ML20035H086

Proposed Tech Specs Re Reactor Protection & Engineered Safeguards & Limiting Safety Sys Settings

ML20035H086
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	04/27/1993
From:	COMMONWEALTH EDISON CO.
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ML19303F591	List: ML20035H083 ML20035H086 ML20035H088 ML20035H089
References
NUDOCS 9305030096
Download: ML20035H086 (33)

Text

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i ATTACHMENT D PROPOSED CHANGES MARKED UP PAGES FOR j

PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS OF FACILITY OPERATING LICENSES DPR-39 AND DPR-48 LICENSE AMENDMENT REQUEST NO. 93-03 PAGES MODIFIED 10a 10b 10c 10d 22 32 130a 131b 135 136 144 i

ZNLD/2562/17 9305030096 930427 DR ADDCK 05000295 PDR

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i PART 1 STEAM GENERATOR OVERFILL PROTECTION

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No. of Hinlaum Hinleum Operator Action c tion Channel ristion IPer tintti No. of Channels Operable Degree of If Column 3 or 4 Channala to Trio.

Channtistii Endandantu m sannot be met +--

Sainninta Aaixillarv fendwater 1.

Manual 1/ pump 1/pvep I/ pump 0

Halntain Hot Shutdown *"

N.A.

2.

Automatic 2

1 2

1 Maintain Hot Shutdow***

N.A.

3.

Steam Generator (5/G)

Wat:r Level low-low I.

Start Hotor 3 per S/G 2 per S/G 2 per 5/G 1 per S/G Halntain Hot shutdown"*

10% Marrow Range" any 1/4 5/G Driven Pumps

11. Start Turbine 3 per 3/G 2 Per 3/G 2 per 5/G 1 per S/G Halntain Hot shutdem"*

10% Marrow Range" any 2/4 5/G Driven Pumps 4-1/ bus 2

3 1

Maintain Hot shutdown *"

75% RCP, Bus Voltage 4.

Und;rvoltag,-aCP butses Start Turbine Driven Pump 1;rbine Driven Pumps 2

1 2

1 Halntain Hot Shutdown"*

N.A.

5.

5.I. Start Hotor and 6.

St:tlen Blactest 3-1/ bus 2

2 1

Maintain Hot Shutdewn"*

Time Dependent 5tcrt Motor and Turbine on Voltage

• Driven Pump 3846 12% volts 7.

Secondary tindervoltage 2/ bus 2

2 0

N.A.

for 5 15% sin.

with inherent

,.... ~.

ti,4 delay of 8 3, q 's, 12 sec.*

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hFOOTNOTESONPAGE131b.

ENG1HEERED SArtGUARDS ACTUATION SYSTEM - LIMITING COH01TIONS FOR OPE I

Table 3.4-1 (Continued) 6 l

Amendment Hos. 439 died I28 l

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11gALGenerator Overfill Protection i

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Steam Generator (S/G)

Water Level Hi-Hi 3 per $/G 2 Per S/G 2 Per S/G 1 Per S/G Maintain Hot Shutdown ***

70% Marrow Range

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If alntmum conditions are not' met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the COLD SHUT 00NN condition within an I

4-

. additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W Setpoints are i established _ tolerances for instrument channel and setpoint errors as specified_Ln8 Channel 7KccuriETe57er11TChannel Accuracles and Sitifolht T61eVances foTfMES PFocess I ~a~nd C neactor Protection and

, ControLSylines" August 30,371 - CEb26S2_for_ Unit-2 untti stattupJrostrafmeling_ outage 22AILand_as_specified Apr

-1992, for inf" Zion NSSS Setpoint' Evaluation, Protection System Channels,Jagle 21 Version" vision 1,il)_rliThe listruments (Orilt T at startu

~ 'liN ff6si refueling oilage ZlftI2 and Unit 2 at startui'Trom refuel 1h

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e de m slat 1 not~be set o exceed i U mlE W SifitT Systim~SetTlh(.-

N 2.,m A..ms-This channel may be placed In' the bypass mode during periods of active testing during safeguards equipment m

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testing as specified in Section 4.4.2.

Setpoints are e established tolerances for instrument channel and setpoint errors as specified in " Channel

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c Accuracles, Overall Channel Accuracles and Setpoint Tolerances for R NES Process I and C Reactor Protection and '

Control Systems" August 30, 1971 - CEM-2652.. The-instruments shall not be set to exceed a Limiting. Safety System-S2tting.

