ML20237D591
| ML20237D591 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/16/1987 |
| From: | Warnick R NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20237D587 | List: |
| References | |
| 50-445-87-30, 50-446-87-22, NUDOCS 8712240061 | |
| Download: ML20237D591 (2) | |
See also: IR 07100104/2012001
Text
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APPENDIX A
NOTICE-OF. VIOLATION.
1
TU Electric
Dockets:
50-445/87-30
50-446/87-22
Comanche' Peak Steam Electric Station
Permits:
CPPR-126
Units l'and 2,1 Glen' Rose, Texas
CPPR-127
.During an NRC inspection conducted on' November 4 through-
December 1, 1987," violations of NRC requirements were identified.
In accordance with the'" General Statement of Policy and Procedure
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for'NRC' Enforcement Actions," 10 CFR Part.'2, Appendix C.(1987), the'
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. violations are listed-below:
A.:
Criterion III of Appendix B to 10 CFR Part 50- as implemented
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by Section 3.0, Revision 3, dated July 31, 1984, of the
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TU' Electric Quality Assurance Plan (QAP), requires in part,
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that measures must be established to assure.that applicable
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regulatory requirements and design bases, as defined in
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Part 50i2.and as specified in the license application, for
those structures, systems and components to which this
appendix applies, are. correctly translated into specifica-
tions, drawings, procedures, and instructions.
The design
control measures must provide for verifying or checking the
adequacy of design, such as by the performance of design
reviews, by:the use of alternate or simplified calculational
methods, or by the. performance of a suitable testing program.
In addition, design changes, including field changes, must be
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subject to design control measures commensurate with those
applied'to the original design.
Contrary to the above, the NRC inspector identified two
capacitors' connected in parallel with a relay coil located in
both Unit 1 emergency diesel generator control panels that
were not shown on facility electrical drawings nor described
in any associated documents.
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This is a Severity Level IV violation (Supplement II)
(445/8730-V-06).
B..
Criterion V of Appendix B to 10 CFR Part 50, as implemented by
Section 5.0, Revision.3 of the TU Electric QAP dated July 31,
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1984, requires that activities affecting quality shall-be
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prescribed by and accomplished in accordance with documented
instructions, procedures, or drawings of a type appropriate to
the circumstances.
8712240061 871216
ADDCK 05000445
Q
POR
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2
Paragraph 2.1.3 of TNE Procedure TNE-DC-7, Revision 16,-dated
February 14, 1986, " Preparation and Review of Design
Drawings," requires that completed drawings shall be checked
for accuracy and compliance.
Paragraph 2.1.4 also requires an
engineering review for technical accuracy upon completion of
the drafting / design check.
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Contrary to the above, drawings were not appropriately
reviewed / checked for accuracy as evidenced by the differences
which existed between the two sets of electrical sc'aematic
drawings for the emergency diesel generator control panels.
Examples of these differences were most evident in the
circuitry for solenoids 6A and 6B and relay contact numbers
and arrangements (i.e., RX/1B and 10X) on Drawings
09-500-76001, Sheet 3 and TNE-El-0067, Sheet 96.
This is a Severity Level IV violation (Supplement II)
(445-8730-V-07).
Pursuant to the provisions of 10 CFR 2.201, TU Electric is hereby
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required to submit a written statement or explanation to the U.
S.
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Nuclear Regulatory Commission, ATTN: Document Control Desk,
20555 with a copy to the Assistant Director for
Inspection Programs, Comanche Peak Project Division, Office of
Special Projects, within 30 days of the date of the letter
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transmitting this Notice.
This reply should be clearly marked as a
" Reply to a Notice of Violation" and should include for each
violation:
(1) the reason for the violation if admitted, (2) the
corrective steps that have been taken and the results achieved,
(3) the corrective steps that will be taken to avoid further
violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in
this Notice, an order may be issued to show cause why the license
should not be modified, suspended, or revoked or why such other
action as may be proper should not be taken.
Consideration may be
given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION
SYf OdAnt4$k',
Dated at Comanche Peak Site
this 16th day of Dectnber, 1987
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