ML17320A358

From kanterella
Revision as of 07:31, 29 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
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)


Text

REGULA f INFORMATIPN DISTRIBUTIO YSTEM (RIDS)

ACCESSION NBR;8302140044 DOC ~ DATE: 83/02/03 NOTARIZED: NO DOCKET,O FACIL:50-316 BYNAME Donald C..Cook Nuclear power Pl ant< Unit 2~ Indiana 8 05000316 AUTH 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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNAL: ASLB 30 1 1 ELD/HDS3 1 0 IE/DEP DIR 1 0 NRR BERGGREN 1 NRH DIR 1 0 NRR/DE/QAO 1 0 NRH/DE/SEB 1 0 NRR/DHFS/PTRB 1 0 NRR/DL D IR 0 NRR/DL/ADL 1 0 NRR/DL/ADOR 1 0 NRR/DL/ADSA 1 0 NRR/DL/LB1 1 0 NRR/DL/LB2 1 0 NRR/DL/LB3 0 NRR/DL/LB4 1 0 NRH/DL/ORAB 1 0 NRR/DL/ORB1 1 0 NRR/DL/ORB2 1 0 NRR/DL/ORB3 1 0 NRR/DL/ORBQ 0 NRR/DL/ORB5 1 0 NRH/DL/SEPB 1 0 NRR/DL/SSPB 1 0 NRR/DSI DIR 1 0 NRR/DS I/AEB 1 0 NRH/DSI/ASB 1 0 NRR/DS I/CPS 1 0 NRH/DSI/ICSB 1 0 NRR/DS I/METB 1 0 NRR/DS I/RA8 0 NRR/DS I/RSB 1 0 NRH/DST DIR 1 0 NRR/DST/GIB 1 0 NRR/DST/RRAB 1 0 NRR/DST/RSCB 1 0 NRR/DST/SPEB 1 0 NRR/TMIPO D IR 1 0 03 2 2 RES 1 1 Ni 1 0 RGN2 1 0 RGN3 1 0 RGN4 1 0 RGN5 1 0 XTRA CCBERGGREN 6 6 EXTERNALS ACRS 13 13 13 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 06 1 1 TOTAL NUMBER OF COPIES REQUIRED'TTR 68 ENCL 27

~ I 'fr 4I

~ I' ff r9 Q f 1 I o e 0 414!4

')44 I

f I',',"4

.'h IJ

$ lf ff f" 44 lf'W, I I' I

ll I I I fi' }4 tl II q'

'l 'fl!4 nn mr ma n n I 'r (

1 Ir 'i

) o' I I fr r+ 4 li JI c/rqf f)f Il II frf

'rf

'4 1

J fK f

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

~O( CI P PDR L AN AFFIUATEOF 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 DOCKS.T .0 FACIL:50-316 Dona'la C, Coot >nuclear Power Pl anti Unit 2i Indiana 05000316 A U T If f'i Al"iE

~ AUT)f~R ArFILIATIQN ChAt OLERi J.C. Exxon iNuc ear Co. Inc. (subs. of Exxon (:orp.)

HEC IP Ic.N f'FF ILIAT 1 <

HEC IP. NAi'E C.O. Star oardi zati on 6 Special Proj ec ts Brancn IGi'b(jVAS>

SUBJECl': Recuests generic review ot PTS-P'lvH2 pla nt transient slirulator coce oe reactivated<due to vi fficulty encountered in uC Cook unit 2 Cycle 4 review OISTRIBUl IuN CuDE: Tolus COPIES RLCEIvEO:LTH I

Ef~CL l TITLE: Non-Proprietary Topical Report N('ES:

P RECIPIENT iOP IES REC IP I tf< T COPIES I 4 CODE/i~'At'~E LTT R Ef<CL ID CODE/AAkE LTTH ENCL INTEHf AL: ASLB 3V 1 1 ELO/HOS3 0' IE/DEP 0 IR 1 0 NRR BERGGREN NRH DIR 1 0 NRR/DE/QAU 0 NR~/OE/SEB 1 0 NRR/OHFS/PTRB 0 NHf(/DL OIf 1 0 NHR/OL/AOL 0 NRH/DL/ADOR 1 0 NRR/OL/AOSA 0 NHr(/DL/Ldl 1 0 NRR/OL/Ld2 0 i4RK/OL/LU3 1 0 fuwR/OL/LB'RR/DL/ORB1 0

hH~/DL/OHAB 1 0 0 NR~/OL/0882 1 0 NHR/Ot./ORB3 0 r."RH/uL/OH&9 1 0 NRR/DL/uRBS G NRh/DL/SEPu 1 0 NRR/DL/SSPB 0 NR~/OSI DID 1 0 NHR/DS I/AEB

  • 0 lvRrt/DS I/ASd 1 0 NRR/DSI/CPS V ivR~/OSI/ICSB 1 0 NR R/DS I /iME Tb 0 NRw/OS I/RAG 1 0 NRR/DS I/RSB 0 ERR/DST OIR 1 0 NiRR/DST/GIB 0 ERR/OST/RRAB 1 0 NRH/OST/RSCB 0 NRH/OST/SPEB 1 0 NRR/TNIPO OIR 0 REG FILE 03 2 RES 1 HGN1 1 0 RGN2 U RGn3 1 0 RGNA 0 RGi'i5 1 0 XTRA CCBEHGGHEN 0 EXTEHhAL: ACHS 13 13 NHC PDR 02 1 1 NSIC 05 1 NTIS 06 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

~o( c P PDR V

AN AFFIUATIOF EXXON CORPORATION

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.

J. C. Chandler Reload Fuel Licensing JCC:gf CC: Hr. J. S. Berggren (USNRC)