ML17291B299
| ML17291B299 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/18/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9604240301 | |
| Download: ML17291B299 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 2055&4001 April 18, 1996 5'o-3'I 7 LICENSEE:
'Washington Public Power Supply System FACILITY:
MPPSS Nuclear Project No.
2
SUBJECT:
MEETING SUNNRY ADJUSTABLE SPEED DRIVES On April ll, 1996, personnel from the Mashington Public Power Supply System (the licensee),
and the General Electric Corporation, met with members of the NRC staff in Rockville, Maryland, to discuss the licensee's proposed change to the WNP-2 technical specifications (TS) to implement adjustable speed drives (ASDs) for the reactor recirculation (RRC) pumps.
A list of attendees is provided in Attachment 1.
The licensee provided a presentation of the history of use of ASDs in non-nuclear related applications in the U.S.
The presentation included discussion of several problems that were identified during the application of ASDs and how they were solved.
These problems included power fluctuations (voltage and current), voltage pulses caused by inverter firing, and electrical harmonics resulting from pulses from the ASD power system.
The presenter discussed the solutions that were implemented for these problems over the years.
The Ormond
.Beach plant in California incorporated the fixes for all the known problems, and has been operating successfully with ASDs since 1988.
The licensee then presented a discussion of the specific application of ASDs for the QNP-2 plant.
The licensee stressed that the ASDs were non-safety components.
The licensee discussed its on-site power distribution system, indicating that only the ASDs themselves are powered directly from their electrical bus.
All otlter loads are powered through transformers, which filter out a significant portion of the electrical harmonics.
The licensee presented their method of calculating total harmonic distortion (THD) on the electrical buses.
The licensee then provided a markup of the electrical distribution system that showed the results of their THD calculations for each of the electrical buses in the flow to and from the buses supplying the ASDs.
These calculations are provided in Attachment 2.
The staff questioned the licensee on application of Standard IEEE-519.
Specific questions included concern over voltage notches created by the ASDs, and the electrical distortion standard that recommends limiting THD to less than 5X.
The licensee indicated that voltage notches are filtered out by the transformers, and that no voltage notches were measured in the previous applications of ASDs.
The licensee also stressed their understanding of IEEE-519 as applicable to buses, and was not intended as an equipment standard.
The licensee considered that HGI-1987 is the appropriate standard for evaluation of equipment effects.
The staff then pursued the licensee's presentation of their calculations on the buses that showed THD above the IEEE-519 limit of 5X.
The licensee discussed the conservatism they considered to exist in their calculations.
In addition, the licensee discussed the test program they had run with the ASDs connected to an RHR pump motor, with measured THD on the bus supplying the ASDs in the 5-6X range, while THD 960424030f 9604f8 PDR ADOCK 05000397 PDR IIIIIIt'FILKI:MI'III~pj
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Washington Public Power Supply System Nuclear Project No.
2 cc w/atts:
Hr. G. 0. Smith WNP-2 Plant General Hanager Mashington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968 Chief Counsel (Hail Drop 396)
Washington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Hr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P. 0.
Box 43172 Olympia, Mashington 98504-3172 Hr. D. A. Swank (Hail Drop PE20)
Regulatory and Industry Affairs Mashington Public Power Supply System P.O.
Box 968
- Richland, Washington 99352-0968 Hr. Paul R.
Bemis (Hail Drop PE20)
Vice President, Nuclear Operations Washington Public Power Supply System P.O.
Box 968
- Richland, Mashington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 4 Pavilion 611 Ryan Plaza Drive, Suite 400 Ar lington, Texas 76011-8064 Chairman Benton County Board of Comnissioners P.O.
Box 69
- Prosser, Washington 99350-0190 Hr. R. C. Barr, Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 69
- Richland, Washington 99352-0968 H. H. Philips, Jr.,
Esq.
Minston 8 Strawn 1400 L Street, N.M.
Mashington, DC 20005-3502 Hr. J.
