ML17333A389
| ML17333A389 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/22/1996 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:118K, NUDOCS 9603280099 | |
| Download: ML17333A389 (33) | |
Text
CATEGORY 1 REGULA.'~
INFORMATION DISTRIBUTION SYSTEM (RIDS)
. y I
AQCESSIOR NBR:9603280099 DOC.DATE: 96/03/22 NOTARIZED: 'NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Pj.ant, Unit 2, Indiana" M." 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michi an Ele RECIP.NAME RECIPIENT AFFILIATION Document Control, Branch (Document Control Desk)
SUBJECT:
Provides annual rept of LOCA evaluation model changes.
Attachment 1 provided to NRC by Westinghouse, describing LOCA model changes, permanently implemented.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
E RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL:
PC~NTER 1
NR 5E H HICB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
1 1
1 1
l.
1 1
1 1
0 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION IISTS FOR DOCUMENTS YOU DON'T NEEDj TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 11
Indiana Michigan Power Company
, P.O. Box 16631 Columbus, OH 43216 March 22, 1996 AEP:NRC:1118K Docket Nos '0-315 50-316 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
ANNUAL REPORT OF LOCA EVALUATION MODEL CHANGES Pursuant to the requirements of 10 CFR 50.46(a)(3)(ii), this letter provides our annual submittal of LOCA model changes.
Attachment 1, which was provided to us by Westinghouse Electric Corporation (Westinghouse),
describes LOCA model changes which have been permanently implemented and provides a discussion in general terms of the impact of these changes on calculated peak clad temperatures (PCT's).
Attachment 2 contains the PCT's calculated specifically for Donald C. Cook Nuclear Plant Units 1 and 2.
In all cases, the calculated PCT's remain within the 10 CFR 50.46 limit of 2200~F.
In accordance with the guidance in WCAP-13451, "Westinghouse Methodology for Implementation of 10CFR50.46 Reporting,"
evaluations of plant changes performed under 10CFR50.59 are not reported under 10CFR50.46, unless an offsetting change to the'valuation Model was made to provide sufficient margin to
,accommodate the proposed change.
As in previous submissions, an analysis of record for the high head safety injection (HHSI) crossties open, Unit 1 SBLOCA analysis has been included.
The new analysis is now complete and is reported as the "crossties open" analysis of record in this submittal.
Only the limiting, "crossties -closed" cases have been submitted for NRC review and approval.
We do not intend to operate Unit 1 at the conditions assumed in the HHSI "crossties open" analysis (i.e. 3588 MWt).
Operation with the crossties open is conservative compared to the approved "crossties closed" case"at 3250 MWt.
Therefore, the "crossties open" case for Unit 1 is not considered to be limiting and has not been submitted for NRC review and approval.
However, for consistency, a
new analysis that was performed by Westinghouse in conjunction with the effort to support an increased r, g /tolerance on the main steam safety valve setpoint has been gQ 9b03280099 9b0322 I DR uDOCK 0S0003is I
U. S. Nuclear Regulatory Commission Page 2
AEP: NRC:1118K included.
This new analysis uses the COSI model and the same conservatively low auxiliary feedwater flow used in the "crossties closed" case.
Attachment 3 contains LOCA PCT's calculated for both Unit 1 and Unit 2 based on analyses that have not yet been approved by the NRC.
This data'is provided for information and does not reflect the current license basis for Cook Nuclear Plant, Currently, both LBLOCA and SBLOCA reanalyses are being reviewed by NRC staff in conjunction with evaluations and analyses to support an increase in allowable steam generator tube plugging (SGTP) for Unit 1.
This work was submitted to the staff in May 1995 with our letter identified as AEP:NRC:1207.
A specific letter explaining the effect of the revised power shape on the increased SGTP LOCA analyses was submitted with our letter identified as AEP:NRC:1207A.
New LBLOCA'nd SBLOCA analyses of record for Unit 2 will be included as part of a planned uprating effort.
The submission of the results of these new Unit 2 analyses is planned for 1996, by letter that will be identified as AEP:NRC:1223.
Sincerely, E.
E. Fitzpatrick Vice President eh Attachments CC:
A. A. Blind G. Charnoff J. Miller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
'4
't.
