ML20040C708
| ML20040C708 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Hartsville, Phipps Bend |
| Issue date: | 01/18/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8201290170 | |
| Download: ML20040C708 (2) | |
Text
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,.s TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNrSSEE 37401 400 Chestnut Street Tower II
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.i4,OFr January 18, 1982 HTRD-50-518/82-02, -519/82-02, 32 Jp, u,4h
-520/82-02, -521/82-02 6
PBRD-50-553/82-02, -554/82-02 O *J Q
OECElygg
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Mr. James P. O'Reilly, Regional Administrator g
U.S. Nuclear Regulatory Commission 9_^ g g, '
7199 4 j Region II - Suite 3100 e
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101 Marietta Street i
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
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IIARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - REPORTABLE DEFICIENCY -
POSSIBLE OUT-OF-PHASE TRANSFER OF EMERGENCY BUS FOR STRIDE -
HTRD-50-518/82-02, -519/82-02, -520/82-02, -521/82-02, PBRD-50-553/82-02, -554/82-02 The subject deficiency was initially reported to NRC-0IE, Region II, Inspector Ross Dutcher, on December 18, 1981 as NCR SDDR-CFB-31. In compliance with paragraph 50.55(e) of 10 CFR Part 50, we are enclosing our first interim report on the subject deficiency. We anticipate transmitting the next report on or before March 1, 1983 If you have any questions, please call Jim Domer at FTS 858-2725.
Very truly yours, TENNESSEE VALLEY AUTHORITY f].
ff L? M.' Mills.14anag'er Nuclear Regulation and Safety Enclosuro ec:
Mr. R. C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 82019.90170 820118 PDR ADOCK 05000518 i
An EquM Opportundy Employer Q} $g W '
,4 ENCLOSURE HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS POSSIBLE OUT-0F-PHASE TRANSFER OF EMERGENCY BUS FOR STRIDE 10CFR50.55(e) Report No. 1 (Interim)
HTRD-50-518/82-02, -519/82-02, -520/82-02, -521/82-02 PBRD-50-553/82-02, -554/82-02 Description of Eeficiency The STPIDE design of the emergency bus does not allow time for Jecay of residual voltage in the low pressure core spray (LPCS) pump motor before the emergency bus transfer from offsite power to diesel generator voltage.
Review of this design by GE/C. F. Braun has shown that in the case where a loss-of-coolant accident (LOCA) precedes a loss of preferred power (LOPP), the diesel generator will be running and ready to receive loads. When LOPP occurs, load shedding immediately takes place.
Reapplication of the bus voltage before the LPCS pump motor residual voltage on Division 1 Bus (RHR B on Division 2 Bus) has had a chance to decay presents the possibility of the pump motor being out of phase with the diesel generator which could cause the development of considerable stress in the LPCS pump motor shaft and resulting possible pump failure.
Although some equipment has been received by TVA, the accompanying software has not been released. Some modification to this equipment may be necessary.
Interim Progress GE/C. F. Braun is in the process of studying a design change to resolve this problem. GE/C. F. Braun has indicated that they will have this study co.npleted by the end of 1982. We are continuing our own review of this problem and anticipate supplying an additional report by March 1, 1983
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