ML17292A890

Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages

ML17292A890
Person / Time
Site:	Columbia
Issue date:	06/06/1997
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17292A889	List: ML17292A888 ML17292A890
References
NUDOCS 9706170163
Download: ML17292A890 (6)

Text

EXIGENT REQUEST FOR AMENDMENTOF SLMCPR MODIFICATIONOF REQUEST Attachment 2

'agel of 1 ATTACHM<22lT2 Revised Technical Specification Page and Corresponding Bases Page 970bi70ib3 970bOb&

05000397 PDR ADOCK P PORE

SLs 2.0

'.0 I

SAFETY LIMITS (SLs)

. 2.1 SLs 2.1.1 Reactor Core SLs

'~

2.1. 1. 1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be a 25% RTP.

With the reactor steam dome pressure a and core M~~~

2. 1. 1.2 785 psig flow a 10% rated core flow:

.M-a

'e: ~ p p p p

2. 1. 1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2. 1.2 Reactor Coolant S stem Pressure SL Reactor steam dome pressure shall be a 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2. 1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

~ngepf The'MCPR for ATRIUM-9X fuel shall be a 1.13 for two recirculation loop~ operation or a 1.14 for single recirculation loop operation.

For all other fuel, the MCPR shall be a 1.07 for two recirculation loop operation or a 1.08 for single recirculation loop operation.

The MCPR limits for the ATRIUM-9X fuel are applicable to Cycle 13 ,.

only.

WNP-2 2.0-1 Amendment No. 149

SLs 2.0 2.0 SAFETY LIHITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs

2. 1. 1. 1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERHAL POWER shall be a 25% RTP.

2. 1. 1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:

The HCPR for ATRIUH-9X fuel shall be a 1.13 for two recirculation loop operation or a 1. 14 for single recirculation loop operation. For all other fuel, the HCPR shall be a 1.07 for two recirculation loop operation or w 1.08 for single recirculation loop operation. The HCPR limits for the ATRIUH-9X fuel are applicable to Cycle 13 only.

2. 1. 1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2. 1.2 Reactor Coolant S stem Pressure SL Reactor steam dome pressure shall be x 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2. 1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

WNP-2 2.0-1 Amendment No.

~t

(

Reactor Core SLs 8 2.1.1

. BASES APPLICABLE 2. 1.1.1 Fuel Cladding Inteoritv {continued)

SAFETY ANALYSES bundle flow for all fuel assemblies that have a relatively high power and potentially can approach a critical heat flux condition. The minimum bundle flow is > 28 x 10'b/hr. The coolant minimum bundle flow and maximum flow area are such that the mass flux is

> 0.25 x 10'.lb/hr-ft'. Full scale critical power tests taken at pressures down to 14.7 psia indicate that the fuel assembly critical power at 0.25 x 10'b/hr-ft~ is approximately 3.35 HWt. At 25se RTP a bundle power of approximately 3.35 Hwt corresponds to a bundle radial peaking factor of

> 2.9, which is significantly higher than the expected peaking factor. Thus, a THERMAL POWER limit of 25" RTP for reactor pressures < 785 psig is conservative.

2.1.1.2 HCPR The HCPR SL ensures sufficient conservatism in the operating HCPR limit that, in the event of. an AOO from the limiting condition of operation, at least 99.K of the fuel rods in the core would be expected to avoid boiling transition. The margin between calculated boiling transition (i.e.,

MCPR 1.00) and the HCPR SL is based on a detailed statistical procedure that considers the uncertainties in monitoring t re opera i ate. One specific uncertai included in the SL is he uncertainty inherent CJ in t critical power correlations. Reference 4 describes

'C th methodology used in determining the MCPR SL For Siemens O wer Corporation fuel. Reference 5 describes the methodology used in determining the HCPR SL for ABB CENO CIS

'a CP Cl fuel.

tD The critical power correlations are'based on a significant O

Cl body of practical test data, providing a high degree of C5 assurance that the critical power, as evaluated by the

~CD H

0 correlation, is within a small percentage or the actual critical power. As long as the core pressure and flow are within the range of validity of the critical power correlations, the assumed reactor conditions used in defining the SL introduce conservatism into the limit because bounding high radial power factors and bounding flat local peaking distributions are used to estimate the number continued WNP-2 8 2.0-3 .Revision 5

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