Text

Proposed Tech Specs,Eliminating Requirement for Use of Rod Sequence Control Sys & Decreasing Power Level Setpoint Above Which Rod Worth Minimizer Sys Would No Longer Be Required
	ML20043B203
Person / Time
Site:	Fermi
Issue date:	05/18/1990
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20043B202	List: ML20043B203; NRC-90-0039, Application for Amend to License NPF-43,eliminating Requirement for Use of Rod Sequence Control Sys & Decreasing Power Level Setpoint Above Which Rod Worth Minimizer Sys Would No Longer Be Required;
References
	NUDOCS 9005250071
	Download: ML20043B203 (15)
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l LIMITING CONDITIONS FOR OPERATION-AND SURVEILLANCE REQUIREMENTS' D

~ SECTION PAGE- -

3/4.0- APPLICABILITY............................................. 3/4 0-l' 3/4.1' REACTIVITY CONTROL SYSTEMS

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' 3/4.1~.1 ' SHUTDOWN MARGIN.............. .......................... . 3/4 1-1 ?

m 3/4.1.2: : REACTIVITY AN0MALIES................................... 3/4 1-2 I

7 3/4.1.3 CONTROL' RODS 3/4 1-3

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Control Rod Operability................................

Control Rod Maximum Scram Insertion Times.............. 3/4 1-6 !

Control Rod Average Scram Insertion Times.............. 3/4 1 l Four Control' Rod Group Scram Insertion Times........... 3/4 1-8 1

Control = Rod Scram Accumulators.........................: 3/4 1-9.

~ Control Rod Dri ve Coupl i ng. . . . . . . . . . . . . . . . . . . . . ... . . . . . . 3/4 1-11 Control-Rod' Position Indication........................ S/4 1-13 ,

Control Rod Drive Housing Support;..................... 3/4 1-15

.3/4;1.4: : CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer.................................... 3/4 1-16~

Red tea.enee Centiel System.. . ..... .. .............. '3/4 1 17- ;

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. Rod Block Monitor............. . ........................ 3/4.1-18 ,

13/4.1.5= ' STANDBY LIQUID CONTR0L' SYSTEM.......................... 3/4'l-19 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE............. -3/4 2-1 ,

3/4'2-5 J3/4-2.2 APRM SETP0lNTS.........................................

.3/4.2.3= MINIMUM CRITICAL POWER RATI0........................... 3/4 2-6 3/4.2.4 LINEAR. HEAT GENERATION RATE............................ 3/4 2-10 U

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. .... LugLu LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS '

~SECTION PAGE REFUELING OPERATIONS (Continued) '

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . 3/4 9-9

~3/4.9.8 WATER LEVEL - REACTOR VESSEL. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 i 3/4.9.9 WATER ~ LEVEL - SPENT FUEL STORAGE P00L................ 3/4 9 3/4.9.10 ' CONTROL ROD-REMOVAL Single Control Rod Remova1........................... 3/4 9-12 :

Mul tipl e Control Rod Removs1. . . . . . . . . . . . . . . . . . . . . . . . . 3/4. 9-14 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water.Leve1..................................... 3/4 9-16 Low Water Leve1...................................... 3/4 9-17 3/4.10. SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY........................ 3/4 10-1 3/4.10.2 P2 Q'Xt:05 00!!TCOL ;Y;TC".. . . .P.f.9.@ T5.4. . . . . . . . . . 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS....................... 3/4 10-3 l

3/4.10. 4 ' RECI RCULATION L00PS. . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . . 3/4 10-4 f-l; -

3/4.10.5 DELETED ............................................. 3/4 10-5 3/4.10. 6 LTRAINING STARTUPS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-6 i

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' FERMI - UNIT 2 x Amendment No. 46

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3/4.10 $PECIAL" TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAllMENT-!NTEGRITY................... 8 3/4 10-1 i

