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                              *6-           " M dF Recirculation Loops Operating 3.4.1 t
*6-
    )         3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating b     LCO 3.4.1         The reactor core shall not exhibit core thermal hydraulic instability or operate in the " Scram" or " Exit" Regions.
" M dF Recirculation Loops Operating 3.4.1
        "I 4
)
8NQ
3.4 REACTOR COOLANT SYSTEM (RCS) t 3.4.1 Recirculation Loops Operating b
        >                          a. Two recirculation loops with matched recirculation loop jet pump flows shall be in operation:
LCO 3.4.1 The reactor core shall not exhibit core thermal hydraulic instability or operate in the " Scram" or " Exit" Regions.
"I 8NQ 4
a.
Two recirculation loops with matched recirculation loop jet pump flows shall be in operation:
M
M
{
{
: b. One recirculation loop may be in operation provided:
b.
: 1. LC0 3.3.1.1 " Reactor Protection System (RPS)
One recirculation loop may be in operation provided:
Instrumentation." Function 2.b (Average Power Range Vl                                     Monitors Simulated Thermal Power-Upscale) Allowable Value of Table 3.3.1.11 is reset for single loop e                                      operation, when in MODE 1: and k                               2. THERMAL POWER is s 67.2% RTP.
1.
          .J
LC0 3.3.1.1 " Reactor Protection System (RPS)
    % q                           ................~............N0TE     -    ---  -- - -  ----  ---
Instrumentation." Function 2.b (Average Power Range Vl Monitors Simulated Thermal Power-Upscale) Allowable Value of Table 3.3.1.11 is reset for single loop operation, when in MODE 1: and e
Required allowatt.e value modification for single loop x                                                                                              j El                     operation and THERMAL POWER limitation may be delayed for up           I L                       to 4 hours after transition from two recirculation loop operations to single recirculation loop operation.
k 2.
APPLICABILITY:   MODES I and 2.-
THERMAL POWER is s 67.2% RTP.
ACTIONS CONDITION                       REQUIRED ACTION             COMPLETION TIME A. Recirculation jet pump       A.1     Declare recirculation     2 hours 100) flow mismatch not               loop with lower flow:
.J
wit 11n limits.                       "not in operation."
% q
(continued) 9907200104 990713 PDR                                                                                     ,
................~............N0TE x
P ADOCK 05000341                                                                   i pg l FERMI - UNIT 2                             3.4 1               Revision 10. 07/09/99 l
Required allowatt.e value modification for single loop j
El operation and THERMAL POWER limitation may be delayed for up L
to 4 hours after transition from two recirculation loop operations to single recirculation loop operation.
APPLICABILITY:
MODES I and 2.-
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Recirculation jet pump A.1 Declare recirculation 2 hours 100) flow mismatch not loop with lower flow:
wit 11n limits.
"not in operation."
(continued) 9907200104 990713 PDR ADOCK 05000341 i
P pg l FERMI - UNIT 2 3.4 1 Revision 10. 07/09/99


Recirculation Loops Operating B 3.4.1
Recirculation Loops Operating B 3.4.1
        )         BASES APPLICABLE SAFETY ANALYSES (continued)
)
BASES APPLICABLE SAFETY ANALYSES (continued)
Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied.
Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied.
Recirculation loops operating satisfies Criterion 2 of 10 CFR 50,36(c)(2)(ii).
Recirculation loops operating satisfies Criterion 2 of 10 CFR 50,36(c)(2)(ii).
LC0             Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of m
LC0 Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the m
          ~
~
the piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. With the limits specified in i                       SR 3.4.1.2 not met, the recirculation loop with the lower d                       flow must be considered not in o             With only one
LOCA analysis are satisfied. With the limits specified in i
          %                      recirculation loop in operation,peration.
SR 3.4.1.2 not met, the recirculation loop with the lower d
modifications to the APRM Simulated Thermal Power-Upscale setpoint (LC0 3.3.1.1) and y{                      a limitation on THERMAL POWER may be applied to allow S                           continued operation consistent with the assumptions of the safety analysis,                                                 f e                      Operations that exhibit core thermal hydraulic instability       )
flow must be considered not in o With only one recirculation loop in operation,peration.
are not permitted. Additionally, in order to avoid G                       potential power oscillations due to thermal hydraulic instability, operation at certain combinations of power and
modifications to the APRM y{
          ?u                       flow are not permitted. These restricted power and flow cc                       regions are referred to as the " Scram" and " Exit" regions y                         and are defined by Bases Figure B 3.4.1-1.
Simulated Thermal Power-Upscale setpoint (LC0 3.3.1.1) and a limitation on THERMAL POWER may be applied to allow S
A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to jl                     establish the APRM Simulated Thermal Power - Upscale m                        setpoint in accordance with the single loop allowable value.     '
continued operation consistent with the assumptions of the safety analysis, f
dt                     which is specified in Table 3.3.1.1-1 and to establish 9C                       operation at 5 67.2% RTP. The 4 hour period is sufficient to make the adjustments given the relatively small change j                       required. This transition that results in a> plying the new 4                       single-loo) allowable values to APRM OPERABI_ITY, is such         !
)
g                        that any ARPM non compliance with the required allowable         I
Operations that exhibit core thermal hydraulic instability e
          >                      value after.this 4 hour allowance results in ACTIONS of         ;
are not permitted. Additionally, in order to avoid G
4                      LC0 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would           l apply.
potential power oscillations due to thermal hydraulic instability, operation at certain combinations of power and
j         --
?u flow are not permitted. These restricted power and flow cc regions are referred to as the " Scram" and " Exit" regions y
l l FERMI - UNIT 2                       B 3.4.1 - 4           Revision 10. 07/09/99 I
and are defined by Bases Figure B 3.4.1-1.
l I
A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to jl establish the APRM Simulated Thermal Power - Upscale setpoint in accordance with the single loop allowable value.
m dt which is specified in Table 3.3.1.1-1 and to establish 9C operation at 5 67.2% RTP. The 4 hour period is sufficient to make the adjustments given the relatively small change j
required. This transition that results in a> plying the new 4
single-loo) allowable values to APRM OPERABI_ITY, is such g
that any ARPM non compliance with the required allowable value after.this 4 hour allowance results in ACTIONS of 4
LC0 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would apply.
j l FERMI - UNIT 2 B 3.4.1 - 4 Revision 10. 07/09/99


                                                                                      $ fEC IFt cAgian) 3 <{. /
$ fEC IFt cAgian) 3 <{. /
3 /4. 4 REACTOR COOLANT SY' STEM
[Nse Su SFi eq/fori 54/0) 3 /4. 4 REACTOR COOLANT SY' STEM 3
[Nse Su SFi eq/fori 54/0) 3               3/4.4.1- RECIRCULATION SYSTEM 1             RECIRCULATION LOOPS                                               <
3/4.4.1-RECIRCULATION SYSTEM 1
LIMITINGtCONDITION FOR OPERATION l.M p ,g       2.t.:.1- Two reactor coolant system recirculation loops shall be in operation.
RECIRCULATION LOOPS LIMITINGtCONDITION FOR OPERATION l.M p,g 2.t.:.1-Two reactor coolant system recirculation loops shall be in operation.
APPLICABILITY: OPERATIONAL CONDITIONS 1-and 2*.
APPLICABILITY: OPERATIONAL CONDITIONS 1-and 2*.
ACTION:
ACTION:
: a. With one reactor coolant system recirculation loop not in operation:
a.
LLo M .I' 3.         Within 4 hours:                                                     LAil t@TW~                                                                                                     -
With one reactor coolant system recirculation loop not in operation:
ra m)Plar/
LLo M.I' 3.
the individual op#atino                rarAculation recirculatio(pumo              pump in the Manual      flow cof roller'for the ] g moda g
Within 4 hours:
LAil t@TW~
m)Plar/ the individual rarAculation pump flow cof roller'for the ] g ra op#atino recirculatio(pumo in the Manual moda g
y gy,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27, of RATED THERMAL POWER.
y gy,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27, of RATED THERMAL POWER.
j ,j
j,j Limit the speedff the operating recire
                                  )      Limit the speedff the operating recire or'eaual to 751f of rated pump speeds)/Intion pump to les/than]
)
                                ^
or'eaual to 751f of rated pump speeds)/Intion pump to les/than]
d) in         ase Ine MiniriurycMITICAL Powtx MAisy (Isrn) barety L1 t to]
^
d) in ase Ine MiniriurycMITICAL Powtx MAisy (Isrn) barety L1 t to]
value for sing)e loop operation reqVired by Specifica on j
value for sing)e loop operation reqVired by Specifica on j
                                            .27 g
.27 g
3                             e) Change the Average Power Range Monitor (APRM) Simulated Thermal,                 n j
3 e) Change the Average Power Range Monitor (APRM) Simulated Thermal, n
                @ N'I'g'g               Power - Upscale Flow Biased Scram tr.f N :".en Nr se- rMis?
j
WA110wable Values to those applicable for single recirculation     ~
@ N'I'g'g Power - Upscale Flow Biased Scram tr.f N :".en Nr se-rMis?
WA110wable Values to those applicable for single recirculation
~
loop operation per Specifications 2.2.1 and 3.3.6.
loop operation per Specifications 2.2.1 and 3.3.6.
l f     '"ferform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is gggfugh7 )f recirculation loop flow in the operating loop is le gg ,,,
l f
less than or equal to 307, of RATED THERMAL POWER or the i
'"ferform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is gggfugh )f recirculation loop flow in the operating loop is le less than or equal to 307, of RATED THERMAL POWER or the gg,,,
u equal to 507, of rated loop flow,
7 i
                        -2. Oth:r "-- 6           4- it h ::: ll0T ;;rJ ;; n                                   3
equal to 507, of rated loop flow, u
                                                                                . 6uin tue u m n ,,_ . . .
3
: b.       With no reactor coolant system recirculation loop in operation while in bTION D           OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.
-2.
: c.      ~ With'no reactor coolant system recirculation loops in operation, while in OPERATIONAL CONDITION 2, initiate measures to place the unit in at least
Oth:r "-- 6 4-it h ::: ll0T ;;rJ ;; n. 6uin tue u m n,,_...
      $ttTtotJC.         HOT SHUTDOWN within the next 6 hours.                         ,
b.
{See         cialTe3rException3.f0.4.]
With no reactor coolant system recirculation loop in operation while in bTION D OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.
~ With'no reactor coolant system recirculation loops in operation, while in c.
OPERATIONAL CONDITION 2, initiate measures to place the unit in at least
$ttTtotJC.
HOT SHUTDOWN within the next 6 hours.
{See cialTe3rException3.f0.4.]
l e
l e
-'              FERMI - UNIT 2                                   3/4 4-1   Amendment No. JJ,64,EJ,EJ, E7.JES, 122 PAGE       2. OF     06                           ggyto i
FERMI - UNIT 2 3/4 4-1 Amendment No. JJ,64,EJ,EJ, E7.JES, 122 PAGE 2.
OF 06 ggyto i


SPEttFicATigd 3.% I (Ais.sa:rpafwrw 3 Go)
SPEttFicATigd 3.% I (Ais.sa:rpafwrw 3 Go)
L                                                               (Mso sa sp;(;w% s E d                   l REACTOR COOLANT SYSTFM
L (Mso sa sp;(;w% s E d
                                                                                                          )
)
l SURVETLIANCE REQUIREMENTS S e4. T4.1.1.1 Each pump discharge valve shall be demonstrated OPHRABLE by                     j
REACTOR COOLANT SYSTFM SURVETLIANCE REQUIREMENTS S e4.
  $bbicycling each valve through at least one complete cycle of full travel at least                     J 3.g,i         once per 18 months.
T4.1.1.1 Each pump discharge valve shall be demonstrated OPHRABLE by j
l
$bbicycling each valve through at least one complete cycle of full travel at least J
                  -4 A .I.1.2     LEO r.u                                                 / h, l d.4.1.1.3 With ne reactor coolant s tem recmuieuon ioop not in
3.g,i once per 18 months.
                  'q eration, at I st once per 12 hours erify that:                     '
-4 A.I.1.2 LEO r.u
                                    . THERMAL POWER i   ess than or equal to 6 .2% of RATED           )
/ h, l d.4.1.1.3 With ne reactor coolant s tem recmuieuon ioop not in
THERMAL POWER, nd
'q eration, at I st once per 12 hours erify that:
: b. The individu recirculation pump flo controller for t e           1 operating r irculation pump is in     e Manual mode, a         j
THERMAL POWER i ess than or equal to 6.2% of RATED
: c. The speed f the operating recircu tion pump is le' than or coual o 75% of rated oumo see       -
)
b4.4.1.1.4         With one reactor coolant system loop not in operatjon with THERMAL 1 POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r4ted loop flow, verify the following differential temperature requirements are met within no 1 more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
THERMAL POWER, nd b.
  )           M
The individu recirculation pump flo controller for t e operating r irculation pump is in e Manual mode, a j
: a. Less than or equal to 145'F between reactor vessel steam space coolant and bottom head drain line coolant, and ged[(cqh'A                 b. Less than or equal to 50'F between the reactor coolant within the loop not in operation and the coolant in the 3 Y.rb /                    reactor pressure vessei *, and
c.
: c. Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the operating loop.**
The speed f the operating recircu tion pump is le' than or coual o 75% of rated oumo see b4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL 1 POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r4ted loop flow, verify the following differential temperature requirements are met within no 1 more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
b*$       *y.
)
m           ** Requirement does not apply when the recirculation loop not ih operation is         1 5p46u.h>             isolated from the reactor pressure vessel.
a.
3M6 FERMI - UNIT 2                           3/4 4-2     Amendment No. 83. 59. 87. US.133 PAGE 3
Less than or equal to 145'F between reactor vessel steam M
_OF     06                   ggqlo
space coolant and bottom head drain line coolant, and ged[(cqh'A b.
Less than or equal to 50'F between the reactor coolant 3 Y.rb /
within the loop not in operation and the coolant in the reactor pressure vessei *, and c.
Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the operating loop.**
b*$ *y.
m
** Requirement does not apply when the recirculation loop not ih operation is 5p46u.h>
isolated from the reactor pressure vessel.
3M6 FERMI - UNIT 2 3/4 4-2 Amendment No. 83. 59. 87. US.133 PAGE 3
_OF 06 ggqlo


r DISCUSSION OF. CHANGES ITS: KECTION 3.4.1 - RECIRCULATION LOOPS OPERATING TECHNICAL CHANGES - NORE RESTRICTIVE Non.
r DISCUSSION OF. CHANGES ITS: KECTION 3.4.1 - RECIRCULATION LOOPS OPERATING TECHNICAL CHANGES - NORE RESTRICTIVE Non.
TECHNICAL CHANGES'- LESS RESTRICTIVE
TECHNICAL CHANGES'- LESS RESTRICTIVE
        " Generic" LA.1       CTS 3.4.1.1,~ Actions a.1.a) and c), and 4.4.1.1.3, impose limitations on: the recirculation pump flow controller mode of operation; and the operating recirculation pump speed. These limitations are                     g' related to operational considerations associated with
" Generic" LA.1 CTS 3.4.1.1,~ Actions a.1.a) and c), and 4.4.1.1.3, impose limitations on:
                  . prevention of possible control oscillations and reactor                     I vessel internals vibration, and are not associated with the function of the Recirculation Loop Operating                     ~
the recirculation pump flow controller mode of operation; and the operating g'
Technical Specification as defined in the NUREG-1433                   4 Bases. Therefore, the requirements for maintaining                   M these limitations can be adequately defined and                     -
recirculation pump speed.
controlled in the Technical Requirements Nanual (TRM),
These limitations are related to operational considerations associated with
. prevention of possible control oscillations and reactor I
vessel internals vibration, and are not associated with the function of the Recirculation Loop Operating
~
Technical Specification as defined in the NUREG-1433 4
Bases.
Therefore, the requirements for maintaining M
these limitations can be adequately defined and controlled in the Technical Requirements Nanual (TRM),
j[
j[
which require revisions to be controlled by 10 CFR 50.59. These relocations continue to provide adequate               >
which require revisions to be controlled by 10 CFR 50.59.
protection of the public health and safety since the ITS retain sufficient requirements related to maintaining thermal limits and thermal hydraulic stability for single. loop operation.
These relocations continue to provide adequate protection of the public health and safety since the ITS retain sufficient requirements related to maintaining thermal limits and thermal hydraulic stability for single. loop operation.
LA.2       Not used i
LA.2 Not used i
I O
O E
FERNI - UNIT E2                            3           REVISION 10,   07/09/99
FERNI - UNIT 2 3
REVISION 10, 07/09/99


Recirculation Loops Operating 3.4.1
Recirculation Loops Operating 3.4.1
    ')     3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1   Recirculation Loops Operating d@b k LCO 3.4.2                 recirculatio                   oops with matched flows sha i be in                                                                     M'8' operation,                            rew c,geg( n + g;),;p                                                                                 3*OI 3) core % mot h'idasuc iris la,Wllfy o''ofetuk-                                                                     -
')
Y                                   in Se " Scrod or %ii% gin
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating d@b k M'8' LCO 3.4.2 recirculatio oops with matched flows sha i be in rew c,geg( n + g;),;p 3*OI 3) operation, core % mot h'idasuc iris la,Wllfy o''ofetuk-Y in Se " Scrod or %ii% gin
                            >0ne recirculation loop may be in op                                   pro
>0ne recirculation loop may be in op pro 4mpts-we-applied-when-the-essoci et
                          ,  ,                            4mpts-we-applied-when-the-essoci et
~ 0:.:.:,.= =.~ = - y m = =-
                                  ~ 0:.:.:,.= =.~ = - y m = =-
F
(     HGR)," single loo operation limits                         pecified in F
(
                        .. 4        eCOLRp                                                                                                                                 l     W
HGR)," single loo operation limits pecified in 4
                                  ,  LCO 3.2.2, " MINI                   CRITICAL POWER         10 (MCPR)," si gl o operation                   mits Isoecifiaa in       +k. entp1 and av n
eCOLRp l
CO 3.3.1.1, " Reactor Protection System (RPS)                                                   u MC                                     f Instrumeritation." Function 2.b (Average Power an e                                                                                     / Achm MonitorslFle ''hudhimulated Thermal Power Allowable Value of Tabl_M1.1-1_is reset for s ngle
W LCO 3.2.2, " MINI CRITICAL POWER 10 (MCPR)," si gl o operation mits Isoecifiaa in
                                                                                                                                                        ,                      N aa.e)\ f loop operatio )                           (   ppe               ,                                                                          />
+k. entp1 and n
    ?
av CO 3.3.1.1, " Reactor Protection System (RPS) u MC f
APPLICABILITY:                  V' lME(LT MODES I and 2.                      L            3 41- l j'                                                                                           ?e ACTIONS                                                 @                                                                                                                  &
aa.e)\\
CONDITION                                         REQUIRED ACTION                 COMPLETION TIME Reg rement of the                               A.1   Satisfy t                     24 hou LC not a     .                                        require nts of the LCO.
Achm Instrumeritation." Function 2.b (Average Power an e
      @  /
/
( --nm. .; ....:: .;, :=.                                                                       (continued)
MonitorslFle ''hudhimulated Thermal Power N
            /tdsEET 3.y.1- 2.
f Allowable Value of Tabl_M1.1-1_is reset for s ngle loop operatio )
BWR/4 STS                                                   3.4-1                             Rev 1, 04/07/95 w4 "
(
ppe
/>
V' lME(LT 3 41-l j'
?
?
APPLICABILITY:
MODES I and 2.
L e
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Reg rement of the A.1 Satisfy t 24 hou LC not a require nts of the LCO.
/
( --nm..;....::.;, :=.
(continued)
/tdsEET 3.y.1-2.
BWR/4 STS 3.4-1 Rev 1, 04/07/95 w4 "
t
t


I Recirculation Loops Operating 3.4.1 INSERT 3.4.1 - 1 LC0 g
I Recirculation Loops Operating 3.4.1 INSERT 3.4.1 - 1 g
3.4.1.1       J b.
LC0 3.4.1.1 J
b.
2.
2.
THERMAL POWER is s 67.2% RTP.
THERMAL POWER is s 67.2% RTP.
                              ..........................N0TE-----
..........................N0TE----- ------------------ -- g 3> 4 Required allowable value modification for single loop operation may be delayed for up to 4 hours after transition from two recirculation loop operation to single y.q,t.1 recirculation loop operation.
Required allowable value modification      ------------------
Ac. nog a.1 FERMI - UNIT 2 Page 3.4 1 (1) (INSERT)
for single loop -- g 3> 4 operation may be delayed for up to 4 hours after transition from two recirculation loop operation to single                 y.q,t.1 recirculation loop operation.                                     Ac. nog a.1 FERMI - UNIT 2         Page 3.4 1 (1) (INSERT)               REVISION 10, 07/09/99l
REVISION 10, 07/09/99l
 
Recirculation Loops Operating B 3.4.1 BASES
.s I
APPLICABLE A plant specific LOCA analysis has been performed assuming SAFETY ANALYSES only one operating recirculation loop. This analysis has (continued) demonstrated that, in the event of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency Core Cooling System response will provide adequate core coo {
j