V. Parrish (Hail Drop 1023)
Chief Executive Officer 3000 George Mashington May Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352-0968
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9 Attachment 1
GT 8
PO SUPP SYST JUST S
J. Clifford B. Bateman
- 0. Chopra P. Gill B. Ruland JMMPSS D. Swank D. Koenigs G.
Freeman P. Steciuk J.
Wood B. Ross
~Bec t 1
J. Oliver P
C 1
T. Loomis
Attachment 2
MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM PROPOSED AMENDMENTTO IMPLEMENTADJUSTABLE SPEED DRIVES APRIL 11, 1996 HANDOUTMATERIALUSED AT THE MEETING
Attachment 2
MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM PROPOSED AMENDMENTTO IMPLEMENTADJUSTABLE SPEED DRIVES APRIL 11, 1996 HANDOUTMATERIALUSED AT THE MEETING
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Figure 6.3 Derating Factor Vs Harmonic Voltage Factor (EAT) 1.0 0.9 O
CJ tO LL p
0.8 Cl 0.7 0.6 0.02 0.04 0.06 0.08 0.1 0 Harmonic Voltage Factor (HVF)
MOTOR DERATING PER MG 1 - 1987 PART 17A V~ '
VN WHERE:
HVF=HARMONICVOLTAGE FACTOR VN = PER UNIT MAGNITUDEOF VOLTAGE FROM HARMONICSTUDY I5.= o.oo6 I13, = 0.048 I7.= o.oo6 I11
= oos4 I17,= o.oo4 I25
= 0.022 I19:= o.oo4 I23
= o.o3 I5'7'11'13'17'19'23'25' 7
11 13 17 19 23 25 HVF = 0.02269 HVF LIMITBEFORE MOTOR DERATING IS REQUIRED FROM FIGURE 17A-1 IS 0.03
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15010 IS02O 15700 25301 ASD MAX SPEE 25%
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e measured on the safety buses was approximately 0.3X.
The licensee considered this as evidence that the modification would not adversely affect safety-related components.
The staff questioned whether or not,the licensee had addressed the EPRI recommendations for protective devices.,
The licensee indicated that all the recommended protective device trips were incorporated in the WNP-2 design.
The staff questioned whether a pulse-torque analysis of the pumps and motors had been performed, and which components were affected most.
The licensee has performed the analysis, including evaluation of the rotor, stator, pump vanes and piping, and determined that the effects were so small, that nothing was significantly affected.
The licensee further stated that they would monitor for vibrations during testing following installation of the ASDs.
The staff then questioned if the licensee had performed a failure modes and effects analysis (FMEA), including for software.
The licensee had done a
FMEA, but did not include software in the analysis.
The licensee indicated that a
FMEA had been performed for another utility, specifically for loss of the notching removal circuit, and determined there were no effects above 40Hz.
WNP-2 will have permanent vibration monitors for the ASDs to monitor for the effects resulting from software failures.
The staff then questioned the licensee regarding their consideration of test results of ASDs at another facility that resulted in failure of the motor being run off the ASDs.
The licensee indicated that a study by GE had been performed of the failure, and the cause of the failure was not definitively determined.
The licensee did indicate that there was evidence the failure indicated potential ground-wall insulation failure, or high voltage waveform spikes, neither of which were characteristic of current source devices such as the ASDs.
At the conclusion of the meeting, the staff indicated that they considered the ASD modification acceptable, contingent on acceptable test results following installation of the ASDs.
No proprietary information was discussed or provided to the staff at the meeting.
Original signed by:
James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
'A Attachments:
l.
Attendance List 2.
Licensee's Handout cc w/atts:
See,next page DOCUMENT NAME:
WNP41196.MTS OFC PDIV-2 LA'DIV-2 PM NAME e
JCli ord 4 (96 DATE 4 lb 96 OFF CIAL RECORD COPY
T UT Docket File*
PUBLIC*
PDIV-2 Reading*
JClifford*
- KPerkins, WCFO*
wyatt WRusse11/FHiraglia RZimmerman (RPZ)
JHitchell, EDO JRoe EAdensam WBateman EPeyton ACRS*
OGC*
EJordan (JKR)
Heeting Participants
- Hard copies