C identifies 55 penetrations to be tested. During the inspection period seven penetrations were tested and witnessed by the inspectors. To ensure the adequacy of the leak rate testing the following items were reviewed:

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Testing was conducted in accordance with approved procedure Latest revision of the test procedure was available and in use by testing personne >

- All test prerequisites were me Minimum test personnel requirements were me Required test equipment was calibrated and in servic Interruptions and discrepancies were properly documente All data were collected for final analysi _

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- All test results indicated preliminary acceptance criteria were met or were properly documente No violations or deviations were identified in the areas inspecte . Preoperational Test Results Evaluation - CILRT Unit 2(70323)

As discussed previously in this report, Procedure PT/2/A/4200/01C for determining containment isolation valve leakage is presently being performed at Catawba. Seven of fifty-five penetrations were tested and witnessed by the inspectors. Of these seven penetrations, four passed initial acceptance criteri The remaining three failed and will require retesting. The specific penetrations tested during this report period are listed below: Penetrations passing the initial acceptance criteria:

- CNIP - 2NS1, Containment Isolation Pressure Channels

- CNIP - 2NS4, Containment Isolation Pressure Channels

- M-220, Instrument Air System

- M-373 Ice Condenser Refrigeration System Penetrations not passing the initial acceptance criteria:

- M - 216, Reactor Coolant System

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- M - 256, Chemical and Volume Control System

- M - 228, Chemical and Volume Control System The test data were reviewed to verify the following:

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- Test results are adequately evaluate Test data are either within acceptance criteria or corrections for identified discrepancies are initiated and properly dispositione In addition, test changes and test execution were evaluated for accuracy.

l Within the areas inspected no violations or deviations were identified.

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