ML20128H227
| ML20128H227 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/02/1996 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9610090279 | |
| Download: ML20128H227 (24) | |
Text
_ _
_ ~ -
DukeIbwer Campany T. C M6faxn McGuira Mudear Generatton thpartment Vice hesident 12iOOHagers ferryRoad(MG0nP)
(704)8754800 Huntersvttle, NC280784985 (704)8754809 Fax
\\
ouKEPOWER October 2, 1996 U. S. Nuclear Regulat ory Commission Document Control Desk washingtoni D.C.
20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369, 50-370 Report Pursuant to 10CFR50.46, Changes to or Errors in an ECCS Evaluation Model 10CFR50.46 (a) (3 ) (ii) requires reporting of changes to or errors in the ECCS evaluation model t*M), or in the application of the EM, which affect the LOCA peak (.H d temperature (PCT).
For large break LOCA analysis the BWFC mark-BW fuel is covered by the BWNT large break LOCA evaluation model.
By letter dated September 24, 1996, BWNT confirms that they have discovered no errors in the EM or its McGuire/ Catawba application for the year ending August 31, 1996.
For small break LOCA the fuel is covered by the Westinghouse small break LOCA EM.
By letters dated February 9, 1996 and July 8, 1996, Westinghouse provided a list and brief description of the Emergency Core Cooling System (ECCS) Evaluation Small Break LOCA Model changes and errors that effect the PCT (see attachment 1) for McGuire/ Catawba. The impact of these Small Ereak LOCA Evaluation Model changes and errors have been incorporated into McGuire's revised LOCA peak clad temperature (PCT) margin utilization sheets.
Questions or problems should be directed to Kay Crane at (704) 875-4306.
I Ver trul u s, T. C. McMeekin, ice President McGuire Nuclear Station cc:
Mr. Victor Nerses, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l
Washington, D. C.
20555 Mr. S. D. Ebneter, Regional Administrator U.S. Nuclear Regulatory Commission Regicn II 101 Marietta Street, NW - Suite 2900 g
Atlanta, Georgia 30323
- N Mr. Scott Shaeffer Senior Resident Inspector McGuire Nuclear Station
\\) u v *,1 3 Ni' J n-9610090279 961002 PDR ADOCK 05000369 P
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e i E ONE MNS CNS NGO Other a E Idac 1)OE FRAM w
Other Key Wortf' Westinghouse Energy Systems
&>x 3ss Electric Corporation Pittsburgh Pennsylvania 1s2304355 February 9,1996 DPC-96-202 p.7.-
Mr. T. E. Ryan, Manager Operating Experience Assessment Duke Power Company ig P.O. Box 1006 FEB 27 Charlotte, North Carolina 28201-1006 9
Mail Code: EC05N DOEE pg c6i.
Duke Power Company McGuire Laits 1 & 2, Catawba Units 1 & 2 10 CFR 50.46 Annual NotiGcation and Reportinn
Dear Mr. Ryan:
This is a notification of 10 CFR 50.46 reporting information pertaining to Westinghouse ECCS Evaluation Models. As committed to in WCAP-13451, Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting, attached is a list and brief description of the Emergency Core Cooling System (ECCS) Evaluation Model changes and errors for the 1995 year that effect the Peak Cladding Temperature for your plant (s) (Attachment 1). These Evaluation Model changes and errors have also been reported to the NRC via Westinghouse letter NSD-NRC-96-4639 dated Febmary 9,1996. The impact of these Evaluation Model changes and errors have been incorporated into Section D of your revised LOCA Peak Clad Temperature (PCT) Margin Utilization Sheets (Attachment 2). This information is for your use in making a determination relative to reporting requirements of 10 CFR 50.46.
If you have any questions concerning this information, please let me know.
