ML13303B877
| ML13303B877 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/14/1988 |
| From: | Medford M SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML13303B878 | List: |
| References | |
| NUDOCS 8801210024 | |
| Download: ML13303B877 (3) | |
Text
REGULA*Y INFORMATION DISTRIBUTId YSTEM (RIDS)
ACCESSION NBR:8801210024 DOC.DATE: 88/01/14 NOTARIZED: NO DOCKET #
FACIL:50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre Nuclear Station, Unit 3, Southern Californ 05000362 AUTH.NAME AUTHOR AFFILIATION MEDFORD,M.O.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Station Procedure S023-3-3.12, "IntegratedESF Sys Refueling Test," station drawings 53000 Rev 12, "Main Control Room Panel Arrangement," & related info per NRC request for addl info prior to approval of PCN-215.
DISTRIBUTION CODE:
AO1D COPIES. RECEIVED: LTR JENCL L SIZE: (
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
PD5 PD ROOD, H INTERNAL: ACRS 6
ARM/DAF/LFMB NRR/DEST/ADS 1
NRR/DEST/CEB NRR/DEST/MTB I
NRR/DEST/RSB I
NRR/DOEA/TSB 1
OQC/HDS2 1
RES/DE/EIC I
REIINTCPE EXTERNAL: LPDR 1
1e NRCPDR I
NSIC 0
1;1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL *2Go
Southem California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD CALIFORNIA 91770 M. O. MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING January 14, 1988 (818) 302-1749 AND LICENSING U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and-3
References:
A. SCE to NRC letter dated May 2, 1986 B. SCE to NRC letter dated October 20, 1986 By Reference A, SCE transmitted proposed Technical Specification Change NPF-10/15-215 (PCN-215), "Diesel Cross-Connect" to the NRC. Following an August 14, 1986 meeting between SCE and the NRC, SCE forwarded additional information (Reference B) to the NRC to facilitate review and approval of PCN-215. During a second meeting to discus PCN-215, the NRC requested the following additional information for review prior to approval of PCN-215:
- 1) Diesel generator load sequences test results
- 2) Probablistic Risk Assessment results and supporting documentation
- 3) Common operator task list
- 4) Common electrical panel equipment details
- 5) Diesel generator fuel consumption calculation
- 6) Diesel generator capacity test results
- 7) Regulatory Guide 1.81 compliance discussion The purpose of this letter is to transmit the requested information to the NRC. Enclosure I includes Station procedure S023-3-3.12, "Integrated ESF System Refueling Test" which details the diesel generator load sequence test methods. Also included are the diesel generator load traces which provide the test results. Enclosure II proyides an "Evaluation of the Reliability Benefits of Proposed Diesel Generator Cross-Connect Modification for San Onofre Nuclear Generating Stations Unit 2 and Unit 3.
This evaluation is the probablistic risk assessment study for the cross-connect and documents all PRA parameters used to demonstrate the safety improvement that would result from the proposed cross-connect. Enclosure III includes five San Onofre Units 2 and 3 procedures (S023-0-2, Rev 3; S0123-0-1, Rev 0; S0123-0-3, Rev 0; S0123-0-30, Rev 0; S023-3-3.0) for control room operation. These procedures 7 88121024 880114 PDR ADOCK 05000361 P
-PDR
Document Control Desk January 14, 1988 clearly define the responsibilities for each control room operator.
Enclosure IV provides the electrical panel instrumentation and control details.
Included are station drawings 53000 Rev 12, "Main Control Room Panel Arrangement"; 53031 Rev 8 and 53032 Rev 11, "Control Panel Layout Electrical Mimic Bus, Sheets 1 and 2"; and 53131 Rev 11 and 53132 Rev 11, "Control Panel Instrument List, Electric Mimic Bus, Sheets 1 and 2."
Enclosure V provides engineering procedure S0123-V-4.12 Rev 2, "Diesel Generator Fuel Oil Tank Size Calculation" which demonstrates adequate fuel volume to support diesel operation in the proposed cross-connect configuration.
Enclosure VI provides engineering procedure S023-SPE-017, Rev 1, "Standby Power Capacity Test" which demonstrates the capability of one diesel generator to supply the worst case accident loads on one unit in conjunction with the safe shutdown loads on the opposite unit. Enclosure VII provides a discussion as to how the proposed cross-connect modification addresses the guidance contained in Regulatory Guide 1.81, "Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants."
If you have any questions, please contact me.
Very truly yours, Enclosures cc: H. Rood, NRR Senior Project Manager, San Onofre Units 2 and 3
- 3. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3