ML19317D311
| ML19317D311 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/25/1970 |
| From: | Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7911270474 | |
| Download: ML19317D311 (3) | |
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UNITED STATES ATOMIC ENERGY COMMISSION 2
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DIVISION oF COMPLIANCE 4
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- 3 7 AT LANT A. GECRGI A 30303 June 25, 1970 J. P. O'Reilly, Chief, Reactor Inspection and Enforcement Branch Division of Cc=pliet.ce, Headquarters INQUIRY MEMORANDUM - DUKE PCWER CCXPETY (CCONEE UNITS 1, 2 AND 3), LICENSE NOS. CPPR-33, 3h AND 35, ::CCKET NCS. 50-2o9, RIO AND 237 Cn June 23, 1970, J. R. Wells, Principal Field Engineer, Cconee Nuclear Station, during a telephone conversation relating to a forthecming site in-spection, advised C. E. Murphy, Reacter Inspector, Region II, that the li-censee had made the decision to change suppliers for the main coolant pumps for the Oconee units. This change is particularly significant since the pump volutes for Unit 1 have already been velded into the primary coolant system. The following additional information relative to this change was
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given to the inspector.
The original pump supplier was the Bingham Pump Company.
D.e pumps were being supplied as part of the nuclear steam supply system which were pur-chased from Babcock and Wilcox Company. The pump motors were purchased I
directly by the licensee from Westinghcuse Elecuric Corporation. Although the details have not been verked out, the new pu=ps vill be supplied by Westinghouse.
i According to *a* ells, Bingham Pu=p Company had net been able to resolve the engineering problems associated with the failure of the pump seals and bearings during testing. The attached data sheet taken frem the FSAR gives the significant operating parameters of the 31nghen pumps.
Wells advised the inspector that the licensee planned to start cutting the pump casings frca the Lnit i piping next veek. At present, he did net.have schedule informatien available, but that the licensee was verking to =inimize he effect of this change on the plant schedule.
He stated that he vould
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attempt to have full details available for tk inspector the week of June 29, 1970.
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- a. C. Seidle CO:II:CEM Senior Eeactor Inspector Enclesure:
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Data Sheet 4
1911270 l$
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J. P. O'Reilly June 25, 1970 ec w/ encl:
E. G. Case, DES (3)
P. A. Morris, DRL R. S. Boyd, DEL (2)
R. C. DeYoung, DRL (2)
D. J. Skovholt, LRL (3)
P. Howe, DRL (2)
L. Kornblith, Jr., C0 R. W. Kirkman, 00:I
- 3. H. Grier, C0:III D. I. Walker, C0:IV R. W. Smith, CO:V FIG Files i
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w-Table 4-7 Reactor Coolant Pump - Design Data J
(Data per Pump)
Design Pressure / Temperature, psig/F 2500/650 Hydrotest Pressure, psig 3750 RPM at Nameplate Rating 1190 Developed Head, ft 396 Capacity, gpm 88,000 Seal Water Injection, gpm 50 Seal Water Return, gpm 46 Injection Water Temperature, F 125 Cooling Water Temperature, F 105 Pump Discharge Nozzle ID, in.
28 Pump Suction Nozzle ID, in.
28 Ovehall Height (Pump-Motor), ft-in.
09-4 Dry Weight Without Motor, Ib 108,300 Coolant Volume, ft 98 Pump-Motor Moment of Inertia, lb-ft 70,000
,3 Motor Data v
Type Squirrel Cage Induction Single Speed, Water Cooled Voltage 6600 Phase 3
Frequency, Hz 60 Insulation Class F
Starting Current, amp 4350 Power, HP (Nameplate)-
9000
.h v
4-44