ML20149G318
| ML20149G318 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/11/1988 |
| From: | Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20149G314 | List: |
| References | |
| 50-424-87-69, NUDOCS 8802180223 | |
| Download: ML20149G318 (3) | |
See also: IR 07100130/2012004
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ENCLOSURE 1
Georgia Power Company
Docket No. 50-424
Vogtle
License No. NPF-68
During the Nuclear Regulatory Commission (NRC) inspection conducted on
December 4,
December 14 - 18, 1987, and January 5,
1988,
November 30
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violations of NRC requirements were identified.
In accordance with the
"General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:
A.
10 CFR 50.49(a) requires that each holder of a license establish a prog am
for qualifying electric equipment.
10 CFR 50.49(b)(3) lists certain
post-accident monitoring system equipment as being important to safety.
10 CFR 50.49 paragraphs (f), (k), and (j), NUREG-0588, and IEEE 323-1974
require that:
1.
This equipment be installed in a manner and position equivalcat to
the as tested /as analyzed condition and;
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2.
Documentation be maintained to verify the equipment is qualified for
its application for the entire period during which the covered item
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is installed in the Nuclear Power Plant.
Contrary
to the above,
a Core Exit Thermocouple Junction Box
(post-accident monitoring instrumentation) in containment was left in an
unqualified environmental condition following system maintenance.
This
condition was identified on April 13, 1987, on MWO 18704972 which stated
that no documentation could be located to verify irsta'.lation of the
environmental seal for the junction box. The condition was not corrected
until October 10, 1987, following six months of power operation.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50 Appendix B Criterion V, and the licensee's accepted QA program,
Final Safety Evaluation Report (FSAR) Section 17.2.5, require that
activities affecting quality shall be prescribed by documented procedures
and shall be accomplished in accordance with these procedures.
The
licentec Deficiency Control Procedure, 00150-C, Revision 6, Sections 1 and
1.2,
require that conditions adverse to quality be identified and
processed oer this procedure.
Contrary to the above, problems involving main steam, chemical and volume
control, main feed, power operated relief valves, and post-accident
monitoring instrumentation systems were not identified as conditions
adverse to quality.
They were processed via the maintenance work order
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program rather than the approved deficiency control program. The specific
work orders are:
8802100223 080211
ADOCK 05000424
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ .
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Georgia Power Company
2
Occket No. 50-424
Vogtle
License No. NPF-68
MWO 18705430
MWO 18706938
MWO 18701732
MWO 18702035
MWO 18704972
This is a severity Level V violation (Supplement I).
C.
10 CFR 50 Appendix B Criterion XI, and the licensee's accepted QA program,
FSAR Section 17.2.11, collectively require that a test program be estab-
li'J.ed to assure that all testing required to demonstrate that systems
will perform satisfactorily in service is performed in accordance with
written test procedures. Additionally, Procedure SUM 22, Maintenance Work
Orders, Revision 16, Section 6.7.1, states that where applicable (dering
the preoperational phase), a functional test is required after maintenance
work to verify that systems are capable of performing their intended
function.
Contrary to the above, following preoperational modifications to the
turbine driven auxiliary feedwater (AFW) pump turbine speed indication
circuit under MWO 18620139, a functional test was not performed to verify
that this system would perform satisfactorily in service. The modifica-
tion placed an oversized resistor in the circuit which resulted in a loss
of AFW turbine speed indication in the control room and shutdown Panel C.
This condition was discovered three months later and was not repaired
until after two months of power operations.
This is a Severity Level V violation (Supplement I).
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Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby
required to submit a written statement or explanation to the Nuclear Regulatory
Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to
the Regional Administrator, Region II, and a copy to the NRC Resident
Inspector, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and
should include [for each violation]: (1) admission or denial of the violation,
(2) the reason for the violation, if admitted, (3) the corrective steps which
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Georgia Power Company
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Docket No. 50-424
Vogtle
License No. NPF-68
(2) the reason for the violation, if admitted, (3) the corrective steps which
have been taken and the results achieved, (4) the corrective steps which will
be taken to avoid further violations, and (5) the date when full compliance
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will be achieved. Where good cause is shown, consideration will be given to
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extending the response time.
If an adequate reply is not received within the
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time specified in this Notice, an order may be issutd to show cause why the
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license should not be modified, suspended, or revoked or why such other action
as may be proper should not be taken.
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FOR THE NUCLEAR REGULATORY COMMISSION
])W? W/lUbb
Caudie A. Ju ian, Chief'lt
Operations Branch
Division of Reactor Safety
Dated at Atlanta, Georgia,
this lith day of February 1988
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