ML20092N402

Requests That Proposed License Condition Requiring Surveillance of Control Blades to Identify & Quantify Stress Corrosion Cracking Be Dropped Since Util Established Program to Inspect & Replace Blades,Per IE Bulletin 79-26

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

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

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.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

id*4 700 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) l 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 been specified, purchased or installed on any present designs. Existing valve monitoring circuits employ NAMCO Model EA-740 limit switch which is i

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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

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