ML20210E211
| ML20210E211 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/31/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20210E187 | List: |
| References | |
| PROC-861231-04, NUDOCS 8702100251 | |
| Download: ML20210E211 (167) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
QGA 000-1 Revistoh 2 TABLE OF CONTENTS December 1986 000 Table of Contents 00 QGA Manual Preface O General Abnormal Procedures 100 Reactor Pressure Vessel 200 Primary Containment 300 Secondary Containment 5
400 Radiation Release 500 Special Contingency Procedures 1000 QGA Procedure Flowcharts Preface 1100 Reactor Pressure Vessel Flowcharts 1200 Primary Containment Flowcharts 1300 SecondaryContainmentF1hwcharts 1400 Radiation Release Flowcharts 1500 Special Contingency Procedures Flowcharts APPROVED DEC121986 g
~
Q.C.O.S.R.
(final) 1/00579
.\\-
I 8702100251 870204 PDR P
ADOCK 05000254 I
I OGA-00 I
Revision 3 October 1985 QGA MANUAL PREFACE The QGA book contains symptom oriented procedures for dealing with abnormal I
operational events.
The procedures do not deal with specific events, but instead try to address control of certain key plant parameters.
The procedures are divided into blocks by the plant equipment to be monitored.
The blocks are as follows:
I QGA 00 Introduction QGA 100 Reactor Pressure Vessel I
QGA 200 Primary Containment QGA 300 Secondary Containment QGA 400 Radiation P.elease QGA 500 Special Contingency Procedures f
These procedures are designed to be executed concurrently.
The operator is I
expected to monitor and maintain all key plant parameters within safe limits, j
i and this involves performing several tasks concurrently.
In addition to these procedures, certain QOA procedures may be required to be executed to deal wttn events as they occur.
Examples of this are loss of power to equipment, trips of equipment, and failure of equipment.
These procedures will need to be Identified as applicable from conditions encountered during abnormal operation, and will not always be referenced directly in the QGA procedures.
i There are seven general cautions which apply at all times when using the QGA procedures.
These cautions are listed here.
Since they do not always apoly to specific steps, they will not be listed in individual procedures.
j CAUTION #1 If an entry condition for a QGA procedure occurs, enter that procedure irrespective of whether that procedure l
has already been executed or is presently being executed. When it is determined that an emergency no longer exists, enter QGP 2-3, Reactor Scram, if a scram has occurred.
If no scram I
has occurred, return to normal plant operation.
APPROVED g
OCT 311985 1/0008g O. C. O. S. R.
QGA 00 Reetston 3 CAUTION #2 Whenever RHR is in the LPCI mode, inject through the heat exchangers as
'I soon as possible.
b L
CAUTION #3 I
Suppression pool temperature is determined by averaging the channel A
[
and channel B temperatures of recorder
[
1602-8 on panel 901-21 (902-21).
If j
these temperatures are not available, t
use the average of point 9 on
[
recorders 1640-200 A and 8.
l I
Orywell temperature is determined by reading the following sensors.
The sensors are listed in order of a
prefered use.
Process computer point C166 (C266)
Process computer point C165 (C265)
Valve Leak Recorder 260-20 pt 18 Valve Leak Recorder 260-20 pt 19 Orywell Environs Indicator 5741-170 pt 36 Orywell Environs Recorder 5741-130 pt 32 I
I APPROVED OCT 311985 l
"o Sa y
,,000,,
2-
QGA 00 Revision 3 CAUTION #4 Whenever_ drywell temperature either:
a.
exceeds the temperature in I
the table AND the instrument reads below the indicated level in the table, I
or, b.
exceeds the RPV saturation temperature.
THEN that instrument may not be used to determine RPV water level.
Orywell Indication RPV water Temperature Level Level Instrument I
169'F
-37 in Yarway Narrow Range (-60 to +60 in) 170*F
+63 in GEMAC Upper 400 Ranga ( 42 to +358 in) lE 361*F
-309 in GEMAC Lower 400 Range (-334 to +66 in)
E 548'F
-242 in Yarway Wide Range (-243 to +57 in) 548'F
+44 in GEMAC Narrow Range (0 to 60 in) lI CAUTION #5 Yarway level indicated levels are not reliable during rapid RPV depressurization below 500 psig.
For these conditions, utilize the GEMAC instruments to monitor RPV water level.
CAUTION #6 If signals of high suppression pool water level (+5 in) or low CCST water level (10,000 gal) occur, confirm automatic transfer of, or manually transfer HPCI and RCIC suct!cn from the CCST to the suppression pool.
I APPROVED OCT 311985 1/0008g 0. C. O. S. R.
'l I
QGA 00 Revision 3 I
CAUTION #7 Observe NPSH requirements for pumps taking suction from the suppression pool.
Enter torus press and level on (A) and (c), draw Itne between the two l
points, determine required head on (8).
Enter torus water temp and required head on (E) and (F), draw line be-tween the two points, determine Max.
Section Flow on (D).
III NAI pf atoutRID TURUs tenus (D)
(A) ratssunt sucten 6 (E) st:cTtcw vArta "EA D mr. E trstc)
(sPn)
(FT.)
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soon
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.. s APPROVED OCT 311985 (final) 1/0008g Q.C.O.S.R.
I
QGA-0 Revision 61 GENERAL ABNORMAL PROCEDURES October 1985 l
OGA-0 General Abnormal Procedures Rev. 61 10-31-85 OGA-1 Procedure Deleted Rev. 25 10-31-85 OGA-2 Procedure Deleted (See QOA 201-1)
Rev. 6 05-10-82 OGA-3 Procedure Deleted Rev. 10 10-31-85 OGA 4 Procedure Deleted (See QOA 201-8)
Rev. 4 05-10-82 OGA-5 Procedure Deleted (See 00A 201-9)
Rev. 5 05-10-82 OGA-6 Procedure Deleted Rev. 8 10-31-85 OGA '
Procedure Deleted (See QOA 400-1)
Rev. 5 05-10-82 OGA-8 Procedure Deleted (See QOA 202-4)
Rev. 10 05-10-82 OGA-9 Procedure Deleted (See QOA 202-5)
Rev. 3 05 10-82 OGA-10 Procedure Deleted (See QOA 5600-4)
Rev. 7 05-10-82 OGA-11 Procedure Deleted (See Q0A 5600-5)
Rev. 8 05-10-82 OGA-12 Procedure Deleted (See QOA 6100-3)
Rev. 15 10-31-85 OGA-13 Procedure Deleted (See QOA 1800-1)
Rev. 3 05-10-82 OGA-14 Procedure Deleted (See QOA 1800-2)
Rev. 3 05-10-82 OGA-15 Procedure Deleted (See QOA 1800-3)
Rev. '
05-10-82 APPROVED OCT 311985 2/0:0ir
_i.
l Q.C.O.S.R.
Revision 61 OGA-16 Procedure Deleted (See Q0A 1700-7)
Rev. 4 10-31-85 l
OGA-17 Rev. 10 10-31-85 Procedure Deleted OGA-18 Procedure Deleted (See 00A 3200-2)
Rev. 7 05-10-82 OGA-19 Procedure Deleted Rev. 3 10-31-85 OGA-20 Procedure Deleted (See QOA 6100-4)
Rev. 8 10-31-85 OGA-21 Procedure Deleted (See QOA 6900-7)
Rev. 2 10-31-85 OGA-Tl Procedure Deleted Rev. 3 10-31-85 I
I APPROVED l
OCT 311985 (final)
Q.C.O.S.R.
2/0101I I I
QGA 100-0 Revision 1 October 1985 REACTOR PRESSURE VESSEL 100-0 Reactor Pressure Vessel Rev. I 10-31-85 100-1 Reactor Pressure Vessel Water Level Control Rev. I 10-31-85 I
100-2 Reactor Pressure Vessel Pressure Control Rev. 1 10-31-85 100-3 Reactor Power Control Rev. 1 10-31-85 100-T1 Initiating Conditions for Automatic Scram Rev. 1 10-31-85 100-T2 Initiating Conditions for Group I Automatic Isolation Rev. I 10-31-85 100-T3 Initiating Conditions for Group II Automatic Ioslation Rev. I 10-31-85 100-T4 Initiating Cor.ditions for Emergency l
Olesel Generator Automatic Start Rev. I 10-31-85 100-T5 Initiating Conditions for Emergency Core Cooling Systems Automatic Start Rev. I 10-31-85 100-F1 l
Heat Capacity Temperature Limit (HCTL)
Rev. I 10-31-85 100-F2 Suppression Pool Load Limit Rev. I 10-31-85 ll
\\
APPROVED OCT 311985 (fina1)
O. C. O. S. R.
8/0543I t
QGA 100-1 Revision 1 I
October 1985 O
REACTOR PRESSURE VESSEL WATER LEVEL CONTROL A.
ENTRY CON 0!TIONS Entry into this procedure is required whenever any of the following condtetons occur:
RPV water level below +8 in.
RPV pressure above 1060 psig Orywell pressure above 2.0 psig
~ A conditions which requires a reactor scram and, following the automatic scran condition or manual scram initiation, reactor power is above 37. or cannot be determined.
(Refer to QGA 100-71, Initiating Condttions for Automatic Reactor Scram.)
Reentry into this procedure is required whenever an additional entry condition occurs, and whenever an entry condition clears and re-occurs.
IO 1i I
I I
I l
OCT 311985 1/0037g 0. C. O. S. R.
l I
I
OGA 100-1 Revisten 1 i
I I
I I
THIS PAGE INTENTIONALLY BLANK I
I l
I I
I I
APPROVED g
OCT 311985 0.c.o.S. R.
l 1/00379 I-
QGA 100-1 Revision 1 i
B.
OPERATOR ACTIONS 1.
If a reactor scram has not been initiated.
I THEN initiate a reactor scram.
2.
Place the reactor mode switch in SHUTDONN.
3.
Execute this procedure concurrently with the following procedures:
QGA 100-2, Reactor Pressure Vessel Pressure Control QGA 100-3, Reactor Power Control 4.
Confirm initiation of the following, consistent with the initiation conditions which are present; initiate those which should have initiated but did not.
Group I isolation (refer to QGA 100-T2, Initiating Conditions for Automatic Group I Isolation)
Group II isolation (refer to QGA 100-T3, Initiating Conditions for Automatic Group I Isolation)
Group III isolation (Iow RPV water level RWCU isolation)
Emergency diesel generator initiation (refer to QGA 100-T4, Initiating Conditions for Emergency Diesel Generator I
Automatic Start)
Emergency core cooling system automatic initiation (refer to I
g lE QGA I
-T5, Initiating Conditions for Emergency Core Cooling Systems Automatic Start)
I I
I APPROVED OCT 311985 I
1/0037g o.c.o.S.R.
I
QGA 100-1 Revision 1 l~EhIliixicutIngitipi5indi:~~~~~~~-~-~~~~--l*
l
_If_
Anycontrolrodisnotinsertedtoorbeyondpositionl*
04, l
THEN exit this procedure and enter QGA 500-7, Reactor l*
Power / Level Control.
I I**
IF RPV water level cannot be determined.
l TiiEN RPV FLOODING IS REQUIRED; exit this procedure and l*
enter QGA 500-6, Reactor Pressure Vessel Flooding.
I I*
IF a high drywell pressure ECCS automatic initiation l
signal (+2.0 psig) occurs or exists while l*
depressurizing the reactor pressure vessel, l THEN before reactor pressure vessel pressure decreases to l*
325 psig, prevent injection from those core spray l
and RHR pumps not required to assure adequate core l*
cooling.
l WHEN the high drywell pressure ECCS automatic l*
initiation signal clears, l
THEN restorecoresprayandRHRtoAUTOMATIC/ STANDBY l*
mode.
I APPROVED OCT31135 1/00379
-4 I
QGA 100-1 Revision 1
- 5.
Restore and maintain RPV water level between +8 in. and +48 in, with one or more of the following systems:
0 erat 1Eg-T RPV Preisuri RaEge - -l
_ _ _ System _ _ _ _ _ _ _ _l_ Procedure _ _ T _for_ System Ope _ratj,on _l l_ Condensate /Feedwater QOP 3300-2 1350-0 psig lRCIC-Butdonotoperate l
l l
turbine below 2200 rpm QOP 1300-2 1150-50 psig l
l l
l HPCI-But do not operate QOP 2300-6 1150-100 psig l
turbine below 2200 rpm l l
l unless aux. oli pump l
1s running l
l l
lSafeShutdownPump lQOP2900-2 l
1150-0 psig l
lCR0 lQOP300-16 l
1500-0 psig l
lLPCImodeofRHR lQ0A1000-7 l
325-0 psig l
lCoreSpray lQOA1400-2 l
325-0 psig l
l_______________I_______1____________l I
6.
IF RPV water level cannot be restored and maintained above + 8 in.,
THEN maintain RPV water level above -143 in. (TAF).
a.
IF RPV water level can be maintained above -143 in.,
I THEN prevent automatic RPV depressurization by placing the AUTO BLOWDOWN INHIBIT switch to the " INHIBIT" position.
l l
b.
IF RPV water level cannot be maintained above -143 in.,
THEN exit this procedure and enter QGA 500-1 Level i
Restoration.
7.
WHEN QGP 2-3, Reactor Scram, is entered from QGA 100-2, Reactor Pressure Vessel Pressure Control,
,I THEN exit this procedure and proceed in accordance with QGP 2-3, Reactor Scram.
l lI APPROVED (final)
OCT 312 I
1/00379 O.C.O.S.R.
QGA 100-2 Revision 1 October 1985 REACTOR PRESSURE VESSEL PRESSURE CONTROL A.
ENTRY CONDITIONS Entry to this procedure is required as specified in QGA 100-1, Reactor Pressure Vessel Water Level Control.
i I
1 l
lI I
APPROVED OCT 311985 l
i/00389
.i.
o.c.o. s. a.
