ML20217H016

Notice of Violation from Insp on 980126-0308.Violation Noted:On 980204,29AB3 Compressor Cooler Was Discovered to Be UF6 Negative W/O Dry Air or Nitrogen Buffer at Greater than or Equal to Psia

ML20217H016
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	03/27/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20217G988	List: ML20217G983 ML20217H016 ML20217H024
References
70-7002-98-03, 70-7002-98-3, NUDOCS 9804030156
Download: ML20217H016 (3)

Text

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NOTICE OF VIOLATION United States Enrichment Corporation Docket No. 70-7002 Portsmouth Gaseous Diffusion Plant Certificate No. GDP-2 During an NRC inspection conducted from January 26,1998, through March 8,1998, four violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed 4

bciow:

1. Technical Safety Requirement 3.11.2 requires, in part, that F trations involving uranium enriched to 1.0 weight percent or higher U-235 anc , giams or more of U-235 shall be performed in accordance with a documented nuclear coticality safety approval (NCSA).

Nuclear Criticality Safety Approval (NCSA)-330-004.A02, " Cascade Operations in the X-330 Building," requires that any cascade equipment shutdown (motor tumed off) and at a Uranium Hexafluoride (UF6) negative shall have a plant dry air or nitrogen buffer at greater than or equal to 14 pounds per square inch absolute (psia).

Contrary to the above, on February 4,1998, the 29AB3 compressor cooler was discovered to be at a Uranium Hexafluoride (UF6) negative without a dry air or nitrogen buffer at greater than or equal to 14 psia.

This is a Severity Level IV violation (Supplement VI). (VlO 70-7002/98003-01)

2. Technical Safety Requirement 2.8.1.3 requires that the criticality accident alarm be operable (audible) in areas where the maximum foreseeable absorbed dose in free air exceeds 12 rad.

For an area that does not have an audibli alarm, the required action is to provide personnet allowed in the area with an attemate means of criticality alarm notification, such as a device that will alarm on sensing a 10 mr/hr dose rate, or a radio in constant communication with the Plant Control Facility.

Contrary to the above, on March 6,1998, two plant employees entered the X-102 Cafeteria while the audible alam1 slaved to the X-710 Laboratory detection was inoperable and without an alternate means of criticality alarm notification.

This is a Severity Level IV violation (Supplement VI). (VIO 70-7002/98003-04)

3. Technical Safety Requirement 2.5.3.10 requires the extended range product (ERP) crane be tagged out of service within one hour of deciering the crane inoperable.

Contrary to the above, on February 20,1998, the certificatee rendered the ERP crane inoperable without tagging the crane out of service during a preventive maintenance activity.

This is a Severity LevelIV violation (Supplement VI). (VIO 70-7002/98003-05) 9804030156 980327

{DR ADOCK 07007002 PDR

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J' Notice of Violation 4

4. 10 CFR 76.93, " Quality Assurance," requires that the Corporation shall establish, maintain, and execute a quality assurance program satisfying each of the applicable requirements of American Society of Mechanical Engineers (ASME) NQA-1-1989,

" Quality Assurance Program Requirements for Nuclear Facilities."

ASME NOA-1-1989 Basic Requirement 16, " Corrective Action," states that conditions adverse to quality (CAQs) shall be identified promptly and corrected as soon as practical.

Appendix A, of Procedure UE2-HR-Cl1031, " Corrective Action Process," lists out of calibration instrumentation, including "as found" conditions, as a specific exarrpie of a CAQ.

Contrary '.o the above, the certificatee did not correct a problem with the autoclave low cylinder pressure shutoff system setpoint that did not account fori,1strument drift. As a result, the certificatee operated Autoclave Numbers 4 and 6 at the X-343 Building between April 18, and November 11,1997, during which time the setpoints drifted below 20 psia, the minimum required by Technical Safety Requirement 2.1.3.9.

This is a Severity Level IV violation (Supplement VI). (VIO 70-7002/98003-06)

Persuant to the provisions of 10 CFR 76.70, United States Endchment Corporation is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region lil, and a copy to the NRC Resident inspector at the Portsmouth

• Gaseous Diffusion Plant of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, D.C. 20555-0001.

Your response may reference or include previously docketed correspondence if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will bs given to extending the response time.

I Notice of Violation Because your response will be placed in the NRC Public Document Room (PDR.), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be p! aced in the PDR without redaction. If personal privacy or propnetary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that delotes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10

. CFR 2,790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protecuon described in 10 CFR 73.21.

Dated at Lisle, Illinois this 27 day of March 1998 l

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