ML19350C904
| ML19350C904 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 03/04/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19350C897 | List: |
| References | |
| 50-369-81-03, 50-369-81-3, NUDOCS 8104100149 | |
| Download: ML19350C904 (2) | |
Text
.-
O APPENDIX A NOTICE OF VIOLATION Duke Power Company Docket No. 50-369 McGuire Nuclear Station License No. NPF-7 s
As a result of the inspection conducted on January 1, 1981 - February 4, 1981 and in accordance with the Interin Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified.
A.
Technical Specification 6.8.1 requires in part that written procedures be established, implemented, and maintained for surveillance activities of safety-related equipment. Technical Specification 4.9.4.1 requires in part that each containment penetration providing direct access Irom the contain-ment atmosphere to the outside atmosphere be verified closed or exhausting through the containment purge and ventilation system within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of core alterations.
Contrary to the above, prior to January 30, 1981, no written procedure existed to verify containment integrity during core alterations, and none was implemented prior to start of core alterations on January 28.
This is a Severity Level V Violation (Supplement I.E.).
B.
Technical Specification 3.9.4.c requires that during core alterations, l
containment penetrations providing direct access from the containment atmosphere to the outside atmosphere be closed by an isolation valve, blind
- flange, or manual valve, or be. exhausting through operable Containment Purge and Ventilation system HEPA filters and charcoal absorbers.
Contrary to the stove, on January 30, 1981, valves 1-VX-40 and 1-VX-41, containment air sample line valves were found open, and the pipe cap was not in place.
f This is a Severity Level V Violation (Supplement I.E.).
C.
10 CFR 50 Appendix B Criterion V requires that activities shall be accomplish-ed in accordance with instructions. Design Engineering Quality Assurance Manual in section HPR-130, " Mechanical System / Restraint Design Drawings, Field Revisions" specifies in paragraph 2.3 and 3.2 the process by which field revisions to structural restraint design drawings are to made.
Contrary to the above, Design Engineering issued structural restraint drawing MC-AA-3730 (RO) for restraint RIO of MC 1683-VI.22 with the notiation "No Structural or Hardware Changes between MC-1683-VI.22-R10 (R6) and MC-AA-3730 (RO)" when in fact an additional sway bar had been added.
810.4100 %
l. _ _ _ _ _.._ _ ____ __._ __ _ _.. _.. -_ -_ __ _ - - - _
~. _... _ _
I 7
)
Notice of Violation Docket No. 50-369 Duke Power Company License No. NPF-9 This is a Severity Level V Violation (Supplement I.E.).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required l
to submit to this office within twenty-five days of the date of this Notice, a j
written statement or explanation in reply, including:
(1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective l
steps which will be taken to avoid further violations; and (5) the date when j
full compliance will be achieved.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
MAR 0 41991 l
Date:
l 1
i
- 1 I
.I I
i l
(
1 e
9 1
l f
I
\\
I l
i I
J i
. *e e-iwe,, -, -....%%,,
,w,.
7, w-.
p--,-. -,
m_,,-,,,,.r.-,
,m-,_nm-,.
m.-.,,
m.--
mmwy-
- - -, -