ML17194B428

Forwards Ref Pages from XN-NF-80-19 (P),Vol 4 & XN-NF-82-77 (P),Applicable to Cycle 9 Reload.Transmittal Ltr Dates for SERs Identified.List of All Exxon Computer Programs Will Be Provided by 830118

ML17194B428
Person / Time
Site:	Dresden
Issue date:	01/13/1983
From:	Chandler J SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Gill A Office of Nuclear Reactor Regulation
References
JCC:008:83, JCC:8:83, NUDOCS 8301180132
Download: ML17194B428 (5)

Text

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. e E)${0N NUCLEAR -COMPANY, Inc.

I' 2101 Hom Rapids Road P. a Bai 130, Richland, Washington 99352 Phone: (509)375-8100 Telex: 15-2878 Ms. Amira M. Gill Core Performance Branch Division of Systems Integration Office of Nuclear Reactor Regu~ation U. S. Nuclear Regulatory Comm~ssion Washington, D. C.

20555

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January 13, 1983 JCC:008:83

SUBJECT:

Approval Date~ for ENC Referenc~s in the Dresden Unit 2 Cycle 9 Reload Submittal

Dear Ms. Gill:

As. you requested, I have enclosed copies of the reference pages from XN-NF-80-19(P), Volume 4, and XN-NF-82-77(P), both of which are applicable to the Dresden Unit 2 Cycle 9 reload.

On the appropriate places on these reference pages, I have identified the dates of the transmittal letters for the NRC Staff Safety Evaluation Reports accepting the documents for referencing in.

future submittals. The names of the computer codes in each of these reports are listed in the document titles except in the case of XN~NF-80-19, Volume i, which encompasses a number of computer programs.

• The neutronics codes specifically treated therein are the XFYRE fuel assembly depletion model, the XTGBWR core simulator, the COTRAN reactor kinetics model, the XDT diffu~ion theofy model, and the XMC Monte Carlo model, all of which are used for the analysis of boiling water reactors.

This document also reports a generic control rod drop* accident analysis for jet-pump BWRs and provides docu-mentation for the power distribution uncertainties used in the generation of the MCPR Fuel Cladding Integrity Safety Limit using ENC methods.

Also as you requested, we are preparing a listing of all of the ENC computer programs formally accepted by the NRC Staff s i nee 1975.

We wi 11 provide a listing of these reports and the dates of formal acceptance by January 18, 1983.

• If you have any questions or comments, please feel free to call,.

telephone (509) 375-8639.

JCC:gf

.Enclosures As noted CC:

Mr. J.

Mr. T.

8301180132 830113 PDR.ADOCK 0500ca37

~P-PDR Sincerely, 5f<~f J. C. Chandler Reload Fuel Licensing f}ool __

S. Berggren (USNRC)

J.,_Rat,1sch (Commonwealth Edison)

AN AFFILIATE OF EXXON CORPORATION

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• X N -NF 19 ( P )

Volume 4

8.0 REFERENCES

FOR EXXON NUCLEAR* METHODOLOGY FOR

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• BOILING WA1ER REACTORS The following referenced reports describe the ENC methodology for the analysis of jet-pump boiling water reactors. They are incorporated into this submittal by reference.

@xN-NF-80-19(A), Volume 1, May 1980 0_4_/_7_/_8_7:)

Exxon Nuclear Methodology for Boiling Water Reactors Neutronics Methods for Design and Analysis XN-NF-80-19(A), Volume 2, Revision 1, June 1981 (\\ / 2. 7 Is?;)

Exxon Nuclear Methodology for Boiling Water Reactors EXEM: ECCS Evaluation Model, Surrrnary Description XN-NF-80-19(A), Volume 2A, Revision 1, June 1981 G /27 /sv Exxon Nuclear Methodology for Boiling Water Reactors RELAX: A RELAP4 Based Computer Code for Calculating Slowdown Phenomena XN-NF-80-19(A), Volume 2B, Revision 1, June 1981 (1/27/ai;)

Exxon Nuclear Methodology for Boiling Water Reactors FLEX: A Computer Code for Jet Pump BWR Refill and Reflood Analysis XN-NF-80-19(A), Volume 2C, June 1981 (j]27 /8V Exxon Nuclear Methodology for Boiling Water Reactors Verification and Qualification of EXEM

