Letter Sequence Request |
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Results
Other: LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS, ML20093K990, ML20134N012, ML20204F478, ML20204F585, ML20204F631, ML20205D780, ML20206A626, ML20206K125, ML20206K572, ML20207P678, ML20209G723, ML20211M517, ML20211M527, ML20214H464
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MONTHYEARML20093K9901984-10-0808 October 1984
Submits Addl Info Re CESEC-III Code for Reload Core Analysis Methodology,Per 840511 Request.Code Applicable to Facility Due to Digital Simulation of C-E PWR NSSS
Project stage: Other
ML20134N0121985-08-20020 August 1985
Advises That Util 850613 Submittal of Rev 1 to OPPD-NA-8301-P, Reload Core Analysis Methodology Overview Will Be Withheld from Public Disclosure,Per 10CFR2.790
Project stage: Other
ML20214H4641986-11-17017 November 1986
Forwards Proprietary Rev 2 to OPPD-NA-8301-P, Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology Overview, Incorporating Methodology Changes for Cycle 11.Rept Withheld (Ref 10CFR2.790(b)(1)).Fee Paid
Project stage: Other
ML20211M5271986-11-30030 November 1986
Partially Withheld Nonproprietary Omaha Batch M Reload Fuel Design Rept (Ref 10CFR2.790)
Project stage: Other
ML20211M5171986-12-15015 December 1986
Forwards CEN-347(O)-NP & CEN-347(O)-P, Omaha Batch M Reload Fuel Design Rept, Re Core Reload Methodology Changes for Cycle 11,per D Sells Request.Proprietary Version Withheld (Ref 10CFR2.790(b)(1)).Affidavit Also Encl
Project stage: Other
ML20207J7061986-12-22022 December 1986
Forwards Request for Addl Info Re Util 861117 Submittal on Core Reload Methodology.Info Requested by 870130 to Meet Schedule for Cycle 11 Reload.Need for Receipt of Reload Amend Application by 870130 Emphasized
Project stage: RAI
ML20207P6781987-01-14014 January 1987
Advises That CEN-347(0)-P, Omaha Batch M Reload Fuel Design Rept, Contains Trade Secrets or Proprietary Commercial Info & Will Be Withheld from Public Disclosure Per 10CFR2.790
Project stage: Other
ML20209G7231987-01-26026 January 1987
Forwards Rev 1-P to CEN-347(O)-P Omaha Batch M Reload Fuel Design Rept, & Responses to Cycle 11 Core Reload Methodology Change Questions for Review.Affidavit Also Encl. Rept Withheld (Ref 10CFR2.790)
Project stage: Other
LD-87-013, Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS1987-02-27027 February 1987
Informs That CESEC-III Computer Code Applicable to Analysis of FSAR Chapter 14 Events (Excluding ATWS) for Facility. Models Included in Code Applicable to Operating Conditions at Plant & Cover All Features of Facility NSSS
Project stage: Other
ML20212N0151987-03-0909 March 1987
Forwards Proprietary & Nonproprietary Revised Reload Methodology Overview Repts,Incorporating Comments & Correcting Typos.Application for Withholding Proprietary Repts (Ref 10CFR2.790) Encl
Project stage: Request
ML20204F3931987-03-18018 March 1987
Forwards Corrected Pages to Proprietary & Nonproprietary Revs to Core Reload Methodology Changes for Cycle 11, Correcting Typos.Application for Withholding Proprietary Repts (Ref 10CFR2.790) Encl
Project stage: Request
ML20204F5851987-03-18018 March 1987
Errata to Rev 1 to Neutronics Design Methods & Verification
Project stage: Other
ML20204F6311987-03-18018 March 1987
Errata to Rev 1 to Reload Core Analysis Methodology Overview
Project stage: Other
ML20204F4781987-03-18018 March 1987
Errata to Rev 2 to Reload Core Analysis Methodology Overview
Project stage: Other
ML20205D7801987-03-23023 March 1987
Forwards Proprietary Info on Cycle 11 Core Reload Methodology,Including List of CESEC-III Basedeck Input Data descriptions,plant-specific Model Values & Specific Input Data.Info Withheld (Ref 10CFR2.790(b)(1))
Project stage: Other
ML20206A6261987-03-30030 March 1987
Advises That Proprietary Rev 1-P to CEN-347 (O)-P, Omaha Batch M Reload Fuel Design Rept, Will Be Withheld (Ref 10CFR2.790),per 870126 Request & C-E 870126 affidavit.C-E Reasons for Withholding Document from Public Listed
Project stage: Other
ML20206G8511987-04-0303 April 1987
Forwards Safety Evaluation Re 861117,870126,0309 & 18 Ltrs Concerning Changes to Listed Reload Core Methodology Repts for Cycle 11.Changes Acceptable
Project stage: Approval
ML20206G8671987-04-0303 April 1987
Safety Evaluation Re 861117,870126,0309 & 18 Ltrs Concerning Changes to Listed Reload Core Methodology Repts for Cycle 11.Changes Acceptable
Project stage: Approval
ML20206K1251987-04-14014 April 1987
Informs That 861117 & 870309 Requests for Withholding Identified Documents from Public Disclosure Granted
Project stage: Other
ML20206K5721987-04-15015 April 1987
Notifies of Determination That Util CESEC-Code Basedeck Listing Should Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended,In Response to Util 870323 Request & Supporting Affidavit
Project stage: Other
1987-01-26
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Omaha Public Power District 1623 Harney Ornaha. Nebraska 68102 2247 402/536 4000 March 9, 1987 LIC-87-140 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Ref erences:
1.
