ML20198C282

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Corrected TS Pages Re Amends 146 & 130 to Licenses NPF-4 & NPF-7,respectively.Removes Requested Changes to Boron Concentration
ML20198C282
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/07/1991
From:
NRC
To:
Shared Package
ML20198C287 List:
References
NUDOCS 9107010122
Download: ML20198C282 (2)


Text

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6791 ADMINISTRATIVE CONTROLS CORE OPERATING 13MTS REPORT 6.9.1.7.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient BOC and EOC limits, and 300 ppm and 60 ppm surveillance limits for Specification 3/4.1.1.4, 2.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.

Control Bank Insertiu Limits for Specification 3/4.1.3.6, 4.

Axial Flux Difference limits for Specification 3/4.2.1, S.

Heat Flux Hot Channel Factor, K(Z), N(Z) for Specification 3/4.2.2, and 6.

Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier, for Specification 3/4.2.3.

6.9.1.7.b The analytical methods used to determihe the core operating limits shall be those previously reviewed and approved by the NRC as identified in 6.9.1.7.0.

6.9.1.7.c The core operating limits shall be determined so that all applicable limits (e.g.,

fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.7.d The CORE OPERATING LIMITS REPORT, including any mid cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.

6.9.1.7.e REFERENCES 1.

VEP FRD-42, Rev.1 A,

  • Reload Nuclear Design Methodology," September 1986.

(Methodology for LCO 3.1.1.4 Moderator Temperature Coefficient, LCO 3.1.3.5 Shutdown Bank Inseition Limit, LCO 3.1.3.6 Control Bank Insertion Limits, LCO 3.2.2 - Heat Flux Hot Channel Factor, LCO 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor).

NORTH ANNA UNIT 1 6 17 Amendment No. A3,146, 9107010122 910625 DR ADOCK 050 8

6791 ADMINISTRATIVE CONTRO(.S s

COBELOPERATING LMTS REPORT 6.9.1.7.a Core operating limits shall be established and documented in the CORE OPERATING LIM:TS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient BOC and EOC limits, and 300 ppra and 6,0 ppm surveillance limits for Specification 3/4.1.1.4, 2,

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.

Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.

Axial Flux Difference limits for Specification 3/4.2.1, 5.

Heat Flux Hot Channel Factor, K(Z), N(Z) for Specification 3/4.2.2, and

'6.

Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier, for Specification 3/4.2.3.

6.9.1.7.b The ansiytical methods used to determine the core operating limits shall be those l

previously reviewed and approved by the NRC as identified in 6.9.1.7.e.

6.9.1.7.c The core operating limits shall be determined so that all applicable limits (e.g.,

fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.7.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and L

Resident inspector.

l 6.9.1.7.e REFERENCES l

1.

VEP FRD-42, Rev.1 A, " Reload Nuclear Design Methodology," September l

1986.

(Methodology for LCO 3.1.1.4 Moderator Temperature Coefficient, LCO 3.1.3.5 Shutdown Bank insertior' Limit, LCO 3.1.3.6 Control Bank Insertion Limits, LCO 3.2.2 Heat Flux Hot Channel Factor, LCO 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor).

NORTH ANNA UNIT 2 6-17 Amendment No. 47,130, l

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DATED: June 25, 1991 CORRFCTION TO:

AMEliDMEllT lio.146 TO FACILITY OPERATING LICEf4SE I40, f4PF-4-NORTH A!iNA UNIT 1 AMENDMENT NO 130 TO FACILITY OPERATING LICEllSE NO. NPF-7-NORTH A!4tlA littlT 2 Docket File NRC & Local PDRs PDil-2 Reading S. Varga, 14/E/4 G. Lainas, 14/H/3 H. Berkow D. Miller L. Engle OGC-WF D. Hagan, 3302 MNBB E. Jordan, 3302 MNBB B. Grimes, 9/A/2 G. Hill (8), P-137 Wanda Jones, P-130A C. Grimes, 11/F/23 T. Huang, 8-E-23 ACRS (10)

GPA/PA OC/LFMB M. Sinkule, R-ll cc:

Plant Service list

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