ML20204E557
| ML20204E557 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/23/1986 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, Lear G Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-86-62 NPNPD-86-293, VPNPD-86-293, NUDOCS 8608010131 | |
| Download: ML20204E557 (2) | |
Text
- - _ _
1 Wisconsin Electnc eow couem 231 W. MICHIGAN. P.O. BOX 2046, MILWAUKEE, Wl 53201 (414)277-2345 July 23, 1986 VPNPD-86-293 NRC-86-62 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regu.,i. tion U.
S.
NUCLEAR REGULATORY COMMISSION Washington, D.C.
20555 Attention:
Mr. George Lear, Director PWR Project Directorate No. 1 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 NOTIFICATION OF POISON ASSEMBLY REMOVAL FROM THE SPENT FUEL STORAGE RACKS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 As required by Point Beach Nuclear Plant Technical Specification 15.6.9.2.B, notification is hereby provided of our intent to remove two poison insert assemblies from the spent fuel storage racks.
These poison insert assemblies will be cut open, and the encapsulated boraflex (borated rubber) sheets will be examined to determine their material condition.
Immediately after each assembly is removed from the spent fuel storage racks, a replacement poison insert assembly, manufactured to original material and appropriate dimensional specifications, will be installed.
This process will be accomplished under a special maintenance procedure which will control the movement and location of spent fuel away from the area while the poison inserts are being replaced.
Testing of the neutron attenuation capability of the poison insert assemblies being replaced was done at the time of fabrication and installation.
The neutron attenuation capability of the replacement poison insert assemblies will be equivalent to that of the assemblies being replaced.
This is ensured by the imposed quality control and associated documen-tation on the material and fabrication of the replacement poison insert assemblies.
The material for the replacement assemblies will be identical to the material used in the fabrication of the original poison insert assemblies, including boraflex with t
l a minimum boron carbide (B C) content of 37.1 weight percent.
g l
Accordingly, the neutron attenuation testing discussed in l
jo l e
8608010131 860723 PDR ADOCK 05000266 PDR p
e I
July 23, 1986 Page 2 Technical Specification 15.6.9.2.B is not considered to be applicable and therefore will not be repeated.
In summary, we plan to remove and examine the poison insert assemblies in August 1986.
Since the poison insert assemblies will be immediately replaced, there is no need for an interim change to the applicable technical specification requirements.
We will notify you of the results of our examination.
If you have any further questions, please contact us.
Very truly yours, b[
Ok.
Fay [
C.
W.
Vice President Nuclear Power bjm Copy to NRC Resident Inspector l
l t
l l
I 1
1 l
l