ML17254A309
| ML17254A309 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/04/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8504090222 | |
| Download: ML17254A309 (16) | |
Text
REGULATORY ORMATION DISTRIBUTION SYS M (RIDS)
ACCESSION NBR;8504090222 OUTDATE: 85/04/04 NOTARIZED:
NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Planti Unit }i Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION KOBER~R ~ l'j, Rochester Gas L Electric Corp.
'REC IP ~ NAME'EC IPIENT AFF ILIATION ZNOLINSKIiJ,A, Operating Reactors Branch 5
SUBJECT:
Forwards tables of computer models used by Exxon Nuclear Corp in most recent ECCS analysis for Exxon fuel in plantsg as reported in XN-NF-82-26iin response to request for info, DISTRIBUTION CODE:
AOO}D COPIES RECEI)ED:LTR
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TITLE:
OR Submittal:
General Distribution NOTES:NRR/DL/SEP }cy, OL: 09/19/69 05000244 RECIPIENT ID CODE/NAME NRR ORB5 BC 01 INTERNAL: ACRS 09 ELD/HDS4 NRR/DL DIR NRR/DL/TSRG NRR/DSI/RAB RGN}
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ROCHESTER GAS AND ELECTRIC CORPORATION o e9 EAST AVENUE, ROCHESTER, N.K 14649.0001 ROGER W. KOBER VICE PRESIDENT ELECTRIC & STEAM PRODUCTION TELEPHONE AREA COOE 7I4 546-2700 April 4, 1985 Director of Nuclear Reactor Regulation
'ttention:
Nr. John A. Zwolinski, Chief Operating Reactor Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Loss of Coolant Accident Analysis.
R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Zwolinski:
The enclosed tables provide information requested by the NRC Staff concerning the computer models used by Exxon Nuclear Corpora-tion in their most. recent, ECCS analysis for ENC fuel in Ginna, as reported in XN-NF-82-26.
V truly yours, e./
er W. Kober Enclosure 000404 asap pp9pp+2 pspppQ+p PDOt:H pDR P
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Table 1
R.E. Ginna LOCA ECCS Nodel Summar 1)
Fission Gas Release Model 2)
Stored Energy Nodel 3)
Blowdown Model 4)
Containment Model 5)
Clad Swelling and Rupture Model 6)
Reflood Model Reflex (WREN IIA)
Current A~nal sis WREM WREM-II a) b)
c) d)
e)
Carryout. and Quench Correlation DowncomerflJpper Plenum Leakage Break Model ll Core Outlet Enthalpy Model 2-Eguivalent Model WREM:, No Leakage "CD =0.',4 Guillotine OFF OFF 7)
Heatup Model a)b)c) d)
e)f)
Steam Cooling Model Heat Transfer Correlation Mixing Vane Multiplier Local Peaking Multiplier 2-Equivalent Model Radiation Model WREN WREM 1.00 1.00 WREM OFF 8)
Documentation of Results XN-NF-82-26
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Table 2
Exxon Nuclear Com an ECCS Models 1.
Fission Gas Release Model Model Reference 2.
a.
GAPEX b.
GAPEX with Uncertainties c.
RODEX2 Stored Energy Model WREM 1
WREM-II 1,
6 EXEM 13 5.
GAPEX RODEK2 RODEX2'n RELAP4 h
'f Blowdown Model a ~b.
c ~
Containment Pressure Model a.
Dry Containment b.
Ice Condenser Containment Clad Swelling and Rupture Model
- WREM, PXEM
'XEM WREM WREM-II
-1 13'lc, 13, 3,
5, 7
3 6,
14 6.
a.
Exxon Model b.
Revised Exxon Model c.
