ML20207A093
| ML20207A093 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 04/20/1987 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| TAC-64236, NUDOCS 8704230655 | |
| Download: ML20207A093 (4) | |
Text
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Docket No. 50-285 April 20,1987 Mr. R. L. Andrews Division Manager - Nuclear Production Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102
Dear Mr. Andrews:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS (TAC NO, 64236)
In conducting our review of your December 23, 1986 submittal relating to the Fort Calhoun Station Unit No. 1 auxiliary feedwater system reliability analysis, we have determined that we will need additional information identified in the enclosure to continue our review.
In order for us to maintain our review schedule, your response is requested within 30 days of your receipt of this letter.
The enclosure was telecopied to your staff on March 23, 1987.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Please contact me at (301) 492-9410 if you have any questions concerning this letter.
Sincerely, Walt
. Paulson, Pro ect Manager Pro 1ect Directorate - V
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PDR IV, V and Special Pro;ects P
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page DISTRIBUTION 9^t4He.
PD4 Reading D. Crutchfield F. Schroeder F. Miraglia OGC E. Jordan B. Grimes J. Partlow W. Paulson P. Noonan ACRS ( 0)
J. cniv PD 1 t File
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PD4/LA*
P PD4/DIIg PNoonan W ulson JCalvo 4/20/87 4/6/87 4/2o/87
Docket No. 50-285 Mr. R. L. Andrews Division Manager - Nuclear Production Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102
Dear Mr. Andrews:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION OF AUXILIARY FEEDWATER SYSTEM RELIABILITY ANALYSIS (TAC NO. 64236) i In conducting our review of your December 23, 1986 submittal relating to the Fort Calhoun Station Unit No.1 auxiliary feedwater system reliability analysis, we have determined that we will need additional information identified in the entlosure to continue our review.
In order for us to maintain our review schedule, your response is requested within 30 days of your receipt of this letter.
The enclosure was telecopied to your staff on March 23, 1987.
l The reporting and/or recordkeeping requirements contained in this letter l
affect fewer than 10 respondents; therefore, OMB clearance is not required l
under P.L.96-511.
l Please contact me at (301) 492-9410 if you have any questions concerning this letter.
Sincerely, Walter A. Paulson, Project Manager l
Proiect Directorate - IV l
Divl sion of Reactor Pro;'ects - III, l
IV, V and Special Pro;'ects
Enclosure:
Request for Additional l
Information cc w/ enclosure:
See next page l
DISTRIBUTION U~ocket File NRC PDR Local PDR PD4 Reading D. Crutchfield F. Schroeder L
F. Miraglia OGC l
E. Jordan B. Grimes J. Partlow W. Paulson P. Noonan ACRS(10)
I PD Plant File
/3dPD4/LA PD4/PM PD4/D
()4/2f/87 PNoonan WPaulson JCalvo l
4/ /87 4/ /87 l
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Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District Unit No. I cc:
Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles 8. BrinksIn, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avedue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Ofrector for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert Director Division of Radiological Health p
Department of Health 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509
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Request for Additional Information Fort Calhoun Station, Unit No. 1 Auxiliary Feedwater System Reliability Analysis 1.
Please provide basis for assuming that plant-specific data developed for Calvert Cliffs is applicable to Fort Calhoun.
In particular, are there test and maintenance data to support the use of a failure probability for a turbine driven pump that is an order of magnitude smaller than the generic value?
2.
Please provide the test intervals for each component.
In particular, provide valve stroke and position checks for all of the valves, especially the valves on the auxiliary feedwater injection path that are not necessarily tested during the monthly pump tasts.
3.
Your analysis included failure to restore valves to the proper position after maintenance but did not include equipment unavailability due to equip-ment being out-of-service during maintenance. Was this an omission or do plant practices or maintenance data indicate that this is a negligible contributor to component unavailability?
4.
Your fault tree indicates that valves FCV-1101, FCV-1102, HCV-1103, and HVC-1104 close on a loss of main feedwater and must be reopened to use the main feedwater lines as injection paths for the AFWS. Please confirm that this is correct.
5.
Please provide a listing of power sources for the AFWS components. This listing should include the AC or DC power supplies for the A0Vs and MOVs, the DC control power source for the pumps, and the source of power for the motor driven pump upon loss of offsite power.