ML17334A872

Forwards 850402 Ltrs Re Description of Loca/Eccs Models Used by Exxon Nuclear Co in Response to 850329 Request. Error Described in Exxon 850322 Ltr GFO:85:010 Applicable to Unit 1 Only

ML17334A872
Person / Time
Site:	Cook
Issue date:	04/03/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0745V, AEP:NRC:745V, NUDOCS 8504120194
Download: ML17334A872 (21)

Text

REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR'8504120194 DOC ~ DATE: 85/0<>/03 NOTARIZED:" NO T" 0 FACIL':50 315 Donald O, -Cook Nuclear'ower Planti Un) t ii Indiana 8 50 316 Donald O, Cook- Nuclear Power Planti Unit 2< Indiana 8 05000316 AUTH',NAME AUTHOR AFF ILIATION ALEXICHiM,P, Indiana L Michigan E~lectr ic -Co ~

RECIP ~ NAME RECIPIENT AFFILIATION DENTONiH ~ R~ Office> of Nuclear Reactor~ Regulationr Director>>

SUBJECT:

Forwards" 850402'.trs re descpiption of LOCA/KOCS,modelp-used by Exxon Nuclear Co in response to described in Exxon 850322'tr GFO':845:010 applicable 850329,request",'r'ror to Uni,t 1 on-lye DISTRIBUTION CODE: A001D OR

'COPIES RECK'/ED:LTR Submittal! General Distribution "ENCL "

SIZE ~ '" 'ITLE:

NOTES; 05000315".

OL ~ 10/25/70 OL'+ 12'/23/72" .-05000316'EC IP IKNT COPIES RECIPIENT COPIES'TYR'NCL" ID CODE/NAME[ LTTR ENCL ID CODE/NAME1 NRR ORB1 BC'1 7 t

7 INTERNALS ACRS 09 6 6 ADM/LFMB 1 0 KLD/HDS3- fa 0 NRR/DE/MTKB 1 1 NRR/DL DIR 1 1 NRR/DL/DRAB 1- 0 NRR/DL'/TSRG=- 1 "'

1 1 1" NRR/DSI/RAB 1 04 1 1 RGN3 1 1 EXTERNAL EGLG BRUSKE'gS 1 1 LPDR 03 2I'I 2(

NRC PDR- 02". 1 1 NSIC 05- 1

'TOTAL NUMBER OF COPIES REQUIRED'TTR 28 ENCL'5

V 1

v A t 1

4 i'

1 i

4 tl

INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 AEP:NRC:0745V April 3, 1985 Donald C. Cook Nuclear Plant Units No. 1 and 2 Docket No. 50<<315, 50-316 Lioense No. DPR-58, DPR-74 DESCRIPTION OF LOCA/ECCS MODELS USED BY EXXON NUCLEAR COMPANY Mr. Harold R. Denton, Director Office of Nuolear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

This letter is submitted pursuant to discussions with your staff concerning the LOCA/ECCS models used by Exxon Nuolear Company for analysis of the Donald C.. Cook Nuclear Plant, Units 1 and 2. Attached please find letter HGS: 100:85 and ENC>>AEP/0437, both dated April 2, 1985, whioh desoribe the LOCA/ECCS models used for D. C. Cook Units 1 and 2, respectively. We are immediately forwarding this information as requested by members of your staff during a meeting on March 29, 1985.

It is of note that we were advised by Exxon Nuolear Company that the coding error described in their letter GFO:85:010, dated Maroh 22, 1985, is applioable to Unit 1 only. The Unit 2 information is being transmitted for completeness and future reference purposes.

This document has been prepared following Corporate procedures whioh inoorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. P. Al xioh Vise President g /

JLB:wg Attachments 8504i20i94 850403 PDR ADOCK 050003i5 PDR P

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Mr. Harold R. Denton AEP:NRC:0745V Attachments: A. HGS:100:85, dated April 2, 1985, from H. G. Shaw to J. L. Bell B. ENC-AEP/0437, dated April 2, 1985, from H. G. Shaw to G. John cc: John E. Dolan W. G. Smith, Jr. - Bridgman George Bruchmann R. C. Callen R. Charnoff NRC Resident Inspector - Bridgman G. F. Owsley, ENC - Richland, WA

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E+0N NUCLEAR COMPANY, INC.

g+ I(QTIIAVBIIQQNt,I O BOX 90TTT BELLEVJE.WAS8000 I200) 4S3.4300 April 2, 1985 HGS:100:85 Mr. 3. L. Bell Nuclear Materials & Fuel Mgmt.