Recirculation Loops Operating B 3.4.1
==; revi,:
    ..                BASES
le er. ::fified The transient analyses of Chapter 15 of the SAR have also been performed for single recirculation loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed,;r n !d;d 1; 7.^7; P3 r:; i - -te a-a d 'f-d.
  .s I
During single recirculation loop operation, modification to the Reactor Protection System (RPS) average power range monitor (APRM) instrument setpoints is also required to account for the diffe t,
APPLICABLE            A plant specific LOCA analysis has been performed assuming SAFETY ANALYSES      only one operating recirculation loop. This analysis has (continued)        demonstrated that, in the event of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency Core Cooling System response will provide adequate core coo {          .
relationships between recirculation drive flow and. ector fI core flow.:;: :t!?
j  ==; revi,: le er. ::fified The transient analyses of Chapter 15 of the SAR have also been performed for single recirculation loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed,;r n !d;d 1; 7.^7; P3     r:; i - -te a-a d 'f-d. During single recirculation loop operation, modification to the Reactor Protection System (RPS) average power range monitor (APRM) instrument setpoints is also required to account for the diffe t ,
?- !!? !''ed fr t.'
relationships between recirculation drive flow and . ector
% ;. The APRM W W
            '2, . ,                                          The A" E P. trd ". = eetveir.t; fr :te:h _!ee n
'2,.,
                    '-              fI core flow.:;: :t!?
The A" E P. trd ". = eetveir.t; fr :te:h _!ee n r Inferi fimulated T)(FJD%I tsetpoint is in LCO 3.3.1.1, " Reactor Protection 5fsteli ( 5 Instr 5==a+=tlan."
r
g3 3.v,/-2. I-
                                                        ?- !!? !''ed fr t.' % ;. The APRM W W fimulated T)(FJD%I                 tsetpoint is in LCO 3.3.1.1, " Reactor Inferi                  Protection 5fsteli ( 5 Instr 5==a+=tlan."
>Recirculatlan loops
g3 3.v,/-2.
- O[5 c* lC.
I-     >Recirculatlan loops                   - O[5 c* lC.
-- M t to cfR sct3HeXaf]erion 2 of 4he-
                                                                                            -- M   t
=^ Fol k, i.i
                                          =^ Fol k,         i.i       ..t.
..t.
to cfR sct3HeXaf]erion 2 of 4he-3 i             LC0                   Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1A to ensure that during a LOCA caused by a break of                   i sne piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. With the limits specified in 5R 3.4.I V not met, the recirculation loop with the lower flow must be considered not in operation. With only one I'Cfleu}agg,n,,1, opp gogyation ,mogtiop,to the,,__
3 i
k'                           .. ... ..      ...... - . . . . . m - - . u ,,um HEAHrENERAHC% MTC (',PZP.)'), "= 10::it: (' 00 3.2 '         .
LC0 Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1A to ensure that during a LOCA caused by a break of i
                                '                                                  [ehnt"(50 applied to allow continuea operation consistent with the 31 assumptio       of Inse rt p,4          a e:.::3.
sne piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. With the limits specified in 5R 3.4.I V not met, the recirculation loop with the lower flow must be considered not in operation. With only one I'Cfleu}agg,n,,1, opp gogyation,mogtiop,to the,,__
                                                                  ^ ^ ^
k'
o sid only y      v-&                 ondUM{aN on W EtM N f 4 %
...... -..... m - -. u,,um HEAHrENERAHC% MTC (',PZP.)'), "= 10::it: (' 00 3.2 '
4 6 3 41-3 } G (continued)
[ehnt"(50 31 applied to allow continuea operation consistent with the assumptio of e:.::3. v - &
                    -" j: liY3-                                   B 3.4-3                           ,ev 1, ^4/"Jiii s
ondUM{aN o sid only p,4 a
Ra/10
y Inse rt
^ ^ ^
on W EtM N f 4 46 3 41-3 } G (continued)
-" j: liY3-B 3.4-3
,ev 1, ^4/"Jiii Ra/10 s


r 1
r 1
Recirculation Loops Operating B 3.4.1 m
Recirculation Loops Operating B 3.4.1 m
l l                                     Insert B 3.4.1 - 2 1
l l
Insert B 3.4.1 - 2 1
Thermal-hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied.
Thermal-hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied.
1 1
1 1
Insert B 3.4.1 -3 Operations that exhibit core thermal-hydraulic instability are not permitted. Additionally, in order to avoid potential             O power oscillations due to thermal-hydraulic instability, l                     operation at certain combinations of power and flow are not permitted. These restricted power and flow regions are referred to as the " Scram" and " Exit" Regions, and are defined   f. s by Bases Figure B 3.4.1-1.                                         y l
Insert B 3.4.1 -3 Operations that exhibit core thermal-hydraulic instability are not permitted. Additionally, in order to avoid potential O
l A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to establish k
power oscillations due to thermal-hydraulic instability, l
T the APRM Simulated Thermal Power-Upscale setpoint in               y accordance with the single loop allowable value, which is specified in Table 3.3.1.1-1 and to establish operation at s; 67.2% RTP. The 4 hour period is sufficient to make the       \y adjustments given the relatively small change required. This transition that results in applying the new single-loop           D l                     allowable values to APRM OPERABILI7, is such that any APRM i                     non compliance with the required aFlowable value after this         f 4 hour allowance results in ACTIONS of LC0 3.3.1.1 being entered; no ACTION of LC0 3.4.1 would apply.
operation at certain combinations of power and flow are not permitted. These restricted power and flow regions are referred to as the " Scram" and " Exit" Regions, and are defined
l$e 9
: f. s by Bases Figure B 3.4.1-1.
l l       FERMI UNIT 2             Page B 3.4 3 (INSERT)         REVISION 10. 07/09/99l l
y l
A Note is provided to allow 4 hours following the transition k
l to single loop operation from two loop operation to establish T
the APRM Simulated Thermal Power-Upscale setpoint in y
accordance with the single loop allowable value, which is specified in Table 3.3.1.1-1 and to establish operation at
\\y s; 67.2% RTP. The 4 hour period is sufficient to make the adjustments given the relatively small change required. This transition that results in applying the new single-loop D
l allowable values to APRM OPERABILI7, is such that any APRM f
i non compliance with the required aFlowable value after this 4 hour allowance results in ACTIONS of LC0 3.3.1.1 being l$
entered; no ACTION of LC0 3.4.1 would apply.
e 9
l l
FERMI UNIT 2 Page B 3.4 3 (INSERT)
REVISION 10. 07/09/99l l


H             .
H SRVs B 3.4.3
SRVs B 3.4.3
)
    )               BASES                               p                                           ;
BASES p
: APPLICABLE       The~ overpressure protection system must accommodate the most
: APPLICABLE The~ overpressure protection system must accommodate the most
                  ' SAFETY ANALYSES- severe pressurization transient. Evaluations have determined that the most severe transient is-the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in
' SAFETY ANALYSES-severe pressurization transient. Evaluations have determined that the most severe transient is-the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in
                                    .the safety mode. The analysis results demonstrate.that the design SRV capacity is capable of maintaining reactor pressure below the ASE Code limit of 110% of vessel design pressure 1(110% x 1250 psig
.the safety mode. The analysis results demonstrate.that the design SRV capacity is capable of maintaining reactor pressure below the ASE Code limit of 110% of vessel design pressure 1(110% x 1250 psig
* 1375 psig). This LCO helps to ensure that the acceptance limit of 1375 psig is met during.
* 1375 psig). This LCO helps to ensure that the acceptance limit of 1375 psig is met during.
the Design Basis Event.
the Design Basis Event.
From an over>ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected.to actuate the SRVs.
From an over>ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected.to actuate the SRVs.
SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
I LC0             The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The. requirements of this LCO are applicable only to the capability of the SRVs to mechanically open to relieve -
I LC0 The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The. requirements of this LCO are applicable only to the capability of the SRVs to mechanically open to relieve -
excess pressure when the lift setpoint is exceeded (safety function).
excess pressure when the lift setpoint is exceeded (safety function).
The SRV setpoints, and 3% allowance for setpoint drift. are Ok~l      ,
Ok~l The SRV setpoints, and 3% allowance for setpoint drift. are established to ensure that the ASME Code limit on peak reactor pressure.is satisfied. The ASME Code specifications require the lowest safety valve set vessel design pressure (1250 psig) point to be at or below and the highest safety-valve-to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based'on these setpoints.
established to ensure that the ASME Code limit on peak reactor pressure.is satisfied. The ASME Code specifications require the lowest safety valve set vessel design pressure (1250 psig)   andpoint to be atsafety-the highest or below valve-to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based'on these setpoints.
Operation with fewer valves OPERABLE than specified, or with i
Operation with fewer valves OPERABLE than specified, or with     i setpoints outside the ASME limits, could result in a more       i severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor
setpoints outside the ASME limits, could result in a more i
    ...                              pressure being exceeded, i
severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded, i
        ?
?
l FERMI:- UNIT 2 -                       B 3.4.3 -2             Revision 10   07/09/99
l FERMI:- UNIT 2 -
B 3.4.3 -2 Revision 10 07/09/99


S/RVs B 3.4.3 f           BASES APPLICABLE         pressure (110% x 1250 psig - 1375 psig). This LC0 helps to SAFETY AMALYSES   ensure that the acceptance limit of 1375 psig is met during (continued)   the Design Basis Event.
S/RVs B 3.4.3 f
BASES APPLICABLE pressure (110% x 1250 psig - 1375 psig). This LC0 helps to SAFETY AMALYSES ensure that the acceptance limit of 1375 psig is met during (continued) the Design Basis Event.
From an overpressure standpoint, the design basis events are bounded by the MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the S/RVs.
From an overpressure standpoint, the design basis events are bounded by the MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the S/RVs.
Op,f       S/RVs satisfy Criterioni_b    3- of 'M 50.$
Op,f S/RVs satisfy Criterion 3 of 'M ""! "eli-{-- Ote% D )- c t^
t^
i_b CTR 50.$ Ql'2 LC0 The safety functiori ofX1lyS/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The requirements of this LC0 are applicable only to the capability of the S mechanically open to relieve excess pressu/RVs to re when the lift setpoint is exceeded,Jsafety faartioni e Op*q TheS/RVsetpoints.(.r,..staolisneasoensurethatthee AttoGwet. Or algaid d aw3 3)
                                                                      ""! "eli-{--
Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for ssurization conditions. The transie_n valuations in ove arW+basedonthesesetpoints;4 sty"ofeehade-tta
CTR
]
_-          Ql'2 Ote% D )- c LC0             The safety functiori ofX1lyS/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The requirements of this LC0 are applicable only to the capability of the S mechanically open to relieve excess pressu/RVs re whentothe lift setpoint is exceeded,Jsafety faartioni e                 -
t
Op*q                               aw3 3)
:f ' f-9 ree ':fet! : a' + " a' na 2:. ;;tp'.;.t dei't tr ;n;f t :: :'f:f t;n; ;f ;;;.;;r;;ti;;;.
TheS/RVsetpoints.(.r,..staolisneasoensurethatthee           AttoGwet. Or algaid d Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for ove    ssurization conditions. The transie_n   valuations in
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
  ]  -                .
1 l
t arW+basedonthesesetpoints;4 sty"ofeehade-tta
,l U
:f ' f-9 ree ':fet! :     a' + " a' na -
APPLICABILITY InMODES1,2,and3.hS/RVsmustbeOPERABLE,since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Heat Removal (RHR) System is capable of i
2:. ;;tp'.;.t l
dissipating the core heat.
dei't tr ;n;f t :: :'f:f t;n; ;f ;;;.;;r;;ti;;;.
Operation with fewer valves OPERABLE than specified, or with                     ;
setpoints outside the ASME limits, could result in a more                       '
severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.                                                         1
                                                          -                                                    l
          ,l APPLICABILITY U
InMODES1,2,and3.hS/RVsmustbeOPERABLE,since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Heat Removal (RHR) System is capable of                         i dissipating the core heat.
(continued)
(continued)
BWR/4-STS-                         B 3.4-13                   Re; 1,- 0"j^7/n-
BWR/4-STS-B 3.4-13 Re; 1,- 0"j^7/n-


RCS Operational LEAKAGE 3.4.4
RCS Operational LEAKAGE 3.4.4
    )       3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LC0 3.4.4-         RCS operational LEAXAGE shall be limited to:
)
: a. No pressure boundary LEAKAGE:
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LC0 3.4.4-RCS operational LEAXAGE shall be limited to:
: b. 5 5 gpm unidentified LEAKAGE:
a.
: c. s 25 gpm total LEAKAGE averaged over the previous 24 hour period: and
No pressure boundary LEAKAGE:
: d. s 2 gpm increase in unider . ,fied LEAKAGE within the previous 24 hour period in MODE 1.
b.
APPLICABILITY:     MODES 1, 2. and 3.
5 5 gpm unidentified LEAKAGE:
ACTIONS CONDITION                   REQUIRED ACTION           COMPLETION TIME s
c.
A. Unidentified LEAKAGE     A.1     Reduce LEAKAGE to       4 hours not within limit,                 within limits.
s 25 gpm total LEAKAGE averaged over the previous 24 hour period: and d.
s 2 gpm increase in unider.,fied LEAKAGE within the previous 24 hour period in MODE 1.
APPLICABILITY:
MODES 1, 2. and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME s
A.
Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours not within limit, within limits.
M Total LEAKAGE not within limit.
M Total LEAKAGE not within limit.
h       B. Unidentified LEAKAGE     B.1     Reduce LEAKAGE to       4 hours t           increase not within               within limits.
h B.
      ?           limit.
Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours t
k                                     2 (continued) l l
increase not within within limits.
l- FERMI - UNIT 2                         3.4 8                 Revision 10, 07/09/99   j
?
limit.
k 2
(continued) l l
l-FERMI - UNIT 2 3.4 8 Revision 10, 07/09/99 j


l
l l
  ,        .                                                                                    l RCS Operational LEAKAGE
RCS Operational LEAKAGE 3.4.4
                    $                                                                    3.4.4 l
)
  )         ACTIONS (continued)                                                               l CONDITION                   REQUIRED ACTION           COMPLETION TIME   j g                                                                                       i B. (continued)               B.2     Verify source of       4 hours unidentified LEAKAGE increase is not                           4 service sensitive type 304 or type 316 austenitic stainless steel.
ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME j
C. Required Action and       C.1     Be in MODE 3.           12 hours associated Completion Time of Condition A       6tLD                                               >
i g
or B not met.                                                                 I C.2     Be in MODE 4.           36 hours 2
B.
Pressure boundary LEAKAGE exists.                                                              .
(continued)
i SURVEILLANCE REQUIREMENTS SURVEILLANCE                             FREQUENCY fl   SR 3.4.4.1     Verify RCS unidentified and total LEAKAGE and unidentified LEAKAGE increase are 8 hours within limits.
B.2 Verify source of 4 hours unidentified LEAKAGE increase is not 4
l FERMI     UNIT 2                       3.4 9               Revision 10, 07/09/99
service sensitive type 304 or type 316 austenitic stainless steel.
C.
Required Action and C.1 Be in MODE 3.
12 hours associated Completion Time of Condition A 6tLD or B not met.
C.2 Be in MODE 4.
36 hours 2
Pressure boundary LEAKAGE exists.
i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY fl SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 8 hours and unidentified LEAKAGE increase are within limits.
l FERMI UNIT 2 3.4 9 Revision 10, 07/09/99


r (c
r (c
* L RCS Operational LEAKAGE B 3.4.4
L RCS Operational LEAKAGE B 3.4.4
      )         BASES APPLICABILITY       In MODES 1, 2. .and 3 the RCS operational LEAKAGE LC0 a> plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized.
)
In MODES 4 and 5. RCS operational LEAKAGE limits are not required since the reactor-is not pressurized and stresses l                                   .in the RCPB materials and potential for LEAKAGE are reduced.
BASES APPLICABILITY In MODES 1, 2..and 3 the RCS operational LEAKAGE LC0 a> plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized.
R               -ACTIONS             &J l                                     With RCS unidentified or total LEAKAGE greater than the
In MODES 4 and 5. RCS operational LEAKAGE limits are not required since the reactor-is not pressurized and stresses l
                                    . limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively belos the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as h
.in the RCPB materials and potential for LEAKAGE are reduced.
R
-ACTIONS
&J l
With RCS unidentified or total LEAKAGE greater than the
. limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively belos the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down.
If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as h
identified LEAKAGE:.however, the total LEAKAGE limit would remain tuhanged.
identified LEAKAGE:.however, the total LEAKAGE limit would remain tuhanged.
      ' kl -                         B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpm within a 24 hour-t                                     period is an indication of a potential flaw in the RCPB and
' kl -
!-                                    must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required Completion Time by evaluating service sensitive type 304 and
B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpm within a 24 hour-t period is an indication of a potential flaw in the RCPB and must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required Completion Time by evaluating service sensitive type 304 and
                                    . type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or
. type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or
: intermittent flow fluids and determine it is not the source I                                   of the increased LEAKAGE. This type piping is very I
: intermittent flow fluids and determine it is not the source I
susceptible to IGSCC. For an unidentified LEAKAGE increase l                                   greater than required limits (in accordance with LCO 3.0.2),
of the increased LEAKAGE. This type piping is very I
an alternative to this evaluation is to reduce the LEAKAGE-increase to within limits (i.e.. reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase i                      in the previous 24 hours" limit: either by isolating the l                                   source or other possible methods).
susceptible to IGSCC. For an unidentified LEAKAGE increase l
greater than required limits (in accordance with LCO 3.0.2),
an alternative to this evaluation is to reduce the LEAKAGE-increase to within limits (i.e.. reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase in the previous 24 hours" limit: either by isolating the i
l source or other possible methods).
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
l FERMI     . UNIT 2 -                   B 3.4.4-4               Revision 10, 07/09/99 l
l FERMI
. UNIT 2 -
B 3.4.4-4 Revision 10, 07/09/99


RCS Operational LEAKAGE B 3.4.4
RCS Operational LEAKAGE B 3.4.4
    }       BASES ACTIONS (continued)
}
BASES ACTIONS (continued)
C.1 and C.2 l
C.1 and C.2 l
If any Required Action and associated Completion Time of Condition A or B is not met or if pressure ~ boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apaly. To achieve this status, the plant must be brought to 10DE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner
If any Required Action and associated Completion Time of Condition A or B is not met or if pressure ~ boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apaly. To achieve this status, the plant must be brought to 10DE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.
,                              and without challenging plant safety systems.
SURVEILLANCE SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity, RPV head flange leak detection, and sump monitoring systems).
SURVEILLANCE     SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity, RPV head flange leak detection, and sump monitoring systems).
Leakage detection instrumentation is discussed in more detail in the Bases for LC0 3.4.6 "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any method may be used to quantify LEAKAGE within the guidelines 3
Leakage detection instrumentation is discussed in more detail in the Bases for LC0 3.4.6 "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any method may be used to quantify LEAKAGE within the guidelines 3                       of Reference 5. In conjunction with alarms and other Tl administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and fur kl                       tracking required trends (Ref. 6).
of Reference 5.
REFERENCES       1. 10 CFR 50, Appendix A. GDC 30.
In conjunction with alarms and other Tl administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and fur
: 2. GEAP 5620, April 1968.
-kl tracking required trends (Ref. 6).
: 3. NUREG-76/067, October 1975.
REFERENCES 1.
l
10 CFR 50, Appendix A. GDC 30.
: 4. UFSAR, Section 5.2.7.4.3.3.
2.
: 5. Regulatory Guide 1.45.
GEAP 5620, April 1968.
: 6. G0neric Letter 88-01, Supplement 1.
3.
l FERMI - UNIT 2                       B 3.4.4-5               Revision 10, 07/09/99 i
NUREG-76/067, October 1975.
l 4.
UFSAR, Section 5.2.7.4.3.3.
5.
Regulatory Guide 1.45.
6.
G0neric Letter 88-01, Supplement 1.
l FERMI - UNIT 2 B 3.4.4-5 Revision 10, 07/09/99 i


Sfec4cotwa 344 D
S ec4cotwa 344 f
      .p REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
D
. p REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued)
ACTION: (Continued)
: e.      In OPERATIONAL CONDITION 1, with any reactor coolant system
In OPERATIONAL CONDITION 1, with any reactor coolant system
[ g , art $               UNIDENTIFIED LEAKAGE increase greater than 2 gpa within any 24
[ g, art $
                '                    hour period, identify the source of leakage increase as not service sensitive Type'304 or 316 austenttic stainless steel
e.
                                  - within 4 haursfor be in at least HOT SHUTDOWN within the next 12 Action C                  hours and in COLD SHUTDOWN within the following 24 hours.
UNIDENTIFIED LEAKAGE increase greater than 2 gpa within any 24 hour period, identify the source of leakage increase as not service sensitive Type'304 or 316 austenttic stainless steel Action C
: f.       In OPE           L COND         2 and (with any         ctor coo nt system v           L.2 UNID       FIED L         increase       ater tha     gpm wit       any 4   ur   I p     d, ident         he sour     f leakage     rease       et serv nsitive           304 or       austeniti       ainles     eel wi       4     /
- within 4 haursfor be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
hours           in at -     t HOT SHUT       withi     e next in         SHUTDOW       thin the fo     wing 24 ours j-             hoursand}
f.
SURVEILLANCE REOUIREMENTS
In OPE L COND 2 and (with any ctor coo nt system v L.2 UNID FIED L increase ater tha gpm wit any 4 ur I
        ~3 4 -}     -4.4.2.2.b The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
p d, ident he sour f leakage rease et serv nsitive 304 or austeniti ainles eel wi 4
o          e ne d en d =n+                   We,qese'o*'u                   LA.I
/
,                                        dio       vit[6tleastonceperenours1_
hours in at -
bgo#DnaAne primary corttetsment-tump -tro er      hours th vrt.MilDML wnplIIUM ItVand at least once per 4 hour (iin OPERATIONAL CONDITIONS 2 and 3,                                             l          d 3            _
t HOT SHUT withi e next hoursand}
T
in SHUTDOW thin the fo wing 24 ours j-SURVEILLANCE REOUIREMENTS
                      /   [c #enftorgthe.ArfGeMacMn4Mel hourst*rin OPERA"IONAL CONDITION W and at least#once                 1dOper 4 [j 'f
~3 4 -}
                    <                                                                                                                i ours in OP7 RATIONAL CONDITIONS 2 and 3, and                                         ,,
-4.4.2.2.b The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
rin AdakAMM%
e ne d en d =n+
We,qese'o*'u LA.I o
dio vit[6tleastonceperenours1_
bgo#DnaAne primary corttetsment-tump -tro hour (ihours th vrt.MilDML wnplIIUM ItVand at least once per 4 l
d er 3
in OPERATIONAL CONDITIONS 2 and 3, T
/ [c#enftorgthe.ArfGeMacMn4Mel # 1dO [ 'f hourst*rin OPERA"IONAL CONDITION W and at least once per 4 j i
ours in OP7 RATIONAL CONDITIONS 2 and 3, and rin AdakAMM%
LA. )
LA. )
l I
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FERMI - UNIT 2                               3/4 4-11                       Amendment No. 89 1
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  %m' PAGE- c2             0F                                 86VlO 02
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I FERMI - UNIT 2 3/4 4-11 Amendment No. 89 1
%m' PAGE-c2 0F 02 86VlO