QGA 100-2 Reviston 1 l~WKtTe~execuilEg~siois~ltErough4?-~l*
~
~
l~~l((Te_e_xe_cu_tingsteps2through4:____________l" lE Emergency RPV Wh1 Oepressurization l
15 anticipated.
l THEN rapidly depressurize l Do not depressurize the RPV below l**
l the RPV with the main l
100 psig turbine bypass valves.
lUNLESS motor drive pumps l**
l Cooldown rates above l
sufficient to assure 100*F/hr may occur as l
adequate core cooling l"
l a result of executing l
are running and available this step.
l for injection.
l**
l l
E Emergency RPV lE suppression pool l"
Depressurization is l
temperature cannot be l
- required, l
maintained below the Heat l**
THEN exit this procedure l
Capacity Temperature and enter QGA 500-2, l
Limit (QGA 100-F1),
l**
l Emergency RPV l
THEN maintain RPV pressure Ospressurization.
l below the Limit.
l" l~~~~~~~~~~~~~~~l lE suppression pool water l**
level cannot be maintained l
below the Suppression l"
Pool Load Limit.
l (QGA 100-F2),
l**
THEN maintain RPV pressure l
below the Limit.
l ".
LF Boron Injection is required.
l ANO the following condttions exist:
l" Hain condenser available
=
No indication of gross fuel failure l'
l No indication of a steam line break l THEN open the HSIVs and reestablish the main condenser as a heat sink l"
IF low low RPV water level MSIV isolation intericcks must be l
bypassed to accomplish this steD.
I"
~
THEN install jumpers in accordance wtth QGA 500-T1.
l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l
=,,,, =,,,.
-r 2,,,,,T,,.
-i mi -
- =::,"~~
gemmir APPROVED
=
= n. - g dm = m.g
=m a
.c. y'l gx qfgM %g 1
I
-.i "M
0CT 311985 e : r.:=. E g" EEE.... - =F. w. aie
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,,m o
h ~~~ b![$".:":"'
I*
M O. C. O. S. R.
i p
t Lj r{u[T i
- '.::.l::::::::,="*"""::"
,, :::::::;".*"**"t:::::::
J.:".==4
,I l
==*:
i i,
L
"*~~~~: = =4
- E. n2 1/0038g l
QGA 100-2 Revision 1 1
8.
OPERATOR ACTIONS 1.
IF any ADS valve is cycling, TEEN open AOS valves until RPV pressure drops to 940 psig.
l 2.
Control RPV pressure between 1060 psig and 940 psig with the main l
IF the MSIVs are closed, f
IE0 no Group I automatic isolation condition exists (refer to QGA 100-T2, Initiating Conditions for Automatic Group I I
Isolation,),
AND the main condenser is available.
AND no indication of gross fuel failure exists, I
AND there has been no indication of a steam Itne break, THEN reopen the HSIV1 per QOP 250-1, Pressurizing the Main Steam I
Lines Following a Group I Primary Containment Isolation.
RPV pressure control may be augmented by one or more of the Il l
following systems:
l~_T_-[Buttdonotoperate[ [ ~_Sisje5
[ [ [ [l~ 5piritini fricidiri ((
~-
I HPC QOP 2300-3 E
!E I
tur$'a' b
" 2200 rpm i
l unless aux. oil pump s
l l
ts running.
l l
l RCIC - But do not operate l
QOP 1300-2 l
turbine below 2200 rpm.
I l
1 I
g lSteamjetairejectors l
N/A l
l Main steam line drains l
N/A l
l A05 - BUT ONLY IF l
00A 201-10 l
Il Valves suppression pool water l
1evel 1s above 5 ft l
l l RWCU - in normal rectre-l N/A l
ulation mode, l
BUT ONLY IF no l
l I
boron has been l
Injected into the l
l RPV l
l I
RWCU - in blowdown mode, QOP 1200-7 l
BUT ONLY IF no l
l APPROVED Il boron nas been l
Injected into the l
l OCT 311985
- 0. C. O. S. R.
l l............l 1/00389 II
Revision 1 l Wh1Te_ executing steps 3 and 4:------- ----------------------
l' IF the reactor is not shut down, l*
l THEN return to step 2 of this procedure l
l' IF required to:
Conserve RPV water inventory
\\*
l ~~
Protect primary containment integrity Limit radioactive release to the environment l*
l THEN a cooldown rate exceeding 100*F/hr may be used.
Do not depressurize the RPV below 100 psig l UNLESS motor driven pumps sufficient to assure adequate core cooling I
are running and available for injection i
I Emergency RPV Depressurization is anticipated.
lETHEN rapidly depressurize the RPV with the main turbine bypass valves.1 Cooldown rates above 100*F/hr may occur as a result of executing l
this steD.
l l5E0 Boron Injection is required, l
IF the following conditions exist:
main condenser available l
l no indication of gross fuel failure no indication of a steam line break l
l THEN open the MSIVs and reestablish the main condenser as a heat sink.
l IF low low RPV water level MSIV isolation interlocks must be i
bypassed to accomplish the step above, l
THEN instill jumpers in accordance with QGA 500-71.
l lE suppression pool temperature cannot be maintained below I
the Heat Capacity Temperature Limit (QGA 100-FI),
l THEN maintain RPV pressure below the Limit.
l lE suppression pool water level cannet be maintained below I
the Suppression Pool Load Limit (QGA 100-F2),
l THEN maintain RPV pressure below the Limit.
l lE Emergency RPV Depressurization is required, I
THEN exit this procedure and enter QGA 500-2, Emergency Reactor l
Pressure Vessel Depressurization.
l
~ m::'r na~::
2~
=.a.~:.:.
, " i'
!:Jg g " EE ::=!:
ihmt#j APPROVED EEx.!:::.-,, O:"m.- y' 0CT31155
=
%sm =,=,'
I.
o iihi EE.-~5E 8-d I- !EEE5iEE:=n:-
fa 1
! JWW]gj
'F E!
1 0.c.o.
E@B:gE!iG:::.~~~s, d
I=
n 1
l j,.[y
- -- Esinn '.d:
~~
f
- et-===. :.=:::..5 a
n n
m,
_x ;
,x ;
1/0038g
-4 I
QGA 100-1 Revision 1 I
- 3.
WHEN any one of the following conditions has been established:
All control rods are inserted to or beyond position 04, or 537 pounds of boron have been injected into the RPV (a change of 70% in S8LC tank level), or The reactor is shutdown and will remain shutdown as determined by a Quallfled Nuclear Engineer.
THEN depressurize the RPV and maintain cooldown rate below 100*F/hr.
4.
WHEN the RHR shutdown cooling interlocks clear, t
flRR initiate the shutdown cooling mode of RHR in accordance with
! g
- g QOP 1000-5, Shutdown Cooling Startup and Operation.
I F, RHR shutdown cooling cannot be established and further I
cooldown is required, THEN continue to cool down using one or more of the systems used for depressurization (listed in step 2).
5.
Exit this procedure and proceed in accordance with QGP 2-3 Reactor Scram.
I I
I I
APPROVED OCT 31 M
- 0. C. O. S. R.
(final) 1/00389 I
QGA 100_3 Revision 1 October 1985 REACTOR POWER CONTROL A.
ENTRY CONDITIONS Entry to this procedure is required as specified in QGA 100-1. Reactor Pressure Vessel Water Level Control.
I I
I I
'O I
I I
I I
I I
APPROVED 10 octatises O. C. O. S. R.
1/0039g
_1_
I
QGA 100-3 Revision 1 l HEITe eiecuiiRg tRii procedure: --l-l~IF all control rods are inserted to l*
=
or beyond position 04,
~
l THEN terminate boron injection; l**
exit this procedure and enter l
QGP 2-3, Reactor Scram.
l*
l If the reactor is shutdown, l*
AND no boron has been injected l
into the RPV, l**
THEN exit this procedure and enter l
QGP 2-3, Reactor Scram.
l*
,_ _ _ _ _ _ip the main turbine - generator
- Do not tr lifreactorpowerisabove3%. Maintain l*
g on-line as long as possible to provide l
l4heatsinkforreactorpower. Control l**
RPV water level transient following the l tripping of the recirculation pumps to l*
prevent a turbine trip on high level.
l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ l' I
I III IIII APPROVED OCT 311985 o.c.0.S. R.
1/00399 I
QGA 100-3 Revision 1 I
8.
OPERATOR ACTIONS
- 1.
IF the turbine generator is on-line, AE0 the HSIVs are open, TiilN confirm or initiate recirculation flow runback to minimum pump I
speed.
2.
IF reactor power is above 3% or cannot be determined, MEN trip both recirculation pumps.
3.
Execute steps 4 and 5 concurrently.
4.
Insert control rods as follows:
a.
Arm and depress the ARI (ATHS) pushbuttons.
I
(
b.
[F, any scram valve is not open, THEN (1) Remove fuses:
590-715 A. C, E, and G (Panel 901-15) 590-715 8 O, F, and H (Panel 901-17)
(2) Vent scram air header:
Close valves 301-147A and B (scram air header filter inlets).
Open valve RV-4710 (scram air header relief valve).
WHEN control rods are not moving inward, THEN (1) Replace fuses:
590-715 A, C, E, and G (Panel 901-15) 590-715 8, 0, F, and H (Panel 901-17)
(2)
Restore scram air header:
Close valve RV-4710 (scram air header I
relief valve).
Open valves 301-147 A and 8 (scram air I
header filter inlets),
c.
Reset the reactor scram.
IF the reactor scram cannot be reset.
MEN continue at step 4j.
d.
Orain the scram discharge volume.
e.
Verify open valve 301-25 (HCU accumulator charging water header. valve).
APPROVED OCT 311965 1/0039g ggg
QGA 100_3 Revision 1 Y
lWstTeeliecuitsgtstiproceduri:----~l l ~IF all control rods are inserted to l
or beyond position 04, l THEN terminate boron injection; l
exit this procedure and enter l
QGP 2-3, Reactor Scram.
l 4
lE the reactor is shutdown, l
no boron has been injected l 90 Into the RPV, l
THEN ex!t this procedure and enter l
QGP 2-3, Reactor Scram.
l While executing steps 4j (1) through l4j(4):
l*,
lE the reactor scram can be reset, l**
ANO control rods moved inward l
following the last scram l*
g THEN reset the reactor scram, l
l ANO return to step 4d of this l*
procedure l--_-------------._l gl e
AP' ROVED OC 311985 g
O. C. O. S. R.
6 l]
1/00399 4
I:
OGA 100-3 f
E Revision 1 g
i f.
Initiate a reactor scram.
E control rods moved inward.
THEN return to step 4c.
g.
Reset the reactor scram.
I E
the reactor scram cannot be reset, THEN continue at step 4j.
s h.
Drain the scram discharge volume.
I i
1.
Individually open the scram test switches located on panel 901-16 (902-16) for control rods not inserted to or beyond l
position 04.
WHEN a control rod is not moving inward, THEN close its scram test switch.
- j.
Manually insert control rods as follows:
(1)
Start both CRD pumps.
I E
no CR0 pump can be started, THEN start both CR0 pumps on the unaffected unit and open the CRD crosstle valves.
E no CRD pump can be started, and the unaffected unit's CR0 system is unavailable.
THEN continue in this procedure at step 4j (4).
(2)
Close valve 301-25 (HCU accumulator charging water header valve).
(3)
Rapidly insert control rods manually.
E the rod worth minimizer blocks rod motion, THEN bypass the rod worth minimizer by placing the RHH lgg key switch to BYPASS.
(4)
E any control rod cannot be inserted to or beyond position 04, THEN Individually direct the effluent from valve 301-119 (CR0 withdraw line vent valve) to a contained radwaste drain and open valve 301-119 lI for that control rod UNTIL the rod stops moving in.
WHEN a control rod is not moving inward.
THEN close valve 301-119 for that control rod.
APPROVED 1/00399 0.C. O. S. R.
OGA 100-3 Reelslon 1 d
[ HRtTe~e ecuilig tRti Ereciduri:- - - ~ j l~IF all control rods are inserted to l
or beyond position 04,
) THEN terminate boron injection; l
exit this procedure and enter l
QGP 2-3, Reactor Scram.
l lIf the reactor 15 shutdown, l
ANO no boron has been injected l
Into the RPV, l
THEN exit this procedure and enter l
QGP 2-3, Reactor Scram.
l eIt
,i E
- . PROVED E
U 3U985 g
@l 0.C. O. S. R.
1 I/0039g I
wea iw-a Reelston 1 5.
IF the reactor cannot be shutdown before suppress 1Cn pool temperature reaches 110'F,
'~
I THEN BORON INJECTION IS REQUIRED:
Inject boron into the RPV with 58LC and place the Auto Blowdown Inhibit keylock switch in the INHIBIT position, I
a.
IF boron cannot be injected with SBLC, MEN inject boron into the RPV using the RWCU system in accordance with QGA 500-8, Boron Injection with Reactor I
Hater Cleanup.
b.
IF boron is not being injected into the RPV by RWCU, MEN confirm automatic isolation or manually isolate RWCU.
c.
Continue injecting boron into the RPV untti 537 pounds of
,I boron have been injected.
(This is a change of 70% in tank level if sodium pentaborate concentration is 9.7%.
Refer to QGA 500-T3, Boron Injection Weight, for computing the weight of boron injected for a different concentration.)
Manually trip SBLC pumps before tank level reaches 0%.
6.
Exit this procedure and enter procedure QGP 2-3, Reactor Scram.
I
.I L
p APPROVED l
00T 311985 o.c.o.s.a.
(final) 1/0039g !
I
\\
I QGA 100-T1 Revision 1 October 1985 INITIATING CONDITIONS FOR AUTOMATIC REACTOR SCRAM The following conditions cause an automatic initiation of a reactor scram.
1.
Mode switch in SHUT 00HN (auto reset after 10 seconds) 2.