~

l ** Requires simultaneous actuation of two switches.

' Maintain Hot shutdown' means maintain or be in 100T SMUTDONM within four hours if the unacceptable condition arises during power operation.

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ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING ColeITIONS FOR OPERATION AIS SETPOIN 4

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(Footnotes to Table) p i

TABLE 3.4-1 (Continued)

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Amendment Mos. 4Si~a;M30-,'

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ACTUATION CHANNEL CHANNEL CHANNEL CNAMEL DESCRIPTION

. CHECK.

CALIBRATION FUNCTIONAL TEST j,-

IV.

STEAMLINE ISOLATION 1.

Manual Actuation M.A.

M.A.

R 2.

Automatic Actuation M.A.

M.A.

M 3.

High-Nigh Containment Pressure See Item II Above 4.

Nigh Steam Line flow in Coincidence with Low-Low Tavg or Low Steam Prassure See Item 1 Above V.

AH11LIARY FEEDNATER 1.

Manual N.A.

N.A.

R 2.

Automatic N.A.

M.A.

M 3.

Steam Generator S

R Q

Mater Level Low-Low 4.

Undervoltage - RCP Susses M.A.

R R

5.

Safety Injection See Item I on Page 134 6.

Station Blackout N.A.

R R

7.

Secondary Undervoltage M

R R

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P-11 N.A.

M.A.

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P-12 N.A.

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[S-Oncepershift M - Once per. month N.A. - Not appilcable

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, R - Once per refueling shutdown - callbration of these instruments may be done as much as six months )

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prior to start of refueling outage and still satisfy this requirement.

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ENGINEERED SAFEGUARDS SYSTEM TESTING AND CALIBRATION REQUIREMENTS TABLE 4.4 (Continued) 135' Amendment Nos. IM. 4 ; &

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STEAM GENERATOR

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Bases

, 3.4 The engineered safety features instrumentation Availability of control power to the engineered safety measure temperatures, pressures, flows, levels in features trip channels is continuously monitored.

In 4

a reactor coolant system, steam system, reactor general, the loss of instrument power to the sensors, containment and aux 111ary systems.

It actuates instruments, or logic devices in the engineered safety the engineered safety features and monitors their features instrumentation, places that channel in the operation.

Process variables required on a trip mode. The one exception is the containment spray continuous basis for the start-up, operation, and initiating channels which require instrument power for shutdown of n unit are indicated, recorded and actuation.

controlled from the control room. The quantity and types of process instrumentation provided The engineered safety features actuation channels are ensure safe and crderly operation of all systems designed with sufficient redundancy to provide the and processes over the full operating range of a capability for channel callbration and test during unit.

(1) power operation. Bypass removal of one actuation channel is accomplished by placing that channel in a The engineered safety features instrumertation tripped mode, i.e., a two out of three matrix logic 1

monitors parameters to detect failures in the becomes a one out of two matrix logic. Testing does Reactor Coolant and Steam Flow Systems and to not trip the system unless a trip condition occurs in a initiate engineered safety features equipment concurrent channel (2).

operation.

The engineered safety features actuation system The engineered safety features systems are setpoints specified in Table 3.4-1 are the nominal actuated by radundant logic and coincidence values at which the trips are set. The setpoint for an networks similar to those used for reactor engineered safety features actuation system or protection.

Each network actuates a device that interlock function is considered to be set consistent operates the associated engineered safety features with the nominal value when the "as measured" setpoint equipment, motor starters and valve operators.

Is within the band (estab11thed tolerance) allowed for The channels are designed to combine redundant calibration accuracy.

sensors, and independent channel circuitry, and coincident trip logic. Mhere possible, different The high steam Ilne flow set point is maintained at a but related parameter measurements are utilized.

level which will trip with a steam ifne break as analyzed in the Zion FSAR.

(3) At zero power level, This ensures a safe and reliable system in which a the postulated steam flow for a large break is > 40%

steam flow.

For the spurlous opening of a safety single failure will.not defeat the Intended valve, the safety injection and steam line actuation function.

