05000346/LER-1980-005, Forwards LER 80-005/03L-0

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Forwards LER 80-005/03L-0
ML19260D991
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/06/1980
From: Murray T
TOLEDO EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19260D992 List:
References
L80-06-1, L80-6-1, NUDOCS 8002120712
Download: ML19260D991 (2)


LER-1980-005, Forwards LER 80-005/03L-0
Event date:
Report date:
3461980005R00 - NRC Website

text

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TOLEDO e EDISDN February 6, 1980 L80-061 FILE:

RR 2 (NP-33-80-05)

Docket No. 50-346 License No. NPF-3 Mr. James G. Keppler Regional Director, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

Reportable Occurrence 80-005 Davis-Besse Nuclear Power Station Unit 1 Date of Occurrence: January 10, 1980 Enclosed are three copies of Licensee Event Report 80-005 with a supplemental information sheet whlch is being submitted in accordance with Technical Speci-fication 6.9 to provide 30 day written notification of the subject occurrence.

Yours truly, b. N /B W h d. @

Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station TDM/ljk Enclosure cc:

Mr. Victor Stello, Jr., Director Office of Inspection and Enforcement Encl:

30 copies LER 80-005 Mr. Normal Hailer, Director Office of Management Program Analysis Encl:

3 copics LER 80-005 1951 336 8009120 7/2.

THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MADISON AVENUE

'OLEDO. CHIO 43652

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-05 DATE OF EVENT: January 10, 1980 FACILITY: Davis-Besse Unit 1 Technical Specification late date exceeded on IDEh"rIFICATION OF OCCURRENCE:

ST 5011.01, " Boron Injection Flowpath Test", Section 6.1, Boric Acid Flowpath Heat Tracing The unit was in Mode 1, with Power (MWT) = 2765, Conditions Prior to Occurrence:

and Load (Gross ?NE) = 920 Description of Occurrence: On January 10,1980 at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the Technical Speci-fication late date was passed on the Boric Acid Flowpath Heat Tracing Weekly Surveil-lance Test, ST 5011.01, Section 6.1, with the maximum allowable extension. This required that the flowpath from the concentrated boric acid storage system be de-clared inoperable. This placed the unit in the action statement of Technical Speci-fication 3.1.2.2.a which requires the system be restored to operable status within to 1%

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot standby and borated to a shutdown margin equivalent O k/k at 200 F within the next six hours.

The test was started within the allowa-Designation of Apparent Cause of Occurrence:

traced temperature points did not meet ble time interval, however, three of the heatThis was due to the constant addition of either the acceptance criteria ofJ.105 F.

trace line to the primary or demineralized water through part of the boric acid heat Reactor Coolant System (RCS) for boron concentration control due to the station being Due to deficiencies in the design returned to power following a maintenance outage.

the addition of cold water reduces the temperature in the boric acid heat of this system, trace line below the minimum limit of 105 F.

The frequent addition of water to the RCS delayed the test long enough that it exceeded the maximum time interval.

There was no danger to the health and safety of the public Analysis of Occurrence:

The flowpath from the Borate <' Water Storage Tank (BWST) or to station personnel.

was operable.

Corrective Action

The boric acid heat trace test was successfully completed at 0905 Facility 11, 1980, removing the unit from the action statement.

hours on January(FCR)78-508 was written to look into the possibility of designing Change Request exchanger into the system to heat the water before it reaches the heat traced a heat portion of the pipe.

Previous occurrences were reported in Licensee Event Reports Failure Data:

NP-33-78-132, NP-33-79-15, and NP-33-79-ll5.

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LER #80-005