ML19322A876
| ML19322A876 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/23/1973 |
| From: | Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| 50-269-72-01Q, 50-269-72-1Q, NUDOCS 7911270633 | |
| Download: ML19322A876 (2) | |
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i U. S. ATOMIC ENERGY C0!CIISSION
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REGION II DIRECTORATE OF REGULATORY OPERATIONS
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RO Inquiry Report No.:
50-269/73-1Q Licensee: Duke Power Cc=pany Power Building 422 South Church Street Charlotte, North C Jolina 28201 License No.: DPR-38 Facility: Ocenee 1 Descriptive
Title:
Secondary System Water Quality hn<_,
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Prepared By:
A4e F. Jape, React 6r Inspector Date Facilities Test and Startup Branch A.
Date and Manner AEC Was Infor ed:
Mr. J. E. Smith, Oconee. Plant Superintendent, advised R. F. Warnick, Region -II Principal Inspector, by telephene of the incident en March 10, 1973, at about 1:00 p.m.
Follovup informaticn was obtained by F. Jape, Region II Inspector, by telephone from J. E. Smith en March 20, 1973.
B.
Descriptien of Pa-ticular Event or cireurstance:
Two callons of 50% NaOH vere mistakenly used in place of NH 0H in the 3
che:dcal mix tank which was used to adjust the "A" steam generator feedvater pH.
The error was discovered approxi=a.nely 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after it was..ade.
A sample of the feedvater taken at 10:00 a.m. cn Manh 9, 1973, revealed the concentration of NaOH vas 35 p;n and the pH vas 11.
The te=perature of the water during the event was not greater than 80*F.
C.
Action by Licensee:
It was decided to drain.and refill the steam generator with vater of the proper quality..:1 raining began at 1:05 p.m. and vas ec=pleted by 12:00 p.m. en March 9, 1973 A sa=ple taken after the stea= generater vss filled had 2.7 ppm Ns0H. DPC decided t, drain and refill a second b
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RO Inquiry Ept. Uc.
50-269/73-1Q time. Ris was completed by h:30 a.m. en March 10, 1973, and a sample at that time had 0.77 ppm HaOH.
In addition to the draining and refilling of the water in the steam generator, the storage arrangement of the chemicals has been modified to prevent a recurrence.
The licensee has stated that there was essentially no da= age to the reactor coolant boundary and is, therefore, not a reportable incident.
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