ML20092N402
| ML20092N402 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/25/1984 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| EF2-62810, IEB-79-26, NUDOCS 8407030096 | |
| Download: ML20092N402 (3) | |
Text
a W;yne H. Jins i
Etear p tions WI
~
g
$EoI7/ENa"n*UEas June 25, 1984 (3' 3HS*"
- EF2-62810 Director.of Nuclear Reactor Regulation
-Attention:
Mr.
B. J.
Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Youngblood:
Reference:
(1)
Fermi 2 NRC Docket No. 50-341 (2)
NUREG-0798, Fermi 2 Safety Evaluation Report, Supplement 3, dated January 1983 (3)
NRC IE Bulletin 79-26 " Boron Loss from BWR Control Blades", Revision 1, dated August 29, 1980 (4)
NRC Inspection Report 83-09, May 23, 1983
Subject:
License Condition'for Control Blade Stress Corrosion Cracking Reference 2 identified a license condition which would require surveillance of control blades to identify and quantify stress corrosion cracking and boron depletion.
Detroit Edison requests that the proposed license condition not be included, since Edison has established a program to inspect and replace control blades, when necessary.
This program has been reviewed and deemed acceptable by the NRC in accordance with the closure of IE Bulletin 79-26 as noted in Reference 4 (Attachment 1).
IE -Bulletin 79-26 identified a concern addressing a failure mode Sor control blades, identified by GE, which resulted in a loss of boron-10.
The boron would leach out through-cracks at tube locations with more than 50 percent local boron-10 depletion.
Operating plants were requested to both analyti-cally determine the boron depletion in the upper quarter of i(
sw l
m
g-0}.
.g Mr.
B. J. Youngblood June 25 1984 EF2-62$10 Page 2-every control blade, and perform a destructive examination of the most highly exposed control blade and document the loca-tion of cracks in the blade.
Fermi 2 responded to this bul-letin by developing Reactor Engineering Procedure 57.000.09, Core Component Management Guidelines, which requires the replacement of control blades when a 10 percent reduction of rod worth occurs (i.e., a. 34 percent average boron-10 deple.-
tion in the top quarter segment).
This position was reviewed and accepted.by the NRC via Reference 4.
Detroit Edison believes that the requirements of IE Bulletin 79-26, Revision 1, are satisfied by the procedure cited
.above, and requests that the condition set forth in SER Supplement 2 not be included in the license on this basis.
If you have any questions concerning this submittal, please contact Mr. O. Keener Earle at (313) 586-4207.
Sincerely, l
700 id*4 cc:. Mr.
P.
M.-Byron Mr.
M.
D.
Lynch USNRC, Document Control Desk Washington, D.
C.
20555
~~
Attach; rent 1 i
Excerpt frcm NRC Inspection Report 83-09
(-
I&E Bulletin No. 79-24 (CLOSED) " Frozen Lines:" Review of DECO internal meno dated October 16, 1981 states that this bulletin not applicable to Termi. The subject of freezing environmental effects was transmitted on l
their docket by NRC Question 212.27 which was satisfactory.
This bulletin is considered closed.
I&E Bulletin No. 79-26 and ' Revision 1 (CLOSED) 8' Boron Loss From BWR Control Blades:" Review of DECO letter dated January 9,1981 (EF2-51,583) subject as above stating that the licensee plans to discharge blades when they have reached 34% boron-10 depletion in the upper quarter. It also planned to to track boron depletion by computer calculation, which should prove adequate.-
l This bulletin is considered closed.,
j r
I&E Bulletin No. 79-27 (OPEN) " Loss of Non-Class-1-E Instrumentation and Control Fower System BUS During Operation:" Review of DECO letter dated August 31, 1981 (EF2-54,384) to licensing project manager U.S. NRC.
l This bulletin remains open pending review by the Licensing Project Manager and his response to the licensee.
I I&E Bulletin No. 79-28 (CLOSED) "Fossible Malfunction of NAMCO Hodel EA180 Limit Switches at Elevated Temperatures:" Review of DECO letter subject as above dated January 25, 1980 (EF2-47,811) stating that design 9
engineering has determined that the referenced Model NAMCO switch has not i
been specified, purchased or installed on any present designs. Existing I
valve monitoring circuits employ NAMCO Model EA-740 limit switch which is l
c4em operated compared to the latch operated EA-180. Current and j
potential valve suppliers have by design based their valve position j
indication on the use of can operated swtiches.
l l
\\
This bulletin is considered closed.
I I&E Bulletin 80-03 (CLOSED) " Loss of Charcoal from Standard Type II, 2 Inch, Tray Adsorber Cells:" A visual inspection was performed by the licensee to determine rivet spacing and screen casing separation, which could lead to loss of charcoal from the charcoal adsorbers. The licensee has determined that charcoal adsorbers are used for three applications on site. Control center HVAC Emergency Makeup and Recirculating Air Filter i
Unit, and Standby Cas Treatment System Air Filter Units were inspected for rivet spacing and screen / casing separation and determined by the licensee to be adequate. The reactor pressu a vessel head purging unit i
has not been designed and the licensee has constitted to review design prior to construction of unit.
This bulletin is considered closed.
I&E Bulletin No. 80-06 (CLOSED) " Engineered Safety Feature (EST) Reset i
Controls:" Review of the licensees records, indicates that a reset of an F.SF actuation signal at Fermi 2, for those systems described in the j
i
\\
l
-