Indiana & Michigan Electric Co,

, c/o American Electric Power Service Corp.

One Riverside Plaza Columbus, OH 43216-6631 Qesr Joe:

This information is provided to you in accordance with Exxon Nuclear's agreement with the NRC in a meetin j on March 29, 1985.

Attached is a description of models used by Exxon Nuclear to analyze the D. C. Cook 1 Plant prior to determination of coding misformulation and a description of models used after the coding misformulation was cor" rected. These corrected models provide part of the basis for your current operation. The descriptions are structured to be included as a pert of an NRC submission.

Please contact us if you have any questions regarding this attach" Very truly yours, Cont r ac t Adminis tra t or t lm Attachment c: M. P. Alcxich J. M. Cleveland II>ra III.

paE AII 4f FaI IAIDO OF fXXOH COR~QII4I IOII

Table 1 D.C. Cook Unit 1 LOCA/ECCS Model Sugary Prior Prior Current+

~Anal sis ~Anal sis ~Anal sis

1) Fission Gas Release Model WREM-I I EXEM

2) Stored Energy Model EXEM EXEM

3) Blowdown Model WREN WREN WREN

4) Containment Model WREN-II WREN- I I WREM-II

5) Clad Swelling and Rupture Model WREN-I I EXEM EXEM

6) Ref lood Model a} Car ryout and quench Correlation WREN WREN b) Oowncomer/Upper Plenum Leakage NO NO NO c) Break Model Sp 1 it Split Sp 1 it CO - l.o CO = 1.0 CO 1.0 d) Core Outlet Enthalpy Model OFF OFF OFF e) Z-Equsivalent Model OFF OFF OFF 7} Heatup Model a} Steam Cooling Model WREM EXEM EXEM b Heat Transfer Correlation WREN-II WREN-II WREM-II c) Mixing Vane Multiplier OFF OFF OFF d) t Local Peak ing Mu 1 i p 1 i er OFF OFF <<<< OFF e) 2-Equivalent Model NREM WREN WREN f) Radiation Model OFF ON ON 8} Documentation of Results XN-NF-81-07 XN-NF-83-61 Letter, GFO:85:010 2/12/8l 8/3/83 3/22/85

• Current analysis performed to correct error in code TOOOEE2,

• • This analysis for 48,000 MND/MTU used a version of the TOODEE2 code which contained an error such that a multiplier was applied when not intended.

RAPIPIIII IIII.

%(

Table 2 Exxon Nuclear Company ECCS Models Model Reference

1. Fission Gas Release Model

a. GAP EX NREM 1

b. GAPEX with Uncertainties WREM-II 1, 6

c. RODEX2 EXEM 13

2. Stored Energy Model

a. GAPEX WREN 1

b. RODEX2 EXEM 13

c. ROOEX2 in RELAP4 EXEM llc, 13

3. Blowdown Model WREN 3, 5, 7

4. Containment Pressure Model

a. Dry Containment WREN 3

b. Ice Condenser Containment WREN-II 6, 14

5. Clad Swelling and Rupture Model

a. Exxon Model WREN 3, 4 b, Revised Exxon Model WREN- I I 3,4,6

c. Exxon Model including NVREG-0630 EXEM 10

6. Ref lood Mode 1

a. RELAP4 WREN

b. REFLEX EXEH c~ Carryout and quench Correlations

1) 15xl5 FLECHT WREN 2 2 17x17 FLECHT EXEH lla

3) 15x15/17x17 FLECHT EXEM lib

d. Oowncomer/Upper Plenum Leakage EXEN lla

e. Break Model

1) Split Break EXEN 11a

2) Guillotine Break EXEM 1la Core Outlet Enthalpy Hodel EXEM Ila ge Z-Equivalent Model

1) WREN WREN 3

2) EXEM EXEH lid

0 Table 2 (Continued)

7. Fuel Rod Heatup Model'.

TOODKE2 WREM

b. Steam Cooling Model

1) WREH WREM 3, 9

2) WREM- I I WREM-II 6, 9

3) EXEM EXEM 11 C. Heat Transfer Correlation

1) 15x15 WREM 3

2) 15x15 WREM-II 6

3) 17xl7 EXEM lla 4 15x15/17x17 EXEM 11b

d. Mixing Vane HTC Multipliers

1) Off WREM 3

2) EXEM EXEM lla e.