Manual scram buttons (depressed) 3.
APRM high flux (Flow biased) (RUN Mode) 4.
APRM inoperative 5.
APRM downscale with companion IRM high (RUN Mode) 6.
APRM high flux (15%) (Bypassed in RUN mode) 7.
IRM h!gh flux (120/125) (Bypassed in RUN mode) 8.
High reactor pressure (1060 pstg) 9.
High drywell pressure (+2.0 psig) l 10.
Low reactor water level (+8 in.)
11.
High scram discharge volume water level 12.
Low turbine condenser vacuum (21 in. Hg) (RUN mode) 13.
High main steam line radiation (7 x normal full pcwer background) 14.
MSIV closure (RUN mode) 15.
Turbine control valve fast closure (RUN Mode > 45% rated steam flow) 16.
Turbine stop valve closure (RUN Mode > 45% rated steam flow) 17.
Low EHC fluid pressure (900 psig) (RUN Mode > 45% rated steam flow) la.
IRM inoperative l
19.
SRM high flux (5 x 105 cps) (Bypassed when shorting links u
installed) l APPROVED OCT 311985 l
C II"'I]
O.C. O. S. R.
1/0030g I
QGA 100-T2 Revision 1 October 1985 INITIATING ONDITIONS FOR GROUP I C
AUTOMATIC ISOLATION The following conditions cause an automatic initiation of a Group I isolation:
1.
Low low reactor vessel water level (-59 in.)
2.
Low main steam line pressure with mode switch in RUN (825 psig) 3.
High main steam line radiation (7X normal full power background) l 4.
High main steam line flow (140% of rated flow) j 5.
High main steam tunnel temperature (200*F) l The following valves close on a Group I isolation:
1.
Main steam isolation.
Inboard MSIV's A0-203-1A, IB, 1C 10 Outboard MSIV's A0-203-2A, 28, 2C, 20 Main steam line drains MO-220-1,2 2.
Sampling.
Rectrc. Sample valves A0-220-44, 45 I
I AP. PROVED OCT 311985 (final)
O. C. O. S. R.
l
I QGA 100-T3 Revision 1 I
October 1985 INITIATING CONDITIONS FOR GROUP II AUTOMATIC ISOLATION The following conditions cause an automatic initiation of a Group II isolation.
1.
Low reactor water level (+8 in.)
2.
High drywell pressure (+2.0 psig) 3.
High drywell radiation (2000 R/hr)
The following valves close on a Group II isolation:
1.
RHR.
RHR discharge to radwaste MO-1001-20,21 Shutdown cooling supply MO-1001-47,50 i
Head spray valves MO-1001-60,63 2.
Pressure suppressten.
l Orywell purge valve A0-1601-21 l
Vent valve A0-1601-22 Orywell vent valve A0-1601-23 l
Vent to R.B. exhaust A0-1601-24 Nitrogen purge A0-1601-55 Torus purge valve A0-1601-56 Makeup valve MO-1601-57 Torus makeup valve A0-1601-58 Orywell makeup valve A0-1601-59 Torus vent valve A0-1601-60 l
Torus 2-inch vent relief A0-1601-61 Orywell 2-inch vent relief A0-1601-62 Vent to SBGTS A0-1601-63 l
Orywell pneumatic supply isolation A0-4720, 4721 1
3.
Radwaste.
Drywell floor drain discharge A0-2001-3,4 Drywell equipment drain discharge A0-2001-15,16 4.
Oxygen analyzer.
02 analyzer. valves A0-8801 A,B,C,0 A0-8802 A,B,C,0 A0-8803 A0-8804 APPROVED OCT 311985 1/0028g 0. C. O. S. R.
QGA 100-?3 Reelston 1 I
5.
Traversing Incore Probe (TIP).
On Group II, the TIP Ball valve 700-733 detector is withdrawn if in use, 5 ball valves and itp purge valve 700-743 I
one nitrogen purge valve are closed.
I I
I I
I I
I I
I I
I I
~
APPROVED l
OCT 311985 (f1nal) 0.C. O. S. R.
1/00289 I
I QGA 100-T4 Revision 1 October 1985 INITIATING CONDITIONS FOR EMERGENCY DIESEL GENERATOR AUTOMATIC START The following conditions cause an automatic start of the appropriate diesel generator.
1.
Low low reactor vessel water level (-59 in.)
2.
High drywell pressure (+2.0 psig) 3.
Undervoltage on Bus 13-1, 14-1, (23-1, 24-1) 4.
Undervoltage on Bus 13, 14, (23, 24) 5.
Feed breaker open to Bus 13-1, 14-1, (23-1, 24-1) 6.
Both feed breakers open to Bus 14 (24) 7.
Second level undervoltage for 5 minutes on Bus 13-1, 14-1, (23-1, 24-1) t AP. PROVED OCT 311985 O.C.O. 1 R.
1/00269
-1
j l
QGA 100-T5 Revision 1 October 1985 INITIATING CONDITIONS FOR EMERGENCY CORE COOLING SYSTEMS AUTOMATIC START The following conditions will cause the automatic initiation of emergency core cooling systems.
1.
HPCI a.
High drywell pressure (+2.0 psig) b.
Low low reactor water level (-59 in.)
2.
Core Spray and LPCI mode of RHR a.
High drywell pressure (+2.0 psig) b.
Low low reactor water level (-59 in.) in combination wtth low reactor pressure (325 psig) c.
Low low reactor water level (-59 in.) for 8.5 minutes.
I I
I I
AP. PROVED OCT 311985 (final) l 1/00279 O. C. O. S. R.
l l
\\
M M
M M
M M
M QCA 100-F1 Revision !
oct her i9as HEAT CAPACITY TEMPERATURE LIMIT (HCTL) 250
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en APPROVED 250 500 750 1000 1250 Oh E RPV PRESSURE (PSIG)
Q. C. O. S R. (Iinal)
8 g v*i
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(133.d) 13A31100d NOISS3WddOS
{
I QGA 200-0 Revision 1 October 1985 PRIMARY CONTAINMENT 200-0 Primary Containment Rev. I 10-31-85 200-1 Suppression Pool Temperature Control Rev. I 10-31-85 200-2 Orywell Temperature Control Rev. I 10-31-85 200-3 Primary Containment Pressure Control Rev. I 10-31-85 200-4 Supression Pool Water Level Control Rev. I 10-31-85 200-F1 Heat Capacity Temperature Limit (HCTL)
Rev. I 10-31-85 200-F2 Reactor Pressure Vessel Saturation Temperature Rev. I 10-31-85 I
200-F3 Orywell Spray Initiation Pressure Limit Rev. I 10-31-85 200-F4 Pressure Suppression Pressure Rev. I 10-31-85 I
200-F5 Primary Containment Design Pressure Rev. I 10-31-85 200-F6 Primary Containment Pressure Limit Rev. I 10-31-85 200-F7 Heat Capacity Ldvel Limit Rev. I 10-31-85 200-F8 Suppression Pool Load Limit Rev. I 10-31-85 t
APPROVED OCT 311985 l g (final)
Q C. a & R.
I g 8/0544I (
QGA 200-1 Revision 1 I
Octcber 1985 SUPPRESSION POOL TEMPERATURE CONTROL A.
ENTRY CON 0!TIONS Entry into this procedure is required whenever any of the following conditions occur:
Suppression pool temperature above 95'F Orywell temperature above 180*F Orywell pressure above 2.0 psig Suppression pool water level above +2.0 in.
Suppression pool water level above -2.0 in.
Reentry into this procedure is required whenever an additional entry condition occurs, or whenever an entry condition clears and re-occurs.
O I
I I
l AP. PROVED 00T 311985 1/00409 Q. C. O. S. R.
GGA 2C0-1 Revision 1 O{
I
)
lHEITeeiecuitsgsies3:----la l ~IF continuous LPCI operation l*
]
of any RHR pump is J
l required to assure l*
adequate core cooling l THEN do itot divert that pump l*
]
from the LPCI mode.
l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I
)
l WEITe eieiuitKg sisis 5 aKd 6 l" l Do not depressurize the RPV l"
]
below 100 psig lUNLESS motor driven pumps l"
sufficient to assure l
l adequate core cooling l" J
are running and avall l
able for injection l"
]
g;;'r'
t=l
?
ll 3!S&RMi ~;!i*l,l1 5
r 1
- m.manin
- ,;
b" f U-
'E h
! NK i
$$l!ll!@!!Y.!
l
!!Mfhs[EPJEFi l *=
iG[1:
3ppaoveo 1
Ssd@=e!!! die!$
pb cnmv p!lse i i
J s s niku OoT 3i BBS e
o.c.o. S. R.
O 1/00409,
I-si i
QGA 200-1 Revision i B.
OPERATOR ACTIONS 1.
Execute this procedure concurrently with the following procedures:
QGA 200-2, Drywell Temperature Control QGA 200-3, Primary Containment Pressure Control QGA 200-4, Suppression Pool Water Level Control 2.
Close all stuck-open ADS valves.
E any stuck-open ADS valve cannot be closed, THEN scram the reactor.
I l
- 3.
WHEN suppression pool temperature exceeds 95'F, THEN operate available suppression pool cooling.
(Refer to QOP 1000-9, Suppression Pool Cooling.)
4.
BEFORE suppression pool temperature reaches 110'F, scram the reactor.
CAUTION Cooldown rates above 100*F/hr may occur as a result of performing steps 5 and 6 below.
- 5.
E suppression pool temperature cannot be maintained below the Heat Capacity Temperature Limit (QGA 200-F1),
THEN maintain RPV pressure below the Limit; enter QGA 100-1, I
Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure.
6.
E suppression pool temperature and RPV pressure cannot be restored and maintained below the Heat Capacity Temperature Limit (QGA 200-F1),
THEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRED, enter QGA 500-2 I
Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procedure.
l I
l I
APPROYED (final) 00T 311985 I
1/0040g Q.C.O.S.R.
1 I
QGA 200-2 l
Revision 1 i
October 1985 9
,g ORYWELL TEMPERATURE CONTROL
'E A.
ENTRY CONDITIONS l
Entry into this procedure is required as specified in QGA 200-1, Suppression Pool Temperature Control.
I I
I I
l I
'O I
' I I
I I
1 I
APPROVED gh OCT 311985 O. C. O. S. R.
1/00419 I
QGA 200 2 Revision 1 4-sasurts fasqsufue 4tytsten 1 GCM 1M ese ses Im_......___._._._.._
1........__.._...
.....r._._....
m.
...a..___....._____.._.__..._..__.____._.............
._..._. _....._._._ _.. 1_....____
age see 7se taas taas syv musase para i
l_While executing this procedure:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l*
IF drywell pressure is above 5 I
l-psig.
l' THEN trip all drywell coolers i
l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l I
l l
l_WhlTe_e_xe_cu_ ting step 4:__________l".
~
l IF continuous LPCI operation ofl" any RHR pumo is required to l
assure adequate core l"
~
C00 ling.
l THEN do not divert that pump froml" the LPCI mode.
l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l h.m musas O. C. O. S. R.
1/00419 2-1
QGA 200-2 Revision 1 D
8.
OPERATOR ACTIONS CAUTION i
High drywell temperature adversely affects RPV water level instrument indication; refer to QGA 00 - Caution M4.
1.
WHEN drywell temperature exceeds 180'F, THEN operate availabla drywell cooling.
2.
Execute steps 3 and 4 concurrently.
3.
E drywell temperature reaches the RPV Saturation Temperature (QGA 200-F2),
THEN RPV FLOODING IS REQUIRED: enter QGA 500-6, Reactor Pressure I
Vessel Flooding, and execute it concurrently with this procedure.
BEFORE drywell temperature reaches 280*F I 9 "4.
BUT ONLY IF drywell pressure is above 5 psig THEN a.
Trip both recirculation pumps.
b.
Trip all drywell coolers c.
Initiate drywell sprays in accordance with 00P 1000-8. Post Accident Containment Spray, limiting flow to one loop.
E drywell temperature cannot be maintained celow 280*F.
THEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRED: enter QGA 100-1 Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure.
I AP. PROVED h
OCT 311985
- 0. C. O. S. R.
(final) 3-1/0041g
,,-.,-,y,----s-,--
-,c--w
,,,,-vm,, -,
QGA 200-3 I
Revision 1 October 1985 O
l PRIMARY CONTAINMENT PRESSURE CONTROL A.
ENTRY CCNDITIONS Entry into this procedure is required as specified in QGA 200-1 Suppression Pool Temperature Control.
I I
I I
iO I
I I
I I
lh APPROVED OCT 311985 I
1/0042g I
GGA 200-3 Reelston 1 O
l WRITE eseiuitsg tsti irociduri:- - - - - - -l
- lg suppression pool spray has been l*
Initiated.
l AM suppression chamber pressure drops to l*
O pstg.
E l
l THEN terminate suppression pool sprays.
l*
g t
l WEtTe eieiuitKg sinis 2 aRd 3T - - - - - - -l" lE continuous LPCI operation of any RHR l"
g pump is required to assure adequate g
l l
core cooling, l"
THEN do not divert that pump from the l
LPCI mode.
l**
1 i
APPRC' LED OCT 3 1985 o.c.o. S. R.
4 1/00429 -
E-
QGA 200-3 Revision 1 8.
OPERATOR ACTIONS CAUTION Suppression chamber pressure above 25 psig will cause the RCIC turbine to trip on high exhaust pressure.
- 1.
Operate the following systems to control drywell ANO suppression chamber pressures:
a.
S8GTS or R8 vent system in accordance with QOP 1600-13, Post Accident Venting of Primary Containment, ONLY IF the space being evacuated is less than 212*F.
b.
Drywell coolers if drywell pressure is below 5 pstg.
- 2.
BEFORE suppression chamber pressure reaches 12.5 psig, BUT ONLY IF suppression pool water level is below 27.5 ft.
