ML20149H282

Notice of Violation from Insp on 970519-0629.Violation Noted:Portsmouth Procedure XP4-CO-CA 2380, Operations of Tails Station, Rev 1 Was Not Maintained to Cover Operator Actions to Prevent or Mitigate Consequences of Accidents

ML20149H282
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	07/18/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20149H271	List: ML20149H268 ML20149H282 ML20149H286
References
70-7002-97-04, 70-7002-97-4, NUDOCS 9707240305
Download: ML20149H282 (3)

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NOIICF OF VIOLATION United States Enrichment Corporation Docket No. 70-7002 Portsmouth Gaseous Diffusion Plant Certificate No. GDP-2 i

During an NRC inspection conducted from May 19 to June 29,1997,  !

l three violations of NRC requirements were identified, in accordance with the  ;

" General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, I the violations are listed below:

1. Technical Safety Requirement 3.9.1 requires, in part, that written procedures shall be )

maintained to cover operator actions to prevent or mitigate the consequences of accidents described in Safety Analysis Report (SAR) Chapter 4. j l

Contrary to the above:

A. Portsmouth Procedure XP4-CO-CA 2380, " Operations of the Tails Station,"

Revision 1, was not maintained to cover operator actions to prevent or l mitigate the consequences of accidents described in SAR Chapter 4, l Table 4.2-5. Specifically, changes A and B to the procedure did not correct a reference to high pressure vent panels that were not fully installed.

I B. Plant Procedure XP4-CO-CN2116(C), " Cell Treatments in X-330," did not I require that safety screenings to changes in the normal valve line up for cell l treatment were performed to ensure that the ability to evacuate a cellin an '

emergency was maintained as described in SAR Section 4.1.1.2.2.

This is a Severity Level IV violation (Supplement VI) (70-7002/97004-01).

2. 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) NOA-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 5, " Instructions, Procedures, and Drawings" states, in part, that activities affecting quality shall be prescribed by procedures which shallinclude or reference appropriate quantitative or qualitative acceptance criteria for determining that prescribed activities have been satisfactorily accomplished.

9707240305 PDR 970718 C ADOCK 07007002 pg

l-Notice of Violation I Contrary to the above, a procedure for an activity affecting quality did not include or reference appropriate quantitative or qualitative acceptance criteria {

for determining that prescribed activities had been satisfactorily accomplished.

Specifically, Portsmouth Procedure XP2-EG-NS1030, " Safety Evaluations of As-Found Discrepancies," Revision 0, did not provide enough guidance to satisfactorily accomplish an Unreviewed Safety Question Determination. The safety evaluation did not identify that an as-found condition of a condensate drain screen in the X-344 building autoclaves could potentially increase the consequences of an accident identified in Section 4.2.3.2 of the SAR.

This is a Severity Level IV violation (Supplement VI) (70-7002/97004-02).

3. 10 CFR 95.35(a) requires, in part, that no person subject to the regulations in this part may receive or may permit any individual to have access to matter revealing Confidential Restricted Data unless the individual has a "O" or "L" access authorization.

Contrary to the above, from March 3 through June 13,1997, the certificatee subject to the regulations in Part 95, permitted individuals not having "O" or "L" authorizations to have access to an area where valve labeling revealed Confidential Restricted Data.

This is a Severity Level IV violation (Supplement lil) (70-7002/97004-03). 1 Pursuant to the provisions of 10 CFR 2.201, 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 111, 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.

Your response may reference or include previously docketed correspondence,if the correspondence ;dequately 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.

l be issued as to why the license should not be modified, suspended, or revoked, or why such .

other action as may be proper shotsd not be taken. Where good cause'is shown, l consideration will be given to extending the response time.

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l 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 l

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 response 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 must specifically identify the portions of your response 1 that you seek to have withheld and provide in detail the bases for your claim of withholding I (e.g., explain why the disclosure of information will create an unwarranted invasion of l personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financialinformation). If safeguards information is necessary to provide an acceptable response, please provide the level of j protection described in 10 CFR 73.21.

l Dated at Lisle, Illinois this 18th day of July 1997 l

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