- 3/4.10.2 E6 ;ET6ENCE TATEL SY; TEM. . .#.?.'.4.r,9 R . . . . . . . 8 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DENDNSTRATI0NS.................. B 3/4 10-1 3/4.10.4 AECIRCULATION L00PS............................. B 3/4 10-l' 3/4.10.5 -DELETED ........................................ 83/410-1 3/4.10.6 TRAINING STARTUPS............................... B 3/4 10-1 1

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1-l FERMI - UNIT 2 xvi Amendment No.46 l

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2.2* LIMlflNG SAFETY SYSTEM SETTINGS I J

. ' BASES

2. 2.1- REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The Reactor Protection System instrumentation setpoints specified in:

Table 2.2.1-1 are the values at which the reactor trips are set for each para-meter. The Trip Setpoints have been selected to ensure that the reactor core i

< and reactor coolant system are prevented from exceeding their Safety Limits i I

during notsal operation and design basis anticipated operational occurrences-and to assist in mitigating the consequences.of accidents. Operation with'a

- trip set less conservative than its Trip Setpoint but within its specified , ,

Allowable Value is acceptable on the basis that the difference between each l Trip-Setpoint and the Allowable Value is equal to or less than the drift 1 allowance assumed for each trip in the safety analyses, t

1. Intermediate Range Monitor Neutron Flux - High The IRM system consists of 8 chambers, 4 in each of the reactor trip ,

l systems. 'The IRM is a 5 decade 10 range instrument. 'The. trip setpoint of 120 divisions of scale is active in each of the 10 ranges. Thus as the IRM is

- ranged up to accommodate the increase in power level, the trip setpoint is also ranged up. The IRM instruments provide for overlap with both the APRM and SRM systems.

The most significant source of reactivity changes during the power 'l-r increase is due-to control rod withdrawal. In order to ensure that the IRH

-provides the required protection, a range of rod withdrawal accidents have .

l- been analyzed. The results of these analyses are in Section 15B.4.1.2 of the L FSAR. The most severe case involves an initial condition in which THERMAL

}~ POWER is at approximately 1% of RATED THERMAL POWER. Additional conserva-tism was taken in this analysis by assuming-the IRM channel closest to the control rod being withdrawn is bypassed. The results of this analysis.show -

L that the reactor is shutdown and peak power is limited to 21% of RATED L THERMAL POWER with the peak fuel enthalpy well below the fuel failure thres-L hold of 170 cal /gm. Based on this analysis, the IRM provides protection i' against local control rod errors and continuous withdrawal of control rods in sequence and provides backup protection for the APRM.

2. Averaae Power Ranae Monitor For operation at low pressure and low flow during STARTUP, the APRM scram setting of 15% of RATED THERMAL POWER provides adequate thermal margin between the setpoint-and the. Safety Limits. The margin accommodates the anticipated

l. maneuvers associated with power plant startup. Effects of increasing pressure L at zero or low ~ void content are minor and cold water from sources available L during startup is not mach colder than that already in the system. Tempera-ture coefficients are small and control rod patterns are constrained by the 505 d RWM. Of all the possible sources of reactivity input, uniform con- I trol rod withdrawal is the most probable cause of significant power increase.

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- REACTIVITY CONTROL SYSTEMS >

LIMITING CONDITION FOR OPERATION (Continued)

-l ACTION: .(Continued) 1

.If the inoperable control rod (s) is inserted, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months disarm

2. '

the associated directional control-valves ** either:

a)- Electrically, or b) ' Hydraulically by closing the drive water 'and exhaust water-

. isolation-valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12' hours.: ,

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3. The. provisions of Specification 3.0.4 are-not applicable. l 1

c.- With more than 8 control rods inoperable, be in at least HOT SHUTDOWN . .;

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

d. .Withonesc'rakdischargevolume.ventvalveand/oronescramdischarge volume drain valve inoperable and open,-. restore the inoperable valve (s);

to OPERABLE status' within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next-12 hours,

e. With any-scram discharge; volume vent valve (s) and/or any scram-dis- ,

-charge volume drain valve (s) otherwise inoperable, restore the~ . - -

inoperable-valve (s)'to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or-be in at. b y least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . -

SURVEILLANCE REQUIREMENTS ;

4.1.3.1.1 The scramIdischarge volume drain and vent valves shall be R demonstrated OPERABLE by: .

a. At.least once per 31 days verifying each: valve to be open,* and

'b. At least once per 92 days cycling each valve through at least one ,

complete cycle of full travel. l

4.1.3.1.2 When above the preset power level of the RWM ;.M "000, all ;

withdrawn control rods not required to have their directional control valves '

disarmed electrically'or hydraulically shall be demonstrated OPERABLE by.

