ML20052C076: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot change
StriderTol Bot change
 
Line 14: Line 14:
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| page count = 6
| page count = 6
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter::   of Dresden Station Units 2 and 3 Proposed Changes to Operating Licenses DPR-19 and DPR-25 Technical Specifications.
{{#Wiki_filter::
Revised Page:   77 4015N
of Dresden Station Units 2 and 3 Proposed Changes to Operating Licenses DPR-19 and DPR-25 Technical Specifications.
Revised Page:
77 4015N
:20 5 04 0 SM
:20 5 04 0 SM


wi u .        . % ur          ~ ~ ~ ~            = = ' ' ~ * --                                                ~~~                        -
. :~..a xs:, :As.y.:a - 2 wi u.
                        . :~..a xs:, :As.y .:a -tw        2                                                                                                                                             . . .t.
. % ur
                                                                                                                                                                                              '      ~
= = ' ' ~ * --
DPR-19                                                                                               ~~7 i
~~~
                                                                                                                                                                                                          . t
.t.
:.5 !.!MITING CONDITION FOh OPERATION,                                 ,    ],         4.5 SURVEILLANCE REQUIREh!ENT                                                           h
~ ~ ~ ~
                                                                            '                                                                                                                                  7
tw
                                              .      containmcal cooling subsystem, both core                                                                                     '                            I spray subsysicms and both diesel gencr-                                                                                                 '
~
ators required for operation of such                                                                                                                     [;
DPR-19
components if no external source of -                                              -
~~7 i
t
:.5 !.!MITING CONDITION FOh OPERATION,
],
4.5 SURVEILLANCE REQUIREh!ENT h
7 containmcal cooling subsystem, both core I
spray subsysicms and both diesel gencr-
[
ators required for operation of such components if no external source of -
(
(
                                                    ' power were available, shall be operable.
' power were available, shall be operable.
f t
f t
: 4.       If the requirements of 3.5.B cannot be met                                                                                                                 !
4.
                      .                            , an orderly shutdown shall be initiated and                                                                                                                 i d
If the requirements of 3.5.B cannot be met
the reactor shall be in a Cold Shutdown                                                                                                                   '
, an orderly shutdown shall be initiated and i
condition within 24 hours.
d the reactor shall be in a Cold Shutdown condition within 24 hours.
p *                   .
p
C.              IIFCI Subsystem                                                       C. Surveillance of HPCI Subsystem shall be performed as follows:
* C.
: 1. Except as speclfled in 3.5.C.2 below.                             1.     IIPCI Subsystem Testing shall be as spect-                                         '
IIFCI Subsystem C.
the llPCI subsystem shall be operable                                 ' fled;hl 4.5. A.1.a, b, c, d, and f, except whenever the reactor pressure is greater                                 that the IIPCI pump shall deliver at least than 90 il sig and Irradiated fuel is in the                             5000 gpm against a system head correspond-
Surveillance of HPCI Subsystem shall be performed as follows:
                                                  . reactor vessel.                                  -
1.
Ing to a reactor vessel pressure of 1150 psig to 150 psig.
Except as speclfled in 3.5.C.2 below.
: 2.       From and after the date that the IIPCI                   .
1.
subsystem is made or found to be Inoper-                          2.          When it is determined that HPCI subsystem is inoperable, able for any reason, reactor operation is                                     the 1.PCI subsystem, both core spray subsystems, the auto-
IIPCI Subsystem Testing shall be as spect-the llPCI subsystem shall be operable
                                                                                                                                    "**i' P'***"'' '*li*f '"b'7'**** *"d th* * * '
' fled;hl 4.5. A.1.a, b, c, d, and f, except whenever the reactor pressure is greater that the IIPCI pump shall deliver at least than 90 l sig and Irradiated fuel is in the 5000 gpm against a system head correspond-i Ing to a reactor vessel pressure of 1150 psig
Pcrmissible only during the succeedlng               .
. reactor vessel.
