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{{#Wiki_filter:REGULA f INFORMATIPN DISTRIBUTIO YSTEM (RIDS)ACCESSION NBR;8302140044 DOC~DATE: 83/02/03 NOTARIZED:
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NO DOCKET,O FACIL:50-316 Donald C..Cook Nuclear power Pl ant<Unit 2~Indiana 8 05000316 AUTH BYNAME AUTHOR AFFILIATION CKANDLER<J,C, Exxon Nuclear Co~r Inc, (subs, of Exxon Corp.)RECIP~NAMF-RECIPIENT AFFILIATION THOMASgC F 0'tandardization 8, Special Projects Branch
 
==SUBJECT:==
Requests generic review of PTS-PNR2 plant transient simulator code be reactivated,due to difficulty encountered in DC Cook Unit 2 Cycle 4 review, DISTRIBUTION CODE: T010S COPIES RECEIVED:LTR ENCL.SIZEo TITLE: Non"Proprietary Topical Report NOTES: RECIPIENT ID CODE/NAME INTERNAL: ASLB 30 IE/DEP DIR NRH DIR NRH/DE/SEB NRR/DL D IR NRR/DL/ADOR NRR/DL/LB1 NRR/DL/LB3 NRH/DL/ORAB NRR/DL/ORB2 NRR/DL/ORBQ NRH/DL/SEPB NRR/DSI DIR NRH/DSI/ASB NRH/DSI/ICSB NRR/DS I/RA 8 NRH/DST DIR NRR/DST/RRAB NRR/DST/SPEB 03 Ni RGN3 RGN5 COPIES LTTR ENCL 1 1 1 0 1 0 1 0 0 1 0 1 0 0 1 0 1 0 0 1 0 1 0 1 0 1 0 0 1 0 1 0 1 0 2 2 1 0 1 0 1 0 RECIPIENT ID CODE/NAME ELD/HDS3 NRR BERGGREN NRR/DE/QAO NRR/DHFS/PTRB NRR/DL/ADL NRR/DL/ADSA NRR/DL/LB2 NRR/DL/LB4 NRR/DL/ORB1 NRR/DL/ORB3 NRR/DL/ORB5 NRR/DL/SSPB NRR/DS I/AEB NRR/DS I/CPS NRR/DS I/METB NRR/DS I/RSB NRR/DST/GIB NRR/DST/RSCB NRR/TMIPO D IR RES RGN2 RGN4 XTRA CCBERGGREN COPIES LTTR ENCL 1 0 1 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 1 1 0 1 0 6 6 EXTERNALS ACRS NSIC 13 13 13 05 1 1 NRC PDR NTIS 02 06 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED'TTR 68 ENCL 27
~I'fr 4I ff r9 Q f 1 I~I'o e 0 414!4 I I',',"4$lf')44 f.'h IJ ff f" 44 lf'W, I I I'll I I I fi'}4'l'fl!4 tl II q'n nn mr ma n I'r 1 (Ir'i)o'I I fr r+4 li JI c/rqf f)f II Il frf'rf'4 1 J f fK hl r I q 4'Q e 14r 11 2101 Hom Bepids 11ood P.D Box 130 RicNand,@habington 8%52 Phone: (509)375-8100 Telex: 15-2878 February 3, 1983, JCC:026:83 Dr.Cecil 0.Thomas, Chief Standardization 8 Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
 
==SUBJECT:==
XN-74-5, Rev.1,"Description of the Exxon Nuclear Plant Transient Simulation Model for Pressurized Water Reactors (PTS-PWR)," dated May 15, 1975
 
