ML17321A787

Revised Tech Specs,Changing Tables 2.2-1,3.2-1 & 3.3-3 Re Rdf Resistance Temp Detector

ML17321A787
Person / Time
Site:	Cook
Issue date:	08/13/1985
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17321A784	List: ML17321A783 ML17321A785 ML17321A786 ML17321A787
References
NUDOCS 8508150386
Download: ML17321A787 (9)

Text

TADLE 2.2-1 AEACTOll TAlP SYSTEkl IHSTAUklEIITATIOIITRIP SETPOIIITS FUNCT IONAL UIIIT TAlP SETPOINT VALUES

1. Hanual Reactor Trip Not Applicable Ilot Appl icable I

2. power Range, Neutron Flux Los Setpolnt - < 25k of AAIEO Low Setpolnt - < 26>> of RAT(D

~ TIIEIIHAL POMER TIIEAIIAL POIIER ~4 lllgh Sctpolnt - <'-109>>'of AATED lllgh Setpolnt - < 110>>of RATED TIIEAklAL POllER TIIEAklAL POMER

3. Power Range, Neutron Flux, < 5>> of RATED TIIEAIQL POMER with < 5.5 "of AATEO TIIEAHAL POXR with Illgh Positive Rate tlae constant > 2 seconds a tlae constant 2 seconds loop'LLOMADLE 4 >

I. Po~er Range, Neutron Flux, < 5>> of AATED TIIEAHAL POMEIl wltli < 5.5 (of RATED TIIEAIOL POMER with Illgh Ilegative Rate a tlie constant > 2 seconds a time constant > 2 seconds

5. lnteracdlate Range, Ileutron < 25>> of RATED TIIEAHAL POMER < 30>> if RATED TIIEAIIAL POMER Flux

6. Source Range, Neutron Flux < 105 counts per second < 1.3 x 105 counts per second

l. Ovcrtemyerature aT See Ilote 1 See Ilote 3

8. Overpower .aT Sec Note 2 See Ilote 4

9. Pre ssurl zcr Prcssure--Low > 1065 pslg > 1855 pslg

10. Prcssurl zer Pre ssure--Ill gh < 23U5 psl g < 2395 pslg

11. Prcssurlzer Mater Level--lllgh < 92>> of instrmaent span < 93>> of Instruwent span

12. Loss uf flow > 9O>> of dcslgik I low > 89.1% of desl<Jll f1oM pcr per loop'Design flow ls 91.6OO gpm per loop.

8g08gg0386 850806 8>0003$ g pgg ggGCH, 0 pgg P

TAOLE 2.2-1 (Co,... rue<<l)

CI REACTOR TRIP SYSIEI4 Ill TRUE tlTATIO>> TRIP SETPOI>>TS n HOTATIOll (Continued) n Cl Cl x3S Note 2: Overpower aT < aTo [K4-K~ T - K6 (T-T")-f2(hl)]

~>x3 chere: aTo Extrapolated aT at QESIGll TllERHAL POWER Average temperature, f Indicated Tavg at OESIGN TllERNL, POllER 577.1 f K4 ee 1.009 KS ee 0.0177/"f for increasing average temperature and 0 for decreasing I

average temperature K6 0.0011 for T > T"; K6 0 for T < T" x3S

.Ihe function generaten by the rate lag controller for J dynamic compensation

$3 ee Time constant utilized in the rate lag controller for Tag 10 secs.

S Lap) ace transform operator f2(ai) - f1 (aI) as <<lef ined in llote 1 above.

channe)'s trip point shall not exceed its computed trip point by more than 2.5 percent tlote 3: The maximum

'i'lie charm<< l's trip point snail not oxen' its eompnted trip point by more than an 3-4 yercent.

3- .pt.r<<:ent.

Hot<< 4: tttaxitttt<<ttt Q.

lABa. 3. 2- l OWG PAAAHDEAS L IIIIIS 4 Loops la Operation i Loops la Operation 3 Loops la Operatioa PARNK lER at RhlEO 'lllERHAL POWER at OESICiW ll!ERHAL P0WER at RAlE li tuOL 10MER-Reactor Coolant Systea la9 570.< oF 579. 7 F 570.5 F Pressurizer Pressure > 2220 psiai > 2220 psia' > 2220 isla'0.99l?

