ML17334A872
| 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 AFFILIATION 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 850329,request",'r'ror described in Exxon 850322'tr GFO':845:010 applicable to Uni,t 1 on-lye DISTRIBUTION CODE:
A001D
'COPIES RECK'/ED:LTR "ENCL SIZE ~'"
'ITLE:
OR Submittal! General Distribution NOTES; OL ~ 10/25/70 OL'+ 12'/23/72" 05000315".
.-05000316'EC IP IKNT ID CODE/NAME[
NRR ORB1 BC'1 INTERNALS ACRS 09 KLD/HDS3-NRR/DL DIR NRR/DL'/TSRG=-
NRR/DSI/RAB RGN3 COPIES LTTR ENCL 7
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1 1-0 1
1" 1
1 EXTERNAL EGLG BRUSKE'gS NRC PDR-02".
1 1
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INDIANA8 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, JLB:wg Attachments M. P. Al xioh g /
Vise President 8504i20i94 850403 PDR ADOCK 050003i5 P
H
~
. r
~,
dl
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.
& 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 meetinj 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 tor t lm Attachment c:
M. P. Alcxich J.
M. Cleveland AII4fFaI IAIDOOF fXXOHCOR~QII4IIOII II>ra III.
paE
Table 1
D.C.
Cook Unit 1 LOCA/ECCS Model Sugary Prior
~Anal sis Prior
~Anal sis Current+
~Anal sis 1)
Fission Gas Release Model 2)
Stored Energy Model 3)
Blowdown Model 4)
Containment Model 5)
Clad Swelling and Rupture Model 6)
Ref lood Model a}
b) c)
Car ryout and quench Correlation Oowncomer/Upper Plenum Leakage Break Model d)
Core Outlet Enthalpy Model e)
Z-Equsivalent Model 7}
Heatup Model WREM-II WREN WREN-II WREN-II WREN NO Sp 1 it CO - l.o OFF OFF EXEM WREN WREN-II EXEM WREN NO Split CO = 1.0 OFF OFF EXEM EXEM WREN WREM-II EXEM NO Sp 1 it CO 1.0 OFF OFF a}
b c) d)
e)f)
Steam Cooling Model Heat Transfer Correlation Mixing Vane Multiplier Local Peak ing Mu 1tip 1 ier 2-Equivalent Model Radiation Model 8}
Documentation of Results WREM WREN-II OFF OFF NREM OFF EXEM WREN-II OFF OFF <<<<
WREN ON 2/12/8l 8/3/83 XN-NF-81-07 XN-NF-83-61 EXEM WREM-II OFF OFF WREN ON
- Letter, GFO:85:010 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 b.
GAPEX with Uncertainties c.
RODEX2 NREM WREM-II EXEM 1
1, 6
13 2.
Stored Energy Model a.
GAPEX b.
RODEX2 c.
ROOEX2 in RELAP4 WREN EXEM EXEM 1
13llc, 13 3.
Blowdown Model WREN 3, 5, 7
4.
Containment Pressure Model a.
Dry Containment b.
Ice Condenser Containment WREN WREN-II 3
6, 14 5.
Clad Swelling and Rupture Model a.
Exxon Model b,
Revised Exxon Model c.
Exxon Model including NVREG-0630 WREN WREN-II EXEM 3,
4 3,4,6 10 6.
Ref lood Mode 1 a.
b.
c ~
d.
e.
ge RELAP4 REFLEX Carryout and quench Correlations 1) 15xl5 FLECHT 2
17x17 FLECHT 3) 15x15/17x17 FLECHT Oowncomer/Upper Plenum Leakage Break Model 1)
Split Break 2)
Guillotine Break Core Outlet Enthalpy Hodel Z-Equivalent Model 1)
WREN 2)
EXEM WREN EXEH WREN EXEH EXEM EXEN EXEN EXEM EXEM WREN EXEH 2lla lib lla 11a 1la Ila 3lid
0 Table 2 (Continued) 7.
Fuel Rod Heatup Model'.
b.
C.
d.
e.
TOODKE2 Steam Cooling Model 1)
WREH 2)
WREM-II 3)
EXEM Heat Transfer Correlation 1) 15x15 2) 15x15 3) 17xl7 4
15x15/17x17 Mixing Vane HTC Multipliers 1)
Off 2)
EXEM Local Peaking HTC Multipliers
')
~ Off 2,'XEM 3)
D.C.
Cook 2
Z-Equivalent Model 1)
WREM
')
EXEM
'adiationHodel 1)
WREM 2)
WREM Expanded New Geometries WREM WREM WREM-II EXEM WREM WREM-II EXEM EXEM WREM EXEM EXEM WREM EXEM EXEM WREH EXEM WREM EXEM 3,
9 6,
9 11 3
6lla 11b 3lla 11 3
1ia 16 3lid 3lid 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, 5.
7.
8.
9 ~
10.
12.
13.
XN-75-6, "Flow Blockaqe Model for LOCA Analysis," Exxon Nuclear
- Company, Inc., Richland, WA 99352, April 1, 1975.
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 ion Rel at ing to," March 1977.
XN-76-44, "Revised Nucleate Boiling Lockout for ENC WREM-Based ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, September 1976.
