ML20247Q121

Notice of Violation from Insp on 890218-0410 & 0517-19. Violation Noted:Operators Did Not Maintain Drywell to Torus Differential Pressure at Any Time While Plant Operating Since Jul 1985

ML20247Q121
Person / Time
Site:	Fermi
Issue date:	06/01/1989
From:	Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20247Q104	List: IR 05000341/1989008 ML20247Q121
References
50-341-89-08, 50-341-89-8, NUDOCS 8906060333
Download: ML20247Q121 (2)

Text

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NOTICE OF VIOLATION Detroit Edison Company Docket No. 50-341 Fermi 2 License No. NPF-43 l

As a result of the inspection conducted on February 18 through April 10, and May 17-19, 1989, and in accordance with 10 CFR Part 2, Appendix C - General l Statement of Policy and Procedure for NRC Enforcement Actions (1988), the following violations were identified:

1. 10 CFR 50, Appendix B, Criterion V, states in part, " Activities affecting quality shall be prescribed by documented instructions, procedures or '

drawings, of a type appropriate to the circumstances and shall be 3 accomplished in accordance with these instructions, procedures, or drawings..."

Procedure FMD PR1, " Procedures, Manuals, and Orders," Section 4.11.1.3 states, in part, "Where the next required step in a procedure cannot be performed, for whatever reason, the activity shall be terminated until the appropriate change to the procedure is approved..."

Contrary to the above:

a. Operators did not maintain a drywell to torus differential pressure at any time while the plant was operating since July 1985 (initial license) even though Steps 5.3.1.3 and 5.4.1.3 of Operating Procedure NPP-23.406, " Primary Containment Nitrogen Inerting and Purge System,"

required a differential pressure.

b. On numerous occasions from August 7, 1988, to February 26, 1989, operators continued to perform overspeed testing of the turbine without the illumination of the RESET No. 2 OVERSPEED RESET pushbutton backlight even though Step 6.12 of Procedure 27.112.03,

" Turbine Generator Mechanical Overspeed On Load Test," required backlight illumination.

c. On two occasions from November 9, 1988, to March 13, 1989, operators continued to perform the valve lineups of NPP-23.208, "RHR Complex Service Water System," even though the valve labels and the procedural designations of six valves did not agree.

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

2. 10 CFR 50, Appendix B, Criterion XVI, states in part, " 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. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the conditions is determined and corrective action taken to preclude repetition."

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.6 Notice of Violation 2 l

i Contrary to the above:  !

The measures established to correct Violation 341/89006-03 were inadequate in that the installed diesel fire pump alternator was a 12 volt alternator.

versus the required 24 volt alternator and this was not identified by the suitability review.

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

3. 10 CFR 50.72 b.(2), states in part, "the licensee shall notify the NRC as soon as practical and in all cases within four hours of...(iii) any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems needed to...(D) mitigate the consequences of an accident.

Contrary to the above:

The High Pressure Coolant Injection System was declared inoperable on February 23, 1989, at 3:00 p.m. but notification to the NRC was not made until 12:52 a.m. on February 24th, approximately six hours late.

This occurred despite multiple reviews by operations supervision.

This is a Severity Level V violation (Supplement I).

With respect to Items 1 and 2, the inspection showed that actions had been taken to correct the identified violations and to prevent recurrence.

Consequently, no reply to the violations is required and we have no further questions regarding these matters. With respect to Item 3, pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) the corrective actions that have been taken and the results achieved; (2) the corrective actions that will be taken to avoid further violations; and (3) the date when full compliance will be achit ed. Consideration may be given to extending your response time for good cause shown.

JUN 1 .

C / I Dated Richard C. Knop, Chief Reactor Projects Branch 3

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