DISCUSSION OF CHANGES ITS8 SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE TECHNICAL CHANGES - LESS RESTRICTIVE                                                           O
DISCUSSION OF CHANGES ITS8 SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE TECHNICAL CHANGES - LESS RESTRICTIVE O
    " Specific"                                                                                   2.
" Specific" 2.
L.1           CTS 4.4.3.2.1 rquires that leakage be demonstrated to be within limit,in N
N L.1 CTS 4.4.3.2.1 rquires that leakage be demonstrated to be within limit,in part, by monitoring primary containment atmospheric gaseous radioactivity at least once per 4 hours. However, the remaining parts of CTS 4.3.2.1 l
part, by monitoring primary containment atmospheric gaseous radioactivity at least once per 4 hours. However, the remaining parts of CTS 4.3.2.1         l require leakage be demonstrated to be within limit by monitoring once per 12 hours; and this 12 hour monitoring is done on the system that actually quantifies the leakage (the atmospheric gaseous radioactivity monitor is p_ot o
require leakage be demonstrated to be within limit by monitoring once per 12 hours; and this 12 hour monitoring is done on the system that actually quantifies the leakage (the atmospheric gaseous radioactivity monitor is p_ot o
utilized to quantify the leakage for comparison to the LCO limit, as provided in CTS footnote
utilized to quantify the leakage for comparison to the LCO limit, as provided in CTS footnote
* to the referenced surveillance). Note also that in Mode 1   l this Frequency is restricted from applying the 25% extension of ITS SR 3.0.2.
* to the referenced surveillance). Note also that in Mode 1 l
this Frequency is restricted from applying the 25% extension of ITS SR 3.0.2.
ITS SR 3.4.4.1 requires verification every 8 hours that the RCS unidentified and total Leakage, and unidentified Leakage increase, are within limits (which is more restrictive than these latter CTS requirements, but included here for completeness). RCS Leakage is monitored by a variety of instruments designed to provide alarms when excessive Leakage is indicated and to quantify the various types of Leakage. In conjunction with alarms and administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying Leakage and for tracking trends. With this increased Frequency of performance (from 12 to 8 hours), the 25% extension of SR 3.0.2 is allowed to be applied (i.e., a 10 hour maximum interval; still
ITS SR 3.4.4.1 requires verification every 8 hours that the RCS unidentified and total Leakage, and unidentified Leakage increase, are within limits (which is more restrictive than these latter CTS requirements, but included here for completeness). RCS Leakage is monitored by a variety of instruments designed to provide alarms when excessive Leakage is indicated and to quantify the various types of Leakage. In conjunction with alarms and administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying Leakage and for tracking trends. With this increased Frequency of performance (from 12 to 8 hours), the 25% extension of SR 3.0.2 is allowed to be applied (i.e., a 10 hour maximum interval; still
                . more restrictive than the CTS 12 hours). This change is consistent with the intent of Generic Letter 88 01, to provide an effective means to determine any adverse trends and as such will have a negligible impact on safety.
. more restrictive than the CTS 12 hours). This change is consistent with the intent of Generic Letter 88 01, to provide an effective means to determine any Q
Q
adverse trends and as such will have a negligible impact on safety.
                                                                                                ;3 FERMI - UNIT 2                             2                 REVISION 10,       07/09/99
;3 FERMI - UNIT 2 2
REVISION 10, 07/09/99


  .                                                                          RCS Operational LEAKAGE 3.4.4 3            3.4 REACTOR COOLANT SYSTEM (RCS)
RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3 CIS}
I         3.4.4 RCS Operational LEAKAGE CIS}
I 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:
LCO 3.4.4           RCS operational LEAKAGE shall be limited to:
a.
: a. No pressure boundary LEAKAGE;
No pressure boundary LEAKAGE; 3**
: b. s   gpa unidentified LEAKAGE                       3**
b.
p*l                    c. s fSS) gpm total LEAKAGE averaged over the previous 24hourperiod;fand
s gpa unidentified LEAKAGE c.
: d. s 2 gpa increase in unidentified LEAKAGE within the             l previous M hour period in MODE 1.K                             j APPLICABILITY:     MODES 1, 2, and 3.
s fSS) gpm total LEAKAGE averaged over the previous p*l 24hourperiod;fand d.
ACTIONS CONDITION                   REQUIRED ACTION           COMPLETION TIME A. Unidentified LEAKAGE       A.1     Reduce LEAKAGE to       4 hours not within limit,                 within limits.                         ,3,7 Achto!L b.
s 2 gpa increase in unidentified LEAKAGE within the previous M hour period in MODE 1.K j
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours not within limit, within limits.
,3,7 Achto!L b.
Total LEAKAGE not within limit.
Total LEAKAGE not within limit.
B. Unidentified LEAKAGE increase not within B.1     Reduce LEAKAGE to within limits.
B.
4 hours              g limit.
Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours g
                                                                                                        \
increase not within within limits.
                                                  .Qll                                                 N t
limit.
(continued) 1
\\
              - "":n/4 373 -
.Qll N
                  .                                      3.4-7                     En 1, G4/G7/55 e#
t (continued) 1
- "":n/4 373 -
3.4-7 En 1, G4/G7/55 e#
1
1


l RCS Operational LEAKAGE 3.4.4 ACTIONS                                                                          / CTS)
l RCS Operational LEAKAGE 3.4.4
CONDITION                   REQUIRED ACTION           COMPLETION TIME           y i
/ CTS)
B.   (continued)               B.2     Verify source of       4 hours unidentified LEAKAGE                 3.4. 3. 2 increase is not                         ,
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME y
service sensitive                 dc,htoftd.
i B.
(continued)
B.2 Verify source of 4 hours unidentified LEAKAGE 3.4. 3. 2 increase is not service sensitive dc,htoftd.
type 304 or type 316 austenitic stainless steel.
type 304 or type 316 austenitic stainless steel.
C. Required Action and       C.1     Be in MODE 3.
C.
associated Completion                                       12 hours Time of Condition A        AEl                                            3.4.3.1 or B not met.                                                           d#^ #>
Required Action and C.1 Be in MODE 3.
C.2     Be in MODE 4.           36 hours     b /6 DE Pressure boundary LEAKAGE exists.
12 hours associated Completion 3.4.3.1 Time of Condition A AEl or B not met.
.c SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1       Verify RCS unidentified and total LEAKAGE       S hours and unidentified LEAKAGE increase are                           ,4.3,2.tk G within limits.                                                         /   g 3L"'/t :;T3                             3.4-B                     -Rev 1, O'/07/o t
d#^ #>
C.2 Be in MODE 4.
36 hours b /6 DE Pressure boundary LEAKAGE exists.
.c SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE S hours and unidentified LEAKAGE increase are
,4.3,2.tk G within limits.
/
g 3L"'/t :;T3 3.4-B
-Rev 1, O'/07/o t
./
./
Rev' W 4
Rev' W 4


RCS Operational LEAKAGE B 3.4.4 f-         BASES (continued)
RCS Operational LEAKAGE B 3.4.4 f-BASES (continued)
ACTIONS             L1 With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as identified LEAKAGE; however, the total LEAKAGE limit would remain unchanged.
ACTIONS L1 With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as identified LEAKAGE; however, the total LEAKAGE limit would remain unchanged.
y i
y i
k B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpa within         our period is an indication of a potential flaw in the RCPB and                     1 must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to             _
k B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpa within our period is an indication of a potential flaw in the RCPB and 1
the source of the LEAKAGE increase within the required un accorda m Completion Timer)for an unidentified LEAKAGE increase         w;w r   o.z ')
must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to the source of the LEAKAGE increase within the required un accorda m Completion Timer)for an unidentified LEAKAGE increase w;w r o.z ')
greater than required limitsf an alternative to ' '--               ^
greater than required limitsf an alternative to ' '--
LEAKAGE increase to within limits (i.e., reducing the         thi5e*Lution zy       LEAKAGE rate such that the current rate is less than the Qsto %ct fhe, "2 com increase in the previou       hours" limit; either by         ~
^
Op'q isolating the source or other p ss ble methods? is::ta=.
LEAKAGE increase to within limits (i.e., reducing the thi5e*Lution zy LEAKAGE rate such that the current rate is less than the Qsto %ct fhe, Op'q "2 com increase in the previou hours" limit; either by
p)                         r-+m service sensitive type 3v, anc type 3e6 austenttici est{afj stainless steel iping that is subject to high stress or that contains re atively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to ISSCC.
~
isolating the source or other p ss ble methods? is::ta=.
p) r-+m service sensitive type 3v, anc type 3e6 austenttici est{afj stainless steel iping that is subject to high stress or that contains re atively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to ISSCC.
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B is not met or if pressure boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within It hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, (continued) nun /A NS--                             B 3.4-20                   Rr; I, 0i/07/95 Rev10
C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B is not met or if pressure boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within It hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, (continued) nun /A NS--
B 3.4-20 Rr; I, 0i/07/95 Rev10


I RCS Operational LEAKAGE B 3.4.4 5-           BASES
I RCS Operational LEAKAGE B 3.4.4 5-BASES
      ]
]
ACTIONS         C.1 and C.2 (continued) based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.
ACTIONS C.1 and C.2 (continued) based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.
                                                                      =
=
les               Con kinme.<tMmos JAra 6esem.s SURVEILLANCE    SR 3.4.4.1      /d.oum(/ae   f,V;/yl,, R,wbv Ata,I 8/ age lee.le c(4 1
les Con kinme.<tMmos JAra 6esem.s
REQUIREMENTS                               men i e e M _s vs1eis.3         -
/d. (/ae f,V;/yl,, R,wbv Ata,I 8/ age lee.le c(4 SURVEILLANCE SR 3.4.4.1 1
The RCS LEAKAG       s mon ored by a vari y of instrumiints               -
REQUIREMENTS oum men i e e M _s vs1eis.3 The RCS LEAKAG s mon ored by a vari y of instrumiints designed to provide alarms when L is indicated and to quantify the various types of LEAKAG Leakage detection instrumentation is discussed in more detail in the Bases for LCO 3.4.6, 'RCS Leakage Detection Instrumentation." Sump
designed to provide alarms when L               is indicated and to quantify the various types of LEAKAG           Leakage detection instrumentation is discussed in more detail in the Bases for LCO 3.4.6, 'RCS Leakage Detection Instrumentation." Sump
' level and flow rate are typically monitored to determine actual LEAKAGE rates; however, an quantify LEAKAGE within the guide'y method may be used to Jines of Reference 5.
                            ' level and flow rate are typically monitored to determine actual LEAKAGE rates; however, an quantify LEAKAGE within the guide'y     Jines method     may 5.
In conjunction with alarus and other administrative controls, an 8. hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and for tracking required trends
of Reference  be used In to .
[
            '                  conjunction with alarus and other administrative controls, an 8. hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and for tracking required trends                     [
(Ref. 6).
(Ref. 6).                                                                 I REFERENCES       1. 10 CFR 50, Appendix A. GDC 30.
I REFERENCES 1.
10 CFR 50, Appendix A. GDC 30.
r- )
r- )
    ./                         2. GEAP-5620, April 1968.
./
: 3. NUREG-76/067, October 1975.
2.
                                                                      ,2 .Y.
GEAP-5620, April 1968.
                              .4. yFSAR, Section ."..         ...
3.
: 5. Regulatory Guide 1.45.
NUREG-76/067, October 1975.
: 6. Generic Letter 88-01, Supplement 1.
,2.Y.
                                          . n.,,   _
.4. yFSAR, Section.".....
              ?""f' !!!   -
5.
B 3.4-21                         Rsi ;, O'/0:'/0 fievl0
Regulatory Guide 1.45.
6.
Generic Letter 88-01, Supplement 1.
. n.,,
?""f' !!!
B 3.4-21 Rsi ;, O'/0:'/0 fievl0


JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE NON BRACKETED PLANT SPECIFIC CBANGES P.1       These changes are made to NUREG 1433 to reflect Fermi 2 current l                   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.
JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE NON BRACKETED PLANT SPECIFIC CBANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current l
!        P.2       Bases changes are made to reflect plant specific design details, I                   equipment terminology, and analyses.
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.
P.3       Not used.
P.2 Bases changes are made to reflect plant specific design details, I
P.4       Change made for editorial preference or clarity.
equipment terminology, and analyses.
h P.5       Not used.                                                               d P.6       The reference to the NRC Policy Statement has been replaced with a lh more appropriate reference to the Improved Technical Specification
P.3 Not used.
                    " split" criteria found in 10 CFR 50.36(c)(2)(ii).
P.4 Change made for editorial preference or clarity.
      )
h lh d
4 FERMI UNIT 2                         1                 REVISION 10, 07/09/99l
P.5 Not used.
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).
)
4 FERMI UNIT 2 1
REVISION 10, 07/09/99l


1 I
1 I
RCS Leakage Detection Instrumentation 3.4.6
RCS Leakage Detection Instrumentation 3.4.6
    ]         3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detetion Instrumentation LC0 3.4.6                 The following RCS leakage detection instrumentation. shall be OPERABLE:
]
: a. Drywell floor drain sump flow monitoring system:
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detetion Instrumentation LC0 3.4.6 The following RCS leakage detection instrumentation. shall be OPERABLE:
d                                 b. The primary containment atmosphere gaseous radioactivity 1                                       monitoring system channel; and
a.
: c. Drywell floor drain sump level monitoring system.
Drywell floor drain sump flow monitoring system:
APPLICABILITY:             MODES 1, 2, and 3.
d b.
The primary containment atmosphere gaseous radioactivity 1
monitoring system channel; and c.
Drywell floor drain sump level monitoring system.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS
ACTIONS
              .................................. NOTE- ---- ---- - - -------------                        ---------
.................................. NOTE- ---- ---- - - -------------
LC0 3.0.4 is not applicable.
LC0 3.0.4 is not applicable.
s CONDITION                                 REQUIRED ACTION             COMPLETION TIME A. Drywell floor drain                   A.1         Restore drywell floor     30 days sump flow monitoring                               drain sump flow system inoperable.                                 monitoring system to OPERABLE status.
s CONDITION REQUIRED ACTION COMPLETION TIME A.
              .B. Required primary                       B.1         Analyze grab samples     Once per containment atmosphere                             of primary               24 hours gaseous radioactivity                             containment monitoring system                                 atmosphere.
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 containment atmosphere of primary 24 hours gaseous radioactivity containment monitoring system atmosphere.
inoperable.
inoperable.
(continued) j l FERMI       UNIT 2                                     3.4-13                 Revision 10, 07/09/99
(continued) j l FERMI UNIT 2 3.4-13 Revision 10, 07/09/99


1 RCS Leakage Detection Instrumentation     !
RCS Leakage Detection Instrumentation 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS)
3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detection Instrumentation                               [ cts)      l d
[ cts) 3.4.6 RCS Leakage Detection Instrumentation d
LCO 3.4.6         The following RCS leakage detection instrumentation shall be       I OPERABLE.
LCO 3.4.6 The following RCS leakage detection instrumentation shall be
[
[
: a. Drywell floor drain sumpfmo to ing system:M(7.4,J.l.b h
OPERABLE.
: b.   ^ - ""---' -           pr imary containment 6
Drywell floor drain sumpfmo to ing system:M(7.4,J.l.b h a.
                      *g cat-r em+-matmosphe           gaseousmonitoring_systeg;f.43I.
b.
^ - ""---' -
imary containment 6 pr gaseousmonitoring_systeg;f.43I.
*g cat-r em+-matmosphe Stand a
9foyg@g,,g r cooler 3pertiensajed1pate]
c.
c.
Stand                      a 9foyg@g,,g noe     r cooler 3pertiensajed1pate]
noe h
h DrfN *LE Noor drain surp APPLICABILITY:   MODES 1, 2, and 3.     '###$   "'*0 N##'"j 5[8b-               g ACTIONS f                 3 CONDITION
DrfN *LE Noor drain surp APPLICABILITY:
                                      \     REQUIRED ACTION           COMPLETION TIME
MODES 1, 2, and 3.
                                        \
'###$ "'*0 N##'"j 5[8b-g ACTIONS f 3
A. Drywell floor drain       ----
\\
                                                  -NOTE-------- D g         sumpamonitoring system   LCO 3.0.4 is not applicable.             3,4,3 l       !
CONDITION REQUIRED ACTION COMPLETION TIME
I j          inoperable.             .                            .          Ac-l.io tt A.I     Restore drywell floor   30 days drain summ monitoring system tof0PERABLE status.
\\
A.
Drywell floor drain
-NOTE-------- D g
sumpamonitoring system LCO 3.0.4 is not applicable.
3,4,3 l j
inoperable.
Ac-l.io tt A.I Restore drywell floor 30 days drain summ monitoring system tof0PERABLE status.
(continued)
(continued)
    .-0Wtf* T.r-                           3.4-12                     En 1, 54/07/fr5-
.-0Wtf* T.r-3.4-12 En 1, 54/07/fr5-W fD
~~'
~ ~ '
W fD


RCS P/T Limits 3.4.10
RCS P/T Limits 3.4.10
  ]                 SURVEILLANCE REQUIREMENTS (continued)
]
SURVEILLANCE                                               FREQUENCY SR 3.4.10.5   -- ------- --- - - NOTE-- ------ ----------
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.10.5
-- ------- --- - - NOTE-- ------ ----------
Only required to be met during a THERMAL POWER increase or recirculation flow
Only required to be met during a THERMAL POWER increase or recirculation flow
            /                       inc.' ease in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow.
/
L                                                                                                  Once within Verify the difference between the bottom                               15 minutes l                 head coolant temperature and the RPV steam                             prior to a space coolant temperature is s 145'F.                                 THERMAL POWER l                                                                                       increase or recirculation l
inc.' ease in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow.
l                                                                                        flow increase SR 3.4.10.6   --------- --- ---- NOTE-                   --- - - ------- -
Once within L
Only required to be met during a THERMAL POWER increase or recirculation flow                                                     i increase in MODES 1 and 2 with one non-isolated idle recirculation loo) when THERMAL POWER is s 30% RTP or w1en                                                       l operating loop flow is s 50t rated loop flow.
Verify the difference between the bottom 15 minutes l
                                    ...........................................                          Once within
head coolant temperature and the RPV steam prior to a space coolant temperature is s 145'F.
                                                                                                  .      15 minutes         4 l                 Verify the difference between the reactor                             prior to a coolant temperature in the idle                                       THERMAL POWER
THERMAL POWER l
              /                   . recirculation loop and the RPV coolant                               increase or temperature is s 50*F.                                                 recirculation 3f l                                                                                            flow increase l
increase or recirculation l
l (continued)   !
flow increase l
1 I
SR 3.4.10.6
I l FERMI.- UNIT 2                                       3.4 26                     Revision 10   07/09/99
--------- --- ---- NOTE-Only required to be met during a THERMAL POWER increase or recirculation flow i
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 50t rated loop flow.
Once within 15 minutes 4
l Verify the difference between the reactor prior to a coolant temperature in the idle THERMAL POWER
/
. recirculation loop and the RPV coolant increase or 3f l temperature is s 50*F.
recirculation flow increase (continued) 1 I
l FERMI.- UNIT 2 3.4 26 Revision 10 07/09/99


o ,_      .
o r
r E                                                                                       RCS P/T Limits B 3.4.10   i l   }           ' BASES SURVEILLANCE. REQUIREMENTS (continued)
E RCS P/T Limits B 3.4.10 i
,                                      This SR has been modified with a Note that requires this l-                                     Surveillance to be performed as applicable only during           J system heatup and cooldown operations and inservice leakage and hydrostatic testing.                                       <
l }
SR 3.4.10.2 l
' BASES SURVEILLANCE. REQUIREMENTS (continued)
A separate limit is used when the reactor is approaching           )
This SR has been modified with a Note that requires this l-Surveillance to be performed as applicable only during J
I criticality. Conse uently, the RCS pressure and temperature must be verified wi hin the appropriate limits before withdrawing control rods that will make the reactor critical.
system heatup and cooldown operations and inservice leakage and hydrostatic testing.
Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality           ;
SR 3.4.10.2 A separate limit is used when the reactor is approaching
provides adequate assurance that the limits will not be           j exceeded between the time of the Surveillance and the time         !
)
of the control rod withdrawal.                                     l SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3                               Differential temperatures within the applicable limits             l
l I
      ~j'                             ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances.
criticality. Conse uently, the RCS pressure and temperature must be verified wi hin the appropriate limits before withdrawing control rods that will make the reactor critical.
Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be j
exceeded between the time of the Surveillance and the time of the control rod withdrawal.
SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3
Differential temperatures within the applicable limits l
~j' ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances.
Limiting _ differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow
Limiting _ differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow
                                    -increase in single loop operation, while THERMAL POWER s 30t RTP or operating loop flow s 50% of rated loop flow, ensure         i that thermal stre b es resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design         !
-increase in single loop operation, while THERMAL POWER s 30t RTP or operating loop flow s 50% of rated loop flow, ensure i
                                    - allowances.
that thermal stre b es resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase       i during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase. or flow increase.
- allowances.
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase i
during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase. or flow increase.
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating
                                    -recirculation loop and the idle loop.
-recirculation loop and the idle loop.
J           ..
J l FERMI - UNIT 2 B 3.4.10 - 7 Revision 10, 07/09/99
l FERMI - UNIT 2                           B 3.4.10 - 7           Revision 10, 07/09/99