')2,'XEM Local Peaking

~ Off HTC Multipliers EXEM WREM EXEM 11 3

1ia

3) D.C. Cook 2 EXEM 16 Z-Equivalent Model

1) WREM WREH 3 lid

')

EXEM EXEM Hodel

'adiation

1) WREM WREM 3

2) WREM Expanded New Geometries EXEM lid

8. Core Wide Metal-Water Reaction WREM RAPIFAX 'Ao.

oooo 9 oF7

REFERENCES

1. XN-73-25. "GAPEXX: A Computer Program for Predicting Pellet-to-Cladding Heat Transfer Coefficients," Exxon Nuclear Company, Inc., Richland, WA 99352, August 1973.

2. XN-75-19, "Carryout Rate Fraction Correlation for Pressurired Water Reactors," Exxon Nuclear Company, Inc., Richland, WA 99352; {a) March 24, 1975; (b) Supplement 1, "Statistical Evaluation of the Carryout Rate Fraction," June 1975.

3. )(N-75-41, "Exxon Nuclear Company WREN-Based Generic PWR ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352.

a. Volume 1, July 25, 1975.

b. Volume 2, "Model Justification," August 1, 1975.

c. Supplement 1, "Further Definitions and Justifications to Ref lood Heat Transfer Models," August )4, 1975.

d. Supplement 2, "Supplementary. Information Related to Blowdown and Ref lood Analysis," August 14, 1975.

e. Supplement 3, "Supplementary Information Related to Blowdown and Heatup Analysis," August 16, 1975.

f. Supplement 4, "Supplementary Information Related to Slowdown and Heatup Analysis," August 20, 1975.

g. Supplement 5, "Supplementary Information Related to Blowdown and Heatup Analysis," October 3, 1975.

h. Supplement 6, "Supplementary Information Related to Blowdown and Heatup Analysis," October 27, 1975.

Supplement 7. "Supplementary Information," November 9, 1975.

Volume II Appendix A and B, "3-Loop Westinghouse Sample Problem,"

August 1, 1975.

k. Volume II Appendix C, "Yankee Rowe Example Problem," August 22, 1975.

1, Volume II Appendix D, "3-Loop Westinghouse Large Break Example Problem {Using September 26, 1975 Model)," October 2, 1975.

m. Volume III Revision 2, "Small Break Model," August 20, 1975 EEPWgg. ~S~

PAGE~OF. g. =

REFERENCES (Continued) 4, XN-75-6, "Flow Blockaqe Model for LOCA Analysis," Exxon Nuclear Company, Inc., Richland, WA 99352, April 1, 1975.

5. XN-75-43, "Core Physics Methods and Data Used as Input to LOCA Analysis,"

Exxon Nuclear Company, Inc., Richland, WA 99352, August 1975.

XN-76-27(A), "Exxon Nuclear Company WREM-Based Generic PWR ECCS Evalu-ation Model Update ENC NREM-II," Exxon Nuclear Company, Inc., Richland, WA 99352; (a) March 1977; (b) Supplement 1(A), "Supplementary Infor-mation Relating to," Ma~ch 1977; and (c) Supplement 2(A), "Supplementary Informat i on Rel at ing to," March 1977.

7. XN-76-44, "Revised Nucleate Boiling Lockout for ENC WREM-Based ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, September 1976.

8. XN-NF-78-30(A), "Exxon Nuclear Company WREM-Based Generic PWR ECCS Model Updates ENC WREM-IIA," Exxon Nuclear Company, Inc., Richland, WA 99352, May 1979.

9~ Letter, G,F, Owsley {Exxon Nuclear Company) to D.F." Ross (VSNRC),

Subject:

TOOOEE2 Updates; Letter No. GFO:077:80 dated April 1, 1980.

