ML13331A519
| ML13331A519 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/18/1990 |
| From: | Nandy F Southern California Edison Co |
| To: | NRC/IRM |
| References | |
| NUDOCS 9012210015 | |
| Download: ML13331A519 (2) | |
Text
Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 December 18, 1990 F. R. NANDY TELEPHONE MANAGER. NUCLEAR LICENSING (714) 454-4504 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Amendment Application No. 162 Containment Spray Actuation Instrumentation San Onofre Nuclear Generating Station, Unit 1 This letter notifies you that a delay will be required for submittal of the supplement to Amendment Application No. 162. Amendment Application No. 162 creates new technical specifications for the containment spray actuation system instrumentation. As discussed with Mr. James Tatum of the NRC staff, we are in the process of revising the analyses which determine peak accident pressure and temperature after a design basis accident. Because of these revisions, submittal of the supplement to Amendment Application No. 162 will be delayed until two months after restart from the Cycle 11 refueling outage.
Background
Amendment Application No. 162 was originally submitted on December 29, 1988.
It was prepared in response to an open item from Systematic Evaluation Program Topic IV-10A, "Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing." In response to NRC questions about the setpoint for the containment spray actuation system instrumentation, a supplement to Amendment Application No. 162 was initiated. In support of the supplement the peak containment pressure and temperature were recalculated.
As stated in our June 18, 1990 letter, based on a 2'F increase in peak containment temperature, submittal of the supplement was delayed pending verification of the environmental qualification of equipment inside containment.
New Single Failure Analysis As described in our July 31, 1990 submittal, we have updated our single failure analysis for the emergency core cooling system. As a result, it was necessary to reanalyze the peak containment pressure and temperature following a main steam line break or a loss of coolant accident. The analysis of the peak containment conditions is currently in progress and will be completed
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Document Control Desk December 18, 1990 prior to startup from the Cycle 11 refueling outage. Submittal of the supplement to Amendment Application No. 162 must be delayed until the peak containment conditions are determined.
As discussed with Mr. Tatum, revision of the containment response analyses may also affect the containment design and test pressure. The containment design pressure is currently being reevaluated. An additional submittal will be provided by January 31, 1991 to discuss the containment design pressure analysis and the pressure at which containment testing will be performed.
Submittal Schedule Since resolution of SEP Topic IV-10.A is scheduled for the Cycle 12 refueling outage, delaying submittal of the supplement to Amendment Application No. 162 until two months after the Cycle 11 outage will not impact the overall schedule of Cycle 12 issues. The submittal discussing the containment design and test pressures will be submitted by January 31, 1990.
If you have any questions, please do not hesitate to call me.
Very truly yours, cc:
J. B. Martin, Regional Administrator, NRC Region V C. W. Caldwell, NRC Senior Resident Inspector, San Onofre Unit 1, 2 & 3 C. D. Townsend, NRC Resident Inspector, San Onofre Unit 1