ML20032C541
| ML20032C541 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 10/26/1981 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20032C538 | List: |
| References | |
| NUDOCS 8111100555 | |
| Download: ML20032C541 (2) | |
Text
1 41 ATTACHMENT Containment components other than mentioned above, which develop leaks requiring repairs during the performance of a Type A test, shall be included in subsequent Class B tests:
" Component Leak Surveillance System: A leak surveillance system (i.e., continuous pressurization of individual containment components) that maintains a pressure not less than 52 psig at individual test chambers of conti.inment penetrations and seals during normal reactor operation shall be acceptable in lieu of Type B tests for the components under such leak surveillance."
(b) Acceptance Criteria: The permissible leak flow rate of any individual leak penetration detected by a Type B test shall meet the following:
(1) Personnal air lock
-10% of leakage rate Lpo (2) Emergency air lock
-2% of leakage rate Lpo (3)
Individual cable penetrations
-0.25% of leakage rate Lpo in electrical penetrations units 18 and 1C (4) All other testable containment
-1% of leakage rate Lpo penetrations (c) Corrective Action:
Leaks which exceed the acceptance criteria of (b) shall be repaired and retested until the criteria are met. Repairs of lesser leaks are optional.
"(d) Test Frequency: Type B tests (except for air locks) shall be performed during each reactor shutdown for fuel reloading or other convenient intervals, but in no case at intervals greater than 2 years. Air locks shall be tested at 4-month intervals. The freight door shall be tested following each closure prior to plant startup."
l 5.2.1.3 Containment Isolation Valve Tests (Type C Tests):
(a) Tests: The ventilation system isolation valves and the vacuum relief valves shall be subjected to operability and leak-detection tests.
The isolation valves and the vacuum relief valves shall be exercised for at least one full cycle of opening and closing by the means provided for normal actuation prior to the performance of a leak-detection test.
The leak detection tests shall be conducted at 52 psig.
" Containment isolation valves in the main steam and feedwater
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systems shall be tested with air at a pressure not less than 52 psig I
either individually or by pressurization between the reactor vessel and the isolation valves."
"(b) Acceptance Criteria:
For containment isolation valves in the main steam and feedwater systems, the total permissible leakage rate shall not exceed 60% of leakage rate Lpo. The permissible leakage rate of any other valve tested shall not exceed 1% of leakage rate Lpo."
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ATTACHMENT 42 (c) Corrective Action: Valve malfunctions disclosed by any Type C test i
shall be corrected and reported in a subsequent technical report (see Section 5.2.1.5below).
Leaks which exceed the acceptance criteria of (b) shall be repaired and retested
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until the criteria are met.
Repairs of lesser leaks are optional.
(d) Test Frequency: Type C tests shall be performed during each reactor i
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shutdown for refueling, but in no case at intervals greater than 2 years.
5.2.1.4 Permissible Periods for Testing: The performance of Type A tests shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition under administrative control and safety procedures.
5.2.1.5 Report of Test Results:
The leakage rate results of Type A, B, and C tests that meet the acceptance criteria shall be reported in the applicable LACBWR operating report. Leakage test results of Type A, B, and C tests that fail to meet the acceptance criteria shall be reported in a separate summary f
that includes an analysis and interpretation of the test data, the least-squares fit analysis of the test data, the instrumentation error analysis, and the structural conditions of the containment or components, if any, which contributed to the failure in meeting the acceptance criteria.
Results and analyses of the supplemental verification test employed to demonstrate the validity of the leak-age rate test measurements also shall be included.
5.2.2 The reactor building isolation system will be tested for proper operation prior to every cold startup, but this test will not be required more often than at 30-day intervals.
i 5.2.3 The exterior surfaces of the LACBWR ventilation stack and the smoke stack of the conventional steam power generating station, Genoa 3, adjacent to the LACBWR plant shall be inspected for structural integrity at an interval no longer than 5 years following the initial construction inspection, and at subsequent intervals not longer than 5 years apart.
l 5.2.4 The reactor vessel shall be hydrostatically tested at 1400 psig af ter any of its gasketed joints have been opened and resealed. All hydrostatic tests I
shall be performed with the vessel at a temperature no lower than that specified l
in Section 4.2.2.4.
5.2.5 The forced circulation system controls and automatically-operated valves shall be tested for proper operation annually.
I 5.2.6 The shutdown condenser system control valves shall be tested at least quarterly to demonstrate their operability. The integrated system shall be i
tested for proper operation annually.
In addition, the condenser tube bundle shall be pressurized to greater than 1250 psig and tested for leakage annually.
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5.2.7 The high-pressure core spray system controls and remotely-operated valves shall be tested semi-annually to demonstrate their operability. The integrated system shall be tested for proper operation annually. This annual teit shall include a determination of the differential pressure betaeen the coolant supply line and the reactor vessel.
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