ML20247N271: Difference between revisions

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| number = ML20247N271
| number = ML20247N271
| issue date = 05/06/1998
| issue date = 05/06/1998
| title = Ack Receipt of 980331 Ltr Transmitting Copy of Semiannual Status Rept of CE Criticality Safety Program Update Covering Period from 971001-980331.NRC Continues to Endorse Methods Described in Alche Handbook
| title = Ack Receipt of Transmitting Copy of Semiannual Status Rept of CE Criticality Safety Program Update Covering Period from 971001-980331.NRC Continues to Endorse Methods Described in Alche Handbook
| author name = Weber M
| author name = Weber M
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
| author affiliation = NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = TAC-L31062, NUDOCS 9805270098
| document report number = TAC-L31062, NUDOCS 9805270098
| title reference date = 03-31-1998
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 2
| page count = 2

Latest revision as of 13:25, 16 March 2021

Ack Receipt of Transmitting Copy of Semiannual Status Rept of CE Criticality Safety Program Update Covering Period from 971001-980331.NRC Continues to Endorse Methods Described in Alche Handbook
ML20247N271
Person / Time
Site: 07000036
Issue date: 05/06/1998
From: Weber M
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Sharkey R
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
TAC-L31062, NUDOCS 9805270098
Download: ML20247N271 (2)


Text

_ _ . _ _

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May 6, 1998 2

.e-Mr. Robert W. Sharkey, Director Regulatory Affairs Combustion Engineering, Inc.

3300 State Road P Hematite, MO 63047

SUBJECT:

. CRITICALITY SAFETY PROGRAM UPDATE (TAC NO. L31062)

Dear Mr. Sharkey:

This acknowledges receipt of your letter of March 31,1998, transmitting a copy of the semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1997 to March 31,1998.

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 March letter that the CSPU is on schedule. This letter also requested confirmation that the Integrated Safety Assessment (ISA) performed under your present -

methodology, (i. e., following the Guidelines for Hazard Evaluation Procedures by American Institute of Chemical Engineers Second Edition with Worked Examples) (AIChE handbook) will be acceptable under the pending revisions to 10 CFR Part 70. NRC previously endorsed the use of the methods described in the AIChE handbook in draft NUREG-1513, " Integrated Safety Analysis Guidance Document." NRC continues to endorse the methods described in the AIChE

- handbook. CE should recognize, however, that the application of specific methods needs to be justified by the licensee to ensure that the methods used for each ISA task, and the basis for selection of each method are consistent with the criteria described in NUREG-1513 for selection of ISA methods. As you know, the NRC is in the process of developing proposed revisions to 10 CFR Part 70 to require ISAs and is preparing a Standard Review Plan to provide the acceptance criteria for reviewing ISAs. The staff currently expects that additional guidance will be available by the end of 1998 in conjunction with the rulemaking.

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

Sincerely,

.; m CM1 Original signed by:

Michael F. Weber, Chief Q Q @ @ (Eftty Licer} sing Branch Division of Fuel Cycle Safety and Safeguards, NMSS Docket 70-36 License SNM-33 Distnbution TOochet 70 38 id7&PUBUC7Z NRC File Center 3 FCLB R/F NMSS R/F DS M \

FCSS R/F owe.up pe S pr ou.concun.noe Region 111 PHiland, Rill PTing SChotoo b4/$ Q OFC FCL8'E , FCLB*E h FCLB'E Ce FCLB M NAME SSoong 'tt, PShea M JGiltter g pg MWeber M () j DATE 4/22/98 4/22/98 debet $ {a N 5' N 9905270098 980506 POR C ADOCK 07000036 g,y __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

,p 4 UNITED STATES s j NUCLEAR REGULATORY COMMISSION

$ 2 WASHINGTON, D.C. 2066& 0001 1

%, . . , g / , Ma.y 6, 1998 '

Mr. Robert W. Sharkey, Director Regulatory Affairs Combustion Engineering, Inc.

3300 State Road P Hematite, MO 63047

SUBJECT:

CRITICALITY SAFETY PROGRAM UPDATE (TAC NO. L31062)

Dear Mr. Sharkey:

This acknowledges receipt of your letter of March 31,1998, transmitting a copy of the ,

semiannual status report of Combustion Engineering's (CE's) Criticality Safety Program Update (CSPU) covering the period from October 1,1997 to March 31,1998.

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 l reporting frequency was changed to a semiannual basis. J We note from your March letter that the CSPU is on schedule. This letter also requested confirmation that the Integrated Safety Assessment (ISA) performed under your present methodology, (i. e., following the Guidelines for Hazard Evaluation Procedures by American Institute of Chemical Engineers Second Edition with Worked Examples) (AIChE handbook) will be acceptable under the pending revisions to 10 CFR Part 70. NRC previously endorsed the use of the methods described in the AIChE handbook in draft NUREG-1513, " Integrated Safety Analysis Guidance Document." NRC continues to endorse the methods described in the AIChE handbook. CE should recognize, however, that the application of specific methods needs to be justified by the licensee to ensure that the methods used for each ISA task, and the basis for selection of each method are consistent with the criteria described in NUREG-1513 for selection of ISA methods. As you know, the NRC is in the process of developing proposed revisions to 10 CFR Part 70 to require ISAs and is preparing a Standard Review Plan to provide the acceptance criteria for reviewing ISAs. The staff currently expects that additional guidance will be available by the end of 1998 in conjunction with the rulemaking.

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

Sincerely, fic$

Michael F. Weber, Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS l l Docket 70-36 License SNM-33

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