ML20116G489

Proposed Tech Specs Modifying 15.2.3 & 15.5.3 of Change Request 188 & 15.2.1,15.2.3 & 15.3.1.G of Change Request 189 Supporting SEs

ML20116G489
Person / Time
Site:	Point Beach
Issue date:	08/05/1996
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19311C175	List: ML20116G454 ML20116G489 ML20116G512
References
NUDOCS 9608080133
Download: ML20116G489 (5)

Text

l (3)

Low pressurizer pressure 21865 psig for operation at 2250 psis primary system pressure 21790 psig for operation at 2000 psia primary syst:m pressure (4)

Overtemperature J

AT(1+ z s S) 1 1+11 S A T (K1-K2(T(1 + x s3)- T')(1 + s 25) + Ks(P - P S

where (values are applicable to operation at both 2000 psia and 2250 psia unless otherwie indicated)

ATo indicated AT at rated power, F

=

average temperature, UF T

=

T' 5

5732.9 F;-(Unit 4) f 570.0% ("n:t 2)

P pressurizer pressure, psig

=

P' 2235 psig (2250 osia operation only)

=

_ P' 1985 osic (2000 osia coeration ontvP

=

K 5

!.301.19 (2250 psia operation only) i K

(__,

1.14 (2000 psia operation onlyP g

K 0.0200 0.025 (2250 nsia operation only) 2 K,

0.022 (2000 psia operation onlyP

=

K 0.00070! DA0J 3 (2250 osia operation only) 3 Ky 0.001 (2000 psia ooeration ontvP

=

25 sec I

ti 3 see x2

=

2 sec for Rosemont or equivalent RTD 13

=

0 sec for Sostman or equivalent RTD

=

t, 2 sec for Rosemont or equivalent RTD

=

0 see for Sostman or equivalent RTD

=

and f{AI) is an even function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests, where q, and q are the percent power in the top and bottom halves of the core respectively, and q, + qb s total core power in percent of rated power, such that:

i (a) for q,- q within -17, +5 percent, f(AI) = 0.

(b) for each percent that the magnitude of q,- q. exceeds +5 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of rated power for Un:' !, er by n

)

eq= !:- cf 3.! percent cf rated pcwer for Un : 2.

t These311ges aoply to Unit 2 following U2R22 and to Unit I following UlR24. Prior to UlR24. the values for Unit I are: T < 573.9'F. P' = 2235 psig. K < 1.30. K, = 0.0200. and K = 0.000791.

y y

9608080133 960805 PDR ADOCK 05000266 p

PDR Unit 1 - Amendment No. 4%

15.2.3-2 0:tr-ber 28, !991 Unit 2 - Amendment No. 40

Other reactor trips:

(1)

High pressurizer water level - s95% of span (2)

Low-low steam generator water level >20% of narrow range instrument span 25% of narrow range instrument span (Unit IP (3)

Steam-Feedwater Flow Mismatch Trip - sl.0 x 10'Ib/hr (4)

Turbine Trip (Not a protection circuit)

(5)

Safety Injection Signal (6)

Manual Trip o

This setting limit anplies to 1Init i until the narrow range lower tan is changed to the lower position consiste.nl with Unit 2, 15.2.3-3a U9 ' 'L'd: 2 May !"?3/ March 'n?3 i

- _ _ -. -.... _ _ _ _. - -.... - - -. _ _.. _. -. _ _ _. _....... ~. _ _ - - _

l TABLE 15.3.5-1 i

(PAGE I OF 2)

ENGINEERED SAFETY FEATURES INITIATION INSTRUMENT SETTING LIMITS I

HQ FUNCTIONAL UNIT-CHANNEL SETTING LIMIT I

liigh Containment Pressure (Hi)

Safety injection

• s 6 psig

{

2 liigh Containment Pressure (Hi-Hi)

a. Containment Spray 5 30 psig

b. Steam Line Isolation of l

Both Lines s 20 psig -

3 Pressurizer Low Pressure Safety injection *

.21715 psig 4

Low Steam Line Pressure Safety injection

• 2 500 psig

' Lead Time Constant 212 seconds Lag Time Constant s 2 seconds 5

High Steam Flow in a Steam Line Steam Line Isolation of s d/p corresponding to Coincident with Safety Injection and Aficcted Line 0.66 x 10'lb/hr at Low T vo 1005 psig 4

2 540 F 6

High-high Steam Flow in a Steam Line Isolation s d/p corresponding to Steam Line Coincident with of Affected Line 4 x 10'lb/te at Safety injection 806 psig 7

Low-low Steam Generator Water Auxiliary Feedwater 220% of narrow range instrument Level Initiation 2 5% of narrow range instrument (Unit 1)"

8 Undervoltage on 4 KV Busses Auxiliary Feedwater 2 75% ofnormal Initiation voltage Initiates also containment isolation, feedwater line isolation and starting of all containment fans.

• nis setting limit annlies to Unit I until the narrow range lower tan is changed to the lower oosition consistent with Unit 2.

d/p means differential pressure Unit I - Amendment No.-144 Unit 2 - Amendment NoA47 Page I of 2 Ap n !S, '983 4

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1 ATTACHMENT LOW AND HIGH PRESSURIZER PRESSURE REACTOR TRIP j

INSTRUMENT UNCERTAINTY /SETPOINT CALCULATION t

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l VECTRA July 30,1996 0087-00033.303-106 Wisconsin Electric Power Company 3

Nuclear Power Department l

231 W. Michigan Street j

P.O. Box 2046 Milwaukee, WI 53201 i

ATTENTION:

Mr. Gene Gross j

Instrumentation and Control Engineer

SUBJECT:

Point Beach Nuclear Plant Setpoint Verification Program Contract Number 232007 Low and High Pressurizer Pressure Reactor Trip Instrument Uncertainty /Setpoint Calculation j

PBNP-IC-12, Revision 1

Dear Mr. Gross:

Per your request, VECTRA Technologies, Inc. has revised the subject calculation to include setpoint evaluations of the proposed Technical Specification values and plant setpoints for the Low and High Pressurizer Pressure Reactor Trips. The purpose of this calculation is to support the Unit 2 Steam Generator Replacement in October,1996 and the associated Technical Specification changes. By copy of this letter, VECTRA calculation PBNP-IC-12, Revision 1 is being transmitted to you in accordance with Wisconsin Electric Procedure NP 7.2.4, Revision 1," Calculation Preparation, Review, and Approval." Please note this calculation will be updated at a later date to incorporate the remaining portions of the loop.

Should you require additionalinformation, please feel free to call Karen De Podesta at (708) 778-4445 or me at (708) 778-4442.

Very tmly yours,

{ ~ri g ll T,s./ d 2 Y 5'zh l' l

Joseph R. Basak Project Manager l

0 WPWEPCOTLETTER003-106 dos Enclosure cc:

Rick Kohrt (w/o)

Dave Andreoni(w/o)

Paul Katers (w/o)

File

.IllL 311996