ML20246N827

Notice of Violation from Insp on 890515-19,0605-09 & 19. Violations Noted:Sampling Methodology Did Not Assure Representative Samples of Emergency Diesel Generator Fuel Oil Storage Tanks

ML20246N827
Person / Time
Site:	Hatch
Issue date:	08/18/1989
From:	Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20246N806	List: IR 05000321/1989008 ML20246N800 ML20246N827
References
50-321-89-08, 50-321-89-8, 50-366-89-08, 50-366-89-8, NUDOCS 8909080277
Download: ML20246N827 (2)

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ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321 and 50-366 Hatch Units 1 and 2 License Nos'. DRP-57 and NPF-5 During the Nuclear Regulatory Commission (NRC) inspection conducted on May 15-19, June 5 1989, and June 19, 1989, a violation of NRC requirements was identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violation is listed below with two examples:

10 CFR 50, Appendix B, Section XVI, Corrective Action, requires, in part', that measures shall be established to assure that conditions adverse to quality, such as failures ~, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

A. Sampling and analysis requirements for the Emergency Diesel Generator fuel oil storage tanks are specified in the Technical Specifications (Unit 1, section 4.9.A.2.d and Unit 2, section 4.8.1.1.2.c). The Technical Specifications for both units state that operability of the Emergency Diesel Generators shall be maintained "At least once per 92 days by verifying that a sample of Emergency Diesel Generator fuel oil from the fuel oil storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment." These fuel sampling discre-pancies were identified during a quality assurance audit conducted during November 1988, 88-MNT-2.

Cor trary to the above, sampling n ethods did not comply with methods described in ASTM D270-65, Sampling Petroleum and Petroleum Products, as required by Technical Specifications, in that the sample methodology did not assure representative samples of the Emergency Diesel Generator fuel oil storage tanks.

B. Section 9.5.4.5 of the Unit 2 Final Safety Analysis Report states that

" Samples of the fuel oil from all tanks are analyzed periodically to ensure that the fuel oil quality requirements of the Emergency Diesel Generator manuf acturer are met." Fuel oil specifications as stated in the vendor manual, Fairbanks-Morse, include requirements for viscosity, carbon residue, sulphur, flash point, bottom sediment, water, ash, pour point, distillation, potential gum, cetane number, high heat value and A.P.I. gravity. Procedure Number 62CH-SAM-003-05, Revision 2, and the Technical Specifications only address requirements for viscosity, water and sediment. These discrepancies were identified during a quality assurance audit conducted during November 1988, 88-MNT-2.

Contrary to the above, the discrepancies between the procedure, Technical Specifications and Final Safety Analysis Report have not been resolved and the corrective actions had not been finalized or implemented by the end of this inspection.

8909080277 890818 PDR ADOCK 05000321 O FDC  ;

Georgia Power Company 2 Docket Nos. 50-321 and 50-366 l Hatch Units 1 and 2 License Nos. DRP-57 and NPF-5 This is a Severity Level IV violation (Supplement 1).

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, Hatch, 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 Tsr 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 l

action as may be proper should not be taken.

i FOR THE NUCLE REGULATORY COMMISSION l I(

Albert F. Gibson, Director Division of Reactor Safety Dated at Atlanta, Georgia this 18th day of August 1989 l

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