Text

Proposed Its,Rev 15
	ML20211Q735
Person / Time
Site:	Fermi
Issue date:	09/03/1999
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20211Q732	List: ML20211Q735; NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev;
References
	NUDOCS 9909150137
	Download: ML20211Q735 (800)
	v • d • e

INSERT THIS PAGE IN FRONT OF VOLUME 4 i

30-

~

Volume 4: SECTIONS 3.3.1.1 ~- 3.3.4.1 - ; -I Remove Replace B 3.3.1.1 ITS pg B 3.3.1.1-14 Rev 2 B 3.3.1.1 ITS pg B 3.3.1.1-14 Rev 15 B 3.3.1.1 ITS pg B 3.3.1.1-15 Rev 0 B 3.3.1.1 ITS pg B 3.3.1.1-15 Rev 15 B 3.3.1.1 ITS pg B 3.3.1.1 16 Rev 0 B 3.3.1.1 ITS pg B 3.3.1.1-16 Rev 15 B 3.3.1.1 NUREG M/U pg B 3.3-15 B 3.3.1.1 NUREG hW pg B 3.3-15 Rev 15 I

l I

l Rev 15 09/03/99 P

[

i

.-__._.,1 - . - -

RPS Instrumentation B 3.3.1.1 I

BASES APPLICABLE SAFETY ANALYSES. LCO. and APPLICABILITY (continued)

5. Main Steam Isolation Valve-Closure HSIV closure results in loss of the main turbine and the condenser as a heat sink for the nuclear steam supply system and indicates a need to shut down the reactor to reduce heat generation. Therefore, a reactor scram is initiated on a Main Steam Isolation Valve-Closure signal before the MSIVs are completely closed in anticipation of the complete loss l m of the normal heat sink and subsequent overpressurization 4 transient. However, for the overpressurization protection analysis pf Reference 4. the Averagt. Power Range Monitor Neutron Flux-Upscale Function, alcag with the SRVs. limits the peak RPV pressure to less tnan the ASME Code limits.

y That is, the direct scram on position switches for MSIV closure events is not assumed in the overpressurization analysis.

The reactor scram reduces the amount of energy required to be absorbed and, along with the actions of the ECCS. ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46.

MSIV closure signals are initiated from aosition switches located on each of the eight MSIVs. Eac1 MSIV has one J position switch that provides the originating sensor for two se)arate channels: one inputs to RPS trip system A while the otler inputs to RPS trip system B. Thus, each RPS trip system receives an input from eight Main Steam Isolation Valve-Closure channels, each channel consisting of one position swi ch, u which is shared with one other channel.

'f l The logic for the Main Steam Isolation Valve-Closure l Function is arranged such that either the inboard or outboard valve on three or more of the main steam lines must close in order for a scram to occur.

The Main Steam Isolation Valve-Closure Allowable Value is specified to ensure that a scram occurs prior to a significant reduction in steam flow, thereby reducing the severity of the subsequent pressure transient.

Sixteen channels of the Main Steam Isolation Valve-Closure Function, with eight channels in each trip system are required to be OPERABLE to ensure that no single instrument failure will preclude the scram from this Function on a valid signal. This function is only required in MODE 1 since, with the MSIVs open and the heat generation rate UNIT 2 B 3.3.1.1 - 14 Revision 15 09/03/99 l FERMI

- " , .- ,,,,__N--

o RPS lnstrumentation B 3.3.1.1 BASES APPLICABLE SAFETY t.NALYSES. LCO, and APPLICABILITY (continued) high, a pressurization transient can occur if the MSIVs l close. In MODE 2. the MSIV closure trip is automatically bypassed, and the heat generation rate is low enough so that the other diverse RPS functions provide sufficient protection.

6. Main Steam Line-Hiah Radiation Main Steam Line-High Radiation Function ensures prompt reactor shutdown upon detection of high radiation in the I vicinity of the main steam lines. High radiation in the !

vicinity of the main steam lines could indicate a gross fuel failure in the core. The scram is initiated to limit the '

fission product release from the fuel. This Function is not specifically credited in any accident analysis but is being retained for overall redundancy and diversity of the RPS as required by the NRC approved licensing basis.

Main Steam Line-High Radiation signals are initiated from four radiation monitors. Each monitor senses high gamma ,

radiation in the vicinity of the main steam line. The Main j Steam Line-High Radiation Allowable Value is selected high l enough above background radiation levels to avoid spurious stran, yet low enough to promptly detect a gross release of fission products from the fuel.

Four channels of Main Steam Line-High Radiation Function with two channels in each trip system, arranged in a one-out of-two logic, are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this function on a valid signal. This Function is required in MODES 1 and 2 where considerable energy exists such that steam is being produced at a rate which could release considerable fission products from the fuel.

The Allowable Value is based on the NRC guidelines of 3.6 times the full )ower background radiation level with nominal full power lydrogen injection rate. This Allowable Value remains fixed at this nominal full-power basis even when operating at reduced power and/or reduced hydrogen injection rates.

7. Drywell Pressure-High High pressure in the drywell could indicate a break in the RCPB. A reactor Scram is initiated to minimize the l FERMI UNIT 2 B 3.3.1.1 - 15 Revision 15. 09/03/99

RPS Instrumentation B 3.3.1.1 BASES APPLICABLE SAFETY ANALYSES. ). and APPLICABILITY (continued) possibility of fuel damage and to reduce the amount of energy being added to the coolant and the drywell. The Drywell Pressure-High Function is assumed to scram the olant coincident with the Reactor Vessel Water Level-Low. Level 3 function in the analysis of the LOCA inside primary containment. The reactor scram reduces the amount of energy to be absorbed and helps the ECCS ensure that the fuel peak I cladding temperature remains below the limits of 10 CFR l 50.46.

High drywell pressure signals are initiated from four pressure transmitters that sense drywell pressure. The Allowable Value was selected to be as low as possible and indicative of a LOCA inside primary containment.

Four channels of Drywell Pressure-High Function. with two i channels in each trip system arranged in a one out-of-two logic, are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this Function on a valid signal. The Function is required in MODES 1 and 2 where considerable energy exists in the RCS. resulting in the limiting transients and accidents.

Sa. 8b. Scram Discharae Volume Water Level-Hiah l The SDV receives the water displaced by the motion of the CRD pistons during a reactor scram. Should this volume fill to a point where there is insufficient volume to accept the j displaced water, control rod insertion would be hindered.

, Therefore, a reactor scram is initiated while the remaining free volume is still sufficient to accommodate the water from a full core scram. The two types of Scram Discharge Volume Water Level-High Functions are an input to the RPS logic. No credit is taken for a scram initiated from these Functions for any of the design basis accidents or transients analyzed in the UFSAR. However. they are retained to ensure the RPS remains OPERABLE.

SDV water level is measured by two diverse methods. The l level is measured by four float type level switches and four l level transmitters for a total of eight level signals. The I

outputs of these devices are arranged so that there is a signal from a level switch and a level transmitter to each RPS logic channel. The level mea'surement instrumentation satisfies the recommendations of Reference 8.

] l FERMI - UNIT 2 B 3.3.1.1 - 16 Revision 15. 09/03/99

RPS Instrumentation B 3.3.1.1 BASES APPLICABLE 5. Main steam Isolation valve-Closure (continued)

SAFETY ANALYSES, LCO, and The reactor scram reduces the amount of energy required to p,L __ APPLICA8ILITY be absorbed and, along with the actions of the ECCS, ensures that the fuel peak cladding temperature remains below the n a,PS*S M {5p O) limits of 10 CFR 50.46.

gigina41 p 5, aask . MSIV closure signal are initiated from position switches .

C k

e *\ ; located on each of he eight MSIVs. Each MSIV has cwe

_ f.k position switt. one inputs to RPS trip system A whi e e other inputs to RPS trip system B. Thus, each RPS trip system receives an inout from eight Main Steam Isolation g g> Valve-closure channels, eachtconsisting of one position '

switch) The logic for the Main Steam Isolation W4D5

'j valve-Closure Function is arranged such that either the l

6 a#.uj oM inboard or outboard valve on three or more of the main steam c lines must close in order for a scram to occur.

l g,t The Main Steam Isolation Valve-Closure Allowable Value is specified to ensure that a scram occurs prior to a )

significant reduction in steam flow, thereby reducing the ]

severity of the subsequent pressure transient.

l Sixteen channels of the Main Steam Isolation Valve-Closure l Function, with eight channels in each trip system, are required to be OPERABLE to ensure that no single instrument l

failure will preclude the scram from this Function on a valid signal. This Function is only required in MODE 1 since, with the MSIVs open and the heat generation rate high, a pressurization transient can occur if the MSIVs close. In MODE 2, heat generation rate is low enough so i that the other divers RPSfunctionsprovide_ sufficient]soradent/7 j protection.

[ye -

MStv c Lature try ~s as

- Q y f a ts t al a.tt p d l

h g) 3EE.

gRf .. .,....,,mo,-

03.3- '

u4,.h 7 .....

4. n. g ;

s,

.d d '"d'.n'" ; $ Peak-14

~

2% in- . m H"n W_^ 'ini"iz'-th'~

u w . :i z z = r :-'h r -W- -- 'L C ~1MIIi,.1Z'e'+" HFCI.3 '.'d

,+ -,,-...:.T- ., i "i . %: : _ :, ul-l.f 7"'.' '"", ' * ' ", !' N",' JTin I ' rI Q

'" 7'2'E Z~ ~.' ' , 'T.' . I" ; ' I'; ' ';i i' i ' . I-. Z'; "'" ';_

""nr,'<~2il ,Ex ;:D,': :17 :; a "nL ' '1, :3' r

-- e ,

'"",m'"". ' '.n..

uiw r

" _ .;.fl. _'J.

'..:. ' .' !'.; i n -r---

'"<_ _I L--""*

' : _ 3'i :< ' ";

{.

NSCAf (33,3. I l- (continued)

BWR/4 STS B 3.3-15 Rc.tI,04/07/95 I

Rev /r 9' 'w"_-

i l

}

INSERT THIS PAGE IN FRONT OF VOLUME 5

. _ . . 7;l re:;; % Volumeb; SECTIONS 3.3.5.1 - 3.3.8.2 4 5 ;

Remove Replace B 3.3.5.2 ITS pg B 3.3.5.2 3 Rev 0 B 3.3.5.2 ITS pg B 3.3.5.2-3 Rev 15 B 3.3.5.2 ITS pg B 3.3.5.2-4 Rev 0 B 3.3.5.2 ITS pg B 3.3.5.2-4 Rev 15 I B 3.3.5.2 ITS pg B 3.3.5.2-5 Rev 12 B 3.3.5.2 ITS pg B 3.3.5.2-5 Rev 15 B 3.3.5.2 NUREG M/U pg B 3.3-144 Rev 12 B 3.3.5.2 NUREG M/U pg B 3.3-144 Rev 15 -

l l

I I l

i l

l l

t I

Rev 15 09/03/99

-h, % -.uN

I l

RClC System Instrue.entation B 3.3.5.2 BASES APPLICABLE SAFETY ANALYSES. LCO. and APPLICABILITY (continued)

The individual Functions are required to be OPERABLE in MODE 1. and in MODES 2 and 3 with reactor steam dome pressure > 150 psig since this is when RCIC is required to be OPERABLE. (Refer to LC0 3.5.3'for Applicability Bases.

for the RCIC System.)

The specific Applicable Safety Analyses. LCO. and Applicability discussions are listed below on a function by

. Function basis.

1. Reactor Vessel Water Level-Low Low. Level 2 Low reactor pressure vessel (RPV) water level indicates that normal feedwater flow is insufficient to maintain reactor vessel water level and that the capability to cool the fuel may be threatened. Should RPV water level decrease too far, fuel damage could result. Therefore, the RCIC System is initiated at Level 2 to assist in maintaining water level above the top of the active fuel.

Reactor Vessel Water Level-Low Low. Level 2 signals are initiated from four level transmitters that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

The Reactor Vessel Water Level-Low Low. Level 2 Allowable Value is set high enough such that for complete loss of .

feedwater flow. the RCIC System ficw with high pressure coolant injection assumed to fail will be sufficient to avoid initiation of low pressure ECCS at Level 1.

Four channels of Reactor Vessel Water Level-Low Low.

Level 2 Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC initiation.

Refer to LCO 3.5.3 for RCIC Applicability Bases.

2. Reactor Vessel Water Level-Hioh. Level 8 High RPV water level indicates that sufficient cooling water inventory exists in the reactor vessel such that there is no danger to the fuel. Therefore, the Level 8 signal is used to close the RCIC steam supply. steam supply bypass, and cooling water supply valves to prevent overflow into the i .

g l FERMI UNIT 2 B 3.3.5.2 - 3 Revision 15. 09/03/99

i RCIC System Instrumentation B 3.3.5.2 l

BASES APPLICABLE SAFETY ANALYSES. LCO, and APPLICABILITY (continued) main steam lines (MSLs). (The injection valve also closes due to the closure of the steam supply valve.)

Reactor Vessel Water Level-High. Level 8. signals for RCIC are initiated from two slevel transmitters from the wide range water level measurement instrumentation, which sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

The Reactor Vessel Water Level-High. Level 8 Allowable Value is high enough to preclude isolating the injection valve of the RCIC during normal operation, yet low enough to trip the RCIC System prior to water overflowing into the MSLs.

Two channels of Reactor Vessel Water Level-High. Level 8 Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC initiation. Refer to LC0 3.5.3 for RCIC Applicability Bases.

3. Condensate Storaae Tank Level-Low Low level in the CST indicates the unavailability of an adequate supply of makeup water from this normal source.

Normally, the suction valve between the RCIC pump and the CST is open and, upon receiving a RCIC initiation signal.

water for RCIC injection would be taken from the CST.

However, if the water level in the CST falls below a l preselected level, first the suppression pool suction valves automatically open, and then the CST suction valve (consistency) automatically closes. This ensures that an adequate supply of makeup water is available to the RCIC pump. To prevent losing suction to the pump. the suction valves are interlocked so that the suppression pool suction valves must be open before the CST suction valve automatically closes.

Two level transmitters and trip units in the HPCI system are used to detect low water level in the CST. The Condensate Storage Tank Level-Low Function Allowable Value is set high enough to ensure adequate pump suction head while water is being taken from the CST.

h l FERMI UNIT 2 B 3.3.5.2 -4 Revision 15. 09/03/99

I l

1 RCIC System Instrumentation B 3.3.5.2 BASES APPLICABLE SAFETY ANALYSES. LCO, and APPLICABILITY (continued)

Two channels of Condensate Storage Tank Level-Low Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC swap to suppression pool source.

Refer to LC0 3.5.3 for RCIC Applicability Bases. )

4. Manual Initiation l

The Manual Initiation channel provides manual initiation I capability to individual valves. There is one manual initiation channel for the RCIC System. '

The Manual Initiation Function is not assumed in any accident or transient analyses in the UFSAR. However, the I

d. Function is retained for overall redundancy and diversity of Q the RCIC function as required by the NRC in the plant licensing basis.

There is no Allowable Value fo' this Function since the channel is mechanically actuated based solely on the position of the valve control. One channel of Manual Initiation is required to be OPERABLE when RCIC is required to be OPERABLE.

~

ACTIONS A Note has been provided to modify the ACTIONS related to RCIC System instrumentation channels. Section 1.3.

Completion Times, specifies that once a Condition has been ,

entered, subsequent divisions, subsystems components, or j variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for -

inoperable RCIC System instrumentation channels provide a)propriate compensatory measures for separate inoperable c1annels. As such a Note has been provided that allows separate Condition entry for each inoperable RCIC System instrumentation channel. ,

l

] FERMI - UNIT 2 B 3.3.5.2 - 5 Revision 15. 09/03/99 l

1 l

n- O

RCIC System Instrumentation B 3.3.5.2 i

,,, BASES APPLICABLE Manual Initiation SAFETY ANALYSES, LCO, and daunc[

The Manual Initiation paah Lit;; cuit s- hirc i x: - ";-9 l APPLICABILITY Ste th "C' Cy;;;; '-ithtu; h;h tht M 7:t-%-t t: -

(continued) th ;;;_ _ iis pruiw6U.. ;n.i. oi.i;.,n .od provides manual ! I g initiation capabilit There is one =h ht'n for the d RCIC System.

ggQ ggg ugd. e 04

')g The Nanual Initiation Function is n sumedn.in;

.;;Hab clan,uf

- accident or transient analyses in t AR. However, the

' Function is retained for overall re ancy and diversity of the RCIC function as required by__the_NRC in the plant j d licensing basis.

gQfg -

There is no Allowable Value for this Function since the l channel is mechanically actuated based solely on the -

position of the E " ' " . One channel of Manual '

Initiation is required to be OPERABLE when RCIC is required to be OPERABLE.

ACTIONS Rev te: Certain LC0 Completion Times ar- 4 8 approved top ca In ord consee to use l the times, the license he Completion Times as required afety Evaluat on' 43 l A Note has been provided to modify the ACTIONS related to

RCIC System instrumentation channels. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate l entry into the Condition. Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RCIC System instrumentation channels provide l appropriate compensatory measures for separate inoperable i channels. As such, a Note has been provided that allows separate Condition entry for each inoperable RCIC System j instrumentation channel. i (continued)

BWR/4 STS B 3.3-144 Rev 1, 04/07/95 rav %

. w, -y W

INSERT THIS PAGEIN FRONT OF VOLUME 8 6 ,a '^ i / . , , , Valmne 8: SECTION 3.7 .,; . , . .;

.g1 Remme Replace 3.7.4 NUREG M/U pg 3.715 Rev 13 3.7.4 NUREG M/U pg 3.7-15 Rev 15 B 3.7.4 NUREG M/U pg B 3.7 29 Rev 13 B 3.7.4 NUREG M/U pg B 3.7 29 Rev 15 3.7.4 JFDs pg i Rev 0 3.7.4 JFDs pg 1 Rev 15 l

l t

f i

j' Rev 15 09/03/99

$ Control oor System (e.ifp c 3.7 ACTIONS (continued) hh}

CONDITION REQUIRED ACTION COMPLETION TIME E. Two4contro C$c - NOTE - -

subsystems inoperable LC0 3.0.3 is not applicable. [ ,",' 7 2 AC I'. J"/

during movement of . - -

irradiated fuel assemblies in the E.1 Suspend movement of Imediately

(secondary}< irradiated fuel containment, during assemblies in the Q.7,2. de feb C,3 ,

CORE ALTERATIONS, or ;(secondary}:-

during CPDRVs. containment.

M E.2 Suspend CORE Imediately ALTERATIONS. l (3.7,2 /7ctI% C. N 1 E.3 Initiate actions to Innediately suspend OPDRVs. /

(3 ,"/,2. Acis,on C _.:

SURVEILLANCF REQUIREMENTS SURVEILLANCE FREQUENCY

SR 3.7.h.1 Verifygach2: :tr:1 ;; s ".C7"; i;,;t a hu I."] e-th:-

MMty te . -.. U. eee.ud hat 4 t.

A gs corr lro{ (corrs ae'r kretf aa{vff. Il- l10Vf5

th .6 95'F. - ' i l

l

- i;;;/4 STS--- 3.7-15 -Rn 1. O'/"/*"

. RetWll Rev 13/ ;

^_ , _ h* hN

O . ,.

i' M44T fControlRoom.AC) B 3.7.8c- System

~

BASES

~.

ACTIONS E.1. E.2. and E.3 (continued) require isolation of the control room. This places the unit in a condition that minimizes risk.

If applicable, CORE ALTERATIONS and handling of irradiated -

fuel in the } secondary) containment must be suspended issnediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, actions must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue untti the OPDRVs are suspended.

h SURVEILLANCE REQUIREMENTS SR 3.7 '

T M

This SR verifies that the heat removal capability of the quificofiatd system is sufficient to remove the control room heat load ,

lb. canhol Itbn4 ,b. Z_ ...L_.I.'.'

"_'5. 'II.I.I.I5 C "* !,,N* *I. *. . . . . .

.., ...'_.IIE..i.iE. ..I. _...

k l .pwp-c/d k/m a N Frequency is appropriate since significant deg,radation of '

Ithe the( ntrol Epen AC{ System is not expected over this time R Cs & )

REFERENCES I. uFSAR,Section36.4{.

.2. O rsAR, .S ee flo., fl. 'l . I l

8WR/t !!! B 3.7-29 -Rev-h--04/M/M-l i

l ..

. get15 Il Rw 0 l h =m s e, i W

JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.7.4 CONTROL CENTER AIR CONDITIONING (AC) SYSTEM NON BRACKETED PLANT SPECIFIC CHANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and commitments. Additional rewording, reformatting, and revised numbering is made to incorporate these. changes consistent ,

with Writer's Guide conventions. Refer to CTS Discussion Of Changes k to the related requirements for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented.

P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses.

P.3 Bases changes are made to reflect changes made to the Specification.

Refer to the Specification change (and associated JFD) for additional detail.

1 P.4 The reference to the NRC Policy Statement has been replaced with a l

more appropriate reference to the Improved Technical Specification

" split" criteria found in 10 CFR 50.36(c)(2)(ii).

1 FERMI UNIT 2 1 REVISION 15. 09/03/99l

f:!

INSERT THIS PAGE IN FRONT OF VOLUME 10 Jolume: 10 SECTIONS 3.9,3.10,4.0 & 5.0' --

4 Remove Replace 3.10.5 ITS pg 3.10-15 Rev 0 3.10.5 ITS pg 3.10-15 Rev 15 3.10.5 NUREG M/U pg 3.10-15 . 3.10.5 NUREG M/U pg 3.10-15 Rev 15 3.10.5 JFDs pg i Rev 0 3.10.5 JFDs pg i Rev 15 1

i l

l 1

Rev 15 09/03/99

Single CPD Removal-Refueling 3.10.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods. Other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. are fully inserted. j SR 3.10.5.2 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. in a five by five array centered on the control rod withdrawn for the removal of the associated CRD. are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l () )) progress.

l l

l I

l 1

l

] FERMI UNIT 2 3.10 15 Revision 15. 09/03/99 1

i

- .._-_..a

1 Single CRD Removal-Refueling 3.10.5 SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no CORE ALTERATIONS are in progress.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Doc A,g) fa #v '@

l l

I l

l

"""/4 SIS

- 3.10-15 by 2,- 0 je7,2 mee game e.w m F .e mp -- .a 6A Fe6 +

M" JWI W+h4'-

. _#m'4

I JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.10.5 - SINGLE CRD REMOVAL REFUELING NON-BRACKETED PLANT SPECIFIC CHANGES P.1 Not used.

P.2 Not used.

P.3 Bases changes are made to reflect changes made to the Specification.

Refer to the Specification change (and associated JFD) for additional detail.

P.4 Additional detail added to the Bases to reflect information relocated from CTS. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis, which are reflected in the ITS as presented.

P.5 Revisions to NUREG 1433 are made to correct the presentation of ,

the appropriate steps for a control rod drive (CRD) removal. The NUREG requirements and associated Bases discussions infer that the control rod is fully withdrawn, and then in conjunction with j

disconnecting the position indication probe for the drive a control rod block is inserted and/or valving out of the CRD is l performed. However, after disconnecting the position indication probe the step preceding insertion of a control rod block and/or valving out the CRD is to de couple the control rod blade from the ;

drive, which necessitates applying another control rod withdraw j signal. This final withdraw signal can not be applied if a !

control rod block is in place or if the CRD is valved out.

ITS 3.10.5 presents revised requirements and Bases that are consistent with the actual procedures necessary to perform the applicable CRD maintenance. These changes are also the subject of l a pending generic change to NUREG 1433 (reference BWROG 42).

P.6 The reference to the NRC Policy Statement has been replaced with a more appropriate reference to the Improved Technical Specification

" split" criteria found in 10 CFR 50.36(c)(2)(ii).

P.7 ITS LC0 3.10.5.c and the Bases corresponding to the Bases for SR 3.10.5.5 clearly discuss the need to assurt. that no "other" (other than the control rod being withdrawn / removed) Core Alterations are in progress. NUREG SR 3.10.5.5 is corrected to explicitly add the k "other" phrasing (consistent with the LCO) to correct an editorial oversight.

FERMI UNIT 2 1 REVISION 15. 09/03/99l l

mv ew4 A w. m er p r .une A 4 e m g e_pg

p INSERT THIS PAGE IN FRONT OF VOLUME 12

' Volume 12: IMPROVED TECHNICAL SPECIFICATIONS ,

Remove Replace I 3.10.5 ITS pg 3.10-15 Rev 0 3.10.5 ITS pg 3.10-15 Rev 15

)

l l

1 l

)

l I \

j l

l l

Rev 15 09/03/99

-_. --m- a_--mm

Single CRD Removal-Refueling 3.10.5 i

l l

SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD, in a five by five array centered on the control rod withdrawn for the removal of the associated CRD are disarmed.

! SR 3.10.b.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted. 1 i

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 i

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

hl SR 3.10.5.5 Verify no other CORE ALTERATIONS are in progress.

l i

(

l l

l l FERMI UNIT 2 3.10 15 Revision 15. 09/03/99

I INSERT THIS PAGE IN FRONT OF VOLUME 13 i

)

l Volume 13:' IMPROVED TECHNICAL SPECIFICATIONS BASES

)

Remove Replace '

B 3.3.1.1 ITS pg B 3.3.1.1 14 Rev 2 B 3.3.1.1 ITS pg B 3.3.1.1-14 Rev 15 B 3.3.1.1 ITS pg B 3.3.1.1-15 Rev 0 B 3.3.1.1 ITS pg B 3.3.1.1-15 Rev 15 l

B 3.3.1.1 ITS pg B 3.3.1.1-16 Rev 0 B 3.3.1.1 ITS pg B 3.3.1.1-16 Rev 15 B 3.3.5.2 ITS pg B 3.3.5.2-3 Rev 0 B 3.3.5.2 ITS pg B 3.3.5.2-3 Rev 15 .

B 3.3.5.2 ITS pg B 3.3.5.2-4 Rev 0 B 3.3.5.2 ITS pg B 3.3.5.2-4 Rev 15 B 3.3.5.2 ITS pg B 3.3.5.2-5 Rev 12 B 3.3.5.2 ITS pg B 3.3.5.2-5 Rev 15 l

l l

(

Rev 15 09/03/99

RPS Instrumentation l B 3.3.1.1 l BASES APPLICABLE SAFETY ANALYSES. LCO and APPLICABILITY (continued)

5. Main Steam [ solation Valve-Closure MSIV closure results in loss of the main turbine and the condenser as a heat sink for the nuclear steam supply system and indicates a need to shut down the reactor to reduce heat generation. Therefore, a reactor scram is initiated on a Main Steam Isolation Valve-Closure signal before the MSIVs are completely closed in anticipation of the complete loss n of the normal heat sink and subsequent overpressurization 4 transient. However, for the overpressurization protection analysis of Reference 4. the Average Power Range Monitor Neutron Flux-Upscale Function, along with the SRVs. limits the peak RPV pressure to less than the A5ME Code limits.

q That is, the direct scram on position switches for MSIV closure events is mt assumed in the overpressurization analysis.

The reactor scram reduces the amount of energy required to be absorbed and, along with the actions of the ECCS. ensures that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46.

MSIV closure signals are initiated from position switches located on each of the eight MSIVs. Each MSIV has one position switch that provides the originating sensor for two separate channels; one inputs to RPS trip system A while the other inputs to RPS trip system B. Thus, each RPS trip iL system receives an input from eight Main Steam Isolation g Valve-Closure channels, each channel consisting of one j position switch, which is shared with one other channel.

j The logic for the Main Steam Isolation Valve-Closure Function is arranged such that either the inboard or outboard valve on three or more of the main steam lines must close in order for a scram to occur.

The Main Steam Isolation Valve-Closure Allowable Value is specified to ensure that a scram occurs prior to a significant reduction in steam flow, thereby reducing the severity of the subsequent pressure transient.

l Sixteen channels of the Main Steam Isolation Valve-Closure {

Function, with eight channels in each trip system, are l required to be OPERABLE to ensure that no single instrument failure will preclude the scram from this Function on a valid signal. This Function is only required in MODE 1 since, with the MSIVs open and the heat generation rate i 1

i i

'l FERMI - UNIT 2 B 3.3.1.1- 14 Revision 15. 09/03/99

RPS Instrumentation B 3.3.1.1 BASES APPLICABLE SAFETY ANALYSES. LCO, and APPLICABILITY (continued) high, a pressurization transient can occur if the MSIVs close. In MODE 2. the MSIV closure trip is automatically bypassed. and the heat generation rate is low enough so that the other diverse RPS functions provide sufficient protection.

6. Main Steam Line-Hiah Radiation Main Steam Line-High Radiation Function ensures prompt reactor shutdown upon detection of high radiation in the vicinity of the main steam lines. High radiation in the vicinity of the main steam lines could indicate a gross fuel failure in the core. The scram is initiated to limit the fission product release from the fuel. This Function is not specifically credited in any accident analysis but is being retained for overall redundancy and diversity of the RPS as 3

required by the NRC approved licensing basis.

Main Steam Line-High Radiation signals are initiated from four radiation monitors. Each monitor senses high gamma radiation in the vicinity of the main steam line. The Main Steam Line-High Radiation Allowable Value is selected high enough above background radiation levels to avoid spurious scrams yet low enotgh to promptly detect a gross release of fission products fr(m the fuel.

Four channels of Main Steam Line-High Radiation Function with two channels in each trip system. arranged in a one-out of two logic, are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this function on a valid signal. This Function is required in MODES 1 and 2 where considerable energy exists such that steam is being produced at a rate which could release considerable fission products from the fuel.

The Allowable Value is based on the NRC guidelines of 3.6 times the full ]ower background radiation level with nominal full power lydrogen injection rate. This Allowable Value remains fixed at this nominal full-power basis even when operating at reduced power and/or reduced hydrogen I

injection rates.

7. Drywell Pressure-Hiah High pressure in the drywell could indicate a break in the RCPB. A reactor Scram is initiated to minimize the l

l l FERMI - UNIT 2 B 3.3.1.1 - 15 Revision 15. 09/03/99

.A__._._.2._'. re %. p,%,

RPS Instrumentation B 3.3.1.1 BASES APPLICABLE SAFETY ANALYSES, LCO. and APPLICABILITY (continued) possibility of fuel damage and to reduce the amount of energy being added to the coolant and the drywell. The Drywell Pressure-High Function is assumed to scram the plant coincident with the Reactor Vessel Water Level-Low. Level 3 function in the analysis of the LOCA inside primary containment. The reactor scram reduces the amount of energy to be absorbed and helps the ECCS ensure that the fuel peak cladding temperature remains below the limits of 10 CFR 50.46.

High drywell pressure signals are initiated from four pressure transmitters that sense drywell pressure. The Allowable Value was selected to be as low as possible and indicative of a LOCA inside primary containment.

Four channels of Drywell Pressure-High Function, with two channels in each trip system arranged in a one out of two logic are required to be OPERABLE to ensure that no single instrument failure will preclude a scram from this Function on a valid signal. The Function is required in MODES 1 and 2 where considerable energy exists in the RCS. resulting in the limiting transients and accidents.

8a. 8b. Scram Discharae Volume Water Level-Hiah The SDV receives the water displaced by the motion of the CRD pistons during a reactor scram. Should this volume fill to a point where there is insufficient volume to accept the displaced water, control rod insertion would be hindered.

Therefore, a reactor scram i.; initiated while the remaining free volume is still sufficient to accommodate the water from a full core scram. The two types of Scram Discharge Volume Water Level-High Functions are an input to the RPS .

logic. No credit is taken for a scram initiated from these Functions for any of the design basis accidents or transients analyzed in the UFSAR. However, they are retained to ensure the RPS remains OPERABLE.

SDV water level is measured by two diverse methods. The level is measured by four float type level switches and four level transmitters for a total of eight level signals. The outputs of these devices are arranged so that there is a signal from a level switch and a level transmitter to each ,

RPS logic channel. The level measurement instrumentation satisfies the recommendations of Reference 8.

] l FERMI UNIT 2 E 3.3.1.1 - 16 Revision 15. 09/03/99 l

. . - ~ . ~ .

1 RCZC System Instrumentation B 3.3.5.2 8ASES 1

APPLICABLE SAFETY ANALYSES. LCO. and APPLICABILITY (continued) {

The individual Functions are required to be OPERABLE in MODE 1. and in MODES 2 and 3 with reactor steam dome

)ressure > 150 psig since this is when RCIC is required to

)e OPERABLE. (Refer to LCO 3.5.3' for Applicability Bases for the RCIC System.)

The specific Applicable Safety Analyses. LCO, and Applicability discussions are listed below on a Function by

. Function basis.

1. Reactor Vessel Water Level-Low Low.__ Level 2 Low reactor pressure vessel (RPV) water level indicates that normal feedwater flow is insufficient to maintain reactor vessel water level and that the capability to cool the fuel may be threatened. Should RPV water level decreese too far, fuel damage could result. Therefore, the RCIC System is initiated at level 2 to assist in maintaining water level !

above the top of the active fuel.

Reactor Vessel Water Level-Low Law. Level 2 signals are initiated from four level transmitters that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

The Reactor Vessel Water Level-Low Low. Level 2 Allowable Value is set high enough such that for complete loss of feedwater flow, the RCIC System flow with high pressure coolant injection assumed to fail will be sufficient to avoid initiation of low pressure ECCS at Level 1. l Four channels of Reactor Vessel Water Level-Low Low.

Level 2 Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC initiation.

Refer to LCO 3.5.3 for RCIC Applicability Bases.

2. Reactor Vessel Water level-Hich. Level 8 High RPV water level indicates that sufficient cooling water inventory exists in the reactor vessel such that there is no danger to the fuel. Therefore, the Level 8 signal is used to close the RCIC steam supply, steam supply bypass, and cooling water supply valves to prevent overflow into the I

UNIT 2 B 3.3.5.2 - 3 Revision 15. 09/03/99 h l FERMI

RCXC System Instrumentation B 3.3.5.2 BASES APPLICABLE SAFETY ANALYSES. LCO. and APPLICABILITY (continued) main steam lines (MSLs). (The injection valve also closes due to the closure of the steam supply valve.)

Reactor Vessel Water Level-High. Level 8. signals for RCIC are initiated from two , level transmitters from the wide range water level measurement instrumentation, which sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

The Reactor Vessel Water Level-High. Level 8 Allowable Value is high enough to preclude isolating the injection valve of the RCIC during normal operation, yet low enough to trip the RCIC System prior to water overflowing into the MSLs.

I Two channels of Reactor Vessel Water Level-High. Level 8 '

Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC initiation. Refer to LCO 3.5.3 for RCIC Applicability Bases.

3. Condensate Storace Tank Level-Low Low level in the CST indicates the unavailability of an adequate supply of makeup water from this normal source.

Normally. the suction valve between the RCIC pump and the CST is open and, upon receiving a RCIC initiation signal, water for RCIC injection would be taken from the CST. l However, if the water level in the CST f alls below a preselected level. first the suppression pool suction valves automatically open. and then the CST suction valve 1 (consistency) automatically closes. This ensures that an j adequate supply of makeup water is available to the RCIC pump. To prevent losing suction to the pump. the suction valves are interlocked so that the suppression pool suction valves must be open before the CST suction valve automatically closes.

Two level transmitters and trip units in the HPCI system are used to detect low water level in the CST. The Condensate Storage Tank Level-Low Function Allowable Value is set high enough to ensure adequate pump suction head while water is being taken from the CST.

i g l FERMI UNIT 2 B 3.3.5.2-4 Revision 15. 09/03/99

RCIC System Instrumentation B 3.3.5.2 BASES l

APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

Two channels of Condensate Storage Tank Level-Low Function are available and are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC swap to suppression pool source.

Refer to LCO 3.5.3 for RCIC Applicability Bases.

~

4. Manual Initiation The Manual Initiation channel provides manual initiation capability to individual valves. There is one manual initiation channel for the RCIC System.

The Manual Initiation Function is not assumed in any

- accident or transient analyses in the UFSAR. However, the d Function is retained for overall redundancy and diversity of the RCIC function as required by the NRC in the plant Q licensing basis.

There is no Allowable Value for this Function since the channel is mechanically actuated based solely on the position of the valve control. One channel of Manual Initiation is required to be OPERABLE when RCIC is required to be OPERABLE.

ACTIONS A Note has been provided to modify the ACTIONS related to RCIC System instrumentation channels. Section 1.3.

Completion Times specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Section 1.3 also specifies that 1 Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable RCIC System instrumentation channels provide appropriate compensatory measures for separate inoperable channels. As such, a Note has been provided that allows separate Condition entry for each inoperable RCIC System instrumentation channel.

l l FERMI UNIT 2 B 3.3.5.2 - 5 Revision 15. 09/03/99

I 1

l l

l f

l I

ATTACHMENT 3 TO ,

1 NRC-99-0079 DETROIT EDISON COMMENTS ON DRAFT ITS SAFETY EVALUATION I

4

)

l I

Attachment 3 to NRC-99-0079 Page 2 Detroit Edison's Comments on Draft Safety Evaluation (SE)

As discussed with the NRC, these comments do not encompass formatting, references between ITS sections and the SE, and the updating of the SE for the most current information from supporting discussions of changes. These items should be checked in the final SE preparation following comment incorporation.

