ML20112G370

Amends Response to NRC Ltr Re Unresolved Item Noted in Insp Rept 50-341/84-68.Corrective Actions:Fsar Figures 7.3-10, Sheets 1,2 & 3 Will Be Revised to Reflect Implementation of Fmr S-1109

ML20112G370
Person / Time
Site:	Fermi
Issue date:	03/01/1985
From:	Jens W DETROIT EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
EF2-70448, NUDOCS 8504010086
Download: ML20112G370 (4)

Text

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. t Coyne H.,hs -

Veo President Nuclear Operations kh (

6400 North Drxne Hghway Newport, Mchgan 48166

< i j sam 0 March 1, 1985 EF2-70448 Mr. James G. Keppler Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road

-Glen Ellyn, Illinois 60137

Reference:

(1)

Fermi 2 NRC Docket No. 50-341 (2)

Letter, W. H. Jens to J. G.

Keppler, February 22, 1985, EF2-70400

Subject:

Detroit Edison Amended Response Unresolved Item 50-341/84-68-02 This letter amends Detroit Edison's response to Unresolved Item 50-341/84-68-02.

The changes to the previous response, Reference 3,_are. identified by a revision bar in the right hand margin.

We trust _this letter satisfactorily responds to the unresolved issue: cited in the inspection report.

If you have' questions regarding this matter, please. contact Mr.-Lewis Bregni, (313) 586-5083.

Sincerel f

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M.. Byron R. C. Knop C. C. Williams

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NRC Document-Control Desk Washington, D.C.

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r THE. DETROIT EDISON COMPANY FERMI-2 NUCLEAR; OPERATIONS ORGANIZATION RESPONSE TO-NRC UNRESOLVED ITEM NO. 50-341/84-68-02 DOCKET NO. 50-341 LICENSE NO. CPPR-87 INS'PECTION AT:

FERMI 2, NEWPORT, MICHIGAN p

INSPECTION CONDUCTED:. DECEMBER 19-20, 1984

. JANUARY 3-5, 1985 JANUARY 10-12,_1985 9

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-R'ESPONSE~TO.NRC INSPECTION REPORT NO. 50-341/84-68 s

UNRESOLVED ITEM-84-68-02 1&un l inspector reviewed P&ID 6M721-2089,' Revision K, and other. electrical drawings (discussed below) and observed the followingLdiscrepancies:

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Fermi 12.FSAR figuresi7.3-10' sheets 1,_2, and 3 do not

. appear.to reflect the-implementation of FMR.S-1109

' dated. March 115, 1979.

'(2).'It appears that the correc.t reactor low water level 2

interlocks are not used -in the MSIV. isolation. logic (Ref.Jdrawin's[6I721'-2095-141& 15,: Revision C).

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..(3) xColor/ code discrepancies. exist between the drawings 1 listed;in-the; brackets., (6I721-21-16

.;[ sic-6I721-2155-16] and'17, Revision C, and 26I721-2282-55, 60, 65, an'd 70, Revision F. )

'(Ref.

DCP-B2100-IO5.and. IO6, - IDCN-442, IRMR-1087 ~ and 3DCN-5990.'). It appears.that some of theireferenced

design change documents we're not properly and j

completely: implemented.'

RESPONSEJTO UNRESOLVED ITEM 84-68-02 (1) _ Detroit _ Edison made an effort;to keep the FSAR updated

during-the_ construction phase..FSAR Figure 7.3-10, sheets 1, 2, and 3,'" Nuclear Boiler System FCD" are

covered under/ Interfacing Procedure' 11.000.121, "FSAR and1ER Amendments."This-procedure.provides for1 annual f-

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updates of the FSAR_beginning two years after~the s

operatingLlicense_is issued.

. Typically, however, there.

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?is a1significant. delay in the inco'rporation of-changes l-into.FSAR-drawings issued:and> maintained by General Electric if'the change-is,not initiated by GE.

.This is the case with FMR S-1109.

To' alleviate this problem,

~ Detroit Edison will;obtain the mylars for these drawings and will maintain these. drawings 1 internally.

The revised drawings willLbe annotated to show that-the

~?GE issued drawings are'being maintained _by-Detroit Edison.- FSAR Figure 7.3-10:is being revised,by 3

'FCN-84-579 which is scheduled.to be incorporated by

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? July,.1986.

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-' RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68

RESPONSE TO' UNRESOLVED ITEM 84-68-02 (Continued) 51 0,;

. (2); Th'e: Inspector reviewed Revision C of drawings-26I721-2095-14 and 15.

Revision F was effective at theitime'of thexinspection.

Detroit Edison has not1been.able'to determine how:the inspector was M

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' supplied'with the superceded drawing.

g J-ETheidesign shown'on' Revision C utilized C71A-KlA

- contacts luand 2 -(water : level :2) in.the interlock

' circuit. : Revision F,.which was in1effect at the time R4 Tof-inspection,:shows:a: design that1 utilizes relay e"

~ C71A-K260Ac-contacts.(water level 1);in'the. interlock 7l circuit.

The signal for the C71A-K260A contacts -is supplied by;a' wide range. level _ transmitter (B21-N081A).

}which is capable of and does'supplylsignals for relays p-

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activated by both reactor waterclevels:1 and 2.-

The reactor low water slevel interlocks 1shown on Revision-F of' drawing _ 6I721-2095-14 and 15 are. correct.s s

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l(3)TheJinspectorsl observations concerning color. code x

discrepancies are correct.

These'particular color code.

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- ;discrepanc'ies exist because,an acceptable alt'ernate g'.

-cable type =was used due'to material ~ availability when

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the' cables were installed.

In;this' case,'. Cable Code

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No.K119 was; substituted for-No. 111.

DCN-5990, which -

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L. documented the change,. corrected the cable color on-the Lpull.cardiand. wiring ~ diagrams;6I721-2282-55, 60'andi70,~

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but failed;to change >the color'on schematics

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6I721-2155216 and 17.-

This_errorawas' corrected on-7 -

. Revision D~ of the schematic.exceptsfor: 2 cables which -

were again overlookedi 1 Cable. color.doesLnot affect the function of the s

'~. circuit;:however,.it:could have led to-confusion 1on the

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accordance with-theLelectrical and IEC as-built

'part"of: maintenance.or' operations. personnel.

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program,xa; Deviation / Event' Report (DER) was-used to Y

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_ jdocumentithis discrepancy.. This DER will be' posted against the' drawing to: prevent confusion until the

^drawingLis updated.

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