I
~4+I<'ll ATTACHMENT 1 TO AEP'NRC'1118K WESTINGHOUSE ELECTRIC CORPORATION DESCRIPTION OF LOCA MODEL CHANGES
ATTACHMENT 1
TO AEP:NRC:1118K Page 1
'KEWED FOWL SHAXES Imuu E I PSSM WrrrIDRAWm Aff Ev uati nM el 1981 Westinghouse Large Break LOCA Evaluation Model Using BASH 1981 Westinghouse Large Break LOCA Evaluation Model Using BART B~ack r cad Starting in 1991, Westinghouse began using the PSSM (Power Shape Sensitivity Model, WCAP-12909-P) as a methodology for addressing skewed axial core power shapes in LBLOCA analyses.
In 1995, Westinghouse elected to withdraw the PSSM methodology and implement an updated version of previously approved methodology which incorporated explicit analysis ofskewed power shapes (WCAP-10266-P-A, Addendum 1, Revision 2-P-A). This withdrawal was formally requested ofthe NRC in letter NTD-NRC-95<518, effective October 30, 1995.
The new process is designated ESHAPE (Explicit
'Hape Analysis for PCl'ffects).
tim Eff Evaluations were performed for all affected plants and the results reported to the affected utilities in 1995.
In some cases, credit for a Hot Leg Nozzle Gap 'compensatory benefit'mprovement to the BASH Large Break LOCAEvaluation Model (WCAP-14404) was required to continue to meet the 10 CFR 50 46 limit of 2200'F.
For the affected plants, revised LBLOCA Margin Utilization Summary Tables were transmitted along with sufficient information for reporting.
',"" i!
ATTQCHHENT 1
TO AEP:NRC:1118K 7
NOTRUMP SPECIFIC'ENTXIALPYERROR Page 2
1985 Westinghouse Small Break LOCA Evaluation Model Using NOTRUMP Qggkk,r~i~n A typographical error was found in a line of coding in the NOTRUMP code.
This line of coding was intended to model the calculation found in Equation L-127 ofWCAP-10079-P-A. Although the equation in the topical report is correct, the coding represented the last term as a partial derivative with respect to the fluid node mixture region total energy instead of the mixture region total mass.
This correction is a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.
d Representative plant calculations have led to an estimated effect of +20'F for this error correction.
0
ATTACHMENT 1
TO AEP:NRC:1118K page 3
SALIBRARYDOUBLE PRECISION ERRORS Aff val i n el 1981 Westinghouse Large Break LOCA Evaluation Model Using BASH 1985 Westinghouse Small Break LOCA Evaluation Model'Using NOTRUMP Qggkk~n During migration ofthe LOCAcodes from the CRAYcomputer to UNIXkased platforms, programming errors were made in two library routines related to improper specification of double precision variables.
'Ipse errors were found and fixed during later code maintenance.
Es im Eff Test cases with individual codes in the models demonstrated very small differences in only the SATAN and NOTRUMP code results, with correspondingly minor effects on final peak clad temperature predictions.
Because the error only affects a very limited number of LBLOCA analyses which were performed on the UNIXplatform prior to correcting the codes, the evaluation of effects for LBLOCA analyses were assessed on a plant-specific basis.
For SBLOCA analyses performed on the UNIX platform, representative plant calculations resulted in an estimated generic effect of -15 F for affected analyses.
ATTACHMENT 2 TO AEP:NRC:1118K WESTINGHOUSE ELECTRIC CORPORATION DETERMINATION OF EFFECT OF LOCA MODEL CHANGES ON COOK NUCLEAR PLANT LOCA ANALYSES
I Attachment 2 to AEP:NRC:1118K Page 1
LARGE BREAK LOCA PLANT NAME:
Donald C.
Cook Unit 1 Comments:
Evaluation Model:BASH, FQT 2 15, FdH 1 55, SGTP
- 15X, Other:
RHR Cross Tie Valve Closed, 3250 MWt Reactor Power A,
ANALYSIS OF RECORD B.
PRIOR LOCA MODEL ASSESSMENTS
- 1989 CD PRIOR LOCA MODEL ASSESSMENT
- 1990 D.
PRIOR LOCA MODEL ASSESSMENTS
- 1991 E.
PRIOR LOCA MODEL ASSESSMENTS
- 1992 F.
PRIOR LOCA MODEL ASSESSMENTS
- 1993 PCT 2162'F APCT
+
O' hPCT
+
O' APCT
+
20'F APCT
-117'F APCT
-60F G.
PRIOR LOCA MODEL ASSESSMENTS
- 1994 BPCT OCF H.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
Skewed Power Shape Penalty
- 2. Hot Leg Nozzle Gap Benefit LICENSING BASIS PCT + PERMANENT ASSESSMENTS hPCT~ +
253oF 5PCT-~25 'F PCT ~2C 5'F
Attachment 2 to AEP:NRC:1118K
,'I
Page";2 j,'.
