ML20151D640

Notice of Violation from Insp on 880511-0610.Violation Noted:Failure to Follow Procedures for Storage of Compressed Gas Cylinders & to Provide Adequate Operability Insps on Unit 1 post-accident Containment Ventilation Filter Unit

ML20151D640
Person / Time
Site:	Farley
Issue date:	07/07/1988
From:	Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151D625	List: ML20151D623 ML20151D640 ML20151D653
References
50-348-88-19, 50-364-88-19, NUDOCS 8807250187
Download: ML20151D640 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Alabama Power Company Docket Nos. 50-348 and 50-364 Farley 1 and 2 License Nos. NPF 2 and NPF-8 During the Nuclear Regulatory Commission (NRC) inspection conducted on May 11 -

June 10, 1988 violations of NRC requirements were identified. The violations involve the failure to: adequately inspect and maintain safety related equip-ment; conduct an adequate 10 CFR 50.59 Safety Evaluation, and, failure to follow procedures. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violations are cited below:

A. 10 CFR 50 Appendix B Criterion X states in part that a program for inspection of activities affecting quality shall be established and executed to verify conformance with documented instructions and drawings for accomplishing the activity. Farley's Operations Quality Assurance Policy Manual, chapter 10, states in part that inspections shall be performed to insure quality of safety related activities with inspections i performed in accordance with documented instructions and check lists to assure substandard items do not remain undetected.

Contrary to the above, adequate inspections to verify operability of the Unit 1 post accident containment ventilation filter unit were not l performed in that on May 9, 1988, five of eight bolts to the carbon fill l port coverplate and two of four bolts to a blank flange were found loose. l l

This is a Severity Level IV violation (Supplement 1). l B. 10 CFR 50.59 authorizes the licensee to make changes in the facility as described in the safety analysis repwt unless the change involves a ,

change in the technical specifications or an unreviewed safety question. )

Contrary to the above, during the 1988 Unit i refueling outage, the l licensee replaced the individual battery powered emergency light units inside Unit 1 containment with an emergency lighting system supplied from two redundant uninterruptible power supply units which are located outside '

containment. However, the licensee failed to perform an adequate evalua-tion to determine if this change resulted in a change to the safety analysis  ;

report. The new emergency lighting system for the Unit 1 containment is an improvement over the previously installed system but does not conform to the system description in the Final Safety Analysis Report (FSAR).

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

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Alabama Power Company 2 Docket Nos. 50-348 and 50-364 Farley 1 and 2 License Nos. NPF 2 and NPF-8 C. Technical Specification 6.8.1 requires that applicable written procedures recommended in Appendix A of Regulatory Guide (RG) 1.33, Revision 2, 1078 shall be established, implement and maintained.

Procedure 0-SHP-122. Storage and Handling of. Compressed Gas Cylinders, requires gas cylinders to be firmly secured with wall brackets, chains, rope or other adequate restraints.

Contrary to the above; on May 28, 1988, one span gas oxygen cylinder at Unit I hydrogen recombiner and three span gas cylinders at Unit 2 hydrogen recombiner were not secured to prevent mechanical damage. These cylinders were too large for the available storage racks and were not secured in place.

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

Pursuant to the provision of 10 CFR 2.201, Alabama Power Company is hereby required to subinit 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, Farley, 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 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 will be achieved. Where good cause is shown, consideration will be given to extending the response time. 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.

FOR THE NUCLEAR REGULATORY COMMISSION )

David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor. Projects Dated this Matday Atlanta of J, 4 Georgia 1988 j 1

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