L p. _ moving each control rod at least one notch:

Oi a. At least once per 7 days, and j b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a .

y M' . result of excessive friction or mechanical ~ interference.

b' A *These valves may be closed intermittently for testing under administrative p controls.

- May be rearmed intermittently, under administrative control, to permit J. I l

testing associated with restoring the control rod to OPERABLE status.

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~ REACTIVITY CONTROL SYSTEMS'

. CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION <

3.1.3.6 J Alltcontrol rods shall be coupled to their drive mechanisms. ,

. APPLICABILITY: OPERATIONAL' CONDITIONS 1, 2, and 5*. -

ACTION: <

. a. In OPERATIONAL CONDITION 1 and 2 with one contro1~ rod not coupled'.4o its associated drive mechanism, within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

1. If permitted by the RWM.:nd RSCS, insert:the control rod drive .

mechanism to accomplish recoupling and verify recoupling by with-I drawing the control rod, and-

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a) ObservingLany indicated response.of the nuclear '

instrumentation, and' '

b) Demonstrating that the control rod will not go to the- :

overtravel position.

2. If recoupling is not accomplished on the first attempt or, if [

not permitted by the' RWM er RSCS, then until permitted by the y RWM :nd RSCS, declare the control rod inoperable, insert the :

control rod'and disarm the associated directional control >

valves ** either:

a) ' Electrically, or b) Hydraulically by closing the drive' water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to-its associated drive mechanism, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1. Insert the control rod.to accomplish' recoupling and verify J recoupling by withdrawing the control' rod and demonstrating that -

the control rod will not go to the overtravel position. or

2. If recoupling is not: accomplished, insert the control rod and '

disarm the associated directional control valves ** either:

a)- Electrically, or b) Hydraulically by closing the. drive water and exhaust water isolation valves.

c. The provisions of Specification 3.0.4.are not applicable.

At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed intermittently, under adm ii n strative control, to permit testing-associated with restoring the control rod to OPERABLE status.

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! LIMITING E+I1T10M FOR OPERATION 1 3.1.3.7; The control red position indication system shall be OPERABLE.."p j

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OPERAT!WAL CONDITIONS 1, 2 and $*.

A, : APPLICABILITY:

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T a.' InOPERATIONALCONDITION1'er&g #

i A ttith C one or scre control rod position indicators inoperable; W Or tE "?;W t " :: "! " ::t" indi::t=, within one hour:

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1, b . Determine the position of the' control rod by:

'q)M Moving the. control rod, by single notch sovement, to a f.

l' position with an OPERABLE position indicator, .l j))( . Returning the control rod, by single notch movement, to

-itsl original. position-and f

J c) M -Verifying no control rod drift alate at least once per-12 hours, or-

.t. g Move the control rod to a position with an OPERABLE position

-indicator, or_

,t J, M When THERMAL POWER is:

declare the Within the preset power. level of the +

5) 39 control rod inoperable, or - ItWM ]

h 4 Greater than the preset power level of the R$66, declare '

-f b)29 the contro1' red inoperable,; insert the contro ,

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) jus Electrically, or p)(t9 etydraulically by closing the drive water and exhau !

water isolation valves. i Otherwise, be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Fe S' Not applicable to control rods removed l

E "At least each wtthdrawn control rod.

per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed intermittently, under ttsadministrative control, tf f

-associated with restoring the control rod to OPERABLE s a u , I t

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LIMITING CONDITION FOR OPERATION (Continued)

AgT[gl[:c,_.(Continued)

. t"th ;

= ;.ge n:J,r.1 % "7w11-h" C% ";'.11 position indicators inoperable, either:

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When THERMAL POWER is within the proset power 1 of the-CS:

1) ithin 1 hour:

(a termine the position of control red (s) per ;

ON a.1.a), above, '

(b)~ Move control to a position with an 10PER4BLE iti indicator,or [

l , ,. -(c)- Declare rol rod inoperable.

