ML20098A450

Proposed Tech Spec Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints

ML20098A450
Person / Time
Site:	Catawba
Issue date:	09/18/1995
From:	DUKE POWER CO.
To:
Shared Package
ML20098A448	List: ML20098A446 ML20098A450 ML20098A451
References
NUDOCS 9509260004
Download: ML20098A450 (6)

Text

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3 E"$ TABLE 2.2-1 (Continued) .

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"$ 9 REACTOR TRIP SYSTE'M INSTRUMENTATION TRIP SETPOINTS x,8 C -

s TRIP SETPOINT ALL'0WABLE VALUE gg 7 FUNCTIONAL UNIT ,

o 3l$ E 12. Steam Generator Water E.*U h u -

Level Low-Low

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'llo.i nat row can e. 19% e narroe ran sp4n to of spcu ^Ip

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a. Unit 1 ' n .. ,

". 0% to 30% 0% to 30% T incret linearly increas cinearly i

.0% of span to . % of span  ; y

/toom 30% to 100% RTP* m 30% to 100% RTP* i &

S-

b. Unit 2 236.8% of narrow 235.1% of narrow jg range span range span a

13. Undervoltage - Reactor 277% of bus voltage 276% (5016 volts)

? Coolant. Pumps (5082 volts) with a .

• 0.7s. response time

14. Underfrequency - Reactor 156.4 Hz with a 255.9 Hz Coolant Pumps 0.2s response time

15. Turbine Trip ,

>2 2550 psig 2500 psig 55 a. Stop Valve EH Pressure Low

}i k$ b. Turbine Stop Valve Closure 21% open AIX open

16. Safety Injection Input from ESF H.A. . N.A.

2S E2 '

kb *RTP - RATED THERHAL POWER .

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3- TABLE 2.2-1 (Continued) .

g TABLE NOTATIONS (Continued) 5

' NOTE 1: .

(Continued) 58l.5 F E_ T' 5^0."*? (Nn ~ al Tm allowed by Safety Analysis);

$ K3 -

Overtemperature AT reactor trip depressurization setpoint penalty coefficient as

, presented in the Core Operating Limits Report; ,

P =

Pressurizer pressure, psig; P' = 2235 psig (Nominal RCS operating pressure);

S - Laplace transform operator, s"; t

=

and f (AI) is a function of the indicated difference between top and bottom detectors of. the power-3 8 r range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that: '

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m A 4 0) For q -q between the " positive" and " negative" f 3(ol) breakpoints as presented in the i

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Core 5pera,tingtimitsReport; , i f (oi) = 0, where q and q are percent RATED THERMAL POWER in the top and bottom halves of gg t e core respectiv y, an q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER; EE (ii) -q is more negative than the f -

For each percent

" negative" breakpoint AIpresented that the in magnitude the Core of q,Oper,ating Limits Report,ipthe AT Yr(AI)

Setpoint or shall be automatically reduced by the f,(AI) " negative" slope presented in the Core gg Operating Limits Report; and

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(Eii) -q

, For each breakpoint

" positive" percent AIpresented that the in magnitude the Core of q,Oper,ating Limits,Reportis , theATYripSetpoint more positive than gg shall be automatically reduced by the f i(AI) " positive" slope presented in the Core 3, 3. -

Operating Limits Report.

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NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more -

than 4.5% of Rated Thermal Power. .

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9 TABLE 2.2-1 (Continued)

$ TABLE NOTATIONS (Continued)

S NOTE 3: (Continued) 7 E K6 =

Overpower AT reactor trip heatup setpoint penalty coefficient as presented in

] the Core Operating Limits Report for T > 590.8'F and K6 - O for T s 590.8'F. '

[ T = As defined in Note 1, T" -

Indicated T at ED ERMAL OWER (Calibration temperature for AT instrumental.y ion,<-5^0.3"f))T 5@.

S -

As defined i~n Note and f2 (AI) is a function of the indicated differences between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that: 3 '

8 m (i) for q, - q3 between the " positive" and " negative" f 2(AI) breakpoints as presented in

.L the Core Operating ' Limits Report; f2 (AI) - 0, where q and q are percent RATED {

e THERMAL POWER in the top and bottom halves of the cor,e respe,ctively, and q, + q3 is R total THERMAL POWER in percent of RATED THERMAL POWER; -'

kk (ii) for each percent AI that the magnitude of q - q, is more negative than the f RR

" negative" breakpoint presented in the Core, Operating Limits Report, the AT fr(AI) ip 33 Setpoint shall be automatically reduced by the f 2(AI) " negative" slope presented in EE . the Core Operating Limits Report; and Ek (iii) for each percent Al that magnitude of q -q is more positive than the f (AI)

__ " positive"breakpointpresentedintheborebperatingLimitsReportthe2TTrip g; 5 Setpoint shall be automatically reduced by the f2(AI) " positive" slope presented in the Core Operating Limits Report.

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%; NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more m -- than 3.0% (Unit 1) and 3.3% (Unit 2) of Rated Thermal Power.

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T ,

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AttacNment 2' Catawba Nuclear Station -

- Technical Specification Change-

Page 1 of 2 '

Prana-A revision to Technical Snecification Table 2 2-1 Reactor Trip System instmmentation Trip Setonints In Note 1: _

! change "T's 590.8

• F (Nominal T,yo allowed by Safety Analysis)"

to "T's 585_.1

• F, (Nominal T,yo allowed by Safety Analysis)"

" In Note 3 change "T" = Indicated T,yo at RATED THERMAL POWER (Calibration temperature for AT instrumentation,5 590.8 *F)"

to "T" = Indicated T,yo at RATED THERMAL POWER (Calibration temperaiure for AT

instrumentation, s 585.1 *F)"

Technical Justification The values for T' and T" are defined as T 4va Allowed by Safety Analysis and Reference

.T4va at RATED THERMAL POWER respectively. In Note 1 and 3 of Table 2.2-1. When the steam generators are replaced at Catawba Unit 1, progranuned full power T,yo will be changed from 590.8 *F to 585.1

• F. This temperature was chosen based on returning the secondary side steam pressure to the original value after replacement of the steam generators.

585.1

• F was the assumed value for nominal full power T,yo in all applicable safety analyses related to replacement of the steam generators.

No Significant Harnrds Analysis The following analysis, required by 50.91, concludes that the proposed amendment will not involve significant hazards considerations as defined by 10 CFR 50.92.

10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or -

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(2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or

Attachment 2 L Catawba Nuclear Station Technical Specification Change Page 2 of 2 :

(3) - Involve a significant reduction in a margin of safety.

This proposed change to the Technical Specifications does not involve a significant increase in the probability or consequences of an accident previously evaluated. Changing the value for T ava in Notes 1 and 3 of Table 2.2-1 will update the value to agree with the T,yo assumed in the applicable safety analyses for replacement of the steam generators. Acceptable results were obtained for all required reanalyses. The probability of an accident will not be significantly affected by operation with the new T,yo value, because all equipment will be operated within acceptable design limits. The consequences of previously evaluated .

accidents which are affected by this change have been evaluated, and have been determined to be within acceptable limits.

This proposed change will not create the possibility of a new or different kind of accident from any previously evaluated. This change does not change the physical configuration of -

the plant, and all analyses which are affected by replacement of the steam generators have been determined to have acceptable results assuming this value for T,yo.

This proposed change to the Technical Specifications will not involve a significant reduction in the margin of safety. All safety analyses which were affected by replacement of the steam generators assumed this value for T,yo and the results were determined to be within pn:viously acceptable limits.

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