ML20198H232
| 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: |
| References | |
| 70-7002-97-12, NUDOCS 9801130234 | |
| Download: ML20198H232 (3) | |
See also: IR 07100103/2012014
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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
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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 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 33353).
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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 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
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(NRC Event Notification 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.
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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
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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
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(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
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