ML20148N542

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Part 21 Rept Re Error Identified in Release 21.1 of STAAD-III Program Which Yielded non-conservative Results at Portsmouth Gaseous Diffusion Plant.W/Evaluation Checklist & Pertinent Problem Rept
ML20148N542
Person / Time
Site: Portsmouth Gaseous Diffusion Plant
Issue date: 06/24/1997
From: John Miller
UNITED STATES ENRICHMENT CORP. (USEC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-97 GDP-97-0106, GDP-97-106, NUDOCS 9706270226
Download: ML20148N542 (6)


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United Statis j

Enrichmint Corpor; tion 2 Democracy Center 6903 Rockledge orive DECEl??tfa@o8'7 Tel: 301)564-3200 l$N JI)l} Mx:(%1)pg01 l

' JAMES H. MILLER Dir: (301) 564-3309 l

VicE PRESIDENT, PRooOCTioN Fax: (301) 571-8279 I

1 June 24,1997 SERIAL: GDP 97-0106 U.S. Nuclear Regulatory Commission Attention: NRC Operations Center Washington, D.C. 20555-0001 Portsmouth Gaseous Diffusion Plant (PORTS)

Docket No. 70-7002 Initial Notification of 10 CFR 21 Report The purpose of this letter is to provide initial notification to the NRC in accordance with 10 CFR 21.21(d)(3) of a reportable defect that has been identified at the Portsmouth Gaseous Diffusion Plant 1

(PORTS). The defect is associated with Release 21.1 of the STAAD-III structural analysis program supplied by Research Engineers, Inc., 22700 Savi Ranch, Yorba Linda, California, 92887-4608. This program is being used to evaluate the existing crane support structure at the X-326 ERP Withdrawal Station as part of an ongoing project to replace the existing liquid UF, handling crane at this location.

An error was identified in Release 21.1 of the STAAD-III program which yielded non-conservative results. If the results provided by Release 21.1 of the program had been used as input for the design of the crane support structure, the margin of safety could have been reduced and the potential to drop a I cylinder containing liquid UF could have increased, thereby creating a substantial safety hazard.

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The Paducah Gaseous Diffusion Plant has been apprised of this situation. The associated POR

.10 CFR 21 evaluation checklist and a copy of the pertinent PORTS problem report is enclosed.

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Offices in Uvermore, Califomia Paducah, Kentucky Portsmouth. Ohio Washington, DC

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l U.S,Nucl' ar Regulatory Commission l_

e Attn: NRC Operations Center June 24,1997 i

l GDP 97-0106 Page 2 i

L Any questions related to this subject should be directed to me at (301) 564-3309 or Mark Lombard j

at (301) 564-3248, l

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.w es H. Miller rice President, Production i

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Enclosures:

As stated l

cc: NRC Region III Office NRC Resident Inspector - PGDP J

NRC Resident Inspector - PORTS

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ENCLOSURES PORTS PART 21 CHECKLIST AND RELATED PROBLEM REPORT I

10CFR21 97-0013 4

Uk.141 (1622 M) 1 j

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10 CFR PART 21 EVALUATION CHECKLIST I

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The following questions provide the criterb for evaluation of10 CFR Part 21 reportability:

j Has the NRC already been infonned of this condition pursuant to 10 CFR 21 (for example, by a A.!

No_g, Yes,_.

i supplier)?

A.2 N o_,,,,,,

Yes if yes, has USEC or LMUS been samed as a recipient ofthe defective itern?

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Has this condition aheady been reported to NRC in accordance with procedure UE2 MC-RE!030?

i A.3 Nog Yes.,,,,,,

f If the answer to Questions A.! and A.2 are "Yes", or the auswer to Question A.3 is "Yes", the condition need n 10 CFR21. Attach objective evidence of nodfication of the NRC and complete Part E.

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l If th2 answers to Questions.A.2, A2, and A.3 are "No", continue with tbc evaluation.

Is the' identified condition a deviation or failure to comply associated with a basic component J

B.1 No._,,,

Yesg (including design, analysis, inspection, testing, fabricacion, replacement parts, or consulting service If'the answer to Question B.1 is "No", te condition is not reportable under 10 CFR 21; anach basis for conclus l

i' Section E. If the answer to Question B.! is "Yes", continue the evaluation.

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B.2 No Yes2 If the answer to Question B.1 is "yes", has the basic cornponent been delivered to USEC/LMUS and accepted for use in the plant or an activity (includes USEC dedicated commercial grade items)?

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If the answer to Question B.2 is "No", the condition is tvA reportable under 10 CFR 21; ansch basis for conclu j

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Section E. If the answer to Question B.2 is '"fes", condition is potentially reportable. Continue with the evaluation.

Fwther, does the activity 'or basic component contain any of the following types of conditions? (Deviation means C.

.,,... from the technical requiremems included in a im.....ent doement.)

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[ No,,_, Yes2

1) The installation, use, or operation of a basic component comaining a deviation?

Nog Yes

2) A condition or circumstance involving a basic consponent that could contribute to Miag

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a safety limit as defined in the GDPs Technical Safety Requirements (TSRs)?

Nod Yes_

3) A failure to comply with any ap'plicable regulation, order, or certificate issued by.de.NRC if all of the answers in this section are "No", the condition is not reportabic; attach basis for conclusion and procee If any answers are "Yes" continue with the evaluation.

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i Could the deviation or failure to comply create a substantial safety hazard resulting in any of the following (assum a

A D.

are no redundant or back-up systems):

e Nog 2, s.,___

1) Exposure in excess of10 CFR 20.1201 timiu Nog Yes_,,,
2) Exposdre of an individual in an unstricted area to more than 0.5 rum in one calendar year (10 CFR 20.1301(c))

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No _,,,, Yes/

3) Release of radioactive material to an unrestricted area in excess of the limits in 10 CFR 20, Appendix 8. Table 2 J

No,,,,,_ Yes[ 4) A deficiency which seriously compromised the ability of a UF, confinement systm to J

j perform its designated function j

No Yes

5) Other.(explain)

I if all answers in this section are "No", the condition is not reportable; complete Part E. If any answer is "Yes", condition is j

rMie. Continue with evaluation.

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Evaluation resuhs and recommendation. Recommend condition be reported?

j No.,,,,, Yesg.

If answer is "Yes", sign this put and continue to follow procedure UE2 EG GE1059.' Sign the evaluation checkhst and forward to the Manager, NRA. If answer is "No", evaluation is complete.

i Si n the evaluation checklist and fotward to Commitment Management for closure of Problem Report.

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l suunnary of Evaluation and basis for conclusions i

Reference:

PR. PTS-97-4154. Error in Stnictural Analysis Software

.i sTAAD III, Revision 21.1, was used to evaluate the existirsg ERP crane support.

Problem structure for Project No. E2072, X-326 ERP Crane Replacement Project.

l Report No. PR-PTS-97-4184 identified an error in this software prior to final approval of the design package, therefore, no field modifications have been l

Because an error in the analysis of a liquid trF, handling system 1

implemented.

could compromise the integrity of that system, this defect'has been determined i

to be reportable under the notification requirements of 10 CFR Part 21.

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