ML18227A431

Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/12/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification

ML18227A431
Person / Time
Site:	Turkey Point
Issue date:	06/25/1976
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/RGN-II
References
PRN-LI-76-164
Download: ML18227A431 (5)

Text

FLORIDA POWER & LIGHT COMPANY June 25, 1976 PRN-LI-76-164 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 251-76-5 TURKEY POINT UNIT 4 DATE OF OCCURRENCE: JUNE 12, 1976 LOW BORON CONCENTRATION

.The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9.2 to provide prompt notification of the subject occurrence.

Very truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement, (40)

Director, Office of Management Information and Program Control (3)

HELPING BUILD FLOR ID A

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LlCENSEE EVENT REPORT CONTROL BLOCK: SE PRINT ALL REQUIRED INFORMATION) 6 UCENSEE UCENSE EVENT NAME UCENSE NUMBER TYPE TYPE IQD>] P4c T P S 4 0 0 0 0 0 0 0 0 0 4 1 1 1 ~01

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.7 89 ,,14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT DATE REPORT DATE

~01 OON'T 'P Z, 0 6 1 2 7 6 0 6 2 5 7 6 7 8 57 58 59 60 61 68 69 ~

74 75 80 EVENT OESCRIPTION Jog ha the b ron concentration of the boron 7 8 9 80 in'ection tank B):T and the "B" boric acid stora e tank BAST) weri 7 8 9 80 toO4J below the Technical S ecification limit of 20,000 ppm. This had 7 8 9 80

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7 8 9 iscus d in 80

[OO~] Re ortable Occurrence 251-76-4. Corrective action was to initiate a 7 8 9 PFOM E 80 SYSTEM, CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER

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E V A L E X D 0 2 5 10 11 12 17 47 CAUSE OESCRIPTION tOOI Dilution of the Unit 4 B):T was caused by inleakage from the RWST via the 7 8 9 80 tOOI B):T inlet and outlet isolation valves. Since the BIT was bein re-7 8 9 80 s o diluted.

7 89 80 IH8 7

FACUTY STATUS kJ 9

FORM OF ACTIVITY 10 COATENT

~0% POWER 12 13 OTHER STATUS N A 44 METHOO OF DISCOVERY 45 46 OISCOVERY DESCRIPTION N A 80 RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE I?~I L~j LiJ N/A N/A 7 8 9 10 11 44 45 80 PEFISONNEL EXPOSURES 7

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89 NUMBER 11 TYPE z

12 13 OESCRIPTION N A 80 PERSONNEL INJURIES NUMBER OESCRIPTION I?4] LOOooJ N A 7 8 9 11 12 80 PROamLE CONSEOUENCES N

7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE OESCRIPTION

~z N A 7 89 10 80 PUBLICITY N A 7 89 ~ 80 AOOITIONAL FACTORS'I See a e 2 for continuation of Event Descri tion and Cause Description.

7 89 80 7 89 80 M. A. Scho man PHONE 305 552-3779 CPO ddI e ddT

"REPORTABLE OCCURRENCE 251-76-5 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (continued) shutdown in accordance with Administrative Procedure 103.8 and to commence adding a concentrated boric acid solution to the tanks.

The boron concentration of the tanks was returned to within specification and normal operation was resumed., (251-76-5).

Cause Descri tion (continued)

Maintenance was performed on the inlet isolation valves to stop the leakage. Leakage past the outlet isolation valves was stopped by isolating the leakoff line from those valves.

Similar cases of BIT dilution have occurred, however, this was the first occurrence attributable directly to leakage past the isolation valves. Also, a situation in which cross dilution occurred between a BIT and a BAST was previously discussed in report 251-75-12.

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