ML20042A555
| ML20042A555 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 03/02/1982 |
| From: | Sherwood G GENERAL ELECTRIC CO. |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-PT21-82 CAC-19-82, MFN-028-82, MFN-28-82, PT21, NUDOCS 8203230551 | |
| Download: ML20042A555 (3) | |
Text
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GENERAL ELECTRIC COMPANY.175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 682, (408) 925-5040 MFN 028-82 CAC 19-82 March 2,1982 4
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U.S. Nuclear Regulatory Commission
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Office of Inspection and Enforcement 6-UI"a rr 8-MW $$[A 4
Washington, DC 20555 D
Attention:
Richard C. DeYoung N
oT Gentlemen:
SUBJECT:
10CFR PART 21, REPORTABLE CONDITION RHR DESIGN DOCUMENTATION ERROR This letter advises the NRC of a reportable defect per 10CFR Part 21 as reported to W. Mills of your office by Charles A. Cameron, Manager of Safety Evaluation Programs on March 2, 1981.
Attached is the report of the defect, which is an error found in a document released by GE to the i
utility for fabrication.
The affected plant is Hartsville A1.
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General Electric has informed the Tennessee Valley Authority of the defect and has advised them of the appropriate corrective action taken by GE.
Very truly yours, Glenn G. Sherwood, Manager Nuclear Safety and Licensing Operation GGS: rf/102N3 Attachment cc:
R. C. DeYoung, NRC (two extra copies)
J. P. O'Reilly, NRC Region II-U. Potapovs, NRC Region IV L. S. Gifford, General Electric cois ga G203230551 820302
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REPORTABLE CONDITION RHR DESIGN DOCUMENTATION ERROR I.
Description of Deficiency The reportable defect is an error found and corrected in a document released for fabrication for Hartsville A1, a TVA Project.
The error is the statement of a 0.63" diameter orifice requirement in the fabrication specification, instead of the actual required diameter of 6.31".
It was found while performing a normal ongoing review of the containment design to assure its conformance with GE containment requirements.
The error was discovered and corrected after the drawing was released for fabrication, but before the hardware was fabricated and installed in the plant.
II.
Analysis of Safety Implication The system affected by this error is.the RHR discharge line to the containment pressure suppression pool.
The purpose of the orifice is to create the correct flow and velocity from the RHR discharge line to promote circulation and mixing.
In the unlikely event of a LOCA the consequence of this error, had 3
it not been detected by the Design Review or in preoperation test, could have been the overpressurization of the containment.
The use of a 0.63" diameter orifice in the discharge line would cause a severe reduction in the RHR heat removal capability from the suppression pool.
In fact, if the orifice had been fabricated with the incorrect orifice diameter, it would have been detected immediately during preoperation testing.
Therefore, the potential overpressurization of the containment could not have happened.
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This type of defect is reportable when it is found in a basic component after the component has been accepted by the purchaser, and the defect could cause a substantial safety hazard.
Specifically the. erroneous specification had been accepted for fabrication.
Although the likelihood for such an error to go undetected is very small,_it is reportable under 10CFR Part 21.
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