isolation valves and shell side make-up system for the P''***d seven days unless such subsystem Is                                           isolation condenser system shall be demonstrated to be sooner made operabic. Provided that dur-                                     operable issnediately. The motor operated isolation valves Ing such scVCn days all aClive components                                     and shall side make-up system of the isolation condenser shall be demonstrated to be operable daily thereafter.
to 150 psig.
of the Automatic Pressure flelief Sub-                                       Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems, LPCI                                       syst== operability is not required provided that two subsystem. and Isolation cooling system
2.
                                                                                                            ~
From and after the date that the IIPCI 2.
f"d"**"     P""P' ''e oPuating at pown Inels abm 300 IGle; and one feedwater pump is operating as normally re-
When it is determined that HPCI subsystem is inoperable, subsystem is made or found to be Inoper-able for any reason, reactor operation is the 1.PCI subsystem, both core spray subsystems, the auto-
                                                . are operable.                                                                 quired with one additional feedwater pump operable at power levels less than 30016e.
"**i' P'***"'' '*li*f '"b'7'****
: 3.       If the requirements of 3.5.c canno,t be met l                         an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 90 psig within 24 Imurs.
*"d th* * * '
                                                                    ~.
P''***d Pcrmissible only during the succeedlng isolation valves and shell side make-up system for the seven days unless such subsystem Is isolation condenser system shall be demonstrated to be sooner made operabic. Provided that dur-operable issnediately. The motor operated isolation valves Ing such scVCn days all aClive components and shall side make-up system of the isolation condenser shall be demonstrated to be operable daily thereafter.
e
of the Automatic Pressure flelief Sub-Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems, LPCI
; .                                                                                                                                                                                    77
~
syst== operability is not required provided that two subsystem. and Isolation cooling system f"d"**"
P""P' ''e oPuating at pown Inels abm 300 IGle; and one feedwater pump is operating as normally re-are operable.
quired with one additional feedwater pump operable at power levels less than 30016e.
3.
If the requirements of 3.5.c canno,t be met l
an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 90 psig within 24 Imurs.
~.
e 77


                                                                                                                  ~
~..A nd
                                                      ~
~
                                                              ^ ' * '   #~
^ ' * '
    ,. . ,,      ~ . .A nd            .
#~
DPR-25 g                         -
~
DPR-25 g
4
4
                    ~3. , IJ38tTING CONDITION FOh OPEr4ATION                             4.5 SINtVEILLANCE REQUDtEntENT
~., IJ38tTING CONDITION FOh OPEr4ATION 4.5 SINtVEILLANCE REQUDtEntENT 3
* containment cooling subsystem, both core spray subsystems and both dicscl gener-                                                           '
containment cooling subsystem, both core spray subsystems and both dicscl gener-alors required fur operation of such components if no external source of power were available, shall be operable.
  .                          alors required fur operation of such components if no external source of power were available, shall be operable.
4.
: 4. If the requirements of 3.5.8 cannot be met                                                                                                                                     '
If the requirements of 3.5.8 cannot be met t
            ,                an orderly shutdown shall be initiated and                                                                                       .
an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours.
the reactor shall be in a Cold Shutdown                                                                       ,
C.
condition within 24 hours.
IIPCI 86 system C.
C. IIPCI 86 system                                             C. Servel!!ance of HPCI - ' ,.;^.;;;;; aball be performed as follows:
Servel!!ance of HPCI - ',.;^.;;;;; aball be performed as follows:
: 1. Escept as specified in 3.5.C.2 below,                     1.       HPCI Subsyslem Testing shall be as spect-the llPCI subsystem shall be operable                         ' fled:Isl 4.5. A. I.a b, c, d, and f, encept whenever the reactor pressure is greater                             that the IIPCI pump shall deliver at least than 90 psig and irradiated fuel is in the                         5000 gym against a system head correspond-
1.
                            . reactor vessel.
Escept as specified in 3.5.C.2 below, 1.
* Ing to a reactor vessel pressure of 1150 psig to 150 psig.
HPCI Subsyslem Testing shall be as spect-the llPCI subsystem shall be operable
: 2. From and alter the date that the llPCI subsydCm Is made or found to be Inoper-                   I*       When it is determined that HPCI subsystem is inoperable.