The Engineered Safety Features Instrumentation System actuates (depending on the result from low pressurtzer pressure.

severity of the condition) the Safety Injection System, Containment Isolation, Containment Spray System and the Diesel Generators.T% sem &

(1)

FSAR Section 7.5.1

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FSAR Section 7.5.2 b cm +avdee gm w%

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(3)

FSAR Section 14.2.5 Amendment Mos. G0-.2 E0 144

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_ _ _ _ _ ___ _ _ _ _ _ _ _. _. _ _ _ _ _.. _ _.. _., _ _ _ _ ~ _.. -, _ _,..

k PART 2 TECHNICAL SPECIFICATION EQUATIONS DESCRIBING-THE OVERPOWER DELTA T AND OVERTEMPERATURE DELTA T FUNCTIONS 1

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NOTE 1: Overtemperature AT (sheet I of 2) k I * *{S

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1 AT,$

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n.,,es,u (,y m

r s.,;s, i

sh;-T'ha+K,(P-P')-f

( K, - K2 T;

AT II l

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Where:

f i.tsi - Lead-lag compensator on measured AT

,.);

1+ts Time constants utillred in the lead-lag controller for AT, tg - 8 seconds, tg - 3 seconds ty, v7 A

s 4

5

(

f Lag compensator on measured'AT'

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Time constant utilized in the lag compensator for AT, t3 - O seconds

(

t 3

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Indicated AT at RATED THERMAL PONER AT, 1.36 K,

[

K

- 0.0180/*F 2

(

1.,,s

- The function generated by the lead-lag controller for Tay, dynamic compensation

(

i + t,s y

Time constants utilized in the lead-lag controller for T,yg, t - 33 seconds, ty - 4 seconds'

(

tg, t,

t T.

- Average temperature, 'F s

q-Amendment Nos. i 5 = W -If8 10a

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NOTE 1: Overtemper w e AT-(sheet'2 of 2)

(

s

- Lag compensator on measured T.,9

.(

. 1+v5 g

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= 0 sec W s -

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Q

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1. 89T avg _%cfjaW,t, T'

- 1 562.2*F (Nominal T at RATED THERMAL POWER)

~~

avg K

- 0.000935 3

(

P

- Pressurtzer pressure, psig m

P'

- 2235 psig (Nominal RCS operating pressure)

)

S

- Laplace transform operator, S-a y

I and f,(AI) is a function of the Indicated difference between top and bottom detectors of the power range nuclear ton chamber; with gains to be selected based on measured instrument response during plant startup tests such that:

(

POWER in the top and bottom halves of the core resp,(ectively, and qt + qb is total THEIMAL. POWE for qt - qb between -50 percent and +8.0 percent f (1)-

percent of RATED THERMAL PONER).

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e (11) for each percent that the magnitude of (qt'- qb) exceeds -50 percent, the AT trip setpoint.shall be

/'

auts.t.tically reduced by 0.0 percent of its value at RATED THERMAL PONER.

(111) for each percent that the magnitude of (qt - qb)-exceeds +8.0 percent, the AT trly setpoint shaII be automatically reduced by 1.66 percent of its value et RATED THERMAL PONER.

(

(

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NOTE 2: Overpower AT (sheet 1 of 2) s V

g)1)

_, c 1 ATy;,[, K f I+TSAI I

[

T - K,',1 ff I

I 4

f TS 1

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1 1

AT 4

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- f ( AD

)

-( 1 + t,5 [ - T*

( I + Ty ) ([ I + T S j g I + t,S j g

[

S i +' v -

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j

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Where:

'O

)

I + tyS 4

- Lead-lag compensator on measured ai

)

1+tS

(

t*

)

ty, tg Time constants utt11 red in the lead-lag controller for AT, vg - 8 seconds, vg - 3 seconds.

et 6

4 3

-LagcompensatoronmeasureNT i+T5.