Reactor Coolant Systea > 1.3S6 x l0 lbs/hr l.366 x l0 lbs/Ar x I06 lbsjhr Total i'lo~ Nate B~it PPIEB~g per alnute or a I I IN'SIIIL Puln w I I~

IllENQLL PNER step increase ln eacess of l0 perceat Rhlf0 lllERHAL PQIER.

I 5 P L RllED IgsNIL touES

TABLE 3. 3-3 Conti nues ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION C7 HINIHUH C) TOTAL NO. CHANNELS CiiANNELS APPLICABLE 4D FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION 7C I

f. S team Floe in Two Steam L ines-iiigh Four Loops 2/steam line 1/steam 1 ine 1/steam 1 ine 14 Operating any 2 steam lines Three Loops 2/opera t i ng 1 /any 1/operating 15 Operating s team 1 inc operating steam line steam line COINCIDENT WITH EITHER 3ll **

T avg four

--Low-Low Loops 1 T /loop 2 Taz any 1 T any I

~

Operating loops 3 loops Three Loops Operating 1T/ avg in 15 operating any operating two operating t4 loop loop loops 0

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTFM INSTRUMENTATION HIHIMI<

TOTAL HO. CHAHHELS CHANNELS APPLICA6LE FUNCTIONAL UHIT OF CHANNELS TO TRIP OPERABLE MODES ACTION COIHCIDEHT MITH EITHER T Low-Low 1. 2, 3ll **

Four Loops 1 T /loop 2 T any 1 T any Operating loops 3 loops Three Loops 1 Tav /oper- ill Tav in 1T in any 15 Operating two operating ating loop any operating loop loops OR, COIHCIOEHT MITH Steam Line Pressure-3fl Low

. Four Loops 1 pressure/ 2 pressures 1 pressure 14

'perating loop any loops any 3 loops Three Loops 1 pressure/ 1 pressure 1 pressure in Operating operating loop in any oper- any 2 oper-

ating loop ating loops

5. -

TURBINE TRIP h FEEOWATER ISOLATION

a. Steam Generator 3/loop 2/loop in 2/loop in 1, 2, 3 Mater Level-- any oper- each oper-High-High ating loop -'ating loop

~

~

I ABLE 3.3-3 Continued TABLE NOTATIOfl

~Trip function may be bypassed $ n this BODE belo<<P-ll.

~

Trip functioA may be bypassed in this'tlODE below P-12.

'--The channel(s) associated with the protective functions det ived from the out of service Reactor Coolant'oop shall be placed in the tripped mode.

<<The provisions of Specification 3.0.4 are not applicable.

• • Rod drop testing in accordance with specification jndication Calibration, and hot zero power physics 4.1.3.3, testing Rod Position to the correction of RTD Calibration Curves for may proceed prior the beginning of cycle. cross-calibration results at ACTION S TATEllEllTS ACTION 13 - >lith the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STAllOGY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDO/l'I within the following 30 hours; however, one channel may be bypassed For up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for surveillance testing per Specification 4.3.2. 1. 1.

ACTIOll 14 - With the number of OPERABLE Channels one less tha'n the Total Number of Channels:

a. Below P-ll or P-12, place the inoperable channel in the tripped condition swithin hour; restore the inoperable 1

channel to OPERABLE s tatus within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding P-11 or P-12; otherwise be in at least HOT STAtlDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. Above P-11 and P-12, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may continue until performance of the next required CHANtlEL FUflCTICNAL TEST.

ACTIOtl 15 - With a channel associated with an operating loop. inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDO'.ill within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an. operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Speci f i ca ti on 4,3.2.1.1.

ACTIOll 16 - With the'umber of OPERABLE Channels one less than the Total Number, of Channels:

a. Below P-ll or P-12, place the inoperable channel fn the bypass condition; restor e the inoperable channel to OPERABLE status within 24 hours after exceeding P-11 or P-12; othe+;ise be in at least HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. C. COOV-UNIT 1 3/4 3-22 Amendment No.

Attachment 3 to AEP:NRC:0942D REQUEST FOR WITHHOLDING PROPRIETARY INFORMATION ASSOCIATED WITH RdF RTD SAFETY EVALUATION IN ATTACHMENT 1