' fled:Isl 4.5. A. I.a b, c, d, and f, encept whenever the reactor pressure is greater that the IIPCI pump shall deliver at least than 90 psig and irradiated fuel is in the 5000 gym against a system head correspond-
able for any reason, reactor operation is permissible only during the succeeding              .
. reactor vessel.
                                                                                                    ,$, gf,,I,, *[ Cie7s$b         e[and           N 'oh a [
Ing to a reactor vessel pressure of 1150 psig to 150 psig.
isolation valves and shell side make-up system for the Seven days unless such subsystem is                                 isolation condenser system shall be demonstrated to be sooner made operabic, provided that dur-                             operable issediately. The motor operated isolation valves ing such seven days all active components                           *[i [1 $,"l"l]P
2.
                                                                                                          'h
From and alter the date that the llPCI subsydCm Is made or found to be Inoper-I*
                                                                                                                            '7'
When it is determined that HPCI subsystem is inoperable.
                                                                                                                                  ** *fg Q'y ''"y""'
able for any reason, reactor operation is
of the Automatic Pressure Relief Sub-                               Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems. LPCI                             system operability is not required provided that two subsystem, and Isolation cooling system                             feedwater pumps are operating at power levels above 300 We; and one feedwater pump as operating as normally re-are operable.                                                       quired with one additional feedwater pump operable at power levels less than 300 We,
,$, gf,,I *[ Cie7s$b e[and N 'oh a [
;                        3. If the requirements of 3.5.t: cannot be met an orderly shutdown shall be inittsted and the rea cor pressure shall be reduced to 90 psig within 24 hours.
permissible only during the succeeding isolation valves and shell side make-up system for the Seven days unless such subsystem is isolation condenser system shall be demonstrated to be sooner made operabic, provided that dur-operable issediately. The motor operated isolation valves ing such seven days all active components
*[i [1 $,"l"l]P
'7' ** *fg Q'y ''"y""'
'h of the Automatic Pressure Relief Sub-Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems. LPCI system operability is not required provided that two subsystem, and Isolation cooling system feedwater pumps are operating at power levels above 300 We; and one feedwater pump as operating as normally re-are operable.
quired with one additional feedwater pump operable at power levels less than 300 We, 3.
If the requirements of 3.5.t: cannot be met an orderly shutdown shall be inittsted and the rea cor pressure shall be reduced to 90 psig within 24 hours.
77
77
            *-~~^~~~' **           *;l
*-~~^~~~' **
*;l


='
='
Quad Cities Units 1 and 2 Proposed Changes to Operating License DPR-29 and DPR-30 Technical Specifications Revised Page:   3.5/4.5-5 4015N
Quad Cities Units 1 and 2 Proposed Changes to Operating License DPR-29 and DPR-30 Technical Specifications Revised Page:
3.5/4.5-5 4015N


                                                                              -- ~-
-- ~-
QUAD-C111ES DPR-29 I
QUAD-C111ES DPR-29
( f'
( f' I
                                .                                                      operable immediately. The RCIC provided that dwing such 7 days all                           system shall be demonstrated to active componess of the autcmatic                           be operable daily thereafter.
operable immediately. The RCIC provided that dwing such 7 days all system shall be demonstrated to active componess of the autcmatic be operable daily thereafter.
Daily demonstration of the pressure relief absystems, the core                                                 '*
Daily demonstration of the pressure relief absystems, the core spray subsystems LPCI mode of the
spray subsystems LPCI mode of the                             *"',[**$*p,C'*y'i,((f,,*hred
*"',[**$*p,C'*y'i,((f,,*hred
                                                                                        ,y RHR system.andthe RCIC system are                           provided that two feedwater pumps are operating at levels above 300 operable,                                                   MWe; and one feedwater purp is operating as normally required
,y RHR system.andthe RCIC system are provided that two feedwater pumps are operating at levels above 300
: 3. If the         niremets of SEcincation                         with one additional feedwater 3.5.C cannot be set. an orderly shut-                       pump operable at power levels down shall be in'siated. and the reac-                       less than 300 MWe.
: operable, MWe; and one feedwater purp is operating as normally required
sor pressure shalbe reduced to 90 psig withia 24 hours.                   -
: 3. If the niremets of SEcincation with one additional feedwater 3.5.C cannot be set. an orderly shut-pump operable at power levels down shall be in'siated. and the reac-less than 300 MWe.