(

3

)

3

_ - Time constant uttitzed in the lag compensator for AT, 23 - O seconds j 2

AT,

- Indicated AT at RATED TNElW%L POWER K,

- 1.09 K

- 0.020/*F for increasing average temperature and 0 for decreasing average touperature

[

3 t,3

(

5

- The function generated by the lead-lag controller for T.,, dynamic compensation

/

1 + t,,S t

- Time constants utt11 red in the lead-lag controller for Tavg* TJ = 10 seconds y

- Lag compensator on measured Tavg 1+tS

(

(

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(

7

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10c Amenenent Mos.' 'O ; N28

0 o-o, NOTE 2: Overpower AT (sheet 2 cf 2)

{

)

(p=

lagcompensator,t,-0s'conds)

(

= Ilme Constant utlllZed In the measured T e

ayg

)

6 K'

- 0.002117/*F for T>T" and K, = 0 for TIT" 6

),

T

- Average temperature, *F T"

- Indlcated T at RATED THERMAL POWER (calibratlon temperature for AT Instrumentatlon, 1 562.2*F)'

avg S

- Laplace transform operator, S-3

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f (AI)

- O for all AI 2

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indicated by difference between top and bottom The overpower AT reactor trip prevents power power range nuclear detectors, the reactor trip density anywhere in a core from exceeding 1181 of limit is automatically reduced. (6)-

design power density, as described in Sections 7.2.3 and 14.1.2 of the FSAR and includes corrections for axial power distributton, change In density and heat capacity of water with temperature,'and dynamic compensation for piping delays from a core to the loop temperature

==

detectors.

g %.k-( be The low flow reactor trip protects core against

\\,d DNS in the event of a loss of one or two reactor I

The undervoltage reactor trip coolant pumps.

protects a core against DN8 In the event of a loss of two or more reactor coolant pumps. (7)

The low frequency reactor coolant pump trip also 1'

protects against a decrease in flow by tripping a reactor before the low flow trip power is reached.

(3) FSAR Section 14.1.2 (6) FSAR Section 7.2.2 (7) FSAR Section-14.1.6 4

i-Amendment Mos.1-M sf 123 -

1 22

. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _______... -, _. + _-,,

m

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The overtemperature AT and overpower AT reactor 1

trip functions include lag compensation on measured AT and measured T constants have been accounk N. These lag time for in the safety analysis and provide allowance for RTD response characteristics.

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P-6 101 Rated Neutron Flow and Pressure P-7 Eigvivalent to 101 of Rated Turbine Leed" r

1 281 of Rated Power (4 loops) for Unit I at startup from refweling estage Z1R12 and Unit 2 at startup C

F-8 free refuellag estage Z2Rit.**

601 et stated Power (4 loops) for Unit 2 watif startup free refweling estage 22R12.M8 Li 161 of Rated stowtron Flen "

P-It If einlaus conditions are not met within 24 howes, the unit shall be in the Cold htdown conditlen within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Y

+

Setpoints are a estabilshed tolerances for lastrwnent channel and setpelat errors as specified leib1 Accurecies, OMe1

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[CM1 AccidaclEa75Te reEtie~lerancEbr W iiEUrocess'I endTReactir Frotectlen andstrol.Systeme* Auges.t j

+e (CE*452 for_ Unit 2 watti startup free refueling outage Z2RIZ and as specified inj" Zion NSS Chemnels., E.agle 21 Versten", Revision 1. April Safety System Setting.

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(free refwelleg outage Z2Rit., The Instruments shall not be set to enceed a tietting

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Tcr channel test, calibration er enintenance, the minlaue avstYeef ~gPERAblE channels say be reduced by one but te not less than one, For Automatic

-and the einleum degree of i frcy may be reduced by one but to not less than aere, for a menlaws of two hours.

+++

Reactor Trly Logic and Reacter Trip treakers, the alloweble outage time is a seuleme of eight howes.

When block conditions eulst, maintain normal operation.

' Maintain Het h tdown' means maintain er proceed to Not Shotdown within fove hoves if the unacceptable conditlen arises during power operetten.

When blocked condittens outst, meintain norsel operetten.

Verify shutdesse margin lassediately and comply with Section 3.2.1.A,5.

During Modes 3, 4 or 5 and with the Reecter Trly System breakers closed and the Centrol Red Drlwe System capable of re With the number of SPERABLE channels one less then the Minlaus SPDtASLE rhls respetroment, restore the O

the following applies Insperable channel to GPERASLE states within 48 heers or open the Reacter trip brookers within the ment hour.

i During Modes 1 er 2 with one of the dlwerse trip festores (undervettage er Shent Trip Attachment) Insperable, restore it to clotwo within 48 hoors or declare the broeter inoperable and saintain er proceed to Met Sheldoun within fewe heers if the e

88 The broeter shall not be bypassed while one of the diverse trip featween is unacceptable conditten arises during pe=or operetten.