The following are specific comments on the Draft Safety Evaluation for the Fermi 2 Improved Technical Specifications:

Reference Comment

1. Page 1,3'd paragraph, There were other conference calls that took place

... conference calls and meetings beyond July 8,1999. This statement should be that concluded on July 8,1999." revised to clarify this fact or remove reference to

- July 8.1999.

2. Page 5,2"d paragraph,"The Staff's The dates of the individual supplements should be evaluation..., including the restated here to avoid confusion with the table of supplements listed above...". recent license amendments provided above the statement.

3. Page 5, 3"' paragraph, "...will make This statement should be revised to indicate that the enforceable... the implementation license condition makes the implementation of new and revised SRs in the ITS". transition provisions enforceable and not the actual SRs, which are enforceable by way of their inclusion in the ITS.

4. Page 19, Section D -Type 2,3 and These statements should be revised to eliminate 4 paragraphs, "...specified in reference to relocation of details to plant

. . station procedures..." procedures. Relocations to procedures is not in accordance with the current NRC ITS conversion guidance.

5. Page 21, Section D,2"d bullet under This statement should be revised to indicate that the 1" paragraph, "UFSAR (which UFSAR includes the TRM."

includes the TRM by reference)

6. Page 32, Section E,1" paragraph This statement should be revised to accommodate after bulin , 'The ,elocated the fact that the LCO for Decay Time (bullet 21) specifications...do not fall within satisfies Criterion 2.

the criteria for mandatory inclusion in the TS in 10 CFR 50.36 (c)(2)(ii)."

i i

Attachment 3 to NRC-99-0079

' Page 3 Reference Comment

7. Page 33, Section F,1" paragraph, This statement should be removed since it is not

" Temporary procedure changes are germane to the Fermi 2 ITS conversion.

also controlled by 10 CFR 50.54(a)."

8. Page 36, Section G, bullet 3 for ITS This section should be revise to reflect the recent 3.4.1, " CTS 3.4.1.1, Recirculation - revision Fermi 2 ITS that added provisions related System... Operation". to resetting the operating limits for minimum critical power ratio and maximum average planar linear heat generation rate for single loop operation.

9. Page 43,Section IV, states "The For clarity, these sections (i.e., IV and V) should be licensee has been requested to revised to reflect that "... Fermi 2 was requested and submit a license condition to make did submit the requested license conj.itions..."

this commitment enforceable."

Page 43,Section V, states "In the letter of ... , the licensee proposed a license condition...".

10. Table A,2.0, A.4 These changes should be indicated as "not used."

Table A,3.5.2, A.13 Table A,5.7, A.4

11. Table L,3.3.5.2, LC.1 The table should be revised to categorize this change as "C"instead of"G".

12. Table L, 3.6.1.1, L.1 The SE should be revised to define the change category of" Unique" for 3.6.1.1 L.1 as stated in this table. As discussed with the NRC, a global search of the SE should be performed for similar problems following comment incorporation.

1 l

l

)

l l

\

ATTACIIMENT 4 TO NRC-99-0079 I

l FERMI 2 ITS AND BASES 1

I L

Definitions

'1.1 1.0 USE AND APPLICATION 1.1 Definitions

................................... NOTE- ---

The defined terms of this section a pear in ca italized type and are applicable throughout these Technic 1 Specific tions and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that 1 prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE Pl.ANAR LINEAR The APLHGR shall be applicable to a specific HEAT GENERATION RATE 31anar height and is equal to the sum of the (APLHGR) _HGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it O responds within the necessary range and accuracy to known values of the )arameter that the channel monitors. A CHANNEL CA_IBRATION shall encompacs all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. j Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. A CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

I (continued)

FERMI UNIT 2 1.1-1 Amendment No. 134

+

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel 0PERABILITY. A CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power l

range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

l Suspension of CORE ALTERATIONS shall not preclude j completion of movement of a component to a safe position.

'- (continued)

FERMI - UNIT 2 1.1 2 Amendment No. 134

Definitions 1.1 i

( 1.1 Definitions (continued)

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131. I-132. 1-133. I-134.

and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID 14844 AEC.1962. " Calculation of Distance Factors for Power and Test Reactor Sites."

EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until

/~T the ECCS equipment is capable of performing its V safety function (i.e.. the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading l

! delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

)

fl !

d (continued)

FERMI - UNIT 2 1.1-3 Amendment No. 134 e

Definitions 1.1 l -.

f)l s

1.1 Definitions (continued)

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE -

1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank: or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the l operation of leakage detection systems or not to be pressure boundary LEAKAGE:

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE:

c. Iptal LEAKAGE i

/~T Sum of the identified and unidentified V

LEAKAGE:

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. '

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

/m

(") (continued)

FERMI UNIT 2 1.1 4 Amendment No. 134 L

~

Definitions 1.1 1.1 Definitions (continued)

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power RATIO (MCPR) ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the a)propriate correlation (s) to cause some point in tie assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE -0PERABILITY A system, subsystem, division,, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety i function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that s are required for the system, subsystem, division.

component, or device to perform its specified

~

safety function (s) are also capable of performing their related support function (s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to ,

measure the fundamental nuclear characteristics of i the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14. Initial Test Program I of the UFSAR: ,

b. Authorized under the provisions of 10 CFR 50.59: or i

c. Otherwise approved by the Nuclear Regulatory Commission.

O (continued)

FERMI UNIT 2 1.1-5 Amendment No. 134 i

L

Definitions 1.1 1.1 Definitions (continued)

(

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3430 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the r.hannel sensor until de energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured, SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subtritical assuming that:

a. The reactor is xenon free; I

b. The. moderator temperature is 68*F: and ,

l

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

pJ With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillanta Frequency, so that all systems, subsyste s, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, cr other designated components in the associated function.

l 10 V (continued)

FERMI UNIT 2 1.1 6 Amendment No. 134 l

i Definitions 1.1

( 1.1 Definitions (continued)

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant, TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of the time from when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine by required positions. pass valves travel The response to their time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

O O

FERMI UNIT 2 1.1 7 Amendment No. 134

t. ,

F .

Definitions 1.1

'l Table 1.1-1 (page 1 of 1)

V H0 DES REACTOR MODE AVERAGE REACTOR

! MODE TITLE SWITCH POSITION COOLANT TEMPERATURE

! (*F) 1 Power Operation Run NA 2 Startup Refuel (a) or NA Startup/ Hot Standby 3 Hot Shutdown (a) Shutdown > 200 4 Cold Shut'Jown(a) Shutdown s 200 5 Refueling (b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

l l

FERMI' UNIT 2 1.1 8 Amendment No. 134

i

! Logical Connectors 1.2 l

> y~s

( ) 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

l Logical connectors are used in Technical Specifications (TS) l to discriminate between, and yet connect, discrete l Conditions, Re

! Surveillances, quired Actions, Completion and Frequencies. Times,connectors The only logical i i that appear in TS are ANQ and 2 The physical arrangement of these connectors constitutes logical conventions with specific meanings.

I BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the

('_') number of the Required Action). The successive levels of V , logic are identified by additional digits of the Required l

Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completicn Time, Surveillance, or Frequency, only the first

, level of logic is used, and the logical connector is left l justified with the statement of the Condition, Completion Time. Surveillance, or Frequency.

i i

f (Continued)

FERMI - UNIT 2 1.2 1 Amendment No. 134 l

1

Logical Connectors 1.2 1.2 Logical Connectors (continued)

EXAMPLES The following examples illustrate the use of logical connectors.

EXat!PLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LC0 not met. A.1 Verify . . .

htQ A.2 Restore . . .

In this example the logical connector 8NQ is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

O l

l i

I l

(continued) ;

FERMI - UNIT 2 1.2 2 Amendment No. 134

(

Logical Connectors 1.2 7w 1.2 Logical Connectors i]

EXAMPLES EXAMPLE 1.2-2 (continued) '

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LC0 not met. A.1 Trip . . .

2 A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

E A.2.2.2 Perform . . .

O V A.3 Align . . .

This example represents a more complicated use of logical connectors. Required Actions A.1. A.2 and A.3 are alternative choices. only one of which must be performed as indicated by the use of the logical connector M and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND.

Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector M indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

rN U

FERMI UNIT 2 1.2 3 Amendment No. 134

Completion Times 1.3 O

v 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LC0 state Conditions that typically describe the ways in which the requirements of the LC0 can fail to be met. Specified with each stated Condition are Required Action (s) and Completion Times (s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or varicble not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Q

V Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LC0 Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LC0 (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of j the situation that required entry into the Condition. !

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the l Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

1 (continued)

FERMI - UNIT 2 1.3 1 Amendment No. 134

i l

Completion Times 1.3

( 1.3 Completion Times DESCRIPTION However, when a subseauent division, subsystem, component.

(continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time (s-) may be extended. To apply this Completion Time extension. two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability:

and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

j

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

b The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely seaarate re entry into the Condition (for each division, su) system, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re entry. These exceptions are stated in individual Specifications. j The above Completion Time extension does not apply to a Completion Time with a modified " time zero." This modified !

" time zero" may be expressed as a repetitive tina (i.e.,

"once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ." where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ." Example 1.3 3 illustrates one use of

, this type of Completion Time. The 10 day Completion Time i specified for Condition A and B in Example 1.3 3 may not be.

extended.

O (continued)

FERMI - UNIT 2 1.3 2 Amendment No. 134

I Completion Times 1.3

\

1.3 Completion Times (continued) l EXAMPLES The following examples illustrate the use of Completion l Times with different types of Conditions and changing Conditions. l EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

l Condition B has two Required Actions. Each Required Action I has its own separate Completion Time. Each Completion Time

'O is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of l 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from !

the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3. the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

l n

U (continued) :

l FERMI UNIT 2 1.3 3 Amendment No. 134 i

Completion Times 1.3 O

LJ 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued) {

ACTIONS )

CONDITION REQUIRED ACTION COMPLETION TIME i

A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and !

associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met. ,

, When a pump is declared inoperable. Condition A is entered.

If the pump is not restored to OPERABLE status within 7 days. Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered. Conditions A and B are exited, and therefore. the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable. Condition A is not re-entered for the second pump. LC0 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump.

The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3 if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired. LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

,( p) (continued)

FERMI - UNIT 2 1.3 4 Amendment No. 134 L

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in LC0 3.0.3 if one of the inoperable pumps is -

restored to OPERABLE status and the Com)letion Time for Condition A has expired, LC0 3.0.3 may )e exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this ;

does not result in the second pump being inoperable for

> 7 days. i i

O l

l (continued)

FERMI UNIT 2 1.3-5 Amendment No. 134

Completion Times 1.3 4 1

0 1.3 co a'et4eo T4 es

-EXAMPLES EXAMPLE 1.3-3 -

(continued) -

4 ACTIONS 1

COWITION REQUIRED ACTION COMPLETION TIME A. One. A.1 Restore 7 days Function X Function X subsystem subsystem to E

inoperable. OPERABLE status. i discovery of failure to meet j the LC0 B. One ' B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y subsystem subsystem to- E !

inoperable.' OPERABLE status.

O 10 days from discovery of failure to meet the LC0 C. One C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X Function X subsystem subsystem to inoperable. OPERABLE status.

M QB One C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y subsystem subsystem to

. inoperable. OPERABLE status.

e h,-. (continued)

FERMI - UNIT 21 1.3 6 Amendment No. 134

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are ino>erable. Condition A and Condition B are concurrently applica)le. The Com)letion Times for Condition A and Condition B are tracted separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time. Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired.

operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable

-(i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a

' logical connector, with a separate 10 day Completion Time O- measured from the time it was discovered the LC0 was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A. B.

and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO.

The separate Completion Time modified by the phrase "from discovery of failure to meet the LC0" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time allows for an exception to the normal

" time zero" for beginning the Completion Time " clock". In this instance, the Completion Time " time zero" is specified as commencing at the time the LC0 was initially not met, instead of at the time the associated Condition was entered.

t (continued) 1 FERMI UNIT 2 1.3-7 Amendment No. 134 I l

Completion Times 1.3

( 1.3 Completion Times EXAMPLES EXAMPLE 1.3 4 (continued)

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve (s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s valves to OPERABLE inoperable. status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

/ n U A single Completion Time is used for any number of valves '

ino)erable at the same time. The Completion Time associated wit 1 Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis.

Declaring subsequent valves inoperable, while Condition A is still in effect. does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The I Completion Time may be extended if the valve restored to l OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable.

Condition B is entered.

O)

% (continued)

FERMI - UNIT 2 1.3-8 Amendment No. 134

Completion Times 1.3 1.3 Completion Times V(3 EXAMPLES EXAMPLE 1.3 5 (continued) '

ACTIONS

.. ......................... NOTE -- --------

Se arate Condition entry is allowed for each inoperable j va ve.

............................................................ )

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND O' Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve. and Completion Times tracked on a per valve basis. When a valve is declared inoperable.

Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable. Condition A is (

entered for each valve and separate Completion Times start [

and are tracked for each valve. s (continued)

FERMI UNIT 2 1.3 9 Amendment No. 134

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

If the Completion Time associated with a valve in

Condition A expires. Condition B is entered for that valve.

If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times. Completion Time extensions do not apply.

O (continued)

FERMI UNIT 2 1.3 10 Amendment No. 134

Completion Times 1.3 1.3_ Completion Times EXAMPLES EXAMPLE 1.3 6 (continued)

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable. SR 3.x.x.x. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

.08 A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to 5 50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion t,_s) Time not v met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" i Completion Time, which qualifies for the 25% extension, per SR 3.0.2 to each performance after the initial performance.

The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be coalplete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2), Condition B is entered.

If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met. Condition B is entered.

If after entry into Condition B. Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

(continued)

FERMI - UNIT 2 1.3 11 Amendment No. 134 i

l

~

l Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3 7 (continued)

ACTIONS .

COEITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable, isolated. Ngl Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

O V B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered Required Action A.1 is not met within either the initial I hour or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2). Condition B is entered. The

! Completion Time clock for Condition A does not stop after l Condition B is entered, but continues from the time I

Condition A was initially entered. If Required Action A.]

i (continued)

FERMI UNIT 2 1.3 12 Amendment No. 134 l

i

Completion Times 1.3 1.3- Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A.

provided the Completion Time for Required Action A.2 has not expired.

IMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

O FERMI - UNIT 2 1.3 13 Amendment No. 134

Frequency 1.4 Q

U l.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define 't proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated v as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the 1 associated LC0 is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only " required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of " met" or " performed" in these instances conveys specific meanings., A Surveillance is " met" only when the !

acceptance criteria are satisfied. Known failure of the !

requirements of a Surveillance, even without a Surveillance specifically being " performed." constitutes a Surveillance i not " met." " Performance" refers only to the requirement to ;

specifically aetermine the ability to meet the acceptance '

L (continued)

FERMI - UNIT 2 1.4 1 Amendment No. 134

Frequency 1.4 1.4 Frequency DESCRIPTION criteria. SR 3.0.4 restrictions would not apply if both the (continued) following conditions are satisfied: ,

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LC0 (LC0 not shown) is MODES 1. 2.

and 3.

l EXAMPLE 1.4-1 j SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

'( Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

Exam)le 1.41 contains the type of SR most often encountered in t1e Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time.

Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met )er SR 3.0.1 (such as when the equipment is inoperaale, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO. and the performance of the Surveillance is not (continued)

FERMI UNIT 2 1.4 2 Amendment No. 134

Frequency 1.4 n

() 1.4 Frequency EXAMPLES EXAMPLE 1.4 1 (continued) otherwise modified (refer to Examples 1.4 3 and 1.4-4), then SR 3.0.3 becomes applicable.

!/ the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LC0 for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

1 EXAMPLE 1.4 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within

/l 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after ;

V a 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4 2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "6N_D" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to a 25% RTP. the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by SR 3.0.2.

()

o (continued)

FERMI UNIT 2 1.4 3 Amendment No. 134

Frequency 1.4 m

Q 1.4 Frequency EXAMPLES EXAMPLE 1.4 2 (continued) l "Thereafter" indicates future performances must be -

established per SR 3.0.2. but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP. the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

l' EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

...............N0TE -- -- - --- ---

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after = 25% RTP.

tO V

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is

< 25% RTP between performances, i l

As the Note modifies the required performance of the l Surveillance, it is construed to be part of the "specified l Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after :

power reaches = 25 RTP to perform the Surveillance. The l Surveillance is still considered to be within the "specified Frequency." Themf ore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES. even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power a 25% RTP.

'O Q (continued)

FERMI UNIT 2 1.4 4 Amendment No. 134

1 Frequency 1.4 m

(j 1.4 Frequency ,

EXAMPLES EXAMPLE 1.4 3 (continued)

Once the unit reaches 25% RTP,12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

I 1

EXAMPLE 1.4 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

..................N0TE - - ----+ ----

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months O

Example 1.4 4 specifies that the requirements of this ,

Surveillance do not have to be met until the unit is in i MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4 1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2),

but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the :

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that th, bour Frequency were not met). SR 3.0.4 would require se.fisfying the SR.

F'.MI - UNIT 2 1.4 5 Amendment No. 134

r SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 1

2.1.1 Reactor Core SLs -

1 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure = 785 psig and core flow = 10% rated core flow:

MCPR shall be = 1.11 for two recirculation loop operation or = 1.13 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.

U .

2.2 SL Violations E

With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.1 Restore compliance with all SLs: and 2.2.2 Insert all insertable control rods.

I I

O FERMI - UNIT 2 2.0 1 Amendment No. 134

i LC0 Applicability 3.0 l

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LC0 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LC0 3.0.2 and LC0 3.0.7.

LC0 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LC0 3.0.5 and LC0 3.0.6.

If the LC0 is met or is no longer applicable prior to expiration of the specified Completion Time (s), completion of the Required Action (s) is not required, unless otherwise stated.

{

J LC0 3.0.3 When an LC0 is not met and ch.a associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS. the unit shall be ) laced in a MODE or other specified condition in which the _C0 is not i applicable. Action shall be initiated within I hour to l A place the unit, as applicable, in: l U. {

a. MODE 2 within 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months s:

b. MODE 3 within 13 hour1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months s: and

c. MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LC0 or ACTIONS. completion of the actions required by LC0 3.0.3 is not required.

LC0 3.0.3 is only applicable in MODES 1. 2, and 3.

O (continued)

FERMI UNIT 2 3.0-1 Amendment No. 134 I

c LC0 Applicability 3.0 0 3.o 'C0 ^ee'ica81'1Tv <comt4"oeo) .

LC0 3.0.4 When an LC0 is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued

operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Exceptions to this-Specification are stated in the individual Specifications.

LC0 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2.

and 3.

LC0 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other

[\ equipment. This is an exception to LC0 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LC0 3.0.6 When a supported system LC0 is not met solely due to a support system LC0 not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LC0 ACTIONS are required to be entered. This is an exception to LC0 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.11. " Safety Function Determination Program (SFDP)." If a loss of safety function is octermined to exist by this program, the appropriate Conditions and Required Actions of the LC0 in which the loss of safety function exists are required to be entered.

() (continued)

FERMI UNIT 2 3.0 2 Amendment No. 134

i l

LC0 Applicability )

3.0 l l

,-~ \

' 3.0 LC0 APPLICABILITY LCO 3.0.6 When a_ support system's Required Action directs a supported (continued) system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LC0 3.0.2.

LC0 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless

, otherwise specified, all other TS requirements remain unchanged. Compliance with Special 0)erations LCOs is optional. When a Special Operations C0 is desired to be met but is not met, the ACTIONS of the Special Operations LC0 shall be met. When a Special Operations LC0 is not desired to be met entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

o V

FERMI - UNIT 2 3.0 3 Amendment No. 134

SR Applicability 3.0 t

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs. unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

C%, If a Completion Time requires >eriodic performance on a V "once per . . . " basis, the a)ove Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

2

(~)

(continued)

FERMI UNIT 2 3.0 4 Amendment No. 134 1

I

SR Applicability 3.0 3.0 SR APPLICABILITY (continued) 0 SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LC0 not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LC0 must immediately be declared not met, and the applicable Condition (s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LC0 shall not be made unless the LC0's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into i

MODES or other specified conditions in the Applicability x that are required to comply with Actions or that are part of a shutdown of the unit.

SR 3.0.4 is only applicable for entry into a' MODE or other specified condition in the Applicability in MODES 1. 2. and 3.

c, O

b FERMI UNIT 2 3.0 5 Amendment No. 134

o

.;; . SDM 3.1.1 l 3.1 REACTIVITY CONTROL SYSTEMS-3.1.1- SHUTDOWN MARGIN (SDM)

-LC0 3.1.1- SDM shall be: -

a. = 0.38% Ak/k, with the highest worth control rod analytically determined; or

b. = 0.28% Ak/k. with the highest worth control rod determined by test.

-APPLICABILITY:- MODES 1, 2, 3, 4, and 5.

}

ACTIONS-C0lOITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits A.1 Restore SDM to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in MODE 1 or 2. limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

~ Time.of_ Condition AL not met.

C. SDM not within limits C.1 Initiate action to Immediately

, in MODE 3. fully insert all insertable control rods.

(continued)

)

O i

~

FERMI UNIT 2- 3.1-1 Amendment No. 134

SDM 3.1.1 ACTIONS (continued)

CONDITION COMPLETION TIME REQUIRED ACTION D. SDM not within limits D.1 Initiate action to Immediately-in MODE 4. fully insert all insertable control rods.

AND D.2 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to OPERABLE status.

AND D.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months '

restore one standby gas treatment (SGT) subsystem to OPERABLE l

status.

O AND V

D.4 Initiate action to I hour restore isolation l capability in each required secondary !

containment penetration flow path not isolated.

L I

(continued)

O FERMI UNIT 2 3.1 2 Amendment No. 134 i

SDM 3.1.1 i

i ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. SDM not within limits E.1 Suspend CORE Immediately-in MODE 5. ALTERATIONS except for control rod l insertion and fuel assembly removal.

E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

AND E.3 Initiate action to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore secondary containment to

(

l(3.)

M

-OPERABLE status.

E.4 Initiate action to I hour restore one SGT subsystem to OPERABLE '

status.

AND E.5 Initiate action to I hour restore isolation capability in each required secondary containment penetration flow path ;

not isolated.

~

l fx FERMI - UNIT 2 3.1 3 Amendment No. 134 l

f l

l SDM 3.1.1 l O suavet'teace aeouineasu1s SURVEILLANCE FREQUENCY

!- 'SR 3.1.1.1 Verify SDM is: Prior to each in vessel fuel

a. = 0.38% Ak/k with the highest worth movement during control rod analytically determined; fuel loading or sequence

b. = 0.28t Ak/k with the highest worth ANQ control rod determined by test.

Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel O

O FERMI - UNIT 2 3.1 4 Amendment No. 134 l

l i

Reactivity Anomalies !

3.1.2 O'3.1REACTIVITYCONTROLSYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored reactivity and the predicted reactivity shall be within i lt Ak/k.

APPLICABILITY: MODES 1 and 2.

_ ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity A.1 Restore core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months difference not within reactivity difference limit, to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

i l

FERMI - UNIT 2 3.1 5 Amendment No. 134

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify core reactivity difference between Once withiri the monitored reactivity and the predicted 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reactivity is within i 15 Ak/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel AND 1000 MWD /ST thereafter during operations in MODE 1 O

O FERMI UNIT 2 3.1 6 Amendment No. 134

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3- Control Rod 0PERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

..................................... NOTE--- - --- - - --------- - - - --- -

Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control -----

- - NOTE -- --- - -

rod stuck, Rod worth minimizer (RWM) may be bypassed as allowed by N'

LC0 3.3.2.1, " Control Rod

' Block Instrumentation." if required, to allow continued operation.

A.1 Verify stuck control Immediately rod separation criteria are met.

8NQ A.2 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND (continued) m U

FERMI UNIT 2 3.1-7 Amendment No. 134

1 Control Rod OPERABILITY 3.1.3 pd ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i'

A. (continued) A.3 Perform SR 3.1.3.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from and SR 3.1.3.3 for discovery of each withdrawn Condition A l OPERABLE control rod, concurrent with (

THERMAL POWER greater than the low power setpoint (LPSP) l of the RWM j 8NQ A.4 Perform SR 3.1.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two or more withdrawn B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods stuck.

O C. One or more control ------

- NOTE - - - -- -

rods inoperable for RWM may be bypassed as reasons other than allowed by LC0 3.3.2.1. if Condition A or B. required. to allow insertion of inoperable control rod and continued operation.

C.1 Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control i rod.

AND C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD. j i

l (continued)

I O

FERMI UNIT 2 3.1 8 Amendment No. 134

Control Rod OPERABILITY 3.1.3 I ACTIONS (continued)

COMPLETION TIME CONDITION REQUIRED ACTION D. -

- NOTE .......- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Not ap)licable when with the prescribed THERMA. POWER withdrawal sequence.

> 10% RTP.

...................... g One or more inoperable D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months control rods not in to OPERABLE status.

compliance with the prescribed withdrawal sequence.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A.

C. or D not met.

/~')

k/ Nine or more control rods inoperable.

l l

I I

)

,)

i t

FERMI UNIT 2 3.1 9 Amendment No. 134 i

I l

Control Rod OPERABILITY 3.1.3 Il y/

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 - - - -- - NOTE - - -- - -- --

Not required to be performed until 7 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of RWM.

Insert each fully withdrawn control rod at 7 days least one notch.

SR 3.1.3.3 - - ----- -

NOTE -- - - -- --

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of t

c the RWM.

's ...........................................

Insert each partially withdrawn control rod 31 days at least one notch.

SR 3.1.3.4 Verify each control rod scram time from In accordance fully withdrawn to notch position 06 is with s 7 seconds. SR 3.1.4.1.

SR 3.1.4.2.

SR 3.1.4.3. and SR 3.1.4.4 (continued)

FERMI UNIT 2 3.1 10 Amendment No. 134

Control Rod OPERABILITY 3.1.3 O' SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I 5R 3.1.3.5 Verify each control rod does not go to the Each time the withdrawn overtravel position. control rod is withdrawn to

" full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling O

i l

i I

1 I

i O l I

FERMI UNIT 2 3.1 11 Amendment No. 134

Control Rod Scram Times l 3.1.4 i 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 13 OPERABLE control rods shall be "sidw "

in accordance with Table 3.1.4 1: and

b. No more than 2 OPERABLE control rods that are " slow" shall occupy adjacent locations.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LC0 not met.

(3 LJ SURVEILLANCE REQUIREMENTS

..................................... NOTE --- - -- ----- ---- - -- --- -

During single control rod scram time Surveillances. the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is Prior to within the limits of Table 3.1.41 with exceeding reactor steam dome pressure a 800 psig. 40% RTP after each reactor shutdown

> 120 days (continued) )

FERMI UNIT 2 3.1 12 Amendment No. 134

Control Rod Scram Times 3.1.4 SURVEILLANCE REWIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify. for a representative sample, each 120 days -

tested control rod scram time is within the cumulative limits of Table 3.1.41 with reactor steam - operation in dome pressure = 800 psig. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor-steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time 3.1.4.4 Verify each affected control rod scram time Prior to O ' SR is within the limits of Table 3.1.4-1 with reactor steam dome pressure = 800 psig.

exceeding 40% RTP after fuel movement within the associated core l cell l AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time O

FERMI UNIT 2 3.1 13 Amendment No. 134 t

Control Rod Scram Times 3.1.4 h" Table 3.1.41 (page 1 of 1)

Control Rod Scram Times

.....................................yoyg5....................................

1. OPERABLE control rods with scram times not within the limits of this Table are considered " slow." -

2. Enter applicable Conditions and Required Actions of LCO 3.1.3. " Control Rod OPERABILITY." for control rods with scram times > 7 seconds to notch position 06. These control rods are inoperable, in accordance with SR 3.1.3.4. and are not considered " slow.

SCRAMTIMESwhenREACTORSTEApag NOTCH POSITION PRESSURE = 800 psig (seconds) 46 0.457 36 1.084 26 1.841 O 06 V 3.361 (a) Maximum scram time from fully withdrawn position, based on de.energization of scram pilot valve solenoids at time zero.

(b) When reactor steam dome pressure is < 800 psig established scram time limits apply.

FERMI . UNIT 2 3.1 14 Amendment No. 134 1 I

l

Control Rod Scram Accumulators i 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5' Each control' rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

..................................... NOTE- - <-- ------ - - -- - --- --- - --

Separate Condition entry is allowed for each control. rod scram accumulator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 -- .- --NOTE.-- --- -

accumulator inoperable Only applicable if with reactor steam the associated O dome pressure

= 900 psig.

control rod scram time was within the limits of Table 3.1.4 1 during the last scram time Surveillance.

Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control rod scram time

" slow."

A.2 Declare the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated control

-rod inoperable.

)

(continued)

O FERMI UNIT 2 3.1 15 Amendment No. 134 l

)

Control Rod Scram Accumulators 3.1.5

)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

B. Two or more control B.1 Restore charging 20 minutes from rod scram accumulators water header pressure discovery of inoperable with to a 940 psig. Condition B reactor steam dome concurrent with pressure = 900 psig. charging water header pressure

< 940 psig 8h!Q B.2.1 ------- NOTE --------

Only applicable if the associated control rod scram time was within the limits of Table 3.1.4 1 during the last scram time Surveillance.

Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control ,

rod scram time l

" slow." j 1

B.2.2 Declare the I hour associated control rod inoperable.

(continued)

O l 1

FERMI - UNIT 2 3.1 16 Amendment No. 134

I Control Rod Scram Accumulators 3.1.5 i

j ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control C.1 Verify all control Immediately'upon

, rod scram accumulators rods associated with discovery of

! inoperable with inoperable charging water reactor steam dome accumulators are header pressure l pressure < 900 psig. fully inserted. < 940 psig AND C.2 Declare the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated control rod inoperable.

D. Required Action and D.1 ---

NOTE ---- -

associated Completion Not applicable if all Time of Required inoperable control Action B.1 or C.1 not rod scram met. accumulators are associated with fully

[] inserted control rods.

Place the reactor Immediately mode switch in the shutdown position.

SURVEILLANCE REQUIREMENTS I SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is a 940 psig.

i O

FERMI - UNIT 2 3.1 17 Amendment No. 134 l

l

r-l Rod Pattern Control 3.1.6 i

l h? 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control I

LC0 3.1.6 OPERABLE control rods shall comply with the requirements of I the prescribed withdrawal sequence.

APPLICABILITY: MODES 1 and 2 with THERMAL POWER s 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more OPERABLE A.1 ---

---NOTE---------

control rods not in Rod worth minimizer compliance with the (RWM) may be bypassed prescribed withdrawal as allowed by sequence. LC0 3.3.2.1, " Control Rod Block n Instrumentation."

Move associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod (s) to correct position.

E A.2 Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod (s) inoperable.

(continued) o ;

. FERMI UNIT 2 3.1-18 Amendment No. 134 l

l L

i Rod Pattern Control j 3.1.6 l l 't ACTIONS (continued) I R,j' :

CONDITION REQUIRED ACTION COMPLETION TIME I

B. Nine or more OPERABLE B.1 -

--- -NOTE-- ---

l control rods not in Rod worth minimizer '

compliance with the (RWM) may be bypassed prescribed withdrawal as allowed by s sequence. LC0 3.3.2.1.

Ruspend withdrawal of Immediately control rods.

1 AND B.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

(~) SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with the prescribed withdrawal sequence.

()g

/

FERMI - UNIT 2 3.1-19 Amendment No. 134

SLC System 3.1.7

(~J v

3.1 . REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LC0 3.1.7 Two SLC subsystems shall be OPERABLE.

~

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable. to OPERABLE status.

B. Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. subsystem to OPERABLE

.j status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. .

I

)

O FERMI - UNIT 2 3.1 20 Amendment No. 134

SLC System 3.1.7 O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pentaborate solution is within the limits of Figure 3.~ .7-1.

SR 3.1.7.2 Verify temperature of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is = 48'F.

I SR 3.1.7.3 Verify temperature of pump suction piping 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is = 48'F.

SR 3.1.7.4 Verify continuity of explosive charge. 31 days O SR 3.1.7.5 Verify the concentration of boron in 31 days solution is within the limits of Figure 3.1.7 1. AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored a 48*F (continued) !

FERMI - UNIT 2 3.1-21 Amendment No. 134

I SLC System 3.1.7 O suavetu^~ce acouineaeaTs <coet4""ed)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual valve in 31 days '

the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify each pump develops a flow rate In accordance

= 41.2 gpm at a discharge pressure with the

= 1215 psig. Inservice Testing Program l

SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS O SR 3.1.7.9 Verify all piping between storage tank and 18 months explosive valve is unblocked.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored e 48 F SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to a 65 atom percent B-10. addition to SLC tank

_O l l

FERMI UNIT 2 3.1-22 Amendment No. 134 I

O 15 -

I O

i h a

is s

II*E!

g i

El ws

=

5 x

8 $

u a

lN - l- $

lt 1

I_

I$E . t B[' -

/

l5 y<

~

)

O' -

ei!

IlB z~ -

ec

>w Ell

~

'N i 5

~

/ ll-l gr e

3 E3 8E L*

IE

~ g8 g$

I ;

I.*g I I meiam As NOuMMIDNOD EWOWm3d nocOS MEDWEd FERMI UNIT 2 3.1 23 Amenament No. 134

SDV Vent and Drain Valves 3.1.8 h 3.1. REACTIVITY CONTROL SYSTEMS 3.1.8 . Scram Discharge Volume (SDV) Vent and Drain Valves LC0 3.1.8 Each SDV vent and drain valve shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

..................................... NOTE - ---- -- --------- ---- ----- -

Separate Condition entry is allowed for each SDV vent and drain line.

1 CONDITION REQUIRED ACTION COMPLETION TIME

' A. One or more SDV vent A.1 Restore valve to 7 days or drain lines with OPERABLE status.

one valve inoperable.

O B. One or more SDV vent B.1 -

NOTE---- - -

or drain lines with An isolated line may both valves be unisolated under inoperable. administrative control to allow draining and venting of the SDV.

Isolate the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated line.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met..

i i

FERMI - UNIT 2 3.1 24 Amendment No. 134

SDV Vent and Drain Valves 3.1.8 o

SURVEILLANCE REQUIREMENTS

!]

SURVEILLANCE FREQUENCY SR 3.1.8.1 ---NOTE-- ---- -- --

Not required to be met on vent and drain valves closed intermittently for testing under administrative control.

Verify each SDV vent and drain valve is 31 days open.

SR 3.1.8.2 Verify each SDV vent and drain valve: 18 months

a. Closes in s 30 seconds after receipt of an actual or simulated scram l signal: and !

b. Opens when the actual or simulated scram signal is reset.

O L,J i FERMI - UNIT 2 3.1 25 Amendment No. 134

APLHGR 3.2.1

( 3.2 POWER DISTRIBLITION LIMITS 3.2.1 AVERAGE PLANfR LINEAR HEAT GENERATION RATE (APLHGR)

LC0 3.2.1 All APLHGRs shall be less than or equal to the limits '

specified in the COLR.

APPLICABILITY: THERMAL POWER = 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits. within limits. ;

i I

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months o associated Completion to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after a 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter O

FERMI - UNIT 2 3.2-1 Amendment No. 134

MCPR ;

3.2.2

)

O 3.2 eowea ois>a18u11oa 'intTs !

3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LC0 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER = 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months !

limits. within limits.

i B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months p associated Completion to < 25% RTP.

V Time not met. j l

I

- \_./

FERMI UNIT 2 3.2 2 Amendment No. 134

i- . 1 MCPR 3.2.2 L

SURVEILLANCE REQUIREMENTS

. SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after l

= 251 RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.1 AND Once within i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after O- each completion of SR 3.1.4.2 8NQ Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.4 O

FERMI . UNIT 2 3.2 3 Amendment No. 134 l l

K 3 ..

LHGR 3.2.3 h 3.2. POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3- - All LHGRs shall be less than or equal to the limits

specified 'in the COLR.

APPLICABILITY: : THERMAL POWER = 25% RTP. I ACTIONS.

-CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limitst within limits.

1 B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to'< 25% RTP.

'O Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.SR. 3.2.3.1- . Verify all LHGRs are less than or equal to Once within the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

= 25% RTP

, ANQ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter 1

0 i

FERMI UNIT.2- 3.2 4 Amendment No. 134 l

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LC0 3.3.1.1- The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1 1.

ACTIONS

.....................................NTE----------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable. trip.

gg A.2 ---------NOTE--------

Not applicable for Functions 2.a. 2.b.

2.c. and 2.d.

Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

(continued)

A V

l FERMI UNIT 2 3.3 1 Amendment No. 134

RPS Instrumentation 3.3.1.1

'O actioas <ce#14##eo)

CONDITION REQUIRED ACTION COMPLETION TIME B. .

.......N0TE------ -

B.1 P1 ace channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months -

-Not applicable for trip system in trip.

Functions 2.a. 2.b.

2.c, and 2.d. IE One or more Functions in trip.

with one or more required channels inoperable in.both trip systems.

C. 'One or more Functions C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability.

capability not maintained.

O D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A. Table 3.3.1.1-1 for B, or C not met. the channel.

E. As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 30% RTP.

and referenced in Table 3.3.1.1 1.

F. As required by F.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in

. Table 3.3.1.1-1.

(continued)

O FERMI - UNIT 2 3.3 2 Amendment No. 134

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. As required by G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

Required Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by H.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Recuired Action D.1 steam lines.

anc referenced in Table 3.3.1.1-1. @

H.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I. As required by I.1 Initiate action to Immediately Required Action D.1 fully insert all 3 and referenced in insertable control Table 3.3.1.1-1. rods in core cells

] containing one or more fuel assemblies.

O FERMI UNIT 2 3.3 3 Amendment No. 134 i

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

{m')

..................................... NOTES-- ---- -- ------------------- -

l

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.1.3 ------------------NOTE ----- ----- ------

(A)

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER = 25% RTP.

Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power is s 2% RTP, while operating at = 25% RTP.

SR 3.3.1.1.4 ----- ----- -

NOTE ----------- ---

Not required to be performed when entering MODE 2 from MODE 1 until ;

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2. '

Perform CHANNEL FUNCTIONAL TEST. 7 days i SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. 7 days i

I (continued) g

.x FERMI - UNIT 2 3.3 4 Amendment No. 134

. r RPS Instrumentation 3.3.1.1 O suavetu^ ace acou'aeae"'s (ce"t4"#ed)

SURVEILLANCE FREQUENCY SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to fully intermediate range monitor (IRM) channels withdrawing overlap. SRMs from the core SR 3.3.1.1.7 ------- ------- --NOTE --------- -- ---

Only re uired to be met during entry into MODE 2 rom MODE 1.

Verify the IRM and APRM channels overlap. 7 days SR 3.3.1.1.8 Calibrate the local power range monitors. 1000 MWD /T average core exposure O

SR 3.3.1.1.9- Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.1.1;10 Verify the trip unit setpoint. 92 days

-SR 3.3.1.1.11 - - -- - - --

-NOTES -- -- - --

1. Neutron detectors are excluded.

2. . For Function 1.a not required to be performed when entering MODE 2 from ;

MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering '

MODE 2.

Perform CHANNEL CALIBRATION. 184 days .

l (continued)

O l FERMI' UNIT 2 3.3 5 Amendment No. 134

RPS Instrumentation 3.3.1.1 h SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.12 - ---- ------ - NOTE - --- -- - - -- -

For Function 2.a. not required to be

Herformed when entering MODE 2 from

,100E 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.1.1.13 Perform CHANNEL FUNCTIONAL TEST. 18 months 1

SR 3.3.1.1.14 Perform CHANNEL CALIBRATION. 18 months

( .SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and 18 months Turbine Control Valve Fast Closure Functions are not bypassed when THERMAL POWER is a 30t RTP.

1 (continued) 1 FERMI UNIT 2 3.3-6 Amendment No. 134 l

i i

RPS Instrumentation 3.3.1.1

'( SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.17 --

---- ---NOTES --- --- -- - -

)

1. Neutron detectors are excluded.

2. For Functions 3 and 4 channel sensor response times are not required to be measured.

3. For Function 5 "n" equals 4 channels for the purpose of determining the {

STAGGERED TEST BASIS Frequency. j Verify the RPS RESPONSE TIME is within 18 months on a limits. STAGGERED TEST BASIS SR 3.3.1.1.18 - ------ ----

---NOTE-------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.19 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

('

(_)s FERMI UNIT 2 3.3 7 Amendment No. 134

RPS Instrumentation 3.3.1.1 A)/

r\, Table 3.3.1.1 1 (page 1 of 3)

Reactor Protection System Instrtmentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM .

l SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREENTS VALUE

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 G SR 3.3.1.1.1 s 122/125 SR 3.3.1.1.4 divisions of SR 3.3.1.1.6 full scale SR 3.3.1.1.7 SR 3.3.1.1.11 J SR 3.3.1.1.15 5(a) 3 I SR 3.3.1.1.1 s 122/125 i SR 3.3.1.1.5 divisions of i SR 3.3.1.1.11 full scale i SR 3.3.1.1.15 l

b. Inop 2 3 G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) 3 I SR 3.3.1.1.5 NA !

SR 3.3.1.1.15 1

2. Average Power Range

. Monitors

a. Neutron Flux - Upscale 2 3(C) G SR 3.3.1.1.2 s 20% RTP (g (Setdown) SR 3.3.1.1.7 t 4 SR 3.3.1.1.8 V .

SR 3.3.1.1.12 SR 3.3.1.1.18

b. Simulated Thermal 1 3(c) F SR 3.3.1.1.2 s 0.63 (W aW)

Power - Upscale SR 3.3.1.1.3 + 64.31 RTP SR 3.3.1.1.8 and s SR 3.3.1.1.12 RTP(b)115.51 SR 3.3.1.1.18 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies. l (b) 4W = 83 when reset for single loop operation per LCO 3.4.1, " Recirculation Loops Operating."

Otherwise 4W = 08.

(c) Each APRM channel provides inputs to both trip systems.

O V

FERMI UNIT 2 3.3 8 Amendment No. 134 I

!I RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (page 2 of 3)

Reactor Protection System Instrtmentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED StRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE I

2. Average Power Range i Monitors (continued)

c. Neutron 1 3(C) F SR 3.3.1.1.2 s 1201 RTP Flux - Upscale SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.12 SR 3.3.1.1.18 i

d. Inc3 1.2 3(C) G SR 3.3.1.1.12 NA

e. 2-out of 4 Voter 1.2 2 G SR 3.3.1.1.2 NA SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.19

3. Reactor Vessel Steam 1.2 2 G SR 3.3.1.1.1 s 1113 psig Dome Pressure - High SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17

4. Reactor Vessel Water 1.2 2 G SR 3.3.1.1.1 = 171.9 inches A Level - Low. Level 3 SR 3.3.1.1.9 l

(/ ) SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17

5. Main Steam Isolation 1 8 F SR 3.3.1.1.9 s 122 closed Valve - Closure SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17

6. Main Steam Line 1.2 2 H SR 3.3.1.1.1 s 3.6 X full Radiation - High SR 3.3.1.1.9 power SR 3.3.1.1.14 background SR 3.3.1.1.15

7. Drywell Pressure - High 1.2 2 G SR 3.3.1.1.1 s 1.88 psig SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 (continued)

(c) Each APRM channel provides inputs to both trip systems, i

I O

FERMI - UNIT 2 3.3-9 Amendment No. 134

RPS Instrumentation 3.3.1.1 Table 3.3.1.11 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM .

SPECIFIED PER TRIP REQUIRED StRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREENTS VALUE

8. Scram Discharge Volume Water Level-High

a. Level 1.2 2 G SR 3.3.1.1.1 s 596 ft.

Transmitter SR 3.3.1.1.9 0 inches SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15 5(a) 2 I SR 3.3.1.1.1 s 596 ft.

SR 3.3.1.1.9 0 inches SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.15

b. Float Switch 1.2 2 G SR 3.3.1.1.9 s 596 ft.

SR 3.3.1.1.14 0 inches SR 3.3.1.1.15 5(a) 2 I SR 3.3.1.1.9 s 596 ft.

SR 3.3.1.1.14 0 inches SR 3.3.1.1.15

9. Turbine Stop a 301 RTP 4 E SR 3.3.1.1.9 s 71 closed Valve - Closure SR 3.3.1.1.14 f.- SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

10. Turbine Control Valve a 301 RTP 2 E SR 3.3.1.1.9 NA Fast Closure SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17

11. Reactor Mode Switch- 1.2 2 G SR 3.3.4.1.13 NA Shutdown Position SR 3.3.1.1.15 5(a) 2 I SR 3.3.1.1.13 NA SR 3.3.1.1.15

12. Manual Scram 1.2 2 G SR 3.3.1.1.5 NA SR 3.3.1.1.15 5(a) 2 1 SR 3.3.1.1.5 NA SR 3.3.1.1.15

.(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

[

\

FERMI - UNIT 2 3.3 10 Amendment No. 134

SRM Instrumentation 3.3.1.2 0 3.3 INSTRUMENT ^TIO" 3.3.1.2 Source Range Monitor (SRM) Instrumentation 1

LCO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

i APPLICABILITY: According to Table 3.3.1.2 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

A. One or more required A.1 Restore required SRMs 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRMs inoperable in to OPERABLE status.

MODE 2 with i intermediate range '

monitors (IRMs) on Range 2 or below, p

b B. Three required SRMs B.1 Sus)end control rod Immediately inoperable in MODE 2 wit 1drawal.

with IRMs on Range 2 or below.

i l

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i associated Completion i Time of Condition A or B not met.

(continued) i

.p, (j-FERMI UNIT 2 3.3 11 Amendment No. 134 L

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all I hour SRMs inoperable in insertable control MODE 3 or 4. rods.

AND D.2 Place reactor mode I hour switch in the shutdown position.

E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5. for control rod insertion.

ANQ E.2 Initiate action to Immediately fully insert all O~ insertable control rods in core cells containing one or more fuel assemblies.

O FERMI UNIT 2 3.3 12 Amendment No. 134

SRM Instrumentation 3.3.1.2 O suaveit'aace atouiarac Ts

...................................-. NOTE .....--- --- - .- ------ -- -

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2.2 --- --- -- -

- NOTES -- - - - ---

1. Only required to be met during CORE l ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months located in:

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region: and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

O FERMI UNIT 2 3.3 13 Amendment No. 134

. n. _ - - _ - - _ _

1 SRM Instrumentation 3.3.1.2

/ SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.3.1.2.4 -- -- ----

NOTE- -- - .--. -- -.-- l Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE

a. = 3.0 cps: or ALTERATIONS

b. = 0.7 cps when signal-to noise ratio AND is = 20:1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.2.5 ------- -- -

--NOTE- - ------ - - ---

Signal-to noise ratio not required to be determined when SRM count rate is O = 3.0 cps Perform CHANNEL FUNCTIONAL TEST and 7 days determination of signal-to noise ratio.

SR 3.3.1.2.6 ---- - - - -

--NOTES -- - - -- - ---

1. Signal-to noise ratio not required to be determined when SRM count rate is

= 3.0 cps

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to-noise ratio.

(continued)

O FERMI UNIT 2 3.3-14 Amendment No. 134

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.7 - - ---

- NOTES - -- - - ------- '

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. 18 months O

FERMI UNIT 2 3.3 15 Amendment No. 134

SRM Instrumentation 3.3.1.2 Table 3.3.1.2 1 ( ge 1 of 1)

/ Source Range Monitor Instrumentation APPLICABLE MODES OR OTER REQUIRED SLRVEILLANCE FUNCTION SPECIFIED CONDITIONS CMNNELS REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1,2.7 5 2(b)(c) SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 (a) With IRMs on Range 2 or below.

(b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector.

(c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

l l

t I

l i

l

(

FERMI UNIT 2 3.3-16 Amendment No. 134

ControlRodBlockInstrum$tation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation

-LC0 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.11.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (RBM) channel to OPERABLE status, inoperable.

B. Required Action and B.1 Place one RBM channel I hour

n associated Completion in trip.

Time of Condition A not met.

M Two RBM channels inoperable.

l C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor scram.

startup.

2 (continued)

(

, V) !

FERMI - UNIT 2 3.3-17 Amendment No. 134

Control Rod Block Instrumentation 3.3.2.1 ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.1 Verify = 12 rods Immediately-withdrawn.

.QB C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable has not been performed in the current calendar year.

AND C.2.2 Verify movement of During control control rods is in rod movement compliance with the prescribed withdrawal sequence by a second O. licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control reactor shutdown. control rods is in rod movement accordance with the prescribed withdrawal sequence by a second licensed operator or other qualified member of the technical staff.

(continued)

O FERMI UNIT 2 3.3 18 Amendment No. 134

Control Rod Block Instrumentation I 3.3.2.1-ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Reactor E.1 Sus and control rod Immediately-Mode Switch-Shutdown wit 1drawal.

Position channels-inoperable. Mil l

l E.2 Initiate action to Immediately fully insert all i insertable control rods in core cells j l containing one or more fuel assemblies.

I SURVEILLANCE REQUIREMENTS

.....................................N0TES - - --- -- - - - - --------

.1. - Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances entry into associated Conditions i and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the '

associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY l

SR 3.3.2.1.1 - ---

NOTE ----- ----- -- --

Not required to be performed until I hour after any control rod is withdrawn at s 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days (continued)

O FERMI UNIT 2 3.3-19 Amendment No. 134 l

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.2 -- ----- - - NOTE- - --- - -- - - -

j Not required to be performed until I bour after THERMAL POWER is s 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days i

SR 3.3.2.1.3 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.1.4 -- - ----- ----NOTE - - -- - --------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.2.1.5 Verify the RBM is not bypassed when 24 months THERMAL POWER is = 30% RTP.

SR 3.3.2.1.6 -- --

---.-------NOTE --- ----- - .--

Neutron detectors are excluded.

I Perform CHANNEL CALIBRATION. 24 months j l

SR 3.3.2.1.7 Verify control rod sequences input to the Prior to RWM are in conformance with the declaring RWM prescribed withdrawal sequence. OPERABLE following loading of sequence into RWM O

FERMI UNIT 2 3.3 20 Amendment No. 134 I l

l i

l Control Rod Block Instrumentation 3.3.2.1 8

Table 3.3.2.1 1 (page 1 of 1)

Control Rod Block Instrimentation APPLICABLE MODES OR

OTER SPECIFIED REQUIRED SLRVEILLANCE ALLOWABLE RmCTION COWITIONS CHANNELS REQUIREENTS VALUE

1. Rod Block Monitor

a. Upscale (a) 2 SR 3.3.2.1.3 As specified in SR 3.3.2.1.5 the COLR SR .3.3.2.1.6

b. Inop. (a) 2 SR 3.3.2.1.3 NA

c. Downscale (a) 2 SR 3.3.2.1.3 As specified in SR 3.3.2.1.6 the COLR

2. Rod Worth Minimizer 1(b) 2(b)

. 1 SR 3.3.2.1.1 NA SR 3.3.2.1.2 SR 3.3.2.1.7

3. Reactor Mode Switch - Shutdown (c) 2 SR 3.3.2.1.4 NA Position O (a) THERMAL POWER = 302 RTP.

.(b) With TERMAL POWER s 101 RTP.

(c) Reactor mode switch in the shutdown position.

O FERMI - UNIT 2 3.3-21 Amendment No. 134

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LC0 3.3.2.2 Four channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER a: 25% RTP.

ACTIONS

.....................................N0TE --- --

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more fL Jwater A.1 Place channel in 7 days and main turbine high trip.

water level trip O-channel (s) inoperable.

I B. Feedwater and main B.1 Restore feedwater and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months turbine high water main turbine high level trip capability water level trip not maintained. capability.

C. Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

I I

i O

FERMI - UNIT 2 3.3 22 Amendment No. 134

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2

( SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The 18 months Allowable Value shall be 5 219 inches.

SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including valve actuation.

i l

4 l

(3 '

V FERMI UNIT 2 3.3 23 Amendment No. 134

PAM Instrumentation 3.3.3.1 O 3.3 INSTRUMENTATION V

3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LC0 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1 1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

.................................- - NOTES - ---- ---- --- --- --- -- - --

1. LC0 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE G

V channel inoperable. status. 4 l

i B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.7.

not met.

C. ----- - NOTE- ------- C.1 Restore one required 7 days l Not applicable to channel to OPERABLE i 3rimary containment status.

lydrogen and primary j containment oxygen 4 concentration channels.

One or more Functions with two required channels inoperable.

g(3 (continued)

FERMI UNIT 2 3.3-24 Amendment No. 134

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required primary D.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months containment hydrogen primary containment concentration channels hydrogen inoperable. concentration channel to OPERABLE status.

E AND Two required primary containment oxygen D.2 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months concentration channels primary containment inoperable. Oxygen concentration channel to OPERABLE status.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3.1-1 for f or D not met. the channel.

(

F. As required by F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action E.1 and referenced in Table 3.3.3.1 1.

G. As required by G.1 Initiate action in Immediately Required Action E.1 accordance with and referenced in Specification 5.6.7.

Table 3.3.3.1-1.

O FERMI - UNIT 2 3.3-25 Amendment No. 134

PAM Instrumentation 3.3.3.1 r

( SURVEILLANCE REQUIREMENTS

- - - -- ----- -- ---~~~--

...................................- NOTE----

These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days I

SR 3.3.3.1.2 --- -.---- -

- NOTES - --- ---- -- -

1. Only applicable to Functions 7 and 8.

2. Not required to be performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for one channel and 7 days for the second channel after a 15% RTP.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.3.1.3 -- - -

--- NOTES------ -- ----- -

1. Not applicable to Functions 7 and 8.

2. Radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months O

l FERMI UNIT 2 3.3 26 Amendment No. 134

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FRON REQUIRED FUNCTION- CHANNELS ACTION E.1

1. Reactor Vessel Pressure 2 F

2. Reactor Vessel Water Level - Fuel Zone 2 F

3. Reactor Vessel Water Level - Wide Range 2 F

4. Suppression Pool Water Level 2 F

5. Suppression Pool Water Temperature 2 F

6. Drywell Pressure Wide Range 2 F

7. Primary Containment 0, Concentration 2 F

8. Primary Containment H, Concentration 2 F

9. Primary Containment High Range Radiation Monitor 2 G

10. PCIV Position 2g tgtg F (a) Not required for itolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve closed manual valve. blind flange. or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

O FERMI UNIT 2 3.3 27 Amendment No. 134

Remote Shutdown System 3.3.3.2

-O L)- 3.3 INSTRUMENTATION

)

3.3.3.2 Remote Shutdown System LC0 3.3.3.2 The Division I Remote Shutdown System Functions in Table 3.3.3.2 1 shall be OPERABLE. .,

APPLICABILITY: MODES 1 and 2.

ACTIONS

.................................... NOTES------

1. LC0 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each function.

CONDITIOd REQUIRED ACTION COMPLETION TIME O

O 'A. One or more required functions inoperable.

A.1 Restore required 30 days function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

l p

(_)

l FERMI- UNIT 2 3.3 28 Amendment No. 134 J

l

4 Remote Shutdown System 3.3.3.2 l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel.

SR 3.3.3.2.2 Verify each required control circuit and 18 months transfer switch is capable of performing the intended-function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 18 months required _ instrumentation channel.

O O

FERMI - UNIT 2 3.3-29 Amendment No. 134

'\.

Remote Shutdown System 3.3.3.2 Table 3.3.3.2 1 (page 1 of 1)

Remote Shutdown System Instrumentation INSTRUMENT FUNCTION

1. Reactor Vessel Pressure

2. Reactor Vessel Water Level

3. Suppression Chamber Water Temperature

4. Drywell Pressure

5. RHR Heat Exchanger Discharge Flow

6. RCIC Flow CONTROL FUNCTION

1. Control Rod Drive Pump A

2. Control Rod Drive Pump B

3. RHR Valve E1150-F009

4. RHR Valve E1150-F008

5. RHR Valve E1150-F006A O

V

6. Recirc Pump A Valve B3105-F023A

7. Main Steam Line (D) Relief Valve B2104 F013A

8. Main Steam Line (C) Relief Valve B2104 F0138

9. RHR Valve E1150 F015A

10. RHR Valve E1150 F017A

11. RHR Valve E1150 F004A

12. RHR Pump A

13. RHR Valve E1150 F024A

14. RHR Valve E1150-F028A

15. RHR Valve E1150 F048A

16. RHR Valve E1150 F068A

17. RHR Service Water Pump A

18. RHR Service Water Pump C

19. Cooling Tower Fan A

20. Cooling Tower Fan C

21. RCIC Valve E5150-F059

22. RCIC Valve E5150 F045

23. RCIC Initiate

24. Division II DC Transfer

25. B0P Transfer

26. Division I DC Transfer

27. Division I AC Transfer

28. Swing Bus Transfer I (3

NY.

l FERM1 UNIT 2 3.3 30 Amendment No. 134

ATWS-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS RPT) Instrumentation LC0 3.3.4.1 Two channels per trip system for each ATWS RPT 1 instrumentation Function listed below shall be OPERABLE: j

)

a. Reactcr Vessel Water Level-Low Low. Level 2: and

b. Reactor Vessel Pressure-High.

l APPLICABILITY: MODE 1. l ACTIONS

.....................................N0TE - ----- - - -- - ------ - - -- - l Separate Condition entry is allowed for each channel. l CONDITION REQUIRED ACTION' COMPLETION TIME l

A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

2 A.2 -------NOTE- -- -- -

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 14 days trip.

(continued)

C)

't FERMI UNIT 2 3.3 31 Amendment No. 134

ATWS RPT Instrumentation 3.3.4.1 w

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B, One Function with B.1 Restore ATWS RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months -

AlWS RPT trip capability.

capability not maintained.

C. Both Functions with C.1 Restore AlWS RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS RPT trip capability for one capability not Function.

maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump Time not met. from service.

D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months o

V FERMI - UNIT 2 3.3-32 Amendment No. 134

I ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

.....................................N0TE.............................-.......

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided the associated Function maintains ,

A1WS RPT trip capability. l

.............................................................................. l SURVEILLANCE FREQUENCY

{

SR 3.3.4.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1

SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days i

SR 3.3.4.1.3 Perform CHANNEL CALIBRATION. The 18 months Allcwable Values shall be-I

a. Reactor Vessel Water Level-Low Low, I Level 2: a 103.8 inches; and

b. Reactor Vessel Pressure-High:

s 1153 psig.

1 SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including breaker actuation.

G U

FERMI UNIT 2 3.3 33 Amendment No. 134

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LC0 3.3.5.1 The ECCS instrumentation for each function in Table 3.3.5.11 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1 1.

ACTIONS

..................................... NOTE -- -- - --

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in r i Table 3.3.5.1 1 for s the channel. ,

1 (continued)

O FERMI UNIT 2 3.3-34 Amendment No. 134 1

l l

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPI.ETION TIME B. As required by B.1 - - --- NOTES - - - -

Required Action A.1 1. Only applicable !

and referenced in in MODES 1, 2. I Table 3.3.5.1-1. and 3. I

2. Only applicable for Functions 1.a. 1.b. 2.a.

2.b. 2.d and 2.g.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from feature (s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable. feature (s) in both divisions AND B.2 .........N0Te........

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable, initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

(continued) l

)

O V i 1

FERMI ' UNIT 2 3.3 35 Amendment No. 134

ECCS Instrumentation 3.3.5.1 (3 ACTIONS (continued)

(/

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by C.1 - - NOTES- --- -

Required Action A.1 1. Only applicable and referenced in in MODES 1, 2.

Table 3.3.5.1 1. and 3.

2. Only applicable for Functions 1.c, 2.c. 2.e, ,

and 2.f.

Declare supported I hour from feature (s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable, feature (s) in both divisions )

AND C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued) 4 O

FERMI UNIT 2 3.3-36 Amendment No. 134

ECCS Instrumentation 3.3.5.1 1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 - --- NOTE - ---- -

Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1. not aligned to the suppression pool.

)

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of HPCI initiation capability AN_Q D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

2 D 2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

/ suction to the suppression pool.

(continued) i l

l l

V'O FERMI UNIT 2 3.3 37 Amendment No. 134

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

. CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from' Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1 1. inoperable. initiation capability in both trip systems AND E.2 Place channel in 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from trip. discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable i AND 8 days I

(continued) p

()

FERMI - UNIT 2 3.3-38 Amendment No. 134

ECCS Instrumentation 3.3.5.1 i ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME l

l F. As required by F.1 - ---

NOTE- -- -

Required Action A.1 Only applicable for and referenced in Functions 4.c. 4.e.

Table 3.3.5.1 1. 4. f. 4.g. 5.c, 5.e.

5.f. and 5.g.

I Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from l inoperable. discovery of l loss of ADS

initiation I

capability in l both trip systems AND F.2 Restore channel to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status. discovery of inoperable channel

's concurrent with HPCI or RCIC inoperable AND 4 8 days i

G. Required Action and G.1 Declare associated Immediately associated Completion supported feature (s) l Time of Condition B. inoperable.

l C. D. E. or F not met.

l l

l fh) l FERMI UNIT 2 3.3 39 Amendment No. 134 l

ECCS Instrumentation 3.3.5.1 (m) SURVEILLANCE REQUIREMENTS

.................................... NOTES-- --------------- - --- - - ****

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function. ,

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 3.c: and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days d SR 3.3.5.1.3 Verify the trip unit setpoint. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.5.1.6 Perform CHANNEL FUNCTIONAL TEST. 18 months l r

1

()

,m FERMI - UNIT 2 3.3 40 Amendment No. 134

ECCS Instrumentation 3.3.5.1 O Table 3.3.5.1 1 (page 1 of 5)

Emergency Core Cooling system Instrimentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OROTER CHANNELS FROM SPECIFIED PER REQUIRED SLRVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Vessel Water 1.2.3. 4(b) B SR 3.3.5.1.1 a 24.8 inches Level - Low Low Low. SR 3.3.5.1.2 Level 1 4(a). 5(a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1.2.3 4(b) B SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Steam Dome 1.2.3 4 C SR 3.3.5.1.1 a 441 psig Pressure - Low SR 3.3.5.1.2 (Injection Permissive) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 4(a). 5(a) 4 B Sh 3.3.5.1.1 a 441 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

d. Manual Initiation 1.2.3. 2(C) C SR 3.3.5.1.6 NA 4(a). 5(a)

(continued)

(a) When associated subsystem (s) of LCO 3.5.2 are required to be OPERABLE.

(b) Also required to initiate the associated emergency diesel generator (EDG).

(c) Individual component controls.

FERMI - UNIT 2 3.3 41 Amendment No. 134 l l

ECCS Instrumentation 3.3.5.1 6

Table 3.3.5.1 1 (page 2 of 5)

Emergency Core Cooling System Instrumentation l

l l APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OROTER CHANNELS FROM .

SPECIFIED PER REQUIRED SlRVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water 1.2.3. 4 B SR 3.3.5.1.1 e 24.S inches Level - Low Low Low. SR 3.3.5.1.2 Level 1 4(a), $(a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1.2.3 4 B SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Steam Dome 1.2.3 4 C SR 3.3.5.1.1 m 441 psig Pressure - Low SR 3.3.5.1.2 (Injection Permissive) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 4(a), 5(a) 4 B SR 3.3.5.1.1 = 441 psig SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.4

( SR 3.3.5.1.5

d. Reactor Vessel Water 1.2,3 4 B SR 3.3.5.1.1 e 103.8 Level - Low Low. Level SR 3.3.5.1.2 inches 2 (Loop Select Logic) 4(a). 5(a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

e. Reactor Steam Dome 1.2.3. 4 C SR 3.3.5.1.1 m 886 psig Pressure - Low (Break SR 3.3.5.1.2 Detection Logic) 4(a)5(a) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

f. Riser Differential 1.2.3 4 C SR 3.3.5.1.1 s 0.927 psid Pressure - High (Break SR 3.3.5.1.2 Detection) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

g. Recirculation Pinp 1.2.3 4 per punp B SR 3.3.5.1.1 s 1.927 psid Differential SR 3.3.5.1.2 Pressore - High (Break SR 3.3.5.1.3 Detection) SR 3.3.5.1.4 SR 3.3.5.1.5

h. Manual Initiation 1.2.3 2(C) C SR 3.3.5.1.6 NA 4(a). 5(a)

(continued) j (a) When associated subsystem (s) of LCO 3.5.2 are required to be OPERABLE.

(c)- Individual conponent controls.

FERMI - UNIT 2 3.3 42 Amendment No. 134 l

i l

ECCS Instrumentation 3.3.5.1 s

Table 3.3.5.1 1 (page 3 of 5)

Emergency Core Cooling System Instrunentation APPLICABLE CONDITIONS MODES OR REQUIRED PIFERENCED OTER CHANNELS FROM SPECIFIED PER REQUIRED SLRVEILLANCE ALLDWABLE CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE FUNCTION i

3. High Pressure Coolant l i

In,)ection OPCI) System

a. Reactor Vessel Water 1. 4 B SR 3.3.5.1.1 = 103.8 Level - Low Law. SR 3.3.5.1.2 inches Level 2 2(d), 3(d) SR 3.3.5.1.3 l SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1. 4 8 SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 2Id)3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Reactor Vessel Water 1. 2 C SR 3.3.5.1.1 s 219 inches Level - High. Level 8 SR 3.3.5.1.2 2(d). 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

d. Condensate Storage 1. 2 D SR 3.3.5.1.1 a 0 inches Tank Level - Low SR 3.3.5.1.2 2(d). 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 y SR 3.3.5.1.5

e. Suppression Pool Water 1. 2 D SR 3.3.5.1.1 s 5.0 inches Level - High SR 3.3.5.1.2 2(d), 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

f. Manual Initiation 1, 1(c) C SR 3.3.5.1.6 NA 2(d), 3(d)

(continued)

(c) Individual conponent controls.

(d) With reactor steam dome pressure > 150 psig.

t l

(d FERMI UNIT 2 3.3 43 Amendment No. 134

i

{

ECCS Instrumentation 3.3.5.1 e

/

Table 3.3.5.1 1 (page 4 of 5)

Emergency Core Cooling System Instr o entation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER REQ'JIRED SLRVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREENTS VALUE

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water 1, 2 E SR 3.3.5.1.1 = 24.8 inches Level - Low Low Low. SR 3.3.5.1.2 Level 1 2Id). 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1, 2 E SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 2Id). 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Automatic 1. 1 F SR 3.3.5.1.2 s 117 seconds Depressurization SR 3.3.5.1.4 System Initiation 2(d), 3(d) SR 3.3.5.1.5 {

Timer

d. Reactor Vessel Water 1. 1 E SR 3.3.5.1.1 = 171.9 Level - Low, Level 3 SR 3.3.5.1.2 inches (Confirmatory) 2(d)3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 N SR 3.3.5.1.5

e. Core Spray P mp 1. I per pinp F SR 3.3.5.1.1 = 125 psig Discharge SR 3.3.5.1.2 Pressure - High 2(d),3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

f. Low Pressure Coolant 1. 2 per pump F SR 3.3.5.1.1 = 115 psig Injection Puip SR 3.3.5.1.2 Discharge 2Id)3(d) SR 3.3.5.1.3 Pressure - High SR 3.3.5.1.4 SR 3.3.5.1.5

g. Drywell 1. 2 F SR 3.3.5.1.2 s 450 seconds Pressure - High Bypass SR 3.3.5.1.3 2(d), 3(d) SR 3.3.5.1.4 SR 3.3.5.1.5

h. Manual Inhibit 1. 1 F SR 3.3.5.1.5 NA 2(d), 3(d)

1. Manual Initiation 1. I r F SR 3.3.5.1.6 NA 2(d), 3(d)

(continued)

(d) With reactor steam dome pressure > 150 psig.

FERMI UNIT 2 3.3 44 Amendment No. 134

r ECCS Instrumentation 3.3.5.1

. Table 3.3.5.1 1 (page 5 of 5)

V Emergency Core Cooling System Instrisnentation l

l APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FRON SPECIFIED PER REQUIRED SlRVEILLANCE ALLOWABLE

' FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE I 5. ADS Trip System B

a. Reactor Vessel Water 1. 2 E SR 3.3.5.1.1 e 24.8 inches Level - Low Low Low. SR 3.3.5.1.2 Level 1 2(d), 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

b. Drywell 1, 2 E SR 3.3.5.1.1 s 1.88 psig Pressure - High SR 3.3.5.1.2 2(d). 3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

c. Automatic 1, 1 F SR 3.3.5.1.2 s 117 seconds Depressurization SR 3.3.5.1.4 System Initiation 2(d), 3(d) SR 3.3.5.1.5 Timer

d. Reactor Vessel Water 1. 1 E SR 3.3.5.1.1 e 171.9 Level- Low. Level 3 SR 3.3.5.1.2 inches (Confirmatory) 2(d),3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

e. Core Spray Ptap 1. 1 per pump F SR 3.3.5.1.1 = 125 psig Discharge SR 3.3.5.1.2 Pressure - High 2(d),3(d) SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5

f. Low Pressure Coolant 1. 2 per pimp F SR 3.3.5.1.1 e 115 psig Injection Ptap SR 3.3.5.1.2 Discharge 2(d), 3(d) SR 3.3.5.1.3 Pressure - High SR 3.3.5.1.4 SR 3.3.5.1.5

g. Drywell 1, 2 F SR 3.3.5.1.2 s 450 seconds Pressure - High Bypass SR 3.3.5.1.3 2(d),3(d) SR 3.3.5.1.4 SR 3.3.5.1.5

h. Manual Inhibit 1, 1 F SR 3.3.5.1.5 NA 2(d), 3(d)

1. Manual Initiation 1. I r F SR 3.3.5.1.6 NA va ve 2(d), 3(d)

(d) With reactor steam dome pressure > 150 psig.

, .vn FERMI UNIT 2 3.3-45 Amendment No. 134 l

RCIC System Instrumentation 3.3.5.2 I' 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LC0 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: MODE 1.

MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

.................................... NOTE- --

Separa37,gondj$jon 7ntry !s anoygd for eaSh ?hannel

)

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2 1 for the channel. I B. As required by B.1 Declare RCIC System I hour from Required Action A.1 inoperable. discovery of and referenced in loss of RCIC Table 3.3.5.2 1. initiation capability AND B.2 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

C. As required by C.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action A.1 OPERABLE status. I and referenced in Table 3.3.5.2 1.

(continued)

G

.N)

FERMI - UNIT 2 3.3 46 Amendment No. 134

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 - ----- NOTE----- ---

Required Action A.1 Only applicable if and referenced in RCIC p g suction is Table 3.3.5.2-1. not aligned to the suppression pool.

Declare RCIC System I hour from inoperable. discovery of loss of RCIC initiation capability 8NQ D.2.1 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip.

2 D.2.2 Align RCIC pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months o suction to the Q suppression pool.

E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.

Time of Condition B, C, or D not met.

O

' FERMI UNIT 2 3.3 47 Amendment No. 134 j l

l

RCIC System Instrumentation 3.3.5.2 O suavei uaace aeouineae#1s

.....................................N0TES...........

1. Refer to Table 3.3.5.2 1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required i Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Function 2:

. and (b) for up to_6 hours for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days b

.a SR 3.3.5.2.3 Verify the trip unit setpoint. 92 days SR 3.3.5.2.4 Per form CHANNEL CALIBRATION. 18 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.5.2.6 Perform CHANNEL FUNCTIONAL TEST. 18 months l

FERMI . UNIT 2 3.3 48 Amendment No. 134 ;

i

RCIC System Instrumentation 3.3.5.2 l

Table 3.3.5.2 1 (page 1 of 1) y Reactor Core Isolation Cooling System Instrunentation CONDITIONS REQUIRED StRVEILLANCE REFERENCED CHANNELS ALLOWABLE FROM REQUIRED REQUIREMENTS PER FUNCTION VALUE FUNCTION ACTION A.1

1. Reactor Vessel Water 4 B SR 3.3.5.2.1 e 103.8 inches Level - Low Low.. Level 2 SR 3.3.5.2.2 l SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5

2. Reactor Vessel Water 2 C SR 3.3.5.2.1 s 219 inches Level - High. Level 8 SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5

3. Condensate Storage Tank 2 D SR 3.3.5.2.1 a 0 inches Level - Low SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5

4. Manual Initiation 1 per valve C SR 3.3.5.2.6 NA O(%

1

(*)

%.)

FERMI - UNIT 2 3.3 49 Amendment No. 134 ,

l

Pri ary Containment Isolation Instrumentation 3.3.6.1 n

! 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LC0 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE. ,

I i

l APPLICABILITY: According to Table 3.3.6.1-1. I l

ACTIONS l

.................................... NOTE -- ---- --- - --------- ------ -

Separate Condition entry is allowed for each channel.

1 CONDITION REQUIRED ACTION COMPLETION TIME 1 A. One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. trip. Functions 1.f.

O' V

2.a. 2.c.

and 6.b MD )

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions

1. f. 2. a . 2. c.

and 6.b B. One or more automatic B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with capability.

isolation capability not maintained.

I (continued) l

]J FERMI UNIT 2 3.3 50 Amendment No. 134

)

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter the Condition Immediately- )

associated Completion referenced in l Time of Condition A Table 3.3.6.1-1 for 1 or B not met, the channel.

l I

D. As required by D.1 Isolate associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l Required Action C.1 main steam line and referenced in (MSL).

Table 3.3.6.1 1.

