ML20132B031

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Notice of Violation from Insp on 850729-0802
ML20132B031
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 09/20/1985
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20132B015 List:
References
50-348-85-32, 50-364-85-32, NUDOCS 8509260081
Download: ML20132B031 (2)


See also: IR 05000729/2008002

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ENCLOSURE 1

tj0TICE OF VIOLATION

Alabama Power Company

Docket Nos. 50-343 and 50-364

Farley Units 1 and 2

License Nos. NPF-2 and NPF-S

The follcwing violations were identified during an inspection conducted on

July 29 - August 2, 1953. The Severity Levels were assigned in accorcance with

the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1.

Technical Specification (TS) 6. 5. 3.1.b requires that proposed modifica-

tions to plant nuclear safety-related structures, systems, and components

be approved by the Plant Manager prior to implementation. 10 CFR 50,

Aopendix B, Criterion III and the accepted Quality Assurance (QA) Program

(Final Safety Analysis Report, Chapter 17.2.3) collectively require that

desigm _ changes , including field changes to be subjected to design control

measu :s commensurate with those applied to the original design, and be

approved by the organization that performed the original design, unless the

licensee designates another responsible organization.

The accepted QA

program also requires that design changes and/or modifications will be

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handled in a manner which will comply with the requirements of ANSI

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Contrary to the above,. the licensee has failed to establish measures which

ensure the implementation of TS 6.5.3.1.b; 10 CFR 50, Appendix B, Criterion

III; the accepted QA program; and, ANSI N45.2.11-1974 in that procedure

FNP-0-AP-8, Design Modification Control, Revision 10 does not require that

minor departure from designs be approved by the plant manager prior to

implementation, and be controlled in a manner commensurate with the original

design.

This is a Severity Level IV violation (Supplement I.)

2.

Technical Speci fication 6.5.3.1.c requires that proposed tests and experi

ments which affect plant nuclear safety, and are not addressed in the Final

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Safety Analysis Report be approved by the plant manager before implementation.

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Contrary to the above, measures have not been established to ensure that the

requirements of TS 6.5.3.1.c are implemented in that procedure FNP-0-AP-1,

Development, Review and Approval of Plant Procedures, Revision 17 does

not address that the plant manager has to approve proposed tests and

experiments before implementation.

This is a Severity Level V violation (Supplement 1).

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Alabama Power Company

Docket Nos. 50-348 and 50-364

Farley Units 1 and 2

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License Nos. NPF-2 and NPF-8

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30

days of the date of this Notice, a 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 steps which will be taken to avoid

further violations; and (5) the date when full compliance will be achieved.

Security or safeguards information should be submitted as an enclosure to

facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)

or 10 CFR 73.21.

Date:

September 20, 1985

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