Inoperable oncept for the time respelred for performing antatenance and testing to restore the breaker to GPUtASLE states.

f Setrolets are a estabilshed tolerances for instrument channel and setpoint errors an'specified in " Channel Acevracles, Overa 30, 1971 -

Channel Accwrecies and Setpelat Telerances for W HES Process I and C Reacter Protection and Centrol Systeme* August auf g

The lastrweents'shall not be set to exceed a limiting Safety Systee Setting.

CEW-452.

'h TABLE 3.1-1 (Continued)

Reacter Protection System - Lietting Operetten Candittens and Setpoints j

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5.

6.

Actuation Channel No. of Minimum Minimum Operator Action Descrintion (Per Uniti.

~ Channel s to Trio..

Ch annel s +*

. Degree.of if Column 3 or 4 t

No. of-Channels Operable

~ Redundancy +++

cannot be met +

le_tpoints

.V.

guxiliarv Feedwater 4 -

1.

Manual 1/ pump 1/ pump 1/ pump 0

Maintain Hot Shutdown"*

. N.A.

2.

Automatic 2

1 2

1 Maintain Hot Shutde,<n*"

N.A.

3.

Steam Generator (S/G)

Water Level low-low i

' L Start Motor 3 per S/G 2 per S/G 2 per S/G 1 per S/G Maintain Hot Shutdown"*

10% Narrow -

Driven Pumps any 1/4 S/G Range" II. Start Turbine

- 3 per S/G 2 per S/G 2 per S/G 1 per S/G Maintain Hot Shutdown"*

10% Narrow Driven Pumps

. any 2/4 S/G Range" 4.

Undervoltage-RCP 4-1/ bus 2

3 1

Maintain Hot Shutdown"*

75% RCP, Bus busses Start Turbine Voltage Driven Pump 5.

S.I. Start Motor and Turbine Driven Pumps 2

1 2

1 Maintain Hot Shutdown"*

N.A.

6 '. Station Blackout 3-1/ bus 2

2 1

Maintain Hot Shutdown *"

Time Start Motor and Turbine Dependent Driven Pump

- on Voltage *'

7.

Secondary Undervoltage 2/ bus 2

2 0

N.A.

3846 12% volts for 5 5% min.

with inherent time delay of 8 12 sec.*

VI. SteamJeatrALQE Overfill Protegf,ign i

1.

Steam Generator ($/G)

Water Level Hi-Hi 3 per S/G 2 Per S/G 2 Per S/G 1 Per S/G Maintain Hot Shutdown"*

70% Narrow Range "

SEE FOOTNOTES ON PAGE 131b.

t

. ENGINEERED SAFEGUARDS; ACTUATION SYSTEM - LIMITING CONDITIONS FOR OPERATION AND SETPOINTS

- Table 3.4-1 (Continued)

OSR-299/25 130a Amendment Nos.

hue = = s m.en,.

e.u___s% v es,n-

_si..-. _,.c de w,

we

-er e-en. w.c 2-===

e

. =

,-w

=.=w-

,..-m

-.se--w

--rwmw. - -ew 2.-.vrw-+..--,wre%~-en e,m.m. e e+mm-vi==%i e me #

s,

..m-pr-c----r-*-

e

-ew m.we

=ew.+---a:r.

h.

..+r. w w

+ If minimum conditions are not met within 24-hours, the unit shall be in the COLD SHUTDOWN condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Setpoints are established tolerances for instrument channel and setpoint errors as specified in " Zion NSSS

++

Setpoint Evaluation, Protection System Channels, Eagle 21 Version", Revision 2, March 1993.

The instruments shall not be set to exceed a Limiting Safety System Setting.

This channel may be placed in the bypass mode during periods of active testing during safeguards equipment

+++

testing as specified in Section 4.4.2.

Setpoints are

• established tolerances for instrument channel and setpoint errors as specified in " Channel Accuracles, Overall Channel Accuracles and Setpoint Tolerances for H NES Process I and C Reactor Protection and Control Systems" August 30, 1971 - CEW-2652.

The instruments shall not be set to exceed a Limiting Safety System Setting.

Requires simultaneous actuation of two switches.

'Haintain Hot Shutdown' means maintain or be in HOT SHUTDOWN within four hours if the unacceptable condition arises during power operation.

ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITIONS FOR OPERATION AND SETPOINTS (Footnotes to Table)

TABLE 3.4-1 (Continued) l 20SR-299/26 131b Amendment Nos.

=.

ACTUATION CHANNEL CHANNEL CHANNEL CBANNEL DESCRLP_UDli

_. CHECK _

CALLBRATION FUNCTIONAL TEST IV.

SlEAM_UXE ISOLATIQt!

1.

Manual Actuation N.A.

N.A.

R 2.

Automatic Actuation N.A.

N.A.

M 3.

High-High Containment Pressure See Item II Above 4.

High Steam Line Flow in Coincidence with Low-Low Tavg or Low Steam Pressure See Item I Above V.

AJJXLUARY FEEDHATER 1.

Manual N.A.

N.A.

R 2.

Automatic N.A.

N.A.

M 3.

Steam Generator 5

R Q

Hater Level Low-Low 4.

Undervoltage - RCP Busses N.A.

R R

5.

Safety Injection See Item I on Page 134 6.

Station Blackout N.A.

R R

7.

Secondary Undervoltage M

R R

ENGINEERED SAFEGUARDS SYSTEM TESTING AND CALIBRATION REQUIREMENTS TABLE 4.4 (Continued)

ZOSR-299/27 135 Amendment Nos.

ACTUATION CHANNEL CHANNEL CHANNEL CliMRELQESCRIf1LON

._CtLECL CALIBRAIl0E EUECIIORal lESl VI.

SIELM_GERERA_T_QR QVERELLLJ_RolECIl0N 1.

Steam Generator-(S/G) Hater S

R Q

Level Hi-Hi EERMISSIXES 1.

P-11 N.A.

N.A.

Q 2.

P-12 N.A.

N.A.

Q ENGINEERED SAFEGUARDS SYSTEM TESTING AND CALIBRATION REQUIREMENTS TABLE 4.4 (Continued)

ZOSR-299/28 136 Amendment Nos.

B1361 3.4 The engineered safety features instrumentation measure Availability of control power to the engineered safety features trip temperatures, pressures, flows, levels in a reactor coolant channels is continuously monitored. In general, the loss of system, steam system, reactor containment and auxiliary instrument power to the sensors, instruments, or logic devices in the systems. It actuates the engineered safety features and engineered safety features instrumentation, places that channel in monitors their operation. process variables required on a the trip mode. The one exception is the containment spray initiating continuous basis for the start-up, operation, and shutdown of channels which require instrument power for actuation, a unit are indicated, recorded and controlled from the control room. The quantity and types of process instrumentation The engineered safety features actuation channels are designed with provided ensure safe and orderly operation of all systems and suf ficient redundancy to provide the capability for channel processes over the full operating range of a unit. (1) calibration and test during power operation. Bypass removal of one actuation channel is accomplished by placing that channel in a The engineered safety features instrumentation monitors tripped mode, i.e., a two out of three matrix logic becomes a one out parameters to detect failures in the Reactor Coolant and Steam of two matrix logic. Testing does not trip the system unless a trip Flow Systems and to initiate engineered safety features condition occurs in a concurrent channel (2).

equipment operation.

The engineered safety features actuation system setpoints specified The engineered safety features systems are actuated by in Table 3.4-1 are the nominal values at which the trips are set, redundant logic and coincidence networks similar to those used The setpoint for an engineered safety features actuation system or for reactor protection. Each network actuates a device that interlock function is considered to be set consistent with the operates the associated engineered safety features equipment, nominal value when the "as measured" setpoint is within the band motor starters and valve operators. The channels are designed (established tolerance) allowed for calibration accuracy.

to combine redundant sensors, and independent channel circuitry..and coincident trip logic. Where possible, The high steam line flow set point is maintained at a level which different but related parameter measurements are utilized.

will trip with a steam line break as analyzed in the Zion FSAR. (3)

At zero power level, the postulated steam flow for a large break is >

This ensures a safe and reliable system in which a single 40% steam flow. For the spurious opening of a safety valve, the failure will not defeat the intended function. The Engineered safety injection and steam line actuation result from low pressurizer Safety Features Instrumentation System actuates (depending on pressure.

the severity of the condition) the Safety Injection System.

Containment Isolation, Containment Spray System and the Diesel i

Generators. This system also provides a feedwater system (1)

FSAR Section 7.5.1 isolation to prevent Steam Generator overfill.