S fE c t r-t c N n M 8 .'h l O (MSOSeeSecTScaHM
S E c t r-t c N n M 8.'h l O f
                                                                          /                3 4. /)
(MSOSeeSecTScaHM 3 4. /)
/
lse? Set Geci $~CaNM 8 0~'I)
lse? Set Geci $~CaNM 8 0~'I)
REACTOR COOLANT SYSTEM SURVETLLANCE RFOUIREMENTS
REACTOR COOLANT SYSTEM SURVETLLANCE RFOUIREMENTS Si (8 b cy.4.1.1.1 4
* 4 (8 b cy.4.1.1.1         Each pump discharge valve shall be demonstrated OPGRABLE by Si                cling each valve through at least one complete cycle of full travel at least 3Sil         once per 18 months.                                   '
Each pump discharge valve shall be demonstrated OPGRABLE by cling each valve through at least one complete cycle of full travel at least 3Sil once per 18 months.
i.4.1.1.2       DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that:                   '
i.4.1.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that:
Sq                     a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and
Sq a.
    %cifuah%                    b. The individual recirculation pump flow controller for the 3.Y. I                     .
THERMAL POWER is less than or equal to 67.2% of RATED
operating recirculation pump is in the Manual mode, and
%cifuah%
: c. The speed of the operating recirculation pump is less than or equal to 75% of rated pump speed.
THERMAL POWER, and b.
4.4.1.1.4     With one reactor coolant system loop not in operation with TilERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
The individual recirculation pump flow controller for the 3.Y. I operating recirculation pump is in the Manual mode, and c.
GC3. 4 lD.I a.         Lets than or equal to 145*F between reactor vessel steam         I space coolant and bottom head drain line coolant, and
The speed of the operating recirculation pump is less than or equal to 75% of rated pump speed.
: b. Less than or equal to 50'F between the reactor coolant M M.lo .h                wi_tttin the loop not in operation and (the coolant in th
4.4.1.1.4 With one reactor coolant system loop not in operation with TilERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
                              .      Qeactor pressure vesset=. ano                       A
GC3. 4 lD.I a.
: c. Less than or equal to 50'F between the reactbr/ coolant within the loop not in operation andine operating loop)**
Lets than or equal to 145*F between reactor vessel steam I
space coolant and bottom head drain line coolant, and b.
M M.lo.h Less than or equal to 50'F between the reactor coolant wi_tttin the loop not in operation and (the coolant in th Qeactor pressure vesset=. ano A
c.
Less than or equal to 50'F between the reactbr/ coolant within the loop not in operation andine operating loop)**
4
4
                  --*"at u seh
--*"at u seh
                  ** Requirement does not apply when the recirculation loop not ih operation is 3.'f.la.h       isolated from the reactor pressure vessel.
** Requirement does not apply when the recirculation loop not ih operation is 3.'f.la.h isolated from the reactor pressure vessel.
~
~
FFRMI - UNIT 2                           3/4 4-2     Amendment No. 53. 59. E7. UB,133 PAGE     c1     0F     08 RW     0
FFRMI - UNIT 2 3/4 4-2 Amendment No. 53. 59. E7. UB,133 PAGE c1 0F 08 RW 0


r I
r I
RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)
RCS P/T Limits 3.4.10M SURVEILLANCE REQUIREMENTS (continued) i SURVEILLANCE FREQUENCY SR 3.4.10.3 NOTE-C'I Only requ.. ired to.be met in MODES 1, 2, 3 h
M        l i
' YO; gig) l
SURVEILLANCE                                           FREQUENCY l
.no 4,p u... -.....- a _......
C'I      SR 3.4.10.3   -          ---
l Auti (tLitcal 'on -
NOTE-         -----
,~ er,.i.,X,. '''''" ~~~~~ ~~ ~ " ~~~~~~-
Only requ.. uired
L tu y s M qa h.95)M Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes y
                                    .no 4,p         .. .to.be
: SPact, pressure vessel (RPV)fcoolant temperature prior to each is Mth
                                                          - . . met
.: li:::it: :pe:!'!ed 4' +he DTLD startup of a (iqg,y recirculation pump SR 3.4.10.4
                                                                . . .-inaMODES
---------------NOT E-------------
_ .. . . ..1, 2, 3          h        ' YO; gig)      l l  Auti (tLitcal 'on -     ,~ er ,.i.,X,. '''''" ~~~~~ ~~ ~ " ~~~~~~-
Only required to be met in MODES 1, 2, 3,
L tu y s M qa Verify the difference between the bottom                     Once within y    ,      head coolant temperature and the reactor                       15 minutes h.95)M SPact,     pressure vessel (RPV)fcoolant temperature                     prior to each is Mth         .: li:::it: :pe:!'!ed     4'
[3.4l#, AglicW/f/y) dvrG, it ppp forkup, -- -
                                                                                    +he DTLD     startup of a (iqg,y                                                 recirculation pump SR 3.4.10.4   ---------------NOT E-------------                            -
Verify the difference between the reactor
Only required to be met in MODES 1, 2, 3,                         [3.4l#, AglicW/f/y) dvrG, it                       - - - - - - - - -          ---      - - - - - - - -
: 3. 4 \\ d Once within 4.4. l. M coolant temperature in the recirculation 15 minutes loop to be started and the RPV coolant prior to each temperature 1-t (Mke 14-it: spt:i't:d-startup of a
ppp forkup, -- -                                                                                     3. 4 \ d Verify the difference between the reactor                     Once within     4.4. l . M coolant temperature in the recirculation                       15 minutes loop to be started and the RPV coolant                         prior to each temperature
-in the PTLR. yi f5oy recirculation lt5 E W B. % to - 2 SR 3.4.10
                                  -in the PTLR. yi 1-t (Mke 14-it: spt:i't:d-f5oy startup of a recirculation lt5 E W B. % to - 2                                                                   #
------------------NOTE--------------------
SR 3.4.10     ------------------NOTE--------------------                                               I Only required to be performed when tensioning the reactor vessel head bolting                              " 4 fal.'l b )
I Only required to be performed when studs.
studs.
" 4 fal.'l b )
Verify reactor vessel flange and head                         30 minutes flange temperatures are ti.hin +he 'i=i+3                                         J h
tensioning the reactor vessel head bolting Verify reactor vessel flange and head 30 minutes flange temperatures are ti.hin +he 'i=i+3 J
PTL".J> il s p When
&::i't:dinth:kc4x vedeIhead 5H dvd.s are PTL".J> il s p When
                                &::i't:dinth:kc4x vedeIhead 5H dvd.s are                                         [             j (continued)
[
BWR/4 STS                                   3.4-25                             Rev 1, 04/07/95 RW LO
h j
(continued)
BWR/4 STS 3.4-25 Rev 1, 04/07/95 RW LO


I RCS P/T Limits 3.4.10 i
I RCS P/T Limits 3.4.10 i
      ~
~
INSERT 3.4.10 _2                                       j l
INSERT 3.4.10 _2 j
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                 FREQUENCY SR 3.4.10.5' ----- ----- --- --NOTE - --- ------            ---
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.5' ----- ----- --- --NOTE - --- ------
Only required to be met during a THERMAL                   MchmA4h' POWER increase or recirculation flow increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50t rated loop flow.
Only required to be met during a THERMAL MchmA4h' POWER increase or recirculation flow increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50t 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 l
Verify the difference between the bottom Once within head coolant temperature and the RPV steam 15 minutes space coolant temperature is s 145 F.
SR 3.4.10.6     -  ------- -
prior to a THERMAL POWER increase or recirculation flow increase SR 3.4.10.6 NOTE- - - ----- --- ----
NOTE- - - ----- --- ----
Only required to be met during a THERMAL (AcTionatE) h POWER increase or recirculation flow increase in MODES 1 and 2 with one non-isolated idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow.
Only required to be met during a THERMAL POWER increase or recirculation flow                     (AcTionatE)      h increase in MODES 1 and 2 with one non-isolated idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow.
l 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.
l Verify the difference between the reactor             Once within coolant temperature in the idle                       15 minutes             ;
THERMAL POWER increase or recirculation flow increase FERMI - UNIT 2 Page 3.4-25 (INSERT)
recirculation loop and the RPV coolant               prior to a             !
. REVISION 10, 07/09/99l 1
temperature is s 50*F.                               THERMAL POWER increase or recirculation flow increase FERMI - UNIT 2                   Page 3.4-25 (INSERT)           . REVISION 10, 07/09/99l 1


i-RCS P/T Limits B 3.4.10 BASES SURVEILLANCE         SR 3.4.10.2 REQUIREMENTS (continued)         A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.
i-RCS P/T Limits B 3.4.10 BASES SURVEILLANCE SR 3.4.10.2 REQUIREMENTS (continued)
Perfoming the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be                     {
A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.
1 exceeded between the time of the Surveillance and the time
Perfoming the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality
                                                                                                                        )
{
provides adequate assurance that the limits will not be 1
exceeded between the time of the Surveillance and the time
)
of the control rod withdrawal.
of the control rod withdrawal.
h             sa 3.4.10.3 w .sR 3.4.10.4 .J R 7,'/,/0 f' a d 5 # I''//0 #
h sa 3.4.10.3 w.sR 3.4.10.4.J R 7,'/,/0 f' a d 5 # I''//0 #
C_ __-                    -
C_ __-
Differential temperatures within the applicable MtR-limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allow             Ir. Pities., :----Hr.:: it;. ihe>= iisiis h.ensur;ances.; thet the-asst.ri, tie... 'vi the anai I,uer                     :f c.1;i. .. ....i.i;... i.. , g.r. ;; .ysis ..for-;at4sf4ed tne star 6 p 6 M' D dJ                hf:=t:; th Ern!!P :: MtN5:astnutus=before                                   k
Differential temperatures within the applicable MtR-limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allow Ir. Pities., :----Hr.::
it;. ihe>= iisiis h.ensur;ances.; thet the-asst.ri, tie... 'vi the anai I,uer
:f c.1;i.......i.i;... i.., g.r. ;;.ysis for tne star 6 p
.. -;at4sf4ed 6 M' D d hf:=t:; th Ern!!P :: MtN5:astnutus=before k
{
{
steriiny i;       14h n:*-reh* %;=pid== =4===te
J steriiny i; 14h n:*-reh* %;=pid== =4===te
                                          'Isaurqc,eIna         sne gimiin will . ^ ,. . . z f:f,;:' ::- the
'Isaurqc,eIna sne gimiin will. ^,... z f:f,;:' ::- the
                                                                      =_; .. Ine-tn:c n- = ...._,-
=_;.. Ine-tn:c n- =...._,-
GR 3{/_Op An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 s to compare the temperatures of the operating recirculation loop
GR 3{/_Op An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 s to compare the temperatures of the operating recirculation loop
                                      -- and.the idle loop.
-- and.the idle loop.
* QRs hove.  -SR 3.(;3' . 3. b: been modified by Nohatrequire Surveillance to be performed on1 in ~ 2, 2, 3 f:-f           the?
QRs hove. (;3 b: been modified by Nohatrequire in ~
* DE S T
2, 2, 3 f the
                    .Tnsed wi%-ceostere==             d- awee   e4 ~, p;i . In overali stress on limiting components is Iower. MODE           5, the Therefore, h   f8 3 4.tD-V . _
-SR 3. '. 3.
                                          # """"'" "'I"'"I"d" SR 3.4.10           SR 3.4.10     and SR 3.4.10 h Limits on the reactor vessel flange and head flange temperatures are generally bounded by the other P/T limits (continued)         {
Surveillance to be performed on1
BWR/4-STS-                                   B 3.4-53.                   Rev.4-04107/95---       i 6
:-f ?
* DE S wi%-ceostere== d-awee e4 ~, p;i. In T
overali stress on limiting components is Iower. MODE 5, the
.Tnsed Therefore, h
f8 3 4.tD-V.
# """"'" "'I"'"I"d" 3.4.10 h SR 3.4.10 SR 3.4.10 and SR Limits on the reactor vessel flange and head flange temperatures are generally bounded by the other P/T limits (continued)
{
BWR/4-STS-B 3.4-53.
Rev.4-04107/95---
i 6
Ren0
Ren0


RCS P/T Limit B 3.4.10 Insert' B 3.4.10 - 3 Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30%     k RTP or operating loop flow s 50% of rated loop flow, ensure that resulting thermal stresses will not exceed design allowances.
RCS P/T Limit B 3.4.10 Insert' B 3.4.10 - 3 Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30%
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase
k RTP or operating loop flow s 50% of rated loop flow, ensure that resulting thermal stresses will not exceed design allowances.
;                          during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start. power increase, or flow increase.
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start. power increase, or flow increase.
Insert B 3.4.10 - 4
Insert B 3.4.10 - 4
                          ... for SRs 3.4.10.3 and 3.4.10.4 in MODE 5.     In MODES 3, 4 and 5. THERMAL POWER increases are not possible, and recirculation flow increases will not result in additional stresses. Therefore AT limits are only required for SRs 3.4.10.5 and 3.4.10.6 in MODES 1 and 2.     The Notes also state that the SR is only required to be met during the event of concern (e.g. pump startup, power increase or flow increase) since this is when the stresses occur.
... for SRs 3.4.10.3 and 3.4.10.4 in MODE 5.
l l
In MODES 3, 4 and 5. THERMAL POWER increases are not possible, and recirculation flow increases will not result in additional stresses. Therefore AT limits are only required for SRs 3.4.10.5 and 3.4.10.6 in MODES 1 and 2.
l s
The Notes also state that the SR is only required to be met during the event of concern (e.g. pump startup, power increase or flow increase) since this is when the stresses occur.
FERMI - UNIT 2         Page B 3.4 53 (INSERT)             REVISION 10. 07/09/99l
s FERMI - UNIT 2 Page B 3.4 53 (INSERT)
REVISION 10. 07/09/99l


l l
l l
JUSTIFICATION FOR DIFFERENCES FROM NUREG     1433 ITS: SECTION 3.4.10 - RCS P/T LIMITS
JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.4.10 - RCS P/T LIMITS
      \
\\
NON BRACKETED PLANT SPECIFIC CH/NGES P.1-       These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and comitments. Additional rewording. reformatting.
NON BRACKETED PLANT SPECIFIC CH/NGES P.1-These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and comitments. Additional rewording. reformatting.
and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented.                                                   l P.2       Bases changes are made to reflect plant specific design details, equipment terminology, and analyses.
and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented.
P.3       Not used.
l P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses.
P.4       NUREG 1433 Bases do not include discussion of NUREG-1433 3.4.10 Action C Note. Appropriate Bases are included for completeness.
P.3 Not used.
P.5       The reference to the NRC Policy Statement has been replaced with a
P.4 NUREG 1433 Bases do not include discussion of NUREG-1433 3.4.10 Action C Note. Appropriate Bases are included for completeness.
        ,                more appropriate reference to the Improved Technical Specification
P.5 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).
" split" criteria found in 10 CFR 50.36(c)(2)(ii).
P.6       ITS SRs 3.4.10.5 and 3.4.10.6 are added to reflect the specific coolant temperature limits applicable to thermal power and flow increases while in single loop operation. These limits were located in the CTS Specification for recirculation loops operating but are more appropriately located in the Specification for Pressure and Temperature limits. This location for these SRs results in applying the appropriate Actions. This is also the subject of a pending generic change to NUREG-1433.
P.6 ITS SRs 3.4.10.5 and 3.4.10.6 are added to reflect the specific coolant temperature limits applicable to thermal power and flow increases while in single loop operation. These limits were located in the CTS Specification for recirculation loops operating but are more appropriately located in the Specification for Pressure and Temperature limits. This location for these SRs results in applying the appropriate Actions. This is also the subject of a pending generic change to NUREG-1433.
GENERIC CHANGIS C.1       TSTF 35: NRC approved change to NUREG 1433.
GENERIC CHANGIS C.1 TSTF 35: NRC approved change to NUREG 1433.
FERMI   UNIT 2                       1                   REVISION 10. 07/09/99l
FERMI UNIT 2 1
REVISION 10. 07/09/99l


l INSERT THIS PAGE IN FRONT OF VOLUME 11                           i Volume 11: CTS MARKUP COMPILATION -                 '
INSERT THIS PAGE IN FRONT OF VOLUME 11 i
                                                                                            )
Volume 11: CTS MARKUP COMPILATION -
Remove                                     Replace 3/44-1(3.4.1 CTS M/U) pg 2 of 6 Rev 2       3/44-1(3.4.1 CTS hW) pg 2 of 6 Rev 10       j 3/44-2(3.4.1 CTS hW) pg 3 of 6 Rev 4       3/4 4-2 (3.4.1 CTS hW) pg 3 of 6 Rev 10 3/4 4-2 (3.4.10 CTS M/U) pg 2 of 8         3/4 4-2 (3.4.10 CTS hW) pg 2 of 8 Rev 10 3/4 4-11 (3.4.4 CTS hW) pg 2 of 2           3/4 4-11 (3.4.4 CTS M/U) pg 2 of 2 Rev 10 I
)
Remove Replace 3/44-1(3.4.1 CTS M/U) pg 2 of 6 Rev 2 3/44-1(3.4.1 CTS hW) pg 2 of 6 Rev 10 j
3/44-2(3.4.1 CTS hW) pg 3 of 6 Rev 4 3/4 4-2 (3.4.1 CTS hW) pg 3 of 6 Rev 10 3/4 4-2 (3.4.10 CTS M/U) pg 2 of 8 3/4 4-2 (3.4.10 CTS hW) pg 2 of 8 Rev 10 3/4 4-11 (3.4.4 CTS hW) pg 2 of 2 3/4 4-11 (3.4.4 CTS M/U) pg 2 of 2 Rev 10 I
1 i
1 i
Res10 07/09/99
Res10 07/09/99


S PEco r <eihJ M .!
S PEco r <eihJ M.!
3 /4. 4 REACTOR COOLANT SY' STEM
3 /4. 4 REACTOR COOLANT SY' STEM
    'g             3/4.4.1       RECIRCULATION SYSTEM 1           RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION Leo 39j       ?.'.     .:- Two reactor coolant system recirculation loops shall be in operation.
'g 3/4.4.1 RECIRCULATION SYSTEM 1
RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION Leo 39j
?.'..:- Two reactor coolant system recirculation loops shall be in operation.
APPLICABILfTY: OPERATIONAL CONDITIONS 1 and 2*.
APPLICABILfTY: OPERATIONAL CONDITIONS 1 and 2*.
ACTION:
ACTION:
: a.      With one reactor coolant system recirculation loop not in operation:
With one reactor coolant system recirculation loop not in operation:
LCo M. l -       1. Within 4 hours:                                                 LAil tJOTT             r.---.                                                                               s r)a    Pla     the individual re     culation   pump moflow
a.
_      o   atino ret.f rculatio pump   in the Manual     L cof roller' for ythe ] g y g'q,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27. of RATED                               $
LCo M. l -
THERMAL POWER.
1.
j ,j
Within 4 hours:
                                    ) Limit the speed [f the operating recircydation pump to lesp/t han) or eaual to 7 5 of rated pump speed e i
LAil tJOTT r.---.
d) Inc ase Ine Minin           CRITICAL PDWLK Mali (ril,rK) baTeIy L1 L1 th value for sing       loop operation reg red by Specifica on
s r) Pla the individual re culation pump flow cof roller' for the ] g a
                                          .l.2. s y
o atino ret.f rculatio pump in the Manual mo L y
e) Change the Average Power Range Monitor (APRM) Simulated Thermal ,               '
y g'q,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27. of RATED THERMAL POWER.
j,j
) Limit the speed [f the operating recircydation pump to lesp/ han) t or eaual to 7 5 of rated pump speed e i
d) Inc ase Ine Minin CRITICAL PDWLK Mali (ril,rK) baTeIy L1 L1 th value for sing loop operation reg red by Specifica on
.l.2. s y
e) Change the Average Power Range Monitor (APRM) Simulated Thermal,
O N'O'!
Power - Upscale Flow Biased Scram F.r4 M "M; Mr irire'-ts?
Power - Upscale Flow Biased Scram F.r4 M "M; Mr irire'-ts?
O N'O'!                WA110wable Values to those applicable for single recirculation       ~       !
WA110wable Values to those applicable for single recirculation
~
loop operation per Specifications 2.2.1 and 3.3.6.
loop operation per Specifications 2.2.1 and 3.3.6.
l f)     Perform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is ggg fah                     less than or equal to 307. of RATED THERMAL POWER or the g,4 ,,,                 recirculation loop flow in the operating loop is less than or equal to 507. of rated loop flow.
l f)
                          -2. Ot h: .:' --   ha 4-it 1::: "0T ;;;;;;;' . n m nin ine u m ;; ;,_ ,..
Perform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is ggg fah less than or equal to 307. of RATED THERMAL POWER or the g,4,,,
: b.       With no reactor coolant system recirculation loop in operation while in MdD             OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.
recirculation loop flow in the operating loop is less than or equal to 507. of rated loop flow.
: c.        With no reactor coolant system recirculation loops in operation, while in h CTlDb) C,        OPERATIONAL CONDITION 2, initiate measures to place the unit in at least HOT SHUTDOWN within the next 6 hours.                       ,
-2.
See       etialTe3(Exception 3.f0.4.]
Ot h:.:' --
ha 4-it 1::: "0T ;;;;;;;' n m nin ine u m ;; ;,_,..
b.
With no reactor coolant system recirculation loop in operation while in MdD OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.
With no reactor coolant system recirculation loops in operation, while in c.
OPERATIONAL CONDITION 2, initiate measures to place the unit in at least h CTlDb) C, HOT SHUTDOWN within the next 6 hours.
See etialTe3(Exception 3.f0.4.]
I e
I e
FERMI - UNIT 2                                   3/4 4 1   Amendment No. JJ,64,EJ,EJ, EJ,Jpp, 122 PAGE       2. OF     06 Raulo i
FERMI - UNIT 2 3/4 4 1 Amendment No. JJ,64,EJ,EJ, EJ,Jpp, 122 PAGE 2.
OF 06 Raulo i


e i
e i
SPEt tFwAng4 3.% I (Aisw sat paciRutre 3 4o)
SPEt tFwAng4 3.% I (Aisw sat paciRutre 3 4o)
(Aho sat spcil;ukm s E t )
(Aho sat spcil;ukm s E t )
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS S ee. T4.1.1;I         Each pump discharge valve shall be demonstrated OPGRABLE by
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS S ee.
      @w 3,g, ,
T4.1.1;I Each pump discharge valve shall be demonstrated OPGRABLE by
icycling each valve through at least one complete cycle of full travel at least once per 18 aienths.
@w icycling each valve through at least one complete cycle of full travel at least 3,g,,
                                                                                                / 4,1
once per 18 aienths.
                              . .;.2   eus s w
.;.2 eus s w
                            .=.A.1.3   With       reactor coolant s tem recm.u mien eration,'at I st once per 12 hou         erify that:         ivobnotin THERMAL POWER i     ess than or equal to 6 .2% of RATED THERMAL POWER, nd
/ 4,1
: b.     The individu     recirculatioa pump f1     controller for operating     irculation pump is in     e Manual mode, a
.=.A.1.3 With reactor coolant s tem recm.u mien eration,'at I st once per 12 hou erify that:
: c.     The speed f the operating recircu tion pump is le or eoual o 75% of rated aa-a une         -                tha#nl r
ivobnotin THERMAL POWER i ess than or equal to 6.2% of RATED THERMAL POWER, nd b.
j 4.4.1.1.4     With one reactor coolant system loop not in operatjon with THERMAL POWER less than or equal to 305 of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 505 of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
The individu recirculatioa pump f1 controller for operating irculation pump is in e Manual mode, a c.
      --                                a.
The speed f the operating recircu tion pump is le tha#nl or eoual o 75% of rated aa-a une r
M                            Less than or equal to 145'F between reactor vessel steam         4 space coolant and bottom head drain line coolant, and             i ged{gh                   b.     Less than or equal to 50'F between the reactor coolant within the loop not in operation and the coolant in the 3Ya                            reactor pressure vessei+*. and
j 4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL POWER less than or equal to 305 of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 505 of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:
: c.     Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the cperating loop.**
a.
Less than or equal to 145'F between reactor vessel steam M
4 space coolant and bottom head drain line coolant, and i
ged{gh b.
Less than or equal to 50'F between the reactor coolant 3Ya within the loop not in operation and the coolant in the reactor pressure vessei+*. and c.
Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the cperating loop.**
l l
l l
l N*y.                                                                                           j T .u. -       **Reautrement does not apply when the~ recirculation loop not ih operation is
N*y.
        $ip.4 Gu.he-         isolated from the reactor pressure vessel.
j T.u. -
i 3 M .t6 FERMI - UNIT 2                           3/4 4-2       Amendment No. 'U. $9. 57. UB.133 l
**Reautrement does not apply when the~ recirculation loop not ih operation is
PE 3           _OF     06                   Redl0
$ip.4 Gu.he-isolated from the reactor pressure vessel.
3 M.t6 i
FERMI - UNIT 2 3/4 4-2 Amendment No. 'U. $9. 57. UB.133 l
PE 3
_OF 06 Redl0