LARGE BREAK LOCA PLANT NAME:
DONALD C.
COOK UNIT 1 Comments:
Evaluation Model:
BASH FQT 2 15, FdH-1 55, SGTP 15X, Other:
RHR Cross Tie Valve Open, 3413 MWt Reactor Power A.
B.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS
- 1989 hPCT
+
OCF PCT-2181'F C.
PRIOR LOCA MODEL ASSESSMENTS
- 1990 hPCT
+
00F D.
E.
F.
G.
H.
PRIOR LOCA MODEL ASSESSMENTS
- 1991 PRIOR LOCA MODEL ASSESSMENTS
- 1992 PRIOR LOCA MODEL ASSESSMENTS
- 1993 PRIOR LOCA MODEL ASSESSMENTS
- 1994 1995 10CFR50.46 MODEL ASSESSMENTS 1 ~
Skewed Power Shape Penalty
- 2. Hot Leg Nozzle Gap Benefit
- hPCT,
+
30'F 6PCT 6PCT
-25'F 60F BPCT 00F IPCT
+
253'F APCT ~23 'F OTHER MARGIN ALLOCATIONS (Use of PCT Margin):
1.
ANALYSIS MARGINS USED: Power Margin APCT
-94'F J.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS 6c POWER MARGIN PCT 2102'F-
~
~
Attachment 2 to AEP:NRC:1118K Page 3
JUSTIFICATION FOR USE OF POWER MARGIN IN DONALD C.
COOK NUCLEAR PLANT UNIT 1 LARGE BREAK PCT RACK UP The analysis peak clad temperature (PCT) for Donald C.
Cook Nuclear Plant Unit 1 at 3413 MW~ with the RHR cross tie valve open is 2181 F.
When the 1991 LOCA model assessment of 30 F was
- added, the resulting PCT exceeded 2200'F.
The following calculation shows that power margin exists for Cook Nuclear Plant Unit 1 since the core is currently licensed at 3250 MW< versus the analysis power level of 3413 MW~.
A sensitivity to power was previously determined for the Donald C. Cook Nuclear Plant Unit 2 large break analysis. It was conservatively demonstrated that a reduction of 20~F~/% power could be applied for reduced power.
This sensitivity is conservative since it only accounts for the assumed power reduction in the LOCBART run.
A similar reduction in the assumed power for the SATAN run produces an added benefit to PCT during the blowdown portion of the transient.
A reduction in power in the blowdown portion of the transient (i.e.,
SATAN) would be an added benefit which was not accounted for in this sensitivity.
Since both Cook Nuclear Plant unit 1 and unit 2 are four loop ice condenser
- plants, this sensitivity will be applied to the reduction in power from the unit 1 analysis power of 3413 MW~ to the licensed operating condition of 3250 MW< (a 4.7% reduction in power):
(20 F~/% Power)
(4.7% Power) 94 F When this 94 F margin is applied to the Unit 1, 3413 MW~ analysis with RHR cross tie valves open, the 10 CFR 50.46 PCT limit is not exceeded.
pEt p
i Attachment 2 to AEP:NRC:1118K Page 4
SMALL BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 1 Comments:
Evaluation Model:HQTRUMP, FQ-2 32, FsH-1 55, SGTP-~12 Other:
HHSI Cross Tie Valve Closed, 3250 MWt Reactor Power A.
ANALYSIS OF RECORD PCT 1951'F B.
PRIOR LOCA MODEL ASSESSMENTS
- 1992 hPCT~ +
3'Fl C.
D.
PRIOR LOCA MODEL ASSESSMENTS
- March 1994 PRIOR LOCA MODEL ASSESSMENTS
- December 1994 BPCT
-164F hPCT-
-223'F E.
G.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error 2.
SALIBRARY Double Precision Errors Burst and Blockage/Time in Life LICENSING BASIS PCT + PERMANENT ASSESSMENTS
, aPCT- +
BPCT 20'F
-15'F BPCT
+
154FE PCT-~35'F 2.'he 1992 assessment for 15xl5 hydraulic test results was not included in the new analysis of record.
- However, the drift flux flow regime error was incorporated.
It should be noted that the burst and blockage assessment is subject to change as other model assessments are made because the magnitude of the burst and blockage assessments depends on the PCT without burst and blockage.
V t,
Attachment 2 to AEP:NRC:1118K Page
.5'.