(2)

FSAR Section 7.5.2 (3)

FSAR Section 14.2.5 ZOSR-299/29 144 Amendment Nos.

~ --.. - - - --

l i-t i

t i

PART 2

[

t TECHNICAL SPECIFICATION EQUATIONS

-i DESCRIBING THE OVERPOWER DELTA T i

AND OVERTEMPERATURE DELTA T FUNCTIONS l

t i

k

.j 1

i

~

I i

l

-i i

~

i i

i 1

1 I

ZOSR-299/30 l

NOTE 1: Overtemperature AT (sheet 1 of 2) 4 (1 + T453 (1 + t153 f

-T'}: +K3 (P - P') - fj (aI)

AT l 1 AT Kj - K2 T

o (1 + TSSl kl + T2SJ

\\

l i

Hhere:

1 + 14S - Lead-lag compensator on measured AT 1 + tSS 14, t5

- Time constants utilized in the lead-lag controller for aT, t4 = 8 seconds, t5 - 3 seconds AT

- Indicated aT at RATED THERMAL POWER O

K1

- 1.36 I

K

- 0.0180/*F 2

1 + tjS

- The function generated by the lead-lag controller for T dynamic compensation avg 1 + T23 tj, T2

- Time constants utilized in the lead-lag controller for Tavg* T1 - 33 seconds, 12 - 4 seconds T

- Average temperature, "F

- ZOSR-299/31 10a Amendment Nos.

NOTE 1: Overtemperature AT (sheet 2 of 2)

T'

= 1 562.2*F (Nominal T at RATED THERMAL POWER) avg K

- 0.000935 3

P

= Pressurizer pressure, psig P'

= 2235 psig (Nominal RCS operating pressure)

S

= Laplace transform operator, S-1 and f (aI) is a function of the indicated difference between top and bottom detectors of the power range 3

nuclear ion chamber; with gains to be selected-based on measured instrument response during plant startup tests such that:

(1) for qt - qb between -50 percent and +8.0 percent f (AI) = 0 (where qt and qb are percent RATED THERMAL i

POWER in the top and bottom halves of the core respectively, and qt + qb is total THERMAL P0HER in percent of RATED THERMAL POWER).

(11) for each percent that the magnitude of (qt - qb) exceeds -50 percent, the AT trip setpoint shall be automatically reduced by 0.0 percent of'its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (qt - qb) exceeds +8.0 percent, the AT trip setpoint shall be automatically reduced by 1.66 percent of its value at RATED THERMAL P0HER.

1 ZOSR-299/32 10b-Amendment Nos.

NOTE 2: Overpower AT (sheet 1 of 2)

(1 + t S) ft S T

f 3

3 AT s AT K, - K T-K, T - T"

- f (OI) o 3

2 (1 + T 5)

(1 + 1 5)

(

)

3 3

Where:

Lead-lag compensator on measured AT 1+tS3 t

2

- Time constants utilized in the lead-lag controller for AT, t4 - 8 seconds, 13 - 3 seconds.

4, 3

Indicated AT at RATED THERMAL POWER AT g

1.09 K

4 0.020/*F for increasing average temperature and 0 for decreasing average temperature K

s 1b 3

- The function. generated by the lead-lag controller for T dynamic compensation avg 1+T53

- Time constants utilized in the lead-lag controller for Tavg T3 - 10 seconds.

1 3 l

ZOSR-299/33 10c

-Amendment Nos.

~..

~

NOTE 2: Overpower AT (sheet 2 of 2)

K

" 0.002117/*F for T>T" and K6 = 0 for TIT" 6

T

- Average temperature, 'F T"

- Indicated T at RATED THERMAL POWER (calibration temperature for AT inttrumentation, 1 562.2*F) avg S

- Laplace transform operator, S'l f (aI)

= 0 for all AI 2

f 20SR-299/34 10d Amendment Nos.

... ~.

- - -. - - ~. - ~ -. - - -. -

~. - -... - -.

- - ~, - - - -

i indicated by difference.between top and bottom The overpower AT reactor trip prevents power power range nuclear detectors, the reactor trip density anywhere in a core from exceeding 118% of.

limit.is automatically reduced. (6) design power density, as described in Sections 7.2.3 and 14.1.2 of the FSAR and includes corrections for axial power distribution, change in density and heat capacity of water with temperature, and dynamic compensation for piping delays from a core to the loop temperature detectors, t

The overtemperature AT and overpower AT reactor trip functions include lag compensation on constants have been accounke0.