Very tmly yours,
[
K. B. lanahan Account Manager Attachment 0133GL.18
ATTACHMENT 1 t
McGuire Units 1 & 2 i
ECCS EVALUATION MODEL CHANGES AND ERRORS i
l NOTRUMP Specific Enthalpy Error i
Skewed Power Shapes /ESHAPE/PSSM Withdrawal j
4
NOTRUMP SPECIFIC ENTHALPY ERROR Affected Evaluation Model 1985 Westinghouse Small Break LOCA Evaluation Model Using NOTRUMP
===.
Background===
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 of WCAP-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.
Estimated Effect Representative plant calculations have led to an estimated effect of +20'F for this error correction.
SKEM POWER SHAPES / ESHAPE / PSSM WITHDRAWAL Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model Using BASH 1981 Westinghouse Large Break LOCA Evaluation Model Using BART
Background
Starting in 1991, Westinghouse began using the PSSM (Power Shape Sensitivity Model, WCAP-12909-P) l 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 of skewed power shapes (WCAP-10266-P-A, Addendum 1, Revision 2-P-A). His withdrawal was formally requested of the NRC in letter NTD-NRC-95-4518, effective October 30, 1995. De new process is designated ESHAPE (Explicit Shape Analysis for PCT Effects).
Estimated Effect Evaluations were performed for all affected plants and the results reported to the affected utilities in 1995.
i In some cases, credit for a Hot Leg Nozzle Gap ' compensatory benefit' improvement to the BASH Large Break LOCA Evaluation 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.
ATTACHMENT 2 McGuire Units 1 & 2 LOCA Peak Clad Temperature (PCT)
Margin Utilization Sheets
SmallE1cakfcakflad_TemperaturcEargiftUslization Revision Date: 01/25/96 Plant Name: McGuire Units 1 & 2 Eval.Model: NOTRUMP Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
Reference
- Clad Temperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1264 *F 1
B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.2.3 APCT=
132 *F C.10 CFR 50.59 SAFETY EVALUATIONS Table A APCT=
0 *F D.199510 CFR 50.46 MODEL ASSESSMENTS
)
(Permanent Assessment of PCT Margin)
- l. NOTRUMP Specific Enthalpy Error APCT=
20*F E. TEMPORARY ECCS MODEL ISSUES"
- 1. None APCT=
0 *F F. OTHER MARGIN ALLOCATIONS
- 1. None APCT=
0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1416 *F
- References for the Peak Clad Temperature Margin Utilization summary can be found in Table B.
- It is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reporting requirements.
Notes:
None
4..
.o Large Break Peak Clad Temperature Margin Utilization Revision Date: 01/25/)6 Plant Name: McGuire Units 1 & 2 Eval.Model: BASH Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTPul8%
Reference
- Clad Temperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1945 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1
A PCT =
-23 *F C.10 CFR 50.59 SAFETY EVALUATIONS Table A APCT=
0 *F D.199510 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)
- 1. Skewed Power Shape Penalty 4
APCT=
48*F
- 2. BASH Hot Leg Nozzle Gaps 4
APCT=
-48 *F 1.2 E. TEMPORARY ECCS MODELISSUES"
- 1. None APCT=
0 *F F. OTHER MARGIN ALLOCATIONS
- 1. None APCT=
0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1922 *F References for the Peak Clad Temperature Margin Utilization summaries can be found in Table B.
" It is recommended that these temporary PCT allocations which address current LOCA modelissues not be considered with respect to 10 CFR 50.46 reporting requirements.
Notes:
- 1. The effect of BASH Hot leg Nozzle gaps is 0*F for the cosine case (PCT time = 70 seconds) and -203*F for the skewed shape case (PCT time = 242 seconds). As a result, the chopped cosine remains limiting when BASH Hot Leg Nozzle gap credit is taken, and the appropriate PCT benefit is equal to the skewed power shape penalty of 48'F.
- 2. 'Ihe Catawba sensitivity case reported in the 18% SGTP Program report was also evaluated for skewed power shapes and remains bounded by McGuire.