SMALL BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 1 Comments:
Evaluation Model:gOTRUMP, FQ-2 32, FaH-1 55, SGTP-~52 Other; HHSI Cross Tie Valve
~0 en, 3588 MWt Reactor Power A.
B.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS
- December 1994 PCT ~105 'F hPCT
+
204FE C.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error 2.
SALIBRARY Double Precision Errors
~PCTmm +
BPCT 20'F
-154F D.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT ~10 2'F l.
Allprior permanent LOCA model assessments were resolved by the new analysis except for the 20'F penalty for Containment Spray During Small Break LOCA.
il Attachment 2 to AEP:NRC:1118K Page 6
LARGE BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:BASH, FQT-2 335, FdH-1 644, SGTP 152, Other:
RHR Cross Tie Valve Closed, 3413 MWt Reaotor Power A.
ANALYSIS OF RECORD PCTmm 2090'F B.
C.
PRIOR LOCA MODEL ASSESSMENTS
- 1989 (Analysis of record was completed in January 1990.
No prior LOCA Model assessments were made.)
PRIOR LOCA MODEL ASSESSMENTS
- 1990 8 PCT
+
NAoF APCT
+
O' D.
E.
F.
G.
PRIOR LOCA MODEL ASSESSMENTS
- 1991 PRIOR LOCA MODEL ASSESSMENTS
- 1992 PRIOR LOCA MODEL ASSESSMENTS
- 1993 PRIOR LOCA MODEL ASSESSMENTS
- 1994
~PCTem +
IPCT dPCT IPCT 300F
-250F 60F OGF H.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
Skewed Power Shape Penalty
- 2. Hot Leg Nozzle Gap Benefit hPCT- +
253'F APCT ~23 'F I.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT ~1C5'F
r
Attachment 2 to AEP:NRC:1118K
,l
~
~,
Pt'i 'll>
9 I Page 7
,<,'it.
~ ji,!
t NAf LARGE BREAK LOCA PLANT NAME:.
DONALD C.
COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:~BAS FQT 2 22, FdH 1.62, SGTP 15X, Other:
RHR Cross Tie Valve Open, 3588 MWt Reactor Power A.
B.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS
- 1989 (Analysis of record was completed in January 1990.
No prior LOCA model assessments were made.)
PCT 2140'F APCT ~+A'F C.
D.
E.
F.
PRIOR LOCA MODEL ASSESSMENTS
- 1990 PRIOR LOCA MODEL ASSESSMENTS
- 1991 PRIOR LOCA MODEL ASSESSMENTS
- 1992 PRIOR LOCA MODEL ASSESSMENTS
- 1993 4PCT
+
~PCT- +
IPCT BPCT 04F 304F
-25'F
-6'F G.
PRIOR LOCA MODEL ASSESSMENTS
- 1994 BPCT O'
H.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
Skewed Power Shape Penalty
- 2. Hot Leg Nozzle Gap Benefit hPCT
+
253'F APCT-~23 'P I.
OTHER MARGIN ALLOCATIONS 1.
Power Margin J.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS hPCT-
-984F2 PCT-~205 'F This value was obtained by temporarily allocating 4.9X of power margin using a sensitivity of 20'F/X power.
See the Unit 1 justification for the use of power margin in the Donald C.Cook Nuclear Plant Unit 1 Large Break PCT Rack up on page 3 of this attachment.
Attachment 2 to AEP:NRC 1118K
'.Page 8,
'". <.i'">ei 1
I SMALL BREAK LOCA PLANT NAME:
DONALD.C. COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:HOTRUNP, FQ-2 45, FaH-~666, EGTP ~52 Other:
HHSI Cross Tie Valve Closed, 3250 MWt Reactor Power I
A.
ANALYSIS OF RECORD PCT 1956'F B.
PRIOR LOCA MODEL ASSESSMENTS
- October 1993 APCTmm
-13'F C.
PRIOR LOCA MODEL ASSESSMENTS
- March 1994 hPCT
-16'F D.
PRIOR LOCA MODEL ASSESSMENTS
- December 1994 4PCT
+
69'F E.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error hPCT
+
20'F E
Burst and Blockage/Time in Life hPCT
+
OOFI E.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT 2016'F It should be noted that the burst and blockage assessment is subject to change as other model assessments are made because the magnitude of the burst and blockage assessments depends on the PCT without burst and blockage.