D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months O

E. As re uired by E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Recui ed Action C.1 anc referenced in Table 3.3.6.1-1.

F. As required by F.1 Isolate the affected I hour Recuired Action C.1 penetration flow anc referenced in path (s).

Table 3.3.6.1-1. {

G. As required by G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action C.1 penetration flow and referenced in path (s).

Table 3.3.6.1 1.

(continued) 1 FERMI - UNIT 2 3.3 51 Amendment No. 134

p Primary Containment Isolation Instrumentation 1 3.3.6.1 I O ac'ioas- (ce"t4 #ed)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by . H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

Required Action C.1 and referenced in atD Table 3.3.6.1-1.

H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E

Required Action and-associated Completion Time for Condition F or G not met.

I. As required by I.1 Declare associated I hour Required Action C.1 standby liquid and referenced in control subsystem Table 3.3.6.1-1. (SLC) inoperable.

E I.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System.

J. As required by J.1 Initiate action to Immediately Required Action C.1 restore channel to and referenced:in OPERABLE status.

Table 3.3.6.1-1. -

3 E )

J.2 Initiate action to Immediately isolate the Residual Heat Removal (RHR)

Shutdown Cooling System.

O FERMI UNIT 2 3.3 52 Amendment No. 134

Primary Containment Isolation Instrumentation 3.3.6.1 b)

G SURVEILLANCE REQUIREMENTS

..................................... NOTES-----------

1. Refer to Table 3.3.6.11 to determine which SRs apply --- for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to:

a. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Function 5.a when testing non redundant circuitry that results in loss of isolation capability associated with this Function, provided Functions 5.b. 5.c, and 5.e are OPERABLE:

b. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1. 2, 5 (other than non-redundant circuitry of 5.a). and 6, provided the associated Function maintains isolation capability; and

c. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for Functions 3 and 4. provided the associated Function maintains isolation capability.

1 SURVEILLANCE FREQUENCY (3

v' SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days i

l l

SR 3.3.6.1.3 Verify the trip unit setpoint. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months l

SR 3.3.6.1.6 Perform CHANNEL FUNCTIONAL TEST. 18 months n

(continued)

{}

FERMI UNIT 2 3.3-53 Amendment No. 134

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.7 -- - -

--- -NOTES -- - -- -----

1. Radiation detectors may be excluded.

2. Channel sensor response times are not required to be measured.

Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a is within limits. STAGGERED TEST BASIS

(

l O

FERMI UNIT 2 3.3 54 Amendment No. 134

[.

Primary Containment Isolation Instrumentation 3.3.6.1 (m

Nd

) Table 3.3.6.11 (page 1 of 4)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SLRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water 1.2.3 2 D SR 3.3.6.1.1 a 24.8 inches Level - Low Low Low. SR 3.3.6.1.2 Level 1 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

b. Main Steam Line 1 2 E SR 3.3.6.1.1 m 736 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

c. Main Steam Line 1.2.3 2 per D SR 3.3.6.1.1 s 118.4 psid Flow - High MSL SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7

d. Condenser 1. 2 D SR 3.3.6.1.1 s 7.05 psia Pressure - High SR 3.3.6.1.2 i g 2(a), 3(a) SR 3.3.6.1.3 V SR 3.3.6.1.4 SR 3.3.6.1.5 ;

e. Main Steam Tunnel 1.2.3 2 per D SR 3.3.6.1.1 s 206*F i Temperature - High trip SR 3.3.6.1.2 string SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

f. Main Steam Line 1.2.3 2 D SR 3.3.6.1.1 s 3.6 x full Radiation - High SR 3.3.6.1.2 power SR 3.3.6,1.4 background SR 3.3.6.1.5

g. Turbine Building Area 1.2.3 4 D SR 3.3.6.1.1 s 206*F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

h. Manual Initiation 1.2.3 1 r G SR 3.3.6.1.6 NA va e )

(continued)

(a) Except when bypassed during reactor shutdown or for reactor startup under adninistrative control.

%)

FERMI - UNIT 2 3.3-55 Amendment No. 134

Pricary Containment Isolation Instrumentation 3.3.6.1

-.m (y) Table 3.3.6.1 1 (psge 2 of 4)

Primary Containment Isol'. tion Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED StRVEILLANCE ALLOWABLE FUNCTION CONDITIOKS SYSTEM ACTION C.1 REQUIREENTS VALUE

2. Primary Containment Isolation

a. Reactor vessel Water 1.2.3 2 H SR 3.3.6.1.1 = 171.9 inches Level-Low. Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

b. Reactor Vessel Water 1.2.3 2 H SR 3.3.6.1.1 = 103.8 inches Level - Low. Level 2 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3,3.6.1.4 SR 3.3.6.1.5

c. Drywell Pressure - High 1.2.3 2 H SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

d. Manual Initiation 1.2.3 1 r G SR 3.3.6.1.6 NA va ve

3. High Pressure Coolant

(_/ Injection (WCI) System

. Isolation

a. HPCI Steam Line 1.2.3 1 F SR 3.3.6.1.1 s 410 inches Flow - High SR 3.3.6.1.2 of water with SR 3.3.6.1.3 time delay SR 3.3.6.1.4 e 1 second, and SR 3.3.6.1.5 s 5 seconds

b. WCI Steam Supply Line 1.2.3 2 F SR 3.3.6.1.1 a 90 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

c. HPCI Turbine 1.2.3 2 F SR 3.3.6.1.1 s 20 psig Exhaust Diaphragn SR 3.3.6.1.2 Pressure -High SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

d. HPCI Equipment Room 1.2.3 1 F SR 3.3.6.1.1 s 162'F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

e. Drpell Pressure - High 1.2.3 1 F SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

f. Manual Initiation 1.2.3 1 per G SR 3.3.6.1.6 NA valve

. (continued)

FERMI - UNIT 2 3.3 56 Amendment No. 134

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.11 (page 3 of 4)

(s Primary containment Isolation Instrumentation APPLICABLE CONDITIONS NODE $ OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SLRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line 1.2.3 1 F SR 3.3.6.1.1 s 95.0 inches Flow - High SR 3.3.6.1.2 of water with SR 3.3.6.1.3 time delay SR 3.3.6.1.4 = 1 second and SR 3.3.6.1.5 s 5 seconds

b. RCIC Steam Supply 1.2.3 2 F SR 3.3.6.1.1 m 53 psiD Line Pressure- Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

c. RCIC Turbine 1.2.3 2 F SR 3.3.6.1.1 s 20 psig Exhaust Diaphragm SR 3.3.6.1.2 Pressure - High SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

d. RCIC Equipment Room 1.2.3 1 F SR 3.3.6.1.1 s 162'F Tenperature - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

e. Dr)wil 1.2.3 1 F SR 3.3.6.1.1 s 1.88 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

f. Manual Initiation 1.2.3 1 per G SR 3.3.6.1.6 NA valve j l

(continued) l l

I l

i

[\

FERMI UNIT 2 3.3 57 Amendment No. 134

Prirary Containment Isolation Instrumentation 1 3.3.6.1 O Table 3.3.6.1 1 (page 4 of 4)

Primary Containment Isolation Instrtmentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SlRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREENTS VALUE 1

l l 5, Reactor Water Cleanup (RWCU) System Isolation

a. Differential 1,2,3 1 F SR 3.3.6.1.1 s 63.4 gpm Flow - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5

b. Area 1.2.3 1 per F SR 3.3.6.1.1 s 183'F Tenperature - High area SR 3.3.6.1.2 SR 3.3,6.1.4 SR 3.3.6.1.5

c. Area Ventilation 1.2.3 1 per F SR 3.3.6.1.1 s 53'F Differential room SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5

d. SLC System Initiation 1.2 2(b) I SR 3.3.6.1.5 NA

e. Reactor Vessel Water 1.2.3 2 F SR 3.3.6.1.1 a 103.8 inches Level - Low Low. SR 3.3.6.1.2 Level 2 SR 3.3,6.1.3 l SR 3.3.6.1.4

( SR 3.3.6.1.5

f. Manual Initiation 1.2.3 1 per G SR 3.3.6.1.6 NA valve

6. Shutdown Cooling System Isolation

a. Reactor Steam Dome 1.2.3 1 F SR 3.3.6.1.1 s 95.5 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

b. Reactor Vessel Water 3.4.5 2(c) J SR 3.3.6.1.1 a 171.9 inches Level - Low. Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.5

c. Manual Initiation 1.2.3 1 r G SR 3.3.6.1.6 NA va{ve (b) SLC System Initiation only inputs into one of the two trip systems.

(c) Only one trip system required in MODES 4 and 5 when RFR Shutdown Cooling System integrity maintained.

O FERMI UNIT 2 3.3 58 Amendment No. 134

Secondary Containment Isolation Instrumentation 3.3.6.2 1

0 3.3 ins >nuaeaTarioa 3.3.6.2 Secondary Containment Isolation Instrumentation LC0 3.3.6.2 The secondary containment isolation instrumentation for ech Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.2-1.

ACTIONS

..................................... NOTE------ ----------- ---------.------ -

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inoperable. trip. Function 2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Function 2 B. One or more automatic B.1 Restore secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with containment isolation secondary containment capability.

isolation capability not maintained.

(continued) ,

i 7N V_

FERMI - UNIT 2 3.3-59 Amendment No. 134

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1.1 Isolate the Secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months -

associated Completion Containment.

Time.

E C.1.2 Deciare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment isolation valves inoperable.

AND C.2.1 Place the associated I hour standby gas treatment (SGT) subsystem (s) in operation.

C.2.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months O SGT subsystem (s) inoperable.

1 l

l

.. -0 FERMI UNIT 2 3.3-60 Amendment No. 134

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

................................. NOTES-------- -- -------- --- - -- -

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment-Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3- Verify the trip unit setpoint. 92 days O

SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. 18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months I l

i FERMI - UNIT 2- 3.3 61 Amendment No. 134 i

I Secondary Containment Isolation Instrumentation 3.3.6.2 O, Table 3.3.6.2 1 (page 1 of 1)

Secondary Containment Isolation Instrtamentation APPLICABLE MODES OR REQUIRED OTER CHANNELS SPECIFIED PER SlRVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEN REQUIREENTS VALUE

1. Reactor Vessel Water 1.2.3. 2 SR 3.3.6.2.1 = 103.8 inches Level - Low Low. Level 2 (a) SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5

2. Drywell Pressure - High 1.2.3 2 SR 3.3.6.2.1 s 1.88 psig SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.5

3. Fuel Pool Ventilation 1.2.3 2 SR 3.3.6.2.1 s 6 nR/hr Exhaust Radiation-High (a),(b) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 4, Manual Initiation 1.2.3 1 SR 3.3.6.2.5 NA (a),(b)

(a) During operations with a potential for draining the reactor vessel.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in secondary containment.

(

FERMI UNIT 2 3.3 62 Amendment No. 134

LLS Instrumentation 3.3.6.3

3.3 INSTRUMENTATION.-

~

3.3.6.3 Low Low Set (LLS) Instrumentation LC0 3.3.6.3 The LLS valve instrumentation for each Function in Table 3.3.6.31 shall be OPERABLE.

APPLICABILITY:- MODES 1. 2.:and 3.

ACTIONS C0f0ITION REQUIRED ACTION COMPLETION TIME A. One LLS valve A.1 Restore channel (s) to 14 days inoperable due'to OPERABLE status, inoperable channel (s).

(continued) 4 O

' FERMI - UNIT 2 3.3 63 Amendment No. 134

i LLS Instrumentation '

3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. - -

NOTE - -

B.1 Restore one tailpipe 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months -

Separate Condition pressure switch for entry is allowed for 11 OPERABLE SRVs to each SRV. OPERABLE status.

AND l One or more safety /

relief valves (SRVs) B.2 Restore one tailpipe 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with one or more pressure switch in '

Function 3 channel (s) each Division for an 1 inoperable. OPERABLE SRV in the lowest setpoint group, to OPERABLE status.

AND

............N0TE- -- --

LCO 3.0.4 is not applicable.

B.3 Restore both tailpipe Prior to - l pressure switches for entering MODE 2 11 OPERABLE SRVs. or 3 from MODE 4 including 4 of 5 OPERABLE SRVs with the lowest relief setpoints, to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l

Two LLS valves inoperable due to inoperable channels. ,

I O

FERMI - UNIT 2 3.3 64 Amendment No. 134

LLS Instrumentation 3.3.6.3 n

Q SURVEILLANCE REQUIREMENTS

..................................... NOTE- . -

Refer to Table 3.3.6.3 1 to determine which SRs apply for each Function.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for 31 days portion of the channel outside primary containment.

SR 3.3.6.3.3 Perform CHANNEL CALIBRATION. 18 months

,SR 3.3.6.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months

]w G

V FERMI - UNIT 2 3.3-65 Amendment No. 134 l

I J

LLS Instrumentation 3.3.6.3 r-( Table 3.3.6.3 1 (page 1 of 1)

Lw Lw Set Instrunentation REQUIRED CHANNELS PER SLRVEILLANCE ALLOWABLE FUNCTION FUNCTION REQUIREENTS VALUE.

1. ' Reactor Steam Dome Pressure- High 1 per LLS valve SR 3.3.6.3.1 s 1113 psig SR 3.3.6.3.3 SR 3.3.6.3.4

2. Lw Lw Set Pressure Setpoints 2 per LLS valve SR 3.3.6.3.1 Lw:

SR 3.3.6.3.3 Open s 1037 psig SR 3.3.6.3.4 Close (a)

High:

Open s 1067 psig l Close (a)

3. Tailpipe Pressure Switch 2 per SRV SR 3.3.6.3.2 = 25 psig and SR 3.3.6.3.3 s 35 psig SR 3.3.6.3.4 (a) = 100 psi belw actual opening setpoint.

i

)

FERMI - UNIT 2 3.3 66 Amendment No. 134

i CREF System Instrumentation ]

3.3.7.1 '

3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrunientation LC0 3.3.7.1 The CREF System instrumentation for each Function in -

Table 3.3.7.1 1 shall be OPERABLE.

I APPLICABILITY: According to Table 3.3.7.1-1.

ACTIONS i

..................................... NOTE-- -- --- ----- - --------- --- --- -

-Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition Immediately channels inoperable. referenced in Table 3.3.7.1 1 for ON the channel.

B. As required by B.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Required Action A.1 CREF subsystem discovery of and referenced in inoperable. loss of CREF Table 3.3.7.1 1. initiation capability in both trip systems AND B.2 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months trip. ,

i l

(continued)

O FERMI UNIT;2 3.3-67 Amendment No. 134 ,

i

. 1 CREF System Instrumentation 3.3.7.1 ACTIONS (continued)

REQUIRED ACTION COMPLETION TIME CONDITION C. As required by C.1 Declare associated I hour from Required Action A.1 CREF subsystem discovery of and referenced in inoperable. loss of CREF Table 3.3.7.1 1. initiation capability in both trip systems AND C.2 Place channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months downscale trip.

D. Required Action and D.1 Place the CREF System Immediately associated Completion in the recirculation Time of Condition B mode of operation.

or C not met.

08 D.2 Declare associated Immediately CREF subsystem 3 inoperable. '

i l

l

[G FERMI UNIT 2 3.3-68 Amendment No. 134

CREF System Instrumentation 3.3.7.1

. SURVEILLANCE REQUIREMENTS

..................................... NOTES- --

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF Function.

2. For Functions 1, 2,. and 3. when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to

6. hours provided the associated Function maintains CREF initiation I capability.

I SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

SR '3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days

, ' SR 3.3.7.1.3 Perform CHANNEL FUNCTIONAL TEST. 92 days SR' 3.3.7.1.4 Verify the trip unit setpoint.- 92 days SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. 18 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months O I

-FERMI UNIT 2 3.3 69~ Amendment No. 134 i

CREF System Instrumentation 3.3.7.1 7m \

! Table 3.3.7.1 1 (page 1 of 1) '

\._) Control Room Emergency Filtration System Instrunentation l APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTER CHANNELS FROM SPECIFIED PER TRIP REQUIRED StRVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 1.2.3 (a) 2 B SR 3.3.7.1.1 e 103.8 inches Level - Low Low. SR 3.3.7.1.3 Level 2 SR 3.3.7.1.4 SR 3.3.7.1.5 SR 3.3.7.1.6 1

2. Drywell Pressure - High 1.2.3 2 B SR 3.3.7.1.1 s 1.88 psig SR 3.3.7.1.3 !

l SR 3.3.7.1.4 SR 3.3.7.1.5 SR 3.3.7.1.6

3. Fuel Pool Ventilation 1.2.3. 2 B SR 3.3.7.1.1 s 6 d/hr Exhaust SR 3.3.7.1.3 Radiation - High (a).(b) SR 3.3.7.1.5 SR 3.3.7.1.6

4. Control Center Normal 1.2.3. 1 C SR 3.3.7.1.1 s 5 d/hr Makeup Air SR 3.3.7.1.2 Radiation - High (a).(b) SR 3.3.7.1.5 I '

V<

(a) During operations with a potential for draining the reactor vessel.

(b) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the secondary containment.

/*\

V FERMI - UNIT 2 3.3 70 Amendment No. 134 .

l

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LC0 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

When the associated emergency diesel generator (EDG) is required to be OPERABLE by LCO 3.8.2. "AC Sources -Shutdown. "

ACTIONS

..................................... NOTE---- -- ------- -- - -- - --- ---

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more buses with A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one or more channels OPERABLE status, inoperable.

B. Required Action and B.1 Declare associated Immediately associated Completion EDG inoperable.

Time of Condition A not met.

M One or more buses with LOP trip capability not maintained.

O.t V

FERMI UNIT 2 3.3-71 Amendment No. 134

i LOP Instrumentation j 3.3.8.1 l i

O suave > uaace aeouineae 1s

.....................................N0TE--

Refer to Table 3.3.8.11 to determine which SRs apply for each LOP Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. 31 days i

l l SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. 18 months l

l SR 3.3.8.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months i

l l

1 i

l l

t

)

I

)

l l

.O FERMI UNIT 2 3.3 72 Amendment No. 134 I

r LOP Instrumentation 3.3.8.1 Table 3.3.8.1 1 (page 1 of 1)

Loss of Power Instrumentation REQUIRED CHANNELS SLRVEILLANCE FUNCTION PER SUS REQUIREENTS ALLDWA8LE VALUE

1. 4.16 kV Emergency Bus Undervoltage-(Loss of Voltage)

a. Bus Undervoltage 4 SR 3.3.8.1.1 (a)

SR 3.3.8.1.2 SR 3.3.8.1.3

b. Time Delay 4 SR 3.3.8.1.1 (b)

SR 3.3.8.1.2 SR 3.3.8.1.3

2. 4.16 kV Emergency Bus undervoltage (Degraded Voltage)

a. Bus Undervoltage 4 SR 3.3.8.1.1 (c)

SR 3.3.8.1.2 SR 3.3.8.1.3

b. Time Delay 4 SR 3.3.8.1.1 (d)

SR 3.3.8.1.2 SR 3.3.8.1.3 (a) Division I: = 2972.3 V and s 3093.7 V Divi: ion II: a 3016.4 V and a 3139.6 V (b) Division I: a 1.9 see and s 2.1 see Division II: = 1.9 see and a 2.1 see (c) Division I: a 3873.0 V and s 4031.0 V Division II: a 3628.0 V and s 3776.0 V (d) Division I: e 41.8 see and s 46.2 see

- Division II: a 20.33 sec and s 22.47 see i

i I

i FERMI - UNIT 2 3.3-73 Amendment No. 134

. 1 1

RPS Electric Power Monitoring 3.3.8.2

( 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LC0 3.3.8.2 Two RPS electric power monitoring assemblies shall be -

OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1, 2, and 3.

MODES 4 and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies, or with both residual heat removal shutdown cooling (RHR SDC) isolation valves open.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with inservice power O-V one electric power monitoring assembly supply (s) from service.

inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

)ower supplies with inservice power

)oth electric power supply (s) from monitoring assemblies service, inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met in MODE 1. 2. or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

(~

C)/

FERMI UNIT 2 3.3 74 Amendment No. 134 1

I i

RPS Electric Power Monitoring 3.3.8.2 O actions (ce"t4#"ee>

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to Immediately.

associated Completion fully insert all Time of Condition A insertable control or B not met in MODE 4 rods in core cells or 5 with any control containing one or rod withdrawn from a more fuel assemblies.

core cell containing one or more fuel egl assemblies or with both RHR-SDC isolation D.2.1 Initiate action to Immediately valves open. restore one electric power monitoring assembly to OPERABLE status for inservice power supply (s) supplying required instrumentation.

E D.2.2 Initiate action to Immediately

( '

isolate the Residual Heat Rernoval Shutdown Cooling System.

_ l l

l O

FERMI UNIT 2 3.3 75 Amendment No. 134

F i

1 t

l RPS Electric Power Monitoring

< 3.3.8.2 L

i l[ SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.3.8.2.1 -- ---- ---- -- NOTE---- -- - ---- ---

Only required to be performed prior to entering MODE 2 or 3 from MODE 4 when in MODE 4 for = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l .........................................

Perform CHANNEL FUNCTICNAL TEST. 184 days l

l l SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The 18 months Allowable Values shall be:

a. Overvoltage 5 132 V.

b. Undervoltage = 108 V.

c. Underfrequency = 57 Hz.

O t

G SR 3.3.8.2.3 Perform a system functional test. 18 months l

l l

l i

i O

FERMI - UNIT 2 3.3 76 Amendment No. 134

Recirculation Loops Operating 3.4.1

( 3.4 REACTOR COOLANT SYSTEM (RCS)

'3.4.1 Recirculation Loops Operating LC0 3.4.1 The reactor core shall not exhibit core thermal-hydraulic instability or operate in the " Scram" or " Exit" Regions.

NG

a. Two recirculation loops with matched recirculation loop jet pump flows shall be in operation:

b. One recirculation loop may be in operation provided the following limits are applied when the associated LC0 is applicable:

1. LCO 3.2.1. " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)." single loop operation limits I specified in the COLR:

2. LC0 3.2.2. " MINIMUM CRITICAL POWER RATIO (MCPR)."

single loop operation limits specified in the COLR:

3. LC0 3.3.1.1. " Reactor Protection System (RPS)

Instrumentation." Function 2.b (Average Power Range Monitors Simulated Thermal Power-Upscale) Allowable Value of Table 3.3.1.1-1 is reset for single loop operation, when in MODE 1: and

4. THERMAL POWER is s 67.2% RTP.

............................N0TE-- - ---- -- --- -- -----

Application of the required limitations for single loop operation may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after transition from two recirculation loop operations to single recirculation loop operation. l I

APPLICABILITY: MODES 1 and 2. I i

i l

o i

'9) l FERMI UNIT 2 3.4 1 Amendment No. 134 i

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

A. Recirculation jet pump A.1 Declare recirculation 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months j

loop flow mismatch not loop with lower flow: l within limits. "not in operation." l i

B. Reactor core operating ----

---NOTE---- ---- ---

l in the " Exit" Region. Restart of an idle i recirculation loop or l resetting a recirculation j flow limiter is not allowed.

l B.1 Initiate action to Immediately insert control rods or increase core flow I to restore operation I outside the " Exit" Region.

C. No recirculation loops C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months operating while in MODE 2.

(continued) l t

FERMI UNIT 2 3.4-2 Amendment No. 134

Recirculation Loops Operating 3.4.1 i

ACTIONS (continued) t] COMPLETION TIME l CONDITION REQUIRED ACTION

0. No recirculation loops D.1 Place the reactor Immediately.

operating while in mode switch in the MODE 1. shutdown position.

Reactor core operating in the " Scram" Region.

E Core thermal hydraulic j

instability evidenced.

SURVEILLANCE REQUIREMENTS

) SURVEILLANCE FREQUENCY SR 3.4.1.1 - - - -

-NOTE- - -- -

Only required to be performed when operating in the " Stability Awareness" Region.

Verify the reactor core is not exhibiting 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months core thermal hydraulic instability.

(continued)

~

FERMI UNIT 2 3.4 3 Amendment No. 134 I

i

Recirculation Loops Operating 3.4.1 O sVRvE1't>NCe aEouraE N1s <comt4nued)

SURVEILLANCE FREQUENCY SR 3.4.1.2 ...-.........-......N0TE... ... .- -...--

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a. s 10% of rated core flow when operating at < 70% of rated core flow; and

b. .s 5% of rated core flow when operating at = 70% of rated core flow.

O 1

l o

FERMI UNIT 2 3.4 4 Amendment No. 134

Jet Pumps 3.4.2 3.4 REACTOR _' COOLANT SYSTEM (RCS) 3.4.2- Jet Pumps LCO' 3.4.2 , All. jet pumps shall be OPERABLE. -

APPLICABILITY: -MODES 1 and 2. ,

ACTIONS C0lOITION. REQUIRED ACTION COMPLETION TIME 1

A. One or more jet pumps A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months <

inoperable. l I

i O

FERMI UNIT 2 3.4 5 ' Amendment No. 134

m Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY )

l SR 3.4.2.1 ...............- N0TES- -- --- ------ - '

l. Not required to be performed until.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation. .

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP.

Verify at least two of the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months criteria (a. b or c) are satisfied for each operating recirculation loop: ,

a. Recirculation loop drive flow versus recirculation pump speed differs by s 10% from established patterns.

b. Recirculation loop drive flow versus total core flow differs by 510% from established patterns.

t

c. Each jet pu p diffuser to lower plenum differentia )ressure differs by 5 20%

from establisled patterns. or each jet pump flow differs by s 10t from established patterns. ,

)

1 O !

FERMI UNIT 2 3.4 6 Amendment No. 134

SRVs 3.4.3 3.4 - REACTOR COOLANT SYSTEM (RCS)-

3.4.3 Safety Relief Valves (SRVs)

' LC0 3.4.3 The. safety function of 11 SRVs shall be OPERABLE. -

APPLICABILITY: MODES 1. 2..and 3.

I ACTIONS C0lOITION REQUIRED ACTION COMPLETION TIME l

A. One or more required A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SRVs inoperable.

AND A.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months O

I I

O FERMI - UNIT 2 3.4 7 Amendment No. 134 l

SRVs 3.4.3 4

O suavetuaace aeouiaeaeats SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift'setpoints In accordance of the required SRVs are as follows: with the Inservice Number of- Setpoint Testing Program SRVs (osia) .

5 1135

34.05 5 1145

34.35 5 1155 i 34.65 Following testing, lift settings shall be

.within i it.

SR 3.4.3.2 - ----

- ------ NOTE---- -- -- --- -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each required SRV opens when 18 months manually actuated. j i

i

~O ;

i FERMI UNIT 2 3.4 8 Amendment No. 134

RCS Operational LEAKAGE 3.4.4

/ 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO '3.4.4 RCS operational LEAKAGE shall be limited to: -

a. No pressure boundary LEAKAGE:

b. s 5 gpm unidentified LEAKAGE:

c. s 25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period: and

d. s 2 gpm increase in unidentified LEAKAGE within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period in MODE 1.

APPLICABILITY: MODES 1. 2. and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limit. within limits.

2 Total LEAKAGE not within limit.

(continued)

.\

FERMI UNIT 2 3.4 9 Amendment No. 134

RCS Operational LEAKAGE 1 3.4.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME i

B. Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months !

increase not within within limits. '

limit.

0B B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 )

austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months !

associated Completion Time of Condition A AND or B not met.

g . C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months V

Pressure boundary j LEAKAGE exists, l

SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and unidentified LEAKAGE increase are within limits.

t' FERMI - UNIT 2 3.4-10 Amendment No. 134

RCS PIV Leakage 3.4.5 l l

3.4 REACTOR'C00LANT SYSTEM (RCS) !

3.4.5 RCS Pressure Isolation Valve (PIV) Leakage LC0 3.4.5 The leakage from each RCS PIV shall be within limit. -

l APPLICASILITY: MODES I and 2.

MODE 3, except valves in the residual heat removal (RHR) ,

shutdown cooling flow {

transition to or from, path when in, or the shutdown during cooling the of mode ;

operation. '

I ACTIONS

.....................................N0TES - - ---- --- -- -- - ---- ---- --

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by PIVs.

O CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths --- - .---- NOTE - ---- -- --

with leakage from one Each check valve used to or more RCS PIVs not satisfy Required Action A.1 within limit. must have been verified to meet SR 3.4.5.1 at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.

............................. J A.1 Isolate the high 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pressure portion of the affected system from the low pressure portion by use of one other closed manual. j de activated J automatic. or check '

valve. !

/G (continued)

O l

FERMI - UNIT'2 3.4 11 Amendment No. 134 l

RCS PIV Leakage 3.4.5

/'"x ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l

l

{

SURVEILLANCE REQUIREMENTS i SURVEILLANCE FREQUENCY SR 3.4.5.1 -------

NOTE --- -- ---- - ----

Not required to be performed in MODE 3.

Verify equivalent leakage of each RCS PIV, In accordance at an RCS pressure a 1035 and s 1055 psig: with the g')

i

\'

Inservice

a. For PIVs other than LPCI loop A and B Testing Program injection isolation valves is s 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm: ,

i

b. For LPCI loop A and B outboard injection isolation valves is s 0.4 gpm through-seat, and 5 5 ml/ min external leakage: and

c. For LPCI loop A and B inboard injection isolation testable check l

valves is s 10 gpm. l j

FERMI - UNIT 2 3.4 12 Amendment No. 134

4 RCS Leakage Detection Instrumentation 3.4.6 i

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detection Instrumentation LC0 3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell floor drain sump flow monitoring syster;

b. The primary containment atmosphere gaseous radioactivity monitoring system channel: and

c. Drywell floor drain sump level monitoring system.

APPLICABILITY: MODES 1, 2. and 3.

ACTIONS

.................................. NOTE----- -- ----- ----------- ----- ---

LC0 3.0.4 is not applicable. ,

O CONDITION I REQUIRED ACTION COMPLETION TIME i

l A. Drywell floor drain A.1 Restore drywell floor. 30 days sump flow monitoring drain sump flow system inoperable, monitoring system to OPERABLE status.

B. Required primary B.1 Analyze grab samples Once per i containment atmosphere of primary 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months :

gaseous radioactivity containment I monitoring system atmosphere. l inoperable.

(continued)

C v

FERMI UNIT 2 3.4-13 Amendment No. 134

RCS Leakage Detection Instrumentation 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Drywell floor drain C.1 ....... NOTE----- -- -

sump level monitoring Not applicable when system inoperable. primary containment atmosphere gaseous radioactivity monitoring system is inoperable.

Perform SR 3.4.6.1. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D. Primary containment D.1 Restore primary 30 days atmosphere gaseous containment I radioactivity atmosphere gaseous '

monitoring system radioactivity inoperable. monitoring system to OPERABLE status.

8!Q O

V M Drywell floor drain sump level monitoring D.2 Restore drywell floor 30 days system inoperable. drain sump level monitoring system to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A. AND B. C. or D not met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. All required leakage F.1 Enter LC0 3.0.3. Immediately detection systems inoperable.

FERMI - UNIT 2 3.4 14 Amendment No. 134 l l

)

RCS Leakage Detection Instrumentation 3.4.6

] SURVEILLANCE' REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Perform a CHANNEL CHECK of required primary 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

containment atmosphere gaseous radioactivity monitoring system.

SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of 31 days required leakage detection instrumentation.

SR 3.4.6.3 Perform a CHANNEL CALIBRATION of required 18 months leakage detection instrumentation.

.)

l 0

FERMI UNIT 2 3.4-15 Amendment No. 134

1 RCS Specific Activity -

3.4.7 O 2.4 atacToa coo'aa' svsrea <acs) 3.4.7 RCS Specific Activity LC0 3.4.7 The specific activity of the reactor coolant shall be -

limited to DOSE EQUIVALENT I 131 specific activity 5 0.2 yC1/gm.

APPLICABILITY: MODE 1.

MODES 2 and 3 with any main steam line not isolated.

1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant --

- -- NOTE------ - -

specific activity LC0 3.0.4 is not applicable.

> 0.2 pCilgm and ---------------- -- ------ -

s 4.0 Ci/gm DOSE EQUIVALENT I 131. A.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I 131.

O ,

A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months f EQUIVALENT I-131 to within limits.

(continued) 1

.O FERMI UNIT 2 3.4 16 Amendment No. 134

RCS Specific Activity 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT I 131.

Time of Condition A not met. 6@

E B.2.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam lines.

Reactor Coolant specific activity 3

> 4.0 pCi/gm Dose EQUIVALENT I-131. B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

, SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 --- --- -

- NOTE---- - - ----- ---

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 7 days I 131 specific activity is s 0.2 Ci/gm.

b FERMI - UNIT 2 3.4 17 Amendment No. 134

RHR Shutdown Cooling System-Hot Shutdown 3.4.8 3.4 REACTOR COOLANT' SYSTEM (RCS) 3.4.8~ Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

............................N0TES- - - -- - --

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS

.....................................N0TES - - - - -

1. LC0 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Initiate action to Immediately RHR shutdown cooling restore required RHR subsystems inoperable. shutdown cooling subsystem (s) to OPERABLE status, l

AND l 1

(continued) '

I O

FERMI - UNIT 2 3.4 18 Amendment No. 134

RHR Shutdown Cooling System-Hot Shutdown

3.4.8 ACTIONS 4

CONDITION REQUIRED ACTION COMPLETION TIME f

A. (continued) A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem. l AND A.3 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I

B. No RHR shutdown B.1 Initiate action to Immediately cooling subsystem in restore one RHR operation. shutdown cooling I subsystem or one l AND recirculation pump to operation.

f No recirculation pump

in operation. AND B.2 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from coolant circulation discovery of no by an alternate reactor coolant method. circulation AND B.3 Monitor reactor Once per hour coolant temperature and pressure.

GL)

FERMI UNIT 2 3.4-19 Amendment No. 134 L'

RHR Shutdown Cooling System-Hot Shutdown 3.4.8

-s (j SURVEILLANCE REQUIREMENTS 5URVEILLANLL FREQUENCY SR 3.4.8.1 - - -- -

- - - NOTE --- ----- - --

Not required to be met until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reactor steam dome pressure is less than the RHR cut 1n permissive pressure.

Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or recirculation pump is operating.

,/ \

L) 1 l

l LJ FERMI UNIT 2 3.4 20 Amendment No. 134

RHR Shutdown Cooling System-Cold Shutdown 3.4.9 O 34 atactoa coo'^at svs't" <acs) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown LC0 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, '

with no recirculation pump in operation at least one RHR shutdown cooling subsystem shall be in operation.

...........................N0TES-------- --- ------ ----

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODE 4.

............................N0TE- --- --- -- --- - - --

Not applicable when heat losses to the ambient are greater than or equal to beat input to the reactor coolant.

ACTIONS

.................................... NOTE-- ------ --- - - - ----- ---------

. Separate Condition entry is allowed for each shutdown cooling subsystem.

i i

CONDITION REQUIRED ACTION COMPLETION TIME j A. One or two required A.1 Verify an alternate I hour RHR shutdown cooling method of decay heat subsystems inoperable. removal is available AND for each inoperable ,

RHR shutdown cooling Once per subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

O FERMI UNIT 2 3.4 21 Amendment No. 134

l RHR Shutdown Cooling System-Cold Shutdown 3.4.9

- ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Initiate action to Immediately cooling subsystem in restore one RHR operation. shutdown cooling subsystem or one 8ND recirculation pump to operation.

No recirculation pump in operation. AtiD B.2 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from coolant circulating discovery of no by an alternate reactor coolant method. circulation AND B.3 Monitor reactor Once per hour coolant temperature.

O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or recirculation pump is operating. I l

l l

FERMI UNIT 2 3.4 22 Amendment No. 134

RCS P/T Limits 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 RCS Pressure and Temperature (P/T) Limits LC0 3.4.10 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within limits.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---

NOTE -------- A.1 Restore parameter (s) 30 minutes Required Action A.2 to within limits.

shall be completed if this Condition is ANQ entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months O acceptable for D Requirements of the - continued operation.

LC0 not met in MODES 1, 2, and 3.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A N 6_NQ not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued) i FERMI UNIT 2 3.4 23 Amendment No. 134

RCS P/T Limits 3.4.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

C. -----

- NOTE- ------- C.1 Initiate action to Immediately-Required Action C.2 restore parameter (s) shall be completed if to within limits.

this Condition is I entered. AND i C.2 Determine RCS is Prior to Requirements of the acceptable for entering MODE 2 i LC0 not met in other operation, or 3 i than MODES 1. 2 and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 ---- ----- -

--NOTE------ --- ---

Only required to be performed as applicable during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify: 30 minutes

a. RCS pressure and RCS temperature are to the right of the limits specified in Figure 3.4.10 1: and

b. RCS heatup and cooldown rates are limited to:

1. s 100*F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period: and j

2. s 20*F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during inservice hydrostatic and leak testing operations above the 4 heatup and cooldown limit curves.

