ML17317B300: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSIoN NBR:7907060279 Du.DATE: 79/06/26 NOTARIZE(.NO FACIL:50"315 Donald C, Cook Nuclear Power Plantg Unit ig Indiana 8 50-316 Donald C, Cook Nuclear Power Planti Unit 2g Indiana 8 AUTH BYNAME AUTHOR AFFILIATION ANDERSON<T.M.1'les t inghouse E 1 ec t r i c Cor p.RECIP.NAME RECIPIENT AFFILIATION EISENHUTg D~Division of Operating Reactors
{{#Wiki_filter:}}
 
==SUBJECT:==
Advises that HESTDYN computer code analysis of benchmark problems will be completed by 790731, DISTRIBUTION CODE TO11S COPIES RECEIVED:LTR L'NCLSIZE: TITLE: Standard Generic Distribution NOTEs:$~g Q<g$gL Q&<fo z+-E.DOCKFT 05000315 05000316 RECIPIENT ID CODE/NAME INTERNAL: 1 NT A 11Ptu YDIRD 13 AD/ENGR 8 PR 15 ORB&#xb9;1 CHIEF 17 PLANT SYS BR 19, EEB 20 ORB&#xb9;0 CHIEF 22 ORB&#xb9;3 CHIEF 24 DIRECTOR DPM 26 DIRECTOR DSS 28 AD/PLANT SYS 3 I8,E 31 Lt'cR&#xb9;1 CHIEF 33 CONT SYS BR 35 REAC SYS BR 37 BR I NKMAN 39 AD/REAC SFGR<3 1 J SNE I Z I K/IE'DIRECTOR NRR EXTERNAL: u3 ACRS COP IKS LTTR ENCL 16 1 RECIPIENT ID CODE/NAME 10 DIRECTOR DOR 1?.AD/SYS 8 PRO 14 REAL SFTY BR 16 ORB&#xb9;2 CHIEF 18 ENV SPEC BR 2 NRC PDR 21 SKP BR 23 ENG BR 25 DEPUTY DIR D 27 AD/REAL SFTY 29 REAC SFGDS L 30 LHR&#xb9;?CHIEF 32 L ISR&#xb9;3 C HI E F 34 CORE, PERF BR 36 ANALYSIS BR 38 OELD 40 H THORNBERG/
02'E JORDAN/IF' PROGRAM SUPPO COPIES LTTR ENCL+gqN 6z~ting p JvL 6 1979 Go 0 TOTAL NUMBER OF COPIES REQUIRED: LTTR~ENCL 0 lj, II Westinghouse Electric Corporation 49LL'Ett Water Reactor Divisions PWR Systems Dtvisiat 8ox 355 Pittsburgtt Potnsylvettia 15230 NS-TMA-2105 D.Eisenhut Acting Director Division of Operating Reactors U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014
 
