ML20151X518

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Informs That NRC Staff Review Has Identified Addl Info That Is Needed to Complete Review of Compliance Plan,Issue 3, Action 9 Re ASME Code Interpretation & Assessment Results
ML20151X518
Person / Time
Site: Portsmouth Gaseous Diffusion Plant, Paducah Gaseous Diffusion Plant
Issue date: 09/15/1998
From: Yawar Faraz
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: John Miller
UNITED STATES ENRICHMENT CORP. (USEC)
References
TAC-L32093, TAC-L32095, NUDOCS 9809170130
Download: ML20151X518 (1)


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Mr. J:mts H. Mill:r SOPtember 15, 1998

- Vice PresidInt, Production U. S. Enrichment Corporation

.2 Democracy Center 6903 Rockledge Drive Bethesda, MD 20817

SUBJECT:

COMPLIANCE PLAN ISSUE 3, ACTION 9,' ASME CODE INTERPRETATION AND ASSESSMENT RESULTS REQUEST FOR ADDITIONAL INFORMATION -

PORTSMOUTH AND PADUCAH GASEOUS DIFFUSION PLANTS (TAC NOS. L32095 AND L32093)

Dear Mr. Miller.

This refers to your Portsmouth Gaseous Diffusion Plant (PORTS) and Paducah Gaseous Diffusion Plant (PGDP) " Response to Request for Additional Information - Compliance Plan issue 3, Action 9, ASME Code Interpretation and Assessment Results," letters dated August 14,1998, and August 21,1998, respectively.

- Our review of your submittals has identified additional information that is needed for us to complete our review. ASME Code Case 2211, Items (c) and (d), specifically ask for descriptions of all credible operating and upset scenarios and analysis showing the maximum pressure which can result from each scenario. To address this condition, USEC points the NRC staff to various applicable accident scenarios contained in the Chapter 4 of both the proposed SAR-PORTS and t

the proposed SAR-PGDP, dated October 31,1997, in Section 4.3.2.2.2, " Autoclave Steam Control Valve Fails Open (Pressure increase)" and Section 4.3.2.2.14, " Cylinder Failure Inside

- Autoclave (Primary System Integrity)," USEC references analyses that specify how maximum allowable working pressures for the UF, cylinder and autoclave would not be exceeded for the respective scenarios. The NRC requests the referenced analyses be submitted in order to make a determination that there exists adequate overpressure protection by system design in lieu of a pressure relief device as required by ASME Section Vill, Boiler and Pressure Vessel Code.

Please indicate any differences in the analyses between Portsmouth and Paducah pertaining to this issue.

Please provide the additionalinformation within 10 days of this letter. Future correspondence should reference TAC Nos. L32095 and L32093, for PORTS and PGDP, respectively, if you

- have any questions regarding this matter, please contact me at (301) 415-8113.

Sincerely, Cffnd 99Md %

Yawar H. Faraz, Project Manager I[ Q 07007001 980915 Enrichment Section og C

Special Projects Branch Q h)-t fDR Division of Fuel Cycle Safety 3

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.2 and Safeguards, NMSS Dockets: 70-7001,70-7002 nt% fe g y,,pJ u 4" gh@y Certificate GDP-2 HM ' p i

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Mr. Steve Toelle, USEC Mr. Morris Brown. PORTS M"' Q i4 Mr. Howard Pulley, PGDP h.h 1

Mr. Randall DeVault, DOE-OR DISTRIBUTION:(ControlNo. 410S)

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