ML20084U703

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Proposed Tech Specs 2.2.1,3.3.1 & Tables 2.2-1,3.3-1,3.3.2 & 4.3-1,Item 4 Re Negative Flux Rate Trip of Reactor
ML20084U703
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 04/15/1991
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20084U701 List:
References
NUDOCS 9104220202
Download: ML20084U703 (6)
v • d • e


Text

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.ATTACFIMENT 2 PROPOSED TECllNICAL SPECIFICATIONS

2.2.1, 3.3.1, TABLES 2.2 1, 3.3 1, 3.3 2, 4.3 1, ITEM 4 l-

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r 9104220202 910413 hDR ADOCK 05000498 PDR A1/016.N16

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ou . TABLE 2.2-1 gto o. .o.

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5x RFACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS

,$Q j'$" i;; IOTAL SENSOR og$ s Alt 0WANCE ERROR FUNCTIONAL UNIT (TA) Z (S) TRIP SETPOINT ALLOWABLE VAlUE-

< 1. Manual Reactor Trip N.A. N.A. N.A. N.A. N. A.

2. Power Range, Neutron Flux
a. High Setpoint 7.5 4.56 0 <109% of RTP**' 1111.3% of RIP **

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b. Low Setpoint H. 3 4. % 0 -<75% of RTP** :77. 3% of RTP**

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3. Power Range, Neutron Flux,. 0.5 <5% of RTP** with <6.3% of RTP** with
1. 6 0 High Positive Rate 5 time constant 3 time constant gg,Dka ._ >2 seconds g econds 4 Power Range, Neutron Flux, 1. 6 - 0. 5 ~ O <5% of RTP** with <6.3% of RTP** with High Negative Rate ' ~

3 time constant i time constant ro h2 seconds >2 seconds

^

5. Intermediate Range, 17.0 8.41 0 <25% of RTP** <31.1% of RTP**

Neutron Flux

6. Source Range, Neutron Flux 17.0 10.01 0 1105 cps $1. 4 .v 105 cps
7. Overtemperature AT 6.8 4. 66 - .1. 5 + 0. 9 # . See Note 1 See Note 2
8. Overpower AT 5.5 1.74 1. 5 See Note 3 See Note 4
9. Pressurizer Pressure-Low 3.1 0.71* 2. 0 >1870 psig >1862 psig
10. Pressurizer Pressure-High 3.1 0.71 2.0 <2380 psig $2388 psig
11. Pressurizer W'ater Level-High 5.0 2.76 2. 0 $92% of instrument $93.6% of instrument i

span span

12. Reactor Coolant Flow-tow 4.0 3.19 0.6 >91.8% of loop >90.9% of loop Besign flow
  • design flow"

" Loop design flow = 95,400 gpm-

    • RlP = RATED THERMAL POWER
  1. 1.5% span for AT; 0.9% span for Pressurizer Pressure

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. __ _ , _ _ _ _ _ _ . ~ _ . _ _ .

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  • M f/CiMENT 4 ST-HL AE 3750 PAGE .3 0F 5 //

/mN DC LIMITING SAFfTY SYSTEM SETTING.!, -

( AnfJ L AUG 031990 l

REACTOR TRIP SYSTEM INSTRUMEKTATION SETPOINTS (Continued)

\L s COPY

\ T2#

The various Reactor trip ef tcuits automatically open the tReac$,3 bip c breakers whenever a condition monitored by the Reactor Trip System re;atheFa preset or calculated level.

In addition to redundant channels and trains the design approach provides a Reactor Trip System which sonitors numerous sys, tem L

variables, therefore providing Trip System functional diversity. The functional capability at the specified trip setting is required for those anticipatory or i

L diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. This prevents the reactivity insertion that would otherwise result l-

' from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.

Manual Reactor Trip '

The Reactor Trip System includes manual Reactor trip capability.

Power Ranoe, Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables,The setting. Low Setpoint trieach provideswith protection its ownduring trip setting suberttical used andforlow a High and Low i (- power operations to mitigate the consequences of a power excursion beginning from low power, and the High Setpoint trip provides protection during power operations to sitigate the consequences of a reactivity excursion from all l power levels.

i The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) end is automatically reinstated

. below the P-10 Setpoint.

power Range. Neutron Flux, Hion Rates The Power Range Positive Rate trip provides protection against rapid flux l.

i increases which are characteristic of a rupture of a control rod drive housing,

' Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for- rod ejection from mid power.

The Power Range bgative Rate trip provides protection for c6KErollod drop t

accidents. At high power a single or multiple rod drop accident could cause i

t local flux peaking witch could cause an unconservative local DNBR to exist. The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor. No credit is taken for operation of the Power Range Negative Rate trip for those control rod drop accidents for which DNBRs will be greater than the design limit.

