ML20196C009

Proposed Tech Specs,Revising Fuel Cladding Integrity Safety Limit for Use in Calculating Critical Power Operating Limits in Future Reload Analyses

ML20196C009
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	11/30/1988
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20196C006	List: ML20196C003 ML20196C009
References
NUDOCS 8812070134
Download: ML20196C009 (2)

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1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY Applicability: [pplicability:

Applies to the interrelated variable associated Applies to trip setting of the instruments and with fuel thermal behavior, devices which are provided to prevent the nuclear system safety limits from being exceeded.

Objective: Objective:

To establish limits below which the integrity of To define the level of the process variable at the fuel cladding is preserved, which automatic protective action is initiated.

Specification: Specification:

A. Bundle Safety Limit (Reactor Pressure >800 A. Trip Settings psia and Core Flow >10% of Rated)

The limiting safety system trip settings When the reactor pressure is >800 psia and shall be as specified below:

the core flow is greater than 10% of rated, either: 1. Neutron Flux Trip Settings

1. For a core loading which consists of at a. APRM Flux Scram Trip Setting least two successive reloads of P8x8R, (Run Mode) ,

BP8x8R, CE8x8E or CE8x8EB fuel with high (> = 1.04) beginning-of-life bundle When the mode switch is in 'he RUN R-factor (one tcload of which is fuel in position, t'.e APRM flus . ram trip -

its first cycle of operation), the setting s'all be se ,nown on gg existence of a Minimum Critical Power Figure 2 1, -a' shall be: mot Ratio (MCPR) of less than 1.04 (1.05 for [8 Single Loop Operation) shall constitute gg violation of the Fuel Cladding Integrity Safety Limit (FCISL); $d or TO vo

2. For all other core loadings, the bq existence of a MCPR less than 1.07 (1.08 8

. for Single Loop Operation) shall g{

constitute violation of the FCISL. CXL Q.

Amendment No. SI, SS, 94 5 l

n 5

TABLE 3.11.2 .

VERMONT YANKEE NUCLEAR POWER STATION TECHNICAL SPECIFICATION MCPR OPERATING LIMITS T

Value of "M" in RBM Average Control Rod Cycle Equation (1) Scram Time Exposure Range MCPR Operating Limits (2&3) 42% Equal or better BOC to EOC-2 CWD/T 1.26 than L.C.O. EOC-2 CWD/T to EOC-1 GWD/T 1.26 3.3 C.1.1 EOC-1 CWD/T to EOC 1.27 Equal or better BOC to EOC-2 CWD/T 1.25 than L.C.O. EOC-2 CWD/T to EOC-1 CWD/T 1.28 3.3 C.I.2 EOC-1 GWD/T to EOC 1.32 41% Equal or better BOC to EOC-2 CWD/T 1.22 than L.C.O. EOC-2 CWD/T to EOC-1 CWD/T 1.22 3.3 C.I.1 EOC-1 CWD/T to EOC 1.27 Equal or better BOC to EOC-2 CWD/T 1.22 than L.C.O. EOC-2 GWD/T to EOC-1 CWD/T 1.28 3.3 C.1.2 EOC-1 CWD/T to EOC 1.32 140% Equzi or better BOC to EOC-2 CWD/T 1.22 than L.C.O. EOC-2 CWD/T to EOC-1 CWD/T 1.22 3.3 C.1.1 EOC-1 CWD/T to EOC 1.27 Equal or better BOC to EOC-2 CWD/T 1.22 than L.C.O. EOC-2 CWD/T to EOC-1 GWD/T 1.28 3.3 C.I.2 EOC-1 CWD/T to EOC 1.32 NOTES:

(1) The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table 3.2.5 of the Technical Specifications.

(2) The current analysis for MCPR Operating Limits does not include the 7x7, 8x8, or 8x8R fuel types. On this basis, if any of these fuel types are to be reinserted, they will be evaluated in accordance with 10CFR50.59 to ensure that the above limits are bounding for these fuct typer.

O) MCPR Operating limits are increased by 0.01 for single loop operation.

' Amendment No. 12, SS, SA, 100, 180-01

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