.O
,,o TabicA __lfLCER.5fL51 Safety Evaluations Revision Date: 01/25/96 Plant Name: McGuire Units 1 & 2 i
Utility Name: Duke Power Company Reference Clad Temperature Notes I. SMALL BREAK ECCS SAFETY EVALUATIONS A. None APCr=
0 *F I
TOTAL 10 CFR 50.59 SMALL BREAK ASSESSMENTS PCT =
0 *F IL LARGE BREAK ECCS SAFETY EVALUATIONS A. None APCT=
0 *F TOTAL 10 CFR 50.59 LARGE IIREAK ASSESSMENTS PCT =
0 *F Notes:
None TabkR - References
- 1. DPC-94-205," Duke Power Company. McGuire Units 1 & 2. Catawba Units 1 & 2: 10 CFR 50.46 Notification and Reporting Information," February 8,1994.
- 2. DPC-94-226, " Duke Power Company, McGuire Units 1 & 2. Catawba Units 1 & 2: 10 CFR 50.46 Notification and Reporting Information," August 18,1994.
- 3. DPC-94 229," Duke Power Company, McGuire Units 1 & 2, Catawba Units 1 & 2: SBLOCTA Axial Nodalization," October 27,1994.
- 4. DPC-95 224," Duke Power Company, McGuire Units 1 & 2 Catawba Units 1 & 2: LOCA Axial Power Shape Sensitivity Model." August 14,1995.
,, man MNE CNE N
I m m Dot FAAM W
Y Westinghouse Energy Systems Box 35s Electric Corporation Patsburgh Pemsytvama 15230-0355 July 8,1996 DPC-96-218 Mr. T. E. Ryan, Manager Operating Experience Assessment Duke Power Company P.O. Box 1006 Charlotte, Nonh Carolina 28201-1006 Mail Code: EC05N Duke Power Company McGuire Units 1 & 2, Catawba Units 1 & 2 10 CFR 50.46 Small Break LOCA Notifiertion and Reportine
Dear Mr. Ryan:
This is a notification rJ 10 CFR 50.46 reporting information penaining to Westinghouse ECCS Small Break LOCA Evaluation Models. Attached is a list and brief description of the Emergency Core Cooling System (ECCS) Evaluation Small Break LOCA Model changes and errors that effect the Peak Cladding Temperature for your plant (s) (Attachment 1). The impact of these Small Break LOCA Evaluation Model changes and errors have been incorporated into Section D of your revised LOCA Peak Clad Temperature (PCT) Margin Utilization Sheets (Attachment 2). This information is for your use in making a determination relative to your regulatory reporting requirements.
If you have any questions concerning this information, please let me know.
Very truly yours, r
pg
/
K. B. Hanahan Account Manager Attachment 0139GL - 15
3 l
j ATTACHMENT 1 McGuire Units 1 & 2 Small Break LOCA ECCS EVALUATION MODEL CHANGES AND ERRORS SBLOCTA Fuel Rod Initialization Loop Seal Elevation Error
SBLOCTA FUEL ROD INITIALIZATION
.I Backeround An error was discovered in the SBLOCTA code related to adjustments which are made as part of the fuel rod initialization process which is used to obtain agreement between the SBLOCTA model and the fuel data supplied from the fuel thermal-hydraulic design calculations at full power, steady-state conditions. Specifically, an adjustment to the power, which is made to compensate for adjustments to the assumed pellet diameter was incorrs Additionally, updates were made to the fuel rod clad creep and strain model to correct logic errors that could.. cur in certain transient conditions. These model revisions had a small effect on the fuel rod initialization process, ar,d could produce small effects during the transient. Due to the small magnitude of effects, and the interaction between the two iterns, they are being evaluated as a single, closely related effect.
l Affected Evaluation Models l
1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP l
l Estimated Effects Representative plant calculations with the corrected model demonstrated that these revisions result in a predicted peak clad temperature increase on the order of + 10*F. This 10*F penalty will be assessed against all existing analyses of record with the above model.
l l
l l
l l
LOOP SEAL ELEVATION ERROR
===.
Background===
An error was discovered in raw plant geometric data that supports input to the Evaluation Model codes. The erroneous datum was a term associated with the relative elevation of the crossover leg.