(continued)

O O

FERMI - UNIT 2 3.4 24 Amendment No. 134

1 RCS P/T Limits 3.4.10

( ,

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in 15 minutes Figure 3.4.10 1. prior to control rod withdrawal for )

the purpose of achieving ,

criticality I i

i SR 3.4.10.3 ----- ---

- NOTE--- -- ----------- l Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pressure vessel (RPV) steam space coolant prior to each temperature is s 145*F. startup of a recirculation pump SR 3.4.10.4 - --- - --

---NOTE----- - --- ----

Only required to be met in MODES 1, 2. 3, and 4 during recirculation pump startup.

Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes i loop to be started and the RPV coolant prior to each l temperature is s 50"F. startup of a i recirculation {

pump

)

(continued) ,

i v

FERMI UNIT 2 3.4 25 Amendment No. 134 l

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.5 --.- - ------ - - NOTE------------- -- - -

Only required to be met during a THERMAL POWER increase or recirculation flow increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30t RTP or when operating loop flow is s 50% rated loop flow.

Verify the difference between the bottom Once within head coolant temperature and the RPV steam 15 minutes space coolant temperature is s 145'F. prior to a THERMAL POWER increase or recirculation flow increase 1

SR 3.4.10.6 - ---- - ---- ---

NOTE----------- --- - -

Only required to be met during a THERMAL POWER increase or recirculation flow increase in MODES 1 and 2 with one non.

isolated idle recirculation loo) when )

THERMAL POWER is s 30% RTP or w1en operating loop flow is s 50% rated loop flow.

Verify the difference between the reactor Once within coolant temperature in the idle 15 minutes ,

recirculation loop and the RPV coolant prior to a temperature is s 50*F.

THERMAL POWER increase or recirculation flow increase (continued)

/%

U FERMI - UNIT 2 3.4-26 Amendment No. 134

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.7 --.---.....-- ---- NOTE -- - ------ - ----

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head 30 minutes flange temperatures are a 71*F when the reactor vessel head bolt st9ds are under

. tension.

SR 3.4.10.8 ----- -

---NOTE- - ---- -- ---- -

Not required to be performed until 30 minutes after RCS temperature s 80*F in MODE 4.

Verify reactor vessel flange and head 30 minutes f9 V

flange temperatures are a 71*F.

SR 3.4.10.9 ---- - -- --

--- NOTE -- -- -- -- ---

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature s 100"F in MODE 4.

Verify reactor vessel flange and head 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I flange temperatures are a 71*F.

FERMI UNIT 2 3.4 27 Amendment No. 134

. RCS P/T Limits 3.4.10 1600 O

V I

uoo -

/ A I

P A' 8'& C' I - ,

f f I ii I 'l I

=

? I I

$ 1o00 ,

l !

j 5 J I N

e i i E

ya l i e A',F,C'.COREBELTUNE AFTER E j ASStad!D 11cF SWT FROM AN j

NTIAL WELD RTpey OF -erF -

@ Goo ) A . SYSTEM HYDROTEST LMTWTH F12L N VESSEL E

B . NON-NUCLEAR EATLF/ _

COOLDOM LMT g

101*F l/ l C . NUCLEAR (CORE OtmCAL)LMTS _

l -VESSEL DISCONTNUITY LMTS

~

2oe - E

/ ;

--CORE BELTLNE WTH 11rF

~

7 32 EFPY CURVES A', B', C'NOT -

l !

LMTNG. NFORMATION CN.Y

' l l CURVES A, B, C ARE VALD FOR 32

[ EFPY OF OPERATION

, I i e i e i i e too 2co soo ano soo soo 64N4WUW REAC704 VESSEL hETAL TEMPERATURE ('F)

.,, FIGURE 3.4.10-1 HINIMUM REACTOR PRESSURE VESSEL METAL T'EMDERATURE VS. R FERMI UNIT 2 3.4-28 Amencment No. 134

Reactor Steam Dome Pressure 3.4.11 O 3.4 aeacToa coo'^at svs'ea (acs)

'3.4.11 Reactor Steam Dome Pressure LC0 3.4.11' The reactor steam dome pressure shall be s 1045 psig. -

-APPLICABILITY: MODES 1 and 2.

1 ACTIONS-COM)ITION REQUIRED ACTION COMPLETION TIME

'A. Reactor steam. dome A.1 Restore reactor steam 15 minutes pressure not within dome ressure to limit. withi limit.

1 B. ~

Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

g. associated Completion Time not met.

JJRVEILLANCE REQUIREMENTS' SURVEILLANCE FREQUENCY SR '3.4.11.1 Verify reactor. steam dome pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

s 1045 psig. l i

l i

O FERMI ! UNIT 2 3.4 29 Amendment No. 134

ECCS -Operating 3.5.1 0 3.5 eseaceacv cone coo'taa SvSreas <eces) ^~o aeacToa coas iso'^Tio" coo'1"o (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection / spray subsystem and the Automatic Depressurization System (ADS) function of five safety / relief valves shall be OPERABLE.

APPLICABILITY: MODE 1.

MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure s 150 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection / spray ECCS injection / spray subsystem inoperable. subsystem to OPERABLE O' status.

B. One LPCI pump in both B.1 Restore both LPCI 7 days LPCI subsystems pumps to OPERABLE inoperable. status.

C. One CSS subsystem C.1 Restore CSS subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. to OPERABLE status.

b_ND - QB One LPCI subsystem C.2 Restore LPCI 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. subsystem to OPERABLE status.

(continued)

O FERMI UNIT 2 3.5 1 Amendment No. 134

ECCS-Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. ' Required Action'and- D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

associated Completion Time of Condition A. E B, or C not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. HPCI System E.1 Verify by Immediately inoperable, administrative means RCIC System is OPERABLE.

M E.2 Restore HPCI System 14 days to OPERABLE status.

'F. HPCI System F.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

to OPERABLE status.

Condition A.~or F.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Condition B. or ECCSinjection/ spray Condition C entered. subsystem (s) to OPERABLE status.

G. One ADS ~ valve G.1 Restore ADS valve to 14 days

-inoperable. OPERABLE status.

(continued)

FERMI UNIT 2 3.5 2 Amendment No. 134 I

ECCS-Operating 3.5.1

-i ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

H. One ADS valve H.1 Restore ADS valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months -

inoperable. OPERABLE status. ,

i 8NQ @ l l'

Condition A or H.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Condition B entered. ECCSinjection/ spray subsystem (s) to OPERABLE status. 1 I. Two or more ADS valves I.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND- l 2 l I.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ]

Required Action and dome pressure to I associated Completion s 150 psig. l Time of Condition E. I F. G. or H not met.

J. Two or more low J.1 Enter LC0 3.0.3. Immediately pressure ECCS injection / spray subsystems ino)erable for reasons otler than Condition B or C.

2 HPCI System and one or more ADS valves inoperable.

Condition C and Condition G entered.

1 O l FERMI UNIT 2 3.5 3 Amendment No. 134

ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify correct voltage and breaker 7 days -

alignment to the LPCI swing bus.

SR 3.5.1.2 ----- ----

NOTE- - -- - ------- -

When LPCI is placed in an ino erable status solely for performance of thi SR, or when the LPCI swing bus automatic throwaver scheme is inoperable due to EDG-12 being paralleled to the bus for required testing, entry into associated Conditions and Required Actions may be delayed up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for completion of the required testing.

Perform a functional test of the LPCI swing 31 days bus automatic throwaver scheme.

O V

SR 3.5.1.3 Verify. for each ECCS injection / spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the ,

injection valve.

(continued) l l

1 l

O FERMI UNIT 2 3.5 4 Amendment No. 134

. 1 L

ECCS-Operating 3.5.1 l l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.4 - - --- -- -

-- NOTE -- -- ------ -

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3. and for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after exceeding the RHR cut-in permissive pressure in MODE 3.

if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection / spray subsystem 31 days ,

manual, power o>erated and automatic valve l in the flow pat 1. that is not locked, l sealed, or otherwise secured in position, !

is in the correct position. l O SR 3.5.1.5 Verify primary containment pneumatic supply pressure is a 75 psig.

31 days SR- 3.5.1.6 Verify the RHR System power operated cross 31 days tie valve is open.

SR 3.5.1.7 Verify each recirculation pump discharge 18 months valve cycles through one complete cycle of full travel or is de energized in the closed position.

(continued)

O FERMI UNIT 2 3.5 5 Amendment No. 134

l ECCS-Operating 3.5.1 l

) SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.8 Verify the following ECCS pumps develop the In accordance specified flow rate against a system head with the corresponding to the specified reactor Inservice pressure. Testing SYSTEM HEAD Program NO. CORRESPONDING 0F TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray a 6350 gpm 2 = 100 psig LPCI = 10,000 gpm 1 = 20 psig SR 3.5.1.9 -- ---- --

--- NOTE- ---- -- ----

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure s 1045 and In accordance

= 945 psig, the HPCI pump can develop a with the flow rate a 5000 gpm against a system head Inservice corresponding to reactor pressure. Testing Program l

SR 3.5.1.10 ---- -

- -- NOTE--- - ---- --- -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure s 215 psig. 18 months the HPCI pump can develop a flow rate l

= 5000 gpm against a system head !

corresponding to reactor pressure. l (continued)

{

1-FERMI - UNIT 2 3.5 6 Amendment No. 134

E ;

i I

E ECCS- Operating !

3.5.1 <

(~%

V SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.11 --- - -

- -- -- NOTE---- - --- ----- -- -

-Vessel injection / spray may be excluded.

Verify each ECCS injection / spray subsystem 18 months '

actuates on an actual or simulated automatic initiation signal.

SR 3.5.1.12 ------ - -- ---

-NOTE --- --- ------- - i Valve actuation may be excluded.

........................................... j l

Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal.

I SR 3.5.1.13 - -----

-- ----NOTE - - - ------- ---

( Not required to be_ performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test. !

Verify each ADS valve opens when manually 18 months ,

actuated.

I SR 3.5.1.14 - ---- -

- -- NOTE - --- - ---

ECCS instrumentation response times are not required to be measured.

Verify ECCS RESPONSE TIME is within limits. 18 months i

O ,

-FERMI - UNIT 2 3.5 7 Amendment No. 134

ECCS-Shutdown 3.5.2 1

l L O 3 s taeascacv coat coo'iaa svs'tas <eccs) aao aeac'oa coat 'so'au oa COOLING-(RCIC) SYSTEM.

3.5.2 ECCS-Shutdown l -

l LCO 3.5.2 Two low pressure ECCS injection / spray subsystems shall be OPERABLE.

1 APPLICABILITY: MODE 4 MODE 5. except with the spent fuel storage pool gates removed and water level = 20 ft 6 inches over the top of .

the reactor pressure vessel flange.

ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME l'

i A. One reguired ECCS A.1 Restore required ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection / spray injection / spray subsystem inoperable. subsystem to OPERABLE

, status.

B. Required Action and B.1 Initiate action to Immediate1v associated Completion suspend operations Time of Condition A with a potential for not met. draining the reactor vessel (0PDRVs). {

j

)

C. Two required ECCS C.1 Initiate action to Immediately l

injection / spray suspend OPDRVs.

l subsystems inoperable.

AND C.2 Restore one ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection / spray subsystem to OPERABLE status.

i (continued) i

FERMI UNIT 2 3.5 8 Amendment No. 134

ECCS - Shutdown 3.5.2 i A*,TIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D.1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status.

AND D.2 Initiate action to Immediately restore one standby gas treatment I subsystem to OPERABLE status. :

6ND D.3 Initiate action to Immediately restore isolation I capability in each required secondary containment penetration flow path '

O)

(, not isolated.

)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify. for each required low pressure 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months coolant injection (LPCI) subsystem, the suppression pool water level is a 66 inches.

(continued)

O FERMI UNIT 2 3.5 9 Amendment No. 134

ECCS-Shutdown i 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required core spray (CS) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

subsystem. the:

a. Suppression pool water level is

= -66 inches: or

b. .................N0TE---- ----- ----

Only one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level is

= 19 ft.

SR 3.5.2.3 Verify correct voltage and breaker 7 days alignment to the LPCI swing bus.

m SR 3.5.2.4 Verify, for each required ECCS injection / 31 days spray subsystem. the piping is filled with water from the pump discharge valve to the injection valve.

(continued) l FERMI UNIT 2 3.5 10 Amendment No. 134 l l l

I

( j

~

ECCS-Shutdown 3.5.2 O Suave' u^"c" aeoutaeaea's (co#t4##ed)

SURVEILLANCE FREQUENCY SR 3.5.2.5 ...................N0TE.-.....---.-- ---..-

LPCI subsystem (s) may be considered OPERABLE during alignment and operation for-decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection / spray 31 days

' subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

1 SR 3.5.2.6 Verify each required ECCS pump develops the In accordance !

specified flow rate against a system head with the l corresponding to the specified reactor Inservice pressure. Testing O NO.

OF SYSTEM HEAD CORRESPONDING TO A REACTOR Program SYSTEM FLOW RATE. PUMPS PRESSURE OF CS = 6350 gpm 2 = 100 psig LPCI = 10,000 gpm 1 = 20 psig l l

SR 3.5.2.7 ...................N0TE. --.--.. -......- !

Vessel injection / spray may be excluded.

Verify each required ECCS injection / spray 18 months subsystem actuates on an actual or simulated automatic initiation signal.

O b

FERMI . UNIT 2 3.5 11 Amendment No. 134

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ANO REACTOR CORE ISOLATION COOLING A

(RCIC) SYSTEM 3.5.3 RCIC System LC0 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1.

MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant Injection System is OPERABLE.

O =

A.2 Restore RCIC System 14 days to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to s 150 psig.

I l

l O

V FERMI - UNIT 2 3.5 12 Amendment No. 134 s

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS I)

SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days -

with water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.3.3 -- -- - - -- -- -NOTE------ -- -- --- --

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

O ver4rr. ~4th reector pressere and = 945 psig, the RCIC pump can develop a 1o4s as49 92 e xs flow rate m 600 gpm against a system head corresponding to reactor pressure.

SR 3.5.3.4 -- - -

-- - NOTE--- ----- - ----

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify with reactor pressure s 200 psig, 18 months the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure.

(continued)

FERMI - UNIT 2 3.5-13 Amendment No. 134

i l

RCIC System 3.5.3 l l

() SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY i

l SR 3.5.3.5 -- - -- --

- --NOTE--- --- -- - - -

Vessel injection may be excluded.

Verify the RCIC System actuates on an 18 months actual or simulated automatic initiation signal .

O l

1 l

I i

O l

. FERMI' UNIT 2 3.5 14 . Amendment No. 134

a ,

Primary Containment 3.6.1.1

?3.6 -CONTAINMENT SYSTEMS-3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE. .

APPLICABILITYi MODES 1, 2. and 3.

i ACTIONS COWITION REQUIRED ACTION COMPLETION TIME

'A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion O Time not met. egl B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREENTS' SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and In accordance I leakage rate testing except for primary with the l containment air lock testing, in Primary accordance with the Primary Containment Containment

Leakage Rate Testing Program. Leakage Rate Testing Program (continued)

O

' FERMI UNIT 2: 3.6 1 Amendment No. 134

Primary Containment 3.6.1.1 O suave' u^"ce aeoutae"e"'s (c "t4""ed)

SURVEILLANCE FREQUENCY SR 3.6.1.1.2 Verify drywell to suppression chamber 18 months -

differential pressure does not decrease I at a rate > 0.2 inch water gauge per AND minute tested over a 10 minute period at an initial differential pressure of ----

NOTE- -

1 psid. Only required after two consecutive tests fail and continues until two consecutive tests pass i 9 months I i

SR 3.6.1.1.3 ----- -- -----

-NOTE---- ---- -- --- --

Only required to be performed after Q

l safety / relief valve operation with the

\s suppression chamber average water temperature a 160*F and reactor coolant system pressure > 200 psig.

Perform an external visual examination of Once prior to the suppression chamber. entry into MODE 2 or 3 from MODE 4

~%

(O FERMI - UNIT 2 3.6-2 Amendment No. 134

Pricary Containment Air Lock 3.6.1.2 (7

v 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Lock LCO 3.6.1.2 The primary containment air lock shall be OPERABLE. -

~ APPLICABILITY: MODES 1, 2. and 3.

ACTIONS

.....................................N0TES------------

1. Entry and exit is permissible to perform repairs of the air lock components.

2. Enter applicable Conditions and Required Actions of LC0 3.6.1.1. " Primary Containment." when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME O A. One primary - ------

-NOTES - -- ---

containment air lock 1. Required Actions A.1 door inoperable. A.2, and A.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

8ND

, (continued)

O

' ..V FERMI UNIT 2 3.6 3 Amendment No. 134

E l l

Primary Containment Air Lock l 3.6.1.2 l

ACTIONS

) _

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

door closed.

ANQ A.3 -- -- --NOTE-- ------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked '

closed.

, O B. Primary containment ----- -

---NOTES ----------- i air lock interlock 1. Required Actions B.1, mechanism inoperable. B.2, and B.3 are not i applicable if both doors !

in the air lock are l inoperable and Condition C is entered.

, 2. Entry into and exit from containment is permissible under the control of a dedicated individual.

1 B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed.

AND (continued)

G

.L.)

FERMI' UNIT 2 3.6 4 Amendment No. 134 L

1 1

Prinary Containment Air Lock l 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months '

closed.

8NQ B.3 -- NOTE --- -

Air lock doors in high radiation areas or areas with limited access due to j inerting may be verified locked closed by I administrative means.

Verify an OPERABLE Once per 31 days door is locked closed.

O C. Primary containment C.1 Initiate action to Immediately air lock inoperable evaluate primary for reasons other than containment overall Condition A or B. leakage rate per LC0 3.6.1.1. using current air lock test results.

AND C.2 Verify a door is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l closed.

AND i C3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

(continued)

O.

FERMI UNIT 2 3.6 5 Amendment No. 134

Pritary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

associated Completion Time not met. 8NQ D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 - ----

--- NOTES --- -- -- -

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.1.

Perform required primary containment air In accordance lock leakage rate testing in accordance with the with the Primary Containment Leakage Rate Primary Testing Program. Containment Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary 24 months containment air lock can be opened at a time.

l 1

)

O FERMI - UNIT 2 3.6 6 Amendment No. 134

PCIVs l{ .:

3.6.1.3 3.6 CONTAINENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs).

I

^ LCO 3.6.1.3 Each PCIV, except reactor building to suppression chamber vacuum breakers, shall be OPERABLE. 1 APPLICABILITY:- MODES 1, 2, and 3. .

When associated ir.strumentation is required to be OPERABLE per LC0 3.3.6.1, '" Primary Containment Isolation Instrumentation."

ACTIONS i

................................ .... NOTES -- --- - - -- - --- --- --

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. -Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

-(~N 4 Enter applicable Conditions and Required Actions of LC0 3.6.1.1. " Primary V Containment," when PCIV leakage results in exceeding overall containment

'. leakage rate acceptance criteria in MODES 1, 2. and 3.

CONDITION REQUIRED ACTION COMPLETION TIME A. ----

NOTE - - - - A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to >enetration' flow path for main steam penetration flow paths )y use of at least line with two PCIVs. one closed and de activated E

. automatic valve, One or more closed manual valve. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main penetration flow paths .

blind flange, or steam line with one PCIV- check valve with flow inoperable,-except due through the valve l to leakage not within secured.

limit.

E )

(continued)

.O FERMI - UNIT 2- 3.6 7 Amendment No. 134

1 PCIVs 3.6.1.3 l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 -- -

NOTES---- - - -

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked.

sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation is isolated. devices outside O primary containment 8NQ Prior to entering MODE 2 or 3 from MODE 4. if primary containment was de inerted while in MODE 4. if l not performed within the previous 92 days. for isolation i devices inside primary containment ,

l (continued)

FERMI - UNIT 2 3.6 8 Amendment No. 134 I

i I

PCIVs 3.6.1.3 ;

ACTIONS (continued) l C0WITION REQUIRED ACTION COMPLETION TIME B. - --

NOTE- - --

B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months -

Only applicable to >enetration flow path penetration flow paths )y use of-at least with two PCIVs. one closed and de-activated automatic valve, One or more- closed manual valve, penetration flow paths or blind flange.

with two PCIVs inoperable, except due to leakage not within limit.

(continued)

O l

l-O

-FERMI UNIT 2 3.6 9 Amendment No. 134 l

l PCIVs 3.6.1.3 i

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. - -NOTE --- -

C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only applicable to >enetration flow path for excess flow penetration flow paths )y use of at least check valves with only one PCIV. one closed and (EFCVs) and de activated penetrations automatic valve. with a closed One or more closed manual valve, system penetration flow paths or blind flange, with one PCIV ANQ inoperable except due to leakage not within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for limit. EFCVs and penetrations with a closed system AND C.2 ---- NOTES -- --

1. Isolation devices in high radiation O

(J areas may be verified by use '

of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

(continued) n U

FERMI UNIT 2 3.6 10 Amendment No. 134

f PCIVs 3.6.1.3

(, ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more D.1 Restore leakage rates 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for-penetration flow paths to within limit. leakage on with one or more PCIVs hydrostatically inoperable due to tested line secondary containment without a closed bypass leakage rate, system MSIV leakage rate, purge valve leakage ANQ rate, hydrostatically tested line leakage 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for rate. or EFCV leakage secondary rate not within limit. , containment bypass leakage AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for MSIV leakage AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for purge valve leakage 6N_Q 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for leakage on hydrostatically tested line on a closed system and EFCV leakage l

AND (continued)

{

O FERMI UNIT 2 3.6 11 Amendment No. 134

PCIVs 3.6.1.3

~"s O COWITION REQUIRED ACTION COMPLETION TIME D.- (continued) - NOTES --- - - -

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

3. Only applicable to penetration flow paths isolated to restore leakage to within limits.

D.2 Verify the affected Once per 31 days penetration flow path for isolation devices outside O

is isolated, primary z

containment j

Prior to entering MODE 2 or 3 from l MODE 4. if !

primary containment was de inerted while i in MODE 4. if not performed within the previous 92 days. for isolation devices inside primary containment (continued)

O FERMI UNIT 2 3.6 12 Amendment No. 134

PCIVs 3.6.1.3 O ac'ioas (co"t4""ea)

CONDITION REQUIRED ACTION COMPLETION TIME i

j E. Required Action and' E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

I associated Compietion Time of Condition A, egl B. C, or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Required Action and F.1 Initiate action to Immediately associated Completion isolate RHR Shutdown Time of Condition A, Cooling System. ,

B C. or D not met for l RHR-SDC PCIV(s) @

required to be OPERABLE during MODE 4 F.2 Initiate action to Immediately ,

or 5. restore valve (s) to !

OPERABLE status. j 1

O FERMI UNIT 2- 3.6 13 Amendment No. 134

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 -- - .

NOTE-- - -- --- -- -

Not required to be met when the isolation valves for one purge or containment pressure control supply line and one l purge or containment pressure control exhaust line are open for inerting, de-inerting, pressure control. ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each drywell and suppression 31 days chamber purge system and containment pressure control isolation valve is closed.

SR 3.6.1.3.2 - -- ----

-NOTES - - ------ --- -

1. Valves and blind flanges in high 0_ radiation areas may be verified by I

use of administrative means.

2. Not required to be met for PCIVs that ,

are open under administrative I controls.

Verify each primary containment isolation 31 days manual valve and blind flange that is located outside primary containment and is not locked sealed, or otherwise secured and is required to be closed during accident conditions is closed.

(continued)

O

- - - FERMI UNIT 2 3.6 14 Amendment No. 134

PCIVs 3.6.1.3

(] SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY j

l SR 3.6.1.3.3 - - - -

- NOTES - ---- - - -- - -

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation Prior to I manual valve and blind flange that is entering MODE 2 located inside primary containment and is or 3 from not locked. sealed. or otherwise secured MODE 4 if and is required to be closed during primary accident conditions is closed. containment was de inerted while in '

MODE 4. if not

, performed rs within the j previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing 31 days incore probe (TIP) shear isolation valve explosive charge.

i SR 3.6.1.3.5 Verify the isolation time of each power In accordance operated automatic PCIV. except for with the MSIVs. is within limits. Inservice Testing Program (continued)

FERMI UNIT 2 3.6 15 Amendment No. 134

PCIVs 3.6.1.3

) SURVEILLANCE REQUIREMENTS (continued)

SURVEILUWCE FREQUENCY I

SR 3.6.1.3.6 Perform leakage rate testing for each 184 days -

primary containment purge valve with l resilient seals. 6NQ 1 Once within 92 days after I opening the valve SR 3.6.1.3.7 Verify the isolation time of each MSIV is In accordance

= 3 seconds and s 5 seconds. with the l Inservice I Testing Program j l

l SR 3.6.1.3.8 Verify each automatic PCIV actuates to 18 months the isolation position on an actual or i simulated isolation signal.

SR 3.6.1.3.9 Verify each reactor instrumentation line 18 months EFCV actuates on a simulated instrument line break to restrict flow.

SR 3.6.1.3.10 Remove and test the explosive squib from 18 months on a each shear isolation valve of the TIP STAGGERED TEST System. BASIS (continued) i f

FERMI UNIT 2 3.6 16 Amendment No. 134 1

PCIVs 3.6.1.3 l

l e j SURVEILLANCE REQUIREMENTS (continued) b SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths that are not provided with a seal Primary system is s 0.04 L, when pressurized to Containment

= 56.5 psig. Leakage Rate Testing Program and Inservice Testing Program SR 3.6.1.3.12 Verify combined MSIV leakage rate for all In accordance four main steam lines is s 100 scfh when with the tested at = 25 psig. Primary Containment Leakage Rate Testing Program

('

'SR 3.6.1.3.13 --- - - -- -- -- -NOTE - -- - - -------.

Only required to be met in MODES 1, 2.

and 3.

Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrate the primary containment is Primary within limits. Containment Leakage Rate Testing Program I

i i

rm V

FERMI - UNIT 2 3.6 17 Amendment No. 134

1 i

l Pricary Containment Pressure l

3.6.1.4

, 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Primary Containment Pressure LC0 3.6.1.4' Primary containment pressure shall be = -0.10 psig and l 5 +2.0 psig. I APPLICABILITY: MODES 1. 2. and 3.

ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months pressure not within containment pressure I limit. to within limit.

l B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I g associated Completion g Time not mat. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1

SR 3.6.1.4.1 Verify rimary containment pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months within imit.

l i

,s~

U 1 FERMI - UNIT 2 3.6-18 Amendment No. 134 ;

I 1

Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS f) 3.6.1.5 Drpell Air Temperature LC0 3.6.1.5 Drpell average air temperature shall be s 145'F. -

APPLICABILITY: MODES-1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drpell average air A.1 Restore drpell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within average air limit. temperature to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

. (N.l associated Completion v Time not met. MQ l

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drpell average air temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limit.

O.

.U FERMI UNIT 2 3.6 19 Amendment No. 134

LLS Valves 3.6.1.6

( 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Low Low Set (LLS) Valves LC0 3.6.1.6 The LLS function of two safety / relief valves shall be -

OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1

A. One LLS valve A.1 Restore LLS valve to 14 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months fs associated Completion Time of Condition A

(/ )

( ANQ not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Both LLS valves inoperable.

I i

i l

l 2

i O

FERMI UNIT 2 3.6 20 Amendment No. 134

LLS Valves 3.6.1.6 1

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 - . - .

.- NOTE- - - ------ ---

Not required to be performed until !

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each LLS valve opens when manually 18 months j actuated.

SR 3.6.1.6.2 - -

- - -- NOTE- - - --- - ------

Valve actuation may be excluded.

Verify the LLS System actuates on an 18 months actual or simulated automatic initiation signal.

.o l

p.

FERMI - UNIT 2 3.6 21 Amendment No. 134

Reactor Building to Suppression Chamber Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Reactor Building to. Suppression Chamber Vacuum Breakers LC0 3.6.1.7 Each reactor building to-suppression chamber vacuum breaker shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTIONS

.................................... NOTE---- -------- -- - ----- --- ------

Separate Condition entry is allowed for each line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reactor building- breaker.

O V

to suppression chamber vacuum breaker not I closed. l l

l B. One or more lines with B.1 Close one open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l two reactor building- breaker. ;

to suppression chamber vacuum breakers not closed.

C. One line with one or C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months more reactor building- breaker (s) to to-suppression chamber OPERABLE status.

vacuum breakers inoperable for opening.

(continued)

)

FERMI UNIT 2 3.6 22 Amendment No. 134

Reactor Building to Suppression Chamber Vacuum Breakers 3.6.1.7

' ACTIONS (continued)

C0lOITION REQUIRED ACTION COMPLETION TIME D. Two lines with one or D.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months -

more reactor building- breakers in one line to-suppression chamber to OPERABLE status.

vacuum breakers l

inoperable for opening.

I E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

. Associated Completion Time not met. ANQ E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1 -- - --

NOTES-- - -- - ----

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.7.2 Perform a functional test of each vacuum 31 days breaker.

(continued)

O l FERMI UNIT 2 3.6 23 Amendment No. 134 l I

Reactor Building to Suppression Chamber Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREENTS (continued)

SURVEILLANCE FREQUENCY l

l SR 3.6.1.7.3 Verify the opening setpoint of each 18 months -

vacuum breaker is s 0.5 psid.

l 1

O l

)

l l

i A

i FERMI . UNIT 2 3.6 24 Amendment No. 134

4 Suppression Chamber to Dr.Well Vacuum Breakers 3.6.1.8 3.6 CONTAINMENT SYSTEMS

(]

3.6.1.8 Suppression Chamber to Drywell Vacuum Breakers LC0 3.6.1.8 Twelve su)pression chamber to drywell vacuum breakers shall be OPERAB_E.

APPLICABILITY: MODES 1. 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One suppression A.1 Restore vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber to drywell breaker to OPERABLE vacuum breaker status.

inoperable for opening.

(3 kJ B. One or more B.1 Close the open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months suppression chamber- breaker (s).

to-drywell vacuum breaker not closed.

I C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

/'~}

'% J FERMI UNIT 2 3.6 25 Amendment No. 134

Suppression Chamber to Drywell Vacuum Breakers 3.6.1.8 4

SURVEILLANCE REQUIREMENTS j SURVEILLANCE FREQUENCY SR 3.6.1.8.1 - - -- -

- NOTES --- - --

1. Not required to be met for vacuum breakers that are open during Surveillances. '

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 7 days SR 3.6.1.8.2 Perform a functional test of each vacuum Prior to breaker. entering MODE 2 or 3 from MODE 4 if not g- performed in

( the previous 92 days 8NQ Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months !

after any discharge of steam to the suppression chamber from the SRVs SR 3.6.1.8.3 Verify the opening setpoint of each 18 months vacuum breaker is s 0.5 psid.

a O

V FERMI - UNIT 2 3.6 26 Amendment No. 134

MSIV LCS 3.6.1.9 3.6 CONTAINMENT SYSTEMS 3.6.1.9 . Main Steam Isolation Valve (MSIV) Leakage Control System (LCS)

LC0 3.6.1.9 Two MSIV LCS subsystems shall be OPERABLE. -

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV LCS subsystem A.1 Restore MSIV LCS 30 days inoperable. subsystem to OPERABLE status.

B. Two MSIV LCS B.1 Restore one MSIV LCS 7 days subsystems inoperable, subsystem to OPERABLE status.

N)

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. A_N.Q C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l

i rm FERMI UNIT 2 3.6 27 Amendment No. 134

l MSIV LCS l 3.6.1.9 l

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.9.1 Verify each MSIV LCS valve, testable 31 days -

during operation, cycles through at least j one complete cycle of full travel.

SR 3.6.1.9.2 Verify each MSIV LCS valve, not testable Prior to during operation, cycles through at least entering MODE 2 one complete cycle of full travel. or 3 from MODE 4 if not performed in the previous i

31 days SR 3.6.1.9.3 Perform a system functional test of each 18 months MSIV LCS subsystem.

O l

l i

.O i FERMI UNIT 2 3.6 28 Amendment No. 134 l

i

m Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO' 3.6.2.1 Suppression pool average temperature shall be: -

a. s 95*F with THERMAL POWER > lt RTP and no testing that

~a dds heat to the suppression pool is being performed: j

.b. s 105*F with THERMAL POWER > lt RTP and testing that adds heat to the suppression pool is being performed: I and j

c. s 110*F with THERMAL POWER s it RTP.

I APPLICABILITY: MODES 1, 2, and 3.

' ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

, A. Suppression pool A.1 Verify suppression Once per hour

-average temperature pool average

> 95'F but s 110*F. temperature 5 110*F.

M M THERMAL POWER A.2 Restore suppression 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> lt RTP. pool average temperature to M s 95*F.

Not performing testing

.that adds heat to the suppression pool.

(continued)

O

. FERMI UNIT 2 3.6 29 Amendment No. 134 r

Suppression Pool Average Temperature 3.6.2.1

( ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL POWER 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

associated Completion to s 1% RTP.

Time of Condition A not met.

C. Suppression pool C.1 Suspend all testing Immediately average temperature that adds heat to the

> 105*F. suppression pool.

AND THERMAL POWER > lt RTP.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool D.1 Place the reactor Immediately average temperature mode switch in the

> 110*F but s 120"F. shutdown position.

AND i

D.2 Verify suppression Once per pool average 30 minutes temperature s 120*F.

AND D.3 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued) m U

FERMI UNIT 2 3.6-30 Amendment No. 134

Suppression Pool Average Temperature l 3.6.2.1 (O.,1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I average temperature reactor vessel to

> 120*F. < 200 psig.

MQ E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months temperature is within the applicable

/~'N 1imits. AND G

5 minutes when performing testing that adds heat to the suppression pool n

_s/

FERMI UNIT 2 3.6 31 Amendment No. 134

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be a -2 inches and -

5 +2 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within pool water level to limits, within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

, associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within limits.

-. j (3

G 1 l

FERMI.- UNIT 2 3.6 32 Amendment No. 134

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LC0 3.6.2.3 Two RHR suppression pool cooling subsystems shall be -

OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool cooling subsystem suppression pool inoperable. cooling subsystem to OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months O pool cooling subsystems inoperable, suppression pool cooling subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months FERMI - UNIT 2 3.6 33 Amendment No. 134 J

7 RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days -

subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct' position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pum) develops a flow rate In accordance

= 10,000 gpm throug1 the associated heat with the exchanger while operating in the Inservice suppression pool cooling mode. Testing Program O

O FERMI UNIT 2 3.6 34 Amendment No. 134

RHR Suppression Pool Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray

.LC0 3.6.2.4 ~ Two Rm suppression pool spray subsystems shall be OPERABLE.

APPLICABILITY:- MODES 1. 2. and 3.

ACTIONS-COWITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR 7 days pool spray subsystem suppression pool-inoperable. spray subsystem to OPERABLE status.

-B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool spray subsystems suppression pool

- inoperable. spray subsystem to OPERABLE status.

C. Required Action and C.1 Be.in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

' Time not' met. AN_Q C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D

FERMI - UNIT 2 3.6 35 Amendment No. 134

i RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS-SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RtR suppression pool spray 31 days -

subsystem manual, power operated, and

' automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the. correct position or can be aligned to the correct position.

l l SR 3.6.2.4.2 Verify each R}R pum) develops a flow rate In accordance l = 500 gpm through t1e heat exchanger and with the

! suppression pool spray sparger while Inservice operating in the suppression pool spray Testing Program m&.

O i

q l

l l

l i

O FERMI UNIT 2. 3.6 36 Amendment No. 134

P Primary Containment Hydrogen Recombiners 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Hydrogen Recombiners LCO--3.6.3.1 Two primary containment hydrogen recombiners shall be .

OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One primary A.1 ---- ---NOTE- -------

containment hydrogen LC0 3.0.4 is not recombiner inoperable. applicable.

Restore primary 30 days containment hydrogen recombiner to O. OPERABLE status.

B. Two primary B.1 Verify by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months containment hydrogen administrative means recombiners that the hydrogen ANQ inoperable. control function is maintained. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter 8!E B.2 Restore one primary 7 days containment hydrogen recombiner to OPERABLE status.

(continued)

O FERMI' UNIT 2 3.6 37 Amendment No. 134 i

I Primary Containment Hydrogen Recombiners 3.6.3.1 I ACTIONS (continued) ;

CONDITION REQUIRED ACTION COMPLETION TIME j l

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Perform a system functional test for each 18 months primary containment hydrogen recombiner.

I

{ SR 3.6.3.1.2 Visually examine each primary containment 18 months I

(' hydrogen recombiner enclosure and verify there is no evidence of abnormal conditions.

SR 3.6.3.1.3 Perform a resistance to ground test for 18 months each heater phase.

O FERMI UNIT 2 3.6 38 Amendment No. 134

Prirary Containment Oxygen Concentration !

3.6.3.2 I 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Oxygen Concentration LC0 3.6.3.2 The primary containment oxygen concentration shall be l

< 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period: l

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following ,

startup, to I

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next reactor shutdown. ;

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l q oxygen concentration concentration to !

b not within limit. within limit. l B. Required Action and B.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion to 5 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify primary containment oxygen 7 days concentration is within limits.

