ML20196L272

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Ack Receipt of 990407 Ltr,Transmitting Copy of Semiannual Status Rept of C-E Criticality Safety Program Update Covering Period from 981001-990331
ML20196L272
Person / Time
Site: 07000036
Issue date: 05/18/1999
From: Emeigh C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Sharkey R
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
TAC-L31187, NUDOCS 9905270305
Download: ML20196L272 (2)


Text

! ' way EN9 Mr. Robert W. Sharkey, Direct r Regulatory Aff; irs Combustion Engineering, Inc.

. 3300 State Road P Festus, Missouri 63028

SUBJECT:

CRITICALITY SAFETY PROGRAM UPDATE SEMI-ANNUAL STATUS REPORT (TAC NO. L31187)

Dear Mr. Sharkey:

This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1998 to March 31,1999.

The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis.

We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant.

Your letter also expressed the concems that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the Integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for reviewing ISAs. The staff expects that additional guidance will be available to address your concerns in near future in conjunction with the rule making.

Your cooperation in keeping us informed of your progress on the CSPU is appreciated.

Sincerely, Original signed by Charles Emeigh, Section Chief Licensing Section Licensing and International I Safeguards Branch b ,

s Division of Fuel Cycle Safety /

and Safeguards, NMSS

/

Docket 70-36 License SNM-33 h

DISTRIBUTION: [ Completed]

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I r. Robert W. Sharkey, Director -

Regulatory Affairs Combustion Engineering, Inc.

3300 State Road P' - .; e Festus, Missouri 63028

SUBJECT:

CRITICALITY SAFETY PROGRAM UPDATE SEMI-ANNUAL STATUS REPORT (TAC NO. L31187)

Dear Mr,

Sharkey:

This acknowledges receipt of your letter of April 7,1999, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU)

~ covering the period from October 1,1998 to March 31,1999.

The CSPU plan was submitted on September 20,1996, and is designed to formalize and strengthen the nuclear criticality safety program at the Hematite, Missouri site. In that plan, CE committed to submit a quarterly progress report on the implementation of the CSPU. As agreed by the Nuclear Regulatory Commission (NRC), in a letter dated November 6,1997, the reporting frequency was changed to a semiannual basis.

We note from your April letter that you have devoted additional resources to the CSPU plan to bring the progress concerning the Recycle / Recovery area back on schedule, and this effort has been largely successful. For the next reporting period, your work will be focused on the systems and operations in the front end of the pellet plant.

Your letter also expressed the concerns that the NRC's future final rule of the revisions to 10 CFR Part 70 will impose requirements above and beyond your current practices in the preparation of the integrated Safety Analysis (ISA). As you know, the NRC is currently working closely with the nuclear industry in developing the proposed revisions to 10 CFR Part 70 to require ISAs and preparing a Standard Review Plan to provide the acceptable criteria for l reviewing ISAs. The staff expects that additional guidance will be available to address your  !

concerns in near future in conjunction with the rule making.

Your cooperation in keeping us informed of your progress on the CSPU is appreciated.

]

Sincerely, 1

d.N- N

l. Charles Emeigh, ection Chief

! Licensing Section l ,

Licensing and international  :

Safeguards Branch Division of Fuel Cycle Safety ,

and Safeguards, NMSS Docket 70-36--

License SNM-33