2) Verify the ition e ssing of control rods-with i able "FuM-in a or Full-out" position-l indic rs by a second licens operator or other L to ically qualified member of unit technical l- aff.

b) n THERMAL POWER is greater than the preset r level

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of.the RSCS, determine the position of the contr rod (s) '1 y per ACTION a.1.a), above.

L Otherwise, be in at least NOT SHUTDOWN within 12 haun.

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b.. In OPERATIONAL CONDITION 5* with a withdrawn control red position indicator inoperable, move the control rod to a position with an OPERABLE position indicator or insert the control rod.

c, The provisions of Specification 3.0.4 are not applicable.

E FILLANCE REQUIREMENTS' f

'4.1.3.7 The control rod position indication system shall be determined OPERABLE by verifying:

a.. -at le' ast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the position of each control rod is l

indicated.-

b. That the indicated control red position changes during the movement l of the control rod drive when performing Surveillance Requirement-4.1.3.1.2, and 1 1

- c. That the control red position indicator corresponds to the control l

D rod position indicated by the " Full out" position indicator when performing Surveillance Requirement 4.1.3.6.b..

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=4t i.ast .ach withdrawn controi tod. not ap,iscable to controi rods removed p.e sp.cif$ cation 3.e.10.1 or 3.s.10.r.

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FERMI - UNIT 2 3/4 1-14 '

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REACTIVITY CONTROL' SYSTEMS 3/4.1.4' CONTROL ROD PROGRAM 00NTROLS i ROD WORTH MINIMIZER LIMITING CONDITION FOR OPERATION _

3.1.4.1 The rod worth minimiter (RWM) shall be OPERABLE. ,

when THERMAL POWER is less than APPLICABILITY:-

or equal to rot of RATED OPERATIONAL THERMAL POWER, CONDITIONS the ein 1 and 2*laum allowable preset power le

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ACTION:

gepface w ith Inse & '

a. he RWM inoperable, verify control rod movement and c-lh l with t ibed control rod pattern by a se ed operator un t technical staff

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. or other techn c lified who is present at the rol consols. Otherwise, control rod movene on y by actuat inval scram or placing or mode switch in the Shutdown pos'TTDm-

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS , 4.1.4.1 The RWM shall be demonstrated OPERABLE: ,

s. In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of l control rods for the purpose of making the reactor critical, and in L OPERATIONAL CONDITION 1 within I hour after RWM automatic initia-tion when reducing THERMAL POWER, by verifying proper indication of the selection error of at least one out-of-sequence control rod.

b. In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods'for the purpose of making the reactor critical, by veri-fying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod (af ter selection of first control rod).

! c. In OPERATIONAL CONDITIDW 1 within I hour after RWM automatic initiation when reducing THERMAL POWER, by demonstrating the withdraw block and insert block functions.

d. By demonstrating that the Banked Position Withdrawal sequence

!~ input to the RWM computer is correctly loaded following any loading of the program into the computer.

Entry into OPERATIONA! +0NDITION 2 and withdrawal of selected control rods is permitted for the purpue of determining the OPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality. .

3/4 1-16 Amendment No. 42

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.a. . With the RWM inoperable, verify control rod. movement and

j. _-compliance with the prescribed control rod pattern,by a second licensed operator or other technically qualified member of the

. unit technical staff who is present at the ~ reactor control .

console. - The use of this provision during reactor startup prior

.'to the first- 12 control rods being fully withdrawn is restricted to one startup per calendar year. 0therwise,- control rod.

' movement may be only by actuating the manual screm or placing the reactor mode switch in the shutdown position.

