ML19332C809
| ML19332C809 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/22/1989 |
| From: | Warnick R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332C807 | List: |
| References | |
| 50-445-89-76, NUDOCS 8911290028 | |
| Download: ML19332C809 (2) | |
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I APPENDIX A
%v NOTICE OF VIOLATION-t' i
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TU3ElSctric Docket:
50-445/99-76 Comanche Peak-Steam Electric' Station.
Permit:
CPPR-126
, Unit;1,-Glen; Roue, Texas R
[During an NRC inspection conducted on> October 4 through November 7, L
- 1989,) violations.of NRC' requirements were identified.. In accordance l
l iwith the " General Statement of Policy and ProcedureLfor NRC
' Enforcement Actions," 10 CFR Part.2, Appendix C (1989), the
- violations are listed'below
A.-
Criterion V of Appendix B to 10 CFR 50 which is implemented by 0
Section?5.0,. Revision.0 of the TU Electric Quality Assurance Manual (QAM) states " Activities affecting quality shall be prescribed by.' documented instructions, procedures, or drawings, of a type appropriate to the circumstances and thall be
-accomplished'in accordance with these' instructions, procedures,
.or-drawings.
' Paragraph 6.16.7 of Brown & Root (B&R) ASME Construction Procedure-ACP-11.5, " Component Support Fabrication'and 1
Installhtion" states, in part, "Due to field conditions, it may be necessary to make-a relative' angle adjustment between the, snubber end cap and mounting hardware.
All adjustments
-of this type shall be' performed in accordance with the following instructions.
Contrary.to the above, the NRC inspectors identified two snubbers, CC-1-051-006-A43K and CC-1-043-010-A43K, which had-
-not been adjusted in accordance with the above-proceduro.
-This is a Severity Level IV violation (Supplement II)
(445/8976-V-01).
.B.
Criterion V of Appendix B to 10 CFR 50, which is implemented by i
Section 5.0, Revision 0 of the TU Electric Quality Assurance Manual (QAM), states " Activities affecting quality shall be prescribed by documented instructions, procedure, or drawings, of a. type appropriate to the circumstances and shall.be-accomplished in c:cordance with these instructions, procedures, or drawings."
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Specification 2323-MS-100, Revision 10, Appendix D, paragraph-3.11.c states', in part, that ".
. studs shall.be a l,;
-minimum of: flush with the top of the nut face."
Contrary:to'the above,-one stud was underengaged. approximate.y' 1/8-inch on.its associated-nut on flange No. 1, Valve 1-8010A,-'
isometric drawingtBRP-RC-1-RB-028B.
I This'is a Severity Level-IV violation (Supplement II)-
(445/8976-V-02).
Pursuant to the provisions of 10 CFR 2.201, TU Electric is hereby-L required to submit a. written statement or explanation to the U. S.
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= Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC. 20555,.with a copy to the Assistant Director for Inspection Programs, Comanche Peak Project Division, Office of LNuclear' Reactor Regulation, within 30 days of'the date of the letter
-transmittin7 this Notice.
This reply should.be clearly marked as a
" Reply to a Notice of Vialation" 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, (311the 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 mayLbe-issued to show cause why the license-should not1be modified, suspended, or revoked or why such other
. action as may-be proper should not be taken.
Where good cause is
-shown, consideration will be given to extending the response time.
C FOR THE NUCLi'AR REGULATORY COMMISSION.
OJWt th?
- Dated.at Comanche Peak Site this 22nd day of November 1989 2
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