ML20087L527
| ML20087L527 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1984 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20087L529 | List: |
| References | |
| LIC-84-052, LIC-84-52, NUDOCS 8403270249 | |
| Download: ML20087L527 (2) | |
Text
I Omaha Public Power District 1623 Harney Omaha, Nebraska 68102
)
402/536 4000 l
March 19, 1984 LIC-84-052 l
Mr. James R.
Miller, Chief U.
S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Miller:
Inservice Inspection and Testing Program Relief From ASME Boiler and Pressure Vessel Code,Section XI The Omaha Public Power District, on September 26, 1983, submitted the 1983-1993 Inservice Inspection (ISI) Program Plan to the Com-l mission.
Included in the plan was a list of all known exemptions l
required from the Section XI Code.
Attached to this letter are copies of replacement pages 1, 7,
8, 23, 29, and 50 of that sub-mittal.
The reasons and justification for changes and new ex-emptions are as follows:
(1)
Page 1:
The statements, " Class 3 portions of the Waste Dis-posal System have been optionally classified as Class 3 in accordance with Subarticle IWA-1300, Paragraph (g.) of the Section XI Code.
Examination in accordance with the rules of Article IWD will not be performed on the Class 3 portion of the Waste Disposal System.", have been added.
This option is provided for in the Winter, 1980 Addenda of the Section XI Code.
(2)
Page 7:
Item Bl.40 has been revised to allow for partial examination of the closure head-to-flange weld.
Location of the seismic skirt attachment lugs and the skirt itself is responsible for the limitations in access to the weld.
The current statement in the plan incorrectly implies complete inaccessibility.
(3)
Page 8:
Item B12.10 has been revised.
The District's posi-tion has been revised such that unless a reasonable and ac-curate method is found to perform volumetric examinations of the reactor coolant pump casing welds, a surface examination i
of the outside surface of the welds on one pump shall be per-formed before the end of the 1983-1993 inspection interval.
1 l
8403270249 840319 3Ument with Equal Opportunity d55'2d maienemate l )
PDR ADOCK 05000285 G
PDR l
r-b.
Mr.' James'R. Miller LIC-84-052 Page Two (4)
Page'23:
Subarticle exceptions to inlet pressure measure-ment and differential pressure measurement have been added.
Inlet pressure cannot be directly measured due to system de-sign.. Therefore, direct differential pressure measurement is also not possible.
F-(5)
Page 29:
Per changea on page 50, test frequency for HCV-240 and HCV-249 has been changed from quarterly to refueling out-age.
Page 29 provides the basis for this change.
Cycling these valves during operation would cause excess pressurizer spray, resulting in a reactivity excursion.
(6)
Page 50:
Same as above for page 29.
It is requested that the Commission replace the current version of these pages with the_ attached pages and consider these changes as part of the evaluation of the District's exemption requests for the 1983-1993 interval.
Sincere y, b0 IOvyve W. C. Jones Divisiop Manager-Production Operations
~
WCJ/DJM:jmm Attachments cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036.
Mr.
E. G. Tourigny, Project Manager Mr.
L.
A. Yandell, Senior Resident Inspector b'
f l
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