ML20118A246
| ML20118A246 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/31/1992 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 9208260245 | |
| Download: ML20118A246 (2) | |
Text
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_< i RECEIVED 1;RC da REG 10:1 V Southem Califomia Edison Compagry, y -Q l.il 9; 26 23 PARKE R GT REET 1RVINE. CAUFORNLA D2718 O M ROSEfJBLUM TFLEPHONE bt A$MGEH f.F 171414S4 4605 6MLt.AH HEL.ULATOMY AF> AARS U.
S. Nuclear Regulatory Commission, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Attention:
Mr.
J.
B. Martin, Regional Administrator
Dear Sir:
Subject:
Docket Nos. 50-361 and 50-362 Hazardous Cargo Monitoring Report San Onofre Nuclear Generating Station Units 2 and.3
References:
1)
Letter from F.
R. Nandy (SCE) to Region V (NRC) dated February 15, 1991,
Subject:
Docket No9. 50-361 and 50-362 Hazardous Cargo Monitoring Report, San Onofre Nuclear Generating Station Units 2 and 3 2)
Letter from R. M.
Rosenblum (SCE) to Region V (NRC) dated June 17, 1991,
Subject:
Docket Nos. 50-361 and 50-362 Hazardous Cargo Monitoring Report, San Onofre Nuclear Generating Station Units 2'and 3 l-San Onofre Units 2 and 3 Technical Specification 6.9.1.14 L
_requiresLthat " hazardous cargo traffic on Interstate 5 and the AT&SF_ railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years."
Our report.
i.
entitled "Offsite Hazards Evaluation _ Update," dated January, L
1991, which summarized the methods, results, and conclusions of the most recently completed hazardous cargo monitoring effort, was submitted to you by Reference 1.
Reference 2 amended the report to correctly apply Standard Review Plan 2.2.3.
On page.5 of the report,-we made the following statement:
"In the-case of the explosion hazard, the shipment size affects the percentage of shipments capable of causing an L
excessive overpressure at the plant.
All substances capable p
of creating an explosive overpressure in excess of one predetermined value of 7 psiHat the nearest safety-related i
I/00 9208260245-920131
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PDR.ADOCK 05000361 R
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B.
Martin' plant structure were evaluatea together as a single event and'the result compared with the SRP acceptance criteria.
As part of this study, SCE is reconfirming that all safety-related structures were considered in the overpressure evaluation.
We are planning to complete this effort by December, 1991."
We have completed our study and have verified that all safety related structures were considered in the 7 psi overpressure evaluation (Calculation C-260-1, " Blast Loading on Category I Structures").
Therefore, no further action is required by SCE.
If you have any questions concerning the above information, please contact me.
Very truly yours, l'DL l
cc:
C. W.
Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2&3 L
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