ML20151X364

Revised Page 3-4 to Attachment 3 to Deficiency Rept Re Traversing in-core Probe Nitrogen Purge Line Isolation & RWCU Sys Mods.Detailed Review of Potentially Overloaded Embedments Continuing & Will Be Completed Prior to Restart

ML20151X364
Person / Time
Site:	Fermi
Issue date:	01/30/1986
From:	Jens W DETROIT EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
VP-86-0009, VP-86-9, NUDOCS 8602120382
Download: ML20151X364 (2)

Text

-

r ,

Wayne H.Jens

%ce Presedent Nudear Operahons -

Fermi-2 6400 North Ome Hghway P M 48 66 Nuclear

. (3 ) t Operations January 30, 1986 VP-86-0009 FMCMTY ROUTIN3

/f:-sti ScmL Mr. James G. Keppler (cd $f, ::

Regional Administrator f? diL gugstv83 AN Region III 6 U. S. Nuclear Regulatory Commission  !$f dL ""

799 Roosevelt Road Glen Ellyn, Illinois 60137 FILE _s6d'

Reference:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Response to Request for Information Pursuant to 10CFR50.54(f)

Subject:

Revised Page Please replace the attached page in Attachment 3, page 3-4 of Reference 2) due to an inadvertent omission in the original transmittal.

Sincerely,

[

Attachment cc: Mr. P. M. Byron Mr. M. David Lynch Mr. G. C. Wright USNRC Document Control Desk Washington, D. C. 20555 86021203G2 860130 ADOCK 05000341 PDR g PDR FEB 3 1986

[

l(

A ctncarvativa caslysis hrd basa parformed to idsntify thcos cabedments chich pctcutiolly cculd ba overloaded. However ' subsequent detailed review of

the potentially overloaded embedments is on going and will be completed prior to restart.

, 9. Traversing In-Core Probe (TIP) Nitrogen Purge Line Isolation Recent correspondence from the NRC reveals the TIP nitrogen purge line should conform to General, Design

~

l-Criteria 56 (GDC56). An interim design to meet the intent of GDC56 is being implemented which incorporates two QAI seismically-mounted ball valves outside containment. This change will be installed prior to starting-from the present outage.

10. Rame tor Unter Cleanun Svaten Modifications 2

i.

i' During initial operations, numerous unnecessary

- Reactor Water Cleanup System (RWCU) isolations occurred. These isolations have been attributed primarily to the Steam Leak Detection System and to the differential flow (Leak Detection) isolation signals. Instrument and control modifications were 4 made on this system to prevent recurrence of the problem and to provide the operators Control Room j'~

information.

f i

+

t c

3 -4 s

, . _ _ . . _ ,_ _ _ __ __ _ _ _ _ , _ _ . . . _ _ ~ . . _ _ . . , . . _ _ , - _ _ . . _ . . _ . - - , _ _ __ ,