ML18039A600

Notice of Violation from Insp on 980823-1003.Violation Noted:Until 980828,written Procedures Not Adequately Maintained

ML18039A600
Person / Time
Site:	Browns Ferry
Issue date:	11/02/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18039A599	List: IR 05000259/1998006 ML18039A598 ML18039A600
References
50-260-98-06, 50-260-98-6, 50-296-98-06, 50-296-98-6, NUDOCS 9811090246
Download: ML18039A600 (4)

Text

Tennessee Valley Authority Browns Ferry Units 2 and 3 NOTICE OF VIOLATION Docket Nos. 50-260 and 50-296

'icense Nos. DPR-52 and DPR-68 During an NRC inspection conducted on July 12 - August 22, 1998, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action," NUREG-1600, the violation is listed below:

Technical Specification 5.4.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Paragraph 8 of Appendix A of Regulatory Guide 1.33 requires procedures for performing Technical Specification surveillance requirements.

Surveillance Requirements 2-SR-3.3.5.1.6(CI/Cll), Revision 1, and 3-SR-3.3.5.1.6(CI/Cll), Revision 2, Functional Testing of Residual Heat Removal Loop I/II Valve Logic and Interlocks, provides procedural guidance for performing logic system functional testing of Low Pressure Coolant Injection System instrumentation.

Contrary to the above, until August 28, 1998, written procedures were not adequately maintained in that reactor low pressure inputs to the recirculation pump discharge isolation valve automatic closure logic of the Low Pressure Coolant Injection System were not properly tested.

This condition has existed since June 1992 for Unit 2 and September 1995 for Unit 3 when the predecessor surveillance instructions were not properly revised when modified to allow testing when the units were at reactor pressures greater than 230 psig.

This is a Severity Level IVviolation (Supplement I).

The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved'are already adequately addressed on the docket in the enclosed Inspection Report 50-259,260,296/98-06.

However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position.

In that case, or if you choose to respond, clearly mark your response as a "Reply to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 with.a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facilitythat is the subject of this Notice of Violation (Notice), within 30 days of the date of the letter transmitting this Notice.

If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, U. S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

vazxovoaoe wsaaoa PDR ADOCK 05000259 6

PBR Enclosure 1

4

'OV 2

e lf you choose to respond, your response willbe placed in the NRC Public Document Room (PDR). Therefore, to the extent possible, the response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.

. In accordance'with 10 CFR 19.11, you may be required to post this Notice within two working days.

Dated this 2nd day of November 1998

Cl