10. XN-NF-82-07(P)(A), Rev. 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc., Richland, WA 99352, November 1982.

XN-NF-82-20(P), "Fxxon Nuclear'ompany Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, Inc., Richland, WA 99352; (a)

Revision 1, August 1982; (b) Revision 1, Supp. 1, "Revised FLECHT-Based Reflood Carryover and Heat Transfer Correlations," June 1983; (c) Revision 1, Supp. 2(A), February 1985; (d ) Revision 1, Supp. 3, "Response to NRC Request for Additional Information," Draft; (e) Revision 1, Supp. 4(A), "Adjustments to FLECHT-Based Heat Transfer Correlations,"

July 1984.

12. XN-NF-82-49(P), "Exxon Nuclear Company Evaluation Model - EXEM/PWR Small Break Model," Exxon Nuclear Company, Inc., Richland, WA 99352; (a) June 1982; (b) Supp. 1, "Supplement 1: Responses to NRC guestions,"

March 1985.

13. XN-NF-81-58(P)(A), Revision 2, Supps. 1 5 2, "RODEX2 Fuel Rod Thermal Response Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, March 1984.

XN-CC-39, Rev. 1, "ICECON: A Computer Program Used to Calculate Containment Back Pressure for LOCA Analysis { Including Ice Condenser Plants),"

Exxon Nuclear Company, Inc., Richland, WA 99352, November 1978.

IIAFIFN E0.

FEEE 4 EF 7--

REFERENCES (Continued)

15. XN-CC-36, "Exxon Nuclear Procedure for Calculating Core-Mide Metal-Water Reaction Ouring a Loss-of-Coo1ant Accident," Exxon Nuclear Company, inc., Richland, WA 99352, December 1975,

16. Letter, J.C. Chandler (Exxon, Nuclear Company) to H.R. Denton (USNRC),

Subject:

Local Peakinei Multiplier for Ref lood Heat Transfer Coefficient; Letter No. JCC:076:84 dated May 7, 1984.

INPIPIN II.

E)f(()N'UCLEAR COMPANY, INC.

$ 00 100TH avBNvs ht Po 8".1 00777. BELl.tvuE.WA90009 l305) 453.4300 April 2, 1985 ENC-AEP/0437 Mr. George John, Sr, Engineer Nuclear Materials & Fuel Hgmt.

Indiana & Michigan Electric Co.

clo American Electric Power Service Corp.

One Riverside Plaza Co lumbus, OH 43216-6631

Dear Mr. John:

This information is provided to you 'in, accordance with Exxon Nucleer's agreement with the NRC in a meeting on March 29, 1985.

Attached for your use in transmittal to the NRC is a description of thc models used by Exxon Nuclear to analyze the D. C. Cook 2 Plant which provide parr of the current basis for your operation.

Please contact us if you have any questions concerning this attachment.

Ve ry t ru I y you t's, G. haw Contract Administrator Attachment c: M. P. Alexich J M.

~ Cleveland INIfIIII IIII.

aR af~'oats 0~ CxrQHQOAKNAMR PA6E ........ Of ...

Table 1 D.C. Cook Unit 2 LOCA/ECCS Model Sumary Prior PriOr Current

~Anal sis ~Anal sis+ ~Anal sis

1) Fission Gas Release Model EXEM EXEM EXEM

2) Stored Energy Model EXEM EXEM EXEf1/RELAP4

3) Blowdown Model WREM

4) Containment Model WREM-II WREM-II WREM-II S) Clad Swelling arid Rupture Model EXEM EXEH EXEM

6) Ref lood Model a) Carryout and (}uench

~

Correlat'ion EXEH EXEH ' EXEM b) Downcomer/Upper Plenum Leakage Yes (EXEH) Yes (EXEH) Yes (EXEM) c) Break Model Guillotine Gui 1 lotine Gui 11otine CD = 1.0 CD = 1.0 CD = 1.0 d) Core Outlet Enthalpy Model EXEM EXEH EXEM e) l-Equivalent Model OFF OFF EXEM

7) Heatup Model a) Steam Cooling Model EXEM EXEM EXEM b) Heat Transfer Correlation EXEM

• EXEM* EXEH*

c) d)

e)

Mixing Vane Multiplier Local Peaking Multiplier l-Equivalent Model 1.0 WREM

• • ~**

1.0 EXEM

~**

1.0 EXEM f) Radiation Model ON ON ON

8) Documentation of Results XN-NF-84-21 XN-NF-84-21 Not Issued (P) Rev. 1 (P) Rev. 2 Yet (XN-NF-84-21(P),

5/22/84 8/7/84 Rev, 2 Supp.