S fEttPtewnw 3.4.10             \
S EttPtewnw 3.4.10
(Also see S)ecTGcafim 54.1)               )
\\
REACTOR COOLANT SYSTEM
f (Also see S)ecTGcafim 54.1)
[A u s % .9 eci A ca1 % 8 E l)
)
SURVETLtANCE REOUTREMENTS
[A u s %.9 eci A ca1 % 8 E l)
* 4.4.1.1.1       Each pump discharge valve shall be demonstrated OPGRABLE by Sl dab       cycling each valve through at least one complete cycle of full travel at least 351       once per 18 months.                                     '
REACTOR COOLANT SYSTEM SURVETLtANCE REOUTREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OPGRABLE by Sl dab cycling each valve through at least one complete cycle of full travel at least 351 once per 18 months.
i.4.1.1.2         DELETED
i.4.1.1.2 DELETED
          '4.4.1.1.3         With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that:                   '
'4.4.1.1.3 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that:
g                      a. THERMAL POWER is less than or equal to 67.2% of RATED THERMAL POWER, and
THERMAL POWER is less than or equal to 67.2% of RATED g
  % ciffa2h %                b. The individual recirculation pump flow controller for the 3.Y.I                     - operating recirculation pump is in the Manual mode, and
a.
: c. The speed of the operating recirculation pump is less than or equal to 75% of rated pump speed.
% ciffa2h %
4.4.1.1.4       With one reactor coolant system loop not in operation with THERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no           j more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase:                                                                         i i
THERMAL POWER, and b.
6A3. 4.lD8 a.             Less than or equal to 145'F between reactor vessel steam
The individual recirculation pump flow controller for the 3.Y.I
                            ,        space coolant and bottom head drain line coolant, and
- operating recirculation pump is in the Manual mode, and The speed of the operating recirculation pump is less than c.
: b. Less than or equal to 50*F between the reactor coolant M 3.4.10 4                witttin the loop not in operation and(the cooiant in th Qeictor pressure vesset", ano                     N
or equal to 75% of rated pump speed.
: c. Less than or equal to 50*F between the reactbr/ coolant         l within the loop not in operation and Gne operating loop)**
4.4.1.1.4 With one reactor coolant system loop not in operation with THERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation j
            -* NM und. -
flow increase:
            **Recuirement does not apply when the recirculaticn loop not ih operation is 3/f.i0.@       isolated from the reactor pressure vessel.
i i
FERMI - UNIT 2                             3/4 4-2     Amendment No. 53. 49. E7 UB.133 PAGE     c1     0F     08 REY 0
6A3. 4.lD8 a.
Less than or equal to 145'F between reactor vessel steam space coolant and bottom head drain line coolant, and
, b.
M 3.4.10 4 Less than or equal to 50*F between the reactor coolant witttin the loop not in operation and(the cooiant in th Qeictor pressure vesset", ano N
c.
Less than or equal to 50*F between the reactbr/ coolant within the loop not in operation and Gne operating loop)**
- NM und. -
**Recuirement does not apply when the recirculaticn loop not ih operation is 3/f.i0.@
isolated from the reactor pressure vessel.
FERMI - UNIT 2 3/4 4-2 Amendment No. 53. 49. E7 UB.133 PAGE c1 0F 08 REY 0


          -e i-OC/     C4   /d/L     -  -
-e i-OC/
3 i
C4
REACTOR COOLANT SYSTEN LIMITING CONDITION FOR OPERATION (Continued)
/d/L 3
i REACTOR COOLANT SYSTEN LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued)
ACTION: (Continued)
: e.      In OPERATIONAL CONDITION I, with any reactor coolant system                           I h[ oft 8               UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24 hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenttic stainless steel within a haneiror be in at least HOT SHUTDOWN within the next 12 Jc6'on C               hours and in COLD SHUTDOWN within the following 24 hours.
In OPERATIONAL CONDITION I, with any reactor coolant system I
: f.     In OPE                             2 and         ith any       ctor coo nt system %       [. , 2 UNID p        ,
e.
FIED L ident LCONDJ%ncrease
h[ oft 8 UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24 hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenttic stainless steel within a haneiror be in at least HOT SHUTDOWN within the next 12 Jc6'on C hours and in COLD SHUTDOWN within the following 24 hours.
                                                                  .i               ater tha       gpa wit     any 4 ur '
f.
3 I
In OPE LCONDJ%ncrease 2 and ith any ctor coo nt system %
he sour     f leakage         rease     at serv nsitive           304 or       austeniti         ainles     eel wi     4 hours             in at -       t HOT SHUT         withi     e next in           SHUTDOW       thin the fo       wing 24 ours y              hoursand})
[., 2 UNID FIED L
SURVEILLANCE RE001REMENTS N             '''*'
.i ater tha gpa wit any 4 ur 3
The reactor coolant system leakage shall be demonstrated to be 3 A.M        within each of the above limits by:                                                                                     !
p
o
, ident he sour f leakage rease at serv nsitive 304 or austeniti ainles eel wi hoursand})
                                      &                e ne d en W -+ " ~ V vit[6tleastonceperenoursp                        Mu                  LA./
4 hours in at -
bfoMtbrinn,tne ortmary coritetsmaat1umph r
t HOT SHUT withi e next in SHUTDOW thin the fo wing 24 oursy SURVEILLANCE RE001REMENTS N
hours in vrr.MilDML LUNUlilDN Mnd at least once per 4 hour     in OPERATIONAL CONDITIONS 2 and 3 l          i di i 3             -
3 A.M The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:
                                                                                                                                        .T   !
e ne d en W -+ " ~ V M u LA./
                      / [cJier(inrinfthodrfGe' Mardingpgel # ' d                                                                       i
o vit[6tleastonceperenoursp bfoMtbrinn,tne ortmary coritetsmaat1umph hours in vrr.MilDML LUNUlilDN Mnd at least once per 4 l
                                                                                                                                        '    =
i di i
hoursitrin ours in OPERATIONALDPERA"IONAL CONDITIONS    CONDITION 2 and 3, and    Mand at least once per [ *'),4 }
r hour in OPERATIONAL CONDITIONS 2 and 3 3
n
.T
                                                                                  %096aMWs}safyt                 ,
=
LA. I LA.I Cs..a.r-< M & s.g.
/
                            = , _ , - -    , - -
[cJier(inrinfthodrfGe'Mardingpgel # ' d hoursitrin DPERA"IONAL CONDITION Mand at least once per 4 }
n,                         ,        ,,,m     m  m y       L,/             s
[ *'),
                      -s M" = -         --mo rr=r r       in " - --            -
i ours in OPERATIONAL CONDITIONS 2 and 3, and n
                                                                                      =   4.               I A
%096aMWs}safyt LA. I LA.I Cs..a.r-< M & s
=, _, - -
s n,
.g.
,,,m m
y L,/
A
-s M" = -
--mo rr=r r m
in " - --
=
4.
I
(
(
FERMI - UNIT 2                                 3/4 4-II                         Amendment No. 89 PAGE         c2       0F           O'2                   #dl0
FERMI - UNIT 2 3/4 4-II Amendment No. 89 PAGE c2 0F O'2
#dl0


l l
l l
l INSERT THIS PAGE IN FRONT OF VOLUME 12 Volume 12: IMPROVED TECHNICAL SPECIFICATIONS .                     ;
l INSERT THIS PAGE IN FRONT OF VOLUME 12 Volume 12: IMPROVED TECHNICAL SPECIFICATIONS.
I Remove                                       Replace         l 3.4.1 ITS pg 3.4-1 Rev 4                     3.4.1 ITS pg 3.4-1 Rev 10 3.4.4 ITS pg 3.4-8 Rev 0                     3.4.4 ITS pg 3.4-8 Rev 10 3.4.4 ITS pg 3.4-9 Rev 0                     3.4.4 ITS pg 3.4-9 Rev 10 3.4.6 ITS pg 3.4-13 Rev 4                     3.4.6 ITS pg 3.4-13 Rev 10             l 3.4.10 ITS pg 3.4-26 Rev 0                   3.4.10 ITS pg 3.4-26 Rev 10 1
Remove Replace l
Rev10 07/09/99
3.4.1 ITS pg 3.4-1 Rev 4 3.4.1 ITS pg 3.4-1 Rev 10 3.4.4 ITS pg 3.4-8 Rev 0 3.4.4 ITS pg 3.4-8 Rev 10 3.4.4 ITS pg 3.4-9 Rev 0 3.4.4 ITS pg 3.4-9 Rev 10 3.4.6 ITS pg 3.4-13 Rev 4 3.4.6 ITS pg 3.4-13 Rev 10 3.4.10 ITS pg 3.4-26 Rev 0 3.4.10 ITS pg 3.4-26 Rev 10 Rev10 07/09/99


g                                                                                                       q L                             .            w, Recirculation Loops Operating 3.4.1 l
g q
    )         3.4 REACTOR, COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating                                                       d i
L w,
h      LCO 3.4.1         The reactor core shall not exhibit core thermal-hydraulic instability or operate in the " Scram" or " Exit" Regions.
Recirculation Loops Operating 3.4.1 l
      ^l 4
)
8ND
3.4 REACTOR, COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating d
      >                          a. Two recirculation loops with matched recirculation loop W                               jet pump flows shall be in operation:
i h
LCO 3.4.1 The reactor core shall not exhibit core thermal-hydraulic instability or operate in the " Scram" or " Exit" Regions.
^l 8ND 4
a.
Two recirculation loops with matched recirculation loop W
jet pump flows shall be in operation:
k a
k a
: b. One recirculation loop may be in operation provided:
b.
: 1. LC0 3.3.1.1. " Reactor Protection System (RPS)
One recirculation loop may be in operation provided:
Instrumentation," Function 2.b (Average Power Range Vl                                   Monitors Simulated Thermal Power-Upscale) Allnwable Value of Table 3.3.1.11 is reset for single loop e                                    operation, when in MODE 1: and k                               2. THERMAL POWER is s 67.2% RTP.
1.
LC0 3.3.1.1. " Reactor Protection System (RPS)
Instrumentation," Function 2.b (Average Power Range Vl Monitors Simulated Thermal Power-Upscale) Allnwable Value of Table 3.3.1.11 is reset for single loop operation, when in MODE 1: and e
k 2.
THERMAL POWER is s 67.2% RTP.
i
i
    %                            ............................N0TE   - --    - --- --    --    --- -
............................N0TE Required allowable value modification for single loop r
r                        Required allowable value modification for single loop Ml                       operation and THERMAL POWER limitation may be delayed for up L                         to 4 hours after transition from two recirculation loop operations to single recirculation loop operation.
Ml operation and THERMAL POWER limitation may be delayed for up L
APPLICABILITY:     MODES 1 and 2.
to 4 hours after transition from two recirculation loop operations to single recirculation loop operation.
ACTIONS CONDITION                     REQUIRED ACTION             COMPLETION TIME A. Recirculation jet pump     A.1     Declare recirculation     2 hours loo) flow mismatch not               loop with lower flow:                           (
APPLICABILITY:
wit 11n limits.                     "not in operation."
MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Recirculation jet pump A.1 Declare recirculation 2 hours loo) flow mismatch not loop with lower flow:
wit 11n limits.
"not in operation."
(contint.ed)
(contint.ed)
        -l FERMI     UNIT 2                           3.4 1               Revision 10     07/09/99 l
-l FERMI UNIT 2 3.4 1 Revision 10 07/09/99 t
t


                                                              ~
c
c
~
[
[
l RCS Operational LEAKAGE 3.4.4
l 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:
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:
: b. s 5 gpm unidentified LEAKAGE:
a.
: c. s 25 gpm total LEAKAGE averaged over the previous 24 hour period: and
No pressure boundary LEAKAGE:
                                      - d. 5 2 gpm increase in unidentified LEAKAGE within the previous 24 hour period in MODE 1.
b.
APPLICABILITY:       MODES 1, 2, and 3.
s 5 gpm unidentified LEAKAGE:
ACTIONS CONDITION                   REQUIRED ACTION         COMPLETION TIME A. Unidentified LEAKAGE         A.1       Reduce LEAKAGE to     4 hours not within limit.                     within limits.
c.
s 25 gpm total LEAKAGE averaged over the previous 24 hour period: and
- d.
5 2 gpm increase in unidentified LEAKAGE within the previous 24 hour 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 hours not within limit.
within limits.
Total LEAKAGE not within limit.
Total LEAKAGE not within limit.
h       B. Unidentified LEAKAGE         B.1       Reduce LEAKAGE to     4 hours increase not within t                                                  within limits.                             !
h B.
                      ' i mi t-,
Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours t
increase not within within limits.
' i mi t-,
d M
d M
(continued)   ;
(continued) l FERMI UNIT 2 3.4 8 Revision 10, 07/09/99
l FERMI       UNIT 2                         3.4 8               Revision 10, 07/09/99


.=
.=
n-RCS Operational LEAKAGE 3.4.4
n -
  ')           ACTIONS (continued)
RCS Operational LEAKAGE 3.4.4
CONDITION                   REQUIRED ACTION           COMPLETION TIME b3 B. (continued)               B.2     Verify source of.       4 hours
')
        ~
ACTIONS (continued)
unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.
CONDITION REQUIRED ACTION COMPLETION TIME b3 B.
C. Required Action and       C.1     Be in MODE 3.           12 hours associated Completion Time of Condition A       ANQ                                                 .
(continued)
or B not met.
B.2 Verify source of.
C.2     Be in MODE 4.           36 hours             .
4 hours unidentified LEAKAGE
l DB Pressure boundary LEAKAGE exists.
~
increase is not service sensitive type 304 or type 316 austenitic stainless steel.
C.
Required Action and C.1 Be in MODE 3.
12 hours associated Completion Time of Condition A ANQ or B not met.
C.2 Be in MODE 4.
36 hours DB l
Pressure boundary LEAKAGE exists.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE REQUIREMENTS
                                                                                                =
=
SURVEILLANCE                               FREQUENCY l
SURVEILLANCE FREQUENCY jfl SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 8 hours and unidentified LEAXAGE increase are within limits.
jfl   SR 3.4.4.1     Verify RCS unidentified and total LEAKAGE       8 hours and unidentified LEAXAGE increase are within limits.                                                     ;
1 I
i I
i I
l FERMI - UNIT 2                         3.4 9               Revision 10   07/09/99
l FERMI - UNIT 2 3.4 9 Revision 10 07/09/99


F                                                                                                                     )
F
I RCS Leakage Detection Instrumentation t
)
3.4.6 j
I RCS Leakage Detection Instrumentation 3.4.6 t
      ]               -3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 'RCS Leakage Detection Instrumentation
j
      /'
]
1 LCO.3.4.6           The following RCS leakage detection instrumentation shall be           '
-3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 'RCS Leakage Detection Instrumentation
OPERABLE:
/'
: a. Drywell floor drain sump flow monitoring system:
1 LCO.3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE:
                                            ~
a.
Ld                           b.
Drywell floor drain sump flow monitoring system:
8                              The!oringsystemchannel:rimary moni                        and  containment atmos here gaseous ra
Ld b.
: c. Drywell floor drain sump level monitoring system.
~
APPLICABILITY:       MODES 1. 2. and 3.                                                       i
The!oringsystemchannel:rimary containment atmos here gaseous ra 8
                    ' ACTIONS-
moni and c.
                      ..................................N0TE       -- -- --  ---    - -- - ---------          --
Drywell floor drain sump level monitoring system.
LC0 3.0.4 is not applicable.
APPLICABILITY:
      ~
MODES 1. 2. and 3.
4 CONDITION                     REQUIRED ACTION               COMPLETION TIME
i
                      - A. ;Drywell floor drain       A.1     Restore drywell floor       30 days sump flow monitoring               drain sump flow
' ACTIONS-
                            . system inoperable.                 monitoring system to OPERABLE status.
..................................N0TE LC0 3.0.4 is not applicable.
B. Required primary           B.1     Analyze grab samples       Once per containment atmosphere             of primary                 24 hours gaseous radioactivity-             containment monitoring. system                 atmosphere.
~
4 CONDITION REQUIRED ACTION COMPLETION TIME
- 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 containment atmosphere of primary 24 hours gaseous radioactivity-containment monitoring. system atmosphere.
inoperable.
inoperable.
(continued)
(continued)
    .                                                                                                                  l
,/
  ,/                                                                                                                   I
I
                - l' FERMI -' UNIT 2                           3.4 13.             Revision 10. 07/09/99
- l' FERMI -' UNIT 2 3.4 13.
Revision 10. 07/09/99


RCS P/T Limits 3.4.10
RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)
        ;-        SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
SURVEILLANCE                                   FREQUENCY
.SR 3.4.10.5
                  .SR 3.4.10.5   ----.....--- --          ---NOTE------ ------ -- -
---NOTE------
Only required to be met during a THERMAL POWER increase or recirculation flow
Only required to be met during a THERMAL POWER increase or recirculation flow
            /f                   increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is Q                       s 50% rated loop flow.
/f increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is Q
1l                                                                                   Once within Verify the difference between the bottom                     15 minutes l               head coolant temperature and the RPV steam                   prior to a space coolant temperature is s 145'F.                       THERMAL POWER l                                                                             increase or recirculation l                                                                             flow increase SR 3.4.10.6   -- -...--
s 50% rated loop flow.
                                                    ---. -- NOTE----        -----..---
1l Once within Verify the difference between the bottom 15 minutes l
head coolant temperature and the RPV steam prior to a space coolant temperature is s 145'F.
THERMAL POWER l
increase or recirculation l
flow increase SR 3.4.10.6
---. -- NOTE----
Only required to t,e 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.
Only required to t,e 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.
                                ...........................................                  Once within 15 minutes l               Verify the difference between the reactor                   prior to a coolant temperature in the iole                             THERMAL POWER
Once within 15 minutes l
            /                   recirculation loop and the RPV coolant                       increase or 3f                     temperature is s 50*F.                                       recirculation I                                                                             flow increase (continued) l FERMI - UNIT 2                                 3.4 26                 Revision 10. 07/09/99
Verify the difference between the reactor prior to a coolant temperature in the iole THERMAL POWER
/
recirculation loop and the RPV coolant increase or 3f temperature is s 50*F.
recirculation I
flow increase (continued) l FERMI - UNIT 2 3.4 26 Revision 10. 07/09/99


    ,,e INSERT THIS PAGE IN FRONT OF VOLUME 13 Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES .
,,e INSERT THIS PAGE IN FRONT OF VOLUME 13 Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES.
Remove                                       Replace B 3.4.1 ITS pg B 3.4.1-4 Rev 2               B 3.4.1 ITS pg B 3.4.1-4 Rev 10 B 3.4.3 ITS pg B 3.4.3-2 Rev 0               B 3.4.3 ITS pg B 3.4.3-2 Rev 10 B 3.4.4 ITS pg B 3.4.4-4 Rev 0               B 3.4.4 ITS pg B 3.4.4-4 Rev 10 B 3.4.4 ITS pg B 3.4.4-5 Rev 0               B 3.4.4 ITS pg B 3.4.4 5 Rev 10 B 3.4.10 ITS pg B 3.4.10-7 Rev 0             B 3.4.10 ITS pg B 3.4.10-7 Rev 10 l
Remove Replace B 3.4.1 ITS pg B 3.4.1-4 Rev 2 B 3.4.1 ITS pg B 3.4.1-4 Rev 10 B 3.4.3 ITS pg B 3.4.3-2 Rev 0 B 3.4.3 ITS pg B 3.4.3-2 Rev 10 B 3.4.4 ITS pg B 3.4.4-4 Rev 0 B 3.4.4 ITS pg B 3.4.4-4 Rev 10 B 3.4.4 ITS pg B 3.4.4-5 Rev 0 B 3.4.4 ITS pg B 3.4.4 5 Rev 10 B 3.4.10 ITS pg B 3.4.10-7 Rev 0 B 3.4.10 ITS pg B 3.4.10-7 Rev 10 l
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ir<       .
ir<
Recirculation Loops Operating B 3.4.1
Recirculation Loops Operating B 3.4.1
      ') .       BASES APPLICABLE SAFETY ANALYSES (continued)-
').
BASES APPLICABLE SAFETY ANALYSES (continued)-
Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference'4 are satisfied.
Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference'4 are satisfied.
Recirculation loops operating satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).
Recirculation loops operating satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).
LC0             .Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of m;                    the piping of one recirculation loop the assumptions of the i                       LOCA analysis are satisfied. With the limits specified in kJ                    SR 3.4.1.2 not met, the recirculation loop with the lower flow must be considered not in o             With only one
LC0
          .%                      recirculation loop in operation,peration.
.Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the m;
modifications to the APRM     l 5                     Simulated Thermal. Power-Upscale setpoint (LC0 3.3.1.1) and N
i LOCA analysis are satisfied. With the limits specified in k
6                        a limitation on THERMAL POWER may be applied to allow continued operation consistent with the assumptions of the safety analysis.
SR 3.4.1.2 not met, the recirculation loop with the lower J
l r                      Operations that exhibit core thermal hydraulic instability are not permitted. Additionally, in order to avoid G                       potential power oscillations due to thermal hydraulic instability operation at certain combinations of power and 3
flow must be considered not in o With only one recirculation loop in operation,peration.
cc
modifications to the APRM 5
                                  - flow are not permitted. These restricted power and flow regions are referred to as the " Scram" and " Exit" regions y'                         and are defined by Bases Figure B 3.4.1-1.
Simulated Thermal. Power-Upscale setpoint (LC0 3.3.1.1) and 6
A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to 4                      establish the APRM Simulated Thermal Power - Upscale 1l-                    setpoint in accordance with the single loop allowable value.
a limitation on THERMAL POWER may be applied to allow N
A                       which is specified in Table 3.3.1.1-l' and to establish T                       operation at s 67 2% RTP. The 4 hour period is sufficient
continued operation consistent with the assumptions of the safety analysis.
        "                        .to make the sdjustments given the relatively small change-required. - This transition'that results in applying the new b                       single loop allowable values to APRM OPERABILITY. is such l
Operations that exhibit core thermal hydraulic instability r
1g                         that any ARPM non compliance with the required allowable
are not permitted. Additionally, in order to avoid G
            >l                     value after this 4 hour allowance results in ACTIONS of 4                     LCO 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would apply.                                                           j
potential power oscillations due to thermal hydraulic instability operation at certain combinations of power and 3
      ~
- flow are not permitted. These restricted power and flow cc regions are referred to as the " Scram" and " Exit" regions y'
1 l FERMI' L UNIT. 2                     B 3.4.1 - 4         Revision 10. 07/09/99
and are defined by Bases Figure B 3.4.1-1.
A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to 1l-establish the APRM Simulated Thermal Power - Upscale 4
setpoint in accordance with the single loop allowable value.
A which is specified in Table 3.3.1.1-l' and to establish T
operation at s 67 2% RTP. The 4 hour period is sufficient
.to make the sdjustments given the relatively small change-required. - This transition'that results in applying the new b
single loop allowable values to APRM OPERABILITY. is such 1g that any ARPM non compliance with the required allowable l
>l value after this 4 hour allowance results in ACTIONS of 4
LCO 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would apply.
j
~
l FERMI' L UNIT. 2 B 3.4.1 - 4 Revision 10. 07/09/99


i n
i n
    , e .
, e.
i SRVs B 3.4.3
i SRVs B 3.4.3 BASES APPLICABLE The overpressure protection system must accommodate the most SAFETY ANALYSES severe pressurization transient. Evaluations have determined that the most severe transient is the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in the safety mode. The analysis results demonstrate that the design SRV capacity is capable of maintaining reactor pressure below the ASME Code limit of 110% of vessel design pressure (110% x 1250 psig = 1375 psig). This LC0 helps to ensure that the acceptance limit of 1375 psig is met during the Design Basis Event.
      '. BASES APPLICABLE       The overpressure protection system must accommodate the most SAFETY ANALYSES   severe pressurization transient. Evaluations have determined that the most severe transient is the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in the safety mode. The analysis results demonstrate that the design SRV capacity is capable of maintaining reactor pressure below the ASME Code limit of 110% of vessel design pressure (110% x 1250 psig = 1375 psig). This LC0 helps to ensure that the acceptance limit of 1375 psig is met during the Design Basis Event.
From an over)ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the SRVs.
From an over)ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the SRVs.
SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
4 LC0             The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs.1 and 2). The requirements of this LC0 are applicable only to the capability of the SRVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function).
4 LC0 The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs.1 and 2). The requirements of this LC0 are applicable only to the capability of the SRVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function).
t A- l                   The SRV setpoints, and 3% allowance for setpoint drift, are v                       established to ensure that the ASME Code limit on peak             i reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based on these setpoints.
A-l The SRV setpoints, and 3% allowance for setpoint drift, are t
v established to ensure that the ASME Code limit on peak i
reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based on these setpoints.
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded.
l FERMI - UNIT 2                     B 3.4.3-2             Revision 10, 07/09/99
l FERMI - UNIT 2 B 3.4.3-2 Revision 10, 07/09/99