. 8.6 XN-NF-80-19(P), Volume 3, Revision 1, April 1981 Exxon Nuclear Methodology for Boiling Water Reactors THERr~EX: Thermal Limits Methodology, Surrrnary Description XN~CC-33(A), Revision l, November 1975

<1.2q" / 7V HUXY: A Generalized Multirod Heatup Code with OCFRSO

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Appendix K Heatup_Option 8.8 XN-NF-79-7l(P), Revision 2, November 1981 Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors

/@ XN-NF-512(A), Revision 1, March 1981 Q/2-2/si)

The XN-3 Critical Power Correlation 8.10 XN-NF-524{P), November 1979 Exxon Nuclear Critical Power Methodology for Boiling Water Reactors U.., ~.

ll***llltlll or dixtosln ot ttw 8boYe inform*liau i9 sutliect tD the *08'Jictian an ttw first or tttlf 1>>99 of ttiia doc:ument *

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Volume 4 8.11 XN-NF-79-59(P), October 1979 Methodology for Calculation of Pressure Drop in BWR Fuel Assemblies 8.12 XN-NF~81-22(P), September 1981 Generic Statistical Uncertainty Analysis Methodology 8.13 XN-NF-81-58(P), August 1981

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ROOEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model

@xN-NF-82-07(P), January 1982 Jo/14-/82.

Exxon Nuclear Company ECCS Cla ing we ing and Rupture Model Use. reproduction, tr*namittal or disclosure of the above information is subject to the restriction on the first or title page of this document.

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I 33 9.0 ADDITIONAL REFERENCES

-XN-NF-80-19(P)

Volume 4 Although not speciflcally identjfied as part *of the Exxon Nuclear Methodology for Boiling Water Reactors listed in Section 8.0, the followiryg referenced documents provided generic analyses or other pertinent information.

@ S. F. Gaines, "Generic Mechanical Design for Exxon Nuclear...J7t Puma 9 Reload Fuel," XN-NF-81-2l(A), Revision 1, January 1982. (!! Uo/82-

@J.E. Krajicek, "Generic Jet Pump BWR 3 LOCA Analysis Usin NC EXEM Evaluation Model," XN-NF-81-7l(A), October 1981.

t/27/8Z 9.3 U. S. Nuclear Regulatory Corrmission, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,"

NUREG-0800, July 1981.

9.4 General Electric Company, "General Electric Boiling Water Reactor Generic Reload Fuel Application," NED0-24011-A, July 1979.

Use, reproduction.transmittal or disct*:wre of the above information is subject to the restriction on tht first or title page of this document.

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'XN-NF-82-77(P) 9.0 ADDITIONAL REFERENCES S. F. Gaines, aGeneric. Mechanical Design for Exxon Nuclear Jet ~

BWR Reload Fuel,a XN-NF-81-21(A), Revision 1 (January 1982). (80/~

9.2 R. H. Kelley, wExxon Nuclear Plant Transient Methodology for Boiling Water Reactors,u XN-NF-79-71, Revision 2 {November 1981).

9.3 R. H. Kelley, "Plant Transient Analysis Report for Dresden Unit 2 Cycle 9," XN-NF-82-84 (October 1982).

9.4 R.H. Kelley, "Dresden Unit 3 Analyses for Reduced Flow Operation," XN-NF-81-:84 (December 1981).

J. E. Krajicek, "Generic Jet Pump BWR3 LOCA Analysi'S

• n the ENC EXEM Evaluation Model," XN-NF-81-7l(A) (October 1981). 1//-7/82.

9.6 0. J. Braun and P. J. Valentine, "Dresden Unit 2 LOCA Analysis Using the ENC EXEM/BWR Evaluation Model; MAPLHGR Results," XN-NF-82-88 (October 1982).

9.7 J.C. Chandler, "Dresden Unit 3 Cycle 8 Reload Analysis," XN-NF-81-76, Revision 1 (December 1981).

9.8[5. Pimputkar and M. Gross, "The Thermal-Hydraulic Performance of an 8.1-J Rod Bundle Under Boiling Water Reactor Conditions," European Two-Phase Flow Group, Ispra, Italy, June 5-7, 1979.

u~. reproduction. transmittil or disclosure of tht 1boYe information 15 subiect to the restriction on the first or lltlt pq of this document.