D. Automatic Pressure RelietSubsystems                             D. Automatic Pressure Relief Subsystems
sor pressure shalbe reduced to 90 psig withia 24 hours.
    /               -
D. Automatic Pressure RelietSubsystems D. Automatic Pressure Relief Subsystems
/
Surveillance of the automatic pressure relief subsysteins shall be performed as follows:
Surveillance of the automatic pressure relief subsysteins shall be performed as follows:
: 1. The automatic pessure relief subsys.                       .l . The.following surveillance sem shall be opcable whenefer the                             shall be carried out on a resctor pressureis greaier than 90                             six-month surveillance psig, irradiated 6el is in the reactor                       interval:
: 1. The automatic pessure relief subsys.
vessel and prior to reactor startup from a cold condaion.
.l. The.following surveillance sem shall be opcable whenefer the shall be carried out on a resctor pressureis greaier than 90 six-month surveillance interval:
I(                 2. From and afterthedate that one of the a . With' the reactor at Pressure each relief Ave relief valves dithe automade pres.   -
psig, irradiated 6el is in the reactor vessel and prior to reactor startup from a cold condaion.
valve shall be manually sure reliersubsystan is made or found                             opened. Relief valve so be inoperable when the reactor is                             opening shall be verified pressurized aboveM psig with irradi.                             by a compensating turbine ated fuel in the rector vessel. reactor                           bypass valve or control operation is pernisible only during                               **1** *1**"'**
I(
a. With' the reactor at
: 2. From and afterthedate that one of the Pressure each relief Ave relief valves dithe automade pres.
valve shall be manually sure reliersubsystan is made or found opened. Relief valve so be inoperable when the reactor is opening shall be verified pressurized aboveM psig with irradi.
by a compensating turbine ated fuel in the rector vessel. reactor bypass valve or control operation is pernisible only during
**1** *1**"'**
the succeeding 7 days unless repairs
the succeeding 7 days unless repairs
                        . are made and prwided that during                           2. A logic system functional such time the RCI subsystem is                                 test shall be performed operable.                                                       each refueling outage.
. are made and prwided that during 2.
2.a Plant operation shall be                             3. A simulated automatic initiation in accordance with 3.5.D.2                             which opens all pilot valves above except that, for the
A logic system functional such time the RCI subsystem is test shall be performed operable.
                                                                                          "          performed each refueling u   e current operating cycle 5, four of the five relief                           4. When it is determined that one relief valves of the ADS are                                 valve of the automatic pressure relief required to be operable.                             subsystem is inoperable the HPCI In subsequent operating                               shall be demonstrated to be operable cycles, operation shall be                           immediately and weekly thereafter, in accordance with 3.5.D.2.
each refueling outage.
: 3.         If the requirements of Specifi-
2.a Plant operation shall be 3.
                          . cation 3.5.D cannot be met, an
A simulated automatic initiation in accordance with 3.5.D.2 which opens all pilot valves above except that, for the performed each refueling u
: k. > .
e current operating cycle 5, four of the five relief 4.
orderly shutdown shall be initiated and the reactor i                           pressure shall be reduced to l                           90 psig within 24 hours.
When it is determined that one relief valves of the ADS are valve of the automatic pressure relief required to be operable.
Amendment No. g 55                                               3.5/4.5-5
subsystem is inoperable the HPCI In subsequent operating shall be demonstrated to be operable cycles, operation shall be immediately and weekly thereafter, in accordance with 3.5.D.2.
                        -y+.m                       - - - - .
3.
If the requirements of Specifi-
: k. >.
. cation 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor i
pressure shall be reduced to l
90 psig within 24 hours.
Amendment No. g 55 3.5/4.5-5 m
-y+.m
+
+
---i..


e QUAD-CITIES DPR-30 provided that during such 7 days all                         operable immediately. The RCIC active components of the automatic                             system shall be demonstrated to Pressure relief subsystems, the core                           be operable daily thereafter.
e QUAD-CITIES DPR-30 provided that during such 7 days all operable immediately. The RCIC active components of the automatic system shall be demonstrated to Pressure relief subsystems, the core be operable daily thereafter.
oaily demonstration of the spray subsystems, LPCI mode of the                             automatic pressure relief sub-RHR system,and the RCIC system are                             system operabilty is not required operable.                                                     provided that two feedwater pumps are operating at levels above 300
