ML20236U736

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Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model
ML20236U736
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/29/1998
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20236U731 List:
References
NUDOCS 9807300405
Download: ML20236U736 (6)
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- ADMINISTRATIVE CONTROLS I BM1 TRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT 6.9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years.

6.9.1.10 A survey of major pipelines Wsterford 3, which contain explosive or( 14 inches) within a 2-mile radius of flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years.

CORE OPERATING LIMITS REPORT COLR .

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6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING reload cycle. LIMITS REPORT prior to each reload cycle or any remaining part of a 6.9.1.11.l The analytical methods used to determine the core operatin I j

shall be those previously reviewed and approved by the NRC as follows:g limits

1) "The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983; and "C-E Methodology for Core Designs Containin'g Gadolinia-Urania Burnable Absorber," CENPD-275-P-A, May 1988. (Methodology for {

Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating CEA Insertion Limits, 3.1.2.9 Baron Dilution (Calculation of CBC f4 IBW), and 3.9.1 Boron Concentration).

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2) "C-E Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January 1976.

Regulating CEA Insertion (Methodology for Specification 3.1.3.6 for Limits and 3.2.3 for Azimuthal Power Tiit).

3) " Modified May 1988. Statistical Combination of Uncertainties" CEN-356(V)-P-A, (Methodology for Specification 3.2.4 for DNBR Margin and 3.2.7 for ASI).

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4) " Calculative Methods for the C-E Large Break LOCA Calculation Model For The Analysis of C-E and W Designed NSSS," CENPD-132, Supplement 3-P-A, June 1985. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).
5) " Calculative Methods for the C-E Small Break LOCA Evaluation Model,"

CENPD-137-P, August 1974: Supplement 1. January 1977. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI). '

6) "CESEC - Digital Simulation for a Combustion Engineering Nuclear Steam Supply System," CENPD-107, December 1981. (Methodology for Specification ,

l 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA Insertion Limits, 3.1.3.7 for Part Length CEA Insertion Limits and  ;

3.2.3 for Azimuthal Power Tilt). '

WATERFORD - UNIT 3 6-20 AMENDMENT NO. 667102 9807300405 980729 PDR P ADOCK 05000382-pop L

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e NPF-38-208 ATTACHMENT B PROPOSED SPECIFICATIONS L-_---- _- ---- - -

ADMINISTRATIVE CONTROLS i INDUSTRIAL SURVEY OF 70XIC OR HAZARD 0US CHEMICALS REPORT 6.9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years.

6.9.1.10 A survey of major pipelines I Waterford 3, which contain explosive or( 1 4 inches) within a 2-mile radius of flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years.

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CORE OPERATING LIMITS REPORT COLR 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING reload cycle. LIMITS REPORT prior to each reload cycle or any remaining part of a 6.9.1.11.1 The analytical methods used to determine the core operatin shall be those previously reviewed and approved by the NRC as follows:g limits 1)"TheRbCSandDITComputerCodesforNuclearDesign,"CENPD-266-P-A, April 1983, and "C-E Methodology for Core Designs Containin'g Gadolinia-Urania Burnable Absorber," CENPD-275-P-A, May 1988. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating CEA Insertion Limits, 3.1.2.9 Baron Dilution (Calculation of CBC & IBW), and 3.9.1 Baron Concentration).

2) "C-E Method for Control Element Assembly Ejection Analysis," CENPD-0190-A, January 1976. (Methodology for Specification 3.1.3.6 for )

Regulating CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt).  ;

3) " 1988.

May Modified Statistical Combination of Uncertainties" CEN-356(V)-P-A, (Methodology for Specification 3.2.4 for DNBR Margin and 3.2.7 for ASI).

4) " Calculative Methods for the C-E Large Break LOCA Calculation Model For The Analysis of C-E and W Designed NSSS," CENPD-132, Supplement 3-P-A, June 1985. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).

" alcul ive th for the C Sm Br k LOC Eva atio Mo el Inseef E -137 , gust 74: Supp nt ,J uary 77. (Met do gy S cifi tio 3.1. 3 f MTC 3.2. for near eat te, .2 I

1 imut I r it 3. . for SI) f

6) "CESEC - Digital Simulation for a Combustion Engineering Nuclear Steam  !

Supply System," CENPD-107, December 1981. (Methodology for Specification  !

3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for  ;

Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA i Insertion Limits, 3.1.3.7 for Part Length CEA Insertion Limits and  ;

3.2.3 for Azimuthal Power Tilt).  ;

WATERFORD - UNIT 3 6-20 AMENDMENT NO. 68r102 l i

L' INSERT t'

f - 5) " Calculative Methods for the ABB CE Small Break ~LOCA Evaluation Model,"

! CENPD-137, Supplement 2-P-A, April,1998. (Methodology for Specification L 3.1.1.3 for MTC,3.2.1 for Linear Heat Rate,3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).

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I NPF-38-208 i ATTACHMENT C 1 REFERENCES 1

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l' NPF-38-208 LIST OF REFERENCES

! 1. Letter, T. H. Essig (NRC) to I. C. Rickard (ABB), " Acceptance for Referencing of the Topical Report CENPD-137(P), Supplement 2, ' Calculative Methods for the CE Small Break LOCA Evaluation Model' (TAC M95687)," December 16,1997, i L

f 2. CENPD-137, Supplement 1-P, " Calculative Methods for the CE Small Break LOCA i Evaluation Model," January 1977.-

3. CENPD-137P, " Calculative Methods for the CE Small Break LOCA Evaluation Model," August 1974.

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