ML20236U424
| ML20236U424 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/24/1987 |
| From: | Bradfute J Office of Nuclear Reactor Regulation |
| To: | Baskin K SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| TAC-65826, NUDOCS 8712030037 | |
| Download: ML20236U424 (4) | |
Text
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'Novsmber 24 1987-
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b Docket No.: 50-206.
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Mr.'Kenneth P. Baskin.
Vice President Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800
.Rosemead, California 91770
SUBJECT:
RAI RELATING TO PROPOSED CHANGE NUMBE'1179 FOR SONGS-1:
The.encibsedquestions'andcommentshaveresultedfromour.reviewofPCN-179.
We. request that you. provide the additional.information at your: earliest
-convenience.
If you have any questions regarding this request please contact
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Sincerely, original signed by John 0. Bradfute, Project Manager Project Directorate V-01 vision of Reactor Projects - III IV, V and Special Projects.
Enclosure:
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P Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 CC j
Charles R. Kocher, Assistant Mr. Joseph 0. Ward, Chief 3
General Counsel Radiological Health Branch James Beoletto, Esquire State Department of Healti, Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Stephen B. Allman Dennis M. Smith, Chief San Diego Gas & Electric Company Radiological Programs Division P. O. Box 1831 Governor's Office of Emergency Sycs.
San Diego, California 92112 State of California 2800 Meadowview Road Sacramento, CA 95832 i
Resident Inspector / San Onofre NPS c/o U.S. NRC P. O. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Conrnission 1450 Maria Lane Walnut Creek, California 94596
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Questions /Coavrents re: SONGS - 1 Technical Specification Proposed Change No. 179 1.
Please clarify the statement, "When.the plant is planned to be shut down... a Hot SIS Test shall be. performed".
Define your' meaning of " planned shutdown". Must the shutdown be scheduled at the beginning of the fuel cycle? Can there be a planncd shutdown in response to an operational event? Will the test be performed if there is a non-emergency shutdown of the plant?
2.
The SONGS - 1 Inservice Testing program containsa cold snutdown justification for exercising valves HV 8S1 A & B.
IST program requires that these valves be exercised every cold shutdown not more often than every three months.
Discuss the impact of IST cold shutdotm test frequency on the proposed
' Technical Specification test.
3.
If the measured force exceeds 10,000 lbs, the test interval is required to bc reduced in direct proportion to the increased force.
Will the plant be brougnt to Mode 3 and the Hot SIS test perfomed if there is no planned cold shutdown at the calculated test due date?
4.
What is the effective lifetime ef tne proposed test? Over how many fuel cycles will the Hot SIS test be perfomed?
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ENCLOSURE CONTINUED-f
' 1 5.
The previously proposed Technical Specification change (dated November 21, 1985) stated that the test would be considered satisfactory if HV 851 A & B have actuated in 3 to 5 seconds.
Why is the actuation time no longer included in the test criteria?
6.
Technical Specification 4.2.1, as presently written, implies that the trisodium phosphate additive test is to be conducted at reactor shutdown intervals not longer than the normal plant refueling intervals.
Proposed revision states "A test of the trisodium additive shall be conducted once every refueling..."
Please clarify the apparent relaxation of test frequency.
7.
Please sxplain the reason why the 200 F temperature restriction has been deletea from the Component Tests of the proposed Technical Specification.
8.
Provide any faibare data.for pneumatic hydraulic valves which may be available from the manufacturer or other sources such as applications other than nuclear service. Provide the basis for the assumption that the failure rate of P/H valves is identical to that of MOVs or that the assumption is conservative.
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