ML13303B198
| ML13303B198 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/12/1990 |
| From: | Nandy F SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML13303B199 | List: |
| References | |
| NUDOCS 9003160148 | |
| Download: ML13303B198 (3) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION.DISTRIBUTION SYSTEM (RIDS)
SSION NBR:9003160148 DOC.DATE: 90/03/12 NOTARIZED.: NO DOCKET #
ACIL:50-361 San Onofre Nuclear Station, Unit 2, Southern Californ 05000361 50-362 San Onofre.Nuclear Station, Unit 3, Sout rn Californ 05000362 AUTH.NAME AUTHOR AFFILIATION NANDY,F.R.
Southern California Edison Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Docu ent Control Desk)
SUBJECT:
Provides addl info re licensee Proposed Changes Notices 275
& 280,per request for addl details.
DISTRIBUTION CODE:.AO01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT.
COPIES A
ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
1 PD5 PD 1
1 D
KOKAJKO,L.
5 5
D INTERNAL: ACRS 6
6 NRR/DET/ECMB 9H 1
1 NRR/DOEA/OTSB11 1
1 NRR/DST 8E2 1
- 1.
S NRR/DST/SELB 8D 1
1 NRR/DST/SICB 7E 1
1 NRR/DST/SRXB 8E 1
1 NUDOCS-ABSTRACT 1
1 OC/ LFMB 1
0 OGC/HDS2 1
0 01
- 1..
1 RES/DSIR/EIB 1
1 RNAL:
LPDR 1
1 NRC PDR 1
1 NSIC 1
1 R
D S
A D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Ph137 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
WO TAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL.25
Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING (714) 587-5400 March 12, 1990 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362 Amendment Application Nos. 69 and 55 (NPF-10/15-275) and Amendment Application Nos. 72 and 58 (NPF-10/15-280)
San Onofre Nuclear Generating Station Units 2 and 3
Reference:
- 1. SCE to NRC letter, dated 1/8/90, regarding Amendment Applications 69 and 55, Proposed Change Notice NPF-10/15-275
- 2. SCE to NRC letter, dated 1/8/90, regarding Amendment Applications 70 and 56, Proposed Change Notice NPF-10/15-276.
- 3. SCE to NRC letter, dated 1/8/90, regarding Amendment Applications 72 and 58, Proposed Change Notice NPF-10/15-280 This letter provides additional information regarding Southern California Edison's (SCE) Proposed Change Notices (PCNs) 275 and 280. This information is submitted in response to a recent telephone request from the NRC Project Manager to provide additional details for these proposed changes. PCNs 275 and 280 are requests to extend the "refueling" interval surveillances from 18+25% months to 24+25% months. The information requested is supplied as an enclosure to this letter.
The Reactor Protective System (RPS) and Engineered Safety Feature Actuation System (ESFAS) evaluation for calibration extension resulted in changes to Technical Specification setpoints. The revised trip setpoints are based on changes to the Safety Analysis Setpoints and changes to the trip setpoint calculations. No changes to the Safety Analysis Limits were made.
Both SCE and Combustion Engineering (C-E) reviewed all Chapter 15 events and the effect of the extended surveillance intervals on these events. The C-E review consisted of a verification of all trips that are credited in all Chapter 15 analyses. This review is documented in the proposed changes (PCN 275 and 280) and summarized in tabular form in the enclosure to this letter.
9003160148 9012 4,8 FDR ADOCK 0500o361 PDc\\
Document Control Desk March 12, 1990 For each FSAR Chapter 15 Design Basis Event, the table provides the credited RPS trip and the ESFAS functions activated. In addition, those RPS trips and Emergency Feedwater Actuation System functions, for which the Safety Analysis Setpoints were changed, are specifically addressed. These include High Pressurizer Pressure, Low Pressurizer Pressure, High Containment Pressure, Low Steam Generator Water Level, and High Steam Generator Differential Pressure. The effect of those changes are summarized for each of the Chapter 15 events.
Changes to the Containment High pressure setpoint which affect ESFAS functions are addressed in Attachment H to References 1 and 3, but are not included in this table. This information was used in the development of the 10 CFR 50.92 Safety Analysis performed for the proposed changes.
In addition, this letter submits Revision 0, of Report No. M-89047, "Instrument Drift Study."
This Instrument Drift Study was used in support of the instrumentation proposed changes for Reactor Protective System (PCN 275), Remote Shutdown System (PCN 276), and Engineered Safety Feature Actuation System (PCN 280).
If you have any questions regarding this additional information, please call me.
Very truly yours, Enclosures cc:
J.B. Martin, Regional Administrator, NRC Region V C. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3