IR 05000414/1985017
| 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: |
| References | |
| 50-414-85-17, NUDOCS 8507010350 | |
| Download: ML20127M773 (4) | |
Text
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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
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Sf2Gffr J. B, NacDonal Date Signed Approved by:
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 evaluation.
Results: No violations or deviations were identified.
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REPORT DETAILS 1.
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 personnel.
NRC Resident Inspectors P. K. Van Doorn, Senior Resident Inspector
- P. H. Skinner, Senior Resident Inspector
- Attended exit interview 2.
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 findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
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 correct.
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Method of pressurization is specified.
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Test instruments are calibrated.
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Test medium is air or nitrogen.
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Valve seats are drained of water (as appropriate).
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Test conditions are allowed to stabilize prior to recording data.
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Acceptance criteria are specified.
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Test pressure results in a pressure differential greater than the
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definedaccidentpressure(Pa).
No violations or deviations were identified in the areas inspected.
6.
Preoperational Test Witnessing - CILRT Unit 2(70313)
Catawba Nuclear Station's Performance Engineering Group is currently testing containment isolation valves for leakage.
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:
Testing was conducted in accordance with approved procedures.
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Latest revision of the test procedure was available and in use by
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testing personnel.
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All test prerequisites were met.
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Minimum test personnel requirements were met.
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Required test equipment was calibrated and in service.
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Interruptions and discrepancies were properly documented.
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All data were collected for final analysis.
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All test results indicated preliminary acceptance criteria were
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met or were properly documented.
No violations or deviations were identified in the areas inspected.
7.
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 criteria.
The remaining three failed and will require retesting.
The specific penetrations tested during this report period are listed below:
a.
Penetrations passing the initial acceptance criteria:
CNIP - 2NS1, Containment Isolation Pressure Channels
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CNIP - 2NS4, Containment Isolation Pressure Channels
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M-220, Instrument Air System
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M-373 Ice Condenser Refrigeration System
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b.
Penetrations not passing the initial acceptance criteria:
M - 216, Reactor Coolant System
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M - 256, Chemical and Volume Control System
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M - 228, Chemical and Volume Control System
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The test data were reviewed to verify the following:
Test results are adequately evaluated.
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l Test data are either within acceptance criteria or corrections for
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identified discrepancies are initiated and properly dispositioned.
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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