ML17285B201

Proposed Tech Specs Supporting Cycle 6 Reload & Operation of Lead Fuel Assemblies During Feedwater Temp Reduction Anticipated in Cycle 6

ML17285B201
Person / Time
Site:	Columbia
Issue date:	04/13/1990
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285B199	List: GO2-90-075, Application for Amend to License NPF-21,supporting Cycle 6 Reload & Operation of Lead Fuel Assemblies During Feedwater Temp Reduction Anticipated & Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow ML17285B201 ML17285B202
References
NUDOCS 9004230574
Download: ML17285B201 (2)

Text

Table 3.2.3-1 HCPR OPERATING LIMITS ATTACHMENT III Page 1 of 2 HCPR Operating Limit Uo to 106% Core Flow Cycl e Exoosure l.

0 HWD - 3750 HWD RTU RTIJ 2.

3750 HWD -

EOC RTU Equipment Status T4s ~nsmhlgD ormal scram times~

G uel

.24

l. 35

~

l. 31 1.36 1.9g

~ gyBA -'f6 ANF FueP cue 1.24

],37 3.

3750 HWO -

EOC RTU Control rod insertion 1.42 bounded by Tech.

Spec.

limits (3.1.3.4-p 3/4 1-8)

I 55 4.

3750 MWO -

EOC HWO FiiJ RTU 5.

3750 HWO -

EOC MWD RTU RTU 6.

0 HWO -

EOC HWD HHU RTU RPT inoperable Normal scram times~"

RPT inoperable Control rod insertion bounded by Tech.

Spec.

limits (3. 1.3.4-p 3/4 1-8)

Single loop operation RPT operable Normal scram times""

1.48

.35 I 55

1. 35 i,36 I,Vo

<.c t "In this portion of the fuel cycle, operation with the given HCPR operating limits is allowed for both normal and Tech.

Spec.

scram times and for both RPT operable and inoperable.

""These MCPR values are based on the ANF Reload Safety Analysis performed using the control rod insertion times shown below (defined as normal scram).

In the event that surveillance

4. 1.3.2 shows these scram insertion times have been

exceeded, the plant thermal limits associated with normal scram times default to the values associated with Tech.

Spec.

scram times (3.1.3.4-p 3/4 1-8),

and the scram insertion times must meet the requirements of Tech.

Spec.

3. 1.3.4.

Position Inserted From Full Withdrawn Slowest measured average control rod insertion times to specified notches for all operable control rods for each group of' control rods arranged in a a two-b -two arrav seconds Notch 45 Notch 39 Notch 25 Notch 5

WASHINGTON NUCLEAR - UNIT 2 3/4 2-7

.404

.660 1.504 2.624 Amendment No.

69 9004230574 900413 PIN RDOCK OS000397 P

PDC

ATTACHMENT III Page 2 of 2 INSERT D For Final Feedwater Temperature Reduction rated conditions beyond all rods out point, add

.02 to the NCPR for all fuel in the WNP-2 core except for the SYEA-96 LFA fuel.

For the SVEA-96 LFA fuel; add.03 to the MCPR for Final Feedwater Temperature Reduction rated conditions beyond the all rods out point.

The GEll LFA fuel,'he ANF LFA fuel and the GE initial core fuel are also monitored to the ANF 8x8 fuel NCPR Operating Limits (Reference; Power Distribution Limits, Bases. 3/4.2.3; Minimum Critical Power Ratio, p.

B 3/4 2-3).