ML13323A273

Forwards Effects of Vessel Head Voiding During Transients & Accidents in C-E NSSS Prepared for C-E Owners Group.

ML13323A273
Person / Time
Site:	San Onofre
Issue date:	04/28/1982
From:	Baskin K Southern California Edison Co
To:	Miraglia F Office of Nuclear Reactor Regulation
Shared Package
ML13323A274	List: ML13323A273 ML20052B641
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.17, TASK-TM NUDOCS 8205030398
Download: ML13323A273 (3)

Text

REGULATORY ORMATION DISTRIBUTION SYS& (RIDS)

ACCESSION N8Ri8205030398 DOC.DATE: 82/04/28 NOTARIZED: NO DOCKET #

FACIL:50-361 San GOotre Nuclear Station, Unit 2, Southern Cefofrn 05000361 50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTHNAME AUTHUR AFFILIATION BASKINK.P. Southern California Edison Co.

RECIP.NAME RECIPIENT AFFILIATION MIRAGLIAF. Licensing Branch 3 pt

SUBJECT:

Forwards "Effects of Vessel Head Voiding During Transients

& Accidents in C-e NSSSS Prepared for C-E Owners Group,"

DISTRIBUTION CODE: 8001S COPIES 1RECEIVED:LTR .- ENCL SIZE:,-----

TITLE: PSAR/FSAR AMOTS and Related Correspondence NOTES:J Hanchett icy PUR Documents. ELD Chandler icy. 05000361 NRR Scaletti Icy.

J Hanchett Icy PDR Documents, ELD Chandler icy. 05000362 NRR Scaletti icy.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME. LTTR ENCL A/D LICENSNG 1 0 LIC BR,#3 BC 1 0 LIC BR #3 LA I 0 ROOD, 01 1 1 INTERNAL; ELD 1 0 IE FILE 1 1 IE/DEP EPDS 35 1 .1 IE/DEP/EPLB 36 3 3 MPA 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EQB 13 3 3 NRR/DE/GB 28 2 2 NRR/DE/HGEB 30 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTE8 17 1 1 NRR/DE/QAB 21 1 1 NRR/DE/SAB 24 1 1 NRR/DE/SEB 25 1 1 NRR/DHFS/HFEB40 1 1 NRR/DHFS/LGB 32 1 1 NRR/DHFS/OLB 34 1 1 NRR/DHFS/PTRB20 1 1 NRR/DSI/AEB 26 1 NRR/DSI/ASB 27 1 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CSB 09 1 1 NRR/DSI/ETSB 12 .1 .1 NRR/DSI/CSB 16 1 1 NRR/DSI/PSB 19 1 .1 NRR/DSI/RAB 22 1 1 23 1 1 NRR/DST/LGB 33 1 1 REG FILE 04 1 1 RGNS 2 2 EXTERNAL: ACRS 41 10 10 BNL.(AMDTS ONLY) 1 1 FEMA-REP DIV 39 1 1 L:PDR 03 1 1 NRC POR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRLD: LTTR / ENCL ME

A Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING (213) 572.1401 SAFETY, AND LICENSING April 28, 1982 Director, Office of Nuclear Reactor Regulation Attention: . Mr. Frank Miraglia, Branch Chief Licensing Branch No. 3 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 Item II.K.2.17, Potential for Voiding in the Reactor Coolant System (RCS) During Transients, of NUREG-0737 required SCE to analyze the potential for voiding in the RCS during anticipated transients for San Onofre Units 2 and 3. This requirement has also been identified as license condition (19)p of Operating License No. NPF-10 for San Onofre Unit 2.

SCE has participated in the Combustion Engineering Owners Group (CEOG) program for responding to the requirements, Item II.K.2.17 of NUREG-0737. As a result of this effort, CEN-199, "Effects of Vessel Head Voiding During Transients and Accidents in CE NSSS's, March, 1982" was prepared by the CEOG. CEN-199 addresses the potential for void formation during various types of plant transients and concludes that any void formation which may occur is not great enough to impair reactor coolant circulation or core coolability. This conclusion is based upon the premise that operator action is taken in accordance with plant-specific Emergency Operating Instructions (EOI's) which incorporate the typical guidelines, related to RCS voiding, which are presented in Appendix A of CEN-199. The EOI's for San Onofre Units 2 and 3 were developed utilizing plant specific aspects of the typical guidelines presented in Appendix A of CEN-199 and the operators have been trained to take action in accordance with the EOI's. SCE considers that the results of the evaluation on the potential for voiding in the RCS, as discussed in CEN-199, are applicable to San Onofre Units 2 and 3 and that the results demonstrate that the impact of RCS voiding will not result in violation of NRC Standard Review Plan Acceptance Criteria.

8205 03D318

Mr. Frank Miraglia -2 Accordingly, enclosed please find seven (7) copies of the report, CEN-199, "Effects of Vessel Head Voiding During Transients and Accidents in CE NSSS's, March, 1982" (NRC Mail Code (B028). SCE considers that the enclosed information satisfies the requirements of Item II.K.2.17 of NUREG-0737 for San Onofre Units 2 and 3 and license condition (19)p of Operating License No.

NPF-10 for San Onofre Unit 2.

If you have any questions or comments, please let me know.

Very truly yours, Enclosures