O L/

FERMI UNIT 2 3.6-39 Amendment No. 134

l Secondary Containment i 3.6.4.1 h 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment '

LCO 3.6.4.1 The secondary containment shall be OPERABLE. -

I i APPLICABILITY: MODES 1. 2. and 3.

During movement of irradiated fuel assemblies in the secondary containment.

During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

, ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME l

l A. Secondary Containment A.1 Restore railroad bay 7 days inoperable due to one door to OPERABLE railroad bay access status.

door inoperable.

(~')\

w 1 4

B. Secondary containment B.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1. containment to i 2. or 3 for reasons OPERABLE status.

l other than l Condition A.

l C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I

associated Completion Time of Condition A or AND B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued) r~)

NJ FERMI UNIT 2 3.6 40 Amendment No. 134

i Secondary Containment 3.6.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

-NOTE -- --- -- --

D. Secondary containment ---------

inoperable during LC0 3.0.3 is not applicable.

movement of irradiated --- ---- -------------------

fuel assemblies in the secondary containment, D.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDRVs. secondary containment.

8N_Q D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to Immediately suspend OPDRVs.

O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY S.3 3.6.4.1.1 Verify secondary containment vacuum is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

= 0.125 inch of vacuum water gauge.

(continued) l C~J FERMI UNIT 2 3.6 41 Amendment No. 134

Secondary Containment 3.6.4.1

'O suavet u^ ace aeouineae"Ts <co"t4meee>

SURVEILLANCE FREQUENCY SR 3.6.4.1.2 -- -

-- - ----NOTE ----- - - -- --- - -

Not required to be met for one railroad bay access door until:

a. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after opening for entry, exit, or testing: and

b. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after opening for new fuel receipt activities 3rovided the other door remains OPERAB_E and closed.

Verify all secondary containment 31 days equipment hatches. pressure relief doors and railroad bay access doors are closed and sealed.

SR 3.6.4.1.3 Verify one secondary containment access 31 days door in each access opening is closed.

m b

SR 3.6.4.1.4 Verify steam tunnel blowout panels are Prior to closed. entering MODE 2 l or 3 from

, MODE 4 if not performed in the previous 31 days SR 3.6.4.1.5 Verify each standby gas treatment (SGT) 18 months on a subsystem will draw down the secondary STAGGERED TEST containment to a 0.25 inch of vacuum BASIS water gauge in 5 567 seconds.

SR 3.6.4.1.6 Verify each SGT subsystem can maintain 18 months on a

= 0.25 inch of vacuum water gauge in the STAGGERED TEST secondary containment for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a BASIS flow rate s 3000 cfm.

[v "

FERMI UNIT 2 3.6 42 Amendment No. 134

SCIVs 3.6.4.2

_3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment' Isolation' Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3.

During movement of irradiated fuel assemblies in the secondary containment.

During. CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (0PDRVs). ,

ACTIONS l

.....................................N0TES------------ ------ ---- -- - - ----

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

/~s 3. Enter applicable Conditions and Required Actions for systems made V inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months penetration flow paths )enetration flow path with one SCIV )y use of at least inoperable. one closed and de activated automatic valve, closed manual valve.

or blind flange.

AND (continued)

O FERMI UNIT 2 3.6 43 Amendment No. 134

SCIVs 3.6.4.2

/

( ACTIONS s_

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --

---NOTES-------- '

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative 1 means.

Verify the affected Once per 31 days penetration flow path

T is isolated.

(G B. --

- - NOTE----- --- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path ,

penetration flow paths by use of at least !

with two isolation one closed and valves. de activated

...................... automatic valve, closed manual valve.

One or more or blind flange.

penetration flow paths with two SCIVs inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met in MODE 1, 2. or 3. C .;2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

() (continued)

FERMI UNIT 2 3.6-44 Amendment No. 134

SCIVs 3.6.4.2 O ^c" o"s (co"t4""ed)

CONDITION COMPLETION TIME i

REQUIRED ACTION l l

D. Required Action and - ------ ---NOTE -- -- - -

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A ---- -------- ---------

or B not met during movement of irradiated D.1 Suspend movement of Immediately fuel assemblies in the irradiated feel secondary containment, assemblies in the during CORE secondary ALTERATIONS, or during containment.

OPDRVs.

D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to Immediately suspend OPDRVs.

O i

O FERMI - UNIT 2 3.6 45 Amendment No. 134

E ,

SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ------------ --

-NOTES--------- -- - --

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment 31 days isolation manual valve and blind flange not locked, sealed, or otherwise secured that is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each power In accordance operated automatic SCIV is within limits. with the t Inservice Testing Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to 18 months !

the isolation position on an actual or '

simulated actuation signal.

l O

FERMI UNIT 2 3.6 46 Amendment No. 134

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

During movement of irradiated fuel assemblies in the j secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor i vessel (0PDRVs).

I l

ACTIONS

{

l CONDITION REQUIRED ACTION COMPLETION TIME j A. One SGT subsystem A.1 Restore SGT 7 days inoperable. subsystem to OPERABLE status.

I B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

)

I O

FERMI - UNIT 2 3.6 47 Amendment No. 134

i I

l SGT System j l 3.6.4.3 l l

l '/ O. ACTIONS (continued)

! V CONDITION REQUIRED ACTION COMPLETION TIME l 1

1 C. Required Action and ---

-- -- -NOTE -- - ----- -

associated Completion LC0 3.0.3 is not applicable.

Time of Condition A -- ----- ---- -- ------- --

not met during movement of irradiated C.1 Place OPERABLE SGT Immediately ,

fuel assemblies in the subsystem in secondary containment, operation.

during CORE ALTERATIONS, or during @ ;

OPDRVs.

C.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

l O

V AND C.2.3 Initiate action to Immediately suspend OPDRVs.

i D. Two SGT subsystems D.1 Enter LC0 3.0.3. Immediately inoperable in MODE 1, l

2. or 3.

I (continued) l l l O

I FERMI UNIT 2 3.6 48 Amendment No. 134 l

l

L 1 SGT System 3.6.4.3

(]. ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

-- ------- NOTE---

E. Two SGT subsystems -- - -

inoperable during LC0 3.0.3 is not applicable.

movement of irradiated - -- - ------ --- --

fuel assemblies in the l secondary E.1 Suspend movement of Immediately containment, during irradiated fuel CORE ALTERATIONS or assemblies in i during OPDRVs. secondary containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to Immediately suspend OPDRVs.

O 1

i l

l l

l v

FERMI UNIT 2 3.6 49 Amendment No. 134 1

l J

c ..

)

SGT System 3.6.4.3

'{} SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 3.6.4.3.1 Operate each SGT subsystem for a 10 31 days continuous hours with heaters operating.

l SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 18 months actual'or simulated initiation signal.

1 SR 3.6.4.3.4 Verify each SGT filter cooler bypass 18 months damper can be opened and the fan started.

1 i

l I

I l

O FERMI UNIT 2 3.6-50 Amendment No. 134 L

RHRSW System 3.7.1

& 3.7 PLANT SYSTEMS v

3.7.1 Residual Heat Removal Service Water (RHRSW) System LC0 3.7.1 Two RHRSW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1. 2. and 3. i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW pump A.1 Restore RHRSW pump to 30 days inoperable. OPERABLE status.

B. One RHRSW pump in each B.1 Restore one RHRSW 7 days subsystem inoperable. pump to OPERABLE status.

C. One RHRSW subsystem C.1- ----- - NOTE-- --- --

inoperable for reasons Enter applicable other than Conditions and !

i Condition A. Required Actions of !

LC0 3.4.8, " Residual Heat Removal (RHR) 3 Shutdown Cooling :

System- Hot '

Shutdown." for RHR shutdown cooling made inoperable by RHRSW System.

Restore RHRSW 7 days subsystem to OPERABLE status.

(continued)

FERMI UNIT 2 3.7 1 Amendment No. 134

RHRSW System

, 3.7.1 l

'4 ACTIONS (continued) 1 (G COMPLETION TIME CONDITION REQUIRED ACTION l

D. Both RHRSW subsystems D.1 --- -NOTE----- --- -

inoperable for reasons Enter applicable l other than Conditions and Condition B. Required Actions of LC0 3.4.8 for RHR shutdown cooling made inoperable by RHRSW System.

j Restore one RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months i

subsystem to OPERABLE status.

l E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l l

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ;

L SR 3.7.1.1 Verify each RHRSW manual, power operated. 31 days i I

and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

c lO FERMI UNIT 2 3.7 2 Amendment No. 134

EECW/EESW System and UHS ,

3.7.2 I

3.7 PLANT SYSTEMS 3.7.2 Emergency Equipment Cooling Water (EECW)/ Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (VHS) ;

i LC0 3.7.2 Two EECW/EESW subsystems and UHS shall be OPERABLE. !

APPLICABILITY: MODES 1, 2 and 3. ;

i l

ACTIONS l 1

.......................................N0TES--- -------- --------------- ----

1. Enter applicable Conditions and Required Actions of LC0 3.8.1. "AC Sources-0perating." for diesel generator made inoperable by UHS.

2. Enter applicable Conditions and Required Actions of LC0 3.4.8. " Residual I Heat Removal (RHR) Shutdown Cooling System Hot Shutdown." for RHR shutdown cooling made inoperable by EECW/EESW or UHS.

l O CONDITION COMPLETION TIME

.() REQUIRED ACTION A. UHS ino>erable due to A.1 Restore VHS cross tie 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inopera)le cross-tie lines to OPERABLE line(s).

status.

B. One reservoir B.1 Restore reservoir to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

C. One EECW/EESW C.1 Restore the EECW/EESW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable subsystem to OPERABLE for reasons other than status.

Conditions A and B.

(continued)

O FERMI UNIT 2 3.7 3 Amendment No. 134

i EECW/EESW System and UHS !

3.7.2

/ ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

associated Completion Time of Condition A. AND B, or C not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E

Both EECW/EESW subsystems ino>erable for reasons otler than Condition A.

UHS inoperable for reasons other than Conditions A and B.

O l b ,

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level of each UHS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reservoir. and the average water level of each of the two reservoirs, are a 25 ft.

SR 3.7.2.2 Verify the average water temperature of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months each reservoir, and combined average water temperature of the two reservoirs, are s 80*F. j i

(continued) !

i U,,

FERMI - UNIT 2 3.7 4 Amendment No. 134

i EECW/EESW System and UHS 3.7.2

(]~ SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.2.3 - - --- - -

NOTE- - - ----------

Fast speed testing not required to be performed during icing periods.

Operate each cooling tower fan on slow 31 days speed and on fast speed. each for {

= 15 minutes.

l SR 3.7.2.4 -- - --- -

- --- NOTE-- --------------- -

Isolation of EECW flow to individual components does not render EECW System inoperable.

Verify each EECW/EESW subsystem and UHS 31 days manual, power o)erated. and automatic valve.

. in the flow pat 1s servicing safety related systems or components, that is not locked.

sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.5 Verify each EECW/EESW subsystem actuates on 18 months I an actual or simulated initiation signal. '

1 O

FERMI UNIT 2 3.7 5 Amendment No. 134

r CREF System '

3.7.3 I 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Filtration (CREF) System LC0 3.7.3 The CREF System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

During movement of irradiated fuel assemblies in the !

secondary containment. l During CORE ALTERATIONS, I During operations with a potential for draining the reactor vessel (0PDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I

A. One CREF subsystem A.1 Restore CREF 7 days inoperable. subsystem to OPERABLE status. i O. ;

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

associated Completion Time of Condition A ANJ not met in MODE 1, 2.

or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued) f3 U

FERMI UNIT 2 3.7-6 Amendment No. 134

CREF System 3.7.3 f) ACTIONS (continued) v CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and -- --.-

NOTE -- - -- -

associated Completion LC0 3.0.3 is not applicable.

Time of Condition A -- -- ------ ----- --- --

not met during !

movement of irradiated C.1 Place OPERABLE CREF Immediately I fuel assemblies in the subsystem in secondary containment, recirculation mode.

during CORE ALTERATIONS. or during 2 OPDRVs.

C.2.1 Initiate action to Immediately suspend OPDRVs.

AN._Q

..............N0TE------- ---

Not required for a CREF System or subsystem inoperable for performance of

'SR 3.7.3.6 due to failure to O provide the required filtration efficiency. or due U

to replacement of charcoal l filtration media. l C.2.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND C.2.3 Suspend CORE Immediately ALTERATIONS.

(continued)

.O FERMI UNIT 2 3.7-7 Amendment No. 134

CREF System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two CREF subsystems or D.1 Enter LCO 3.0.3. Immediately-a non redundant component or portion of the CREF System inoperable in MODE 1, 2, or 3.

E. Two CREF subsystems or ----- -

---NOTE--------- - -

a non redundant LCO 3.0.3 is not applicable.

component or portion ---------- -------- - --- ---

of the CREF System inoperable during . E.1 Initiate action to Immediately movement of irradiated suspend OPDRVs.

fuel assemblies in the secondary containment, 8@

during CORE ALTERATIONS, or during --

-- --NOTE - -- -----

OPDRVs. Not required for a CREF

/'h System or subsystem V inoperable for performance of SR 3.7.3.6 due to failure to provide the reguired filtration efficiency. or due to replacement of charcoal filtration media.

E.2 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND E.3 Suspend CORE Immediately ALTERATIONS.

O FERMI - UNIT 2 3.7 8 Amendment No. 134

CREF System 3.7.3 SURVEILLANCE REQUIREMENTS i SURVEILLANCE FREQUENCY

.SR 3.7.3.1 Operate one CREF subsystem for = 10 31-days on a continuous hours with the heater operating STAGGERED TEST and operate the other CREF subsystem BASIS for e 75 minutes.

SR 3.7.3.2 ----- - ----- -- NOTE--------- -- - ----

When the CREF system is made inoperable in '

MODE 1. 2. or 3 solely for VFTP required surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Perform required CREF filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

O SR 3.7.3.3 Visually inspect silicone sealant on 12 months accessible portions of CREF system duct work outside the control room that are at negative pressure during accident l conditions and for which potential in-leakage would not receive full filtration.

SR .3.7.3.4 Verify each CREF subsystem actuates on an 18 months actual or simulated initiation signal.

(continued) l 1

'O i V

FERMI - UNIT 2 3.7 9 Amendment No. 134

1 CREF System 3.7.3 t SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l SR 3.7.3.5 Verify each CREF subsystem can maintain a 18 months .

positive pressure of = 0.125 inches water on a gauge relative to the outside atmosphere STAGGERED during the recirculation mode of operation TEST BASIS at a makeup flow rate of s 1800 cfm.

SR 3.7.3.6 Verify that unfiltered inleakage from CREF 36 months system duct work outside the Control Room envelope that is at negative pressure during accident conditions is within limits.

(3 V 1 (9

'J FERMI UNIT 2 3.7 10 Amendment No. 134

Control Center AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Center Air Conditioning (AC) System LC0 3.7.4 Two control center AC subsystems shall be OPERABLE. -

APPLICABILITY: MODES 1. 2, and 3.

During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (0PDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control center AC A.1 Restore control 30 days subsystem inoperable. center AC subsystem to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months -

associated Completion.

Time of Condition A 8N_Q not met in MODE 1, 2.

or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

FERMI UNIT 2 3.7 11 Amendment No. 134 t

Lj .. . . .. . .

l Control Center AC System 3.7.4 ACTIONS (continued) _ _ _ _

CONDITION REQUIRED ACTION COMPLETION TIME !

C. Required Action and --- - NOTE-- -- --- ---

associated Completion LC0 3.0.3 is not applicable. I Time of Condition A ---- -- -- -- - -- --

not met during movement of irradiated C.1 Place OPERABLE Immediately fuel assemblies in the control center AC secondary containment, subsystem in !

I during CORE operation. '

l ALTERATIONS. or during OPDRVs. QB l

C.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment. l

! I E i C.2.2 Suspend CORE Immediately )

ALTERATIONS.

m C.2.3 Initiate action to Immediately ;

suspend OPDRVs.

l D. Two control center AC D.1 Enter LC0 3.0.3. Immediately l subsystems inoperable l in MODE 1, 2. or 3.

(continued) l l

.O FERMI UNIT 2 3.7 12 Amendment No. 134

Control Center AC System 3.7.4 ACTIONS (continued)

C0WITION REQUIRED ACTION COMPLETION TIME E. Two control center AC - ---

- NOTE---- - --- -

subsystems inoperable LC0 3.0.3 is not applicable.

during movement of - - -- - --- -- --- --

irradiated fuel assemblies in the E.1 Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS or during secondary 0PORVs. containment.

M E.2 Suspend CORE Immediately ALTERATIONS.

M l E.3 Initiate actions to Immediately suspend OPDRVs.

1

' SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY i

SR 3.7.4.1 Verify the control room air temperature is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s 95*F. ,

i

.O FERMI - UNIT 2 3.7 13 Amendment No. 134

I L Main Condenser Offgas l 3.7.5 !

} 3.7 PLANT SYSTEMS 3.7.5 Main Condenser Offgas l

l LCO 3.7.5 The gross radioactivity rate of the noble gases measured at the discharge of the 2.2 minute delay piping shall be 5 340 mC1/second after decay of 30 minutes.

APPLICABILITY: MODE 1.

MODES 2 and 3 with any main steam line not isolated and steam jet air ejector (SJAE) in operation.

1 ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME A. Gross radioactivity A.1 Restore gross 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rate of the noble radioactivity rate of gases not within the noble gases to ;

limit, within limit. !

l l

I B. Required Action and B.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months !

associated Completion steam lines Time not met.

2 B.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E

B.3.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

[v FERMI UNIT 2 3.7 14 Amendment No. 134

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 -

--- ---- -- - -NOTE--- ---- -- -------

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross radioactivity rate of the 31 days noble gases is s 340 mci /second after decay of 30 minutes.

SR 3.7.5.2 Verify the gross radioactivity rate of the Once within noble gases is s 340 mci /second 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a after decay of 30 minutes. = 50% increase in the nominal

, steady state fission gas release after c factoring out increases due to changes in THERMAL POWER level 1

I FERMI UNIT 2 3.7-15 Amendment No. 134

Main Turbine Bypass System and Moisture Separator Reheater 3.7.6 3.7 PLANT SYSTEMS 3.7.6 The Main Turbine Bypass System and Moisture Separator Reheater LC0 3.7.6 The Main Turbine Bypass System and Moisture Separator -

Reheater shall be OPERABLE.

DB LC0 3.2.2, " MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System and Moisture Separator Reheater, as specified in the COLR, are made applicable.

APPLICABILITY: THERMAL POWER = 25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A LC0 not met. requirements of the V LCO.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 25% RTP.

Time not met.

O FERMI UNIT 2 3.7 16 Amendment No. 134

l Main Turbine Bypass System and Moisture Separator Reheater 3.7.6 l

rD V SURVEILLANCE REQUIREMENTS 1

l SURVEILLANCE FREQUENCY

.SR 3.7.6.1 Verify one complete cycle of each main 92 days turbine bypass valve.

l Once after each entry into MODE 4 l SR 3.7.6.2 Perform a system functional test. 18 months i I

l SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 18 months TIME is within limits. I l

l c

b FERMI UNIT 2 3.7 17 Amendment No. 134 i

Spent Fuel Storage Pool Water Level 3.7.7

'(3 V 3.7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LC0 3.7.7 The spent fuel storage pool water level shall be = 22 ft over the top of irradiated fuel assemblies seated in the 1 spent fuel storage pool racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent l fuel storage pool. !

1 1

ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 ------- NOTE - -- ---

pool water level not LC0 3.0.3 is not within limit. applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water 7 days !

level is a 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

i I

FERMI UNIT 2 3.7 18 Amendment No. 134

L l l

EDGSW System 3.7.8 i

/3 3.7 PLANT SYSTEMS i U l 3.7.8 Emergency Diesel Generator Service Water (EDGSW) System LC0 3.7.8 Four FDGSW subsystems shall be OPERABLE. -

APPLICABILITY: When associated EDG is required to be OPERABLE. ,

ACTIONS {

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EDGSW A.1 Declare associated Immediately subsystems inoperable. EDG(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify each EDGSW subsystem manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.2 Verify each EDGSW subsystem pump starts 18 months automatically when the associated EDG <

starts.

FERMI UNIT 2 3.7 19 Amendment No. 134

AC Sources-Operating 3.8.1

~

3.8 ELECTRICAL POWER ~ SYSTEMS-3.8.1 AC Sources-Operatings LC0 3.8.1 The. following AC electrical power sources shall be OPERABLE:

-a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Two emergency diesel generators (EDGs) per division.

A APPLICABILITY: MODES 1, 2. and 3.

ACTIONS:

. CONDITION REQUIRED ACTION COMPLETION TIME A. One or both EDGs in. A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

, one division for OPERABLE offsite inoperable. circuit (s). AN12 Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 8NQ A.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from

. feature (s), supported discovery of an by the inoperable inoperable EDG EDGs. inoperable when concurrent with the redundant inoperability of required feature (s) redundant are inoperable, required feature (s) 8N_Q A.3 Verify the status of Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months CTG 11-1.

(continued)

O

' FERMI - UNIT 2. 3.8 1 Amendment No. 134

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months -

EDG(s) are not inoperable due to common cause failure.

2 A.4.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for OPERABLE EDG(s).

AN_Q A.5 Restore availability 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from of CTG 11 1. discovery of Condition A concurrent with CTG 11-1 not available AND D

(/ A.6 Restore both EDGs in 7 days j the division to OPERABLE status.

l 1

B. One or both EDGs in B.1 Restore both EDGs in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months both divisions one division to inoperable. OPERABLE status. i l

C. One or two offsite C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuits inoperable.

% MD Required Action and C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Associated Completion Time of Condition A or B not met.

!3 V

FERMI UNIT 2 3.8 2 Amendment No. 134

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker . alignment and 7 days indicated power availability for each offsite circuit.

I l

SR 3.8.1.2 -

- - -- ---- ----NOTES-- -- - --- ---

1. All EDG starts may be receded by an engine prelube period nd followed by a warmup period prior to loading. )

{

.2. A modified EDG start involving idling i and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

Verify each EDG starts and achieves steady 31 days state voltage = 3740 V and s 4580 V and frequency = 58.8 Hz and s 61.2 Hz.

SR 3.8.1.3 --- --- ---- -

- NOTES - - - - - -

1. EDG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients below the iced limit do not invalidate this test.

3. This Surveillance shall be conducted on only one EDG at a time.

Verify each EDG is synchronized and loaded 31 days and operates for = 60 minutes at a load a 2500 kW.

(continued)

' FERMI UNIT 2 3.83 Amendment No. 134 l

l

p AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains = 210 gal of 31 days -

. fuel oil.

SR 3.8.1.5 Check for and remove accumulated water from 31 days each day tank.

SR 3.8.1.6 Verify each fuel oil transfer system 31 days operates to automatically transfer fuel oil from storage tanks to the day tanks.

SR 3.8.1.7 -- --- -- - - -

- NOTE --- - - -------

All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

( ...........................................

Verify each EDG starts from standby 184 days condition and achieves: I

a. In s 10 seconds, voltage = 3740 V and frequency = 58.8 Hz: and

b. Steady state voltage = 3740 V and s 4580 V and frequency = 58.8 Hz and 5 61.2 Hz. ,

SR 3.8.1.8 Verify each EDG rejects a load greater than 18 months or equal to its associated single largest post accident load, and following load rejection, the frequency is s 66.75 Hz.

(continued) k .

FERMI UNIT 2 3.8 4 Amendment No. 134

1 AC Sources-Operating I 3.8.1 !

I SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY f SR 3.8.1.9 Verify each EDG does not trip and voltage 18 months -

is maintained s 4784 V during and following a load rejection of a 2850 kW.

I SR 3.8.1.10 -- ------- ------ -NOTE-- ------------ ---

All EDG starts may be preceded by an engine prelube period. j

........................................... i Verify on simulated loss of offsite power 18 months j signal: I

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and )

c. EDG auto starts and:

1. energizes permanently connected loads in s 10 seconds,

2. energizes auto-connected shutdown loads through load sequencer.

3. maintains steady state voltage a 3740 V and s 4580 V.

4. maintains steady state frequency a 58.8 Hz and 5 61.2 Hz, and

5. supplies permanently connected and auto-connected shutdown loads for a 5 minutes.

(continued)

O FERMI UNIT 2 3.8 5 Amendment No. 134

1 l

AC Sources-Operating !

3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 ---- - --- -- .--- NOTE---------- - --- - -

All EDG starts may be preceded by an engine prelube period.

Verify on an actual or simulated Emergency 18 months Core Cooling System (ECCS) initiation signal each EDG auto starts and:

a. In s 10 seconds after auto start and during tests, achieves voltage

= 3740 V and frequency = 58.8 Hz:

b. Achieves steady state voltage = 3740 V and s 4580 V. and frequency = 58.8 Hz and s 61.2 Hz: and ;

i

c. Operates for a 5 minutes. I SR 3.8.1.12 Verify each EDG's automatic trips are 18 months bypassed on an actual or simulated emergency start signal except:

a. Engine overspeed:

b. Generator differential current:

c. Low lube oil pressure;

d. Crankcase overpressure: and

e. Failure to start. l (continued)

(' s FERMI UNIT 2 3.8 6 Amendment No. 134

n. .

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13. - - -- - -- -

NOTE- -- -- - - - ---- -

Momentary transients outside the load range.

do not invalidate this test.

Verify each EDG operates for = 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: 18 months

a. For all but the final = 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded

= 2500 kW and s 2600 kW: and )

b. For the final = 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of the test loaded a 2800 kW and s 2900 kW.

SR 3.8.1.14 ----- -- --

- - NOTES ------ -- -- - ---

1. This Surveillance shall be performed within 5 minutes of shutting down the EDG after the EDG has operated

= 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded = 2500 kW or until O.

operating temperatures have stabilized.

Momentary transients below the load

' limit do not invalidate this test.

2. All EDG starts may be preceded by an engine prelube period.

Verify each EDG starts and achieves: 18 months

a. In s 10 seconds, voltage = 3740 V and frequency = 58.8 Hz: and

b. Steady state voltage = 3740 V and s 4580 V and frequency = 58.8 Hz and 5 61.2 Hz.

(continued) l

(~h A.J

' FERMI UNIT 2 3.87 Amendment No. 134

1 AC Sources-Operating 3.8.1

( ' SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 Verify each EDG: 18 months .

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source: and

c. Returns to standby status.

SR 3.8.1.16 Verify interval between each sequenced 18 months ,

load block is within i 10% of design l interval for each load sequencer timer.

(continued)

(-

J

\

1

%J FERMI UNIT 2 3.8 8 Amendment No. 134

AC Sources-Operating i 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 -- ---

-- -----NOTE - -- -- -- - --- -

All EDG starts may be preceded by an engine prelube period. l Verify, on simulated loss of offsite power 18 months signal in conjunction with an actual or simulated ECCS initiation signal:

a. De energization of emergency buses;

b. Load shedding from emergency buses:

and

c. EDG auto starts and:

1. energizes permanently connected loads in s 10 seconds, !

l

2. energizes auto-connected i O

V emergency loads through load sequencer.

3. achieves steady state voltage

= 3740 V and s 4580 V.

4. achieves steady state frequency

= 58.8 Hz and s 61.2 Hz, and

5. supplies permanently connected and auto connected emergency loads for a 5 minutes.

I SR 3.8.1.18 -

- - -- -- -- -NOTE ---- - -- - -

All EDG starts may be preceded by an engine prelube period.

Verify, when started simultaneously each 10 years EDG achieves, in s 10 seconds, frequency

= 58.8 Hz.

FERMI - UNIT 2 3.8 9 Amendment No. 134

n AC Sources-Shutdown 3.8.2 O 3.8 e'eC1a1Ca' eowea Sv5TEMs 3.8.2 AC Sources-Shutdown LC0 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem (s) required by LC0 3.8.8.

" Distribution Systems-Shutdown"; and

b. Two emergency diesel generators (EDGs) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem (s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5.

During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

.................................... NOTE ----- ---- - -- - - ------ ------ -

LC0 3.0.3 is not applicable.

n ..............................................................................

V CONDITION REQUIRED ACTION COMPLETION TIME I A. One required offsite -- ------ -NOTE- --- -- -

circuit inoperable. Enter applicable Condition and Required Actions of LC0 3.8.8. with one required division de-energized as a result of Condition A.

A.1 Declare affected Immediately required feature (s),

with no offsite power available, inoperable.

(continued) {

.o FERMI - UNIT 2 3.8 10 Amendment No. 134

l AC Sources-Shutdown 3.8.2

( ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Suspend CORE Immediately- 1 ALTERATIONS.

M A.2.2 Suspend movement of Immediately l irradiated fuel I assemblies in the secondary containment.

E A.2.3 Initiate action to Immediately sus)end operations wit 1 a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

(continued)

O FERMI UNIT 2 3.8 11 Amendment No. 134

AC Sources-Shutdown 3.8.2

[]

v ACTIONS (continued)

CONDITION REQllIRED ACTION COMPLETION TIME B. One or both required B.1 Suspend CORE Immediately-EDGs inoperable. ALTERATIONS.

M B.2 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

M B.3 Initiate action to Immediately suspend OPDRVs.

AND B.4 Initiate action to Immediately restore required EDGs

(]

%.)

to OPERABLE status.

SURVEILLANCE REQUIREME,NTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -- ---------- -

NOTE - ---- - ----- --

The following SRs are not required to be performed: SR 3.8.1.2, SR 3.8.1.3, and SR 3.8.1.7 through SR 3.8.1.17.

For AC sources required to be OPERABLE In accordance SR 3.8.1.1 through SR 3.8.1.17, are with applicable applicable. SRs I

FERMI UNIT 2 3.8 12 Amendment No. 134

1 Diesel Fuel Oil and Starting Air 3.8.3 Q(~'\ 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil and Starting Air LC0 3.8.3 The stored diesel fuel oil and starting air subsystem shall be within limits for each required emergency diesel generator (EDG).

APPLICABILITY: When associated EDG is required to be OPERABLE.

ACTIONS

..................................... NOTE- --- - - -- - ------ - - --------

Separate Condition entry is allowed for each EDG.

CONDITION REQUIRED ACTION COMPLETION TIME

. A. One or more required A.1 Restore fuel oil 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EDGs with fuel oil level to within v . level < 35.280 gal and limits.

> 30,240 gal in storage tank.

B. One or more required B.1 Restore fuel oil 7 days EDGs with stored fuel total particulates to oil total particulates within limit.

not within limit, j

I C. One or more required C.1 Restore stored fuel 30 days !

EDGs with new fuel oil oil properties to l properties not within within limits. i limits.

(continued)

D i O

FERMI UNIT 2 3.8-13 Amendment No. 134

F Diesel Fuel Oil and Starting Air 3.8.3 O' ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME i 1

D. Required Action and D.1 Declare associated Immediately associated Completion EDG inoperable.

Time not met.

E One or more required EDGs with diesel fuel oil, or starting air subsystem not within limits for reasons other than Condition A, B, or C.

('] SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each required EDG fuel oil storage 31 days tank contains = 35,280 gal of fuel.

SR 3.8.3.2 Verify each required EDG fuel oil In accordance properties of new and stored fuel oil are with the tested in accordance with, and maintained Emergency within the limits of, the Emergency Diesel Diesel Generator Fuel Oil Testing Program. Generator Fuel Oil Testing Program (continued)

O FERMI UNIT 2 3.8 14 Amendment No. 134

Diesel Fuel Oil and Starting Air 3.8.3 i t SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.8.3.3 Verify each required EDG air start receiver pressure.is = 215 psig.

31 days -

)

SR 3.8.3.4 Check for and remove accumulated water from 31 days each required EDG fuel oil storage tank.

i O

i O ;

FERMI UNIT 2 3.8 15 Amendment No. 134

=

DC Sources-Operating 3.8.4

. 3.8 ELECTRICAL POWER' SYSTEMS 3.8.4 DC Sources-Operating

.LCO '3.8.4 The Division I and Division II DC electrical power -

. subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3.

ACTIONS C0WITION REQUIRED ACTION COMPLETION TIME i I

A. One battery charger A.1 Restore battery 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable. charger to OPERABLE )

status.

4

'B. One DC electrical B.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystem power subsystem to inoperable for reasons OPERABLE status. 4 other than Condition A. j l

C. Re' quired Action and- C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

. Associated Completion Time not met. A!gl ,

1 C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 4 l

l l

1 i

O FERMI ' UNIT 2' 3.8 16 Amendment No. 134

DC Sources-Operating 3.8.4 O suavetu ^"ce aeou'aeaea's SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is = 130 V 7 days -

for Division I and = 125.7 V for Division II on float charge.

SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

DB j Verify each battery cell to cell and terminal connection resistance is s 1.5E-4 ohm.

SR 3.8.4.3 Verify battery cells, cell plates, and 18 months ,

racks show no visual indication of physical I damage or abnormal deterioration that could O degrade battery performance.

SR 3.8.4.4 Remove visible corrosion and verify battery 18 months cell to cell and terminal connections are coated with anti-corrosion material.

SR 3.8.4.5 Verify each battery cell-to-cell and 18 months terminal connection resistance is '

s 1.5E-4 ohm.

SR -3.8.4.6 Verify each required battery charger 18 months supplies for Division I: a 100 amps r; a 129 V for a 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and for Divisiv II:

a 100 amps at = 124.7 V for a 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(continued)

.O FERMI - UNIT 2 3.8 17 Amendment No. 134

DC Sources-Operating 3.8.4

' SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.7- ....................N0TE-----.---..-.-. --- -

The performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 once per 60 months.

Verify battery capacity is adequate to 18 months supply. and maintain in OPERABLE status, the actual or simulated emergency loads for !

the design duty cycle when subjected to a i battery service test.

SR 3.8.4.8 -.-.- .-.....- .N0TE-..------- . --.----

This Surveillance shall not be performed in MODE 1. 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is = 80% of the 60 months manufacturer's rating when subjected to a performance discharge test. ANQ 18 months when battery shows degradation or has reached 85%

of expected life O

FERMI UNIT 2 3.8 18 Amendment No. 134 i i

I

DC Sources-Shutdown 3.8.5 l

.3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 The following shall be OPERABLE:

a. One DC electrical power subsystem capable of supplying one division of the onsite Class 1E electrical power distribution subsystem (s) required by LC0 3.8.8.

" Distribution System Shutdown":'and

b. One DC electrical power subsystem battery or battery charger. other than that required by LC0 3.8.5.a. !

capable of supplying the remaining onsite Class 1E -

electrical power distribution subsystem (s) when required by LC0 3.8.8.

APPLICABILITY: MODES 4 and 5. l During movement of irradiated fuel assemblies in the 1 secondary containment.

ACTIONS

.....................................N0TE -- - - - -------- -------- - ----

LC0 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME

A. 'One or more required A.1 Declare affected Immediately DC electrical power required feature (s) subsystems inoperable, inoperable.

.08 (continued)

O FERMI. UNIT 2 3.8 19 Amendment No. 134

DC Sources-Shutdown 3.8.5 O ac'ioas C0WITION. REQUIRED ACTION COMPLETION TIME

)

j A. (continued) A.2.1 Suspend CORE Immediately.

ALTERATIONS.

m A.2.2 Suspend movement of Immediately ;

irradiated fuel !

assemblies in the ,

secondary j containment. j 1

I A.2.3 Initiate action to Immediately )

sus and operations wit 1 a potential for draining the reactor ,

I vessel.

AND

', l A.2.4 Initiate action to Immediately l restore required DC electrical power subsystems to OPERABLE status.

l l

O FEPJil UNIT 2 3.8 20 Amendment No. 134

DC Sources-Shutdown 3.8.5

'h SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 3.8.5.1 --- ------------ -NOTE- - --- - -- --- ---

The following SRs are not required to be performed: SR 3.8.4.6 SR 3.8.4.7, and SR 3.8.4.8.

For DC sources required to be OPERABLE the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8.

SR 3.8.4.3 SR 3.8.4.6 O

V i

,O FERMI - UNIT 2 3.8-21 Amendment No. 134

Battery Cell Parameters 3.8.6

/ 3.8 ELECTRICAL POWER S GTEMS 3.8.6 Battery Cell Parameters l LC0 3.8.6 Battery cell parameters for the Division I and Division II batteries shall be within liinits.

APPLICABILITL W.".ar, associated DC electrica'i oower subsystems are required to be OPERABLE.

ACTIONS )

i

.....................................N0Tr-- --- - - -- --- --------- ----

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME i

A. One or more batteries A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l p/

w.

, with one rc more battery ce l electrolyte level and float voltage meet parameters not within Table 3.8.6 1 4

-Table 3.8.6-1 Category Category C limits. '

A or B limits. l ANQ A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6 1 AND Categcry C limits.

Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Table 3.8.6 1 Category A and B limits.

