Letter Sequence Other |
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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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ggggggggggg February 27 1987 LD-87-013 i.
Mr. Frank J. Miraglia Associate Director for Projects clo Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
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Subject:
Applicability of CESEC-III to the Fort Calhoun Station
Reference:
"CESEC, Digital Simulation of a Combustion Engineering Nuclear Steam Supply System", Enclosure 1-P to LD-82-001, January 6, 1982.
/
Dear Mr. Miraglia:
.r A gaestion has been raised recently as to the applicability of CESEC-III to the Ft. Calhoun Station. The purpose of this letter is to inform you that '
the CESEC-III computer code (Reference) is applicable to the analysis of FSAR Chapter 14 events (excluding ATWS) for.the Fort Calhoun Station.
which is owned and operated by the Omaha Public Powes District (OPPD).
As documented in the referenced letter, 'CESEC-III was developed for the analysis of FSAR transient and accident events for the two-by-four loop Nuclear Steam Supply Systems (NSSSs) designed by Combustion Engineering (C-E).
The Fort Calhoun Station is one of thotlants for which CESEC-III was developed. OPPD's engineering staff was trained extensively in the proper use of CESEC-III and a close consultativ6 relationship has been maintained between this staff and the C-E. team which developed CESEC-III. This has ensured that the CESEC-III models remained applicable to Fort Calhoun even after C-E ceased to be the primo contractor for Fort Calhoun safety analyses. As a result, the wdois included in CESEC-III are applicable to the operating conditions at the Ft.
Calhoun Station and cover all features of the Fort Cdhoun NSSS which are significant for Chapter 14 analyses.
\\
0 h0 8703040072 870227 3
PDR ADOCK 05000285 I 0 P
PDR t
Power Systems 1000 Prespect Hdt Road (2M 688. s911 Combuston Engincenng, Inc.
Post Offee Box 500 Telet W297 Windsor, Connecteut 060954500 l
v.
Mr. Frank J. Miraglia -
LD-87-013 February 27 1987 Page 2 If you have any question, please feel free to contact me or Mr. L.E.
Philpot of my staff at (203) 285-5210.
Very truly 'yours, COMBUSTION ENGINEERING,INC.
h $5 k.E.Schehr Director Nuclear Licensing AES:ss xc:
R. L. Andrews (OPPD)
J. J. Fisicaro (OPPD)
P. H. Harrell (NRC)
J. Lyons (NRC)
W. A. Paulson (NRC)