• 17xl7 FLECHT Correlation

• • Core height and time dependent multiplier used.

+ Models used for administrative limit in place as of April 3, 1985. Item 8 only documents chopped cosine, but 4/3/85 administrative limit accounts for other power distributions not included in Item 8 reference.

++ Models used for new analysis recorrelating existing FLECHT data to account for peaks at the top of the core.

lhPIPhh 00.

Phhh

Table 2 Exxon Nuclear Company ECCS Models Model Reference

1. Fission Gas Release Model

a. GAPEX WREN 1

b. GAPEX with Uncertainties W REM-I I 1, 6 C ~ RODEX2 EXEM 13

2. Stored Energy Model

a. GAP EX WREN 1

b. ROOEX2 EXEM 13 C~ RODEX2 in RELAP4 EXEM llc, 13

3. Blowdown Model WREN 3, 5, 7 4.. Containment Pressure Model at Dry Containment WRKM 3

b. Ice Condenser Containment WREN-II 6, 14

5. Clad S~elling and Rupture Nodel a, Exxon Model NREM 3, 4

b. Revised Exxon Model WREM-I I 3, 4, 6 C ~ Exxon Model including NUREG-0630 EXEN 10

6. Ref 1ood Model

a. RELAP4 WREN

b. REFLEX EXEM Co Carr yout and quench Correlations

1) 15xl5 FLECHT WREN 2

2) 17xl7 FLECHT EXEM lla

3) 15x15/17x17 FLECHT EXEM lib

d. Downcomer/Upper Plenum Leakage EXEM lla

e. Br eak Model

1) Split Break EXEM 11a

2) Guillotine Break EXEM lla Core Outlet Enthalpy Model EXEM lla

9. Z-Equivalent Nodel

1) WREN WREN 3

2) EXEM EXEM lid

Table 2 (Continued)

7. Fuel Rod Heatup Model a, TOODEE2 WREN

b. Steam Cooling Model

1) WREN WREN 3,,9

2) WREN-II WRFN-I I 6, 9

3) EXEM EXEM ll C ~ Heat Transfer Correlation l) 15x15 WREN WREN-I I 3

e

2) 15x15 3 17x17 EXEM lla

4) 15x15/17x17 EXEM lib

d. Mixing Vane HTC Nultipliers

1) Off WREN 3

2) EXEH EXEH lla

e. Local Peaking HTC Nultipliers EXEN 11

1) ,

WREN 3

2) EXEM EXEM lla

3) O.C. Cook 2 EXEM 16 Z-Equivalent Model

1) WREN WREM 3

2) EXEM KXEM lid

g. Radiation Model

1) WREN WREN 3

2) WREH Expanded New Geometries EXEM lid S. Core Wide Metal-Water Reaction WREN

REFERENCES

1. XN-73-25, "GAPEXX; A Computer Program for Predicting Pellet-to-Cladding Heat Transfer Coefficients," Exxon Nuclear Company, Inc., Richland, MA 99352, August 1973.

2. XN-75-19, "Carryout Rate Fraction Correlation for Pressuriied Mater Reactors," Exxon Nuclear Company, Inc., Richland, WA 99352; (a) March 24, 1975; (b) Supplement 1, "Statistical Evaluation of the Carryout Rate Fraction," June 1975.

