On-line PWR RHR pump performance testing following motor and impeller replacement
On-line maintenance and replacement of safety-related pumps requires the performance of an inservice test to determine and confirm the operational readiness of the pumps. In 1995, major maintenance was performed on two Pressurized Water Reactor (PWR) Residual Heat Removal (RHR) Pumps. A refurbished spare motor was overhauled with a new mechanical seal, new motor bearings and equipped with pump`s `B` impeller. The spare was installed into the `B` train. The motor had never been run in the system before. A pump performance test was developed to verify it`s operational readiness and determine the in-situ pump performance curve. Since the unit was operating, emphasis was placed on conducting a highly accurate pump performance test that would ensure that it satisfied the NSSS vendors accident analysis minimum acceptance curve. The design of the RHR System allowed testing of one train while the other was aligned for normal operation. A test flow path was established from the Refueling Water Storage Tank (RWST) through the pump (under test) and back to the RWST. This allowed staff to conduct a full flow range pump performance test. Each train was analyzed and an expression developed that included an error vector term for the TDH (ft), pressure (psig), and flow rate (gpm) using the variance error vector methodology. This method allowed the engineers to select a test instrumentation system that would yield accurate readings and minimal measurement errors, for data taken in the measurement of TDH (P,Q) versus Pump Flow Rate (Q). Test results for the `B` Train showed performance well in excess of the minimum required. The motor that was originally in the `B` train was similarly overhauled and equipped with `A` pump`s original impeller, re-installed in the `A` train, and tested. Analysis of the `A` train results indicate that the RHR pump`s performance was also well in excess of the vendors requirements.
- Research Organization:
- American Society of Mechanical Engineers (ASME), New York, NY (United States)
- OSTI ID:
- 401986
- Report Number(s):
- NUREG/CP-0152; CONF-9607103-; ON: TI96013645; TRN: 96:005268-0020
- Resource Relation:
- Conference: 4. NRC/ASME symposium on valve and pump testing in nuclear power plants, Washington, DC (United States), 15-18 Jul 1996; Other Information: PBD: [1996]; Related Information: Is Part Of Proceedings of the 4th NRC/ASME symposium on valve and pump testing; PB: 719 p.
- Country of Publication:
- United States
- Language:
- English
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