THEN initiate suppression pool spray in accordance with QOP 1000-8, Post Accident Containment Spray.
t 3.
E suppression chamber pressure exceeds 12.5 psig.
I ANO drywell temperature is less than 340'F, fiiEN a.
Trip both recirculation pumps.
b.
Trip all drywell coolers.
c.
Initiate drywell sprays in accordance with QOP 1000-8, Post Accident Containment Spray, limiting flow to one loop.
i APPROVED OCT 311985 g
- 0. c. o. S. R.
1/0042g I
I I
I I
I.
I ggg;
- -1 OCT-i g
=
E
/
I l.
/
I l
l
/
/
I i
10 20 30 40 PRIMARY CONTADGENT LEVEL (FEET)
I APPROVED OCT 311995 I
o.ca**
I 1/0042g I
QGA 200-3 Revision 1 4.
IF suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure (QGA 200-F4),
~
THEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter QGA 500-2, I
Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procedure.
5.
E suppression chamber pressure cannot be maintained below I
55 psig, THEN RPV FLOODING IS REQUIRED; enter QGA 500-6, Reactor Pressure Vessel Flooding, and execute it concurrently with this procedure.
6.
IF drywell pressure exceeds 90 psig, I
THEN trrespective of the offsite release rate, vent the containment in accordance with QOP 1600-13, Post Accident Venting of Primary Containment, as follows:
a.
IF suppression pool level is below 30 ft.,
THEN vent the suppression chamber.
b.
E suppression pool level is at or above 30 ft.,
THEN vent the drywell E
containment isolation interlocks must be bypassed to iI accompIlsh this step, THEN refer to QGA 500-T4, Bypassing Group II Isolation and Reactor Building Vent Isolation.
7.
IF drywell pressure cannot be maintained below 90 psig, THEN 1rrespective of whether adequate core cooling is assured:
a.
IF suppression pool level is below 27.5 ft.
THEN initiate suppression pool sprays in accordance with QOP 1000-8, Post Accident Containment Spray.
I l
b.
IF drywell temperature is below 340*F, I
THEN (1) Trip both recirc. pumps l
(2) Trip all drywell coolers (3) Initiate drywell sprays in accordance with 00P 1000-8, Post Accident Containment Spray, I
limiting flow to one loop.
I l
APPROVED l
OCT 31198S 1
(final)
Q.C.O.S.R.
1/0042g l
QGA 200-4 Revision 1 October 1985 l
SUPPRESSION POOL HATER LEVEL CONTROL A.
ENTRY CONDITIONS Entry into this procedure is required as specified in QGA 200-1, Suppression Pool Water Level Control.
I I
' I I
O I
I I
l I
1 lI APPROVED OCT 311985
- 0. C. O. S. R.
2/0043g
_1
QGA 200-4 Revision 1 I
GGA 200-F7, REVISION i HEAT CAPACITY LEVEL LIMIT OCTOBER 1985 i
30 iir,.
,1;
,,,,,j
- l' 3*h Ik l ' l ' k ;,;;'
it.
i 25
!['.,li
'li 'l e i,
'i,i
.it
.i g
,i g
i i i g
y
...i
'Ed J
i sf i.
.i "J
_..___2____
15
_ c-- H m
j,..,
e b
j/ /,,s, n,,
,ri.i,
$0 t' f f f f f /i /l f / / f f f /l Q / ;/ / / / / */ / J / '/ / s.
I
/ ff
'Li f fif.
~ ~
'//.
Go Myrt omraATA
////d fff sa
~ f f fR' 5
,..,....., _..au p., 9
.. ~.. - <g/ / /,,
pp,;
'//>
/
'/1
/ */ } ')
fff i
f//
//
///fi
\\
t;s ; t.
4,r r,g < s r s.
.,n r,,
10 20 30 40 50 60 HCTL-SUPPRESSION POOL TEMP ( *F)
APPROVED OCT 311985 m
l o.c.o.s.R.
g j
i
3f QGA 200-4 Revision 1 g
8.
OPERATOR ACTIONS 1.
Maintain suppression pool water level between +2 in. and -2 in.
I For removal of water from the suppression pool, refer to 00P 1000-12. Suppression Pool Water Transfer to the Main Condenser.
For makeup to the suppression pool, gravity drain from the condensate storage tank.
2.
IF suppression pool water level cannot be maintained above -2 in.,
TIIEN continue in this procedure at step 4.
3.
IF suppression pool water level cannot be maintained below.2 in.,
@Ncontinuelitthisprocedureatstep5.
4.
Suppression Pool Water Level Below -2 in :
2 a.
Maintain suppression pool water level above the Heat Capacity I
Lavel Limit (QGA 200-F7).
b.
Ij; suppression pool water level cannot be maintained above I
the Heat Capacity Level Limit (QGA 200-F7),
THEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRED; enter QGA 100-1, Reactor Pressure Vessel Water Level Control, j
and execute it concurrently with this procedure.
' I II I
I i
1
,I I
~
APPROVED OCT 31885 O. C. O. S. R.
2/00439 '
I
I l
QGA 200-4 Revision 1 f
l~NElIt eItcuIf ng'sIep 5bI ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~l
- l
~
t l
l Do not depressurize the RPV below 100 pstg l*
l UNLESS motor driven pumps sufficient to l
assure adequate core cooling are
(*
running and available for injection.
l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_l i'
SLPMESSION POOL QGA 200-F8
(
LOAD LIMIT EVISION 1 OCTOBER 1985 l
N
':' F F Iliiierj i4iiii
.Ni y M J 1) ) ~ '
t,inIit i i it il i ! (VII / /11 CD WW161
~
I ' 1 ' i. i I I e i l i i '
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'fi 250 500 750 1000 1250 l
FFV PMSSLM (PSIG1 I.
\\l APPROVED OCT 31191L5 l
t 2/0043g Q.C.O. M
j 1
QGA 200 4 I
Revision 1 f
S.
Suporession Pool h ter level Above +2 in.:
Execute step 5b while executing steps Sc through 5f.
a.
CAUTION Cooldown rates above 100'F/hr may I
occur as a result of executing step Sb(1).
i I
- b.
Maintain suppression pool water level below the Suppression Pool Load List t ('taA 200-F8).
(1)
IF suppression pool water level cannot maintained below the I
Suppression Pool Load Limit.
THEN maintain RPV pressure below the Limit.
(2) I F, suppression pool water level and RPV pressure cannot be maintained below the Suppression Pool Load Limit, ANO adequate core cooling is assured, IRN terminate injection into the RPV from sources external to the primary containment i
EXCEPT do not terminate injection from boron injection systems and the CRD system.
(3)
.If, suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit.
THEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRE 0; enter QGA 100-1, Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure.
1 I
~
,I jl APPROVED l
OCT 311985 Q.c.o.S.R.
2/0043g
-S-
'I y9--
-w-,
QGA 200 4 Revision 1 i
t E
s
' s l wsiTe e7esuiing sisi Idi - - - - - - - - - - l*
lg continuous operation of any RHR pump l*
ls required to assure adequate core l
- cooling, l*
s THEN do not divert that pump from the LPCI l
mode.
l*
M e4 4 4 4 APPROVED l cenou g o.c.o.sa. 2/00439 -~ U H
QGA 200 4 I Revision I ( 5. Suppressiq) Pool Water t.evel Above +2 in.: (Continued) s c. BEFORE suppression pool water level reaches.1810 ft. (wide I range torus water level ledicators 1640-1.0 A/B), 'n BUT ONLY IF adequate core cooling is assured, ~ THEN terminate injection into the RPV from sources external I to the primary containmer.t EXCEPT_ do not terminate injection from boron ir.jection systems and the CR0 system.
- dl WH(f Juppredsion pool water level reaches 18.0 ft, BUT ONLYil[ drywell pressur6 is above 5 psig AE drywell l
temperature is below 340*F, THEN (1) Trtp both reactor recirculation system pumps. \\ (2) Trip all drywcIl coolers. I (b Init' tate drywell sprays in accordance with 00P 1000-8. Post Accident Containment Spray, limiting. flow to one \\ I COP..- 3 if drywell sprays are not operating, OI~ initiation of drywell sprays when suppression pool water level is above 18.0 ft may result in a breach of I primary containment integrity. 3 ~ e. fF suppression pool water level is above 18.0 ft. VIIEN (1) E drywe',1 sprays are not operating,, ~ THEN.do not initiate drywell sprays. I '(2) E drywell sprays are operating, THEN continue to operate drywell spesys. f. WHEN suppression pool water level exceeds 3O'.0'ft, I I THEN trrespective of whether adequate core cooling is assured. terminate injection into the RPV from sources external to th,e primary containment. e j l c. i s b. APPROVED It OCT 311985
- 0. C. O. S. R.
2/0043g (final) I -7 ,8 t s
M M M M l l QCA 200-Fi Revision ! HEAT CAPACITY TEMPERATURE october 1985 LIMIT (HCTL) i i ncn i CJU ' f./ /.' s a s r e i e s s j s s j j /'J' / /~/. / / / / / '/ '/ / '/ '/ / / "/ r.', s / / / / f f J' f j ) ~ J d /~ l J / / .e J a s .i / / / / s )~ / / / / / / / / / t LA. / / / / / / / / / / / / / / / / / / / / / / / 225 '-f / / ./ .f / /,r / / t r , / "/ / "/ s / / / / / r / / / / '/ / / sli w_ s 2 s' ) j' i r artsm i t e s s 1 / / J'/ / / / / / ' / / / / / / / g s y-y / / /,r ,7 .I e - M I 41 % M M I [IM / / / / / / / / / / / / / I y nan CUU \\ ~ j s / e ,r r e e ,r r l w ~: ? / / /.c / / / / ' / / ~ / / / /, / /. / / / / / / / J '~ ' / / / / / / / / ./ / / / / / / / / / / / / / / / / / / / ) ~ oo 175 w ~ e s / / / / < / G. '~ r / e e / e e ,e e,, i ~ ~ e r j / / / / / e e e O Eg 150 ~~ m W i E l' ot APPROVED ot 125 B OCTsigns 0.co.sa 250 500 750 1000 1250 RPV PRESSURE (PSIG) I i (final) I
I I e g.. ul ONY a. ,_ 9 m. c.3 o 4 cm CE L M g>w t Cr $ b I N 1 s } O = O 1 } w 1 1 8$ \\ J t ~ I ei \\ R! = w x E ~ i 8it' i, gE m 0 O$I 20 o
- a. p s,
Og Ee 1 a. I -0 s 0& L e 44 1 g U3 A \\ O ID \\ (U s 'A I V 'm%m, O O O O O O O O LO O v (f) l (d, ) 38n1YuadH31 T13MABO I
8$e vi o a 6 QP. co L H 9 , 5 L' o o l 4 Q E CE &8u y s g l E 2 %.! s <TS N N s h$$ \\ \\ s t \\?NNJN ' s \\,'s\\,'N l \\ I s N T N T N \\ \\ x o \\ s \\ \\ v g g \\ N 5 Y \\ z s O h 3 Y s s N w o (f3 b l-- H \\ lI'm sz a x ZH N L M w h k l --) f N >- w s m s s s s I m <g CD N('\\N \\ l W N I og I gt/) s ( \\ M \\[N \\ j l N Cl- \\ J$ s N i J ^ N N JE \\ \\ a s ( ( \\ l W W N \\\\ \\ 3 s 3 \\ \\ ^ \\ ^ N \\ l C c s ( Q N \\ T N \\ o \\ Q x \\ \\ ( g N?\\\\?\\ u i i \\ s \\[\\\\[N\\s-I l w s \\[\\\\[\\b \\TE l \\[\\ \\ s \\ 's \\ 'N \\ 's \\ 'g KjhQ j\\ N o o o o o O O O O O I LD T (T) 0.1 W (d, ) 3Bn1VB3dH31 T13MABO
imus num num mum num uma inn una muu num num num uma muu muu num ums num num QCA 200-F4 PRESSURE SUPPRESSION PRESSURE Rg sju 50 _n i E / tu / i E 40 / E / E / / / l 5 30 j M Eg APPROVED OCT 3125 10 20 30 40 RCa&R PRIMARY CONTAINMENT LEVEL (FEET) (final)
mun suu muu uma mas uma uun aus nun umu nas uma seu uma muu uma num um um QCA 200-F5 ""i" S aa PRIMARY CONTAINMENT , 33 DESIGN PRESSURE 70 B U& 60 E 50 E E 40 E 30 = 5y 20 E E 10 ARPROVED E OCT 31 E85 "C"*R 10 20 30 40 PRIMARY CONTAINMENT LEVEL (FEET) (final) s
uma uma ime um uma amm uma num um aus uma sus mum mum amm sum uma mum i QCA 200-F6 PRIMARY CONTAINMENT ["g2*a, 33 PRESSURE LIMIT ~ 140 l g 120 E!& 100 E a 80 Fu E 60 i d tu AD E i 20 ARPROVED OCT 311985 10 20 30 40 50 60 70 PRIMARY CONTAINMENT LEVEL (FEET) (final)
QGA 200-F7 Revision 1 I. HEAT CAPACITY LEVEL LIMIT october 1985 30 i l j I i I li I 25 1 9W l jf 20 ii 3 ,l ' ~ i i l i d I I it : I eii U 15 l l ' li 25! N i i 2 UN Il / / >s i il. 2 // / el te i 'v i - el ,,S: o y 10 g y , 7 7,y. 7 py,, y , y;, l m /VV // / /// / /,/ / '/ l, x c,,rl / n </ <i<c / /y l 7 / 4i E O Nur fl#MiiTF I / //V 3 / / X L I' Y / /i/. ,w a m 5 'g 79 w g g yo,m
- g y g g
- ,,
r /i / il 16 I/ //!ri AP. PROVED / fv '/ \\/ / y ti )/ /v v t4 V AA / V1 / A fl / Y\\/ / A / /Ix OCT 31 N85 41 l(l( (if 4.(l( (14t' ' ( o.c.o.s a 10 20 30 40 50 60 HCTL-SUPPRESSION POOL TEMP (
- F) (final)
Em uma ums QCA 200-F8 SUPPRESSION POOL "*181 a October 1985 LOAD LIMIT i j 30 / N i / / / s p N' / / / / 1 1 43 r 3)Eu r E / w N./ /./ r.., , r m. e s t r L, a sL a 3 - an am / s ) _s 25 N i j / / / / / N ' / / / l,i f f,i / a; s ' / , / / / / / / N / / / / // l N .f f / / l: ) o 20 E N / / / / s / / /f t z s 6-4 s 'i, e / O 1 N / g N ,/ e i m 15 cr-s s i "a. APPROVED a ~~~ OCT 31 BBS 250 500 750 1000 1250 RPV PRESSURE (PSIG) (final)
QGA 300-0 Revision 1 October 1985 SECONDARY CONTAINMENT I 300-0 Secondary Containment Rev. I 10-31-85 300-1 Secondary Containment Temperature Control Rev. I 10-31-85 300-2 Secondary Containment Radiation Level Control Rev. I 10-31-85 300-3 Secondary Containment Water I Level Control Rev. I 10-31-85 300-T1 Operating Values of Secondary Containment Temperature Rev. 1 10-31-85 300-T2 Operating Values of Secondary Containment Radiation Rev. I 10-31-85 I ( I APPROVED I 00T 311985 Q.C.O.S.R. I (final) 8/05451 I
I QGA 300-1 Revision 1 October 1985 SECONDARY CONTAINMENT TEMPERATURE CONTROL A. ENTRY CONDITIONS Entry into this procedure is required whenever any of the following i secondary containment conditions occur: Olfferential pressure not able to be restored and/or i maintained below 0 in. of water An area temperature abovo its maximum normal operating value (refer to QGA 300-T1 for a listing of secondary containment areas and their respective maximum normal operating values) Reactor butiding ventilation system exhaust radiation level above 3 mR/hr An area radiation level above its maximum normal operating value (refer to QGA 300-T2 for a 11 sting of secondary containment areas and their respective maximum normal I operating radiation levels) Reactor butiding floor orain sump A and B water level above the high water level alirm setpoint for greater than 15 minutes Reentry into the procedure is required whenever an additional entry conditions occurs, or whenever an entry condition clears and re-occurs. I I ' I l l I I APPROVED l OCT 311985 2/00449 --
Reelsten 1 l HEITe executtsg tsii proceduri:- - - - - - - - - l* l IF reactor building ventilation system l* exhaust radiation level exceeds l 3 mR/hr, l* g THEN confirm automatic isolation or manually gg l initiate isolation of the reactor l* 5 building ventilation system, l ~ANO confirm automatic initiation of or l* E manually initiate SBGTS. l l l* lE the reactor building ventilation system isolates, j* AND reactor building ventilation system l exhaust radiation level is below l* 3 mR/hr, g l THEN restart the reactor building ventilation l* g system. (Refer to QOP 5750-2, Reactor l Building Ventilation System.) l* E it is necessary to bypass the l high drywell pressure and/or l* low RPV water level reactor l building isolation signals l* to accomplish this step, l THEN bypass the high drywell pres-l* sure and RPV low water level Eg l tsolation signals in accordance l* Eg with QGA 500-T4. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l II II II m RC'lCD n 3155 O. C. O. S. R. I 2/00449 I,
===-u_
- e. e e.
