ML20009H438
| ML20009H438 | |
| Person / Time | |
|---|---|
| Site: | Hartsville, Phipps Bend  |
| Issue date: | 07/31/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8108100113 | |
| Download: ML20009H438 (2) | |
Text
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TENNESSEE VALLEY AUTHORITY g
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400 Chestnut Street Tower II July 31, 1981
I [ T 'l Ti 6,. 4 0 HTRD-50-518/81-15, -519/81-11,
-520/81-13, -521/81-11 p
g PBRD-50-553/81-16, -554/81-09 db Mr. James P. O'Reilly, Director
,,9 Office of Inspection and Enforcement
_ AUG 0 7 24, -
C U.S. Nuclear Regulatory Commission uA g Region II - Suite 3100 Q
N 101 Marietta Street Atlanta, Georgia 30303
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Dear Mr. O'Reilly:
HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - REPORTABLE DEFICIENCY -
RCIC STEAM LINE BREAK - HTRD-50-518/81-15, -519/81-11, -520/81-13,
-521/81-11, PBRD-50-553/81-16, -554/81-09 The subject deficiencies were initially reported to NRC-0IE, Region II, Inspector F. S. Cantrell on June 30, 1981 as NCR's HTA NEB 81-03, HTB NEB 81-04, and PBN NEB 81-02.
In compliance with paragraph 50.55(e) of 10 CFR Part 50, we ar? enclosing the first interim report on the subject deficiencies. TVA anticipates transmitting the next report on or before September 30, 1981. We consider 10 CFR Part 21 applicable to this nonconformance.
If you have any questions, please call Jim Domer at FTS 857-2014.
Very truly yours, TENNESSEE VALLEY AUTHORITY
((B ager Nuclear 9egulation And Safety Enclosure cc:
Mr. Victor Stello, Direccor Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 hN) i-Sh 8108100113 810731 PDR ADOCK 05000518 S
PDR An Equal Opportunity Employer
T' ENCLOSURE HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS RCIC STEAM LINE BREAK HTRD-50-518/81-15 -519/81-11, -520/81-13, -521/81-11 PBRD-50-553/81.-16,.-554/81-09 10 CPR PART 50.55(e) REPORT NO. 1 (INTERIM)
Description of Deficiency Due to a design deficiency, in case of an RCIC steam line rupture in the RCIC room, the residual heat removal 1-A (RHR-A) equiprent located in the RCIC room will be exposed to an environment for which it is not qualified.
Interim Progress GE is in the process of evaluating this deficiency to determine the necessary corrective action to prevent occurrence of the above-described events. GE has proposed to correct the. problem by adding a new normally closed valve to be located in the pipe chase between the steam tunnel and the RCIC pump room. This valve would be de powered with a one-inch bypass. The one-inch line would limit flow in the case of a downstream break. We are continuing our investigation into this matter and will supply a second report containing General Electric's corrective action by September 30, 1981.
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