==Dear Dr.Thomas:==
During the course of the review of the licensee's application for license amendment supporting Cycle 4 operation of the D.C.Cook Unit 2 power plant, questions were raised by the Staff reviewer relative to the approval of ENC's PTS-PWR2 plant transient simulator code for pressurized water reactors.The PTS-PWR2 plant transient simulator code is described in the subject report.This report was submitted in 1975 for Staff review and approval in support of the initial insertion of ENC fuel into the H.B.Robinson nuclear power plant.Since that time, PTS-PWR2 has been accepted as licensing basis for a number of PWR license amendments.
Generic review of PTS-PWR2 proceeded to the generation of a draft Safety Evaluation Report which has never been issued.According to NUREG-0390, Topical Report Review Status, this SER has not been issued because acceptance review criteri a are being established for review of accident analysis programs.During the D.C.Cook Unit 2 Cycle 4 review, the Staff reviewer asked for additional information describing PTS-PWR2.In response to that request, we provided the reviewer with copies of XN-CC-38,"User's Manual for PTSPWR2: A FORTRAN Program for Simulation of Pressurized Water Reactor Plant Tran-sients," and XN-CC-38, Supplement 1.These reports expand the initial issue of XN-74-5 with user-oriented information, and describe an improved pres-surizer model which was implemented in support of the initial insertion of ENC fuel into the Ft.Calhoun nuclear power plant.XN-CC-38 is a revision of XN-74-5.8302i40044 830203 FDR AoaCV 0S000316 P PDR L~O(CI AN AFFIUATE OF EXXON COIIPOAATION Dr.C.O.Thomas (NRC)February 3, 1983 Because of the difficulty encountered in the D.C.Cook Unit 2 Cycle 4 review, we would like to reactivate the generic review of PTS-PWR2 and complete the issuance of the generic approval of the code for use in the analysis of PWR plant transients.
If you have any questions regarding this request, please feel free to call, telephone (509)375-8639.Sincerely, u''.C.Chandler Reload Fuel Licensing JCC:gf CC: Mr.J.S.Berggren (USNRC) 0 HcGULATuP f INFO)ct~wTIO)i DISThIo(iTIQfu SYS1EH (RInS>A(:CESS I VN NeH: 83021400<>4 UUC~GATE.: 83/02/03 fl(TAH IZED.: ifO FACIL:50-316 Dona'la C, Coot>nuclear Power Pl anti Unit 2i Indiana A U T If~f'i Al"iE AUT)f~R ArFILIATIQN ChAt OLERi J.C.Exxon iNuc 1 ear Co.<Inc.(subs.of Exxon (:orp.)HEC IP.NAi'E HEC IP Ic.N f'FF ILIAT IGi'b(jVAS>
C.O.Star oardi zati on 6 Special Proj ec ts Brancn DOCKS.T.0 05000316 SUBJECl': Recuests generic review ot PTS-P'lvH2 pla slirulator coce oe reactivated<due to vi in uC Cook unit 2 Cycle 4 review OISTRIBUl IuN CuDE: Tolus COPIES RLCEIvEO:LTH I TITLE: Non-Proprietary Topical Report N('ES: nt transient fficulty encountered Ef~CL l RECIPIENT I 4 CODE/i~'At'~E iOP IES LTT R Ef<CL P REC IP I tf<T ID CODE/AAkE COPIES LTTH ENCL EXTEHhAL: ACHS NSIC 13 05 INTEHf AL: ASLB 3V IE/DEP 0 IR NRH DIR NR~/OE/SEB NHf(/DL OIf NRH/DL/ADOR NHr(/DL/Ldl i4RK/OL/LU3 hH~/DL/OHAB NR~/OL/0882 r."RH/uL/OH&9 NRh/DL/SEPu NR~/OSI DID lvRrt/DS I/ASd ivR~/OSI/ICSB NRw/OS I/RAG ERR/DST OIR ERR/OST/RRAB NRH/OST/SPEB REG FILE 03 HGN1 RGn3 RGi'i5 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 13 1 ELO/HOS3 NRR BERGGREN NRR/DE/QAU NRR/OHFS/PTRB NHR/OL/AOL NRR/OL/AOSA NRR/OL/Ld2 fuwR/OL/LB'RR/DL/ORB1 NHR/Ot./ORB3 NRR/DL/uRBS NRR/DL/SSPB NHR/DS I/AEB*NRR/DSI/CPS NR R/DS I/iME Tb NRR/DS I/RSB NiRR/DST/GIB NRH/OST/RSCB NRR/TNIPO OIR RES RGN2 RGNA XTRA CCBEHGGHEN NHC PDR 02 NTIS 06 0'0 0 0 0 0 0 0 0 G 0 0 V 0 0 0 0 0 1 U 0 0 1 1 1 1 TOTAL N((4UEH OF COPlES~EuUIRtD: l TTR 68 Er~CL 27
 
0 EQON NUCLEAR COMPANY, Inc.2101 Hom Jhpii&Road P.0 Box 13g Richland, Ssdungton 8%$Z Phone: (509)375-8100 Telex: l 5-2878 February 3, 1983 JCC:026:83 Or.Cecil 0.Thomas, Chief Standardization 5 Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
 
==SUBJECT:==
XN-74-5, Rev.1,"Description of the Exxon Nuclear Plant Transient Simu)ation Model for Pressurized Water Reactors (PTS-PWR)," dated May 15, 1975
 
==Dear Dr.Thomas:==
During the course of the review of the licensee's application for license amendment supporting Cycle 4 operation of the D.C.Cook Unit 2 power plant, questions were raised by the Staff reviewer relative to the approval of ENC's PTS-PWR2 plant transient simulator code for pressurized water reactors.The PTS-PWR2 plant transient simulator code is described in the subject report.This report was submitted in 1975 for Staff review and approval in support of the initial insertion of ENC fuel into the H.B.Robinson nuclear power plant.Since that time, PTS-PWR2 has been accepted as'icensing basis for a number of PWR license amendments.
Generic review of PTS-PWR2 proceeded to the generation of a draft Safety Evaluation Report which has never been issued.According to NUREG-0390, Topical Report Review Status, this SER has not been issued because acceptance review criteria are being established for review of accident analysis programs.During the D.C, Cook Unit 2 Cycle 4 review, the Staff reviewer asked for additional information describing PTS-PWR2.In response to that request, we provided the reviewer with copies of XN-CC-38,"User's Manual for PTSPWR2: A FORTRAN Program for Simulation of Pressurized Water Reactor Plant Tran-sients," and XN-CC-38, Supplement 1.These reports expand the initial issue of XN-74-5 with user-oriented information, and describe an improved pres-surizer model which was implemented in support of the initial insertion of ENC fuel into the Ft.Calhoun nuclear power plant.XN-CC-38 is a revision of XN-74-5.8302i40044 B30203 PDR ADGCK 050003l6 P PDR~o(c AN AFFIUATI OF EXXON CORPORATION V
1 Dr.C.O.Thomas (NRC)February 3, 1983 Because of the difficulty encountered in the D.C.Cook Unit 2 Cycle 4 review, we would like to reactivate the generic review of PTS-PWR2 and complete the issuance of the generic approval of the code for use in the analysis of PWR plant transients.
If you have any questions regarding this request, please feel free to call, telephone (509)375-8639.JCC:gf CC: Hr.J.S.Berggren (USNRC)J.C.Chandler Reload Fuel Licensing}}

Revision as of 23:09, 23 October 2019

Requests Generic Review of PTS-PWR2 Plant Transient Simulator Code Be Reactivated,Due to Difficulty Encountered in DC Cook Unit 2 Cycle 4 Review
ML17320A358
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 02/03/1983
From: Chandler J
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To: Thomas C
Office of Nuclear Reactor Regulation
References
JCC:026:83, JCC:26:83, NUDOCS 8302140044
Download: ML17320A358 (9)
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