(

SOUTH TEXAS - UNITS 1 & 2 B 2-4 June 27, 1990

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TABLE 3.3-1 5 REACTOR TRIP SYSTEM INSTRUMENTATION 5

MINIMUM M TOTAL NO. CHANNELS CHANNELS APPLICABLE 5- OF CHANNELS TO TRIP OPERABLE MODES _ ACTION 7 FUNCTIONAL UNIT ,

1, 2 1 1 2 Manual Reactor Trip 2 4*, 5*

E 1. 2 1 2 3*, 10 l

3 I

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2. Power Range, Neutron Flux 4 2 3 ' 1, 2 2
  • High Setpoint 2 j
a. 2 3 1###, 2

~ Low Setpoint' 4 b.

2 i 2 3 1, 2 Power Range, Neutron Flux 4  :

\3. liigh Positive Rate M' J 9s1 w 4. Power Range, deutron Flux 4

~-

2 3 1, 2 2

)

  • High Negative Rate J 1 2 1###, 2 3 Intermediate Range, Neutron Flux 2 45.
6. Source Range, Neutron Flux 1 2 2## 4 2 5* 10
a. Startup 1 2 3*, 4*,

Shutdown 2 b.

2 3, 4, 5 4 2 0 _

Ext. ended Rance, Neutron Flux 7.

Overtemperature AT 4 2 3 1, 2 6 w3l

> --4 -y 8.

4 2 3 1, 2 6 '

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9. Overpower AT 5 11 6 W " E l 3 1 l 10. Pressurizer Pressure--Low 4 2 Ski (Interlocked with P-7) om %o 3 1, 2 6 4 2
11. Pressurizer Pressure--High 2 3 1 6 h I Pressurizer Water Level--High 4 12.

(Interlocked with P-7) ' ,

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' TABLE 3.3-2 IS y ' REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES, y FUNCTIONAL UNIT RESPONSE TIME 1.' Manual': Reactor Trip - N.A.

~2. Power Ran'ge, Neutron Flux. $ 0.5 second*'

h

'I 3. Power Range, Neutron Flux, High Positive Rate. N.A.

h

% 4.V Power Range, Neutron Flux.

High Negative Rate J .5 second*

5. Intermediate Range, Neutron Flux N.A.

w .

1 o. Source Range, Neutron Flux $ 0.5 second*

7. Extended' Range, Neutron' Flux 'N.A.
d. Overtemperature AT $ 8.0 seconds *
9. ' Overpower AT' $ 8.0 seconds *
10. Pressurizer' Pressurr -Low $ 2 seconds
11. Pressurizer Pressure--Hig;a $ 2 seconds ,

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12. Pressurizer Water Level--High -< 2 seconds Si5: <o cng SI r

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  • Neutron detectors'are exempt'from response time testing. Response time of the neutron flux signal portion 'O of the channel shall be' measured from detector output or input of first electronic component in channel. 'm a f I -

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y. TABLE 4.3-1 c

2 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILt.ANCE REQUIREMENTS .

N TRIP ANALOG ACTUATING MODES FOR

] . CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL- OPERATIONAL ACTUATION SURVEILLANCE CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED--

k- _ FUNCTIONAL UNIT

" 1. Manual Reactor Trip M.A. N.A. M.A. R(14) M.A. 1, 2, 3*, 4*, 5* -

e. 2. Power Range, Meutron -

u Flux

a. High Setpoint S O(2,4), Q(17) N.A. N.A. 1, 2 -

'M(3. 4),

Q(4. 6),

[

^

R(4, 5)

$/U(1) N.A. M.A. 1***, 2 w b. Low Setpoint ~,

R(4) 5 3. Power Range, Neutron N. A.' R(4) Q(17) N.A. M.A. 1, 2 Y Flux, tf High Positive Rate .

0.4 f r Range, Neutron N.A. R(4) Q(17) N.A. M.A. p ^

Negative Rate [

5/U(1) N.A. M.A. 1***, 2 {

5. Intermediate Range, 5 R(4,5) e Neutron Flux h 6. Source Range, Neutron S R(4,5) S/U(1).

Q(9)(17) N.A. M.A. 2**, 3, 4, 5 g Flux

  • 7. Extended Range, 5, R(4)- Q(12,17) M.A. N.A. 3, 4, 5 y y Neutron Flux g3-

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8. -dverteeperature AT S R- Q(17) N.A. N.A. 1, 2

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j 9. Overpower AT S R Q(17) N.A. M.A. 1, 2 d2

[o 10. Pressurizer Pressure

,--Low 5 R Q(17) N.A.

N.A. 1 oWp

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. <.g

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