ML20072V493

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ROs 83-31 & 83-28:on 830323,potential Safety Concern Re Calibr Shift of Foxboro 2AO-V31 Modules Associated W/Core Protection Calculators Identified During Testing.Modules Will Be Replaced w/2AO-V21 Modules
ML20072V493
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 03/23/1983
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
83-137, RO-83-28, RO-83-31, NUDOCS 8304110593
Download: ML20072V493 (2)


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U.S.

Nuclear Regulatory Commission Office of Inspection and Enforcement 1

Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention:

Mr.

R.

B.

Engelken, Regional Administrator

Dear Sir:

Subject:

Docket Nos. 50-361 and 50-362 Prompt Reports Licensee Event Report No.83-031 (Docket 50-361)

Licensee Event Report No.83-028 (Docket 50-362)

San Onofre Nuclear Generating Station, Units 2 & 3 Pursuant to Sections 6.9.1.12.i of Appendix A, Technical Specifications to Facility Operating Licenses NPF-10 and NPF-15 for San Onofre Units 2 and 3, respectively, this submittal provides the written confirmation of our March 23, 1983 prompt notification to the NRC of reportable occurrences involving the Reactor Protection Systems (RPS's).

During post-core hot functional testing on Unit 3 and subsequent follow-up troubleshooting, a potential safety concern involving calibration shift of Foxboro 2AO-V3I modules associated with the Core Protection Calculators (CPC's) was identified.

Specifically, this calibration shift, if left uncorrected, could result in erroneous primary loop temperature (T ot and h

Tcold) being transmitted to the CPC's.

This could result in a non-conservative calculation in the CPC's possibly delaying or preventing a reactor trip signal being generated as described in our FSAR.

N 4110593 830323 PDR ADOCK 05000361 S

PDR H-3.1

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s Mr. R. H.

Engelken March 23, 1983 As corrective action, replacement of the Foxboro 2AO-V3I modules with 2AO-v2I modules in Unit 3 will provide assurance that the temperature inputs can be and will remain calibrated.

Although the problem was not identified in Unit 2, a similar change will be instituted.

A 14-day follow-up report with copies of Licensee Event Reports (LER's)82-031 (Docket No. 50-361) and 82-028 (Docket No.

50-362) will be submitted by April 5, 1983 to address these events.

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

Sincerely, cc:

A. E. Chaffee (USNRC_ Resident Inspector, Units 2 and 3)

R. J. Pate (USNRC Resident Inspector, Units 2 and 3) r