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.[,4y' . {s L7ELSTE-Q RNCTIVITYCONTROLSYSTEMS ROD \EQUENCECONTROLSYSTEM LIMIT CONDITION FOR OPERATION ,

s 3.1.4.2 T rod sequence control system (RSCS) shall be OPERABLE.

APPLICABILIT - OPERATIONAL CONDITIONS 1 and 2*#, when THERMAL POWER is ess than or equal to 2 RATED THERMAL POWER, the minimum. allowable preset pow level. l ACTION:

a. With the SCS inoperable, control rod movement shall'n -be permitted, '

except by scram.

b. With an inop rable control rod (s), OPERABLE contro rod movement may l

. continue by b assing the inoperable control rod ) in the RSCS )

provided that: s

1. The position nd bypassing of inoperabl control rods is verified by a second 1 ensed operator or other technically qualified member of the u it technical staff, d 1

There are not more than 3 inoper e control rods in any one of 2.

the first four RSCS roups and t more than 1 inoperable control rod in any of the sub equent tch groups. j SURVEILLANCE REQUIREMENTS X /

4.1.4.2 The RSCS shall be demonstrate RABLE by:

a. . Selecting and attempting t move. inhibited control rod:

1. After withdrawal of he first sequence control rod for each

reactor startup, d

2. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a er rod inhibit mo e automatic initiation when reducing ERMAL POWER.

b. Attempting to mo a control rod more than ne notch prior to other ,

control rod mov ent after the group notch m de is automatically.

initiated dur g:

1. Contro rod withdrawal for each reactor st tup, and

2. Pow reduction.

c. Perfor nce of the comparator check of the group no h circuits withi 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to control rod:

1. Withdrawal for each reactor startup, and J. Insertion to reduce. THERMAL POWER to less than 20% o RATED THERMAL POWER.

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See ecial Test Exception 3.10.2

Ent into OPERATIONAL CONDITION 2 and withdrawal of selected control r s is p mitted for the purpose of determining the OPERABILITY of the RSCS prio to l ' ithdrawal of control rods for the purpose of bringing the reactor to criticality.

FERMI - UNIT 2 3/4 1-17

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SPECIAL' TEST EXCEPTIONS DEt-G n=D 1

-3k.10.2 ~ R0D SEQUENCE CONTROL SYSTEM l

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LIMIT CONDITION FOR OPERATION 3.10.2 The equence constraints imposed on control rod groups by the rod sequence cont ol system (RSCS) per Specification 3.1.4.2 may be suspended by means of bypas switches for the following tests provided that the rod worth !

minimizer is OP ABLE per Specifications 3.1.4.'1: .i

-a, Shutdown argin demonstrations, Specification 4.1.1.

b. Control rod cram, Specification 4.1.3.2.

c. Control rod-fr tion measurements.

i d- Startup Test Prog m with the THERMAL POWER less than 20% of RATED THERMAL POWER.

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APPLICABILITY: OPERATIONAL CONDI ONS 1 and 2.

ACTION:

With the requirements of the above spec ication not satisfied, verify that. ,-l the RSCS is OPERABLE'per Specification.3. .4.2.

-j SURVEILLANCE REQUIREMENTS , 4.10.2 When'the sequence constraints imposed on con ol rod groups,by the'RSCS are bypassed, verify: .

a. Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to bypassing any sequence onstraint.and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while any sequence' constraint bypassed:

1. That'the rod worth minimizer is OPERABLE per ecification , x 3.1.4.1.

2. That movement of the control rods from 50% ROD DEN TY to the RSCS preset pe er level is blocked or limited to the single J l

notch mode.

b. Conformance with this specification-and test procedures by a cond licensed operator or other technically qualified member of the nit technical staff.

I' FERMI - UNIT 2 3/4 10-2 L

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3. ., ;

,.e I REACTIVITY CONTROL SYSTEMS (

ii BASES ;

l CONTROL RODS (Continued)

The surveillance requirement to measure and record the time that the accumu- l lators maintain pressure above the alarm setpoint is intended to provide infor-No action is ,l' mation rather than establish OPERABILITY of the accumulators.

required if the accumulator pressure does not remain above the alare setpcint l for at least 10 minutes, g Control rod coupling integrity is uire ensure compliance with the analysis of the rod drop accident in the .

