ML13308B852

Forwards Revised Emergency Operating Instructions for Use During 810214-15 CE Simulator walk-through in Windsor,Ct & 810218 Facility Control Room walk-through.Procedures Preliminary & Subj to Vendor Review & Approval

ML13308B852
Person / Time
Site:	San Onofre
Issue date:	02/04/1981
From:	Baskin K Southern California Edison Co
To:	Miraglia F Office of Nuclear Reactor Regulation
Shared Package
ML13302A166	List: ML13302A165 ML13302A167 ML13302A168 ML13302A170 ML13308B852 ML20003A835
References
NUDOCS 8102090136
Download: ML13308B852 (3)

Text

PEGULATORONFORMaTION DISTRIBUTION S E!. (RIS)

OuC.DATE: 81/02/0 NOTARIZED: NO DOCKET If ACCESSION NzR:8102090136 FACIL:50-361 San Onofre iuclear Station, Unit 2, Southern Californ 050116-1 Southern Caliform 500362 50-362 San Onofre 'uclear Stationp Unit 3, AUTHONAME AUTHJR AFFILIATION BASKINerK.P. Southern California Edison Co.

RECIP.\IAME RECTPIENT AFFILIATION MIRA GLIA.F,J. Onerating Reactors Branch 3 for use

SUBJECT:

Forwards revisea emergency operating instructions during 810214-15 CE simulator walk-through in Winasor,CT &

810218 facility control room walk-through.ProcedureS preliminary & subj to venoor review & approval.

DISTRIBUTION CODE: 80013 COPIES RECEIVED:LTR ENCL SIZE:2.

TITLE: PSAR/FS-AR AMOTS and Related CorrespondenCe ER amends to L Chandler. 050003b1 NOTES:Send all .FSAR &

1 cy:J Hanchett (Region V).D Scalettist cy of all envir into ER amends to L Chandler, 05000362 Send all FSAR &

1 cy;J Hanchett (Region V),0 Scaletti,1 cy of all envir info ECTPIEN1T LO ES PECIDIE'T C)PTE Iv CODE/NAME LTE[R ENCL ID CocE/NAME LTTEk.NCL ACTION: A/D LICENSNG 1 0 MIRAGLIAF. 1 0 1 0 ROOD,H. 04 1 1 LEEJ.

ACCID EVAL BR2b 1 1 AUX SYS 8R 07 1 1 INTERNAL: 1 CHEM ENG FR 06 1 1 CONT SYS BR 09 1 CORE PERF BR 10 1 1 EFF TR SYS 8R12 1 1 EMERG PREP 22 1 0 EQUIP QUAL 6R13 3 3 14 1 1 HUM FACT ENG bR 1 1 GEUSCIENCES HYD/GEO 3R 15 2 2 I&C SYS BR 16 1 1 06 3 3 LIC GUID BR I I I&E 1 1 MATL ENG 8R 17 '1 1 LIC QUAL BR MECH ENG 9R 16 1 1 MPA 1 0 NRC PDR 02 1 1 CELD 1 0 UP LIC RR 1 1 POWER SYS BR 19 1 1 20 1 1 ')A BR 21 1 1 PRO.C/TST REV

-.&SS 9R2 1 1 REAC SYS 8R 23 1 1 0125 1 1 SIT ANAL BR 24 1 1 LT~FLNG ENG BR25 I1C 1 SYS INTERAC BR 1 1 ACRS 27 to 16 LPDR 03 1 1 EXTERNAL:

NSIC 05 1 1 FEB a 198, J 70oTA L Ny~~ OF COPIES REUUIRED:' LTTR ENL 4s1

Southern California Edison Company P 0. E30X 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALlFORNIA 91770 K. P. BASKIN February 4, 1981 TELEPHONE (13) 572-1401 MANAGER OF NUCLEAR ENGINEERING, SAFETY. ANO LJCENSING Director, Office of Nuclear Reactor Regulation Attention: Mr. Frank Miraglia, Branch Chief Licensing Branch No. 3 A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 SCE's letter of November 12, 1980 transmitted the following four Emergency Operating Instructions (EOI's) for San Onofre Nuclear Generating Station, Units 2 and 3:

Loss of Coolant Accident (LOCA)

Steam Generator Tube Rupture (SGTR)

Loss of Feedwater (LOFW)

Determination of Adequate Core Cooling (DOACC)

SCE met with the NRC PTRB on January 22 and 23, 1981 at the San Onofre Site to discuss the NRC's comments. SCE has revised the above four EOI's consistent with the comments and clarification provided by the NRC.

Since the "Emergency Plant Shutdown" (EPS) EOI is referenced in the Immediate Operator Action section of the above four EOI's, SCE has also revised the EPS EOI consistent with the format of the above four EOI's.

Enclosed please find three (3) copies of the following five revised EOI's:

Loss of Coolant Accident (LOCA)

Steam Generator Tube Rupture (SGTR)

Loss of Feedwater (LOFW)

Determination of Adequate Core Cooling (DOACC)

Emergency Plant Shutdown (EPS)

These EOI's are provided for use by the NRC and SCE during the simulator walk-through which is scheduled for February 14 and 15, 1981, at the CE simulator in Windsor Connecticut and the San Onofre Units 2 and 3 control room walk-through which is scheduled for February 18, 1981 at the San Onofre site. The procedures are preliminary and are subject to review and approval 50 by the NSSS vendor (CE). Final revised versions of these procedures, which

Mr. Frank Miraglia February 4, 1981 incorporates comments from the NSSS vendor and comments resulting from the simulatory and control room walk-through, will he provided as soon as practicable.

If you have any questions or comments concerning this matter, please contact me.

Very truly yours, Enclosures