==Dear Mr.Eisenhut:==
June 26 1979 Ref: a.NS-THA-2094, T.M.Anderson to V.Stello b.WCAP 8252, Revision 1,"Documentation of Selected Westinghouse StructuraI Analysis Codes." c.Letter dated 6/26/79 from L.Shao of NRC to T.H.Anderson On June 22, 1979 Westinghouse representatives met with members of your Staff to review the listing for the'WESTDYN computer code.This review determined that the WESTDYN code as described in.Reference (b)utilizes acceptable methods of , modal combination and established the acceptability of the calculational methods used in WESTDYN for the re-analyses performed for the plants listed in Reference (a).During this review, it was requested that Westinghouse commit to solve,-using the WESTDYN code, a set of three benchmark problems provided by the NRC Staff in addition to those presented in Reference (b)and to provide the infor-mation (system layout, material properties, modelling information, response spectra inputs and analysis results)needed by the NRC Staff to perform a confirmatory analysis of the pressurizer surge line for D.C.Cook.The NRC Staff's request to perform these additional benchmark problems was confirmed by Reference (c).Satisfactory completion of the three additional benchmark problems and the con-firmatory analysis of the D.C.Cook surge line will result in generic approval of the WESTDYN computer code for response spectrum analysis.Westinghouse has committed to solve NRC benchmark problems 1, 4 and 323A.Based on our preliminary review of these problems, these analyses will be completed by July 3'i, 1979.As discussed with your Staff on June 22, 1979, it is possible that Westinghouse may have some difficulties in analyzing these problems with the WESTDYN code.If this occurs, we will consult with your Staff to obtain resolution of the difficulties and to establish an appropriate schedule for completion of the analysis.The information needed by the NRC to confirm the analysis of the D.C.Cook pres-surizer surge line is being compiled for transmittal to the NRC by July 13, 1979.If you have any further questions on this matter, please contact Hr.R.J.Sero (412-373-4189) or Mr.W.R.Sugnet (412-373-5131) of my staff.T.F.Timmons/keg cc: V.Noonan I T..Anderson, Manager Nuclear Safety Department-o pP>90706C Q7P gp.<R<Cy~(4 0 p 1~0%**y4 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I I I 799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 CENTRAL FILES Docket No.50-315 Docket No.50-316 JUN 22 1979 American Electric Power Service Corporation Indiana and Michigan Power Company ATTN: Mr.John E.Dolan Vice Chairman Engineering and Construction 2 Broadway New York, NY 10004 Gentlemen:
In accordance with our plans as described in our May 22, 1979, letter to you, the first of two direct and dedicated telephone lines was recently installed in your facility.This line is part of what has been designated the Off Premise Extension (OPX)network, an automatic ringing system that is designed to facilitate immediate notifications to the NRC of significant incidents and to provide continous and uninterrupted communication of operational information between your facility, the NRC Operations Center in Bethesda, Maryland, and the Regional Office during the course of such incidents.
We have been testing the OPX network on a daily basis for the past several weeks, and plan to continue on this schedule until confidence in the reliability of the network has been established and all problems have been eliminated.
After that we will continue the tests but at a reduced frequency.
A copy of the test procedure is provided as an enclosure to this letter for your information.
The OPX network is not to be used for routine communications with the NRC.It shall be used only for those events requiring immediate notifi-cation as defined in 10 CFR 20.403(a), and in IE Bulletin Series Nos.79-05,-06, and-08, which require notification within one hour of the time a reactor is not in a controlled or expected condition of operation.
In addition, the network shall be used where it is apparent that immediate NRC attention is necessary.
This may include some, but certainly not all, prompt notifications now required.We are now arranging for the installation of the second direct and dedi-cated line into your facility.This line will be part of what has been designated the Selective Signaling System (SS-4)network, a dial-up system-not automatic ringing, which is intended to be used during an~II Q8 Oq Okff American Electric Power Company-2-JUN 2 2 879 incident to provide continuous and uninterupted communication between your facility, the NRC Operations Center, and the Regional Office regarding radiological and environmental matters.You will be contacted soon regarding the installation of this second line.If'ou have any questions concerning these communications networks or any comments regarding their use, please contact A.B.Davis of my staff on 312-858"2660.
Sincerely, James G.Keppler Director
 
==Enclosure:==
 
As stated cc w/encl: Mr.D.V.Shaller, Plant Manager Central Files Director, NRR/DPM Director, NRR/DOR PDR I,ocal PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Citizens for a Better Environment RIII RIII H an/sr pier 6/22/79 TESTING OPX TELEPHONE NETWORK Test Schedule In order to minimize the impact on both NRC and licensees, test will be conducted during specified time periods as follows: Region I, IV, and V Iicensees 10 PM to Midnight EST Region II and III Licensees 5 AM to 7 AM EST P Frequency of the test will be daily until further notice.Test Procedure The Duty Officer at the NRC Operations Center calls the facility and identifies himself.2.The party answering is requested to identify himself.The NRC Duty Officer then requests that the answering party hang up the telephone when the NRC Duty Officer hangs up.3.4.The individual at the facility waits 10 seconds and then picks up the OPX telephone to initiate a signal at the NRC Operations Center.When the NRC Duty Officer answers, the individual identifies the facility from which he is calling.5.6.The NRC Duty Officer asks the caller to hold while a three party conference is established with the Regional Office Duty Officer.Each party identifies himself and determines the quality of the connection.
7.The test is terminated.
8.Any necessary corrective action is initiated by the NRC Duty Officer.NOTE: If, at any time, a licensee has reason to believe his phone is inoperable, he should immediately notify the Duty Officer at the NRC Operations Center at (301)492-8111.Extension Check Occasionally a check of earth extension at the facility will also be made.This check will be scheduled in advance by the Duty Officer in the NRC Operations Center to be performed at a time acceptable to facility personnel.}}

Revision as of 04:32, 24 October 2019

Advises That Westdyn Computer Code Analysis of Benchmark Problems Will Be Completed by 790731
ML17317B300
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/26/1979
From: Anderson T
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NS-TMA-2105, NUDOCS 7907060279
Download: ML17317B300 (6)
v • d • e


Text

Retrieved from "https://kanterella.com/w/index.php?title=ML17317B300&oldid=1971271"