ML20148H885
| ML20148H885 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/18/1988 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20148H876 | List: |
| References | |
| 50-456-87-38, 50-457-87-36, NUDOCS 8803300109 | |
| Download: ML20148H885 (3) | |
See also: IR 07100005/2012022
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CommonwealthEdisonC5mpan)
Docket No. 50-456
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Docket No. 50-457
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As a result of'the inspection conducted on Octt.ber 5 through December 22,'
1987, January 19 ' February 18 and 26,1980 and in accordance with 10 CFR Part 2,
,
Appendix C - General Statement of Policy and Procedure for NRC Enforces;nt
Actions (1987), the following violations were identified:
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10CFR50,AppendixB,CriterionV,asimplementedbyCommonwerlit6 Edison
4.
Company (CECc) Quality Assurance Manual, Nuclear Genera ting Stations,
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Section 5, requires that activities affecting quality be accomplished in
accordance with dccumented instructions, procedures, and drawirgs of a
type appropriate to the circumstances.
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Contrary to the above, the following examples of failure to follow
procedures or inadequate procecures were identified:
a. ' Electrical Lineup Operating Procedures Bw0P OG-El and E2 and
Mechanical Lineup Procedures Bw0P OG-M1 and M2 failed to include
certain vahas and other components required to correctly line up
the electrical and mechanical components of the Hydrogen Recombiner
'$ystem.
b.
Nine termination cards for cables in the Reactor Coolant (RC) system
had been signed and dated even though ti.e cables were still unplugged.
This is contrary to the latest desigr. drawings and to cable
termination procedure WI-4.3.9 which required that termination cards
be signed and dcted whenever a termination is completed.
c.
l.K.L. Q.C. Inspection Checklist of Electrical Termination for
cable RVA720, dated November 16, 1987, contained the wrong drawing
number and revision for the drawing referenced for this 1ctivity.
Also, the termination points noted in the remarks columt were points
in the Ur.it 1 panel rather than the Unit 2 panel.
Furthermore, the
cab M htermination card for the same cable, dated November 11, 1987,
referenced a wirinJ, diagram inat did not exist.
This is contrary
to the requirements of Braidwov Fox .No. 36, "QC Inspection
Checklist Instructions of Electrical Terminations," Procedure 4.8.9.,
Revision G.
This is a Severity Level IV vi61af.ic6 (Supplement I).
2.
10 CFR 50, Appendix B, Cdterion X, as implemented by Commonwealth
Edison Company (CECO) 4t alityr Assurance Manual, Nuclear Generating
Stations, Section 10, ragan%^ that "Inspection program will be
established to provide assutqnce that quality control . . .
inspections . .
are performed.
Qu ity Assurane
inspection and
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8803300109 880318
ADOCK 05000454
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testing will be conducted . . . to verify conformances to applicable
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drawings, instructions, and procedures as necessary to verify quality.
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Written procedures or checklists will be used to specify and verify
final inspections and tests."
Contrary to the above, the following examples of failure to assure that
quality control inspections were properly executed to verify conformance
to applicable drawings and procedures were identified:
a.
Connection diagram 20E-2-4089K, Revision J, and Engineering Change
Notice (ECN) No. 36345 required that the black and white conductors
of cable 2MS683, located in Remote Shutoown Par,al 2PL05J, be terminated
to T87-40 and 39, respectively.
However, the inspector found the
conductors of this cable terminated in reverse.
The latest Q.C.
inspector checklist for cable 2MS683, dated April 24, 1987, indicated
in Step 3.1.2 that the cable was inspected and found terminated per
the latest drawing and the ECN.
b.
The black conductor of cable 2MS286, terminated to T87 point 119
in Remote Shutdown Panel 2PLO5J was observed to be very loose (at
least three full turns).
This conductor is used to provide the
signal to close MSIV 2MS001B on an ESF actuation.
In addition, an
internal conductor installed by the licensee at point 1F on Auxiliary
Exhaust Fan OC control switch OHS-VA007 at panel 0PM02J was also
found to be loose.
The lated QC inspection checklists for the
cable and the conductor indicated that all lug connections were
found to be tight at the termination points and were acceptable.
c.
Safety related flexible conduit C2A17J8 routed to MSIV Junction
Box 2JB499A was observed to be in physical contact with a bare
section of an insulated chemical injection pipe.
The latest
inspection checklist applicable to thia installation, dated
March 25, 1987, indicated in Section 6.2.d., that the required
3" clearance between the pipe and the electrical flexible conduit
was satisfactory.
d.
The metal cover plates for diesel generator skid termination boxes
20G01KA and 20G01KA-P were observed to be unsecured.
Sixteen bolts
were missing from the cover plate for 2DG01KA while six bolts were
missing from the cover plate for 2DG01KA-P.
Also the backplate
inside 2DG01KA, which supports eight terminal blocks, was secured by
only one of four required bolts.
These deficiencies were not
identified or the Electrical Maintenance 0]partment Turnover Review
Checklist.
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The shields for instrument cables terminated to devices F82 and F83
in panels 2PLO75 and 2PL085 were bolted together, untaped, and
'idying inside the panel wireways.
The LKC inspection checklists for
these cables indicattid acceptable terminations even though no such
,
method of termination was available for review in the' applicable
procedures.
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This is a Severity Level IV violation (Supplement I).
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3.
10 CFR 50, Appendix B, Criterion XVI, as implemented by Commonwealth Edison
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Company Quality Assurance Manual Nuclear Generating Stations, Section 16,
requires that measures be established to assure that conditions adverse
to quality such as deviations, nonconformances, deficiencies . . . which
are adverse to quality and might affect the safe operation of a nuclear
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generating station are promptly identified and corrected.
Contrary to the above, the following example of failure to promptly
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correct identified deficiencies was identified:
Numerous examples were identified in which the nameplates and wiring
designations on safety related components such as junction boxes,
switches, MCC compartments, valves, cables, panel termination strips,
etc. . . did not conform to the latest dest
drawings.
The inspector
determined that the licensee had also ider..
- ed numerous deficiencies
with nameplates and designations during the t .gineering verification
conducted during the later part of 1986.
Certain of these deficiencies
were identical to those identified during this inspection.
No documented
evidence was available for review during this inspection to indicate that
corrective action had been initiated to resolve this issue.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this
office within thirty days of the date of this Notice a written statement or
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explanation in reply, including for each violation:
(1) corrective action
taken and the results achieved; (2) corrective action to be taken to avoir
further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
3//B St
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Dated
Hubert/ J. Miller, Director
DiviVion of Reactor Safety
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