ML20214A449

Intervenor Exhibit I-ROREM-135,consisting of 860908 Memo Transmitting Nonconformance Rept 841 Re safety-related Cables

ML20214A449
Person / Time
Site:	Braidwood
Issue date:	09/10/1986
From:	Quaka T COMMONWEALTH EDISON CO.
To:	Kaushal N AFFILIATION NOT ASSIGNED
References
OL-I-ROREM-135, NUDOCS 8705190457
Download: ML20214A449 (6)

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SUBJECT:

Non-Conformance Reports Braidwood Station S & L Specification # A 798A In accordan e with Quality Assurance Procedure MLS-1, copies of 8./

NCR #

are being transmitted for review, information and resolution, if needed.

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Jones D. L. Shamblin E. L. Martin (excluding observations for BCAP NCRs)

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O Sheet 2 of 3 CECO NCR # 84l i

Item 9 (Continued)

And/or are in violation of training radius requirements; and/or are in i

violation of separation requirements; and/or are damaged,at cable grips.

SEE LWC. M 463) ( 4'?t] FOR. EXA>APLtE5 of PPtOBM.Qg,g Item 15 (Continued) support racks (Via ADI's) to resolve training radius and separation problems. In those cases where additional horizontals will not resolve the problem a field problem report (FPR) shall be initiated.

Inspect each cable for damage from the point where the cable leaves the pan to where it enters the riser (LKC-QC will inspect cables). Damaged cable shall be repaired per the attached guideline.

If the damage exceeds the guideline submit an FPR to Ceco for resolution.

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2 r, c c r ~ $'-f I PM-04 Exhibit 8 ME ON Page 1 of 2 CONSTRUCTION DEFICIENCY EVALUATION Revision 1 f

4 Part 1 DESCRIPTION i

Describe the oeficiency (Attach references) 1 l

sfAG.ICUS CABLsS RouTEb TH%& H' AJMS A22 A> u PR.0PER.LN n557?L M /s) CABLE W AA28 kJ V/OLt"TlQ A t

QF T A h /A))AJ G 2 6 Dfil.S W Qllf 2 E NoPA- %

A M JAJ (/roL>4*T*O d 0F ns:PARATu<b d LEQu s2EMEh7CS b s*Rs bA AA AtSt='b FT' l

1 CABLE /SR.PS-i i

4 Part 2 EVALUATION l

2A safety Ispect 4

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Does this deficiency, whether or not safety related, effect safe i

operation of this facility?

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28 significance I

j rEs no j

l Is there a significant breakdown in the 94 program? (This applies j

to those design and construction activities affecting the safety of i

plant operations, including activities such as design verification.

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inspection, and auditing.)

1 Are expenditures of $100,000 necessary to g,gggig structures, j

systems, components, into compliance with approved design?

i l

Are expenditures of $100,000 necessary to I,ggsig, structures, N

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systems, components into compliance with approved design?

I y

Are expenditures of $100,000 necessary to evaluate structures, i

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systems, components to assure compliance with the approved design? b I

l 12871 1

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Exhibit B P&g3 2 of 2 Revision 1 e

YES NO Is approved final design inadequate to assure compliance with SAR N

and construction permit?

1 During Installation / Testing is it apparent that a structure, system, X

component supplied by others can not meet the required performance Specifications and should be reported (10CFR21) other users? (i.e.

Potential Industry Deficiency)

)

Does Inadequate Management review / corrective action exist which N

I ignors significant adverse trends?

Do pre-operational or start-up test results determine a system that does not meet safety analysis report or technical specification requirements?

4 Part 3 REPORTABILITY OF 50.55e N0f!FICATION i

If the answer to part 2A is Yes and any answer in Part 28 is Yes, this deficiency shall be reported to Nuclear Regulatory Commission III Headquarters g

Items not reportable 1

1 1

.l Items reported to date NRC Region III 4

Evaluated / Reported by date 7"'I'M j

C6meonwealth Edison i

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12871

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