ML20205A358

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Provides Addl Info to Support NRC Review of Inservice Testing Program Relief Request 11 Re Current ASME Section XI Vibration Amplitude Levels.Vendor Confirms That Degradation in Performance Would Result in Wear to Pump Impeller
ML20205A358
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 10/20/1988
From: Withers B
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
WM-88-0269, WM-88-269, NUDOCS 8810250483
Download: ML20205A358 (2)


Text

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LF CREEK W@ NUCLEAR OPERATING C

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Bart D. Wahors Proenews and l

Chef rsecutere OWeer October 20, 1988 l

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WM 88-0269 l

U. S. Nuclear Regulatory Commission ATTNt Docursent Control Desk Mail Station PI-137 Washington, D. C. 20555

Subject:

Docket No. 50-482 : Additional Information for Inservice i

Testing Program Relief Request Ce nt leme n t The purpose of this letter is to provide the additional information requested in a telecon on October 13, 1988 between Mr. T. Sullivan, NR(, and Mr.

K.

Petersen, Wolf Creek Nuclear Operating Corporation (WCNOC).

This additional information was requested to support the Staff review of the pump and Vcive Inservice Testing Prograra Relief Request No. 11.

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l A question was raised regarding the current ASME Section XI vibration amplitude levels.

Vibration amplitude for the fuel pool cooling pumps as measured per IWP-4500 is approximately 0.2 mil.

For these pu:sps,

the ASME Section XI Alert Range (High Value) would be 1 mil and the Required Action Range (High Value) would be 1.5 mil.

A comparison of the Section XI Alert and Required Action Range values with the ANSI /ASME OH-6 Standard concluded that for the fuel pool cooling pumps the Section XI values are more conservative.

In addition, a concern was raised regarding the potential failure mechanisins for pumps that would be characterized by a ten to 20 percent degradation in hydraulic performance without an associated rise in component vibration 1

identifying the developing failure.

Discussions with the fuel pool cooling pump vendor have concluded

  • hat this degradation in pe r fo rtsance would indicate significant wear to the pump impe Mer and wear rings with an associated balance induced vibration.

The vendor fully expected that the increase in vibration readings would exceed the alert limit of 1 mil for the fuel pool cooling pumps.

kk HOCK 403 091020 05000402 0

PNu h

3urington, KS 66839 i Phone. Q16) 3644431 an aeuw cwerwwy twere w ScwT g

,' VM h8-0269 Page 2 of 2 October 20, 1988 A copy of this response is also being provided to Mr. H. C. Rockhold of EG&G

Idaho, Inc.

If you have any questions concerning this submittal, please contact me or Mr.

O. L. Maynard of my staff.

Very truly yours.

h., -, J Bart D. Withers President and Chief Executive Officer B D'J/j ad cc B. L. Bartlett ( NRC)

D. D. Chamberlain (NRC)

R. D. Martin (NRC)

T. K. McLellan (NRC)

D. V. Pickett (NRC), (2)

H. C.

Rockhold (EG5G) i

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