ML20198H232

Notice of Violation from Insp on 971103-1214.Violation Noted:On 971107,inspectors Identified That One non-empty F-can,located X-344 Building Was in Storage & Uncapped

ML20198H232
Person / Time
Site:	Portsmouth Gaseous Diffusion Plant
Issue date:	01/09/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20198H217	List: IR 07100103/2012014 ML20198H213 ML20198H232
References
70-7002-97-12, NUDOCS 9801130234
Download: ML20198H232 (3)

See also: IR 07100103/2012014

Text

e

, .

NOTICE OF VIOLATION

United States Enrichment Corporation Docket No. 70 7002

Portsmouth Gaseous Diffusion Plant Certificate No. GDP-2

During an NRC inspedon conducted from November 3 to December 14,1997, 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 3.112 requires, in paK, 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 a documented nuclear criticality safety

approval (NCSA).

NCSA PLANT 025.A01, " General Use of Small Diameter Containers for Storing up to

10% Enriched Material," requires that non-empty F cans be capped at all times except

when filling, sampling, or emptying containers.

Contrary to the above, on November 7,1997, the inspectors identified that one non-empty

F-can, located in the X 344 Building was in storage and uncapped.

This is a Severity LevelIV Violation (Supplement VI). (VIO 70 7002/97012-01)

2. Technical Safety Requirernent 3.9.1 requires that written procedures be implemented to

cover activities described in Safety Analysis Report Section 6.11.4.1 and listed in

Appendix A to Safety Analysis Report Section 6.11.

Appendix A to Safety Analysis Report Section 6.11 states that " investigations and

reporting" shall be covered by a written procedure.

Paragraph 6.2.1 of plant Procedure UE2 RA RE1030, Revision B, * Nuclear Regulatory

Event Reporting," requires verbal notification to the appropriate NRC office within the

time requirements shown in Appendix D of the procedure, and that the information is

completely and accurately desciibed.

Contrary to the above:

a. On October 15,1997, the certificatee failed to make a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification, to report

the use of Engineering Notices to modify nuclear criucality safety approval

requiremonts. The event was reportable because the changes were not formally

.

approved in accordance with nuclear criticality safety program requirements. This

event was subsequently reported to the NRC on November 5,1997 (NRC Event

Notification Number 33219).

b. On October 16,1997, the certificatee failed to make a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to

report the loss of one control, with regards to storage of pigtail gaskets in F-cans

at the X 333 low assay withdrawal station. The event was subsequently reported

to the NRC on November 13,1997 (NRC Event Notification Number 33256).

c. On December 8,1997, the certificatee determined that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification

made on December 4,1997, should have been reported as a loss of two rather

than a single control (NRC Event Notification Number 33353).

9001130234 900109

POR ADOCK 07007002

C pg

. _ _ _ _ _ . _ .._ _ _ . _ _ _ _ _ _ _ . _

_ _ _ _ __ ._ _ _ . ,

4 4

Notice of Violation 2

d. On October 27,1997, the certificatee identified that a failure of the cylinder

intemal pressure loop on Autoclave #3 at the X 344 facility during operation on

October 25,1997, was reportaF , as a safety system component failure (NW  ;

Event Notification Number 33158), in nodition, on November 3,1997, the

certificatee identified that a loss of two nuclear enticality safety controls in the

enrichment cascade on November 2,1997, was reportable as a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification

!

(NRC Event Notification Number 33206).

This is a Severity Level IV Violation (Supplement VI). (VIO 70 7002/97012 02)

3. . Technical Safety Requirement 3.9.1 requires that written procedure, be implemented to

cover activities described in Safety Analysis Report Section 6.11.4.1 and listed in  ;

Appendix A to Safety Analysis Report Section 6.11.

Appendix A to Safety Analysis Report Section 6.11 states that cell treatments shall be

covered by a written procedure.

Paragraph 8.4.2 of plant Procedure XP4 CO-CN2118 TMP, Revision 0, " Static Cell

Treatm6at in X 330," required, if the presence of fluorocarbons or hydrocarbons was

detected and there were no indications of an abnormal reaction, to evacuate the cell

contents to surge drums as needed.

Contrary to the above, on November 11 12,1997, during static treatment on Cell 29-4 4,

the certificatee did not evacuate the contents of the cell when the presence of

'

hydrocarbons was detected.

This is a Severity Level IV Violation (Supplement VI). (VIO 70 7002/97012 03)

4. Surveillance Requirement 2.4.3.2.1 requires that the cold trap pressure relief system

instrumentation be calibrated on a semiannual basis.

Contrary to the above, from March 3,1997, through December 14,1997, infrared

analyzers used to verify relief drum pressure less than or equal to 0.3 pounds per square

inch absolute, as required by Technical Safety Requirement 2.4.3.2.D. were not

calibrated semiannually.

This is a Severity Level IV Violation (Supplement VI) (VIO 70-7002/97012-05)

With regard to item 1, the NRC has concluded that information regarding the reason for

(Violation 70-7002/97012-01), the corrective actions taken and planned to correct the violation

and prevent recurrence and the date when full compliance will be achieved is already adequately

addressed on the docket, in United States Enrichment Corporation's correspondence to the NRC

dated December 23,1997 (GDP 97 2041). However, you are required to submit a written

statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately

reflect your corrective actions or your position. in that case, or if you choose to respond, clearly

mark your response as a * Rep 5/ to a Notice of Violation," and send it 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

!

___.,._ _.._.. . . _ _ _ . _ , _ , , _ _ _ - , . . . , ~ . , -, - . . . - . - ~ . . . . _ . , .,m,._..,, ,,.-, , --.- - , . , ,

l

l

. e

1

I

Notice of Violation 3 j

\

Portsmouth Gaseous Diffusion Plant of this Notice, within 30 days of the date of the letter

transmitting this Notice of Violation (Notice).

With regard to items 2,3 and 4, 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 Comm!ssion, ATTN: Document Control Desk, Washington, D.C. 20555

with a copy to the Regional Administrator, Region Ill, and a copy to the NRC Resident inspecto*

at the Portsmouth Gaseous Diffusion Plant of this Notice, within 30 days of the date of the letter

transmitting this Notice of Viciation (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 'aken and '

the results achieved, (3) the corrective 6teps that will be taken to avoid further vlotations, and

(4) the date when full compliance will be achieved.

/our 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 t e taken. Where good cause is shown, consideration will be

given to extending the response time. ,

Because your resoonw will be placed in the NRC Public Document Room (PDR), to the extent

possiblo, 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

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 mult

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 protection described in 10 CFR 73.21.

Dated at Usle, Illinois

this 9t.h day of January 1998

. . - - -. - - . . .- - - , . .-- .~