Affected Evaluation Modelj 1985 Westinghouse Sniall Break LOCA Evaluation Model Using NOTRUMP 1981 Westinghouse Large Break LOCA Evaluation Model 1981 Westinghouse Large Break LOCA Evaluation Model Using BART 1981 Westinghouse Large Break LOCA Evaluation Model Using BASH Estimated Effects The erroneous elevation terms are estimated to have a negligible effect on Large Break LOCA Evaluation Model calculations. Representative sensitivity calculations with NOTRUMP have determined that a non-significant PCT cffect is to be expected due to the influence of the erroneous elevation on the loop seal clearing process. PCT effects ranging from -44'F to +24*F have been assigned to affected plants depending on the magnitude and direction of the error.
I l
.r 4
ATTACHMENT 2 i
McGuire Units 1 & 2 LOCA Peak Clad Temperature (PCT) l, Margin Utilization Sheets i
i
(
i i
i t
1 1
i i
l 5
_SmallRreak Peak ClaLTemperature. Margin Utilization Revision Date: 06/2696 Plant Name: McGuire Units 1 & 2 Eval.Model: NOTRUMP Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
Reference
- Clad Temperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1264 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.2.3.5 APCT=
152 *F C.10 CFR 50.59 SAFETY EVALUATIONS Table A APCT=
0 *F D.199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)
- 1. SBLOCTA Fuel Rod Initialization Error APCT=
10 'F
- 2. Loop Seal Elevation Error APCT=
24 'F E. TEMPORARY ECCS MODEL ISSUES"
- 1. None APCT=
0 'F F. OTHER MARGIN ALLOCATIONS
- 1. None APCT=
0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1450 'F
- References for the Peak Clad Temperature Margin Utilization summary can be found in Table B.
" It is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reporting requirements.
Notes:
None
- .o' u
,k Large Break Peak Clad Temperature Margin Utilization s
Revision Date: 06/26/96 Plant Name: McGuire Units 1 & 2 Eval.Model: BASH Fuel: OFA 1
Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
Reference
- Clad Temperature Notes j
A. ANALYSIS OF RECORD (3/93)
PCT =
1945 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1,4,5 A PCT =
-23 'F l.2
)
i
}
C.10 CFR 50.59 S AFETY EVALUATIONS Table A APCT=
0 *F 1
4 D.199610 CFR 50.46 MODEL ASSESSMENTS l
i (Permanent Assessment of PCT Margin) l
- 1. None A PCT =
0 *F i
E. TEMPORARY ECCS MODEL ISSUES"
- 1. None APCT=
0 *F 1
F. OTHER MARGIN ALLOCATIONS
- 1. None A PCT =
0 *F 4
i I
LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1922 'F
- References for the Peak Clad Temperaiure Margin Utilization summaries can be found in Table B.
- 1: is recommended that these temporary PCT allocations which address current LOCA model issues not bc considered with respect to 10 CFR 50.46 reporting requirements.
4 Notes:
1
- 1. He effect of BASH Hot Leg Nozzle gaps is 0*F for the cosine case (PCT time = 70 seconds) and.203*F for the skewed shape case (PCT time = 242 seconds). As a result, the chopped cosine remains limiting when i
BASH Hot Leg Nozzle gap credit is taken and the appropriate PCT benefit is equal to the skewed power shape penalty of 48'F.
- 2. De Catawba sensitivity case reported in the 18% SGTP Program report was also evaluated for skewed power
,i shapes and remains bounded by McGuire.
