ML20086F885
| ML20086F885 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/26/1991 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-91-313R, NUDOCS 9112040031 | |
| Download: ML20086F885 (2) | |
Text
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 November-26, 1991 402/636-2000 LIC-91-313R U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mall Station Pl-137 Washington, DC 20555
References:
1.
Docket No. 50-285 2.
Letter from NRC (T. H. Novak) to OPPD (T. L. Patterson) dated September 27, 1991 3.
Letter from CE0G (J. J. Hutchinson) to NRC (C. A. Reed) dated September 27, 1991 (CE0G-91-531)
Gentlemen:
SUBJECT:
OPPD Review of Draf t AE00 Special Report, " Experience with Pump Seals Installed in Reactor Coolant Pumps Manufactured by Byron Jackson" As requested by the NRC, Omaha Public Power District (0 PPD) is providing its comments on the draft AE0D special report, transmitted by Reference 2.
Overall, the draft report is an accurate representation of OPPD's experience with reactor coolant pump (RCP) seals at Fort Calhoun Station (FCS). However, OPPD recommends that the following comments be incorporated in u.a final report:
Pjtqg location Comment 1.
3 first paragraph, Change "very high probability" to sentence 1:
" possibility".
2.
8 figure 3:
The schematic has holes drilled in the stationary face and backup ring.
FCS does not have these holes.
3.
13 Third paragraph, Add: "(5) relatively small RCP shaft diameter sentence 3:
results in a low seal surface velocity.
- Thus, the seal 'PV' is relatively low."
4.
25 Second paragraph, Change " injection" to " seal flush."
sentence 6:
5.
25 Second paragraph, Add: "(f) relatively small RCP shaft diameter sentence 8:
results in a low seal surface velocity.
- Thus, the seal 'PV' is relatively low."
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U. S. Nuclear Regulatory Commission LIC-91-313R Page 2 Since the August 1990 FCS RCP seal failure incident, OPPD has developed an improved method of safety wiring the first-stage pressure breakdown device capscrews.
OPPD believes that this new wiring technique will ensure that the lockwires do not work loose.
OPPD is planning to use this method when all four RCP seals are replaced during the 1992 refueling outage.
OPPD supports the position of the Combustion Engineering Owners Group (CE0G) on Generic issue 23 as stated in Reference 3.
OPPD recognizes the importance of RCP seal performance in maintaining plant safety and reliability.
As a result, OPPD has stringent requirements incorporated in procedures addressing RCP seal maintenance.
If you should have any questions, please contact me.
Sincerely, P
' A. ")ithy.
~
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/
W. G. Gates i
t Division Manager Nuclear Operations WGG/sel c:
LeBoeuf, Lainb, Leiby & MacRae R. D. Martin, NRC Regional Admiliistrator, Region IV T. M. Novak, Director Division of Safety Programs, AE00 D. L. Wigginton, NRC Senior Project Manager R. P. Mullikin, NRC Senior Resident Inspector J. J. Hutchinson, CE0G l
t i
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