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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Omaha Public Power District 1623 Harney Omaha Nebraska 68102 402/536-4000 October 8,1984 L IC-84-310 Mr. James R. Miller, Chief U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Operating Reactors Branch No. 3 Washington, D.C.
20555
Reference:
Docket No. 50-285
Dear Mr. Miller:
Submittal of CESEC-III Code Topical Your letter of May 11, 1984, containing the staff's safety evaluation of the District's reload core analysis methodology report contains a request for the District to submit a topical report for the CESEC-III Code. The District has considered your request and submits the following infonnation.
The District's Transient and Accident Methods and Verification Topical Re-port, OPPD-NA-6303-P, references numerous CESEC topical reports which have been submitted to the NRC. Specifically, references 4.9 and 4.10 provided documentation of the CESEC-III code. The District believes that referencing a topical report, previously schmitted to the NRC, on our docket is equiva-lent to submitting the report itself. Therefore, it is the District's pos-ition that we have satisfied the intent of submitting a topical report on the CESEC-III Code.
It should be noted that the District neither owns nor leases the CESEC-III Code from Combustion Engineering (CE). Rather, the District utilizes a compiled version of the CESEC-III code on the CE computer systen.
It would be inappropriate for the District to directly submit the CESEC-III topical report since we are neither the authors of the topical report nor fully cognizant of the details contained in previous topical reports submit-ted by CE.
The staf f's safety evaluation of the District's transient and accident anal-1 ysis topical report requests the District demonstrate the applicability of the CESEC-III code to Fort Calhoun Station. This applicability is demon-strated by the fact that the CESEC code is a digital simulation of a CE (pressurized water reactor) Nuclear Steam Supply System (NSSS).
The CESEC-III code models primary system components and secondary system components.
The primary system components considered in the code include the reactor vessel, the reactor core, primary coolant loops,.he pressurizer, the steam puoiB88aan8%
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- Mr. James R. Miller Octooer 8,1984 Page Two generators and the reactor coolant pumps. The secondary systen component mod-els include the secondary side of the steam generators, the main steam system, feedwater system and various steam control valves.
In addition, the program models some of the control and plant protective systems. The Fort Calhoun re-
- actor is a typical CE NSSS.
It consists of a pressurized water reactor with two steam generators, four reactor coolant pumps, two hot legs and four cold legs. The Fort Calhoun reactor is nodalized in accordance with the schemes given in' Reference 4.9 of the OPPD Transient and Accident Methods and Verifica-tion Topical Report. The CESEC-III code was designed for the typical CE NSSS and since Fort Calhoun Station is a typical CE NSSS, the CESEC code is, in es-sence, designed for the class of NSSS's of which Fort Calhoun Station is a mem-ber.
In addition, the District's verification of the CESEC-III code demon-strates that the CESEC-III code can be properly applied to Fort Calhoun Sta-tion and can accurately simulate transients which occurred at the station.
The District believes that this provides adequate demonstration that the CESEC-III' code is applicable to Fort Calhoun Station.
Sincerely, R. L. Andrews Division Manager Nuclear Production RLA/JKG/rh-S cc:
LeBoeuf,-Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, D.C.
20036 Mr. E. G. Tourigny, NRC Project Maneger Mr..L. A. Yandell, Senior Resident Inspector