(coittinued)

(V FERMI UNIT 2 3.8 22 Amendment No. 134

Battery Cell Parameters 3.8.6 O actions (comt4""eo)

CONDITION REQUIRED Ar'. inn COMPLETION TIME

.B. Required Action ar.d B.1 Declare associated Immediately associated Ccapletion battery inoperable.

Time of Condition A not met.

0B One or more batteries with average electrolyte temperature of the representative cells not within limits.

O_R.

One or more batteries with one or more battery cell parameters not within D Table 3.8.6-1 (s)' Category C values.

.* = gy -

SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify oattery cell parameters meet 7 days Table 3.8.6-1 Category A limits.

(continued)

FERMI - UNIT 2 3.8 23 Amendment No. 134 m

Battery Cell Parameters 3.8.6

{

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet 92 days Table 3.8.6 1 Category B limits.

AN_Q ,

1 Once within I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery discharge

< 105 V 8ND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery overcharge

> 150 V for Division I and

> 145 V for

, Division II k

SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is > 60*F. l I

O FERMI - UNIT 2 3.8 24 Amendment No. 134

l Battery Cell Parameters 3.8.6 f3 V Table 3.8.6 1 (page 1 of 1)

Battery Cell Parameter Requirements {

I CATEGORY A: CATEGORY C:

LIMITS FOR EACH CATEGORY B: ALLOWABLE -

DESIGNATED PILOT LIMITS FOR EACH LIMITS FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL l

Electrolyte > Minimum level > Minimum level Above top of Level indication mark, and indication mark, plates, and not s V inch above and s V inch above overflowing maximum level maximum level indication mark (a) indication mark (a) .

Float Voltage = 2.13 V a 2.13 V > 2.07 V i Specific = 1.195(c) = 1.190 Not more than Gravity (b) 0.020 below average of all ANJ n , connected cells Average of all connected cells ANA

> 1.200 Average of all connectid

= 1.190 c)cel.5 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level durir.g equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level.

'(c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits.

th U

FERMI.- UNIT 2 3.8-25 Amendment No. 134

= ~ ~

g Distribution Systems-Operating 3.8.7 l

h 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems-Operating i

LC0 3.8.7 The following Division I and Division II AC and DC -

electrical power distribution subsystems shall be OPERABLE:

a. AC electrical power distribution subsystems: 1 Divirion I p_ivision II

1. 4160 V Buses 11EA 12EB 13EC. 14ED 64B. 64C 65E. 65F

2. 480 V Buses 72EA 72EB 72EC 72ED 72B, 72C 72E 72F

3. 120 V MPU 1 MPU 2

b. DC electrical power distribution subsystems: I Division I Division II

1. 130 V Distribution 2PA-2 2PB-2

, Cabinet b 2. 260 V MCC 2PA-1 2PB-1 APPL 7CABILITY: MODES 1, 2 and 3. (

SW CONDITION REQUIRED ACTION COMPLETION TIME I A. One or more required A.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AC electrical power power distribution distribution subsystem (s) to AND subsystems inoperable. OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LC0 l

j (continued)

,O )

..V FERMI - UNIT 2 3.8-26 Amendmant No. 134 l

1 Distribution Systems-Operating 3.8.7 ACTIONS (continurgi)

CONDITi0ti REQUIRED ACTION COMPLETION TIME

, B. -One or more required B.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power power distribution distribution subsystem (s) to ale subsystems inoperable. OPERABLE status.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LC0 s

l C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i associated Completion Time of Condition A 8lQ or B not met.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Two or more required D.1 Enter LC0 3.0.3. Immediately O electrical power

' D. distribution

-subsystems inoperable that result in a loss

.of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and 7 days

' voltage to required AC and DC electrical power distribution subsystems.

l O

FERMI UNIT-2; 3.8 27 Amendment No. 134

Distribution Systems-Shutdown 3.8.8

- (m) 3.8 P/OF: CAL POWER SYSTEMS 3.8.8 Distribution Systems-Shutdown LC0 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY.: MODES 4 and 5.

During movement of irradiated fuel assemblies in the secondary containment.

ACTIONS

.......................................N0TE----------------- ------- - ----- -

LC0 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution feature (s) subsystems inoperable. inoperable.

E A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend handling of Immediately irradiated fuel assemblies in the secondary containment.

AND (continued) j l

l V(3 i i

FERMI UNIT 2 3.8 28 Amendment No. 134 j i

)

1 Distribution Systems-Shutdown 3.8.8 l

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to Immediately-suspend operations with a potential for draining the reactor vessel.

6ND A.2.4 Initiate actions to Immediately restore required AC j and DC electrical l power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem (s) inoperable and not in 5O operation. .

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage to required AC and DC electrical power distribution subsystems.

1%

,V FERMI - UNIT 2 3.8 29 Amendment No. 134

Refueling Equipment Interlocks 3.9.1 r

3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LC0 3.9.1 The refueling equipment interlocks associated with the refuel msition of the reactor mode switch shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in '

the refuel position. ,

ACTIONS I

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel Immediately refueling equipment fuel movement with interlocks inoperable. eguipment associated with the inoperable interlock (s).

1 l

O FERMI UNIT 2 3.9 1 Amendment No. 134

p-Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days )

the following required refueling equipment interlock inputs:

a. All-rods in,

b. Refuel platform position, l l

c. Refuel platform fuel grapple, fuel loaded,

d. . Refuel platform fuel grapple not fully retracted position,

e. Refuel platform frame mounted hoist, fuel loaded, and

f. Refuel platform monorail mounted hoist, fuel loaded.

l l

l

/'N FERMI UNIT 2 3.9 2 Amendment No. 134

Refuel Position One Rod Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One Rod Out Interlock LC0- 3.9.'2' The refuel position one rod out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION' REQUIRED ACTION COMPLETION TIME 1

' A. Refuel position one- A.1 Suspend control rod Immediately rod out interlock withdrawal.

inoperable.

NLD A.2 Initiate action to Immediately fully insert all O insertable control V rods in core cells containing one or more fuel assemblies.

I i

O FERMI UNIT 2 3.9 3 Amendment No. 134

Refuel Position One Rod Out Interlock .

3.9.2 I O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in Refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

SR 3.9.2.2 ----- - - -- -

NOTE ----- -- ---- ---

l Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CilANNEL FUNCTIONAL TEST. 7 days O

t I

._O FERMI UNIT 2 3.9-4 Amendment No. 134

D i p Control Rod Position 3.9.3

'3.9 REFUELING OPERATIONS' 3.9.3 . Control Rod Position L

LC03.9.3' All control rods shall be fully inserted.

APPLICABILITY: When loading fuel' assemblies into the core. .

]

l ACTIONS l

l 'C0WITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately -

rods not fully assemblies into the inserted. core. )

l O

l' l.

l v SURVEILLANCE REQUIREMENTS l- SURVEILLANCE ~ FREQUENCY l

'SR 3.9.'3.1 Verify all' control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

l b

(

L i

4 O

FERMI . UNIT 2. 3.9-5 Amendment No. 134 e

Control Rod Position Indication 3.9.4 (j 3.9 REFUELING OPERATIONS j 1

3.9.4 Control Rod Position Indication l LC0 3.9.4 The control rod " full-in" position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

i ACTIONS j

..................................... NOTE ---- - --------- -- - --------------

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1.1 Suspend in vessel Immediately rod " full-in" position fuel movement.

f)

N/

indication channels inoperable. I 6NQ

)

A.1.2 Sus)end control rod Immediately wit 1drawal.

AND A.1.3 Initiate action to Immediately I fully insert all insertable control rods in core cells I containing one or more fuel assemblies.

QR (continued) ,

i A

V_

FERMI UNIT 2 3.9 6 Amendment No. 134 L

Control Rod Position Indication 3.9.4 I

P G ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to Immediately fully insert the control rod

. associated with the l inoperable " full in" position indicator.

ANQ l A.2.2 Initiate action to Immediately disarm the control I

rod drive associated with the fully inserted control rod.

l y SURVEILLANCE REQUIREMENT SURVEILLANCE FREQUENCY l

SR 3.9.4.1 Verify the required channel has no Each time the

" full-in" indication on each control rod control rod is that is not " full in." withdrawn from l the " full in" position 1

1 1

FERMI UNIT 2 3.9 7 Amendment No. 134 L

Control Rod OPERABILITY-Refueling 3.9.5 m

(d 3.9 REFUELING OPERATIONS

_3.9.5 _ Contr01 Rod OPERABILITY-Refueling LC0 3.9.5 Each withdrawn control rod shall be OPERABLE.

I APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable. inoperable withdrawn-control rods.

1 O S_URVEILLANCE REQUIREMENTS I

J SURVEILLANCE FREQUENCY l SR 3.9.5.1 -

--NOTE--- --- ------ -----

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least 7 days one notch.

SR-'3.9.5.2~ ' Verify each; withdrawn control rod scram

- 7 days accumulator pressure is a 940 psig.

O FERMI -. UNIT 2' 3.9 8 Amendment No. 134 L .,

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure-Vessel (RPV) Water Level LCO .3.9.6' RPV water level shall be = 20 ft 6 inches above the top' of the RPV flange. l l

APPLICABILITY: During movement of irradiated fuel assemblies within the I RPV,-

During movement of new fuel ' assemblies or handling of I control rods within the RPV, when irradiated fuel <

assemblies are seated within the RPV.

ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of Immediately within limit. fuel assemblies and b

d handling of control !

rods within the RPV.

l 4

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is a 20 ft 6 inches 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months above the top of the RPV flange.

O FERMI UNIT-2 3.9 9 Amendment No. 134

RHR-High Water Level 3.9.7 1

m (j 3.9 REFUELING OPERATIONS l 3.9.7 Residual Heat Removal (RHR)-High Water Level l

l LC0 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE. -

l I

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV), the water level = 20 ft 6 inches above the top of the RPV flange, and heat losses to ambient not greater than or equal to heat input to reactor coolant.

l

! ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME l

l l

A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ;

cooling subsystem method of decay heat 1 inoperable. removal is available. AND A Once per V 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter l

l (continued) l l

l l

I h l L/

1 -

1 FERMI UNIT 2 3.9 10 Amendment No. 134

7.

RHR-High Water Level J 3.9.7 i

[} ACTIONS (continued) v CONDITION REQUIRED ACTION COMPLETION TIME ;

l B. Required Action and B.1 Suspend loading Immediately ,

associated Completion irradiated fuel ;

Time of Condition A assemblies into the !

not met. RPV. j AND B.2 Initiate action to Immediately restore secondary containment to OPERABLE status. j AND B.3 Initiate action to Immediately l restore one standby gas treatment subsystem to OPERABLE status.

^

( AND U) l B.4 Initiate action to Immediately j restore isolation !

capability in each required secondary containment l penetration flow path i not isolated. ;

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify the RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is capable of decay heat removal.

v FERMI - UNIT 2 3.9 11 Amendment No. 134

1 i

RHR-Low Water Level 3.9.8 U' 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR)-Low Water Level LC0 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, one RHR shutdown cooling subsystem shall be in operation. 1 1

............................N0TES -----

l

1. The required operating RHR shutdown cooling subsystem I may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per f 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period. ,

1

2. One RHR shutdown cooling subsystem may be inoperable I for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances. j

............................................................ j APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV), the water level < 20 ft 6 inches above the top of the RPV flange, and heat losses to ambient not greater than or equal to heat input to reactor coolant.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

l A. One or two required A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i RHR shutdown cooling method of decay heat I subsystems inoperable, removal is available AND for each inoperable required RHR shutdown Once per cooling subsystem. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued) b, , .

FERMI - UNIT 2 3.9 12 Amendment No. 134

p-RHR-Low Water Level 3.9.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to Immediately associated Completion restore secondary l Time of Condition A containment to not met. OPERABLE status.

AND B.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND 4 I

B.3 Initiate action to Immediately i restore isolation capability in each required secondary I containment i G penetration flow path C not isolated. !

C. No RHR shutdown C.1 Initiate action to Immediately cooling subsysi P in restore one RHR operation. shutdown cooling subsystem or one AND recirculation pump to operation.

No recirculation pump in operation. AND l C.2 Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from l coolant circulation discovery of no by an alternate reactor coolant method. circulation AND C.3 Monitor reactor Once per hour coolant temperature.

O FERMI UNIT 2 3.9 13 Amendment No. 134

r . j t

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or recirculation pump is operating.

SR 3.9.8.2 Verify each RHR shutdown cooling subsystem 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is capable of decay heat removal. l l

l O !

i iO FERMI'- UNIT 2- 3.9 14 Amendment No. 134

Inservice Leak and Hydrostatic Testing Operation i 3.10.1 1 3.10 SPECIAL OPERATIONS 3.10.1- Inservice Leak and Hydrostatic Testing Operation LC0 3.10.1 The average reactor coolant tem)erature specified in -

Table 1.11 for MODE 4 may be clanged to "NA," and operation considered not to be in MODE 3: and the requirements of 4 LC0 3.4.9, " Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown," may be suspended, ~ to allow !

performance of an inservice leak or hydrostatic test j provided the following MODE 3 LCOs are met: ;

1

a. LC0 3.3.6.2, " Secondary Containment Isolation '

Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.21:

b. LC0 3.6.4.1, " Secondary Containment":

c. LC0 3.6.4.2. " Secondary Containment Isolation Valves (SCIVs)"; and

d. LCO 3.6.4.3, " Standby Gas Treatment (SGT) System."

/~'

G APPLICABILITY: MODE 4 with average reactor coolant temperature > 200*F.

I

[

FERMI - UNIT 2 3.10 1 Amendment No. 134

i Inservice Leak and Hydrostatic Testing Operation 3.10.1 O

J ACTIONS

.....................................N0re.....................................

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME J

A. One or more of the A.1 - .

.--NOTE-- ------

above requirements not Required Actions to met. be in MODE 4 include reducing average l reactor coolant temperature to s 200*F.

Enter the applicable Immediately Condition of the l affected LC0.

QB

,e A.2.1 Suspend activities Immediately

\ that could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reactor coolant temperature to s 200*F.

t v

)

FERMI - UNIT 2 3.10 2 Amendment No. 134

r _..;

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS

(

l SURVEILLANCE FREQUENCY l

t l SR 3.10.1.1 Perform the applicable SRs for the required According to MODE 3 LCOs. the applicable SRs l

l O

l l

l O

FERMI UNIT 2 3.10 3 Amendment No. 134

r

. 1 Reactor Mode Switch Interlock Testing 3.10.2 h 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LC0 3.10.2 The reactor mode switch position specified in Table 1.1:1 for MODES 3, 4..and 5 may be changed to include the run, startup/ hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of-instrumentation associated with the reactor mode switch.

interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and

b. No CORE ALTERATIONS are in progress. ,

1

' APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run.

startup/ hot standby, or refuel position, MODE 5.with the reactor mode switch in the run or startup/ hot standby position.

CONDITION REQUIRED ACTION COMPLETION TIME i

A. One or more of the A.1 Suspend CORE Immediately above requirements not ALTERATIONS except met, for control rod insertion.

AN_Q A.2 Fully' insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months insertable control rods in core cells containing one or more fuel assemblies.

8NQ (continued)

O FERMI.-LUNIT 2

. 3.10 4 Amendment No. 134

Reactor Mode Switch Interlock T'esting 3.10.2 19 v

ACTIONS CONDITION REQUIRED ACTION COMPL'dTION TIME A. (continued) A.3.1 Place the rE2Ctor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months -

mode switch in the shutdown position. 4 E

A.3.2 ------- NOTE- --- ---

Only applicable in MODE 5.

Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the refuel position.

N SURVEILLANCE REQUIREMENTS (d.

SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in core cells containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months n

l

. fN \

L) . l l

FERMI - UNIT 2 3.10 5 Amen er t No. 134

n 1

Single Control Rod Withdrawal-Hot Shutdovo 3.10.3 ,

h 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal-Hot Shutdown LC0 3.10.3 The reactor mode switch position specified in Table 1.1-1 l for MODE 3 may oe changed to include the refuel position.

ardi .,aratic; considered not to be in MODE 2, to allow w)thdrawal of a single control rod, provided the following requirements are met:

a. LC0 3.9.2, " Refuel Position One Rod-Out Interlock";

b. LC0 3.9.4, " Control Rod Position Indication":

c. All other control rods are fully inserted; and

d. 1. LC0 3.3.1.1. " Reactor Protection System (RPS)

Instrumentation." MODE 5 requirements for Functions 1.a. 1.b. 8.a. 8.b, 11. and 12 of Table 3.3.1.1 1, and LC0 3.9.5, " Control Rod OPERABILITY-Refueling."

E O

b 2. All other control rods in a five by five array !

centered on the control rod being withdrawn are j disarmed; at which time LC0 3.1.1, " SHUTDOWN MARGIN '

(SDM)." MODE 3 requirements, may be changed to allow the single control rod withdrawn to be assumed to be l the highest worth control rod. J APPLICABILITY: MODE 3 with the reactor mt de switch in the refuel position.

i FERMI UNIT 2 3.10 6 Amendment No. 134

Single Control Rod Withoi ,,i -Hat Shutdown 3.10.3 ACTIONS

.....................................N01E.............................. ...... !

Separate Condition entry is allowed for each requirement of the LCO.

l CONDITION REQUIRED ACTION COMPLETION TIME l A. One or more of the A.1 ..- --..N0TES........ !

above requirements not 1. Required Actions met. to fully insert all insertable !

control rods i include placing !

the reactor mode switch in the shutdown position. ,

i

2. Only applicable if the requirement not met is a required LCO.

O V Enter the applicable Immediately Condition of the affected LCO.

OB A.2.1 Initiate action to Immediately fully insert all insertable control rods.

AND l

A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i mode switch in the shutdown position.

O

%)

FERMI . UNIT 2 3.10 7 Amendment No. 134 l 4

L.

1 Single Control Rod Withdrawal-Hot Shutdown 3.10.3 )

th SURVEILLANCE REQUIREMENTS !

SURVEILLANCE FREQUENCY i

SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.3.2 - .-----.--..- - . NOTE----- ---.---- ---

Not required to be met if SR 3.10.3.1 is satisfied for LC0 3.10.3.d.1 requirements.

l Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn, in a five by I five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months O control rod being withdrawn, are fully V , inserted.

i i

_C/

FERMI - UNIT 2 3.10 8 Amendment No. 134

Single Control Rod Withdrawal-Cold Shutdown 3.10.4 h 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal-Cold Shutdown

]

LC0 3.10.4 The reactor mode switch position specified in Table 1.1' 1 i for MODE 4 may be changed to include the refuel position. l and operation considered not to be in MODE 2, i:o allow '

withdrawal of a single control rod, and subsecuent removal of the associated control rod drive (CRD) if cesired, provided the following requirements are met:

a. All other control rods are fully inserted:

b. 1. LC0 3.9.2, " Refuel Position One Rod-Out Interlock,"

and LC0 3.9.4, " Control Rod Position Indication."

2. A control rod withdrawal block is inserted;

c. 1. LC0 3.3.1.1, " Reactor Protection System (RPS)

Instrumentation." MODE 5 requirements for Functions -1.a.1.b, 8.a. 8.b.11, and 12 of (O./ Table 3.3.1.1-1, and LC0 3.9.5, " Control Rod OPERABILITY-Refueling,"

1

2. All other control rods in a five by five array centered on the control rod being withdrawn are .

disarmed; at which time LC0 3.1.1, " SHUTDOWN MARGIN I (SDM) " MODE 4 requirements, may be changed to allow the single control rod withdrawn to be assumed to be the highest sorth control rod.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

A V.

FERMI UNIT 2 3.10 9 Amendment No. 134

c ,

i Single Control Rod Withdrawal-Cold Shutdown 3.10.4 l

ACTIONS

.....................................N0TE -

Separate Condition entry is allowed for each requirement of the LCO. {

CONDITION REQUIRED ACTION COMPLETION TIME h A. One or more of the A.1 - ---NOTES - - ---

above requirements not 1. Required Actions met with the affected to fully insert control rod- all insertable insertable. control rods include placing the reactor mode switch in the shutdow:

position.

2. Only applicable if the requirement not met-is a required Enter the applicable Immediately i Condition of the affected LC0.

E A.2.1 Initiate action to Immediately fully insert all

' insertable control rods.

AND A.2.2 Place the reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months mode switch in the shutdown position.

I (continued)

O. :

FERMI UNIT 2 3.10 10 Amendment No. 134

Single Control Rod Withdrawal-Cold Shutdown 3.10.4 ACTIONS (continued)

U(9 C0WITION REQUIRED ACTION COMPLETION TIME

>=

B. One or more of the B.1 Suspend withdrawal of Immediately-above requirements not the control rod and met with the affected removal of associated control rod not CRD.

insertable.

8ND B.2.1 Initiate action to Immediately fully insert all control rods.

08 B.2.2 Initiate action to Immediately satisfy the' requirements of this LCO.

O SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs. the applicable SRs SR 3.10.4.2 --

-- ---- - - - NOTE -- ---- - ----

. Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod being withdrawn. in a five by five array centered on the control rod being withdrawn, are disarmed.

(continued)

FERMI - UNIT 2 3.10 11 Amendment No. 134 1

J

r . 1 Single Control Rod Withdrawal-Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months !

control rod being withdrawn, are fully '

inserted.

SR -3.10.4.4 -- ------------ NOTE ------ ----- ---

Not required to be met if SR 3.10.4.1 is satisfied for LC0 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

l FERMI - UNIT 2 3.10 12 Amendment No. 134 L

Single CRD Removal-Refueling 3.10.5 l 3.10' SPECIAL OPERATIONS 3.10.5' Single Control Rod Drive (CRD) Removal-Refueling

. LCO 3.10.5 The' requirements of LC0 3.3.1.1, " Reactor Protection System (RPS) Instrumentation": LC0 3.3.8.2, " Reactor Protection System (RPS) Electric Power Monitoring": and LCO 3.9.5,

" Control Rod OPERABILITY-Refueling," may be suspended in MODE 5 to allow withdrawal of a' single control rod, and subsequent. removal of the associated CRD from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted: and

b. All' other control rods in a five by five array centered on the withdrawn control rod are disarmed; at which time LC0 3.1.1, " SHUTDOWN MARGIN (SDM)," MODE 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

AND In conjunction with a. and b. above, the requirements of LC0 3.9.1, " Refueling Equipment Interlocks": LC0 3.9.2.

O- " Refuel Position One Rod Out Interlock"; and LC0 3.9.4,

" Control Rod Position Indication": may be suspended provided the following requirements are met:

c. No other CORE ALTERATIONS are in progress; and

d. A control rod withdrawal block is inserted.

APPLICABILITY: MODE 5 with LC0 3.9.5 not met. !

O_

' FERMI - UNIT 2 3.10 13 Amendment No. 134

q 1 ,

Single CRD Removal-Refueling l 3.10.5 ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the A.1 Suspend removal of Immediateli above requirements not the CRD mechanism.

met.

81 0

- A.2.1 - Initiate action to' Immediately fully insert all control rods.

QB A.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

O l 1

FERMI,' UNIT 2 3.10 14 Amendment No. 134

r 3

Singl.e CRD Removal-Refueling 3.10.5

' SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. are fully inserted.

SR 3.10.5.2 ' erify all control rods, other than the V 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months control rod withdrawn for the removal of the associated CRD. in a five by five array centered on the control rod withdrawn for the removal of the associated CRD, are 1 disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inserted.

SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months progress.

1 4

FERMI UNIT 2 3.10 15 Amendment No. 134

7 q

Multiple Control Rod Withdrawal-Refueling 3.10.6

( 3.10 SPECIAL OPERATIONS 3.10.6' Multiple Control Rod Withdrawal-Refueling LCO 3.10.6 The requirements of LC0 3.9.3, " Control Rod Position": -

LC0 3.9.4, " Control Rod Position Indication"; and LC0 3.9.5.

" Control Rod OPERABILITY-Refueling," may be suspended, and the " full in" position indicators may be bypassed for any number of control rods in MODE 5. to allow withdrawal (withdrawal only, or withdrawal including removal) of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the associated core cells; and

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted.

APPLICABILITY: MODE 5 with LC0 3.9.3 LC0 3.9.4, or LC0 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME >

A. One or more of the A.1 Suspend withdrawal of Immediately above requirements not control rods and met, removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies. j AND )

(continued) i t

i j

(O_/ i FERMI - UNIT 2 3.10 16 Amendment No. 134 i

~

l Multiple Control Rod Withdrawal-Refueling 3.10.6 ACTIONS C]'

L CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to Immediately fully insert all control rods in core cells containing one or more fuel assemblies.

E A.3.2 Initiate action to Immediately satisfy the requirements of this l LCO.

1 SURVEILLANCE REQUIREMENTS l

() SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months containing one or more fuel assemblies are fully inserted.

~)

FERMI UNIT 2 3.10-17 Amendment No. 134

p .

) i SDM Test-Refueling 3.10.7 h 3.10 SPECIAL OPERATIONS-3.10.7 SHUTDOWN MARGIN (SDM) Test-Refueling LCO 3.10.7 The reactor mode switch position specified in Table 1.1'1 for MODE 5 may be changed to include the startup/ hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

-a. LCO 3.3.1.1, " Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a.

2.d. and 2.e of Table 3.3.1.1 1:

b. 1. LC0 3.3.2.1, " Control Rod Block Instrumentation "

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the prescribed withdrawal sequence requirements of SR 3.3.2.1.7 changed to require'the control rod sequence to conform to t.he SDM test sequence.

08

2. .Conformance to the approved control rod sequence for the SDM test is verified by a second licensed O.

operator or other qualified member of the technical l staff:

c. Each withdrawn control rod shall be coupled to the associated CRD:

d. All control rod withdrawals during local critical testing shall be made in notch out mode:

e. No other CORE ALTERATIONS are in progress; and

f. CRD charging water header pressure m 940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/ hot standby position, j i

n i d i FERMI - UNIT 2 -3.10 18 Amendment No. 134 j i

l l l

l SDM Test-Refueling i l 3.10.7 l l

( ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -- ---- NOTE- -- --- ---- -- ---- NOTE -- -- --

Separate Condition Rod worth minimizer may be entry is allowed for bypassed as allowed by each control rod. LC0 3.3.2.1 " Control Rod Block Instrumentation." if required, to allow insertion One or more of inoperable control rod and control rods not continued operation.

coupled to its --------- ----------- ------

l' associated CRD.

A.1 Fully insert the 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months uncoupled control rod.

AND A.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l CRD.

t U B. One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A. position.

A

_N)

FERMI - UNIT 2 3.10 19 Amendment No. 134 l

l

SDM Test-Refueling 3.10.7 O suave 1 uauce aeou1aeae"'s SURVEILLANCE FREQUENCY SR 3.10.7.1 Perform the MODE 2 applicable SRs for LC0 According to 3.3.1.1, Functions 2.a. 2.d. and 2.e of the applicable Table 3.3.1.1 1. SRs i

SR 3.10.7.2 ---- ----- --

- NOTE - - --------- -- -

Not required to be met if SR 3.10.7.3 satisfied.

Perform the MODE 2 applicable SRs for According to LC0 3.3.2.1, Function 2 of Table 3.3.2.1-1. the applicable SRs 1

SR 3.10.7.3 --- - -- ----

--NOTE--------- ---------

l Not required to be met if SR 3.10.7.2 i

,r m satisfied. l

(- .

i Verify movement of control rods is in During control '

compliance with the approved control rod rod movement sequence for the SDM test by a second licensed owrator or other qualified member of the tec1nical staff.

SR 3.10.7.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued) n b

FERMI - UNIT 2 3.10 20 Amendment No. 134

1 SDM Test-Refueling 3.10.7 4

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.10.7.5 Verify each withdrawn control rod does not Each time the 90 to the withdrawn overtravel position. control rod is withdrawn to

" full out" position AND Prior to i satisfying LCO 3.10.7.c '

requirement after work on control rod or CRD System that l could affect coupling I

j fT O SR 3.10.7.6 Verify CRD charging water header pressure

= 940 psig.

7 days !

I l

I I

1 O

FERMI UNIT 2 3.10 21 Amendment No. l'34

. 1 Design Features 4.0

( 4.0 DESIGN FEATURES 4.1- Site Location The Fermi 2 site is located on the western shore of Lake Erie in Frenchtown Township, Monroe County, Michigan, approximately 8 miles east northeast of the city of Monroe, Michigan.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO,)

as fuel material and water rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs.that have been analyzed with NRC staff approved codes and methods and have been shown by tests cr analyses to comply with all safety design bases. A limited number of lead test assemblies

.r that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality i

The spent fuel storage racks are designed and shall be maintained I with: , I

a. Fuel assemblies having a maximum k-infinity of 1.31 in the normal reactor core configuration at cold conditions:

e

.( (continued)

FERMI UNIT 2 4.0 1 Amendment No. 134

9 Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Stora9e (continued) b.

k,,,ludes inc an allowance for uncertainties as described ins 0.95 if fully floo Section 9.1 of the UFSAR: and f i

c. A nominal 6.22 inch center to center distance between fuel !

assemblies placed in the high density storage racks and a nominal 11.9 x 6.6 inch center to center distance between ,

fuel assemblies placed in the low density storage racks.

4.3.2 Drainaoe The spent fuel sturage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 660 ft 11,5 inches.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2414 fuel O, assemblies.

.- 1 i

l D

FERMI UNIT 2 4.0 2 Amendment No. 134

5.1 5.0 ADMINISTRATIVE CONTROLS

.................................... NOTE .. -- ---

Plant specific titles are designated in the UFSAR for each organizational position listed or described in this Section.

5.1 Responsibility 5.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during any absence.

The Plant Manager or designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment tnat affect nuclear safety.

5.1.2 The Nuclear Shift Supervisor (NSS) shall be responsible for the control room command function. During any absence of the NSS from the control room while the unit is in MODE 1, 2. or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.

During any absence of the NSS from the control room while the unit r~s is in MODE 4 or 5. an individual with an active SR0 license or V Reactor Operator license shall be designated to assume the control room command function.

I 1

O FERMI UNIT 2 5.0 1 Amendment No. 134

l 1

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Oraanizations

Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of tae nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all o>erating organization positions. These relationships shall )e documented and updated, as appropriate,'in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall .be documented in the UFSAR:

b. The Plant Manager shall be responsible for overall safe operation of the-plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant:

c. The Senior Vice President Nuclear Generation shall have j corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety: and

d. The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager: however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

O

-(continued)

FERM1 UNIT 2 5.0 2 Amendment No. 134 L

q l

Organization 5.2

- 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organization shall include the following: '

a. At least two non licensed operators shall be assigned while operating in MODE 1, 2 or 3 and at least one non-licensed operator shall be assigned whenever the reactor contains 4 fuel,

b. - At least one licensed Reactor Operator (RO) shall be present

'in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2 or 3, at least one <

licensed Senior Reactor Operator (SRO) shall be present in l the control room. 1

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g a for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew member.s ;

provided immediate action is taken to restore the shift crew ,

composition to within the minimum requirements.

I d. A Radiation Protection Technician shall be on site when fuel

. is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g., licensed SR0s, licensed R0s, radiation protection technicians, auxiliary operators, and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.

' Any deviation from the established guidelines shall be authorized in advance by the Plant Manager or designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. ;

J i

(continued)

, / FERMI . UNIT-2 '5.0 3 Amendment No. 134

1 Organization 5.2 5.2 Organization- (continued) 5.2.2 Unit Staff (continued)

Controls shall be included in the procedures such that '

individual overtime shall be reviewed monthly by the Plant Manager or designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines I is not authorized. l

f. The Superintendent 0perations. Assistant Superintendent-Operations, or the Operations Engineer shall hold an SRO-license.

g. An STA shall be assigned whenever the reactor is operating in MODES 1, 2. and 3. The Shift Technical Advisor (STA) shall provide advisory technical support to the Nuclear Shift Supervisor (NSS) in the areas of thermal hydraulics.

reactor engineering, snd plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

l O

l n

V (continued)

FERMI - UNIT 2 5.0 4 Amendment No. 134

l l Unit Staff Qualifications l 5.3 n 5.0 ADMINISTRATIVE CONTROLS

^~

5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum (

qualifications of ANSI N18.11971 for comparable positions. bxcept !

for the Superintendent - Radiation Protection or his designee who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

l 1

I l

fM L) .

i I

i

,O FERMI - UNIT 2 5.0 5 Amendment No. 134

r q Procedures 5.4

,-)

(

V-5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established. implemented. and maintained covering the following activities: -

a. The applicable procedures recommended in Regulatory Guide 1.33. Revision 2, Appendix A. February 1978:

b. The emergency operating procedures required to implement the requirements of NUREG 0737 and to NUREG 0737. Supplement 1.

as stated in Generic Letter 82 33:

c. Quality assurance for effluent and environmental monitoring:

d. Fire Protection Program implementation: and

e. All programs specified in Specification 5.5.

O o.

FERMI UNIT 2 5.0 6 Amendment No. 134 u i

p .

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented and maintained. ,

l 5.5.1 Offsite Dose Calculation Manual (0DCM) l

a. The ODCM shall contain:

1. the methodology and parameters used in the calculation of l offsite doses resulting from radioactive gaseous and l liquid effluents, in the calculation of gaseous and

liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and l 2. the' radioactive effluent controls and radiological i environmental monitoring activities and descriptions of l

the information that should be included in the Annual l Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 5.6.2 i

and Specification 5.6.3.

b. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews erformed shall be retained. This documentation shal contain:

i. sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and l 11. a determination that the change (s) maintain the

! levels of radioactive effluent control required by l 10 CFR 20.1302, 40 CFR 190. 10 CFR 50.36a and l / 10 CFR 50, Appendix I. and not adversely impact the I accuracy or reliability of effluent, dose, or

( setpoint calculations:

2. Shall become effective after the approval of the Plant l Manager; and l

l (continued)

FERMI UNIT 2 5.0 7 Amendment No. 134 l

t

Programs and Manuals 5.5 5.5 Programs and Manuals

[]

5.5.1 Offsite Dose Calculation Manual (0DCM) (continued)

3. Shall be submitted to the NRC in the form of a complete.

l legible copy of the entire ODCM as a part of or l concurrent with the Radioactive Effluent Release Report l for the period of the report in which any change in the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the i page that was changed, and shall indicate the date (i.e.,

month and year) the change was implemented.

! 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to l levels as low as practicable. The systems include Core Spray.

l High Pressure Coolant Injection. Residual Heat Removal. Reactor Core Isolation Cooling, reactor water sampling, Post Accident e Sampling, reactor water cleanup. Hydrogen Recombiners, Primary l Containment Monitoring, control rod drive discharge headers, and Standby Gas Treatment. The program shall include the following:

l a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.3 Post Accident Samolina This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive iodines, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel:

(continued)

FERMI - UNIT 2 5.0 8 Amendment No. 134 l

r: ]

Programs and Manuals 5.5 i 1

5.5 Programs and Manuals 5.5.3 Post Accident Samolina (continued) l

b. Procedures for sampling and analysis: and .

.c. Provisions for maintenance of sampling and analysis equipment.

5.5.4 Radioactive Effluent Controls Prooram i

This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to inembers of the public from. radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM. shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program l

shall include the following elements:

l l a. Limitations on the functional capability of radioactive

! liquid and gaseous monitoring instrumentation including i surveillance tests and setpoint determination in accordance with the methodology in the ODCM:

b. Limitations 'on the concentrations of radioactive' material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in 10 CFR 20.1001 - 20.2402, Appendix B. Table 2 Column 2:

c. Monitoring, sampling, and analysis of radioactive liquid anV gaseous effluents in accordance with 10 CFR 20.1302 andwith the methodology and parameters in the ODCM:

d. Limitations on the annual. and quarterly doses or dor .

commitment to a member of the public from radioacti',a <

l materials in liquid effluents released to unrestricted l areas, conforming to 10 CFR 50 Appendix I:

1

e. Determination of cumulative and projected dose contributions i from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days:

l (continued)

L-FERMI UNIT 2 5.0 9 Amendment No. 134 4

T Programs and Manuals 5.5 O

V 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Proaram (continued)

f. Limitations on the functional capability and use of the ,

liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I:

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at or beyond

, the site boundary conforming to the following:

1. For noble gases: s 500 mrem /yr to the total body and s 3000 mrem /yr to the skin: and

2. For Iodine-131, for Iodine-133. for tritium, and for all radionuclides in particulate form with half lives

> 8 days: s 1500 mrem /yr to any organ:

h. Limitations on the annual and quarterly air doses resulting

,e . from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50,

( Appendix I:

i. Limitations on the annual and quarterly doses to a member of the public from iodine 131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to areas beyond the site boundary, confe ming to 10 CFR 50, Appendix I

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190: and i i

k. Limitations on venting and purging of the Mark I containment {

through the Standby Gas Treatment System or the Reactor l Building Ventilation System to maintain releases as low as reasonably achievable, i

(3 V (continued)

FERMI UNIT 2 5.0-10 Amendment No. 134

F .

