ML13310B656
| ML13310B656 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/29/1984 |
| From: | Medford M Southern California Edison Co |
| To: | Paulson W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13310B658 | List: |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8409040121 | |
| Download: ML13310B656 (4) | |
Text
REGULATORY FORMATION DISTRIBUTION SYAM (RIDS)
ACCESSION NBR:8409040121 DOCDATE: 84/08/29 NOTARIZED: NO DOCKET,#
FACIL:50 206 San Onofre Nuclear Station, Unit 1, Southern:Calforn, 05000206 AUTH,NANE AUTHOR AFFILIATION
.ME0FORDM,.O Southern California Edison Co.
RECIP.NAME, RECIPIENT AFF LIATION PAULSONW,A§.
Operating Reactors Bronch 5
SUBJECT:
Forwards add) info re seismic re valuation program per SEP Topic III-6,Sample calculations re seismic evaluation of safe shutdown piping & reswlt of seismic eualuation of vent stacks included.
0 DISTRIBUTION CODE: A028D COPIES RECEILED:L
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TITLE: OR Submittal: SEP Seismic Review NOTES:J Henchett icy POR Documents. NRR/DL/SEP icy, 05000206 OL:03/27/67 RECIPIENT COPIES R CIPIENT COPIES ID CODE/NAME LTTR ENCL JD CODE/NAME LTTR ENCL NRR ORBS BC 01 3
30 INTERNAL: ADM/LFMB 1
ELD4HDS2 1
8 14 1
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NRR DL/TAPMG 1
4 FI WE E*104 1
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EXTERNAL: ACRS 20 6
LPDR 03 1
1 NRC PDR 02 1
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NTIS 11 1
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NOTES:
2 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 4
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Southern California Edison Company P. 0.
BOX 8oo 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M.O. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING August 29, 1984 (213) 572-1749 Director, Office of Nuclear Reactor Regulation Attention: Mr. W. A. Paulson, Acting Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 SEP Topic 111-6 Seismic Design Considerations San Onofre Nuclear Generating Station Unit 1 The purpose of this letter is to provide additional information requested by the NRC relating to the seismic reevaluation program for San Onofre Unit 1. Two reports are provided and include: (1) sample calculations relating to seismic evaluation of safe shutdown piping and (2) results of the seismic evaluation of the vent stack. provides three sample calculations performed on the main feedwater piping. These sample calculations are FW-04, "Safe Shutdown Piping Functionality Assessment," SUP-FW-04-01, "Pipe Support Evaluation for Pipe Functionality" and SUP-FW-04-02, "Pipe Support Capacity Calculations."
These calculations were performed to demonstrate the functionality of the main feedwater piping system as part of the San Onofre Unit 1 seismic return to service program. As shown in SUP-FW-04-01, an iterative quasi-linear analysis procedure was used to demonstrate the functionality of the piping considering variation in the support stiffnesses due to yielding of structural steel members.
This is equivalent to performing a non-linear analysis, accounting for the non-linear load-deflection behavior of the structural steel loaded beyond elastic limits. The calculation iterations are provided as the appendices of SUP-FW-04-01. provides a report entitled "Vent Stack Seismic tho Evaluation, San Onofre Nuclear Generating Station, Unit 1," dated August 14, 001 to 1984. This report provides an evaluation of the San Onofre Unit 1 vent stack 00 !and demonstrates that the vent stack will retain its design function following 0
the occurrence of a 0.67g Design Basis Earthquake using the SONGS 1 Balance of Plant Structures Seismic Reevaluation Criteria.
oo 0<
If you have any questions regarding this information, please call me.
0:I m a_;Very truly yours, Enclosures
ENCLOSURE 1