05000362/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-008/03L-0.Detailed Event Analysis Submitted

ML20083N519
Person / Time
Site:	San Onofre
Issue date:	01/14/1983
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20083N522	List: 05000362/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Submitted 05000362/LER-1982-008-03, /03L-0:on 821215,while in Mode 5,RCS Chloride Level Exceeded Limit of 0.15 Ppm.Caused by Displacement of Chloride from Purification Ion Exchange Resin to Rcs. Resin Replaced
References
NUDOCS 8302010678
Download: ML20083N519 (2)

LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3621982008R00 - NRC Website

text

.

80 g5 Southern California Edison Company ling g, f),3?

S AN ONOFRE NUCLE A R GENER A TING S T A TION

.e.. a,,,,

g

.* ~ c t EuE~T E. c A u roR~u nn

.1.,,o~.."*""

January 14, 1983 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:

Subject: Docket No. 50-362 30-Day Report Licensee Event Report No.82-008 San Onofre Nuclear Generating Station, Unit 3 Pursuant to Section 6.9.1.13.b of Appendix A Technical Specifications to Facility Operating License NPF-15 for San Onofre Unit 3, this submittal provides the required 30-day written report and copy of Licensee Event Report (LER) resulting from an incident involving Limiting Condition for Operation (LCO) 3.4.6 associated with Reactor Coolant System (RCS) chemistry.

LC0 3.4.6 requires steady state RCS chloride level to be maintained below 0.15 ppm at all times. On December 15,1982 at 0224 while in Mode 5, a routine sampling of RCS water indicated a chloride level of 0.28 ppm. The Action Statement associated with LC0 3.4.6 requires reduction of RCS pressura to less than or equal to 500 psia, if the out-of-limit condition exists for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and performance of an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the RCS.

The RCS chloride level was reduced to less than 0.15 ppm on December 16, 1982 at 0300, however, it increased above the limit of 0.15 ppm at 1115 and remained in that condition until December 18,1982 at 0030 when it was again reduced below the limit.

RCS pressure was less than 500 psia throughout this incident.

8302010678 830114 PDR ADOC% 05000362 S

PDR 83 M

4 R. H. Engelken January 14, 1983 The cause of this incident was displacement of chloride from the purification ion exchange resin. This can occur when hydrazine (used for Oxygen control during cold shutdowns) decomposes to form ammonia which, in the presence of boric acid, forms ammonium borate. The borate ions then displace chlorides from the anion resin. The ion exchange resin was replaced on December 18, 1982 and the RCS chloride level returned to within the requirenents of LC0 3.4.6.

The chloride level remained higher than normal (but within the limits of LC0 3.4.6) at approximately 0.13 ppm, until December 21, 1982 when the ion exchanger was " fluffed" as an additional corrective measure, reducing the chloride level to less than 0.05 ppm. Appropriate chemistry procedures will be reviewed and revised as necessary to prevent recurrence of this incident.

An engineering evaluation was performed as required by LC0 3.4.6 and it was concluded that the RCS remains acceptable for continued operation.

Enclosed LER 82-008 addresses this incident.

There was no impact on the health and safety of plant personnel or the public as a result of this incident.

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

Sincerely, Enclosure: LER 82-008 cc:

A. E. Chaffee (USNRC Resident Inspector, San Onofre Units 2 & 3)

R. J. Pate (USNRC Resident Inspector, San Onofre Units 2 & 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 l