1 Programs and Manuals 5.5 t

b v

5.5 Programs and Manuals (continued) 5.5.5 Comoonent Cyclic or Transient Limit I

)

This program provides controls to track the UFSAR Section 5.2.1.2 cyclic and transient (,ccurrences to ensure that components are maintained within the design limits.

5.5.6 Inservice Testina and Insoection Proaram These programs provide controls for inservice testing and

! inspection of ASME Code Class 1, 2, and 3 components. The program l shall include the following:

i a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

! ASME Boiler and Pressure Vessel Code and applicable Addenda Required Frequencies terminology for for performing inservice

, inservice testing and testing and inspection insoection activities activities l

Weekly At least once per 7 days l Monthly At least once per 31 days Quarterly or every l 3 months At least once per 92 days ;

Semiannually or !

l every 6 months At least once per 184 days l Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 day:

! b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice tasting and ;

inspection activities: <

l c. The provisions of SR 3.0.3 are applicable to inservice testing and inspection activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

f3 (continued) r FERMI - UNIT 2 5.0 11 Amendment No. 134 l

Programs and Manuals 5.5 h '5.5 ~ Programs and Manuals- (continued) 5.5.7 Ventilation Filter Testino Prooram (VFTP)

The VFTP shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems.

a. The following tests shall be performed:

1. Once per 18 months:

2. After each complete or partial replacement of the HEPA filter bank or charcoal adsorber bank:

3. After Fry structural maintenance on the HEPA filter or charcoal adsorber housing: and

4. Following painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation.

Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass <

specified below when tested in accordance with Regulatory Guide 1.52. Revision 2. and ASME N5101980 at the system flowrate specified below

10%.

Penetration and ESF Ventilation System Flowrate (cfm) System Byoass Standby Gas Treatment 3800 0.05%

Control Room Emergency 1800 (makeup filter) 1.0% ]

Filtration 3000 (recirculation filter)

I

b. The following tests shall be performed: {

1. Once per 18 months: I

2. After each complete or partial replacement of the HEPA I filter bank or charcoal adsorber bank:

3. After any structural maintenance on the HEPA filter or ,

charcoal adsorber housing: and

4. Following painting, fire, or chemical release in any

~

ventilation zone communicating with the subsystem while it is in operation.

i (continued)

FERMI.- UNIT 2 5.0 12 Amendment No. 134

l .

1 Programs and Manuals 5.5 O s.s ero9ee s eed "em e,e 5.5.7 Ventilation. Filter Testina Procram (VFTP) (continued) f Demonstrate for each of the ESF systems that an inplace test l of the charcoal adsorber shows a penetration and system bypass < specified below when tested in accordance with Regulatory Guide 1.52. Revision 2, and ASME N510 1980 at the

system flowrate specified below i 10%.

l Penetration and ESF Ventilation Systs Flowrate (cfm) System Byoass l

Standby Gas Treatment 3800 0.05%

Control Room Emergency 1800 (makeup filter) 1.0%

Filtration 3000 (recirculation filter) l

c. The following tests shall be performed:

1. Once per 18 months: !

2. After 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation O 3. After a1y structural maintenance on the HEPA filter or V charcoal adsorber housing: and !

4. Following paintirig. fire. or chemical release in any 1 ventilation zone communicating with the subsystem while it is in operation.

Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52. Revision 2. shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803 1989 at a temperature of 30*C and at the relative humidity specified below.

ESF Ventilation System Penetration BB Standby Gas Treatment 0.100* 70%

Control Room Emergency 1.0% 70%

Filtration (continued)

FERMI - UNIT 2 5.0 13 Amendment No. 134

Programs and Manuals 5.5 h 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testina Proaram (VFTP) (continued)

d. The following tests shall be performed once per 18 months.

Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the )refilters (CREF only), and the charcoal adsorbers is less t1an the value specified below when tested in accordance with Regulatory Guide 1.52 Revision 2, and ASME N510-1980 at the system flowrate specified as follows i 10t:

Delta P Flowrate ESF Ventilation System (inches water aauae) (cfm)

Standby Gas Treatment 11.0 3800 Control Room Emergency 6.0 (makeup train) 1800 Filtration (CREF) 8.0 (recirculation 3000 train)

e. The following tests shall be performed once per 18 months.

Demonstrate that the heaters for each of the ESF system dissipate the value specified below when testcd in accordance with ASME N510 1980:

ESF Ventilation System Wattaae (kW)

Standby Gas Treatment a: 24 Control Room Emergency 12.0

2.0 Makeup Inlet Air The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

l (continued)

FERMI UNIT 2 5.0 14 Amendment No. 134 l l

7 l

Programs and Manuals 5.5 l

5.5 Programs and Manuals - (continued) l- 5.5.8 Exolosive Gas and Storaoe Tank Radioactivity Monitorino Prooram l

This program provides controls for potentially explosive gas-i mixtures contained in the Main Condenser offgas treatment system.

! 'and the quantity of radioactivity contained in temporary outdoor L

storage tanks.

The. program shall included

a. A limit of s 4% by volume for concentration of hydrogen in the main condenser offgas treatment system and a surveillance program to ensure the limit is maintained,

b. A surveillance program to ensure that the quantity of radioactivity contained in any outdoor liquid radwaste tank that is not surrounded by liners, dikes, or walls, capable l of holding the tank's contents and that does not have tank overflows and surrounding area drains connected to the liquid radwsste treatment system is s 10 curies, excluding i tritium and dissolved or entrained noble gases.

The provisions of SR 3.0.2 and SR 3.0.3 are a)plicable to the Explosive Gas and Storage Tank Radioactivity ionitoring Program

l. ( surveillance. frequencies.

5.5.9 Emeroency Diesel Generator Fuel Oil Testino Prooram An emergency diesel generator fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within limits.

2. a flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. a clear and bright appearance with proper color:

(continued)

FERMI UNIT 2 5.0 15 Amendment No. 134 i

1 Programs and Manuals j 5.5 1 (l

LJ 5.5 Programs and Manuals 5.5.9 Emeroency Diesel Generator Fuel Oil Testina Prooram (continued)

b. Within 31 days following addition of new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a., above, are within limits for ASTM 2D fuel oil: and

c. Total particulate concentration of the fuel oil is s 10 mg/l when tested every 31 days in accordance with ASTN D-2276.

Method A.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Emergency Diesel Generator Fuel Oil Testing Program testing frequencies.

5.5.10 Technical Soecifications (TS) Bases Control Proaram This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under Q appropriate administrative controls and reviews.

LJ

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

1. a change in the TS incorporated in the license: or

2. a change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.10b above shall be reviewed and ap) roved by the NRC prior to implementation. Changes to t1e Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

p

(/' (continued)

FERMI - UNIT 2 5.0-16 Amendment No. 134

Programs and Manuals I 5.5 I

( 5.5 Programs and Manuals (continued) 5.5.11 Safety Function Determination Proaram (SFDP)

This program ensures loss of safety function is detected and.

appropriate actions taken. Upon entry into LC0 3.0.6. an evaluation shall be made to determine if loss of safety function exists. Additionally. Other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LC0 3.0.6.

a. The SFDP shall contain the following:

1. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go i undetected: l

2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists:

Provisions to ensure that an inoperable supported

3. 4 A system's Completion Time is not inappropriately b , extended as a result of multiple support system inoperabilities: and

4. Other appropriate limitations and remedial or compensatory actions.

b. A loss of safety function exists when. assuming no concurrent single failure. a safety function assumed in the accident analysis cannot be performed. For the pur)ose of this program. a loss of safety function may exist w1en a support system is inoperable, and:

1. A required system redundant to system (s) supported by the inoperable support system is also inoperable: or

2. A required system redundant to system (s) in turn supported by the inoperable supported system is also inoperable; or

3. A required system redundant to support system (s) for the supported systems (a) and (b) above is also inoperable.

t

( (continued)

FERMI UNIT 2 5.0 17 Amendment No. 134

c Programs and Manuals 5.5 l

5.5 Programs and Manuals 5.5.11 Safety Function Determination Proaram (SFDP) (continued)

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LC0 in

'which the loss of safety function exists are required to be entered.

5.5.12 Primary Containment Leakaae Rate Testina Proaram

a. A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163.

" Performance Based Containment Leak-Test Program." dated September, 1995, with the exception of approved exemptions to 10 CFR 50, Appendix J.

b. The peak calculated containment internal pressure for the design basis loss of coolant accident, P., is 56.5 psig.

( c. The maximum allowable containment leakage rate L, at P,,

shall be 0.5% of containment air weight per day.

d. Leakage Rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is s 1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L for the required Type B and C tests and s 0.7$ L, for Type A tests.

2. Air lock testing acceptance criteria are: I Overall air lock leakage rate is s 0.05 L, when i) l

tested at a P., l

, ii) For each door, leakage rate is s 5 scf per hour

! when the gap between the door seals is i pressurized to a P,.

i (continued)

FERMI -' UNIT 2 5.0 18 Amendment No. 134 r

Programs and Manuals 5.5 5.5 Programs and Manuals

(]

u 5.5.12 Primary Containment Leakaoe Rate Testino Procram (continued)

e. The provisions of SR 3.0.2. do not apply to the test frequencies in the Primary Containment Leakage Rate Testing Program.

f. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 Hioh Density Soent Fuel Racks A program shall be provided which will assure that any unanticipated degradation of the high density spent fuel racks will be detected and will not compromise the integrity of the racks.

O i

l l

O.

9 FERMI - UNIT 2 5.0-19 Amendment No. 134 t-

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting R2quirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Reoort l l

A tabulation on an annual basis of the number of )lant, utility, and other personnel (including contractors) for w1om monitoring was required to be performed receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance describe maintenance, waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on i pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge I measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. The report j shall be submitted by April 30 of each year. )

5.6.2 Annual Radioloaical Environmental Ooeratina Reoort The Annual Radiological Environmental Operating Report covering the o)eration of the unit during the previous calendar year shall 1 be su)mitted by May 15 of each year. The report shall include ,

summaries interpretations, and analyses of trends of the results )

of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with !

the objectives outlined in the Offsite Dose Calculation Manual (0DCM), and in 10 CFR 50, Appendix I. Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Reoort i The Radioactive Effluent Release Re) ort covering the operation of i the unit during the previous year s1all be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I.Section IV.B.1.

(n) v (continued)

FERMI UNIT 2 5.0 20 Amendment No. 134 l

L

r q I

Reporting Requirements 5.6

( ') 5.6 Reporting Requirements (continued) 5.6.4 Monthly Doeratina Reoorts Routine reports of operating statistics and shutdown experience .

shall be submitted on a monthly basis no later than the 15th of l each month following the calendar month covered by the report. l 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

LC0 3.2.1 " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)":

LC0 3.2.2. " MINIMUM CRITICAL POWER RATIO (MCPR)"; l LC0 3.2.3. " LINEAR HEAT GENERATION RATE (LHGR)"; and i LCO 3.3.2.1, " Control Rod Block Instrumentation."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by r] the NRC. specifically those described in the following )

(/ ,

documents: j

1. NEDE-24011 P A " General Electric Standard Application for Reactor Fuel." (latest approved version); and

2. NEDE 23785-1-PA. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss of-Coolant Accident -

SAFER /GESTR Application Methodology." (the approved version at the time the reload analyses are performed).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits. Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM transient l analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR. including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

iO

'd (continued)

FERMI - UNIT 2 5.0 21 Amendment No. 134

I Reporting Requirements 5.6

) 5.6 Reporting Requirements (continued) 5.6.6 Safety Relief Valve Challence ReDort The main steam line Safety Relief Valve (SRV) Report documenting all challenges to SRVs during the previous calendar year shall be submitted by April 30 of each year.

5.6.7 PAM Reoort When a report is required by Condition B or G of LC0 3.3.3.1.

" Post Accident Monitoring (PAM) Instrumentation." a report shall be submitted within the following 14 days. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrumentation char.nels of the Function to OPERABLE status.

O V

C FERMI UNIT 2 5.0 22 Amendment No. 134 l 1

n .

High Radiation Area 5.7 L

5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area i 5.7.1 Pursuant to 10 CFR 20. paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as.

defined .in 10 CFR 20, in which the intensity of radiation is l

> 100 mrem /hr but.< 1000 mres/hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto l shall be controlled by requiring issuance of a Radiation Work l l . Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Radiation Protection personnel) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates s 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates O, the radiation dose rate in the area and alarms when a preset ,

integrated dose is received. Entry into such areas with !

this monitoring device may be made after the dose rate ,

levels in the area have been established and personnel have l been made knowledgeable of them,

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Supervisor in the RWP.

I I

(continued)

FERMI - UNIT 2 5.0 23 Amendment No. 134

c High Radiation Area 5.7 5.7' High' Radiation Area (continued)

Si7.2 In addition to the requirements of Specification 5.7.1. areas accessible to individuals with radiation levels such that an individual could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose equivalent > 1000 arems but < 500 rads at one meter from sources of radioactivity shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Nuclear Shift Supervisor on duty and/or the radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the 4 dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.7.3 For individual areas accessible to individuals with radiation levels such that a major portion of the individual's body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose > 1000 mrems with measurement made at 30 centimeters from the source of radioactivity, but < 500 rads at one meter from sources of radioactivity that are located within large areas such as reactor containment, where no enclosure exists aO for purposes of locking.. and where no enclosure can be reasonably constructed around the individual area, that individual area shall be roped off and conspicuously posted, and a flashing light shall be activated as a warning device.

O FERMI m UNIT 2 5.0 24 Amendment No. 134

i Reactor' Core SLs B 2.1.1 v) B 2.0 SAFETY LIMITS (SLs)

B 2.1.1 Reactor Core SLs BASES BACKGROUND GDC 10 (Ref.1) requires, and SLs ensure, that specified acceptable fuel design limits are not exceeded during normal operation, including the effects of anticipated operational occurrences (A00s). i The fuel cladding integrity SL is set such that no significant fuel damage is calculated to occur if the limit is not violated. Because fuel damage is not directly observable, a stepback approach is used to establish an SL, such that the MCPR is not less than the limit specified in {

Specification 2.1.1.2. MCPR greater than the specified !

limit represents a conservative margin relative to the conditions required to maintain fuel cladding integrity.

The fuel cladding is one of the physical barriers that i separate the radioactive materials from the environs. The 1 integrity of this cladding barrier is related to its (3 relative freedom from perforations or cracking. Although l

V some corrosion or use related cracking may occur during the life of the cladding, fission product migration from this 1

source is incrementally cumulative and continuously ;

measurable. Fuel cladding perforations, however, can result ;

from thermal stresses, which occur from reactor operation significantly above design conditions.

While fission product migration from cladding perforation is just as measurable as that from use related cracking, the thermally caused cladding perforations signal a threshold l beyond which still greater thermal stresses may cause gross,

! rather than incremental, cladding deterioration. Therefore, i the fuel cladding SL is defined with a margin to the conditions that would produce onset of transition boiling l (i.e., MCPR = 1.00). These conditions represent a significant departure from the condition intended by design for planned operation. The MCPR fuel cladding integrity SL ensures that during normal operation and during A00s, at least 99.9% of the fuel rods in the core do not experience transition boiling.

Operation above the boundary of the nucleate boiling regime could result in excessive cladding temperature because of the onset of transition boiling and the resultant sharp O

V FERMI UNIT 2 B 2.1.1 - 1 Amendment No. 134 I

h .- -

j

~

l l

l Reactor Core SLs B 2.1.1 BASES ,

BACKGROUND (continued) reduction in heat transfer coefficient. Inside the steam film, high cladding temperatures are reached, and a cladding water (zirconium water) reaction may take place.

This chemical reaction results in oxidation of the fuel cladding to a structurally weaker form. This weaker form may lose its integrity, resulting in an uncontrolled release of activity to the reactor coolant.

APPLICABLE The fuel cladding must not sustain damage as a result of SAFETY ANALYSES normal o)eration and A00s. The reactor core SLs are establis1ed to preclude violation of the fuel design criterion that an MCPR limit is to be established, such that at least 99.9% of the fuel rods in the core would not be expected to experience the onset of transition boiling.

The Reactor Protection System setpoints (LC0 3.3.1.1,

" Reactor Protection System (RPS) Instrumentation"), in combination with the other LCOs, are designed to prevent any anticipated combination of transient conditions for Reactor Coolant System water level, pressure, and THERMAL POWER j level that would result in reaching the MCPR safety limit.

2.1.1.1 Fuel Claddina Intearity General Electric Company (GE) critical power correlations are applicable for all critical power calculations at pressures a 785 psig and core flows a 10% of rated flow.

For operation at low pressures or low flows, another basis is used, as follows:

Since the pressure drop in the by) ass region is essentially all elevation head, t1e core pressure drop at low power and flows will always be > 4.5 psi.

Ref. 2) show that with a bundle flow of Analysey 28 x 10 l (b/hr. bundle pressure drop is nearly independent of bundle power and has a value of 3.5 psi.

Thus, the bundle flow with a 4.5 psi driving head will be > 28 x 10' lb/hr. Full scale ATLAS test data taken at pressures from 14.7 psia to 800 psia indicate that the fuel assembly critical power at this flow is approximately 3.35 MWt. With the design peaking factors, this corresponds to a THERMAL POWER > 50% RTP.

Thus, a THERMAL POWER limit of 25% RTP for reactor pressure < 785 psig is conservative.

FERMI - UNIT 2 82.1.1-2 Amendment No. 134 L ,

j Reactor Core SLs B 2.1.1 BASES APPLICABLE SAFE 17 ANALYSES (continued) 2.1.1.2 tgE The MCPR SL is set such that no significant fuel damage is calculated to occur if the limit is not violated. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling have been used to mark the beginning of the region in which fuel damage could occur. Although it is recognized that the onset of transition boiling would not result in damage to BWR fuel rods, the critical )ower at which boiling transition is calculated to occur has >een adopted as a convenient limit. However, the uncertainties in monitoring i the core operating state and in the procedures used to l calculate the critical power result in an uncertainty in the j value of the critical power. Therefore, the MCPR SL is defined as the critical power ratio in the limiting fuel assembly for which more than 99.9% of the fuel rods in the core are expected to avoid boiling transition, considering the power distribution within the core and all uncertainties.

The MCPR SL is determined using a statistical model that combines all the uncertainties in operating parameters and the procedures used to calculate critical power. The-probability of the occurrence of boiling transition is determined using the approved General Electric Critical Power correlations, Details of the fuel cladding integrity SL calculation are given in Reference 2. Reference 2 also includes a tabulation of the uncertainties used in the determination of the MCPR SL and of the nominal values of the parameters used in the MCPR SL statistical analysis.

2.1.1.3 Reactor Vessel Water Level During MODES 1 and 2 the reactor vessel water level is required to be above the top of the active fuel to provide core cooling capability. With fuel in the reactor vessel during periods when the reactor is shut down, consideration must be given to water level requirements due to the effect of decay heat. If the water level should drop below the top of the active irradiated fuel during this period, the ability to remove decay heat is reduced. This reduction in cooling capability could lead to elevated cladding temperatures and clad perforation in the event that the O

FERMI UNIT 2 B 2.1.1 - 3 Amendment No. 134

f.

Reactor Core SLs B 2.1.1

( ' BASES i APPLICABLE SAFETY ANALYSES (continued) water level becomes < 2/3 of the core height. The reactor vessel water level SL has been established at the top of the active irradiated fuel to provide a point that can be monitored and to also provide adequate margin for effective action.

i SAFETY LIMITS The reactor core SLs are established to protect the integrity of the fuel clad barrier to the release of radioactive materials to the environs. SL 2.1.1.1 and SL 2.1.1.2 ensure that the core operates within the fuel design criteria. SL 2.1.1.3 ensures that the reactor vessel water level is greater than the top of the active irradiated fuel in order to prevent elevated clad temperatures and resultant clad perforations.

1 I

APPLICABILITY SLs 2.1.1.1, 2.1.1.2, and 2.1.1.3 are applicable in all MODES.

O. SAFETY LIMIT Exceeding a reactor core SL may cause fuel damage and create VIOLATIONS a potential for radioactive releases in excess of 10 CFR 100. " Reactor Site Criteria," limits (Ref. 3).

Therefore, it is required to insert all insertable control i rods and restore cogliance with the SLs within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time ensures that the operators take prompt remedial action and also ensures that the probability of an accident occurring during this period is minimal.

REFERENCES 1. 10 CFR 50. Appendix A. GDC 10.

2. NEDE 24011 P A (latest approved revision).

3. 10 CFR 100.

I l

O FERMI UNIT 2 B 2.1.1 - 4 Amendment No. 134 l

l ,

p RCS Pressure SL B 2.1.2 B 2.0 SAFETY LIMITS (SLs)

B 2.1.2 Reactor Coolant System (RCS) Pressure SL BASES BACKGROUND The SL on reactor steam dome pressure protects the RCS against overpressurization. In the event of fuel cladding failure, fission products are released into the reactor coolant. The RCS then serves as the primary barrier in preventing the release of fission products into the atmosphere. Establishing an upper limit on reactor steam dome pressure ensures continued RCS integrity. According to l 10 CFR 50. Appendix A, GDC 14. " Reactor Coolant Pressure Boundary," and GDC 15. " Reactor Coolant System Design" (Ref.1), the reactor coolant pressure boundary (RCPB) shall be-designed with a low probability of failure and sufficient ,

margin to ensure that t1e design conditions are not exceeded during normal operation and anticipated operational l4 occurrences (A00s).

During normal operation and A00s RCS pressure is limited from exceeding the design pressure by more than 10t. in accordance with Section III of the ASME Code (Ref. 2). To (d~3 ensure system integrity, all RCS components are hydrostatically tested at 125% of design pressure, in accordance with ASME Code requirements, prior to initial operation when there is no fuel in the core. Any further hydrostatic testing with fuel in the core may be done under LC0 3.10.1, " Inservice Leak and Hydrostatic Testing Operation." Following inception of unit operation, RCS ,

components shall be pressure tested in accordance with the '

requirements of ASME Code,Section XI (Ref. 3). I Overpressurization of the RCS could result in a breach of l the RCPB, reducing the number of protective barriers designed to prevent radioactive releases from exceeding the limits specified in 10 CFR 100, " Reactor Site Criteria" (Ref. 4). If this occurred in conjunction with a fuel cladding failure, fission products could enter the containment atmosphere.

i O

FERMI - UNIT 2 B 2.1.2 - 1 Amendment No. 134 Y

RCS Pressure SL B 2.1.2 (v SASES l

APPLICABLE The RCS safety / relief valves and the Reactor Protection :

SAFETY ANALYSES System Reactor Vessel Steam Dome Pressure-High Function i have settings established to ensure that the RCS pressure SL will not be exceeded.

The RCS pressure SL has been selected such that it is at a l pressure below which it can be shown that the integrity of the system is not endangered. The reactor pressure vessel. i main steam piping, and reactor coolant system are designed I and built in accordance with a)plicable codes and standards, as detailed in Reference 5. T1e RCS pressure SL is selected I to be the lowest transient overpressure allowed by the )

applicable codes. 1 I

1 l

SAFETY LIMITS The maximum transient pressure allowable in the RCS pressure vessel under the ASME Code.Section III, is 110% of design I pressure. The maximum transient pressure allowable in the RCS piping, valves, and fittings is 110% of design pressures of 1250 psig for suction piping and 1500 psig for discharge piping. The most limiting of these allowances is the 110%

O of the suction piping design pressures: therefore. the SL on d maximum allowable RCS pressure is established at 1325 psig as measured at the reactor steam dome.

APPLICABILITY SL 2.1.2 applies in all MODES.

SAFETY LIMIT Exceeding the RCS pressure SL may cause immediate RCS VIOLATIONS failure and create a potential for radioactive releases in excess of 10 CFR 100, " Reactor Site Criteria," limits (Ref. 4). Therefore it is required to insert all insertable control rods and restore compliance with the SL within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time ensures that the o)erators take prompt remedial action and also assures that tie probability of an accident occurring during this period is minimal.

(3 V

FERMI UNIT 2 B 2.1.2 - 2 Amendment No. 134 1

! I i

RCS Pressure SL B 2.1.2 BASES REFERENCES 1. 10 CFR 50, Appendix A. GDC 14. and GDC 15. -

2. ASME. Boiler and Pressure Vessel Code.Section III. 1 Article NB 7000. <

3. ASME, Boiler and Pressure Vessel Code.Section XI.

Article IWB-5000.

4. 10 CFR 100.

5. UFSAR Section 3.2.

O 1

O FERMI UNIT 2 B 2.1.2 -3 Amendment No. 134

LC0 Applicability B 3.0

(]

V B 3.0 LIMITING CONDITION FOR OPERATION (LC0) APPLICABILITY BASES 4

LCOs LC0 3.0.1 through LC0 3.0.7 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

i LC0 3.0.1 LC0 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LC0 is required to be met (i.e., when the unit is in the MODES or other s)ecified conditions of the Applicability statement of eac1 Specification).

LC0 3.0.2 LC0 3.0.2 establishes that upon discovery of a failure to meet an LCO. the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within (Sj specified Completion Times when the requirements of an LC0 are not met. This Specification establishes that:

a. Completion of the Required Actions within the specified l Completion Times constitutes compliance with a Specification; and

b. Com)letion of the Required Actions is not required when an _C0 is met within the specified Completion Time, unless otherwise specified.

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.) The second type of Required Action specifies the D

(V FERMI UNIT 2 B 3.0-1 Amendment No. 134

LC0 Applicability B 3.0 O

G BASES LC0 3.0.2 (continued) remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time.

In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation.

Completing the Required Actions is not required when an LC0 is met or is no longer applicable, unless otherwise stated in the individual Specifications.

The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual LCO's ACTIONS specify the Required Actions where this is the case.

An example of this is in LCO 3.4.10. "RCS Pressure and Temperature (P/T) Limits."

The Com)letion Times of the Required Actions are also applica)1e when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to.

performance of Surveillances, preventive maintenance, (d corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead. Doing so limits the time both subsystems / divisions of a safety function are inoperable and limits the time other conditions exist which may result in LC0 3.0.3 being entered.

Individual Specifications may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

O FERMI UNIT 2 B 3.0-2 Amendment No. 134

LCO Applicability B 3.0 BASES LC0 3.0.2 0 mtinued)

When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Specification becomes applicable. In this case. the Completion Times of the associated Required Actions would apply from the )oint in time that the new Specification becomes applica)le and the ACTIONS Condition (s) are entered.

LC0 3.0.3 LCO 3.0.3 establishes the actions that must be implemented when an LCO is not met and:

a. An associated Required Action.and Completion Time is not met and no other Condition applies: or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of O. Conditions are such that entering LC0 3.0.3 is warranted: in such cases, the ACTIONS specifically state a Condition corres)onding to such combinations and also that LC0 3.0.3 >e entered immediately.

Thi Specification delineates the time limits for placing the unit in a safe MODE or other s)ecified condition when operation cannot be maintained wit 11n the limits for safe operation as defined by the LC0 and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

Upon entering LCO 3.0.3, I hour is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities O

FERMI-- UNIT 2 B 3.0-3 Amendment No. 134

LC0 Applicability l B 3.0 l BASES LC0 -3.0.3 (continued) of the unit. assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Specification applies. The use and interpretation of specified times to complete the actions of LC0 3.0.3 are consistent with the discussion of Section 1.3.

Completion Times.

A unit shutdown required 1n accordance with LC0 3.0.3 nay be

-terminated and LC0 3.0.3 exited if any of the following occurs:

a. The LC0 is now met.

b. A Condition exists for which the Required Actions have now been performed.

c. ACTIONS exist that do not have expired Com)letion Times. These Completion Times are applica)le from the point in time that the Condition is initially entered p alid not from the time LC0 3.0.3 is exited.

V The time limits of LC0 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, the total allowable time to reach MODE 4, or other applicable MODE. is not reduced. For example, if MODE 2 is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . Therefore, if remedial measures are completed that would permit a return to MODE 1. a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 2, and 3. LC0 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LC0 3.0.3 do not apply in MODES 4 and 5 because the unit is'already in the most restrictive Condition required by LC0 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1. 2, or 3) because the O

FERMI UNIT 2 B 3.0-4 Amendment No. 134 l

LCO Applicability B 3.0 BASES LC0 3.0.3 (continued)

ACTIONS of individual Specifications sufficiently define the remedial measures to be taken.

Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown. in accordance with LC0 3.0.3.

would not provide appropriate remedial measures for the associated condition of the unit. An exam)le of this is in LC0 3.7.7. " Spent Fuel Storage Pool Water _evel." LCO 3.7.7 has an Applicability of "During movement of irradiated fuel assemblies.in the spent fuel storage pool." Therefore. . this LCO can be applicable in any or all MODES. If the LC0 and the Required Actions of LC0 3.7.7 are not met while in MODE 1. 2. or 3. there is no safety benefit to be gained by placing the unit in a shutdown condition. The Required Action of LC0 3.7.7 of " Suspend movement of irradiated fuel assemblies in the spent fuel storage pool" is the

~ appropriate Required Action to complete in lieu of the actions of LC0 3.0.3. These exceptions are addressed in the individual Specifications. .

O 'Co 3.0.4 LC0 3.0.4 establ4shes ,imitat4 ens en chanoes 4n MooeS er other specified conditions in the A)plicability when an LC0 is not met. It precludes placing t1e unit in a MODE or other specified condition stated in that Applicability

.(e.g., Applicability desired to be entered) when the following exist:

a. Unit conditions are such that the requirements of the LC0 would not be met in the Applicability desired to be entered; and

b. Continued noncompliance with the LC0 requirements. if the A>plicability were entered, would result in the unit >eing required to exit the Applicability desired to be entered to comply with the Required Actions.

Compliance with Required Actions that permit continued I operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. . This is without regard to the status of the unit before or after the MODE l

. change. Therefore, in such cases entry into a MODE or 1 other specified condition in the Applicability may be made O

FERMI - UNIT 2 B 3.0-5 Amendment No. 134

i LC0 Applicability B 3.0 A BASES V

LC0 3.0.4 (continued) in accordance with the provisions of the Required Actions. '

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good !

practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

4 The provisions of LC0 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comp y with ACTIONS. In addition, the I provisions of LCO 3.0.4 s all not 3revent changes in MODES or other specified conditions in t1e Applicability that result from any unit shutdown.

Exceptions to LC0 3.0.4 are stated in the individual Specifications. The exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for i continued operation for an unlimited period of time. l Exceptions may apply to all the ACTIONS or to a specific '

Required Action of a Specification.

O L

LC0 3.0.4 is only applicable when entering MODE 3 from MODE 4. MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2.

Furthermore LC0 3.0.4 is applicable when entering any other specified condition in the Applicability only while 1 operating in MODE 1, 2, or 3. The requirements of LC0 3.0.4 ;

do not apply in MODES 4 and 5, or in other specified l conditions of the Applicability (unless in MODE 1, 2, or 3) ;

because the ACTIONS of individual specifications i sufficiently define the remedial measures to be taken. In i some cases (none currently in Fermi-2 Technical Specifications) these ACTIONS provide a Note that states "While this LC0 is not met, entry into a MODE or other specified condition in the Ap)licability is not permitted, unless required to comply witi ACTIONS." This Note is a requirement explicitly precluding entry into a MODE or other specified condition of the Applicability.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS Condition, either in compliance with LC0 3.0.4 or where an exception to LC0 3.0.4 is stated, is not a violation of p

us FERMI - UNIT 2 B 3.0-6 Amendment No. 134

LC0 Applicability B 3.0 BASES LC0 3.0.4 (continued)

SR 3.0.1 or SR 3.0.4 for those Surveillances that do not have to be performed due to the associated inoperable equipment. However, SRs must be met to ensure OPERABILITY ;

prior to declaring the associated equipment OPERABLE (or I variable within limits) and restoring compliance with the affected LCO.

LC0 3.0.5 LC0 3.0.5 establishes the allowance for restoring equipment l to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LC0 3.0.2 (e.g., to not comply with the applicable Required Action (s)) to allow the performance of required testing to demonstrate:

~a. The OPERABILITY of the equipment being r'eturned to service or

b. The OPERABILITY of other equipment.

) The administrative controls ensure the time the equipment is s returned to service in conflict with the requirements of the i ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY.

This Specificati0n does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the required testing.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is ;

taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

FERMI UNIT 2 B 3.0-7 Amendment No. 134

I LC0 Applicability.

B 3.0 BASES LC0 3.0.6 LC0 3.0.6 establishes an exception to LC0 3.0.2 for support systems that have an LC0 specified in the Technical ;

Specifications (13). This exception is provided because LC0 3.0.2 would require that the Conditions and Required Actions of the associated inoperable supported system LC0 be entered solely due to the inoperability of the support system. This exception is justified because the actions that are required to ensure the plant is maintained in a safe condition are sweified in the support system LC0's i Required Actions. T1ese Required Actions may include entering the supported system's Conditions and Required Actions or may specify other Required Actions.

, When a support system is inoperable' and there is an LCO specified for it in the TS the supported system (s) are required to be declared inomrable if determined to be inoperable as a result of tie support system inoperability.

l' However, it is not necessary to enter into the supported-l systems' Conditions and Required Actions unless directed to i do so by the support system's Required Actions. The potential confusion and inconsistency of requirements related to the entry into multiple support and supported iO l

systems' LCOs' Conditions and Required Actions are eliminated by providing all the actions that are necessary to ensure the plant is maintained in a safe condition in the l

support system's Required Actions.

However, there are instances where a support system's :

Required Action may either direct a supported system to be !

declared inoperable or direct entry into Conditions and i Required Actions for the supported system. This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's l Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LC0 3.0.2.

Specification 5.5.11. " Safety Function Determination Program (SFDP)," ensures loss of safety function is detected and appropriate actions are taken. Upon entry into LC0 3.0.6 an evaluation shall be made to determine if loss of safety function exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a O

FERMI UNIT 2 B 3.0-8 Amendment No. 134

LC0 Applicability B 3.0 BASES LC0 3.0.6 (continued) result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. . The SFDP implements the requirements of LCO.3.0.6.

Cross division checks to identify a loss of safety function for those su) port systems that sup) ort safety systems are

. required. T1e cross division checc verifies that the supported systems of the redundant OPERABLE support system are OPERABLE, thereby ensuring safety function is retained.

If this evaluation determines that a loss of safety function exists, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

LCO 3.0.7 There are certain special tests and operations required to be performed at various times over the life of the unit.

These special tests and operations are necessary to demonstrate select unit performance characteristics -to perform special maintenance activities, and to perform special evolutions. Special Operations LCOs in Section 3.10 allow specified TS requirements to be changed to permit performances of these-special tests and operations, which otherwise could not be performed if required to comply with H

the requirements of these TS. Unless otherwise specified.

all the other TS requirements remain unchanged. This will ensure all appropriate requirements of the MODE or other l- specified condition not directly associated with or required I to be changed to perform the special test or operation will remain in effect. j The Applicability of a Special Operations LC0 represents a l condition not necessarily in compliance with the normal ;

l requirements of the TS. Compliance with Special Operations L LCOs is optional. A special operation may be performed either under the provisions of the appropriate Special Operations LC0 or under the other applicable TS l requirements. If it is desired to )erform the special operation under the provisions of tie Special Operations LCO, the requirements of the Special Operations LC0 shall be followed. When a Special Operations LC0 requires another LC0 to be met, only the requirements of the LC0 statement

-are required to be met regardless of that LCO's FERMIL- UNIT 2 B 3.0-9 Amendment No. 134 L

LC0 Applicability i B 3.0 1 BASES LC0 3.0.7 (continued) {

Applicability (i.e., should the requirements of this other LCO not be met, the ACTIONS of the Special Operations LC0 apply, not the ACTIONS of the other LCO). However, there are instances where the Special Operations LC0 ACTIONS may direct the other LCOs* ACTIONS be met. The Surveillances of the other LC0 are not required to be met, unless specified in the Special 0)erations LC0. If conditions exist such that the A other LC0'pplica)ility s requirementsof (ACTIONS any otherand LC0SRs) is met, all the to are required be met concurrent with the requirements of the Special Operations LCO.

j l

l l

FERMI - UNIT 2 B 3.0 - 10 Amendment No. 134

y .

SR Applicability B 3.0 l

B 3.0 SURVEILLANCE REQUIREMENT'(SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Systems and commnents are assumed to be OPERABLE when the '

associated SRs lave been met. Nothing in this Specification, however, is to be construed as implying that

, systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs: or

b. The requirements of the Surveillance (s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LC0 are not applicable, unless otherwise specified. The SRs associated with a Special Operations LCO are only applicable when the Sacial Operations LC0 is used as an allowable exception to t1e requirements of a Specification.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this :

case, the unplanned event may be credited as fulfilling the l performance of the SR. This allowance includes those SRs - l whose performance is normally precluded in a given MODE or other specified condition.

i FERMI UNIT 2' B 3.0-11 Amendment No. 134 4

SR Applicability l 3.0 !

BASES SR 3.0.1 (continued)

Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. I Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This '

includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not '

having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will al

ML20211Q735

Text