ML20198B038

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Forwards 1996 Annual 10CFR40.46 Rept of Changes Affecting Peak Clad Temperature & Margin Utilization Sheets
ML20198B038
Person / Time
Site: Mcguire, Catawba, McGuire  
Issue date: 12/19/1997
From: Tuckman M
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9801060169
Download: ML20198B038 (14)
v • d • e


Text

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'g Duke Power Company.

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A Duke Ewg Comany EC07H

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526 South Church Street PO, Box 1006

. Charlotte, NC 28201 1006

- M.5.T u kman Executin We 1%ident VM)382-2200 omcr Nwlee Generation g gy3gy.435g w December 19, 1997 U. S. Nuclear Regulatory (,'ammission Washington, D. C. 20555 Attention: Document Control Desk

Subject:

McGuire Nuclear Station Docket Numbers 50-369 and -370 Catawba Nuclear Station Docket Numbers 50-413 and -414 Report Pursuant to 10CFR40.46 Errors in or Changes to ECCS Evaluation Model 10 CFR50. 4 6 (a) (3) (ii) requires the reporting of changes to or errors in an ECCS evaluation model (EM), or in an application of the EM, which affect the LOCA peak clad temperature (PCT) calculation.

Reports of errors or changes that are not considered significant (i.e., < 50'F).

Accordingly, attached is a list and description of the changes to the EM (Attachment 1).

The net effects of the changes are shown on The-stations' Peak Clad Temperature Margin Utilization Sheets (Attachment 2).

Very truly yours,

, T.

' ua.A A

M.'S.

Tuckman l ~fU 9901060169 971219 PDR ADOCK 05000369 R

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U. S. Nuclocr Rogulatory Commission Dsctmbor/19,fl997 Page 2 xc:

Mr.

F. Rinaldi~, Project Manager Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Mail Stop 14H25, OWEN-Washington, D. C.

20555 Mr.

P.

S. Tam, Project. Manager Office of Nuclear Reactor Regulation U..S.

Nuclear Regulatory Commission Mail Stop O-14 H25 Washington, D. C.

29555 Mr.

L..A.

Reyes, Regional Admir.istrator U.S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth Street - Suite 23T85 Atlanta, Georgia 30303 Mr.

S. M.

Sheaffer Senior Resident Inspector McGuire Nuclear Station Mr.

D. J. Roberts Senior Resident Inspector Catawba Nuclear Station 4

1996 Annual 10 CFR 50.46 Report Of Changes Affecting PCT e

i i...

I 5

S,

. 4.

SBLOCTA FUEL ROD INIT.'ALIZATION Backaround 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, whicri 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 also had a small affect on the fuel rod initialization process, and can produce small.affects during the transient.

Due to the small magnitude of affects, and the interaction between the two items, they' are being evaluated as a single, closely related affect.

' This change is considered to be a Non-Discretionary Change as described in WCAP.13451.

= Affected Evaluation Modelt, 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP a

a 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 has been assessed against all existing analyses of record with the above model.

4

-TRANSLATION OF FLUID CONDITIONS FROM SATAN TO thCTA '

i Backaround

! n error was discovered in the coding related to the translation of fluid conditions between the -

A rods.: In performing axial interpolations to translate the SATAN fluid conditions onto the mesh _

~

- SATAN blowdown hydraulics code and the LOCTA code used for subchannel analysis of the fuel nodalization used by the LOCTA code, the length of the lower core channel fluid connection to the lower plenunf node was incorrectly calculated.

This change is considered to be a Non Discretionary Change as described in WCAP 13451.

'- Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model-1981 Westinghouse.Large Break LOCA Evaluation Model with BART-1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effects Representative plant calculations with the corrected model demonstrated that this correction resulted in approximately a il5 'F effect on the BASH large break LOCA evaluation model. Evaluations based

}

on these studies conclude that the effect on the BART and 1981 evaluation models was a 5'F benefit.

'Iherefore the following estimated effects are assigned:

BASH EM 15'F penalty BART and 1981 EM 5'F benefit.

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. LOOP SEAL ELEVAT!ON ERROR.

~ Background.

i An error was discovered in raw plant geometric data that suppons input to the Evaluation Model codes. The erroneous datum was a term associated with the relative elevation of the crossover leg.-

This change is considered to be a Non Discretionary Change as described in WCAP 13451.

Affected Evaluation Models-1985 Westin'ghouse Small 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 2

Estimated Effects l

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 effect 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 magnitudc and direction of the error.

?

C

L 1996 Annual 10 CFR 50.46 Report Peak Clad Temperature Margin Utilization Sheets 4

4

Small Break Prak Clad TemperaturcJiargin_ Utilization e.m,c n.m

__.w Revision Datei 02/10/97, 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 OFRECORD(3/93)

PCT =

12f 4 '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 Iniilanization Error 6

APCT=

10 *F

2. Loop Seal Elevation Error 6

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 Refere: ces 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

mm=

____Large Break Peak -

mperature Margin Utilization ____

I Revision Date: 02/10/97 -

Plant Name: McGuire Units I & 2 Eval.Model: BASH Fuel: OFA

-- Utility Name: Duke Power Company FQ=2.32 FdH=1.55 SGTP=18%

Referenec*

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 SAFETY EVALUATIONS Table A APCT=

0 'F D.199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)

~ 1. Translation of Fluid Conditions from SATAN to LOCTA APCT=

15 'F E. TEMPORARY ECCS MODELISSUES"

1. None aPCT=

0 *.c F. OTHER M ARGIN ALLOCATIONS

1. None APCT=

0 'F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

1937 *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. The effect of B ASH 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 reported in the 18% SGTP Program report was also evaluated for skewed power shapes and remains bounded by McGuire.

