ML20212D851

Notice of Violation from Insp on 970811-0921.Violation Noted:On 970913,plant Shift Superintendent Exited X-300 Facility W/O Assigning Designee IAW Tsr 3.1.3

ML20212D851
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	10/28/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20212D844	List: ML20212D838 ML20212D851 ML20212D865
References
70-7002-97-08, 70-7002-97-8, NUDOCS 9710310205
Download: ML20212D851 (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 August 11 to September 21,199~,, 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 below:

1. Technical Safety Requirement 3.2.2.a specified the minimum staffing requirements for each facility (shown in Table 3.2.2-1).

Table 3.2.2-1 requires that 1 plant shift superintendent (PSS) be present in the X-300 M facility at all times, if the PSS needs to leave the X-300, an authorized designee trained to execute plant emergency procedures can be assigned in accordance with TSR 3.1.3.

Contrary to the above, on September 13,1997, the PSS exited the X-300 facility without assigning a designee in accordance with TSR 3.1.3.

R Thir is a Severity Level IV Violation (Supplement VI). (VIO 70-7002/97008-01)

2. Technical Safety Requirement 3.9.1 requires that written procedures be prepared, reviewed, approved, imolemented, and maintained to cover activities described in the safety analysis report (SAR), Section 6.11.4.1.

SAR Section 6.11.4.1 requires that maintenance activities be addressed by written procedures, documented work instructions, or drawings appropriate to the circumstances as described in Section 2.5 of the Quality Assurance Plan (QAP).

Contrary to the above, plant procedure CMG 21," Expansion Joint-Removal And l Installation," Revision 3 was not adequaiely prepared in that it did not provide sufficient cheritical safety controls for removal of a piping x-joint contairiing a uranium deposit from cell 33-3-3 on August 30,1997.

This is a Severity Level IV Violation (Supplement VI). (VIO 70-7002/97008-02)

3. Technical Safety Requirement 3.11.2 requires, in part, that all operations involving uranium enriched to 1.0 weight-percent (wt.%) or higher U-235 and 15 grams (g) or more of U-235 shall be performed in accordance with documented nuclear criticality safety approval.

9710310205 971028 PDR ADOCK 07007002 C PDR

Notice of Violation Cont ary to the above, from August 15 to September 15,1997, receipt and storage of nonstandard 1S sample cylinders with uranium enriched to 1.0 wt% U-235 and 15 g or more of U-235 at the X-344 building was not performed in accordance with a nuclear

, criticality safety approval (NCSA). Specifically, geometry control was not in accordance

': with NCSA 0344A006.

This is a Severity Level IV Violation (Supplement VI) (VIO 70-7002/97008-03).

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."

American Society of Mechanical Engineers (ASME) NOA-1-1989, " Quality Assurance Program Requirements for Nuclear Facilities," Basic Requirement 16, " Corrective Action,"

states that conditions adverse to quality shall be identified promptly and corrected as soon as practical. In the case of a significant condition adverse to quality, the cause of the condition shall be dotermined and corrective action taken to preclude recurrence.

Contrary to the above, on September 10 and September 18,1997, the certificatee identified two examples where required technical safety requirement (TSR) overtime limits were exceeded without prior approval. This is a repetitive violation of TSR 3.2.2 which requires prior approval for exceeding overtime requirements and previously identified overtime concems were not adequately corre :ted to prevent recurrence.

This is a Severity Level IV violation (Supplement VI). (VIO 70-7002/97008-04).

Pursuant to the provisions of 10 CFR 76.70, United States Enrichment 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 Ill, 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 Notica 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 compliano) will be achieved.

Your response may reference or include previously docketed correspondence, if the correspordence 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 certificate 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 be given to extending the response time.

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 placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your

Notice of Violation _

nece*:;ary to provide an acceptable response, then please provide a bracketed copy of your :

rerponse that identifies the information that should be protected and a redacted copy of your response that deletes such information if you request withholding of such material, you 29.11 -

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 r** provide the information required by 10 -

CFR 2.790(b) to support a request for withholding Or:Lential commercial or financial information). If safeguards information is necessary a grovide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

- Dated at Lisle, Illinois this 28tiday of October 1997