I RCS Operational LEAKAGE B 3.4.4 m.
I RCS Operational LEAKAGE B 3.4.4 m.
1       BASES
1 BASES
                  -APPLICABILITY         In MODES 1, 2, and 3 the RCS operational LEAKAGE LC0 a) plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized.
-APPLICABILITY In MODES 1, 2, and 3 the RCS operational LEAKAGE LC0 a) plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized.
In MODES 4 and 5. RCS operational LEAKAGE' limits are not required since the reactor is not pressurized and stresses in the RCPB materials and potential for LEAKAGE are reduced.
In MODES 4 and 5. RCS operational LEAKAGE' limits are not required since the reactor is not pressurized and stresses in the RCPB materials and potential for LEAKAGE are reduced.
ACTIONS           .Ad With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKtSE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and 4
ACTIONS
quantified, it may be reclassified and considered as h.-
.Ad With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKtSE rates before the reactor must be shut down.
identified LEAKAGE: however, the total LEAKAGE limit would remain unchanged.
If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as h.-
kl.                       B.1 and B.2
identified LEAKAGE: however, the total LEAKAGE limit would 4
                                  . An unidentified LEAKAGE increase of > 2 gpm within a 24 hour period is an indication of a potential flaw in the RCPB and must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required
remain unchanged.
                                    .Compietion Time by evaluating service sensitive type 304 and type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to IGSCC. For an unidentified LEAKAGE increase greater than required limits (in accordance with LC0 3.0.2),
kl.
B.1 and B.2
. An unidentified LEAKAGE increase of > 2 gpm within a 24 hour period is an indication of a potential flaw in the RCPB and must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required
.Compietion Time by evaluating service sensitive type 304 and type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to IGSCC. For an unidentified LEAKAGE increase greater than required limits (in accordance with LC0 3.0.2),
an alternative to this evaluation is to reduce the LEAKAGE increase to within limits (i.e., reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase in the previous _24 hours" limit: either by isolating the
an alternative to this evaluation is to reduce the LEAKAGE increase to within limits (i.e., reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase in the previous _24 hours" limit: either by isolating the
                                  . source or other possible methods).
. source or other possible methods).
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety.
Ll FERMI   UNIT 2-                         B 3.4.4 -4           Revision 10,       07/09/99 h..
Ll FERMI UNIT 2-B 3.4.4 -4 Revision 10, 07/09/99 h..


F                                                                                                   1 L
F 1
l RCS Operational LEAKAGE B 3.4.4 l
L l
  ]           BASES ACTIONS (continued)
RCS Operational LEAKAGE B 3.4.4
C.1 and C.2 If any Required Action and associated Completion Time of
]
,                                Condition A or B is not met or if pressure boundary LEAKAGE i
BASES ACTIONS (continued)
exists. the plant must be brought to a MODE in which the LC0       )
C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B is not met or if pressure boundary LEAKAGE exists. the plant must be brought to a MODE in which the LC0
does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience. to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.
)
SURVEILLANCE       SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity. RPV head flange leak detection, and sump monitoring systems).
i does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience. to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems.
Leakage detection instrumentation is discussed in more               l detail in the Bases for LC0 3.4.6. "RCS Leakage Detection             ;
SURVEILLANCE SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity. RPV head flange leak detection, and sump monitoring systems).
Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any             .
Leakage detection instrumentation is discussed in more detail in the Bases for LC0 3.4.6. "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any method may be used to quantify LEAKAGE within the guidelines of Reference 5.
method may be used to quantify LEAKAGE within the guidelines         !
In conjunction with alarms and other 3' l administrative controls, an 8 hour Frequency for this i
of Reference 5. In conjunction with alarms and other 3'
Surveillance is appropriate for identifying LEAKAGE and for
i l                     administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and for kl                         tracking required trends (Ref. 6).
-kl tracking required trends (Ref. 6).
REFERENCES         1. 10 CFR 50. Appendix A. GDC 30.
REFERENCES 1.
: 2. GEAP 5620. April 1968.
10 CFR 50. Appendix A. GDC 30.
: 3. NUREG 76/067. October 1975.                                   ,
2.
: 4. UFSAR. Section 5.2.7.4.3.3.
GEAP 5620. April 1968.
                              .5. Regulatory Guide 1.45.
3.
: 6. Generic Letter 88 01. Supplement 1.
NUREG 76/067. October 1975.
j     .
4.
l FERMI   UNIT 2                       B 3.4.4- 5             Revision 10     07/09/99
UFSAR. Section 5.2.7.4.3.3.
.5.
Regulatory Guide 1.45.
6.
Generic Letter 88 01. Supplement 1.
j l FERMI UNIT 2 B 3.4.4-5 Revision 10 07/09/99


RCS P/i uimits B 3.4.10
RCS P/i uimits B 3.4.10
        )     BASES SURVEILLANCE REQUIREMENTS-(continued)
)
BASES SURVEILLANCE REQUIREMENTS-(continued)
This SR has been modified with a Note that requires this Surveillance to be performed as applicable only during system heatup and cooldown operations and inservice leakage and hydrostatic testing.
This SR has been modified with a Note that requires this Surveillance to be performed as applicable only during system heatup and cooldown operations and inservice leakage and hydrostatic testing.
SR 3.4.10.2 A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.
SR 3.4.10.2 A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.
Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the control rod withdrawal.
Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the control rod withdrawal.
SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3                         Differential temperatures within the applicable limits f                         ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances.
SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3
Differential temperatures within the applicable limits f
ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances.
Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30%
Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30%
RTP or operating loop flow s 50% of rated loop flow, ensure that thermal stresses resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design allowances.
RTP or operating loop flow s 50% of rated loop flow, ensure that thermal stresses resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design allowances.
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase, or flow increase.
Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase, or flow increase.
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating recirculation loop and the idle loop.
An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating recirculation loop and the idle loop.
I FERMI - UNIT 2                     B 3.4.10 - 7           Revision 10 07/09/99
I FERMI - UNIT 2 B 3.4.10 - 7 Revision 10 07/09/99
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Latest revision as of 17:42, 6 December 2024

Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS
ML20209H033
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Issue date: 07/13/1999
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DETROIT EDISON CO.
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References
NUDOCS 9907200104
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" M dF Recirculation Loops Operating 3.4.1 ) 3.4 REACTOR COOLANT SYSTEM (RCS) t 3.4.1 Recirculation Loops Operating b LCO 3.4.1 The reactor core shall not exhibit core thermal hydraulic instability or operate in the " Scram" or " Exit" Regions. "I 8NQ 4 a. Two recirculation loops with matched recirculation loop jet pump flows shall be in operation: M { b. One recirculation loop may be in operation provided: 1. LC0 3.3.1.1 " Reactor Protection System (RPS) Instrumentation." Function 2.b (Average Power Range Vl Monitors Simulated Thermal Power-Upscale) Allowable Value of Table 3.3.1.11 is reset for single loop operation, when in MODE 1: and e k 2. THERMAL POWER is s 67.2% RTP. .J % q ................~............N0TE x Required allowatt.e value modification for single loop j El operation and THERMAL POWER limitation may be delayed for up L to 4 hours after transition from two recirculation loop operations to single recirculation loop operation. APPLICABILITY: MODES I and 2.- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Recirculation jet pump A.1 Declare recirculation 2 hours 100) flow mismatch not loop with lower flow: wit 11n limits. "not in operation." (continued) 9907200104 990713 PDR ADOCK 05000341 i P pg l FERMI - UNIT 2 3.4 1 Revision 10. 07/09/99

Recirculation Loops Operating B 3.4.1 ) BASES APPLICABLE SAFETY ANALYSES (continued) Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied. Recirculation loops operating satisfies Criterion 2 of 10 CFR 50,36(c)(2)(ii). LC0 Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the m ~ LOCA analysis are satisfied. With the limits specified in i SR 3.4.1.2 not met, the recirculation loop with the lower d flow must be considered not in o With only one recirculation loop in operation,peration. modifications to the APRM y{ Simulated Thermal Power-Upscale setpoint (LC0 3.3.1.1) and a limitation on THERMAL POWER may be applied to allow S continued operation consistent with the assumptions of the safety analysis, f ) Operations that exhibit core thermal hydraulic instability e are not permitted. Additionally, in order to avoid G potential power oscillations due to thermal hydraulic instability, operation at certain combinations of power and ?u flow are not permitted. These restricted power and flow cc regions are referred to as the " Scram" and " Exit" regions y and are defined by Bases Figure B 3.4.1-1. A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to jl establish the APRM Simulated Thermal Power - Upscale setpoint in accordance with the single loop allowable value. m dt which is specified in Table 3.3.1.1-1 and to establish 9C operation at 5 67.2% RTP. The 4 hour period is sufficient to make the adjustments given the relatively small change j required. This transition that results in a> plying the new 4 single-loo) allowable values to APRM OPERABI_ITY, is such g that any ARPM non compliance with the required allowable value after.this 4 hour allowance results in ACTIONS of 4 LC0 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would apply. j l FERMI - UNIT 2 B 3.4.1 - 4 Revision 10. 07/09/99

$ fEC IFt cAgian) 3 <{. / [Nse Su SFi eq/fori 54/0) 3 /4. 4 REACTOR COOLANT SY' STEM 3 3/4.4.1-RECIRCULATION SYSTEM 1 RECIRCULATION LOOPS LIMITINGtCONDITION FOR OPERATION l.M p,g 2.t.:.1-Two reactor coolant system recirculation loops shall be in operation. APPLICABILITY: OPERATIONAL CONDITIONS 1-and 2*. ACTION: a. With one reactor coolant system recirculation loop not in operation: LLo M.I' 3. Within 4 hours: LAil t@TW~ m)Plar/ the individual rarAculation pump flow cof roller'for the ] g ra op#atino recirculatio(pumo in the Manual moda g y gy,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27, of RATED THERMAL POWER. j,j Limit the speedff the operating recire ) or'eaual to 751f of rated pump speeds)/Intion pump to les/than] ^ d) in ase Ine MiniriurycMITICAL Powtx MAisy (Isrn) barety L1 t to] value for sing)e loop operation reqVired by Specifica on j .27 g 3 e) Change the Average Power Range Monitor (APRM) Simulated Thermal, n j @ N'I'g'g Power - Upscale Flow Biased Scram tr.f N :".en Nr se-rMis? WA110wable Values to those applicable for single recirculation ~ loop operation per Specifications 2.2.1 and 3.3.6. l f '"ferform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is gggfugh )f recirculation loop flow in the operating loop is le less than or equal to 307, of RATED THERMAL POWER or the gg,,, 7 i equal to 507, of rated loop flow, u 3 -2. Oth:r "-- 6 4-it h ::: ll0T ;;rJ ;; n. 6uin tue u m n,,_... b. With no reactor coolant system recirculation loop in operation while in bTION D OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position. ~ With'no reactor coolant system recirculation loops in operation, while in c. OPERATIONAL CONDITION 2, initiate measures to place the unit in at least $ttTtotJC. HOT SHUTDOWN within the next 6 hours. {See cialTe3rException3.f0.4.] l e FERMI - UNIT 2 3/4 4-1 Amendment No. JJ,64,EJ,EJ, E7.JES, 122 PAGE 2. OF 06 ggyto i

SPEttFicATigd 3.% I (Ais.sa:rpafwrw 3 Go) L (Mso sa sp;(;w% s E d ) REACTOR COOLANT SYSTFM SURVETLIANCE REQUIREMENTS S e4. T4.1.1.1 Each pump discharge valve shall be demonstrated OPHRABLE by j $bbicycling each valve through at least one complete cycle of full travel at least J 3.g,i once per 18 months. -4 A.I.1.2 LEO r.u / h, l d.4.1.1.3 With ne reactor coolant s tem recmuieuon ioop not in 'q eration, at I st once per 12 hours erify that: THERMAL POWER i ess than or equal to 6.2% of RATED ) THERMAL POWER, nd b. The individu recirculation pump flo controller for t e operating r irculation pump is in e Manual mode, a j c. The speed f the operating recircu tion pump is le' than or coual o 75% of rated oumo see b4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL 1 POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r4ted loop flow, verify the following differential temperature requirements are met within no 1 more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: ) a. Less than or equal to 145'F between reactor vessel steam M space coolant and bottom head drain line coolant, and ged[(cqh'A b. Less than or equal to 50'F between the reactor coolant 3 Y.rb / within the loop not in operation and the coolant in the reactor pressure vessei *, and c. Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the operating loop.** b*$ *y. m

    • Requirement does not apply when the recirculation loop not ih operation is 5p46u.h>

isolated from the reactor pressure vessel. 3M6 FERMI - UNIT 2 3/4 4-2 Amendment No. 83. 59. 87. US.133 PAGE 3 _OF 06 ggqlo

r DISCUSSION OF. CHANGES ITS: KECTION 3.4.1 - RECIRCULATION LOOPS OPERATING TECHNICAL CHANGES - NORE RESTRICTIVE Non. TECHNICAL CHANGES'- LESS RESTRICTIVE " Generic" LA.1 CTS 3.4.1.1,~ Actions a.1.a) and c), and 4.4.1.1.3, impose limitations on: the recirculation pump flow controller mode of operation; and the operating g' recirculation pump speed. These limitations are related to operational considerations associated with . prevention of possible control oscillations and reactor I vessel internals vibration, and are not associated with the function of the Recirculation Loop Operating ~ Technical Specification as defined in the NUREG-1433 4 Bases. Therefore, the requirements for maintaining M these limitations can be adequately defined and controlled in the Technical Requirements Nanual (TRM), j[ which require revisions to be controlled by 10 CFR 50.59. These relocations continue to provide adequate protection of the public health and safety since the ITS retain sufficient requirements related to maintaining thermal limits and thermal hydraulic stability for single. loop operation. LA.2 Not used i O E FERNI - UNIT 2 3 REVISION 10, 07/09/99

Recirculation Loops Operating 3.4.1 ') 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating d@b k M'8' LCO 3.4.2 recirculatio oops with matched flows sha i be in rew c,geg( n + g;),;p 3*OI 3) operation, core % mot h'idasuc iris la,Wllfy oofetuk-Y in Se " Scrod or %ii% gin >0ne recirculation loop may be in op pro 4mpts-we-applied-when-the-essoci et ~ 0:.:.:,.= =.~ = - y m = =- F ( HGR)," single loo operation limits pecified in 4 eCOLRp l W LCO 3.2.2, " MINI CRITICAL POWER 10 (MCPR)," si gl o operation mits Isoecifiaa in +k. entp1 and n av CO 3.3.1.1, " Reactor Protection System (RPS) u MC f aa.e)\\ Achm Instrumeritation." Function 2.b (Average Power an e / MonitorslFle hudhimulated Thermal Power N f Allowable Value of Tabl_M1.1-1_is reset for s ngle loop operatio ) ( ppe /> V' lME(LT 3 41-l j' ? ? APPLICABILITY: MODES I and 2. L e ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Reg rement of the A.1 Satisfy t 24 hou LC not a require nts of the LCO. / ( --nm..;....::.;, :=. (continued) /tdsEET 3.y.1-2. BWR/4 STS 3.4-1 Rev 1, 04/07/95 w4 " t

I Recirculation Loops Operating 3.4.1 INSERT 3.4.1 - 1 g LC0 3.4.1.1 J b. 2. THERMAL POWER is s 67.2% RTP. ..........................N0TE----- ------------------ -- g 3> 4 Required allowable value modification for single loop operation may be delayed for up to 4 hours after transition from two recirculation loop operation to single y.q,t.1 recirculation loop operation. Ac. nog a.1 FERMI - UNIT 2 Page 3.4 1 (1) (INSERT) REVISION 10, 07/09/99l

Recirculation Loops Operating B 3.4.1 BASES .s I APPLICABLE A plant specific LOCA analysis has been performed assuming SAFETY ANALYSES only one operating recirculation loop. This analysis has (continued) demonstrated that, in the event of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency Core Cooling System response will provide adequate core coo { j

==; revi,: le er. ::fified The transient analyses of Chapter 15 of the SAR have also been performed for single recirculation loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed,;r n !d;d 1; 7.^7; P3 r:; i - -te a-a d 'f-d. During single recirculation loop operation, modification to the Reactor Protection System (RPS) average power range monitor (APRM) instrument setpoints is also required to account for the diffe t, relationships between recirculation drive flow and. ector fI core flow.:;: :t!? ?- !!? !ed fr t.' % ;. The APRM W W '2,., The A" E P. trd ". = eetveir.t; fr :te:h _!ee n r Inferi fimulated T)(FJD%I tsetpoint is in LCO 3.3.1.1, " Reactor Protection 5fsteli ( 5 Instr 5==a+=tlan." g3 3.v,/-2. I- >Recirculatlan loops - O[5 c* lC. -- M t to cfR sct3HeXaf]erion 2 of 4he- =^ Fol k, i.i ..t. 3 i LC0 Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1A to ensure that during a LOCA caused by a break of i sne piping of one recirculation loop the assumptions of the LOCA analysis are satisfied. With the limits specified in 5R 3.4.I V not met, the recirculation loop with the lower flow must be considered not in operation. With only one I'Cfleu}agg,n,,1, opp gogyation,mogtiop,to the,,__ k' ...... -..... m - -. u,,um HEAHrENERAHC% MTC (',PZP.)'), "= 10::it: (' 00 3.2 ' [ehnt"(50 31 applied to allow continuea operation consistent with the assumptio of e:.::3. v - & ondUM{aN o sid only p,4 a y Inse rt ^ ^ ^ on W EtM N f 4 46 3 41-3 } G (continued) -" j: liY3-B 3.4-3 ,ev 1, ^4/"Jiii Ra/10 s

r 1 Recirculation Loops Operating B 3.4.1 m l l Insert B 3.4.1 - 2 1 Thermal-hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 4 are satisfied. 1 1 Insert B 3.4.1 -3 Operations that exhibit core thermal-hydraulic instability are not permitted. Additionally, in order to avoid potential O power oscillations due to thermal-hydraulic instability, l operation at certain combinations of power and flow are not permitted. These restricted power and flow regions are referred to as the " Scram" and " Exit" Regions, and are defined

f. s by Bases Figure B 3.4.1-1.

y l A Note is provided to allow 4 hours following the transition k l to single loop operation from two loop operation to establish T the APRM Simulated Thermal Power-Upscale setpoint in y accordance with the single loop allowable value, which is specified in Table 3.3.1.1-1 and to establish operation at \\y s; 67.2% RTP. The 4 hour period is sufficient to make the adjustments given the relatively small change required. This transition that results in applying the new single-loop D l allowable values to APRM OPERABILI7, is such that any APRM f i non compliance with the required aFlowable value after this 4 hour allowance results in ACTIONS of LC0 3.3.1.1 being l$ entered; no ACTION of LC0 3.4.1 would apply. e 9 l l FERMI UNIT 2 Page B 3.4 3 (INSERT) REVISION 10. 07/09/99l l

H SRVs B 3.4.3 ) BASES p

APPLICABLE The~ overpressure protection system must accommodate the most

' SAFETY ANALYSES-severe pressurization transient. Evaluations have determined that the most severe transient is-the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in .the safety mode. The analysis results demonstrate.that the design SRV capacity is capable of maintaining reactor pressure below the ASE Code limit of 110% of vessel design pressure 1(110% x 1250 psig

  • 1375 psig). This LCO helps to ensure that the acceptance limit of 1375 psig is met during.

the Design Basis Event. From an over>ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected.to actuate the SRVs. SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). I LC0 The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The. requirements of this LCO are applicable only to the capability of the SRVs to mechanically open to relieve - excess pressure when the lift setpoint is exceeded (safety function). Ok~l The SRV setpoints, and 3% allowance for setpoint drift. are established to ensure that the ASME Code limit on peak reactor pressure.is satisfied. The ASME Code specifications require the lowest safety valve set vessel design pressure (1250 psig) point to be at or below and the highest safety-valve-to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based'on these setpoints. Operation with fewer valves OPERABLE than specified, or with i setpoints outside the ASME limits, could result in a more i severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded, i ? l FERMI:- UNIT 2 - B 3.4.3 -2 Revision 10 07/09/99

S/RVs B 3.4.3 f BASES APPLICABLE pressure (110% x 1250 psig - 1375 psig). This LC0 helps to SAFETY AMALYSES ensure that the acceptance limit of 1375 psig is met during (continued) the Design Basis Event. From an overpressure standpoint, the design basis events are bounded by the MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the S/RVs. Op,f S/RVs satisfy Criterion 3 of 'M ""! "eli-{-- Ote% D )- c t^ i_b CTR 50.$ Ql'2 LC0 The safety functiori ofX1lyS/RVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs. I and 2). The requirements of this LC0 are applicable only to the capability of the S mechanically open to relieve excess pressu/RVs to re when the lift setpoint is exceeded,Jsafety faartioni e Op*q TheS/RVsetpoints.(.r,..staolisneasoensurethatthee AttoGwet. Or algaid d aw3 3) Code limit on peak reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for ssurization conditions. The transie_n valuations in ove arW+basedonthesesetpoints;4 sty"ofeehade-tta ] t

f ' f-9 ree ':fet! : a' + " a' na 2:. ;;tp'.;.t dei't tr ;n;f t :: :'f:f t;n; ;f ;;;.;;r;;ti;;;.

Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded. 1 l ,l U APPLICABILITY InMODES1,2,and3.hS/RVsmustbeOPERABLE,since considerable energy may be in the reactor core and the limiting design basis transients are assumed to occur in these MODES. The S/RVs may be required to provide pressure relief to discharge energy from the core until such time that the Residual Heat Removal (RHR) System is capable of i dissipating the core heat. (continued) BWR/4-STS-B 3.4-13 Re; 1,- 0"j^7/n-

RCS Operational LEAKAGE 3.4.4 ) 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LC0 3.4.4-RCS operational LEAXAGE shall be limited to: a. No pressure boundary LEAKAGE: b. 5 5 gpm unidentified LEAKAGE: c. s 25 gpm total LEAKAGE averaged over the previous 24 hour period: and d. s 2 gpm increase in unider.,fied LEAKAGE within the previous 24 hour period in MODE 1. APPLICABILITY: MODES 1, 2. and 3. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME s A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours not within limit, within limits. M Total LEAKAGE not within limit. h B. Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours t increase not within within limits. ? limit. k 2 (continued) l l l-FERMI - UNIT 2 3.4 8 Revision 10, 07/09/99 j

l l RCS Operational LEAKAGE 3.4.4 ) ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME j i g B. (continued) B.2 Verify source of 4 hours unidentified LEAKAGE increase is not 4 service sensitive type 304 or type 316 austenitic stainless steel. C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion Time of Condition A 6tLD or B not met. C.2 Be in MODE 4. 36 hours 2 Pressure boundary LEAKAGE exists. i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY fl SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 8 hours and unidentified LEAKAGE increase are within limits. l FERMI UNIT 2 3.4 9 Revision 10, 07/09/99

r (c L RCS Operational LEAKAGE B 3.4.4 ) BASES APPLICABILITY In MODES 1, 2..and 3 the RCS operational LEAKAGE LC0 a> plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized. In MODES 4 and 5. RCS operational LEAKAGE limits are not required since the reactor-is not pressurized and stresses l .in the RCPB materials and potential for LEAKAGE are reduced. R -ACTIONS &J l With RCS unidentified or total LEAKAGE greater than the . limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively belos the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as h identified LEAKAGE:.however, the total LEAKAGE limit would remain tuhanged. ' kl - B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpm within a 24 hour-t period is an indication of a potential flaw in the RCPB and must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required Completion Time by evaluating service sensitive type 304 and . type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or

intermittent flow fluids and determine it is not the source I

of the increased LEAKAGE. This type piping is very I susceptible to IGSCC. For an unidentified LEAKAGE increase l greater than required limits (in accordance with LCO 3.0.2), an alternative to this evaluation is to reduce the LEAKAGE-increase to within limits (i.e.. reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase in the previous 24 hours" limit: either by isolating the i l source or other possible methods). The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety. l FERMI . UNIT 2 - B 3.4.4-4 Revision 10, 07/09/99

RCS Operational LEAKAGE B 3.4.4 } BASES ACTIONS (continued) C.1 and C.2 l If any Required Action and associated Completion Time of Condition A or B is not met or if pressure ~ boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apaly. To achieve this status, the plant must be brought to 10DE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems. SURVEILLANCE SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity, RPV head flange leak detection, and sump monitoring systems). Leakage detection instrumentation is discussed in more detail in the Bases for LC0 3.4.6 "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any method may be used to quantify LEAKAGE within the guidelines 3 of Reference 5. In conjunction with alarms and other Tl administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and fur -kl tracking required trends (Ref. 6). REFERENCES 1. 10 CFR 50, Appendix A. GDC 30. 2. GEAP 5620, April 1968. 3. NUREG-76/067, October 1975. l 4. UFSAR, Section 5.2.7.4.3.3. 5. Regulatory Guide 1.45. 6. G0neric Letter 88-01, Supplement 1. l FERMI - UNIT 2 B 3.4.4-5 Revision 10, 07/09/99 i

S ec4cotwa 344 f D . p REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) ACTION: (Continued) In OPERATIONAL CONDITION 1, with any reactor coolant system [ g, art $ e. UNIDENTIFIED LEAKAGE increase greater than 2 gpa within any 24 hour period, identify the source of leakage increase as not service sensitive Type'304 or 316 austenttic stainless steel Action C - within 4 haursfor be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. f. In OPE L COND 2 and (with any ctor coo nt system v L.2 UNID FIED L increase ater tha gpm wit any 4 ur I p d, ident he sour f leakage rease et serv nsitive 304 or austeniti ainles eel wi 4 / hours in at - t HOT SHUT withi e next hoursand} in SHUTDOW thin the fo wing 24 ours j-SURVEILLANCE REOUIREMENTS ~3 4 -} -4.4.2.2.b The reactor coolant system leakage shall be demonstrated to be within each of the above limits by: e ne d en d =n+ We,qese'o*'u LA.I o dio vit[6tleastonceperenours1_ bgo#DnaAne primary corttetsment-tump -tro hour (ihours th vrt.MilDML wnplIIUM ItVand at least once per 4 l d er 3 in OPERATIONAL CONDITIONS 2 and 3, T / [c#enftorgthe.ArfGeMacMn4Mel # 1dO [ 'f hourst*rin OPERA"IONAL CONDITION W and at least once per 4 j i ours in OP7 RATIONAL CONDITIONS 2 and 3, and rin AdakAMM% LA. ) l lad [m wrai.*.rsh1'T7vdM 4 .. a. m. . c. ;.,. . g m m,. a u L,j t m .s M " - - - r.nn u a-..t l in emn n=: - r -- = ;. I FERMI - UNIT 2 3/4 4-11 Amendment No. 89 1 %m' PAGE-c2 0F 02 86VlO

DISCUSSION OF CHANGES ITS8 SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE TECHNICAL CHANGES - LESS RESTRICTIVE O " Specific" 2. N L.1 CTS 4.4.3.2.1 rquires that leakage be demonstrated to be within limit,in part, by monitoring primary containment atmospheric gaseous radioactivity at least once per 4 hours. However, the remaining parts of CTS 4.3.2.1 l require leakage be demonstrated to be within limit by monitoring once per 12 hours; and this 12 hour monitoring is done on the system that actually quantifies the leakage (the atmospheric gaseous radioactivity monitor is p_ot o utilized to quantify the leakage for comparison to the LCO limit, as provided in CTS footnote

  • to the referenced surveillance). Note also that in Mode 1 l

this Frequency is restricted from applying the 25% extension of ITS SR 3.0.2. ITS SR 3.4.4.1 requires verification every 8 hours that the RCS unidentified and total Leakage, and unidentified Leakage increase, are within limits (which is more restrictive than these latter CTS requirements, but included here for completeness). RCS Leakage is monitored by a variety of instruments designed to provide alarms when excessive Leakage is indicated and to quantify the various types of Leakage. In conjunction with alarms and administrative controls, an 8 hour Frequency for this Surveillance is appropriate for identifying Leakage and for tracking trends. With this increased Frequency of performance (from 12 to 8 hours), the 25% extension of SR 3.0.2 is allowed to be applied (i.e., a 10 hour maximum interval; still . more restrictive than the CTS 12 hours). This change is consistent with the intent of Generic Letter 88 01, to provide an effective means to determine any Q adverse trends and as such will have a negligible impact on safety.

3 FERMI - UNIT 2 2

REVISION 10, 07/09/99

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3 CIS} I 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE; 3** b. s gpa unidentified LEAKAGE c. s fSS) gpm total LEAKAGE averaged over the previous p*l 24hourperiod;fand d. s 2 gpa increase in unidentified LEAKAGE within the previous M hour period in MODE 1.K j APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to 4 hours not within limit, within limits. ,3,7 Achto!L b. Total LEAKAGE not within limit. B. Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours g increase not within within limits. limit. \\ .Qll N t (continued) 1 - "":n/4 373 - 3.4-7 En 1, G4/G7/55 e# 1

l RCS Operational LEAKAGE 3.4.4 / CTS) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME y i B. (continued) B.2 Verify source of 4 hours unidentified LEAKAGE 3.4. 3. 2 increase is not service sensitive dc,htoftd. type 304 or type 316 austenitic stainless steel. C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion 3.4.3.1 Time of Condition A AEl or B not met. d#^ #> C.2 Be in MODE 4. 36 hours b /6 DE Pressure boundary LEAKAGE exists. .c SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE S hours and unidentified LEAKAGE increase are ,4.3,2.tk G within limits. / g 3L"'/t :;T3 3.4-B -Rev 1, O'/07/o t ./ Rev' W 4

RCS Operational LEAKAGE B 3.4.4 f-BASES (continued) ACTIONS L1 With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKAGE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as identified LEAKAGE; however, the total LEAKAGE limit would remain unchanged. y i k B.1 and B.2 An unidentified LEAKAGE increase of > 2 gpa within our period is an indication of a potential flaw in the RCPB and 1 must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to the source of the LEAKAGE increase within the required un accorda m Completion Timer)for an unidentified LEAKAGE increase w;w r o.z ') greater than required limitsf an alternative to ' '-- ^ LEAKAGE increase to within limits (i.e., reducing the thi5e*Lution zy LEAKAGE rate such that the current rate is less than the Qsto %ct fhe, Op'q "2 com increase in the previou hours" limit; either by ~ isolating the source or other p ss ble methods? is::ta=. p) r-+m service sensitive type 3v, anc type 3e6 austenttici est{afj stainless steel iping that is subject to high stress or that contains re atively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to ISSCC. The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety. C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B is not met or if pressure boundary LEAKAGE exists, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within It hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, (continued) nun /A NS-- B 3.4-20 Rr; I, 0i/07/95 Rev10

I RCS Operational LEAKAGE B 3.4.4 5-BASES ] ACTIONS C.1 and C.2 (continued) based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems. = les Con kinme.<tMmos JAra 6esem.s /d. (/ae f,V;/yl,, R,wbv Ata,I 8/ age lee.le c(4 SURVEILLANCE SR 3.4.4.1 1 REQUIREMENTS oum men i e e M _s vs1eis.3 The RCS LEAKAG s mon ored by a vari y of instrumiints designed to provide alarms when L is indicated and to quantify the various types of LEAKAG Leakage detection instrumentation is discussed in more detail in the Bases for LCO 3.4.6, 'RCS Leakage Detection Instrumentation." Sump ' level and flow rate are typically monitored to determine actual LEAKAGE rates; however, an quantify LEAKAGE within the guide'y method may be used to Jines of Reference 5. In conjunction with alarus and other administrative controls, an 8. hour Frequency for this Surveillance is appropriate for identifying LEAKAGE and for tracking required trends [ (Ref. 6). I REFERENCES 1. 10 CFR 50, Appendix A. GDC 30. r- ) ./ 2. GEAP-5620, April 1968. 3. NUREG-76/067, October 1975. ,2.Y. .4. yFSAR, Section."..... 5. Regulatory Guide 1.45. 6. Generic Letter 88-01, Supplement 1. . n.,, ?""f' !!! B 3.4-21 Rsi ;, O'/0:'/0 fievl0

JUSTIFICATION FOR DIFFERENCES FROM NUREG - 1433 ITS: SECTION 3.4.4 - RCS OPERATIONAL LEAKAGE NON BRACKETED PLANT SPECIFIC CBANGES P.1 These changes are made to NUREG 1433 to reflect Fermi 2 current l 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. P.2 Bases changes are made to reflect plant specific design details, I equipment terminology, and analyses. P.3 Not used. P.4 Change made for editorial preference or clarity. h lh d P.5 Not used. 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). ) 4 FERMI UNIT 2 1 REVISION 10, 07/09/99l

1 I RCS Leakage Detection Instrumentation 3.4.6 ] 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detetion Instrumentation LC0 3.4.6 The following RCS leakage detection instrumentation. shall be OPERABLE: a. Drywell floor drain sump flow monitoring system: d b. The primary containment atmosphere gaseous radioactivity 1 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. s CONDITION REQUIRED ACTION COMPLETION TIME 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 containment atmosphere of primary 24 hours gaseous radioactivity containment monitoring system atmosphere. inoperable. (continued) j l FERMI UNIT 2 3.4-13 Revision 10, 07/09/99

RCS Leakage Detection Instrumentation 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) [ cts) 3.4.6 RCS Leakage Detection Instrumentation d LCO 3.4.6 The following RCS leakage detection instrumentation shall be [ OPERABLE. Drywell floor drain sumpfmo to ing system:M(7.4,J.l.b h a. b. ^ - ""---' - imary containment 6 pr gaseousmonitoring_systeg;f.43I.

  • g cat-r em+-matmosphe Stand a

9foyg@g,,g r cooler 3pertiensajed1pate] c. noe h DrfN *LE Noor drain surp APPLICABILITY: MODES 1, 2, and 3. '###$ "'*0 N##'"j 5[8b-g ACTIONS f 3 \\ CONDITION REQUIRED ACTION COMPLETION TIME \\ A. Drywell floor drain -NOTE-------- D g sumpamonitoring system LCO 3.0.4 is not applicable. 3,4,3 l j inoperable. Ac-l.io tt A.I Restore drywell floor 30 days drain summ monitoring system tof0PERABLE status. (continued) .-0Wtf* T.r-3.4-12 En 1, 54/07/fr5-W fD ~ ~ '

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 / inc.' ease in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow. Once within L Verify the difference between the bottom 15 minutes l head coolant temperature and the RPV steam prior to a space coolant temperature is s 145'F. THERMAL POWER l increase or recirculation l flow increase l SR 3.4.10.6

--- ---- NOTE-Only required to be met during a THERMAL POWER increase or recirculation flow i

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 50t rated loop flow. Once within 15 minutes 4 l Verify the difference between the reactor prior to a coolant temperature in the idle THERMAL POWER / . recirculation loop and the RPV coolant increase or 3f l temperature is s 50*F. recirculation flow increase (continued) 1 I l FERMI.- UNIT 2 3.4 26 Revision 10 07/09/99

o r E RCS P/T Limits B 3.4.10 i l } ' BASES SURVEILLANCE. REQUIREMENTS (continued) This SR has been modified with a Note that requires this l-Surveillance to be performed as applicable only during J system heatup and cooldown operations and inservice leakage and hydrostatic testing. SR 3.4.10.2 A separate limit is used when the reactor is approaching ) l I criticality. Conse uently, the RCS pressure and temperature must be verified wi hin the appropriate limits before withdrawing control rods that will make the reactor critical. Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be j exceeded between the time of the Surveillance and the time of the control rod withdrawal. SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3 Differential temperatures within the applicable limits l ~j' ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances. Limiting _ differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow -increase in single loop operation, while THERMAL POWER s 30t RTP or operating loop flow s 50% of rated loop flow, ensure i that thermal stre b es resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design - allowances. Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase i during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase. or flow increase. An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating -recirculation loop and the idle loop. J l FERMI - UNIT 2 B 3.4.10 - 7 Revision 10, 07/09/99

S E c t r-t c N n M 8.'h l O f (MSOSeeSecTScaHM 3 4. /) / lse? Set Geci $~CaNM 8 0~'I) REACTOR COOLANT SYSTEM SURVETLLANCE RFOUIREMENTS Si (8 b cy.4.1.1.1 4 Each pump discharge valve shall be demonstrated OPGRABLE by cling each valve through at least one complete cycle of full travel at least 3Sil once per 18 months. i.4.1.1.2 DELETED 4.4.1.1.3 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that: Sq a. THERMAL POWER is less than or equal to 67.2% of RATED %cifuah% THERMAL POWER, and b. The individual recirculation pump flow controller for the 3.Y. I operating recirculation pump is in the Manual mode, and c. The speed of the operating recirculation pump is less than or equal to 75% of rated pump speed. 4.4.1.1.4 With one reactor coolant system loop not in operation with TilERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: GC3. 4 lD.I a. Lets than or equal to 145*F between reactor vessel steam I space coolant and bottom head drain line coolant, and b. M M.lo.h Less than or equal to 50'F between the reactor coolant wi_tttin the loop not in operation and (the coolant in th Qeactor pressure vesset=. ano A c. Less than or equal to 50'F between the reactbr/ coolant within the loop not in operation andine operating loop)** 4 --*"at u seh

    • Requirement does not apply when the recirculation loop not ih operation is 3.'f.la.h isolated from the reactor pressure vessel.

~ FFRMI - UNIT 2 3/4 4-2 Amendment No. 53. 59. E7. UB,133 PAGE c1 0F 08 RW 0

r I RCS P/T Limits 3.4.10M SURVEILLANCE REQUIREMENTS (continued) i SURVEILLANCE FREQUENCY SR 3.4.10.3 NOTE-C'I Only requ.. ired to.be met in MODES 1, 2, 3 h ' YO; gig) l .no 4,p u... -.....- a _...... l Auti (tLitcal 'on - ,~ er,.i.,X,. " ~~~~~ ~~ ~ " ~~~~~~- L tu y s M qa h.95)M Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes y

SPact, pressure vessel (RPV)fcoolant temperature prior to each is Mth

.: li:::it: :pe:!'!ed 4' +he DTLD startup of a (iqg,y recirculation pump SR 3.4.10.4

NOT E-------------

Only required to be met in MODES 1, 2, 3, [3.4l#, AglicW/f/y) dvrG, it ppp forkup, -- - Verify the difference between the reactor

3. 4 \\ d Once within 4.4. l. M coolant temperature in the recirculation 15 minutes loop to be started and the RPV coolant prior to each temperature 1-t (Mke 14-it: spt:i't:d-startup of a

-in the PTLR. yi f5oy recirculation lt5 E W B. % to - 2 SR 3.4.10

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

I Only required to be performed when studs. " 4 fal.'l b ) tensioning the reactor vessel head bolting Verify reactor vessel flange and head 30 minutes flange temperatures are ti.hin +he 'i=i+3 J &::i't:dinth:kc4x vedeIhead 5H dvd.s are PTL".J> il s p When [ h j (continued) BWR/4 STS 3.4-25 Rev 1, 04/07/95 RW LO

I RCS P/T Limits 3.4.10 i ~ INSERT 3.4.10 _2 j SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.5' ----- ----- --- --NOTE - --- ------ Only required to be met during a THERMAL MchmA4h' POWER increase or recirculation flow increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50t 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 SR 3.4.10.6 NOTE- - - ----- --- ---- Only required to be met during a THERMAL (AcTionatE) h POWER increase or recirculation flow increase in MODES 1 and 2 with one non-isolated idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is s 50% rated loop flow. l 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 FERMI - UNIT 2 Page 3.4-25 (INSERT) . REVISION 10, 07/09/99l 1

i-RCS P/T Limits B 3.4.10 BASES SURVEILLANCE SR 3.4.10.2 REQUIREMENTS (continued) A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical. Perfoming the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality { provides adequate assurance that the limits will not be 1 exceeded between the time of the Surveillance and the time ) of the control rod withdrawal. h sa 3.4.10.3 w.sR 3.4.10.4.J R 7,'/,/0 f' a d 5 # I//0 # C_ __- Differential temperatures within the applicable MtR-limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allow Ir. Pities., :----Hr.:: it;. ihe>= iisiis h.ensur;ances.; thet the-asst.ri, tie... 'vi the anai I,uer

f c.1;i.......i.i;... i.., g.r. ;;.ysis for tne star 6 p

.. -;at4sf4ed 6 M' D d hf:=t:; th Ern!!P :: MtN5:astnutus=before k { J steriiny i; 14h n:*-reh* %;=pid== =4===te 'Isaurqc,eIna sne gimiin will. ^,... z f:f,;:' ::- the =_;.. Ine-tn:c n- =...._,- GR 3{/_Op An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 s to compare the temperatures of the operating recirculation loop -- and.the idle loop. QRs hove. (;3 b: been modified by Nohatrequire in ~ 2, 2, 3 f the -SR 3. '. 3. Surveillance to be performed on1

-f ?
  • DE S wi%-ceostere== d-awee e4 ~, p;i. In T

overali stress on limiting components is Iower. MODE 5, the .Tnsed Therefore, h f8 3 4.tD-V.

