IR 05000317/1979020
| ML19294B544 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/31/1979 |
| From: | Caphton D, Rekito W, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19294B541 | List: |
| References | |
| 50-317-79-20, 50-318-79-19, NUDOCS 8003050060 | |
| Download: ML19294B544 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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Region I 50-317/79-20 Report No. 50-318/79-19 50-317 Docket No. 50-318 DPR-53 License No. OPR-69 Priority
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Category C
Licensee: Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection at: Lusby, Maryland Inspection conducted: November 9;11, 13, and 15-16, 1979
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Inspectors:
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date signed Approved by:
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D. L. Laphton, Chief, fluclear Support Section date signed No. 1, RO&NS Branch Inspection Summary:
Inspection on November 9-11,13, and 15-16,1979 (Combined Report Nos. 50-317/
79-20 and 50-318/79-19)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of the Containment Integrated Leak Rate Test - CILRT (Unit 2) and licensee action on previous inspection findings (Units 1 and 2). The inspection involved 42 inspector-hours (Unit 1 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Unit 2 - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) on site by. two NRC regional based inspectors.
Results: No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
80030500hp
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DETAILS 1.
Persons Contacted Baltimore Gas and Electric Comoany
- J. Carroll, Supervisor, Technical Support J. Lawson, Shift Test Supervisor
- B. Rudell, Test Supervisor L. Russell, Chief Engineer R. Wenderlich, Shift Supervisor Bechtel Corporation M. Bergess, Senior Engineer M. Downs, Senior Engineer The inspector also talked with and interviewed several other licensee employees during the inspection.
They included members of the technical and engineering staffs, and reactor operators.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findinos (Closed) Unresolved Item (317/78-25-14, a18/78-19-14):
Procedure STP M-5-7 11, " Local Leak Rate Testing," has been revised to clearly require that both sides of a containment isolation valve (CIV) be drained of water prior to testing. The procedure has also been revised to require that the local leakage rate total of all penetrations is updated after maintenance has been performed on a CIV. These items are considered resolved.
(Closed) Unresolved Item (317/78-25.1, 318/78-19-13):
The licensee has revised procedure STP M-471, " Air Lock Door Operability and Leak Rate Test," to specify a conservative minimum test sensitivity. These items are considered resolved.
(Closed) Unresolved Item (317/78-25-12, 318/78-19-12): The " Personnel Air Lock Seal Test procedure, STP M-171, has been revised to require a test pressure of 15,"0
psig; this conforms to the technicai specification requirements. The option to perform a pressure decay test has also been deleted from the procedure.
These items are considered resolve.
3.
Containment Integrated Leak Rate Test (CILRT)
a.
General On November 9-16, 1979, Calvert Cliffs, Unit 2, performed their first periodic CILRT.
The test was conducted at a peak accident pressure of 50 psig in accordance with procedure STP H-662-2, Revision 1, " Integrated Leak Rate Test, Unit 2," dated November 7,1979. The inspector reviewed the procedure, witnessed various portions of the test, verified quali-fications of test personnel, and independently verified calculations of the test results.
Details of the test are discussed below.
The inspector had no further questions or connents other than those which follow.
b.
Procedure Review The inspector reviewed procedure STP M-662-2, Revision 1, " Integrated Leak Rate Test, Unit 2,"
dated November 7,1979, for technical adequacy and complianc9 with 10 CFR 50, Appendix J, ANSI N45.4, and Calvert Cliffs Technkal Specifications.
The inspector noted that the procedure required a minimum test duration of eight hours.
This reduced duration test is acceptable to the NRC based on the procedure meeting the requirements of Bechtel Power Corporation's Topical Report BN-TOP-1,
" Testing Criteria for ILRT of Primary Containment Structures for Nuclear Power Plants."
c.
Valve Lineup Review On a sampling basis, the inspector checked the CILRT procedure valve lineup sheets to verify that:
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Each penetration was provided with a valve lineup; Valves were in the correct positions;
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Proper vent paths were provided; and,
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Artificial leakage barriers were not created which could mask
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containment leakage.
In addition, the inspector independently verified the correct position of selected valves during various phases of the test.
No valve misalign-ments were identified and no dis;repancies were note d.
Instrumentation The inspector reviewed the calibration records for the resistance temperature detectors, dew point instruments, pressure detectors and the verification test flowmeter.
Their calibration prior to the CILRT was found to be traceable to the National Bureau of Standards.
The calibration errors were found to be properly incorporated into the computer leak rate calculations.
Based upon this review, the instruments were found to be properly calibrated and suitably traceable.
e.
Chronology 11/9 1330 Commenced pressurization.
11/10 1230 Pressurization completed at 65.6 psia.
Commenced four hour temperature stabilization.
1630 Stabilization completed.
Initial data inM cated leakage above acceptance criteria.
2000 Leakage path identified through both steam generators, 11/11 0745 Leakage path identified through the ECCS contain-ment sump suction valve MOV-4145 (later found to be not fully shut).
1440 Commenced depressurization.
11/12 0200 Entered containment.
Repaired and re-closed MOV-4145. Attempted to locate and repair leaks into the steam generators.
0600 Commenced repressurization of containment.
2000 Noted that steam generator pressure increased with containment pressure.
2215 Completed pressurization.
11/13 1045 Commenced depressurization, 11/14 0030 Located and secured additional leakage paths on the steam generator Commenced repressurization.
2248 Completed pressurization at greater than Pa.
Commenced temperature stabilization.
11/15 1300 Commenced CILRT.
2115 Recorded data indicated leak rate was within the acceptance criteria.
Completed CILRT.
2245 Commenced verification test.
11/16 0500 Completed verification test.
f.
CILRT Results On November 16, 1979, the CILRT was successfully completed after the initial attempt had ended in a test failure. The initial attempt is considered a failure due to the leakage past the ECCS containment sump suction valve MOV-4145.
Based on the initial test failure and the requirements of 10 CFR 50, Appendix J, Paragraph III.6.a, the future CILRT test schedule at Calvert Cliffts, Unit 2, is required to be reviewed and approved by the Commission.
The inspector's calculated results of the successful test are summarized below.
(Results reported in weight percent per day unless otherwise stated.)
Acceptance Item Criteria Result.
(1) CILRT Leak Rate by fiass Point 0.052
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Technique (2) CILRT Leak Rate by Mass Point 0.15 0.064 at the Upper 95% Confidence Level (3) Supplemental Verification Test 0.25 La 0.07 La Difference The inspector noted that local leak rate test additions must be made to the above test results for penetrations in use during the test and possibly a correction made for changes in the containment free volume due to water accumulation inside containmen.
The licensee's test results will be reviewed by the NRC when the licensee's summary test report is submitted.
4.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on November 16, 1979.
The inspector summarized the scope and findings of the inspection.
No items of noncompliance were identified.