mu uum u
QGA 300-1 Revisten 1 8. OPERATOR ACTIONS I Or
- 1.
Enter and execute the following procedures concurrently with this procedure. QGA 300-2, Secondary Containment Radiation Level Control l QGA 300-3, Secondary Containment Water Level Control 2. E reactor butiding ventilation system exhaust radiation level is below 3 mr/hr. THEN operate the reactor building ventilation system in accordance 'I with QOP 5750-2, Reactor Building Ventilation System. g it is necessary to bypass the high drywell pressure and/or low RPV water level reactor building isolation signals to accomplish this step, THEN bypass the high drywell pressure and RPV low water level isolation signals in accordance with QGA 500-T4. 3. WHEN the temperature in the RHR CS, or HPCI rooms reaches the value shown in the table below, THEN start the appropriate diesel generator cooling water system to provide cooling to these rooms. G l~~~ Room ~ ~ ~ T ~ ~ ~Tiimpefatufe~(T I ~ ~ ~l F I RHR 160 1 I I CS 160 e l l l HPCI 175 l________l______________l I I APPROVED CCT 31 35 l o.c.o. s. n. 2/0044g..
(%A 300-1 Revision 1 l W51Te execui1Hg thli proceduri:- - - - - - - - - l IJ reactor building ventilation system l l IF-exhaust radiation level exceeds l 3 mR/hr, l ) THEN confirm automatic isolation or manually l initiate isolation of the reactor l building ventilation system, ] lAND confirm automatic initiation of or l manually initiate S8GTS. I i 1 lg the reactor building ventilation J system isolates. l l_N_0 reactor building ventilation system A exhaust radiation level is below l 3 mR/hr, l THEN restartthereactorbuildingventilationl system. (Refer to 00P 5750-2, Reactor ] l Building Ventilation System.) l E It is necessary to bypass the l high drywell pressure and/or l 1 low RPV water level reactor J l building isolation signals l to accomplish this step. l THEN bypass the high drywell pres-l sure and RPV low water level l isolation signals in accordance l with QGA 500-T4. l__________________________l J ] g] APPROVED l cci at 85 g] O. C. O. S. R. 2/0044g ~4-I-
wrTGo-i Revision 1 i 4. IF any area temperature exceeds its maximum normal operating 0 value (QGA 300-71, Operating values of Secondary Containment I Temperature). THEN isolate all system 5 that are discharging into the area EXCEPT do not isolate system s required to Shutdown the reactor, Assure adequate core cooling, or Suppress a working fire. 5. E a primary system is discharging into an area, THEN before the temperature of an area reaches its maximum safe operating value (QGA 300-T1, Operating Values of Secondary Containment Temperature), enter QGA 100-1, Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure. 6. E a primary system is discharging into an area ANO the temperature in two or more areas exceeds their associated maximum safe operating value (QGA 300-T1, Operating Values of I Secondary Containment Temperature), THEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRED, enter QGA 500-2 Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procedure. I APPROVED OCT 311985 o.c. o. S. R. I (final) l 2/0044g -S- ..-_m,, _ _ _ ~..
r QGA 300-2 Revision 1 October 1985 SECONDARY CONTAINMENT RADIATION LEVEL CONTROL l A. ENTRY CONDITIONS Entry'into this procedure is required as specified in QGA 300-1, Secondary Containment Temperature Control. I I I I I O I I I I I I I AP. PROVED IO ocratiS8s O. C. O. S. R. 2/0045g I
f QGA 300-2 Revision 1 l HKlTe eiecuitng tEli proceduri:- - - - - - - - - l,* l IF reactor building ventilation system l* exhaust radiation level exceeds l 3 mR/hr, l* THEN confirm automatic isolation or manually l initiate isolation of the reactor l* building ventilation system. lAND confirm automatic initiation of or l* manually initiate SBGTS. I l' the reactor building ventilation lE system isolates, j* A ND, reactor building ventilation system l l exhaust radiation level is below l* 3 mR/hr, l THEN restartthereactorbuildingventilationl* system. (Refer to QOP 5750-2, Reactor l Butiding Ventilation System.) l* E lt is necessary to bypass the l high drywell pressure and/or l* low RPV water level reactor l building isolation signals l* to accomplish this step, l THEN bypass the high drywell pres-l* sure and RPV low water level l isolation signals in accordance l** with QGA 500-T4. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l p saovED 0 3 311985
- o. c. o. S. R.
9 E 2/00459 E
T QGA 300-2 I Revision 1 B. OPERATOR ACTIONS
- l.
IF any area radiation level exceeds it maximum normal operating value (QGA 300-T2, Operating Values of Secondary Containment I Radiation), THEN isolate all systems that are discharging into the area EXCEPT do not isolate systems required to I i Shutdown the reactor, = 1 Assure adequate core cooling, or I Suppress a working fire. 2. IF a primary system is discharging into an area, THEN before any area radiation level reaches its maximum safe i operating value (QGA 300-T2, Operating Values of Secondary I Vessel Water Level Control, and execute it concurrently with Containment Radiation), enter QGA 100-1, Reactor Pressure this procedure. 3. E a primary system is discharging into an area, AND the radiation level in two or more areas exceeds their - associated maximum safe operating value (QGA 300-T2, Operating I Values of Secondary Containment Radiation), THEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRE 0, enter QGA 500-2, Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procecure. l. 1 APPROVED OCT 311985 o.c. o. S. R. (final) 2/004Sg I --g-,-+
QGA 300-3 Revision 1 October 1985 's SECONDARY CONTAINMENT WATER LEVEL CONTROL A. ENTRY CONDITIONS Entry into this procedure is required as specified in QGA 300-1, Secondary Containment Temperature Control. J I ' I I ' I I O I I I l 1 I
- I d
II AP. PROVED ( OCT 311985 l 2/co4sg o.c.o.S.R. d
QGA 300-3 Revision 1 el l~HElfeexecuitngthiiprociduri:~~~~~~~~~~l* reactor building ventilation system l* l~IF~ exhaust radiation level exceeds l 3 mR/hr, l* THEN confirm automatic isolation or manually l initiate isolation of the reactor l* building ventilation system. lM confirm automatic initiation of or l* manually initiate SBGTS. l l* the reactor building ventilation lE system isolates. l* reactor building ventilation system l@ exhaust radiation level is below l** 3 mR/hr, lTHEN restartthereactorbuildingventilationl* system. (Refer to QOP 5750-2, Reactor l Building Ventilation System.) l** E lt is necessary to bypass the l high drywell pressure and/or l** low RPV water level reactor l building isolation signals l* to accomplish this step, l THEN bypass the high drywell pres-l** sure and RPV low water level l isolation signals in accordance l* with QGA 500-T4. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I APPROVED OCT 311985 A Q.C.O.S.R. 2/0046g, ..-mmum .u. minimmmummmm
QGA 300-3 I Revision 1 OPERATOR ACTIONS O' 8.
- 1.
IF either reactor building floor drain sump water level is above its alarm setpoint (high level alarm indication is provided by ~ l annunciators), THEN operate available sumo pumps to restore and maintain the water level below the alarm setpoint. 2. IF either rett. tor building floor drain sump water level cannot be ~ restored and maintained below the high water level alarm
- setpoint, I
THEN isolate all systems that are discharging into the sump EXCEPT do not isolate systems required to Shutdown the reactor, Assure adequate core cooling, or Suppress a working fire. 3. IF the water level in both reactor building floor drain sumps cannot be restored and maintained below the high water level I alarm setpoint, AND a primary system is discharging into an area, TIiEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRED: enter QGA 100-1, Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure. v 4 APPROVED OCT 311985 O. C. O. S. R. 8 (final) 2/00469 a l a i
QGA 300-T1 I Revision 1 October 1985 OPERATING VALUES OF SECONDARY I CONTAINMENT TEMPERATURE TEMPERATURE SENSOR ALARM MAXIMUM NORMAL MAXIMUM SAFE OPERATING VALUE OPERATING VALUE AREA TEMPERATURE (*F) (*F) (*F) Cleanup Phase Seperator Tank Room Area: 1291-60A (1290-26A) 120 150 226 1291-608 (1290-268) 120 150 226 Cleanup Heat Exchanger Room Area: 1291-60C (1290-26C) 120 150 226 l 1291-600 (1290-260) 120 150 226 l 1291-60E (1290-26E) 120 150 226 l A Cleanup Pump Room Area: 1291-60F (1290-26F) 120 150 226 i B Cleanup Pump Room Area: 1291-60G (1290-26G) 120 150 226 Area Between Cleanup Heat Exchange Room and Phase Seperator Room: f 1291-60H (1290-26H) 120 150 226 HPCI Room Area: 2374A (2340-8A) 175 175 230 23748 (2340-88) 175 175 230 2374C (2340-8C) 175 175 230 23740 (2340-80) 175 175 230 Steam Tunnel Area: 261-22A 160 160 304 261-228 160 160 304 261-22C 160 160 304 261-220 160 160 304 APPROVED RCIC Room Area: OCT 31.1%5 1360-23A 175 175 285
- 0. C. O. S. R.
1360-238 175 175 285 1360-23C 175 175 285 1360-230 175 175 285 l i 1/0031g 1
QGA 300-T1 Reelsion 1 OPERATING VALUES OF SECONDARY CONTAINMENT TEMPERATURE (continued) TEMPERATURE SENSOR ALARM MAXIMUM NORMAL MAXIMUM SAFE OPERATING VALUE OPERATING VALUE AREA TEMPERATURE (*F) (*F) (*F) A RHR Room: 1001-92A 160 160 285 1001-928 160 160 285 1001-92C 160 160 285 l 1001-920 160 160 285 l B RHR Room: 1001-92E 160 160 285 1001-92F 160 160 285 1001-92G 160 160 285 1091-92H 160 160 285 l i f I I 1,g u AP. PROVED OCT 311985 l
- 0. C.O. S. R.
cfin,j) 1/00319
- QGA 300-T2 Revision 1 October 1985 OPERATING VALUES OF SECONDARY CONTAINMENT RADIATION SECONDARY CONTAINMENT ALARM MAXIMUM NORMAL MAXIMUM SAFE RADIATION OPERATING VALUE OPERATING VALUE AREA RADIATION LEVEL (mR/hr)
(mR/hr) (R/hr) U-1 Refuel Floor 5 5 650 U-1 Refuel Floor 100 100 650 I U-1 Refuel Floor 15 15 650 New Fuel Storage Vault 5 5 650 Contaminated Equipment Storage 10 10 650 I U-1 Fuel Pool Pump 40 40 650 U-1 CR0 Storage and Repair 20 20 650 U-1 Clean Up Instrument Rack 10 10 650 I U-1 Clean Up Pump 10 10 650 U-1 Mezzaine Floor Access 5 5 650 U-I CR0 Hydraulle Control Units South 15 15 650 U-1 CR0 Hydraulle Control Units North 15 15 650 U-1 TIP Orive 5 5 650 U-1 TIP Cubical 5000 5000 650 U-1 Suppression Chamber Access 50 50 650 I U-1 HPCI Room 20 20 160 U-1 RCIC Room 25 25 160 U-2 Refuel Floor 5 5 650 U-2 Refuel Floor 100 100 650 lI U-2 Fuel Pool Pump 25 25 650 U-2 Clean Up Instrument Rack 1 1 650 U-2 Clean Up Pump 10 10 650 l U-2 CR0 Hydraulle Control Units North 10 10 650 U-2 CR0 Hydraulle Control Units South 35 35 650 U-2 TIP Orive 5 5 650 l E u-2 tie Cubicie 5000 5000 650 m U-2 Suppression Chamber Access 100 100 650 U-2 HPCI Room 20 20 160 U-2 RCIC Room 30 30 160 t I 1 AP. PROVED OCT 311985
- 0. C. O. S. R.