3. XN-75-41, "Exxon Nuclear Company MREM-Based Generic PMR ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, MA 99352.

a. Volume 1, July 25, 1975.

b. Volume 2, "Model Justification," August 1, 1975.

c. Supplement 1, "Further Definitions and Justifications to Ref lood Heat Transfer Models," August 14, 1975.

d. Supplement 2, "Supplementary Information Related to Blowdown and Ref lood Analysis," August 14, 1975.

e. Supplement 3, "Supplementary Information Related to Blowdown and Heatup Analysis," August 16, 1975.

f. Supplement 4, "Supplementary Information Related to Blowdown and Heatup Analysis," August 20, 1975.

g. Supplement 5, "Supplementary Information Related to Blowdown and Heatup Analysis," October 3, 1975.

h. Supplement 6, "Supplementary Information Related to Blowdown and Heatup Analysis," October 27, 1975.

i. Supplement 7, "Supplementary Information," November 9, 1975.

j. Volume II Appendix A and B, "3-Loop Mestinghouse Sample Problem,"

August 1, 1975.

k. Volume II Appendix C, "Yankee Rowe Example Problem," August 22, 1975.

l. Volume II Appendix 0, "3-Loop Westinghouse Large Break Example Problem (Using September 26, 1975 Model)," October 2, 1975.

m. Volume III Revision 2, "Small Break Model," August 20, 1975.

NAEIIAX N0.,5 .S.

ME .X III 7

REFERENCES (Continued) 4, XN-75-6, "Flow Blockage Model for LOCA Analysis," Exxon Nuclear Company, Inc., Richland, WA 99352, April 1, 1975.

5. XN-75-43, "Core Physics Methods and Data Used as Input to LOCA Analysis,"

Exxon Nuclear Company, !nc., Richland, WA 99352, August 1975.

6. XN-76-27(A), "Exxon Nuclear Company WREM-Based Generic PWR ECCS Evalu-ation Model Update ENC WREM-II," Exxon Nuclear Company, Inc., Richland, WA 99352; (a) March 1977; (b) Supplement 1(A), "SuppIementary Infor-mation Relating to," March 1977; and (c) Supplement Z(A), "Supplementary Information Relating to," March 1977,

7. XN-76-44, "Revised Nucleate Boiling Lockout for ENC WREM-Based ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, September 1976.

8. XN-NF-78-30{A), "Exxon Nuc1ear Company WREN-Based Gener ic PWR ECCS Model Updates .ENC WREM-IIA," Exxon Nuclear Company, Inc., Richland, WA 99352, May 1979.

9. Letter, G.F. Owsley (Exxon Nuclear Company) to D,F. Ross (USNRC),

Subject:

TOODEEZ Updates; Letter No. GFO:077:80 dated April 1, 1980.

10. XN-NF-82-07{P)(A), Rev. 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc., Richland, WA 99352, November 1982.

XN-NF-82-20(P ), "Exxon Nuclear Company Evaluation Model EXEM/PWR KCCS Model Updates," Exxon Nuclear Company, Inc., Richland, WA 99352; (a)

Revision 1, August 1982; (b) Revision 1, Supp. 1, "Revised FLECHT-Based Reflood Carryover and Heat Transfer Correlations," June 1983; (c) Revision 1, Supp. 2(A), Februar'y 1985; (d) Revision 1, Supp. 3, "Response to NRC Request for Additional Information," Draft; (e) Revision 1, Supp. 4(A), "Adjustments to FLECHT-Based Heat Transfer Correlations,"

July 1984.

12. XN-NF-82-49(P), "Exxon Nuclear Company Evaluation Model - EXEM/PWR Small Break Model," Exxon Nuclear Company, Inc., Richland, WA 99352;

{a) June 1982; {b) Supp. 1, "Supplement 1: Responses to NRC questions,"

March 1985,

13. XN-NF-81-58(P)(A), Revision 2, Supps. 1 5 2, "RODEXZ Fuel Rod Thermal Response Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, March 1984.

14. XN-CC-39, Rev. 1, "ICECON: A Computer Program Used to Calculate Containment Back Pressure for LOCA Analysis (Including Ice Condenser Plants),"

Exxon Nuclear Company, Inc., Richland, WA 99352, November 1978

REFERENCES (Continued)

15. XN-CC-36, "Exxon Nuclear Procedure for Calculating Core-Wide Metal-Mater Reaction Ouring a Loss-of-Coolant Accident," Exxon Nuclear Company, Inc., Richland, WA 99352, December 1975.

16. Letter, J.C. Chandler (Exxon Nuclear Company) to H,R. Denton {USNRC),

Subject:

Local Peaking Multiplier for Reflood Keat Transfer Coefficient; Letter No. JCC:076:S4 dated Hay 7, 1984.

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