oaily demonstration of the spray subsystems, LPCI mode of the automatic pressure relief sub-RHR system,and the RCIC system are system operabilty is not required operable.
: 3. If the requirements of Specification                             Mwer and one.feedwater pump is 3.5.C cannot he met, an orderly shut-down shall be initiated, and the reac-
provided that two feedwater pumps are operating at levels above 300
                                                                                          ,$*$9,as o jlQ     l
: 3. If the requirements of Specification Mwer and one.feedwater pump is 3.5.C cannot he met, an orderly shut-
                                                                                                                              ,o d pump operable at power levels for pressure shall be reduced to 90 psig                       less than 300 Mwe.                         ,
,$*$9,as o jlQ
,o d
l down shall be initiated, and the reac-pump operable at power levels for pressure shall be reduced to 90 psig less than 300 Mwe.
within 24 hours.
within 24 hours.
D. Automatic Preuvre Relief Subsystems                       D. Automatic Pressure Relief Subsystems
D. Automatic Preuvre Relief Subsystems D. Automatic Pressure Relief Subsystems
                                                            /
/
Surveillance of the automatic pressure relief sub.   ,
Surveillance of the automatic pressure relief sub.
systems shall be performed as follows:               ,
systems shall be performed as follows:
: l. The automatic pressure relief subsys-                       1. The following surveillance shall be canied tem shall be operable whenever the                             out on a 6 month surrveDlance interval:
: l. The automatic pressure relief subsys-1.
reactor pressure is greater than 90 psig, irradiated fuel is in the reactor vessel and prior to reactor startup from a cold condition.                                       a. With the reactor at pressure each
The following surveillance shall be canied tem shall be operable whenever the out on a 6 month surrveDlance interval:
(,  .
reactor pressure is greater than 90 psig, irradiated fuel is in the reactor vessel and prior to reactor startup from a cold condition.
With the reactor at pressure each a.
relief valve shall be manually opened.
relief valve shall be manually opened.
(,
Relief valve opening shall be verified by a compensating turbine bypass valve or con'.rol valve closure.
Relief valve opening shall be verified by a compensating turbine bypass valve or con'.rol valve closure.
: 2. A logic system functional test shall be performed each refueling outage.
2.
i
A logic system functional test shall be performed each refueling outage.
: 2. From and after the date that one of the                 3. A simulated automatic initlation five relief valves of the automatic pres-                       which opens all pilot valves
i 2.
* sure relief subsystem is made or found                         shall be performed each refueling outage.
From and after the date that one of the 3.
to be inoperable when the reactor is pressurized about 90 psig with irradi-                   4. When it is determined that one relief stad fuel in the reactor vessel, reactor                     valve of the automatic pressure relief operation is permissible only during the                     subsystem is inoperable, the HPCI shall
A simulated automatic initlation five relief valves of the automatic pres-which opens all pilot valves sure relief subsystem is made or found shall be performed each refueling outage.
                  ,      succeeding 7 days unless repairs are                         be demonstrated to be operable im-made and provided that during such time                       mediately and weekly thereafter.
to be inoperable when the reactor is pressurized about 90 psig with irradi-
: 4. When it is determined that one relief stad fuel in the reactor vessel, reactor valve of the automatic pressure relief operation is permissible only during the subsystem is inoperable, the HPCI shall succeeding 7 days unless repairs are be demonstrated to be operable im-made and provided that during such time mediately and weekly thereafter.
the HPCI subsystem is operable.
the HPCI subsystem is operable.
: 3. If the requirements of Specification 3.5.D cannot be met, an orderly shut-down shall b* initiated and the reactor pressure sha*, be reduced to 90 peig within *P' Nurs.
3.
If the requirements of Specification 3.5.D cannot be met, an orderly shut-down shall b* initiated and the reactor pressure sha*, be reduced to 90 peig within *P' Nurs.
1 1
1 1
3.5/45-5                                 Amendment 38 5/2/77 l
3.5/45-5 Amendment 38 5/2/77 l
l}}
l}}

Latest revision as of 07:51, 18 December 2024

Proposed Changes to Licenses DPR-19,DPR-25,DPR-29 & DPR-30 Re Surveillance Requirements to Test Automatic Pressure Relief Valves Daily When HPCI Subsystem Is Inoperable
ML20052C076
Person / Time
Site: Dresden, Quad Cities, 05000000
Issue date: 04/29/1982
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17194A643 List:
References
NUDOCS 8205040339
Download: ML20052C076 (6)


Text

of Dresden Station Units 2 and 3 Proposed Changes to Operating Licenses DPR-19 and DPR-25 Technical Specifications.

Revised Page:

77 4015N

20 5 04 0 SM

. :~..a xs:, :As.y.:a - 2 wi u.

. % ur

= = ' ' ~ * --