(f1nal) I 1/0032g -1
- I
QGA 400-0 Revision 1 October 1985 RADIATION RELEASE I 400-0 Radiation Release Rev. I 10-31-85 400-1 Radioactive Release Control Rev. I 10-31-85 l 'I l l I ARPROVED OCT 311985 i
- 0. C. O. S. R.
(final) 8/0546I iI
QGA 400-1 Revision 1 RADIOACTIVE RELEASE CONTROL A. ENTRY CONDITIONS Entry to this procedure is required when a GSEP Alert condition exists I due to gaseous radiation release from the plant as determined in QEP 200-71 condition #17. I I I I I O I I I I I I APPROVED OCT 311985 l
- 0. C. O. S. R.
2/00479 _i_ ] I
l I GGA 400-1 Reutston 1 3 G I lHEITeeieiuttKgtEliprociduri:-------l* l Refer to QEP 330-9 and QEP 330-12 to l* determine offsite release rates. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ l' I I I Iel I I I I 1 OCT 31. 25
- 0. C. O. S. R.
O 2/00479 I J
OGA 400-1 El Revisten 1 g OPERATOR ACTIONS p B.
- l.
Isolate all primary systems that are discharging into areas outside the primary and secondary containments, EXCEPT do not isolate systems required to: Assure adequate core cooling, or Shutdown the reactor. 2. If the offsite release rate approaches or exceeds the rate which I requires a General Emergency as determined in QEP 200-T1 condition #17, _AP@ a primary system is discharging into an area outside the primary and secondary containments. I THEN EMERGENCY DEPRESSURIZATION IS REQUIRED: enter QGA 100-1, Reactor Pressure Vessel Water Level Control, and execute it concurrently with this procedure. I I IIIO I I (I II lI 1l l 'I I APPROVED llO OCT 311985 I c.c.o. m (final) 2/0047g _3 I
QGA 500-0 Revision 3 January 1987 SPECIAL CONTINGENCY PROCEDURES 500-0 Special Contingency Procedures Rev. 3 01-17-87 500-1 Level Restoration Rev. 2 05-08-86 I Emergency Reactor Pressure Vessel 500-2 Depressurization Rev. I 10-31-85 500-3 Steam Cooling Rev. I 10-31-85 I 500-4 Core Cooling Without Level Restoration Rev. I 10-31-85 500-5 Procedure Does Not Exist 500-6 Reactor Press"re Vessel Flooding Rev. I 10-31-85 500-7 Level / Power Control Rev. I 10-31-8S 500-8 Injection of Baron Using the I Reactor Water Cleanup System Rev. I 10-31-85 500-9 Standby Liquid Control I Test Tank Injection Rev. 2 01-17-87 500-T1 Bypassing Low Low Reactor Water Level Group I Isolation Signal Rev. I 10-31-85 500-T2 Bypassing the Low Reactor Water Level Group III Isolation Signal Rev. I 10-31-85 500-T3 Boron Injection Weight Rev. I 10-31-85 I 500-T4 Bypassing the Group II Isolation and Reactor Building Ventilation Isolation Rev. I 10-31-85 APPROVED I 500-F1 Maximum Core Uncovery Time Limit Rev. I 10-31-85 JAN 171987 (final) 8/05471 Q.C.O.S.R.
QCA 500-1 Revision 2 February 1986 A. ENTRY CONDITIONS l Entry to this procedure is required as specified in QGA 100-1, Reactor I Pressure Vessel Water Level Control. J i-O APPROVED MAY 081955 O. C. O. S. R. 2/00489.
QGA 500-1 Revision 2 9 l~HEiTeexecuting This - - - - l* procedure: Any control rod is ng lg inserted to or beyond l** position 04, lTHENexitthisprocedure l** and enter QGA 500-7, l Level / Power Control. l* lE RPV water level cannot l* be determined. lTHENRPVFLOODINGIS l* REQUIRE 0; exit this l procedure and enter l* QGA 500-6, Reactor t 94 4 4 4 MAY 081986
- o. C. O. S. R.
e%t i
OGA 500-1 Revision 2 p B. OPERATOR ACTIONS U
- 1.
Line up for injection into the RPV and start pumps in two or more of the injection subsystems listed below: I l~--~~Injectici--~~~l~0peraitig-l~RPVPiessuriRange ~l l_ Condensate /Feedwater_ _ _ _ subsystem _ _ _ _ _l_Proceduce_l_for_ Sys I QOP 3300-2 1350 - O psig l lRHR/LPCILoopA lQOA10C0-7l 325 - O psig l lRHR/LPCILoopB lQOA1000-7l 325 - O psig l lCSLoopA l QOA 1400-2l 325 - O psig l lCSLoopB lQOA1400-2l 325 - O psig l 2. I F, less than two of the injection subsystems listed above (step-I
- 1) can be Itned up for injection to the RPV with pumps running, THEN commence lining up as many of the alternate injection subsystems listed below as possible.
I l((AIt[r_Eaie[I_Ej{cjijn_S_ub5y5t{mj(([6pir{tInj[ric[ddr((l I Fire Protection safe shutdown CCP 2900-2 l pump l l lCRDpumpfromtheotherunit l QCP 300-19 l l ECCS keep fill pump l QOP 140053 l l SBLC injection from the test tank l QGA 500-9 l l SBLC injection from the boron tank l QCP 1100-2 l APPROVED
- iAY 081986
- 0. C. O. S. R.
r U 2/00489 I
QGA 500-1 Revision 2 l HEITe eieiuitsgihis-----l procedure: IF Any control rod is not l-inserted to or beyond l position 04, l THEN exit this procedure l and enter QGA 500-7, l Level / Power Control. l l HEITe eielui1Eg sieps 4- - - ~l* through 8. l IF RPV water level cannot l l l* be determined, IF RPV water level l THEN RPV FLOODING IS l l-reverses direction. l* REQUIRE 0; exit this O l procedure and enter l l _R RPV pressure changes region. l* QGA 500-6, Reactor THEN return to step 3. l Pressure Vessel Flooding. l l l* 1 b _IF RPV water level drops ,g THEN place the AUTO BLOWOOWN l INHIBIT keylock switch l* l in the INHIBIT l_ _ _ _ _ _ _ _ _ _ _ position._ _ _ _ _l 'I I I APPROVED MAY 081986 g O. C. O. S. R. I GI ,,- g t
QGA 500-1 Revision 2 I 3. Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table. RPV PRESSURE (P) REGION RPV_ WATER _ LEVEL _l((Pi325[p{tj(([j25isigiPil60[p{lj(([P<[05isig((l l I INCREASING STEP 4 STEP 5 STEP 6 l 5ECREA51RG- -l-TEP 7 1---(Below) STEP 7 - - - - - 1 -(5TEP 8Page 7)-----l (Below) S l l________I_iPage7),__1__(Page7)______1_(Page_9) _ _ _l
- 4.
RPV water level is increasing and RPV pressure > 325 psig: Exit this procedure and enter QGA 100-1, Reactor Pressure Vessel Water Level Control, at step 5.
- 5.
RPV water level increasing and RPV pressure between 100 and 325 pB: a. E HPCI and RCIC are not available and RPV pressure is increasing. THEN EMERGENCY RPV OEPRESSURIZATION IS REQUIRE 0, enter QGA 500-2, Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procedure. WHEN RPV pressure is decreasing, THEN exit this procedure and enter QGA 100-1, Reactor Pressure Vessel Water Level Control, at step 5. b. E HPCI and RCIC are not available and RPV pressure is not increasing, THEN exit this procedure and enter QGA 100-1, Reactir Pressure Vessel Water Level Control. at step 5. c. IF HPC! or RCIC is available, EEEN RPV water level reaches +8 in., exit this procedure and enter QGA 100-1, Reactor Pressure Vessel Water Level Control, at step 5. APPROVEO 'UY U S 1986 0 C. O. S. R. 2/00489 I
QGA 500-1 l Revision 2 m O' l_Wh t Te_e_xe_cu_ti ng thi s l procedure: Any control rod is not lE inserted to or beyond l position 04, l THEN exit this procedure l and enter QGA 500-7, l Level / Power Control. l l~Hh1Te execuitEg sieps 4---la through 8: l ~IF RPV water level cannot l l l* be determined, IF RPV water level lTHENRPVFLOODINGIS l l -- reverses direction, l* REQUIRED: exit this l procedure and enter l l _R_ O RPV pressure changes
- region, l*
QGA 500-6, Reactor THEN return to step 3. l Pressure Vessel Flooding. l l l* _I F RPV water level drops ,9 THEN place the AUTO BLOH00HN h l l INHIBIT keylock switch l* 1 I in the INHIBIT position. l________________I 4 4 l v q g 0g1986 O.C.O.s.R. l e% .e. i
h QGA 500-1 E Revision 2 3 O '6. RPV water level increasing and RPV pressure 6 100 psig: a. IF RPV pressure is increasing, YWEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter 1 QGA 500-2 Emergency Reactor Pressure Vessel Depressur12ation, and execute it concurrently with this procedure. WHEN RPV pressure is decreasing, IIIf5 exit this procedure and enter QGA 100-1, Reactor Pressure Vessel Water Level Control, at step 5. I I b. E RPV pressure is not increasing, THEN exit this procedure and enter QGA 100-1, Reactor { Pressure Vessel Water Level Control, at step 5.
- 7.
RPV water level decreasing and RPV pressure > 100 psig: i a. E HPCI, RCIC, or CR0 t s not operating, THEN restart whichever is not operating, For HPCI start, refer to QOP 2300-6, Manual HPCI Startup to Add Water to Reactor Vessel. For RCIC start, refer to QOP 1300-2, RCIC System Manual Start or to QOA 1300-7, RCIC Local Manual Operation. For CR0 start, refer to QOP 300-1. CR0 System Startup. b. E no injection subsystem (listed in step 1) is lined up for injection with at least one pump running, THEN start pumps in alternate injection subsystems (listed in I step 2) which are lined for injection, c. WHEN RPV water level drops to -143 in. (TAF): p E no system, injection subsystem, or alternate injection subsystem is lined up with at least one pump running, THEN STEAM COOLING IS REQUIRE 0; enter QGA 500-3, Steam Cooling, and execute it concurrently with this procedure. WHEN any system, injection subsystem, or alternate injection subsystem is lined up with at least one pump running, THEN return to step 3 of this procedure. APPROVE 0 Q MAY 081386 V
- 0. C. O. S. R.
l 2/0048g I
OGA 500-1 Revision 2 8 9 l HRtTe eieiuitsg tSti - - - - l procedure: Any control rod 1s not lE Inserted to or beyond l position 04, lTHENexttthisprocedure l and enter QGA 500-7, l Level / Power Control. l l HEITe eiecuitsg sieps 4- - - l* through 8: l ~IF RPV water level cannot l l l* be determined, IF RPV water level lTHENRPVFLOODINGIS l l~ reverses direction. [* g l REQUIRED; exit this l procedure and enter l l_R O RPV pressure changes g
- region, j'
OGA 500-6, Reactor THEN return to step 3. l Pressure Vessel Flooding. l l l* _IF RPV water level drops THEN place the AUTO BLOH00HN l l INHIBIT keylock switch l* 3 in the INHIBIT position. l_____ _ _ _ _ _ _ _ _ -l l 1 I APPROVED. g 0.C.O.S.R. I elI i
QGA 500-1 Revision 2 i O IF any system, injection subsystem, or alternate l I injection subsystem is lined up with at least one b pump running, THEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: entar QGA 500-2, Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently with this procedure. WHEN RPV water level is increasing or RPV pressure drops below 100 pstg, i THEN return to step 3 of this procedure.
- 8.
