ML20202F376
| ML20202F376 | |
| Person / Time | |
|---|---|
| Site: | Paducah Gaseous Diffusion Plant |
| Issue date: | 12/22/1998 |
| From: | Toelle S UNITED STATES ENRICHMENT CORP. (USEC) |
| To: | Paperiello C NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| GDP-98-0287, GDP-98-287, NUDOCS 9902040036 | |
| Download: ML20202F376 (4) | |
Text
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- ' t USEC A sd.
- un.rsy comp.ny December 22,1998.
GDP 98-0287 l
- Dr. Carl J. ' aperiello' P
Director, Office of Nuclear Material Safety and Safeguards Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
- Paducah Gaseous Diffusion Plant (PGDP)
Docket No 70-7001 Notification of Change in Regulatory Commitment - SAR Update Certificate Amendment
. Request - C-315 Accumulator Capacity and Line Size 3
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Dear Dr. Papenello:
The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of a change in the completion date for a regulatory commitment. This commitment was made in USEC letter GDP 97-0188 dated October 31,1997 (Reference 1), and it is related to the SAR Update certificate amendment request and the revision of source-term and consequence analyses affected by the C-315 accumulator capacity and line size. The specifics of the commitment changes are provided below.
Background
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.-In letter GDP 97-0188, Enclosure 1, Table 1, Item 14 USEC stated:
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The DOE S AR Upgrade (KY/EM-174) performed threshold analyses to determine g[g the amount of UF release necessary to reach Evaluation Guideline consequences at 6
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the. site boundary. One case analyzed the C-315 accumulator but used incorrect values for the capacity and a size of the discharge line. The impact on the threshold
. analysis is expected to be small and no changes to the.S ARUP TSRs are anticipated.
The affected consequence analysis will be revised to use the correct values for accumulator capacity and line size. The results of the revised calculations, including any necessary changes to the SARUP, will be submitted to the NRC by December 31, 1998.
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9902040036 981222'
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PDR,ADOCK 07007001 C
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,6903 Rocidedge Drive, Bethesda, MD 20817-1818 Telephone 301-564-3200 Fax 301-564-3201 http://www.usec.com E
Offices in Livermore, CA Paducah, KY Portsmouth, OH ; Washington, DC
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_. _. _ -. _ _ _ _.._ ~.. _.._ _.- __.
s.
Dr. Carl J. Paperiello
' December 22,1998 GDP 98-0287, Page 2 -
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Descrintion of Revised Commitment M
The above commitment has been revised to read as follows:
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' The' DOE SAR Upgrade (KY/EM-174) performed threshold analyses to determine the amount of UF, release necessary to reach Evaluation Guideline consequences at the' site boundary. One analyzed case utilized a release model that incorporated incorrect values for the capacity and discharge line size of accumulators used in the C-315 withdrawal facility. New source-term and consequence analyses will be j
developed as appropriate to correct the identified deficiencies. The results of the new P
analyses, including any necessary changes to the S ARUP CAR, will be sub'mitted to the NRC by December 3,1999.
Justification for Revised Commitment In correspondence between USEC and the NRC earlier this year (see, for example, References 2 through 7), various issues were addressed that relate to the analysis of postulated releases in the C-I
~ 315 tails withdrawal facility. PGDP Engineering is actively working to evaluate these issues and perform the new' source term and consequence analyses. However, additional time is required to j
( complete the analyses, revise the supporting documentation, and revise the SARUP submittal.
Should you have any questions related to this subject, please contact Steve Routh at (301) 564-3251.
i Commitments contained in this submittal are identified in the enclosure.
- Sincerely,-
/1
- 5. A.
I L Steven A. Toelle Nuclear Regulatory Assurance and Policy Manager
References:
1.
. Letter from Mr. James H.~ Miller (USEC) to Dr. Carl J. Paperiello (NRC),
" Certificate Amendment Request - Update the Applications Safety Analysis Report," Paducah Gaseous Diffusion Plant, Letter No. GDP 97-0188, October 31,1997.
2.
Letter from Robert C. Pierson (NRC) to Mr. James H. Miller (USEC),
"Paducah Certificate Amendment Request - Update of the Application Safety Analysis Report 4 (TAC NO L32043)," February 5,1998.
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.Dr. Carl J. Paperiello -
_L December 22,1998 GDP 98-0287, Page 3 3.
Letter from Steve Polston (PGDP) to Mr. A. Bill Beach (NRC), " Notification ofPotential Nonconservative Assumptions in SAR Update Accident Analysis for Postulated Seismic Failures in Buildings C-310/310-A and _C-315," Letter No. GDP 98-1013, February 20,1998.
1 4.
. Letter from Robert C. Pierson (NRC) to Mr. James H. Miller, "Paducah Request for Enforcement Discretion Safety Analysis Report - (TAC NO.
L32057)," February 26,1998.
5.
Letter from James H. Miller-(USEC) to Dr. Carl J. Paperiello (NRC),
" Revised Request for Enforcement Discretion and Justification for Continued Operation," Letter No. GDP 98-0060, March 27,1998.
6.
Letter from Charles Cox (NRC) to Mr. James H. Miller (USEC), "Paducah g
and Portsmouth Certificate Amendment Requests - Update of the Application Safety Analysis Reports (TAC NOS. L32044 and L32043)," June 1,1998.
7.
Letter from Dr. Carl J. Paperiello (NRC) to Mr. J.' H. Miller (USEC),
" Exercise of Enforcement Discretion and Summary Report of the June 16, j
1998, Predecisional Enforcement Conference (NRC Inspection Report.70-
]
7001/98006 (DNMS) and Letter from Dr. Carl J. Paperiello to Mr. William
- H. Timbers, Dated May 28,1998." Letter No. EA 98-239, October 9,1998.
Enclosure:
Commitments Contained in This Submittal cc:
. Mr. Robert C. Pierson, NRC HQ cNRC Region III Office NRC Resident Inspector-PORTS NRC Resident Inspector - PGDP l
. ;.l[
pi
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6 Enclosure to GDP 98-0287 Page1ofI Commitments Contained in This Submittal
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LThe DOE SAR Upgrade (KY/EM-174) performed threshold analyses to determine the n
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.l amount of UF release necessary to reach Evaluation Guideline consequences at the site 6
boundary. - One analyzed case utilized a release model that incorporated incorrect values for the capacity and discharge line size of accumulators used in the C-315 withdrawal facility.
New source-term and consequence analyses will be developed as appropriate to correct the identified deficiencies. The results of the new analyses, including any necessary changes to the SARUP CAR, will be submitted to the NRC by December 3,1999.
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