~~~

.t.

~ ~ ~ ~

tw

~

DPR-19

~~7 i

t

.5 !.!MITING CONDITION FOh OPERATION,

],

4.5 SURVEILLANCE REQUIREh!ENT h

7 containmcal cooling subsystem, both core I

spray subsysicms and both diesel gencr-

[

ators required for operation of such components if no external source of -

(

' power were available, shall be operable.

f t

4.

If the requirements of 3.5.B cannot be met

, an orderly shutdown shall be initiated and i

d the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

p

  • C.

IIFCI Subsystem C.

Surveillance of HPCI Subsystem shall be performed as follows:

1.

Except as speclfled in 3.5.C.2 below.

1.

IIPCI Subsystem Testing shall be as spect-the llPCI subsystem shall be operable

' fled;hl 4.5. A.1.a, b, c, d, and f, except whenever the reactor pressure is greater that the IIPCI pump shall deliver at least than 90 l sig and Irradiated fuel is in the 5000 gpm against a system head correspond-i Ing to a reactor vessel pressure of 1150 psig

. reactor vessel.

to 150 psig.

2.

From and after the date that the IIPCI 2.

When it is determined that HPCI subsystem is inoperable, subsystem is made or found to be Inoper-able for any reason, reactor operation is the 1.PCI subsystem, both core spray subsystems, the auto-

"**i' P'***" '*li*f '"b'7'****

  • "d th* * * '

P***d Pcrmissible only during the succeedlng isolation valves and shell side make-up system for the seven days unless such subsystem Is isolation condenser system shall be demonstrated to be sooner made operabic. Provided that dur-operable issnediately. The motor operated isolation valves Ing such scVCn days all aClive components and shall side make-up system of the isolation condenser shall be demonstrated to be operable daily thereafter.

of the Automatic Pressure flelief Sub-Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems, LPCI

~

syst== operability is not required provided that two subsystem. and Isolation cooling system f"d"**"

P""P' e oPuating at pown Inels abm 300 IGle; and one feedwater pump is operating as normally re-are operable.

quired with one additional feedwater pump operable at power levels less than 30016e.

3.

If the requirements of 3.5.c canno,t be met l

an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 90 psig within 24 Imurs.

~.

e 77

~..A nd

~

^ ' * '

  1. ~

~

DPR-25 g

4

~., IJ38tTING CONDITION FOh OPEr4ATION 4.5 SINtVEILLANCE REQUDtEntENT 3

containment cooling subsystem, both core spray subsystems and both dicscl gener-alors required fur operation of such components if no external source of power were available, shall be operable.

4.

If the requirements of 3.5.8 cannot be met t

an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C.

IIPCI 86 system C.

Servel!!ance of HPCI - ',.;^.;;;;; aball be performed as follows:

1.

Escept as specified in 3.5.C.2 below, 1.

HPCI Subsyslem Testing shall be as spect-the llPCI subsystem shall be operable

' fled:Isl 4.5. A. I.a b, c, d, and f, encept whenever the reactor pressure is greater that the IIPCI pump shall deliver at least than 90 psig and irradiated fuel is in the 5000 gym against a system head correspond-

. reactor vessel.

Ing to a reactor vessel pressure of 1150 psig to 150 psig.

2.

From and alter the date that the llPCI subsydCm Is made or found to be Inoper-I*

When it is determined that HPCI subsystem is inoperable.

able for any reason, reactor operation is

,$, gf,,I *[ Cie7s$b e[and N 'oh a [

permissible only during the succeeding isolation valves and shell side make-up system for the Seven days unless such subsystem is isolation condenser system shall be demonstrated to be sooner made operabic, provided that dur-operable issediately. The motor operated isolation valves ing such seven days all active components

  • [i [1 $,"l"l]P

'7' ** *fg Q'y "y""'

'h of the Automatic Pressure Relief Sub-Daily demonstration of the automatic pressure relief sub-system, the core spray subsystems. LPCI system operability is not required provided that two subsystem, and Isolation cooling system feedwater pumps are operating at power levels above 300 We; and one feedwater pump as operating as normally re-are operable.

quired with one additional feedwater pump operable at power levels less than 300 We, 3.

If the requirements of 3.5.t: cannot be met an orderly shutdown shall be inittsted and the rea cor pressure shall be reduced to 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

77

  • -~~^~~~' **
  • l

='

Quad Cities Units 1 and 2 Proposed Changes to Operating License DPR-29 and DPR-30 Technical Specifications Revised Page:

3.5/4.5-5 4015N

-- ~-

QUAD-C111ES DPR-29

( f' I

operable immediately. The RCIC provided that dwing such 7 days all system shall be demonstrated to active componess of the autcmatic be operable daily thereafter.