RPV water level decreasing and RPV pressure < 100 osig: a. E no core spray subsystem is opeYating, THEN start pumps in alternate injection subsystems (listed in step 2) which are lined up for injection. b. E RPV pressure is increasing, THEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRED, enter QGA 500-2, Emergency Reactor Pressure Vessel Depressurization, and execute it concurrently wtth this procedure, c. WHEN RPV water level drops to -143 in. (TAF), THEN exit this procedure and enter QGA 500-4, " Core Cooling W1thout Level Restoration." I i APPRCVEO ' FAY 0 S 1926 0 c. o s. a. I \\ (final) 2/0048g :
QGA 500-2 Revision 1 p October 1985 EMERGENCY REACTOR PRESSURE VESSEL DEPRESSURIZATION l I A. ENTRY CON 0!TIONS Entry to this procedure is required as specified in the following procedures: QGA 100-2, Reactor Pressure Vessel Pressure Control QGA 200-1. Suppression Pool Temperature Control QGA 200-3, Primary Containment Pressure Control QGA 300-1, Seco.ndary Containment Temperature Control QGA 300-2, Secondary Containment Radiation Level Control QGA 500-1, Level Restoration QGA 500-3, Steam Cooling QGA 500-7, Level / Power Control O I I O APPROVED OCT 311985 2/0049g 0. C. O. S. R. I
l' l OGA 500-2 Revision 1 e\\ \\ l lHKiTeeiecuitsgsiois3aKd4T-------l* l Do not depressurize the RPV below 100 psig l** UNLESS motor driven pumps sufficient to l assure adequate core cooling are (** running and available for injec-l tion. l** Cooldown rates above 100'F/hr. may be lrequiredtoaccomplishthisstep. l* l lWKtTeeiecuitKgsiei4:-----------l" l LF low low RPV water level MSIV l" { isolation interlocks must be l bypassed to accomp11sh this step, l" THEN install jumpers in accordance wtth l QGA 500-T1. l" 1 \\PPROVED JCT 311985
- o. C. O. S. R.
p _g _- _r
QGA 500-2 Revision 1 O 8 b OPERATOR ACTIONS 1. Exit current RPV pressure control procedure. 2. E any control rod is not inserted to or beyond position 04, THEN a. IF any MSIV 1s open, DIEN bypass low low RPV water level interlocks I in accordance with QGA 500-71. b. Terminate and prevent all injection into the RPV, EXCEPT do not terminate or prevent injection I from boron injection systems or CRD. CAUTION Insure low pressure ECCS (core spray and LPCI) and condensate systems will not inject as RPV pressure is lowered.
- 3.
E suppression pool level is above 5.0 ft., THEN open all ADS valves. "4. E fewer than 3 AOS valves are open, Ag RPV pressure is at least 50 psig above suppression chamber I
- pressure, THEN rapidly depressurtze the RPV using one or more of the O
following systems. (Use in order which will minimize radioactive release to the environment.) Main turbine bypass valves Main steam line drains HPCI turbine lI RCIC turbine RPV head vent Steam jet air ejectors RWCU l APPROVED 0CT 311985 l
- 0. C. O. S. R.
2/0049g 3 I.I
QGA 500-2 Revision I g el ~ g I a l i THIS PAGE INTENTIONALLY BLANK G l APPROVED OCT 311985 i
- o. c. O. S. R.
2/0049g 4 i
QGA 500-2 Revision 1 l S. IF RPV Flooding is required. TREN exit this procedure and enter QGA 500-6, RPV Flooding, at step 6. 6. IF any control rod is not inserted to or beyond position 04, THEN exit this procedure and enter QGA 500-7, Level / Power Control, at step 4a., and enter QGA 100-2, Reactor Pressure Vessel I Pressure Control, at step 4. 7. Exit this procedure and enter QGA 100-2, Reactor Pressure Vessel Pressure Control, at step 4. I I I h iO d dii APPROVED OCT 311985 O. C. O. S. R. (final) 2/00499. - - _ - _ - _ _ _ - _, _ _. _. _.
I .,5 -3 g ee. si. i IO STEAM COOLING A. ENTRY CON 0!TIONS Entry to this procedure is required.s specified in QGA 500-1, Level ,es, r... y I tIi ~I .III Il 'IO !II'I I I I
- Il
!II l AP. PROVED OCT 311985 O. C. O. S. R. 2/0050g I !g
QGA 500-3 E Revision 1 5 l HEITe eiecuitEg tEti procedure --l*, lE Emergency RPV Depressurization is l** required. 4 l O_R_ any system, subsystem, or alternate l* Injection subsystem is lined up for l Injection with at least one pump l** running. l THEN exit this procedure and enter l* QGA 500-2, Emergency RPV Depres-l surization. l* f f
- f f
f-ii I APPROVED OCT 311985 m I O.C. O. S. R. l 2/00509 h
QGA 500-3 Revision 1 B. OPERATOR ACTIONS
- l.
Exit current RPV pressure control procedure. I 2. ~ Control RPV pressure below 1060 psig by manually activating ADS valves. 3. WHEN RPV water level drops to -240 in., I OR RPV water level cannot be determined. TIIEN open 1 A05 valve. I WHEN RPV pressure drops below 700 psig THEN exit this procedure and enter QGA 500-2, Emergency Reactor i Pressure Vessel Depressurization. I I
- 10' I
I I I I I, APPROVED OCT 311985 I
- o. c. 0. S. R.
(final) 2/0050g, ~
I QGA 500-4 I Revision 1 October 1985 O CORE COOLING WITHOUT LEVEL RESTORATION A. ENTRY CONDITIONS I Entry to this procedure is required as specified in QGA 500-1, Level Restorat1on. W ,f W W WO lf 1 l d d
- g APPROVED OCT 311985
- 0. C. O. S. R.
2/0051g -1
=. QGA 500 4 Revition 1 I l HsiTe execuitEg tsti ir6ciduri - -[* lE any control rod is not l** inserted to or beyond l position 04, l** THEll exit this procedure and l l enterQGA500-7, Level / Power l* l Control. l__________________l* l l IIIIII I l APPROVED ocutes I g g o.c.o.s.a l l, 2/00519.
QGA 500-4 I, Revision 1 U OPERATOR ACTIONS l O 8 CAUTION Cooldown rates above 100*F/hr may occur as a result of executing the following step. 1. Exit current RPV pressure control procedure. 2. Open all A05 valves by placing control switches to MANUAL. 3. Operate both core spray subsystems with suction from the suppression pool. WHEN at least one core spray subsystem is operating with suction from the suppression pool, AJ RPV pressure is below 190 psig, THEN terminate injection into the RPV from sources external to the primary containment except for CRD. 4. WHEN RPV water level is restored to -143 in., THEN exit this procedure and enter QGA 100-1, Reactor Pressure Vessel Water Level Control, at step 5 and enter QGA 100-2, Reactor Pressure Vessel Pressure Control, at step 4. O i APPROVED { OCT 311985 O. C. O. S. R. I (final) 2/0051 9 - --,-.,ww---,-----y -%-,,.--,,,.-,w,vw-3---,,---ww-,-,w-, - - - - - - - - - e.,,,w,--wv-,,,e- ,w..,w
I QGA 500-6 Revision 1 REACTOR PRESSURE VESSEL FLOODING A. ENTRY CON 0!TIONS Entry into this procedure is required as specified in the following procedures: QGA 100-1, Reactor Pressure Vessel Water Level Control QGA 200-2, Drywell Temperature Control QGA 200-3, Primary Containment Pressure Control QGA 500-1, Level Restoration QGA 500-2, Emergency RPV Depressurization QGA 500-7, Level / Power Control I I ' I10 I 1III .I d ,I 'II . Il AP. PROVED I OCT 311985 g
- 0. C. O. S. R.
1 2/00529 I
QGA 500-6 Revision 1 I e s I I I l~WE1Te eTecuitsg sieps 4 aKd ST - - - - - - - - - - l* lDonotdepressurizetheRPVbelow100psig l** UNLESS motor driven pumps sufficient to l assure adequate core cooling are l** running and available for l Injection. l* l~WEtTe~eieiui1Egsiti5:~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~l** l IF low low RPV water level MSIV isolation l" interlocks must be bypassed to accomplish l this step, l** THEN install jumpers in accordance with QGA 500-T1. " l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I I f f APPROVED OCT 311985
- o. c. O. S. R.
2/00529 QGA 500-6 Revision 1 8. OPERATOR ACTIONS v 1. IF steam cooling is required, WEN ex1t this procedure and enter QGA 500-3, Steam Cooling. 2. Exit current RPV water level and pressure control procedures. 3. E any control rod is no_t inserted to or beyond position 04, THEN a. IF any MSIV is open, WEN bypass low low RPV water level interlocks in accordance w1th QGA 500-T1. b. Terminate and prevent all injection into the RPV, EXCEPT do not terminate or prevent injection from boron I injection systems or CRD. CAUTION Insure low pressure ECCS (core spray and LPCI) and condensate systems will not inject as RPV pressure is lowered.
- 4.
IF suppression pool water level 1s above 5.0 ft., WEN open all ADS valves. I " 5. IF fewer than 3 ADS valves are open, @ RPV pressure is at least 50 psig above suppression chamber I THEN rapidly depressurtze the RPV using one or more of the pressure. following systems. (Use in order which will mintmtze radioactive release to the environment.) Main turbine bypass valves Main steam line drains HPCI turbine (RPV Injection or test mode) RCIC turbine (RPV injection or test mode) RPV head vent I Steam jet air ejectors RWCU (recirculation through the non-regenerative I heat exchanger) I I APPROVED OlV OCT 311985
- 0. C. O. S. R. 2/00529 I
h. CGA 500-6 Revision 1 g ..el l l~WEITe~eiecuitngsieps6Iihrougn6e?~~~~~~~~l* lE RPV water level can be determined, [** ANO suppression chamber pressure can be l maintained below 55 psig. l** THEN proceed as follows: I l'*
- a. E any control rod is not inserted to or l
beyond position 04, l* THEN exit this procedure and enter QGA 500-7, l Level / Power Control, and enter QGA 100-2, l** Reactor Pressure Vessel Pressure Control, l at step 4, and execute these procedures l** concurrently. I l**
- b. IF all control rods are inserted to or l
beyond position 04, l* ~ THEN ex1t this procedure and enter QGA 100-1, l Reactor Pressure Vessel Water Level l** Control, at step 5 and QGA 100-2, Reactor l Pressure Vessel Pressure Control, at l* step 4, and execute these procedures ] concurrently. l* ( l l APPROVED OCT 31985 o.c.o.s. R. 1 _4 I 2/0052g
QGA 500-6 Revision 1 l \\ B. OPERATORACTICHj I l 6. E any control rod is no_t inserted to or beyond position 04, l THEN flood the RPV as follows:
- a.
Terminate and prevent all injection into the RPV EXCEPT do not terminate or prevent injection from boron injection systems and the CRD system, and continue i to prevent injection into the RPV as directed above UNTIL RPV pressure is less than that specified in the table below. l~Sumberof -~l-RPVPrisiure-l I
- _p_en_ ADS v_al_ve_s,_ _ _( PSIG_)
O g-g.___ l 4 l 270 l l 3 l 365 l l l 2 l 555 l E less than 2 ADS valves can be opened, THEN continue in this procedure at step 6c. I\\ b. IF at least 3 ADS valves can be opened. TREN close the following valves: MSIVs Main steam line drains (220-1 and 220-2) HPCI steam line isolations = (2301-4 and 2301-5) RCIC steam line isolations (1301-16 and 1301-17) l Il l I;O ^" "' l OCT 311985 2/0052g 0. C. O. S. R. I
QGA 500-6 Revision 1 ell lWKtTeexecuitigsieps6aihrougK6ei------'-l* IF RPV water level can be determined, l* l KID suppression chamber pressure can be l maintained below 55 psig. l** THEN proceed as follows: l l** a.,I_F any control rod is not inserted to or l beyond position 04, l* THEN exit this procedure and enter QGA 500-7, l Level / Power Control, and enter QGA 100-2, l** Reactor Pressure Vessel Pressure Control, l at step 4, and execute these procedures l* j concurrently. I l**
- b. IF all control rods are inserted to or l
beyond position 04, l* l THEN exit this procedure and enter QGA 100-1, { l Reactor Pressure Vessel Water Level [** Control, at step 5 and QGA 100-2. Reactor l Pressure V9ssel Pressure Control, at l** step 4, and execute trese procedures l concurrently. l* APPROVED OCT 311985 O. C. O. S. R. 2/00529.
QGA 500-6 Revision 1 6. If any control rod is not inserted to or beyond position 04 THEN flood the RPV as follows: (Continued) CAUTION A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage. c. Commence and slowly increase injection l-Humbir of - ~l-RPV Prisiure- -l Into the RPV with the Open valves ADS (PSIG) systems listed below l--------[---------l UNTIL at least 2 ADS valves are open l 5 l 215 l I and RPV pressure is above that l 4 l 270 l specified in the I table alongside l 3 l 365 l l 2 l 555 l l g , _ _ _ _ _ _ _ _ _ _ _ _ _gg,,7, q_ _ _ Systems Procedure l___________I_________l l Condensate /Feedwaterl QOP 3300-2 l l Safe shutdown pump l QOP 2900-2 l l CR0 l QOP 300-16 l l LPCI mode of RHR l 00A 1000-7 l lT5I55TEPC6NTI5UES05PA6E9l g I I APPROVED OCT 311985 g O. C. O. S. R. g 2/0052g -7_ I
QGA 500-6 Revision 1 I I i l'WEITe~execuilng sieps 6a ih ougE lei - - - - - - - l IF RPV water level can be determined, l* lAWO suppression chamber pressure can be l maintained below 55 psig. (** THEN proceed as follows: l l* a._Q any control rod is g inserted to or l beyond position 04, l* THEN exit this procedure and enter QGA 500-7, l Level / Power Control, and enter QGA 100-2, l* Reactor Pressure Vessel Pressure Control, l at step 4, and execute these procedures l** concurrently. I l**
- b. IF all control rods are inserted to or l
beyond position 04, l* ~ THEN exit this procedure and enter QGA 100-1, l Reactor Pressure Vessel Water Level l** Control, at step 5 and QGA 100-2. Reactor l Pressure Vessel Pressure Control, at l* step 4, and execute these procedures l concurrently. l* APPROVED OCT 311985 o.c.o.s.a. 2/0052g I E ._,____m.,_ e ,_.,,,,,_,o.c-.-_.-__----.,_,._._-.,,,,,-.,..._-.-_---.m. ,,.. _, _ - ~,, _..,.. -..
h' QGA 500-6 Revision 1 I l' 6. IF any control rod is not inserted to or beyond position 04, r TREN flood the RPi as follows: (Continued) c. (Continued) IF less than 2 ADS l~ ~ Suilibir~of ~ ~l~ ~ EPV Frisiuie~ ~l are open, I RPV pressure Open valves ADS (PSIG) OR cannot be l________1_________l Increased above that specified in l 5 l 215 l I the table along-
- side, l
4 l 270 l THEN comence and slowly l increase injection 3 l 365 l I Into the RPV with thesystemslistedl 2 l 555 l below I UNTIL atleast2A05vaTvisaieoienindKPVprisiuieli above that specified in the table. l l___________l__ Operating _______l Systems Procedure l___________I_________I lCorespray l QOA 1400-2 l lECCSkeepfill l QOP 1400-3 l lCRDpumpfromotherl QOP 300-19 l unit l____________________I o i I Il APPROVED OCT 311085 l O.C.O.S.R. 2/0052g -9 3-
QGA 500-6 Revision 1 e l WEITe execuilng sieps 6a Ihroug6 lei - - - - - - - -l, lE RPV water level can be determined, [** AMD suppression chamber pressure can be l maintained below 55 psig. l** THEN proceed as follows: I l'
- a. E any control rod is ng inserted to or l
beyond position 04, [* THEN exit this procedure and enter QGA 500-7, l Level /Pcwer Control, and enter QGA 100-2, [* Reactor Pressure Vessel Pressure Control, l at step 4, and execute these procedures l** concurrently.