  1. """"'" "'I"'"I"d" 3.4.10 h SR 3.4.10 SR 3.4.10 and SR Limits on the reactor vessel flange and head flange temperatures are generally bounded by the other P/T limits (continued)

{ BWR/4-STS-B 3.4-53. Rev.4-04107/95--- i 6 Ren0

RCS P/T Limit B 3.4.10 Insert' B 3.4.10 - 3 Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30% k RTP or operating loop flow s 50% of rated loop flow, ensure that resulting thermal stresses will not exceed design allowances. Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start. power increase, or flow increase. Insert B 3.4.10 - 4 ... for SRs 3.4.10.3 and 3.4.10.4 in MODE 5. In MODES 3, 4 and 5. THERMAL POWER increases are not possible, and recirculation flow increases will not result in additional stresses. Therefore AT limits are only required for SRs 3.4.10.5 and 3.4.10.6 in MODES 1 and 2. The Notes also state that the SR is only required to be met during the event of concern (e.g. pump startup, power increase or flow increase) since this is when the stresses occur. s FERMI - UNIT 2 Page B 3.4 53 (INSERT) REVISION 10. 07/09/99l

l l JUSTIFICATION FOR DIFFERENCES FROM NUREG 1433 ITS: SECTION 3.4.10 - RCS P/T LIMITS \\ NON BRACKETED PLANT SPECIFIC CH/NGES P.1-These changes are made to NUREG 1433 to reflect Fermi 2 current licensing basis: including design features, existing license requirements and comitments. Additional rewording. reformatting. and revised numbering is made to incorporate these changes consistent with Writer's Guide conventions. Refer to CTS Discussion Of Changes to the related requirement for a detailed justification of changes made to the current licensing basis which are also reflected in the ITS as presented. l P.2 Bases changes are made to reflect plant specific design details, equipment terminology, and analyses. P.3 Not used. P.4 NUREG 1433 Bases do not include discussion of NUREG-1433 3.4.10 Action C Note. Appropriate Bases are included for completeness. P.5 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.6 ITS SRs 3.4.10.5 and 3.4.10.6 are added to reflect the specific coolant temperature limits applicable to thermal power and flow increases while in single loop operation. These limits were located in the CTS Specification for recirculation loops operating but are more appropriately located in the Specification for Pressure and Temperature limits. This location for these SRs results in applying the appropriate Actions. This is also the subject of a pending generic change to NUREG-1433. GENERIC CHANGIS C.1 TSTF 35: NRC approved change to NUREG 1433. FERMI UNIT 2 1 REVISION 10. 07/09/99l

INSERT THIS PAGE IN FRONT OF VOLUME 11 i Volume 11: CTS MARKUP COMPILATION - ) Remove Replace 3/44-1(3.4.1 CTS M/U) pg 2 of 6 Rev 2 3/44-1(3.4.1 CTS hW) pg 2 of 6 Rev 10 j 3/44-2(3.4.1 CTS hW) pg 3 of 6 Rev 4 3/4 4-2 (3.4.1 CTS hW) pg 3 of 6 Rev 10 3/4 4-2 (3.4.10 CTS M/U) pg 2 of 8 3/4 4-2 (3.4.10 CTS hW) pg 2 of 8 Rev 10 3/4 4-11 (3.4.4 CTS hW) pg 2 of 2 3/4 4-11 (3.4.4 CTS M/U) pg 2 of 2 Rev 10 I 1 i Res10 07/09/99

S PEco r <eihJ M.! 3 /4. 4 REACTOR COOLANT SY' STEM 'g 3/4.4.1 RECIRCULATION SYSTEM 1 RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION Leo 39j ?.'..:- Two reactor coolant system recirculation loops shall be in operation. APPLICABILfTY: OPERATIONAL CONDITIONS 1 and 2*. ACTION: With one reactor coolant system recirculation loop not in operation: a. LCo M. l - 1. Within 4 hours: LAil tJOTT r.---. s r) Pla the individual re culation pump flow cof roller' for the ] g a o atino ret.f rculatio pump in the Manual mo L y y g'q,g,Qb) Reduce THERMAL POWER to less than or equal to 67.27. of RATED THERMAL POWER. j,j ) Limit the speed [f the operating recircydation pump to lesp/ han) t or eaual to 7 5 of rated pump speed e i d) Inc ase Ine Minin CRITICAL PDWLK Mali (ril,rK) baTeIy L1 L1 th value for sing loop operation reg red by Specifica on .l.2. s y e) Change the Average Power Range Monitor (APRM) Simulated Thermal, O N'O'! Power - Upscale Flow Biased Scram F.r4 M "M; Mr irire'-ts? WA110wable Values to those applicable for single recirculation ~ loop operation per Specifications 2.2.1 and 3.3.6. l f) Perform Surveille.nce Requirement 4.4.1.1.4 if THERMAL POWER is ggg fah less than or equal to 307. of RATED THERMAL POWER or the g,4,,, recirculation loop flow in the operating loop is less than or equal to 507. of rated loop flow. -2. Ot h:.:' -- ha 4-it 1::: "0T ;;;;;;;' n m nin ine u m ;; ;,_,.. b. With no reactor coolant system recirculation loop in operation while in MdD OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position. With no reactor coolant system recirculation loops in operation, while in c. OPERATIONAL CONDITION 2, initiate measures to place the unit in at least h CTlDb) C, HOT SHUTDOWN within the next 6 hours. See etialTe3(Exception 3.f0.4.] I e FERMI - UNIT 2 3/4 4 1 Amendment No. JJ,64,EJ,EJ, EJ,Jpp, 122 PAGE 2. OF 06 Raulo i

e i SPEt tFwAng4 3.% I (Aisw sat paciRutre 3 4o) (Aho sat spcil;ukm s E t ) REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS S ee. T4.1.1;I Each pump discharge valve shall be demonstrated OPGRABLE by @w icycling each valve through at least one complete cycle of full travel at least 3,g,, once per 18 aienths. .;.2 eus s w / 4,1 .=.A.1.3 With reactor coolant s tem recm.u mien eration,'at I st once per 12 hou erify that: ivobnotin THERMAL POWER i ess than or equal to 6.2% of RATED THERMAL POWER, nd b. The individu recirculatioa pump f1 controller for operating irculation pump is in e Manual mode, a c. The speed f the operating recircu tion pump is le tha#nl or eoual o 75% of rated aa-a une r j 4.4.1.1.4 With one reactor coolant system loop not in operatjon with THERMAL POWER less than or equal to 305 of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 505 of r$ted loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation flow increase: a. Less than or equal to 145'F between reactor vessel steam M 4 space coolant and bottom head drain line coolant, and i ged{gh b. Less than or equal to 50'F between the reactor coolant 3Ya within the loop not in operation and the coolant in the reactor pressure vessei+*. and c. Less than or equal to 50*F between the reactbr coolant within the loop not in operation and the cperating loop.** l l N*y. j T.u. -

    • Reautrement does not apply when the~ recirculation loop not ih operation is

$ip.4 Gu.he-isolated from the reactor pressure vessel. 3 M.t6 i FERMI - UNIT 2 3/4 4-2 Amendment No. 'U. $9. 57. UB.133 l PE 3 _OF 06 Redl0

S EttPtewnw 3.4.10 \\ f (Also see S)ecTGcafim 54.1) ) [A u s %.9 eci A ca1 % 8 E l) REACTOR COOLANT SYSTEM SURVETLtANCE REOUTREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OPGRABLE by Sl dab cycling each valve through at least one complete cycle of full travel at least 351 once per 18 months. i.4.1.1.2 DELETED '4.4.1.1.3 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours verify that: THERMAL POWER is less than or equal to 67.2% of RATED g a. % ciffa2h % THERMAL POWER, and b. The individual recirculation pump flow controller for the 3.Y.I - operating recirculation pump is in the Manual mode, and The speed of the operating recirculation pump is less than c. or equal to 75% of rated pump speed. 4.4.1.1.4 With one reactor coolant system loop not in operation with THERMAL POWER less than or equal to 30% of RATED THERMAL POWER or with recirculation loop flow in the operating loop less than or equal to 50% of rated loop flow, verify the following differential temperature requirements are met within no more than 15 minutes prior to either THERMAL POWER increase or recirculation j flow increase: i i 6A3. 4.lD8 a. Less than or equal to 145'F between reactor vessel steam space coolant and bottom head drain line coolant, and , b. M 3.4.10 4 Less than or equal to 50*F between the reactor coolant witttin the loop not in operation and(the cooiant in th Qeictor pressure vesset", ano N c. Less than or equal to 50*F between the reactbr/ coolant within the loop not in operation and Gne operating loop)** - NM und. -

    • Recuirement does not apply when the recirculaticn loop not ih operation is 3/f.i0.@

isolated from the reactor pressure vessel. FERMI - UNIT 2 3/4 4-2 Amendment No. 53. 49. E7 UB.133 PAGE c1 0F 08 REY 0

-e i-OC/ C4 /d/L 3 i REACTOR COOLANT SYSTEN LIMITING CONDITION FOR OPERATION (Continued) ACTION: (Continued) In OPERATIONAL CONDITION I, with any reactor coolant system I e. h[ oft 8 UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24 hour period, identify the source of leakage increase as not service sensitive Type 304 or 316 austenttic stainless steel within a haneiror be in at least HOT SHUTDOWN within the next 12 Jc6'on C hours and in COLD SHUTDOWN within the following 24 hours. f. In OPE LCONDJ%ncrease 2 and ith any ctor coo nt system % [., 2 UNID FIED L .i ater tha gpa wit any 4 ur 3 p , ident he sour f leakage rease at serv nsitive 304 or austeniti ainles eel wi hoursand}) 4 hours in at - t HOT SHUT withi e next in SHUTDOW thin the fo wing 24 oursy SURVEILLANCE RE001REMENTS N 3 A.M The reactor coolant system leakage shall be demonstrated to be within each of the above limits by: e ne d en W -+ " ~ V M u LA./ o vit[6tleastonceperenoursp bfoMtbrinn,tne ortmary coritetsmaat1umph hours in vrr.MilDML LUNUlilDN Mnd at least once per 4 l i di i r hour in OPERATIONAL CONDITIONS 2 and 3 3 .T = / [cJier(inrinfthodrfGe'Mardingpgel # ' d hoursitrin DPERA"IONAL CONDITION Mand at least once per 4 } [ *'), i ours in OPERATIONAL CONDITIONS 2 and 3, and n %096aMWs}safyt LA. I LA.I Cs..a.r-< M & s =, _, - - s n, .g. ,,,m m y L,/ A -s M" = - --mo rr=r r m in " - -- = 4. I ( FERMI - UNIT 2 3/4 4-II Amendment No. 89 PAGE c2 0F O'2

  1. dl0

l l l INSERT THIS PAGE IN FRONT OF VOLUME 12 Volume 12: IMPROVED TECHNICAL SPECIFICATIONS. Remove Replace l 3.4.1 ITS pg 3.4-1 Rev 4 3.4.1 ITS pg 3.4-1 Rev 10 3.4.4 ITS pg 3.4-8 Rev 0 3.4.4 ITS pg 3.4-8 Rev 10 3.4.4 ITS pg 3.4-9 Rev 0 3.4.4 ITS pg 3.4-9 Rev 10 3.4.6 ITS pg 3.4-13 Rev 4 3.4.6 ITS pg 3.4-13 Rev 10 3.4.10 ITS pg 3.4-26 Rev 0 3.4.10 ITS pg 3.4-26 Rev 10 Rev10 07/09/99

g q L w, Recirculation Loops Operating 3.4.1 l ) 3.4 REACTOR, COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating d i h LCO 3.4.1 The reactor core shall not exhibit core thermal-hydraulic instability or operate in the " Scram" or " Exit" Regions. ^l 8ND 4 a. Two recirculation loops with matched recirculation loop W jet pump flows shall be in operation: k a b. One recirculation loop may be in operation provided: 1. LC0 3.3.1.1. " Reactor Protection System (RPS) Instrumentation," Function 2.b (Average Power Range Vl Monitors Simulated Thermal Power-Upscale) Allnwable Value of Table 3.3.1.11 is reset for single loop operation, when in MODE 1: and e k 2. THERMAL POWER is s 67.2% RTP. i ............................N0TE Required allowable value modification for single loop r Ml operation and THERMAL POWER limitation may be delayed for up L to 4 hours after transition from two recirculation loop operations to single recirculation loop operation. APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Recirculation jet pump A.1 Declare recirculation 2 hours loo) flow mismatch not loop with lower flow: wit 11n limits. "not in operation." (contint.ed) -l FERMI UNIT 2 3.4 1 Revision 10 07/09/99 t

c ~ [ l 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 hour period: and - d. 5 2 gpm increase in unidentified LEAKAGE within the previous 24 hour 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 hours not within limit. within limits. Total LEAKAGE not within limit. h B. Unidentified LEAKAGE B.1 Reduce LEAKAGE to 4 hours t increase not within within limits. ' i mi t-, d M (continued) l FERMI UNIT 2 3.4 8 Revision 10, 07/09/99

.= n - RCS Operational LEAKAGE 3.4.4 ') ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME b3 B. (continued) B.2 Verify source of. 4 hours 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 hours associated Completion Time of Condition A ANQ or B not met. C.2 Be in MODE 4. 36 hours DB l Pressure boundary LEAKAGE exists. SURVEILLANCE REQUIREMENTS = SURVEILLANCE FREQUENCY jfl SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE 8 hours and unidentified LEAXAGE increase are within limits. i I l FERMI - UNIT 2 3.4 9 Revision 10 07/09/99

F ) I RCS Leakage Detection Instrumentation 3.4.6 t j ] -3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 'RCS Leakage Detection Instrumentation /' 1 LCO.3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE: a. Drywell floor drain sump flow monitoring system: Ld b. ~ The!oringsystemchannel:rimary containment atmos here gaseous ra 8 moni and c. Drywell floor drain sump level monitoring system. APPLICABILITY: MODES 1. 2. and 3. i ' ACTIONS- ..................................N0TE LC0 3.0.4 is not applicable. ~ 4 CONDITION REQUIRED ACTION COMPLETION TIME - 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 containment atmosphere of primary 24 hours gaseous radioactivity-containment monitoring. system atmosphere. inoperable. (continued) ,/ I - l' FERMI -' UNIT 2 3.4 13. Revision 10. 07/09/99

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 /f increase in MODES 1 and 2 with one idle recirculation loop when THERMAL POWER is s 30% RTP or when operating loop flow is Q s 50% rated loop flow. 1l Once within Verify the difference between the bottom 15 minutes l head coolant temperature and the RPV steam prior to a space coolant temperature is s 145'F. THERMAL POWER l increase or recirculation l flow increase SR 3.4.10.6 ---. -- NOTE---- Only required to t,e 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. Once within 15 minutes l Verify the difference between the reactor prior to a coolant temperature in the iole THERMAL POWER / recirculation loop and the RPV coolant increase or 3f temperature is s 50*F. recirculation I flow increase (continued) l FERMI - UNIT 2 3.4 26 Revision 10. 07/09/99

,,e INSERT THIS PAGE IN FRONT OF VOLUME 13 Volume 13: IMPROVED TECHNICAL SPECIFICATIONS BASES. Remove Replace B 3.4.1 ITS pg B 3.4.1-4 Rev 2 B 3.4.1 ITS pg B 3.4.1-4 Rev 10 B 3.4.3 ITS pg B 3.4.3-2 Rev 0 B 3.4.3 ITS pg B 3.4.3-2 Rev 10 B 3.4.4 ITS pg B 3.4.4-4 Rev 0 B 3.4.4 ITS pg B 3.4.4-4 Rev 10 B 3.4.4 ITS pg B 3.4.4-5 Rev 0 B 3.4.4 ITS pg B 3.4.4 5 Rev 10 B 3.4.10 ITS pg B 3.4.10-7 Rev 0 B 3.4.10 ITS pg B 3.4.10-7 Rev 10 l l l l l l Rev 10 07/09/99 L..

ir< Recirculation Loops Operating B 3.4.1 '). BASES APPLICABLE SAFETY ANALYSES (continued)- Thermal hydraulic stability analysis (Ref. 5) has concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference'4 are satisfied. Recirculation loops operating satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii). LC0 .Two recirculation loops are required to be in operation with their flows matched within the limits specified in SR 3.4.1.2 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the m; i LOCA analysis are satisfied. With the limits specified in k SR 3.4.1.2 not met, the recirculation loop with the lower J flow must be considered not in o With only one recirculation loop in operation,peration. modifications to the APRM 5 Simulated Thermal. Power-Upscale setpoint (LC0 3.3.1.1) and 6 a limitation on THERMAL POWER may be applied to allow N continued operation consistent with the assumptions of the safety analysis. Operations that exhibit core thermal hydraulic instability r are not permitted. Additionally, in order to avoid G potential power oscillations due to thermal hydraulic instability operation at certain combinations of power and 3 - flow are not permitted. These restricted power and flow cc regions are referred to as the " Scram" and " Exit" regions y' and are defined by Bases Figure B 3.4.1-1. A Note is provided to allow 4 hours following the transition to single loop operation from two loop operation to 1l-establish the APRM Simulated Thermal Power - Upscale 4 setpoint in accordance with the single loop allowable value. A which is specified in Table 3.3.1.1-l' and to establish T operation at s 67 2% RTP. The 4 hour period is sufficient .to make the sdjustments given the relatively small change-required. - This transition'that results in applying the new b single loop allowable values to APRM OPERABILITY. is such 1g that any ARPM non compliance with the required allowable l >l value after this 4 hour allowance results in ACTIONS of 4 LCO 3.3.1.1 being entered: no ACTION of LC0 3.4.1 would apply. j ~ l FERMI' L UNIT. 2 B 3.4.1 - 4 Revision 10. 07/09/99

i n , e. i SRVs B 3.4.3 BASES APPLICABLE The overpressure protection system must accommodate the most SAFETY ANALYSES severe pressurization transient. Evaluations have determined that the most severe transient is the closure of all main steam isolation valves (MSIVs), followed by reactor scram on high neutron flux (i.e., failure of the direct scram associated with MSIV position) (Ref.1). For the purpose of the analyses 11 SRVs are assumed to operate in the safety mode. The analysis results demonstrate that the design SRV capacity is capable of maintaining reactor pressure below the ASME Code limit of 110% of vessel design pressure (110% x 1250 psig = 1375 psig). This LC0 helps to ensure that the acceptance limit of 1375 psig is met during the Design Basis Event. From an over)ressure standpoint, the design basis events are bounded by t1e MSIV closure with flux scram event described above. Reference 2 discusses additional events that are expected to actuate the SRVs. SRVs satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii). 4 LC0 The safety function of 11 SRVs are required to be OPERABLE to satisfy the assumptions of the safety analysis (Refs.1 and 2). The requirements of this LC0 are applicable only to the capability of the SRVs to mechanically open to relieve excess pressure when the lift setpoint is exceeded (safety function). A-l The SRV setpoints, and 3% allowance for setpoint drift, are t v established to ensure that the ASME Code limit on peak i reactor pressure is satisfied. The ASME Code specifications require the lowest safety valve setpoint to be at or below vessel design pressure (1250 psig) and the highest safety valve to be set so that the total accumulated pressure does not exceed 110% of the design pressure for overpressurization conditions. The transient evaluations in the UFSAR are also based on these setpoints. Operation with fewer valves OPERABLE than specified, or with setpoints outside the ASME limits, could result in a more severe reactor response to a transient than predicted, possibly resulting in the ASME Code limit on reactor pressure being exceeded. l FERMI - UNIT 2 B 3.4.3-2 Revision 10, 07/09/99

I RCS Operational LEAKAGE B 3.4.4 m. 1 BASES -APPLICABILITY In MODES 1, 2, and 3 the RCS operational LEAKAGE LC0 a) plies, because the potential for RCPB LEAKAGE is greatest w1en the reactor is pressurized. In MODES 4 and 5. RCS operational LEAKAGE' limits are not required since the reactor is not pressurized and stresses in the RCPB materials and potential for LEAKAGE are reduced. ACTIONS .Ad With RCS unidentified or total LEAKAGE greater than the limits, actions must be taken to reduce the leak. Because the LEAKAGE limits are conservatively below the LEAKAGE that would constitute a critical crack size, 4 hours is allowed to reduce the LEAKtSE rates before the reactor must be shut down. If an unidentified LEAKAGE has been identified and quantified, it may be reclassified and considered as h.- identified LEAKAGE: however, the total LEAKAGE limit would 4 remain unchanged. kl. B.1 and B.2 . An unidentified LEAKAGE increase of > 2 gpm within a 24 hour period is an indication of a potential flaw in the RCPB and must be quickly evaluated. Although the increase does not necessarily violate the absolute unidentified LEAKAGE limit, certain susceptible components must be determined not to be the source of the LEAKAGE increase within the required .Compietion Time by evaluating service sensitive type 304 and type 316 austenitic stainless steel piping that is subject to high stress or that contains relatively stagnant or intermittent flow fluids and determine it is not the source of the increased LEAKAGE. This type piping is very susceptible to IGSCC. For an unidentified LEAKAGE increase greater than required limits (in accordance with LC0 3.0.2), an alternative to this evaluation is to reduce the LEAKAGE increase to within limits (i.e., reducing the LEAKAGE rate such that the current rate is less than the "2 gpm increase in the previous _24 hours" limit: either by isolating the . source or other possible methods). The 4 hour Completion Time is reasonable to properly reduce the LEAKAGE increase or verify the source before the reactor must be shut down without unduly jeopardizing plant safety. Ll FERMI UNIT 2-B 3.4.4 -4 Revision 10, 07/09/99 h..

F 1 L l RCS Operational LEAKAGE B 3.4.4 ] BASES ACTIONS (continued) C.1 and C.2 If any Required Action and associated Completion Time of Condition A or B is not met or if pressure boundary LEAKAGE exists. the plant must be brought to a MODE in which the LC0 ) i does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours and to MODE 4 within 36 hours. The allowed Completion Times are reasonable, based on operating experience. to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant safety systems. SURVEILLANCE SR 3.4.4.1 REQUIREMENTS The RCS LEAKAGE is monitored by a variety of instruments designed to provide alarms when LEAKAGE is indicated and to quantify the various types of LEAKAGE (e.g., Primary Containment Atmospheric Gaseous Radioactivity. RPV head flange leak detection, and sump monitoring systems). Leakage detection instrumentation is discussed in more detail in the Bases for LC0 3.4.6. "RCS Leakage Detection Instrumentation." Sump level and flow rate are typically monitored to determine actual LEAKAGE rates: however, any method may be used to quantify LEAKAGE within the guidelines of Reference 5. In conjunction with alarms and other 3' l administrative controls, an 8 hour Frequency for this i Surveillance is appropriate for identifying LEAKAGE and for -kl tracking required trends (Ref. 6). REFERENCES 1. 10 CFR 50. Appendix A. GDC 30. 2. GEAP 5620. April 1968. 3. NUREG 76/067. October 1975. 4. UFSAR. Section 5.2.7.4.3.3. .5. Regulatory Guide 1.45. 6. Generic Letter 88 01. Supplement 1. j l FERMI UNIT 2 B 3.4.4-5 Revision 10 07/09/99

RCS P/i uimits B 3.4.10 ) BASES SURVEILLANCE REQUIREMENTS-(continued) This SR has been modified with a Note that requires this Surveillance to be performed as applicable only during system heatup and cooldown operations and inservice leakage and hydrostatic testing. SR 3.4.10.2 A separate limit is used when the reactor is approaching criticality. Consequently, the RCS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical. Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the control rod withdrawal. SR 3.4.10.3. SR 3.4.10.4. SR 3.4.10.5. and SR 3.4.10.6 3 Differential temperatures within the applicable limits f ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances. Limiting differential temperatures within the applicable limits during a THERMAL POWER increase or recirculation flow increase in single loop operation, while THERMAL POWER s 30% RTP or operating loop flow s 50% of rated loop flow, ensure that thermal stresses resulting from THERMAL POWER increases or recirculation loop flow increases will not exceed design allowances. Performing the Surveillance within 15 minutes before starting the idle recirculation pump. THERMAL POWER increase during single loop operation, or recirculation flow increase during single loop operation, provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start, power increase, or flow increase. An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.10.4 and SR 3.4.10.6 is to compare the temperatures of the operating recirculation loop and the idle loop. I FERMI - UNIT 2 B 3.4.10 - 7 Revision 10 07/09/99 .}}

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