ML13322B025
| ML13322B025 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/30/1989 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| TASK-2.K.3.05, TASK-TM TAC-60514, NUDOCS 8909050437 | |
| Download: ML13322B025 (4) | |
Text
August 30, 1989 Docket No.:
50-206 DISTRIBUTION Docket File DJaffe NRC & LPDRs CTrammell (2)
Mr. Harold B. Ray MVirgilio Vice President JLee Southern California Edison Company OGC-White Flint Irvine Operations Center PD5 Plant File 23 Parker EJordan Irvine, California 92718 BGrimes ACRS (10)
SWu
Dear Mr. Ray:
JTatum
SUBJECT:
TMI ACTION PLAN ITEM II.K.3.5 (MPA G-01), REACTOR COOLANT PUMP TRIP ISSUE (TAC NO. 60514)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 We have completed our review of TMI Action Plan Item II.K.3.5 regarding reactor coolant pump (RCP) trip requirements for San Onofre Nuclear Generating Station, Unit 1. As discussed in the enclosed safety evaluation, we find that the RCP trip issue is satisfactorily resolved based on the revised Westinghouse Owners Group methodology that was used.
Sincerely, original signed by Charles Trammell Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation, RCP Trip cc: See next page
[S01 RCP RIP]
0 D
PD5 ell:dr igton
\\~
19,89 Vt e/89 OFFICIAL RECORD COPY
'90 064='
CPD Abo CK ~Or n -.
0()
OP UNITED STATES C)
NUCLEAR REGULATORY COMMISSION o
- E WASHINGTON, D. C. 20555 August 30, 1989 Docket No.:
50-206 Mr. Harold B. Ray Vice President Southern California Edison Company Irvine Operations Center 23 Parker Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
TMI ACTION PLAN ITEM II.K.3.5 (MPA G-01), REACTOR COOLANT PUMP TRIP ISSUE (TAC NO. 60514)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 We have completed our review of TMI Action Plan Item II.K.3.5 regarding reactor coolant pump (RCP) trip requirements for San Onofre Nuclear Generating Station, Unit 1. As discussed in the enclosed safety evaluation, we find that the RCP trip issue is satisfactorily resolved based on the revised Westinghouse Owners Group methodology that was used.
Sincerely, Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation, RCP Trip cc:
See next page
Mr. Harold B. Ray San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc David R. Pigott Mr. F. B. Marsh, Project Manager Orrick, Herrington & Sutcliffe Bechtel Power Corporation 600 Montgomery Street P. 0. Box 60860 San Francisco, California 94111 Terminal Annex Los Angeles, California 90060 Mr. Robert G. Lacy Manager, Nuclear San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego 1600 Pacific Highway Room 335 San Diego, California 92101 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. John Hickman Senior Health Physicist Environmental Radioactive Management Unit Environmental Management Branch State Department of Health Services 714 P Street, Room 616 Sacramento, California 95814 Mr. Don Womeldorf Chief Environmental Management California Department of Health 714 P Street, Room 616 Sacramento, California 95814 (9)
ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SONGS-1 For the reactor coolant pump (RCP) trip issue defined in TMI Action Plan Item II.K.3.5 (Multiplant Action G-01), the staff generically approved the Westinghouse Owners Group (WOG) methodology in the Generic Letter 85-12 with the condition that plant-specific information needs to be addressed. For SONGS Unit 1, WOG methodology does not directly apply because of unique plant features such as fuel rods with stainless steel cladding. Therefore, the licensee chose to use a revised WOG methodology to address two safety concerns - (1)
Delayed RCP trip during a small break LOCA, and (2) Potential pressurizer power operated relief valve (PORV) failures.
The analysis results showed that (1) Adequate core cooling is provided for SONGS Unit 1 for any SBLOCA with delayed RCP trip and (2) PORV will be used only as a secondary steam generator tube rupture SGTR) recovery technique due to a revision to the approved Emergency Operating Procedure (EOP), thereby eliminating the PORV potential failures. We therefore conclude that the licensee has adequately addressed the staff concerns and satisfactorily resolved the RCP trip issue for SONGS Unit 1 based on the acceptable revised WOG methodology.
References:
(1) Letter, M.O. Medford, SCE, to J.A. Zwolinski, NRC, TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," dated October 10, 1985.
(2) Letter, M.O. Medford, SCE, to G.E. Lear, NRC, TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps," dated January 21, 1986.