Daily demonstration of the pressure relief absystems, the core spray subsystems LPCI mode of the

  • "',[**$*p,C'*y'i,((f,,*hred

,y RHR system.andthe RCIC system are provided that two feedwater pumps are operating at levels above 300

operable, MWe; and one feedwater purp is operating as normally required
3. If the niremets of SEcincation with one additional feedwater 3.5.C cannot be set. an orderly shut-pump operable at power levels down shall be in'siated. and the reac-less than 300 MWe.

sor pressure shalbe reduced to 90 psig withia 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Automatic Pressure RelietSubsystems D. Automatic Pressure Relief Subsystems

/

Surveillance of the automatic pressure relief subsysteins shall be performed as follows:

1. The automatic pessure relief subsys.

.l. The.following surveillance sem shall be opcable whenefer the shall be carried out on a resctor pressureis greaier than 90 six-month surveillance interval:

psig, irradiated 6el is in the reactor vessel and prior to reactor startup from a cold condaion.

I(

a. With' the reactor at

2. From and afterthedate that one of the Pressure each relief Ave relief valves dithe automade pres.

valve shall be manually sure reliersubsystan is made or found opened. Relief valve so be inoperable when the reactor is opening shall be verified pressurized aboveM psig with irradi.

by a compensating turbine ated fuel in the rector vessel. reactor bypass valve or control operation is pernisible only during

    • 1** *1**"'**

the succeeding 7 days unless repairs

. are made and prwided that during 2.

A logic system functional such time the RCI subsystem is test shall be performed operable.

each refueling outage.

2.a Plant operation shall be 3.

A simulated automatic initiation in accordance with 3.5.D.2 which opens all pilot valves above except that, for the performed each refueling u

e current operating cycle 5, four of the five relief 4.

When it is determined that one relief valves of the ADS are valve of the automatic pressure relief required to be operable.

subsystem is inoperable the HPCI In subsequent operating shall be demonstrated to be operable cycles, operation shall be immediately and weekly thereafter, in accordance with 3.5.D.2.

3.

If the requirements of Specifi-

k. >.

. cation 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor i

pressure shall be reduced to l

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

Amendment No. g 55 3.5/4.5-5 m

-y+.m

+

+

---i..

e QUAD-CITIES DPR-30 provided that during such 7 days all operable immediately. The RCIC active components of the automatic system shall be demonstrated to Pressure relief subsystems, the core be operable daily thereafter.

oaily demonstration of the spray subsystems, LPCI mode of the automatic pressure relief sub-RHR system,and the RCIC system are system operabilty is not required operable.

provided that two feedwater pumps are operating at levels above 300

3. If the requirements of Specification Mwer and one.feedwater pump is 3.5.C cannot he met, an orderly shut-

,$*$9,as o jlQ

,o d

l down shall be initiated, and the reac-pump operable at power levels for pressure shall be reduced to 90 psig less than 300 Mwe.

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

D. Automatic Preuvre Relief Subsystems D. Automatic Pressure Relief Subsystems

/

Surveillance of the automatic pressure relief sub.

systems shall be performed as follows:

l. The automatic pressure relief subsys-1.

The following surveillance shall be canied tem shall be operable whenever the out on a 6 month surrveDlance interval:

reactor pressure is greater than 90 psig, irradiated fuel is in the reactor vessel and prior to reactor startup from a cold condition.

With the reactor at pressure each a.

relief valve shall be manually opened.

(,

Relief valve opening shall be verified by a compensating turbine bypass valve or con'.rol valve closure.

2.

A logic system functional test shall be performed each refueling outage.

i 2.

From and after the date that one of the 3.

A simulated automatic initlation five relief valves of the automatic pres-which opens all pilot valves sure relief subsystem is made or found shall be performed each refueling outage.

to be inoperable when the reactor is pressurized about 90 psig with irradi-

4. When it is determined that one relief stad fuel in the reactor vessel, reactor valve of the automatic pressure relief operation is permissible only during the subsystem is inoperable, the HPCI shall succeeding 7 days unless repairs are be demonstrated to be operable im-made and provided that during such time mediately and weekly thereafter.

the HPCI subsystem is operable.

3.

If the requirements of Specification 3.5.D cannot be met, an orderly shut-down shall b* initiated and the reactor pressure sha*, be reduced to 90 peig within *P' Nurs.

1 1

3.5/45-5 Amendment 38 5/2/77 l

l