The overtravel position feature 1l provides the only positive means of detemining that a rod is properly coupled

.and therefore this check must be performed prior to achieving criticality after completing CORE ALTERATIONS that could have affected the control rod coupling integrity. The subsequent check is performed as a backup to the initial demonstration. 1 In order to ensure that the control rod patterns can be followed and I therefore that other parameters are within their limits, the control rod posi-tion indication system must be OPERABLE.

The control rod housing support restricts the outward movement of a control rod to less than 3 inches in the event of a housing failure. The amount of rod reactivity which could be added by this small amount of rod withdrawal is less than a normal withdrawal increment and will not contribute to any damage to the primary coolant system. The support is not required when there is no pressure to act as a driving force to rapidly eject a drive housing.

The required surveillance intervals are adequate to determine that the rods are OPERABLE and not so frequent ~as to cause excessive wear on the system components.

3/4.1.4 CONTROL ROD PROGRAM CONTROLS Control rod withdrawal and insertion sequences are established to assure that the maximum insequence individual control rod or control rod segments which

'are withdrawn at any time during the fuel cycle could not be worth enough to result in a peak fuel enthalpy greater than 280 cal /gm in the event of a control rod drop accident. The specified sequences are characterized by homogeneous, scattered patterns of control rod withdrawal. When THERMAL POWER is greater thaf(M percent'of RATED THERMAL POWER, there is no possible rod worth which, if dropped at the design rate of the velocity limiter, could result in a peak enthalpy of 280 cal /gm. Thus requiring the R666-ene RWM to be OPERABLE when THERMAL POWER is less than or equal t6Xtc percent of RATED THERMAL POWER provides adequate control.

The R666-end RWM providessutomatic supervision to assure that out-of- l sequence rods will not be withdrawn or inserted.

The analysis of the rod drop accident is presented in Section 15.4.9 of the UFSAR and the techniques of the analysis are presented in a topical report, Reference 1.

The RBM is designed to automatically prevent fuel damage in the event of erroneous rod withdrawal from locations of high power density during high power operation. Two channels are provided. Tripping one of the channels will block erroneous rod withdrawal soon enough to prevent fuel damage. This system backs up the written sequence used by the operator for withdrawal of control rods.

8 3/4 1-3 Amendment No. 42

-FERMI - UNIT 2 1

Q s 4 3, , -

,.c L3 /4.10i SPECIAL' TEST EXCEPTIONS .

__ 4 1

BASES ,

3/4.10.1 PRIMARY CONTAINMENT INTEGRITY The requirement for PRIMARY CONTAINMENT INTEGRITY is no the period when open vessel tests- are being performed during the310w p PHYSICS TESTS. i

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I l

1 to perform the tests' required in.the technical specifications.n. he 1 he sequence-restraints on controlcations on heat

!itisnecessar ute th not exceeded during the l

-additional- surveillance requ

, d worths do

-generation rates and shutdown gr.ge' ng perfomed and- that period when the values assumed in the safety analysis. !

1 3/4.10.3 ' SHUTDOWN MARGIN DEMONSTRATIONS .

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requires additional restrictions restrictions are in order in'thisto ensu i

These additional specified q monitored and controlled.

LCO:-

3/4.10;4 - RECIRCULATION LOOPS 3 This special. test' exception permits reactor criticality HYSICS under no flow.

TESTS while~

i conditions and is required to perform certain startup .and P K 'I

" at low THERMAL POWER levels t 3/4.10.6 TRAINING STARTUPS a

This special- test exception permits OWER andtraining startups to be perf temperature:while- ,

.the reactor vesse1Ldepressurizedi at low h rge THERMAL Pcont to.the ,

. cooling mode in order to minimize contaminated. water d sc a radioactive waste disposal system. l l

L 1 L .

l i

L. j L Amendment No.46 B 3/4 10-1 FERMI - UNIT 2 r

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ML20043B203

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