ML20206F207

Notice of Violation from Insps on 870201-28

ML20206F207
Person / Time
Site:	Browns Ferry
Issue date:	04/08/1987
From:	Zech G NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20206F193	List: ML20206F187 ML20206F207 ML20206F231
References
50-259-87-09, 50-259-87-9, 50-260-87-09, 50-260-87-9, 50-296-87-09, 50-296-87-9, NUDOCS 8704140178
Download: ML20206F207 (2)

Text

-

• 4 ,

ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-259, 50-260, and 50-296 Browns Ferry 1, 2, and 3 License Nos. OPR-33, DPR-52 and DPR-68 During the Nuclear Regulatory Comission (NRC) inspection conducted on February 1-28, 1987, a violation of NRC requirements was identified. The violation-involved failure to adkere to maintenance instructions during work on the A3 Residual Heat Removal Service Water Pump, failure to adequately evaluate an event reportability determination, and failure to make correct procedure updates as required.

In accordance with the " General ' Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:

Technical Specification 6.3 recpires that detailed written procedures covering plant operations shall be prepared, approved and adhered to.

1. Contrary to the above, Mechanical Maintenance Instruction (MMI)-29, RHRSW Pump Inspection and Maintenance, was not adhered to on November 24, 1986. As documented on Maintenance Request (MR)

No. A-706494, the A3 RHRSW Pump baseplate nuts were to be torqued as required by MMI-29, Section B, Step 10.4. Although this step requires that the torque be adjusted between 15 and 1,000 ft-lbs, one of the- A3 RHRSW pump nuts was adjusted to a value outside of this range (0 ft-lbs.).

2. Corttrary to the above, this requirement was not met in following Browns Ferry Standard Practice 15.2, Licensee Event Report, for preparing Licensee Reportable Event Determination (LRED) 87-1-035 in sufficient detail for determining reportability. Unit I reactor

' building ventilation exhaust continuous air monitor, 1-90-250, failed a low flow alarm test during performance of Surveillance Instruction SI 4.8.B.4-3A for the monthly functional test on 1/16/87 as observed by the inspector. Excessive in-leakage from a loose orifice flange and a large dead band for the Magnehelic flow gage was determined to be the cause. One of the items to be checked for reportability determination stated on the LRED was a flow check for each CAM.

Thirty days after the initial surveillance test no flow checks were conducted. The CAM in-leakage creates the potential for an unmonitored relean from the reactor building.

3. Contrary to the above, Site Standard Practice 2.11, Review, Approval of Site-Generated Procedures / Instructions, requires in part that long-tem comitments to organizations outside BFN (such as DQA, NRC, ANI, etc.) shall be marked in a manner to easily identify the comitment and the text which implements that comitment. When an 8704140178 87040s PDR ADOCK 05000259 G PDR 4

Tennessee Valley Authority 2 Docket Nos. 50-259, 50-260, and 50-296 Browns Ferry 1, 2, and 3 License Nos. DPR-33, DPR-52 and DPR-68 entire procedure implements a commitment, it is acceptable to denote that commitment in the purpose or scope of that procedure.

Mechanical Maintenance Instruction 157, Inspection, Lubrication, and Replacement of the LPCI MG-Set Couplings and Bearings, does not satisfy the requirements in that the procedure was revised to clarify coupling alignment criteria which was a Licensee Event Report (LER 296/86-11) commitment, but did not denote that commitment within the procedure.

This is a Severity Level V Violation (Supplement I) and is applicable to all three units.

Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including: (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.

FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED By

. GARY G. 2ECH Gary G. Zech, Assistant Director Regional Inspections DivisionofTVAProjects OfficeofSpecialProjects l Dated at Atlanta, Georgia this 8th day of April 1987 l

t l

!