05000361/LER-1982-169, Forwards LER 82-169/03L-0.Detailed Event Analysis Submitted

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Forwards LER 82-169/03L-0.Detailed Event Analysis Submitted
ML20083N486
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 01/11/1983
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20083N487 List:
References
NUDOCS 8302010668
Download: ML20083N486 (2)


LER-2082-169, Forwards LER 82-169/03L-0.Detailed Event Analysis Submitted
Event date:
Report date:
3612082169R00 - NRC Website

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Southern California Edison Company I;n,y SCE S AN ONOFRE NUCLE AR GENER A TING S T A TION ff[ g, p.o. som 128 S AN C LEMENT E. C A LiFORNI A 92672 k,

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,,. vion o. Nan a January 11, 1983 (t:434,27700 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. R. H. Engelken, Regional Administrator

Dear Sir:

SJbject: Docket No. 50-361 4 30-Day Report Licensee Event Report No.82-169 San Onofre Nuclear Generating Station, Unit 2

References:

1) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC),

dated December 29,1982 "30-Day Report - Licensee Event Report Nos.82-153 and 82-154"

2) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC),

dated January 6,1983 "30-Day Report - Licensee Event Report No.82-162"

3) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC),

dated January 11,1983 "30-Day Report - Licensee Event Report No.82-168" Pursuant to Section 6.9.1.13.b of Appendix A Technical Specifications to Facility Operating License NPF-10 for San Onofre Unit 2, this submittal provides the required 30-day written report and a copy of Licensee Event

! Report (LER) for an occurrence involving Limiting Condition for Operation I (LC(') 3.3.4 associated .rith the Turbine Overspeed Protection System (T0PS).

While in Mode 1, at 0801 on December 12, 1982, following a reactor trip and resultant turbine trip as described in Reference 3, low pressure turbine stop valve 2UV-2200R, located on Low Pressure Turbine #2 failed l

to close fully and was declared inoperable. Accordingly, LC0 3.3.4 Action Statement 'a' was invoked. As reauired by this Action Strtement, valve 2VV-2200Q was shut at 2000 on the same day, isolating the affected steam lead.

l 8302010668 830111 DRADOCK05000g

83-I7

d f R. H. Engelken January 11, 1983 As detailed in References 1 and 2, valva 20V-2200R was disassembled and galling was observed between the butterfly valve disc stub and casing bore. After machining of the stub shaft, cleaning, and reassembly, the valve was returned to operable status in accordance with S023-3-3.34 on December 28, 1982. The attached LER 82-169 addresse: this event.

As stated in References 1 and 2, the operation of all turbine stop and intercept valves will be closely monitored throughout the remainder of the power escalation test program and corrective action, similar to the above, will be applied to the valves as necessary.

Since the affected steam lead was isolated by closing the control valve on the lead, there was no impact on the health and safety of plant personnel or the public.

If there are any questions regarding the above, please contact me.

Sincerely, Heit 3 / nus cc: A. E. Chaffee (USNRC Resident Inspector, San Onofre Units 2 and 3)

R. Pate (USNRC Resident In:pector, San Onofre Units 2 and 3)

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Office of Management Information and Program Control Institute of Nuclear Power Operations