ML20244C973

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Notice of Violation from Insp on 890201-0315.Violation Noted:On 890127,AI-58 Not Properly Implemented in That Clearance 1-189A Did Not Adequately Establish Clearance Boundaries for Maint Work to Be Done on Unit 1 Valves
ML20244C973
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/06/1989
From: Verrelli D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20244C969 List:
References
50-324-89-05, 50-324-89-5, 50-325-89-05, 50-325-89-5, NUDOCS 8904210085
Download: ML20244C973 (2)


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l-ENCLOSURE NOTICE OF VIOLATION-Carolin'c Power and Light Comoany ;Docke't Nos. 50-3'25 and 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 During -the Nuclear Regulatory Commission (NRC) inspection conducted on February 1 - March 15, 1989, violations of NRC requirements were identified.

o 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. Technical . Specification .6.8.1.a requires the licensee to implement written procedures as recommended by Appendix A of. Regulatory Guide 1.33, November 1972. Appendix item A.3, Equipment Control, requires procedures for l

clearances.

Administrative Instruction (AI)-58, Equipment Clearance Procedure.

Revision 25, Section 4.1'.2.3.3.c requires that' Clearance Tag Sheet, Attachment- C, be filled out for each valve which is to be manipulated during the maintenance work indicating location (valve number). N/A is to be marked in the " Tag No." column to indicate that a clearance tag is not-required.

AI-58, Section 4.1.2.3.5 requires that equipment be in a safe condition to perform the work when valves are positioned according to Clearance Tag Sheet, Attachment C.

< Al-58, Section 4.1.4 requires that individuals accepting a clearance verify that tags have been properly placed on components as necessary. tc place equipment in a safe condition.

Contrary to the above, on January 27, 1989, AI-58 was not properly implemented in that, clearance 1-189A, which was prepared and goroved by operations personnel and accepted by maintenance personnel, did not adequately establish the clearance boundaries for maintenance work to be done on the unit 1 C41-F010 and C41-F014 valves. In addition, Attachment ~ j C to clearance 1-189A did not list valves C41-F010 and C41-F014 as valves i to be manipulated during the maintenance activity. The improper I clearance, manipulation of the valves, and subsequent maintenance, resulted 'in an inadvertent draining of approximately 450 gallons from the Unit 1 Standby Liquid Control System Tank.

This is a Severity Level IV violation (Supplement I) applicable to Unit 1 only.

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Carolina Power and Light Company 2 Docket Nos. 50-325 and 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 l

. B. Technical Specification 6.8.1.f requires that written procedures be established and implemented covering the fire protection program implementation. Periodic Test (PT)-34.11.2.1, Rev. 6, Portable Fire Extinguisher Inspection, Reactor Buildings 1 and 2, implements inspection of fire extinguishers. PT acceptance criteria 6.0.1.7 states that, "For a dry chemical portable extinguisher to be acceptable, the pressure gauge reading must fall in the acceptable range."

Contrary to the above, PT-34.11.2.1 was not implemented in that, on l March 8, 1989, two dry chemical portable extinguishers were verified acceptable while undercharged.

This is a Severity Level V. violation (Supplement I) applicable to Unit'2-only.

Pursuant to the prov'isions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit-to this office within thirty days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including (for each violation): (1) admission or denial of the violation, .(2) the reasons for the violation if admitted (3) the corrective steps which have been taken and t;ie 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.

FOR THE NUCLEAR REGULATORY COMMISSION st bw Dav'd M. rrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects Dated at Atlanta, Georgia this day of April 1989

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