Docket No. 50-285 2.
Letter, OPPD (R. L. Andrews) to NRC (A. C. Thadani) dated November 17, 1986 (LIC-86-677) 3.
Letter, NRC (D. E. Sells) to OPPD (R. L. Andrews) dated December 2, 1986 4.
Letter, OPPD (R. L. Andrews) to NRC (D. E. Sells) dated January 26, 1987 (LIC-87-042)
Gentlemen:
SUBJECT:
Core Reload Methodology Changes for Cycle 11 Enclosed for your review and approval is OPPD's revised reload methodology overview consisting of the following analyses:
OPPD Nuclear Analysis, Reload Core Analysis Methodology Overview -
OPPD-NA-8301-P, Revision 2, dated November, 1986.
OPPD Nuclear Analysis, Reload Core Analysis Methodology, Neutronics Design Methods and Verification, OPPD-NA-8302-P, Revision 1, dated November, 1986.
OPPD Nuclear Analysis, Reload Core Analysis Methodology, Transient and Accident Methods and Verification - OPPD-NA-8303-P, Revision 1, dated November 1986.
Reference 2 provided OPPD's draft submittal of the enclosed analyses.
By Reference 3, OPPD received NRC review comments.
Reference 4 discussed OPPD's responses to these comments.
Review comments have been incorporated and noted in our final submittal.
Additionally typographical errors have been corrected as noted on the revision summary sheets.
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i U. S. Nuclear Regulatory Commission LIC-87-140 Page 2 Please note that this submittal contains a proprietary and a non-proprietary version of the analysis. We look forward to receiving your approval of this analysis.
Sincerely, A
R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Ave., N.W.
Washington, DC 20036 W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector
...i-,,...-.
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the matter of
)
)
OMAHA PUBLIC POWER DISTRICT
)
Docket No. 50-285 (Fort Calhoun Station,
)
Unit No. 1)
)
APPLICATION FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE Pursuant to Section 2.790(b)(1) of the regulations of the Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District ("the District")
submits this application to withhold certain information from public dis-closure. Applicant has obtained this information from documents which identify this information as being owned by Combustion Engineering, Inc. (CE) or by I
- Advanced Nuclear Fuels Corporation, (ANFC), formerly Exxon Fuel Company, Inc.
It is the opinion of CE and ANFC that the information in question contains trade secrets and/or privileged or confidential commercial or financial infor-mation. The CE and ANFC information was purchased by the District under a proprietary information agreement.
1 i
The information for which proprietary treatment is sought is contained in the following documents:
OPPD Nuclear Analysis, Reload Core Analysis Methodology Overview -
OPPD-NA-8301-P, Revision 2, dated November, 1986.
OPPD Nuclear Analysis, Reload Core Analysis Methodology, Neutronics Design Methods and Verification, OPPD-NA-8302-P, Revision 1, dated November, 1986.
OPPD Nuclear Analysis, Reload Core Analysis Methodology, Transient and Accident Methods and Verification, OPPD-NA-8303-P, Revision 1, dated November 1986.
These documents have been appropriately designated as proprietary.
2-This information was obtained by the District from documents for which CE and ANFC has executed affidavits which set forth the bases on which the information may be withheld from public disclosure by the Commission.
Respectfully Submitted, OMAHA PU IC POWER DISTRICT By R. L. Andrews Division Manager Nuclear Production Sworn to before me on this Q*
day of March 1987 saminaneum-meed m MELVA L EVANS g myceem. asp. 0-il-M S A>K MstA
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