ML20207J979
| ML20207J979 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/24/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| 0613V, 613V, GN-1010, NUDOCS 8607290309 | |
| Download: ML20207J979 (3) | |
Text
w Georgia Pbwer Company Fbst Offica Box 28.2 W:yncsborn Georgia 30830 Telephone 404 554-9961 404 724 8114 Southern Company Services. Inc.
Pbst Office Box 2625 b
Birmingham, Alabama 35202 Telephone 205 8704011 VOgtie Project July 24, 1986 Director of Nuclear Reactor Regulation File: X3BL01 Attention:
Mr. B. J. Youngblood Log:
GN-1010 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 1:
EQUIPMENT QUALIFICATION
Dear Mr. Denton:
Pursuant to our responses on July 10, 1986 to the SQRT and PVORT audit concerns, we have corrected two typographical errors involving AP and WCAP 8687. The revised pages are attached.
)
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, l.
1, J. A. Bailey
/
Project Licensing Manager JAB /sm Attachment xc; R. E. Cec.ny Clarke Kido R. A. Thomas B. Jones, Esquire J. E. Joiner, Esquire G. Bockhold, Jr.
B. W. Churchill, Esquire D. C. Teper M. A. Miller (3)
W. C. Ramsey Jag Singh L. T. Gucwa Vogtle Project File 0613V hCK05000424 09 860724 f
E PDR i
i 1
B.
Feedwater pump speed control vs. programmed setpoint (which is a A P feedwater-to-steam pressure) is verified for power levels up to 100%.
C.
Steam generator level control to transients is verified during several different tests. These transients cover recovery from low to high level conditions and plant transients to load swings, load rejections, and plant trips.
Trending of the equipment's functional-characteristics will be performed through the ISI Program. In the case of check valves, if degradation has occurred the information will be trended and the disassembly and inspection frequency will be increased if necessary.
3.
Paragraph 1 discusses the velocity needed to fully hold open the disc of the MFW check valve at 100% power. Whenever the auxiliary feedwater pumps are used for startup, shutdown or hot standby modes the steam generators are fed through the auxiliary feedwater lines, thus bypassing the MFW check valves. The potential for disc chatter exists between low power and 100% power operation. Check valves capable of the wide range of flows needed for the main feedwater system requirements, and without any potential for check valve chatter would be difficult to procure if not impossible to design.
For Vogtle, the tilting disc style of MFW check was selected due to water hammer considerations. Its integral disc design has advantages over the bolted disc regarding possible disc failure.
The MFW check valves are nelected based on 100% power operations, designed to consider water hammer and located to satisfy other overriding safety considerations.
All check valves within the scope of the IST program are tested at regular intervals. Those check valves required for containment isolation receive a leak rate test. Other check valves receive a flow rate test.
If the system configuration does not allow for a flow rate test, the valves are disassembled and inspected for degradation on a staggered basis.
Safety-related check valves outside the scope of the IST program are disassembled and inspected for degradation on 36 month intervals.
In both cases, any degradation will be documented on the maintenance work order. These work orders are reviewed to determine if the potential for a common mode failure exists.
r
~
a The test was performed on both multi-stage vertical high head and low head safety injection pumps. These pumps were purchased by Westinghouse from Pacific on Westinghouse P.O. 546-AAV-236990. The Pacific Pump S.O. Nos. were VN 49752/54, and pump serial Nos. were 51696 and 51701. The pumps were installed in a flow test loop as shown on Figure 1.
Instrumentation included flow measurement, fluid pressure, temperature, pump head, and pump vibration.
A pre-test and post-test inspection were performed on the pumps.
Each pump was first tested on cold clean water to establish baseline performance. The pumps were then subjected to the thermal transient and foreign particle test. The test foreign. particle concentration was 92 PPM and was made up of the following constituents:
Concrete and Glass 60 PPM Asbestos and Fibers 20 PPM Paint Chips 12 PPM The pumps were operated in the hot condition until temperature stabilization resulted. The flow loop was then cooled to initial cold conditions and data retaken, Figure 2.
The change in hydraulic performance was less than 1% (part of which could be attributed to instrument error and data repeatability).
Pump shaf t and casing vibration levels did not change throughout the tests.
The disassembled pumps showed no signs of adverse wear nor did the mechanical seal exhibit leakage before, during or after the test.
PVORT Comment 8 Provide documentation which demonstrates 1 year post-accident operating time for Namco limit switches covered by WCAP 8687-H03A/H06A. Furthermore the TRS does not envelop the input motion requirement at low frequency range.
GPC Response The aging temperature used by Westinghouse for post-accident simulation was 2500F as shown in figure 23 of WCAP 8687 Supp 2 - H03A/H06A (Rev. 2).
This temperature was selected for the NAMCO limit switch qualification. Using this aging temperature and activation energy of 0.8 ev the Arrhenius equation was applied to the curve in figure D-8 of WCAP 8587 Appendix D from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 1 year in small increments of time. The required aging times to simulate these small increments are then summed to yield a total test time of 12.7 days to simulate 1 year post-accident operation. The actual post-accident test time was 13 days.
Concerning the seismic input motion, WCAP 8687 - Supplement 2 (H03A/H06A) paragraph 3.3.3.3 states that line mounted valve accessories are seismically tested by the single frequency test method. The peak input acceleration for the SSE is 4.0g in each of three mutually perpendicular axes. The peak input acceleration for the OBE is 3.2g in each of three mutually perpendicular axes.
The required input motion curve on Figure 21 (attached as Figure 3) is not correctly labeled.
Since the required seismic input levels are defined in paragraph 3.3.3.3 of the test report the RIM curve on Figure 21 is not necessary and will be revised during the next routine revision as shown in Figure 4.
.