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.
Letter, G,F, Owsley {Exxon Nuclear Company) to D.F." Ross (VSNRC),
Subject:
TOOOEE2 Updates; Letter No. GFO:077:80 dated April 1, 1980.
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.
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.
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.
& 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.
Very tru Iy you t's, G.
haw Contract Administrator Attachment c:
M. P. Alexich J
~
M. Cleveland aR af~'oats 0~ CxrQHQOAKNAMR INIfIIII IIII.
PA6E........
Of...
Table 1
D.C.
Cook Unit 2 LOCA/ECCS Model Sumary Prior
~Anal sis PriOr Current
~Anal sis+
~Anal sis 1)
Fission Gas Release Model 2)
Stored Energy Model 3)
Blowdown Model 4)
Containment Model S)
Clad Swelling arid Rupture Model 6)
Ref lood Model EXEM EXEM WREM-II EXEM EXEM EXEM WREM WREM-II EXEH EXEM EXEf1/RELAP4 WREM-II EXEM a) b)
c)
Carryout and
(}uench
~ Correlat'ion Downcomer/Upper Plenum Leakage Break Model d)
Core Outlet Enthalpy Model e) l-Equivalent Model 7)
Heatup Model EXEH Yes (EXEH)
Guillotine CD
= 1.0 EXEM OFF Yes (EXEH)
Gui 1 lotine CD
= 1.0 EXEH OFF Yes (EXEM)
Gui 11otine CD
= 1.0 EXEM EXEM EXEH EXEM a) b)
c) d)
e)f)
Steam Cooling Model Heat Transfer Correlation Mixing Vane Multiplier Local Peaking Multiplier l-Equivalent Model Radiation Model EXEM EXEM
- 1.0 WREM ON EXEM EXEM*
1.0~**
EXEM ON EXEM EXEH*
1.0~**
EXEM ON 8)
Documentation of Results XN-NF-84-21 (P) Rev.
1 5/22/84 XN-NF-84-21 (P) Rev.
2 8/7/84 Not Issued Yet (XN-NF-84-21(P),
- 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.
b.
C ~
GAPEX GAPEX with Uncertainties RODEX2 WREN WREM-II EXEM 1
1, 6
13 2.
Stored Energy Model a.
b.
C ~
GAP EX ROOEX2 RODEX2 in RELAP4 WREN EXEM EXEM 1
13llc, 13 3.
Blowdown Model WREN 3, 5, 7
4..
Containment Pressure Model a t b.
Dry Containment Ice Condenser Containment WRKM WREN-II 3
6, 14 5.
a, b.
C ~
Clad S~elling and Rupture Nodel Exxon Model Revised Exxon Model Exxon Model including NUREG-0630 NREM WREM-II EXEN 3,
4 3, 4, 6
10 6.
Ref 1ood Model a.
b.
Co d.
e.
9.
RELAP4 REFLEX Carr yout and quench Correlations 1) 15xl5 FLECHT 2) 17xl7 FLECHT 3) 15x15/17x17 FLECHT Downcomer/Upper Plenum Leakage Br eak Model 1)
Split Break 2)
Guillotine Break Core Outlet Enthalpy Model Z-Equivalent Nodel 1)
WREN 2)
EXEM WREN EXEM WREN EXEM EXEM EXEM EXEM EXEM EXEM WREN EXEM 2lla lib lla 11a lla lla 3lid
Table 2 (Continued) 7.
Fuel Rod Heatup Model a,
b.
C ~
d.
e.
g.
TOODEE2 Steam Cooling Model 1)
WREN 2)
WREN-II 3)
EXEM Heat Transfer Correlation l) 15x15 2) 15x15 3
17x17 4) 15x15/17x17 Mixing Vane HTC Nultipliers 1)
Off 2)
EXEH Local Peaking HTC Nultipliers 1) 2)
EXEM 3)
O.C.
Cook 2
Z-Equivalent Model 1)
WREN 2)
EXEM Radiation Model 1)
WREN 2)
WREH Expanded New Geometries WREN WREN WRFN-II EXEM WREN WREN-I I EXEM EXEM WREN EXEH EXEN WREN EXEM EXEM WREM KXEM WREN EXEM 3,,9 6,
9 ll 3
ella lib 3lla 11 3lla 16 3lid 3lid 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.
NAEIIAXN0.,5.S.
ME
.X III 7
REFERENCES (Continued) 4, 5.
6.
7.
8.
9.
10.
12.
13.
14.
XN-75-6, "Flow Blockage Model for LOCA Analysis," Exxon Nuclear
- Company, Inc., Richland, WA 99352, April 1, 1975.
XN-75-43, "Core Physics Methods and Data Used as Input to LOCA Analysis,"
Exxon Nuclear
- Company,
!nc., Richland, WA 99352, August 1975.
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, XN-76-44, "Revised Nucleate Boiling Lockout for ENC WREM-Based ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352, September 1976.
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.
- Letter, G.F.
Owsley (Exxon Nuclear Company) to D,F.
Ross (USNRC),
Subject:
TOODEEZ Updates; Letter No. GFO:077:80 dated April 1, 1980.
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.
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, 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.
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.
~ 8
~
't