(4 Attachment 2 to.AEP.:NRC:1118K
'w Page 9
SMALL BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:~OTRUNP, FQ-2 44, FaH-1 644, SGTP-15X Other:
HEST Cross Tie Valve Closed, 3413 MHt Reactor Power A.
B.
C.
D.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS
- October 1993 PRIOR LOCA MODEL ASSESSMENTS
- March 1994 PRIOR LOCA MODEL ASSESSMENTS - December 1994 6PCT IPCT 13oF
-16'F BPCT 33OF PCT ~194 'F E.
F.
G.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error Burst and Blockage/Time in Life LICENSING BASIS PCT + PERMANENT ASSESSMENTS hPCT~ +
20'F 4 POT-~+4'F
'OT-~19 9'F It should be noted that the burst and blockage assessment is subject to change as other model assessments are made because the magnitude of the burst and blockage assessments depends on the PCT without: burst and blockage.
)
4
~i Attachment 2 to AEP:NRC:1118K Page 10 SMALL BREAK LOCA PLANT NAME:
DONALD.C. COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:MOTRCMP, FQ-2 32, FeH-1 62,SGTP-152, Other:
HHSI Cross Tie Valve
~O en, 3588 MWt Reactor Power A.
B ~
C.
D.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS
- October 1993 PRIOR LOCA MODEL ASSESSMENTS
- March 1994 PRIOR LOCA MODEL ASSESSMENTS
- December 1994 BPCTmm hPCT
+
-16CF 35CF PCT ~153 'F hPCT
-13'F E.
F.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error LICENSING BASIS PCT + PERMANENT ASSESSMENTS aPCT-~+O' PC1'155
'F
uu ATTACHMENT 3 TO AEP'NRC'1118K WESTINGHOUSE ELECTRIC CORPORATION DETERMINATION OF EFFECT OF LOCA MODEL CHANGES ON UNAPPROVED COOK NUCLEAR PLANT LOCA ANALYSES
0 Attachment 3 'to AEP:NRC:1118K Page 1
LARGE BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 1 Comments:
Evaluation Model:BASH, FQT 2 15, FdH 1 55, SGTP 30X, Other:
RHR Cross Tie Valve Closed, 3250 MWt Reactor Power A.
SUBMITTED ANALYSIS OF RECORD B.
PRIOR LOCA MODEL ASSESSMENTS PCT 2164'F APCT~ +
O'F~
C.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
SALIBRARY Double Precision Errors BPCT 5oF D.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT 2159'F Allprior permanent LOCA model assessments were resolved by the new analysis.
Attachment 3 to AEP,:NRC:1118K
',Page 2, '
SMALL BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 1 Comments:
Evaluation Model:~OTRUMP, FQ-2 32, FaH-l 55,SGTP-302, Other:
HHSI Cross Tie Valve Closed, 3250 MWt Reactor Power A.
B.
ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS PCT APCT 1443'F 00F1 C.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error 2.
SALIBRARY Double Precision Errors hPCT
+
dPCT 20'F
-15'F D.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCTmm 1448'F Allprior permanent LOCA model assessments were resolved by the new analysis.
I
0 Attachment.3'o AEP:NRC:1118K Page 3
LARGE BREAK LOCA PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model: BASH, FQT-2 335, FdH-1 644, SGTP-153, Other:
RHR Cross Tie Valve Closed, 3588 MWt Reactor Power A.
NOT YET SUBMITTED ANALYSIS OF RECORD B.
PRIOR LOCA MODEL ASSESSMENTS C.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT 2051'F hPCT
+
O' PCT 2051 F Allprior permanent LOCA model assessments were resolved by the new analysis.
f tj
Attachment 3 to AEP:NRC:1118K SMALL BREAK LOCA Page 4
t II p
PLANT NAME:
DONALD C.
COOK NUCLEAR PLANT UNIT 2 Comments:
Evaluation Model:NOTRUMP, FQ-2 32, F~H 1 62,SGTP
- 15X, Other:
HHSI Cross Tie Valve Closed, 3588 MWt Reactor Power A.
B.
NOT YET SUBMITTED ANALYSIS OF RECORD PRIOR LOCA MODEL ASSESSMENTS PCT~
20650F BPCT 00F1 C.
1995 10CFR50.46 MODEL ASSESSMENTS 1.
NOTRUMP Specific Enthalpy Error 2.
SALIBRARY Double Precision Errors
~PCT- +
BPCT 20'F
-15'F
.D.
LICENSING BASIS PCT + PERMANENT ASSESSMENTS PCT 2070'F l.
Allprior permanent LOCA model assessments were resolved by the new analysis.
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