1 i
j 4
1 1
1
~,.. _. -. _ _ _ _.
l 4-l 1
{
4
~
Table A - 10 CFR 50.59 Safc.ty_Eyaluations Revision Date: 06/26/96 Plant Name: McGuire Units 1 & 2 Utility Name: Duke Power Company Reference Clad Temperature Notes 1, SMALL BREAK ECCS SAFETY EVALUATIONS A. None A PCT =
0 *F 1
TOTAL 10 CFR 50.59 SMALL BREAK ASSESSMENTS PCT =
0 *F II. LARGE BREAK ECCS SAFETY EVALUATIONS A. None A PCT =
0 *F
\\
TOTAL 10 CFR 50.59 LARGE BREAK ASSESSMENTS PCT =
0 *F Notes:
None Table B - References
- 1. DPC-94-205 " Duke Power Company. McGuire Units 1 & 2. Catawba Units 1 & 2: 10 CFR 50.46 Notification and Reporting Information," February 8,1994.
l
- 2. DPC 94-226. " Duke Power Company McGuire Units 1 & 2, Catawba Units 1 & 2: 10 CFR 50.46 Notification and Reporting Information," August 18,1994.
- 3. DPC-94-229," Duke Power Company, McGuire Units 1 & 2, Catawba Units 1 & 2: SBLOCTA Axial Nodalization " October 27,1994.
- 4. DPC-95-224," Duke Power Company McGuire Units 1 & 2. Catawba Units 1 & 2: LOCA Axial Power Shape Sensitivity Model," August 14,1995.
- 5. DPC-96 202," Duke Power Company, McGuire Units 1 & 2. Catawba Units 1 & 2: 10 CFR 50.46 Annual Notification and Reporting," February 9,1996.
- r-7 ATTACHMENT 1 Catawba Units 1 & 2 Small Break LOCA ECCS EVALUATION MODEL CHANGES AND ERRORS SBLOCTA Fuel Rod Initialization
SBLOCTA FUEL ROD INITIALIZATION f
Backeround An error was discovered in the SDLOCTA code related to adjustments which are made as part of the fuel rod initialization process which is used to obtain agreement between the SBLOCTA model and the fuel data supplied from the fuel thermal-hydraulic design calculations at full power, steady-state conditions. Specifically, an adjustment to the power, which is made to compensate for adjustments to the assumed pellet diameter was incorrect. Additionally, updates were made to the fuel rod clad creep and strain model to correct logic errors that could occur in certain transient conditions. These model revisions had a small effect on the fuel rod initialization process, and could produce small effects during the transient. Due to the small magnitude of effects, and the interactic:' between the two items, they are being evaluated as a single, closely related effect.
Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effects Representative plant calculations with the corrected model demonstrated that these revisions result in a predicted peak clad temperature increase on the order of + 10 F. This 10 F penalty will be assessed against all existing analyses of record with the above model.
f ATTACHMENT 2 Catawba Units 1 & 2 LOCA Peak Clad Temperature (PCT)
Margin Utilization Sheets me
=
1**
l SmalLBreakfcak_ Clad TsmperaturcEargi2 Utilization Revision Date: 06/2686 i
i Plant Name: Catawba Units 1 & 2 Eval.Model: NOTRUMP Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
j Reference
- CladTemperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1264 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.23.5 APCT=
152 *F C.10 CFR 50.59 S AFETY EVALUATIONS Table A APCT=
0 *F D.199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)
- 1. SBLOCTA Fuel Rod initialization Error A PCT =
10 *F E. TEMPORARY ECCS MODEL ISSUES" i
- 1. None A PCT =
0 *F F. OTHER MARGIN ALLOCATIONS
- 1. None APCT=
'O *F i
LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1426 *F
- References for the Peak Clad Temperature Margin Utilization summary can be found in Table B.
- It is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reponing requirements.
Notes:
None
ee
- h 12rge Break Peak Clad Temperature Margin Utilization Revision Date: 06/26/96 Plant Name: Catawba Unit i Eval. Model: BASH Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
Reference
- Clad Temperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1945 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.4.5 APCT=
-23 *F 1.2 C.10 CFR 50.59 S AFETY EVALUATIONS Table A APCT=
0 *F D.199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)
- 1. None A PCT =
0 *F E. TEMPORARY ECCS MODEL ISSUES"
- 1. None APCT=
0 *F
~
F. OTHER MARGIN ALLOCATIONS
- 1. None A PCT =
0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1922 *F
- References for the Peak Clad Temperature Margin Utilization summaries can be found in Table B.
