ML13317A492
| ML13317A492 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/26/1983 |
| From: | Baskin K Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8301280248 | |
| Download: ML13317A492 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, January 26, 1983 (213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention:
D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Containment Ventilation Isolation Valves Leakage Rate Test Program San Onofre Nuclear Generating Station Unit 1 Your letter of February 17, 1982 forwarded a request for additional information related to the subject topic. In particular, item 4 of of your letter requested the details of the test program that we propose in order to implement the requirements for the containment ventilation isolation valves given in Enclosure 1 of your letter.
A narrative description of the Containment Ventilation Isolation System leakage rate tests that SCE proposes is attached as Enclosure 1.
Existing procedures are currently being revised to reflect your testing requirements. These revised procedures will be completed prior to startup from the current outage.
If you have any questions or desire additional information regarding this subject, please contact me.
Very truly yours, Enclosure 8301280248 830126 PflR ADOCK 05000206 P
R PROPOSED LEAKAGE TEST PROGRAM FOR CONTAINMENT VENTILATION ISOLATION VALVES The proposed test program for the contianment ventilation isolation valves is to perform a test in accordance with Appendix J of 10 CFR Part 50 with the preconditions and initial conditions as given by Appendix J and ANSI N45.4-72. These are pressure decay tests conducted on the volume of the piping between containment isolation valves of a penetration. This comprises the potential for a double ended leak through either valve rather than through the two valves in series. Hence, the test results would indicate higher leakage rates than would be experienced in operation.
The acceptance criteria for a successful test and the actions to be taken if a criterion is not met are:
o if the combined leakage for all penetrations exceeds 90% of allowable* as indicated by a pressure decay test, initiate corrective maintenance action as practicable to reduce the total below 90%;
o if any single penetration exceeds 20% of allowable* as indicated by a penetration pressure decay test, an assessment should be made to determine the major source and maintenance action should be initiated as practicable; and o
if leakage exceeds 100% of allowable* as indicated by a pressure decay test, report this condition to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The tests on the containment ventilation valves will be performed at intervals no greater than 6 months plus or minus 45 days. Past local leakage rate tests on containment ventilation valves CV-10, -40 and -116 indicate that the seal material has not deteriorated during an interval twice this test interval.
Negative test results, which lead to actions required in the Limiting Conditions for Operations 3.6.2 but which are not subject to prompt notification, will be reported by a Licensee Event Report. Summaries of Types B and C leakage test results will be included in the Type A test report.
Allowable is 0.072 wt/o per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> which is 60% of the leakage rate used to relate DBA to 10 CFR Part 100 (SE by ONRR, 4-1-77) and is the recommended maximum combined leakage of all penetrations subjected to either Types B or C tests.
MThomas:6750