These lag time measured AT'and measured T for in the safety analysis.and provide allowance for'RTD response characteristics.

The low flow reactor trip protects core against DNB in the event of a loss of one or two reactor coolant pumps.

The undervoltage reactor trip protects a core against DNB in the event of a loss-of two or more reactor coolant pumps. (7)

The low frequency reactor coolant pump trip also protects against a decrease in flow by tripping a reactor before the low flow trip power is reached.

(3)

FSAR Section 14.1.2 (6)

FSAR Section 7.2.2 (7)

FSAR Section 14.1.6 l

ZOSR-299/35 22 Amendment Nos.

3 4

-..w:.

..w..--.

e.... - - -

=+%

m--.

..-s..

c 4,i m

+

.m,

-,a..

-. - ~.. - - -

,_.--_.m._

PERMISSIVES SfM 01NI P-6 10-10,,p,###

P-7 10% Rated Neutron Flux and Pressure Equivalent to 10% of Rated Turbine Load P-8 28% of Rated Power (4 loops) for Unit I at startup f rom refueling outage ZlR12 and Unit 2 at startup from refueling outage ZZR12. "

60% of Rated Power (4 loops) for Unit 2 until startup f rom refueling outage Z2R12.###

P-10 10% of Rated Neutron Flux ###

+ If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be in the Cold Shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Setpoints are i established tolerances for instrument channel and setpoint errors as specified in " Zion NSSS Setpoint Evaluation, Protection System Channels, Eagle 21 Version", Revision 1. April 1992 for Westinghouse source range and intermediate range neutron flux channels. For channels other than the Westinghouse source and intermediate range neutron flux channels, setpoints are f established tolerances for instrument channel and setpoint errors as specified in " Zion NSSS Setpoint Evaluation, Protection System Channels, Eagle 21 Version", Revision 2, Harch 1993. The instruments shall not be set to exceed a Limiting Safety System Setting, o+

For channel test, calibration or maintenance. the minimum number of OPERABLE channels may be reduced by one but to not less than one, and the minimum degree of redundancy may be reduced by one but to not less than zero, for a maximum of two hours. For Automatic Reactor Tri? Logic and Reactor Trip Breakers, the allowable outage time is a maximum of eight hours.

When block conditions exist, maintain normal operation.

' Maintain Hot Shutdown' means maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises during power operation.

Verify shutdown margin innediately and comply with Section 3.2.1. A B.

When blocked conditions exist, maintain normal operation.

1. During Modes 3, 4 or 5 and with the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal, the following applies: With the number of OPERABLE channels one less than the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.

1. 1. During Modes 1 or 2 with one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and maintain or proceed to Hot Shutdown within four hours if the unacceptable condition arises during power operation. The breaker shall not be bypassed while ont of the diverse trip features is inoperable except for the time required for performing maintenance and testing to restore the breaker to OPERABLE status.

f## Setpoints are established tolerances-for instrument channel and setpoint errors as specified in

• Channel Accuracies, Overall Channel Accuracies and Setpoint Tolerances for W NES Process I and C Reactor Protection and Control Systems" August 30, 1971 - CEW-652. The instruments shall not be set to exceed a limiting Safety System Setting.

TABLE 3.1-1 (Continued)

Reactor Protection System - Limiting Operation Conditions and Setpoints ZOSR-299/36 32 Amendment Mos.

1 ATTACHMENT E SUPPORTING TECHNICAL INFORMATION i

l l-1)

" ZION NSSS SETPOINT EVALUATION, PROTECTION SYSTEM CHANNELS, i

EAGLE 21 VERSION, REVISION 2, MARCH 1993 ", PROPRIETARY CLASS 2.

2)

" ZION NSSS SETPOINT EVALUATION, PROTECTION SYSTEM CHANNELS, EAGLE 21 VERSION, REVISION 2, MARCH 1993", NON-PROPRIETARY CLASS 3.

l.

3)

HESTINGHOUSE LETER, " APPLICATION FOR HITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE" (CAW-93-441) HITH RELATED AFFIDAVIT AND PROPRIETARY INFORMATION NOTICE.

l 4

i ZOSR-299/37 i

-.