Table AAgCgjoMSafety Evaluationt_

l

, -n u==m

==m-__..m

==.m._

Revision Date: 02/10/97 -

Plant Name: McGuire Units 1 & 2 Utility Name: Duke Power Company

- Reference Clad Temperature Notes

1. 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 - Referencet

==

_ = _ _ _ _..

I. 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, Catawb4 Units 1 & 2: 10 CFR 50.46 Notification and Reporting Information," August 18,1994.
3. DPC-94-229," Duke Power Company, McGuire Units I & 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 I & 2, Catawba Units 1 & 2: 10 CFR 50.46 Annual Notification and Reporting," February 9,1996.
6. DPC-96-218, " Duke Power Company, McGuire Units 1 & 2, Catawba Units 1 & 2: 10 CFR 30.46 Small Break LOCA Notification and Reporting," July 8,1996.

e Small Break Peak Clac,tTemperatureNarsin.Util.iration '

- mmm-m

_ _,mm Revision Date: 02/10/97 -

t

- Plant Name: Catawba Units 1 & 2 Eval.Model: NOTRUMP Fuel: OFA Utahty Name: Duke Power Company

.FQ=2.32.

FdH=1.55 SGTP=!8%

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. 'l0 LFR 50.59 SAIITY EVALUATIONS Table A APCT=

0 *F D,199610 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)

- 1. SBLOCTA Fuel Rod Initialization Error 6

APCT=

10 *F E. TEMPORARY ECCS MODEL ISSUES"

l. None APCT=

0 *F F. OTHER MARGIN ALLOCATIONS

1. None APCT=

0 *F 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 reporting requirements.

Notes:

None

.n r

a.e-

-. - ~.

e large._Breakleak Clad _Ternperature Margin Utilization Revision Date: 02/10/97 Plant Name: Catawba Unit i Eval.Model: BASH Fuel: OFA Utility Name: Duke Power Company FQ=2.32 -

FdH=1.55 SGTP=lB%

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 l.2 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. Translation of Fluid Conditions from SATAN to LOCTA APCT=

15 *F E. TEMPORARY ECCS MODELISSUES"

1. None APCT=

0 *F F. OTHER MARGIN ALLOCATIONS

1. None APCT=

0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

1937 *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:

l. The effect of B ASH 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 reported in the 18% SGTP Program report was also culuated for skewed power shapes and remains bounded by McGuire.

)

= r==cm_z=_m= L.arge BJ,cak Peak Clad Temperature Margi U!ilization _ _ mm= _ =__,

A Revision Date: 02/10/97 Plant Namei Catawba Unit 2 Eval.Model: BASH Fuel: GFA Utility Name: Duke Power Company -

FQu2.32 FdH=1.55 SGTP=18%

Reference

  • Clad Temperature Notes A; ANALYSIS OF RECORD (3/93)

PCT =

1945 *F j

B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS,

1,4,5 APCT=

-11 *F 1,2 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. Translation of Fluid Conditims from SATAN to LOCTA APCT=

15 'F h

E. TEMPORARY ECCS MODELISSUES"

1. None APCT=

0 'F F. OTHER MARGIN ALLOCATIONS APCT=

, 0 *F LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

1949 'F

  • References for the Peak Clad Tempersture 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. The effect of BASH Hot Leg Nozzle gaps is O'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 reported in the 18% SGTP Program report was also evaluated for skewed power shapes and remains bounded by McGuire.

o mx==mm=me=,== =TabicA&10 CFR 30.59_SafetymEvaluations_, _. __

m Revision Date: 02/10/97 Plant Name: Catawba Units 1 & 2 Utility Name: Duke Power Company

- Reference Clad Temperature Notes

1. SMALL BREAK ECCS SAFETY EVALUATIONS A. None APCT=

0 *F TOTAL 10 CFR 50.59 SMALL BREAK ASSESSMENTS PCT =

0 'F

11. LARGE BREAK ECCS SAFETY EVALUATIONS A. None APCT=

0 *F TOTAL 10 CFR 50.59 LARGE BREAK ASSESSMENTS PCT =

0 'F Notes:

None

=m m=-=m.m=.=.mmm---

Table B - References m

1. DPC-94-205, " Duke Power Company, McGuire Units I & 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 Reponing 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 I & 2, Catawba Units 1 & 2: 10 CFR 50.46 Annual Notification and Reporting." February 9,1996.

6.- DPC 96-218. " Duke Power Company, McGuire Units 1 & 2, Catawba Units I & 2: 10 CFR 50.46 Small Break LOCA Notification and Reporting," July 8,1996.

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