- It is recommended that these temporary PCT allocations which address current LOCA model issues not be considered with respect to 10 CFR 50.46 reporting requirements.
Notes:
- 1. 'ITe efrect of BASH Hot Leg Nozzle gaps is 0*F for the cosine case (PCT time = 70 seconds) and -203*F for the skewed shape case (PCT time = 242 seconds). As a result, the chopped cosine remains limiting when BASH Hot Leg Nozzle gap credit is taken. and the appropriate PCT benefit is equal to the skewed power shape penalty of 48'F.
- 2. The Catawba sensitivity case reponed in the 18% SGTP Program report was also evaluated for skewed power shapes and remains bounded by McGuire.
i
~ _ _ -. _ - _ _ -. - _ _ _ _.
t**
~,
I LargcJrcakPealLCladlemperaturc_MargiRUliliZalion Revision Date: 06/2666 i
Plant Name: Catawba Unit 2 Eval.Model: BASH Fuel: OFA Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%
Reference
- Clad Temperature Notes A. ANALYSIS OF RECORD (3/93)
PCT =
1945 *F B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.4.5 APCT=
-11 'F 1.2 C.10 CFR 50.59 SAFETY EVALUATIONS Table A A PCT =
0 *F D.199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)
- 1. None A PCT =
0 *F E. TEMPORARY ECCS MODEL ISSUES"
- 1. None A PCT =
0 *F i
F. OTHER MARGIN ALLOCATIONS APCT=-
0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =
1934 *F
- References for the Peak Clad Temperature Margin Utilization summaries can be found in Table B.
" It is recommended that these temporary PCT allocations whict address current LOCA model issues not be i
considered with respect to 10 CFR 50.46 reporting requirements.
)
Notes-l
- 1. The effect of BASH Hot Leg Nozzle gaps is 0*F for the cosine case (PCT time = 70 seconds) and -203*F for the skewed shape case (PCT time = 242 seconds). As a result, the chopped cosine remains limiting when B ASH Hot Leg Nozzle gap credit is taken, and the appropriate PCT benefit is equal to the skewed power shape penalty of 48'F.
- 2. The Catawba sensitivity case reponed in the 18% SGTP Program report was also evaluated for skewed power shapes and remains bounded by McGuire.
l I
g..e
,I TahicA _10fFA50.51 Safety _Eyaluations Revision Date: 06/26f>6 Plant Name: Catawba Units 1 & 2 Utility Name: Duke Power Company Reference Clad Temperature Notes
!. SMALL BREAK ECCS SAFETY EVALUATIONS A. None APCT=
0 *F
. TOTAL 10 CFR 50.59 SMALL BREAK ASSESSMENTS PCT =
0 'F
!!. LARGE BREAK ECCS SAFETY EVALUATIONS A. None APCT=
0 *F TOTAL 10 CFR 50.59 LARGE BREAK ASSESSMENTS PCT =
0 *F Notes:
None Table B - References
- 1. DPC-94-205. " Duke Power Company. McGuire Units 1 & 2, Catawba Units 1 & 2.10 CFR 50.46 Notification and Reporting Information." February 8.1994.
- 2. DPC-94-226 " Duke Power Company. McGuire Units 1 & 2, Catawba Units 1 & 210CFR50.46 Notification and Reporting information." August 18,1994.
l
- 3. DPC-94-229," Duke Power Company. McGuire Units 1 & 2. Catawba Units 1 & 2: SBLOCTA Axial Nodalization," October 27,1994.
- 4. DPC-95-224. " Duke Power Company. McGuire Units 1 & 2. Catawba Units 1 & 2: LOCA Axial Power Shape Sensitivity Model." August 14,1995.
- 5. DPC-96-202, " Duke Power Company, McGuire Units 1 & 2. Catawba Units 1 & 2: 10 CFR 50.46 Annual Notification and Reporting," February 9,1996.
.