Exxon Model including NUREG-0630 Reflood Model WREM 3,
4 WREM-II 3, 4, 6
EXEM 10 a
0b.
c ~
d.
e.
f.
g RELAP4 REFLEX Carryout and Quench Correlations 1) 15 x 15 FLECHT 2) 17 x 17 FLECHT 3) 15 x 15/17 x 17 FLECHT Downcomer/Upper Plenum Leakage Break Model 1)
Split Break 2)
Guillotine Break Core Outlet Enthalpy Model Z-Equivalent Model 1)
WREM 2)
EXEM WREM EXEM WREM EXEM EXEM EXEM EXEM EXEM EXEM WREM EXEM 3
8 2
11a lib lla lla lla lla
P f
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Table 2 (Continued)
Fuel Rod Heatup Model Model Reference a ~b.
C.
e.
g TOODEE2 Steam Cooling Model 1 )
WREM 2)
WREN-II 3)
EXEM Heat Transfer Correlation 1) 15 x 15 2) 15 x 15 3) 17 x 17 4) 15 x 15/17 x 17 Mixing Vane HTC Nultipliers 1)
Off 2)
EXEM Locak Peaking HTC Multipliers 1)
Off 2)
EXEM 3)
D.C.
Cook 2
Z-Equivalent Model 1)
WREM 2)
EXEM Radiation Model 1 )
WREM 2)
WREN Expanded New Geometries WREM 3
WREM-II 6
EXEM lla EXEM 11b WREM EXEM EXEM WREN EXEM EXEM WREM EXEM WREM EXEM 3
11a 11 3lla 16 3lid 3lid WREM 3
WREM 3,
9 WREM-II 6,
9 EXEM 11 Core Wide Metal-Water Reaction WREM
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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 Pressurized 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.
XN-75-41, "Exxon Nuclear Company WREM-Based Generic PWR ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA 99352.
a ~
Volume 1, July 25, 1975.
b.
c ~
Volume 2, "Model Justification," 'August 1, 1975.
il " e Suppleme'nt 1, "Further Definitions and Justifications to Reflood Heat Transfer Models," August 14, 1975.
d.
Supplement 2,
"Supplementary Information Related to Blowdown and Reflood Analysis," August 14, 1975.
e.
g h.
Supplement 3,
"Supplementary Information Related to Blowdown and Heatup Analysis," August 16, 1975.
Supplement 4,
"Supplementary Information Related to Blowdown and Heatup Analysis," August 20, 1975.
Supplement 5,
"Supplementary Information Related to Blowdown and Heatup Analysis," October 3, 1975.
Supplement 6,
"Supplementary Information Related to Blowdown and Heatup Analysis," October 27, 1975.
- 3. ~
Supplement 7,
"Supplementary Information," November 9, 1975.
k.
Volume II Appendix A and B, "3-Loop Westinghouse Sample Problem," August 1, 1975.
Volume II Appendix C, "Yankee Rowe Example Problem,"
August 22, 1975.
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.
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REFERENCES (Continued) 4 5.
6.
7.
8.
9.
10.
12.
13.
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, Inc., Richland, WA
- 99352, August 1975.
XN-76-27(A), "Exxon Nuclear Company WREM-Based,,Generic PWR ECCS Evaluation Model Upda'te ENC WREN-II," Exxon Nuclear Company, Inc., Richland, WA 99352; (a) March 1977; (b)
Supplement 1(A), "Supplementary Information Relating to,"
March 1977; and (c) Supplement 2(A), "Supplementary Infor-mation 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-78-39(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. Oswley (Exxon Nuclear Company) to D.F. Ross (USNRC),
Subject:
TODDEE2 Updates, Leter 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 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 Questions,"
March 1985.
XN-NF-81-58(P) (A), Revision 2, Supps.
1
& 2, "RODEX2 Fuel Rod Thermal
Response
Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA
- 99352, March 1984.
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REFERENCES (Continued) 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.
15.
XN-CC-36, "Exxon Nuclear Procedure for Calculating Core-Wide Metal-Water Reaction During 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 Heat Transfer Coefficient; Letter No. JCC:076:84 dated May 7, 1984.
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