- b. IF all control rods are inserted to or l
beyond position 04, l* THEN exit this procedure and enter QGA 100-1, l Reactor Pressure Vessal Water Level l** Control, at step 5 and QGA 100-2, Reactor l Pressure Vessel Pressure Control, at l** step 4, and execute these procedures l concurrently. l* g II I I p l E APPROVED g! OCT 311985 O. C. O. S. R. 0 g-10-2/0052g 6 m --w .-9 ww .ywype-_ _ - - .--.,_,____,m-_._wg w- -- . w.- smmm m m-- m-
QGA 500-6 ,E Revision 1 3 l I[ 6. IF any control rod is not inserted to or beyond position 04, MEN flood the RPV as follows: (Continued) d. Control injection into the RPV to maintain: At least 2 ADS valves open, and l i RPV pressure above that specified in the table below, but as low as practicable. l-~Sumberof~~l~~RPVPrisiure~~~l ~ Open ADS Valves (PSIG) I l_________I___________I l 5 l 215 l l 4 l 270 l l 3 l 365 l l 2 l 555 l e. WHEN either of the following occur: l All control rods inserted to or beyond position 04, or The reactor is shutdown and no boron has been injected into the RPV, THEN continue in this procedure at step 7. 7. IF at least 3 ADS valves can be opened, MENclosethefollowi/1gvalves: MSIVs I Main steam line drains (220-1 and 220-2) i HPCIsteamhineisolations(2301-4and2301-5) l RCICsteamflineisolations(1301-16and1301-17) IlO APPROVED i 1 enuses O.C.O.S.R. 2/00529.. -
i QGA 500-6 Reelston 1 1 1 lHEITeeiecui1EgsiepssaihrougEadi---l*, jE RPV water level can be determined. (** THEN continue in this procedure at l step 9b. l* l I I i l APPROVED OCT 311985 O.C.O.S.R. 2/00529 II
QGA 500-6 g Revision 1 ' LJ 8. IF RPV water level cannot determined, I [h V TREN flood the RPV as follows:
- a.
Commence and increase injection into the RPV with the systems I listed below UNTIL all of the following Conditions have been establ15hed: At least 3 ADS valves open, and RPV pressure not decreasing, and I RPV pressure at least 77 psig above suppression chamber pressure. ll _____________y, g Systems Procedure l___________l_________l l l Condensate /Feedwaterl QOP 3300-2 l lCR0 l QOP 300-16 l lLPCImodeofRHR l QOA 1000-7 l lCS l QOA 1400-2 l i l Safe shutdown pump l QOP 2900-2 l l ECCS keep fill l QOP 1400-3 l CRD pump from I l other unit l QOP 300-19 l l SBLC test tank l QGA 500-9 l Il SBLC boron tank injection l QOP 1100-2 l 1 I; II APPROVED OCT 311985 gl
- 0. C. O. S. R.
2/00529 l3-
QGA 500-6 Revision 1 9% l_WhtTe_e_xe_cu_tingsteps8athroughad:_______________l* I lIF RPV water level can be determined, l** TIIEN continue in this procedure at l step 9b. [* l i ( 1 o nc- ! r i ni i.l li .. l rp.,- l >=.cr===.m l i i i .l. l i il .i li i =. .o j . 1.!; l'=uarii !!lFj l , lib l .I!!' l i !! l } '.. ; i h. .!. L. 'L I i i y I i I ili !iM.:. i,lil ' 1 ! "I . !. t. gi i. '. .g. . r }.,j~ n, t._ ... ; g ,l !g'
- . j ' " !..;._. 1.pl l M4 Iii i l
l Ib lI!i 1 . l .. i i ! i.: 114. . W, , i ai l l. L lol i i i n i ! ! i.j . n s i i i,I r l l!!.. =. = = m.i m e. im . }... !.l ; ]. ' ' r ', ', ' + I ._......;j' ii 1 f, j: i g I L ,c, cc-l i i j j i -i . ol 1 i ,. wi, fl 1
- . u.4 siv=l s'!
. e rstee o .t il i i I ir=siumt l iij i i t!; !l T -' "[ T". I i! 'l l-l ' ' ! J I - r -- - --- '- 4 ,,, l [;l 1 - ;i I i i i iili t j _p..}..1p.i i 1 APPROVED l ilI i ,.,l . l, ! -.I.j.jk,l[l 'j I i i '~! OCT 31.1985 '!l j l i l.yL i i i F >!l o.c. 0. S. R. i ,,c- -' l l ,i*l ,i ;...:. jl rue uts asactee sum.eu luer ll._..._.'.;.. I i !,i,....._._l. j !I' I l' i! Iljl _. ___.L. 2_muu_'. l l' l lI l i t 2/0052g I
QGA 500-6 Revision 1 IO' 8. IF RPV water level cannot be determined, THEN flood the RPV as follows: (Continued) b. Control injection into the RPV to maintain both of the following conditions: I At least 3 ADS valves open, and RPV pressure at least 77 psig above suppression chamber pressure, but as low as practicable. c. WHEN the following conditions have been established: RPV water level instrumentation is available, and Temperature near the RPV cold water level instrument leg vertical runs is below 212*F (as determined by the drywell environs monitor rack temperature indicators, when available), and Suppression chamber pressure is below 55 psig, Reactor pressure has remained at least 77 psig above a sw pression chamber pressure for at least the time spectfled in the table below. l l-Sumber of - -l- - - TIME - - - - -l Open ADS Valves (minutes) l_________I___________I l 3 l' 130 l l 4 l 70 l i l 5 l 40 l THEN terminate all injection into the RPV and reduce RPV water level. CAUTION l It may be necessary to open the RPV head vents to prevent drawing a vacuum in the RPV while reducing RPV level. d. IF RPV water level indication is not restored within the Maximum Core Uncovery Time Limit (QGA 500-F1) after connancing termination of injection into the RPV, THEN return to step 8a of this procedure. p/ APPROVED Q OCT 311985 2/00529 -iS-0.C.O.S.R. g l
l QGA 500-6 Revision i s l~WEITe~eiecuilEg~sieps~9I ThrougE Idi ~ ~ ~l* IF RPV water level can be determined, j' lTEENcontinueinthisprocedureat i l step 84. l* ~~~~-------_ 9 i i 8F i ' s' s ,,, e - i )CT 31885 0.C.O.S.R.
- 6lI, 2/0052g
QGA 500-6 Revisten 1 [ m e. Exit this procedure and enter QGA 100-1, Reactor Pressure (s Vessel Water Level Control, at step 5 and QGA 100-2, Reactor Pressure Vess.1 Pressure Control, at step 4, and execute these steps concurrently. 9. IF RPV water level can be determined, TiiEN flood the RPV as follows:
- a.
Conmence and increase injection into the RPV wtth the systems 1isted below UNTIL RPV water level is increasing. Systems' Procedure l___________I_________I l Condensate /Feedwaterl QOP 3300-2 l lCR0 l QOP 300-16 l l LPCI mode of RHR l QOA 1000-7 l l CS l QOA 1400-2 l f lSafeshutdownpump l QOP 2900-2 l lECCSkeepfill l QOP 1400-3 l CR0 pump from lotheruntt l QOP 300-19 l l SBLC test tank l QGA 500-9 l SBLC boron I-tank injection l QOP 1100-2 b. Control injection into the RPV to maintain RPV water level increasing. c. WHEN suppression chamber pressure can be maintained below 55 I 1
- psig, THEN exit this procedure and enter QGA 100-1, Reactor
) Pressure Vessel Water Level Control, at step 5 and QGA ,g 100-2, Reactor Pressure Vessel Pressure Control, at step '3 4, and execute these steps concurrently. l APPROVED 0CT 311985 l" (final)
- 0. C. O. S. R.
2/0052g.
QGA 500-7 Revision 1 October 1985 IO' LEVEL / POWER CONTROL l A. ENTRY CONDITIONS Entry to this procedure is required as specified in the following procedures: QGA 100-1, Reactor Pressure Vessel Water Level Control QGA 500-1, Level Restoration QGA 500-2, Emergency Reactor Pressure Vessel Depressurization QGA 500-4, Core Cooling Without Level Restoration QGA 500-6, Reactor Pressure Vessel Flooding I I I O I lI I I I APPROVED %o ocnuns g 2/00539. O
QGA 500-7 Revision 1 ~9 lHEITeeieiuitngtEtipriciduri:-------l* IF RPV water level cannot be determined l* lTRENRPVFLOODINGISREQUIRED: exit this l procedure and enter QGA 500-6, l** Reactor Pressure Vessel Flooding. l l** IF all control rods are inserted to or l-beyond position 04, l** THEN exit this procedure and enter l QGA 100-1, Reactor Pressure Vessel l** Water Level Control, at step 5. l_______________________l 9Iit ppROVED CT 311985
- a. c. O. S. R.
2/00539 l 5
QGA 500-7 Revision 1 8. OPERATOR ACTIONS CAUTION I Large reactor power oscillations may I be observed while executing step 1.
- l.
IF reactor power is above 37. or cannot be determined, IlI ANO suppression pool water temperature is above 110*F, AND an ADS valve is open or opens, or drywell pressure is above 2.0 psig, THEN a. IF any MSIV is open, t l THEN bypass low low RPV water level interlocks in accordance with QGA 500-T1. b. Lower RPV water level by terminating and preventing all I injection into the RPV EXCEPT do not terminate or prevent injection from baron injection system or CRD, and continue to prevent injection into the RPV as instructed above I UNTIL either: Reactor power drops below 37., or = RPV water level drops to -143 in., or All ADS valves remain closed and I drywell pressure remains below 2.0 psig. CAUTION Insure that low pressure ECCS (core t g spray and LPCI) and condensate systems E will not inject as RPV pressure is lowered. I II 1 l II APPROVED OCT 311985 O. C. O. S. R. 2/00539 i
QGA 500-7 Revision 1 lHEITeeiecuitngtEtiir6ciduri:-------------l IF RPV water level cannot be determined, l [TEENRPVFLOODINGISREQUIRED: exit this procedure and l enter QGA 500-6, Reactor Pressure Vessel Flooding l lE all control rods are inserted to or beyond l pos1 tion 04, lTHENexitthisprocedureandenterQGA100-1, Reactor l Pressure Vessel Water Level Control, at step 5. l_____________________________l l WEITe eiecuitHg sieps 2 tsr6 ugh 4i - - - - - - - - - - l* lE reactor power is above 3% or cannot be determined l* AND RPV water level is above - 143 in., lANO suppression pool temperature is above 110*F, l* l @ pressure is above 2.0 psig, either an ADS valve is open or opens, or drywell l* THEN return to step 1 of this procedure. l_____________________________l l WEITe eiecuitsg siois 2 tKr6ugn 5i - - - - - - - - - - l* lE Emergency RPV Depressurization is required. l* THENexitthisprocedureandenterQGA-500-2. Emergency l* ___ ______l Reactor Pressure Vessel Depressurization. l lE a high drywell pressure ECCS automatic initiation signal (+2.0 psig) l' occurs or exists while depressurtzing the reactor pressure vessel, l THEN before reactor pressure vessel pressure decreases to 325 psig, l* prevent injection from those core spray and RHR pumps not required l to assure adequate core cooling. l* WHEN the high drywell pressure ECCS automatic intt1ation l signal clears, (* THEN restore core spray and RHR to AUTCMATIC/ STANDBY. l______________________________________I APPROVED OCT 315 O. C. O. S. R. 2/0053g 1 I
El OGA 500-7 Revision 1 3
- 2.
Maintain RPV water level as follows: CAUTION A rapid increase in injection into the I RPV may induce a larger power excursion and result in substantial core damage. I a. IF RPV water level was deliberately lowered in step 1 I THEN maintain RPV water level at the level to which is was lowered. Use one or more of the systems listed below. b. IF RPV water level was not deliberately lowered in step 1 THEN maintain RPV water level between +8 in. and +48 in. Use one or more of the system listed below. I I p System Procedure for System Operation I l____________1______1_____________I l l Condensate /Feedwater lQOP3300-2'l 1350 - O psig l lRCIC-BUTdonot lQOP1300-2 l 1150-50 pstg l operate turbine l below 2200 rpm l l l l l HPCI - But do not l QOP 2300-6 l 1150 - 100 psig l operate turbine l below 2200 rpm l l l unless aux. oil l l pump is running l l l l Safe shutdown pump l00P2900-2 l 1150 - O psig l l l CRD l QOP 300-16 l 1500 - O psig l 3. IF RPV water level cannot be maintained as instructed in step 2, THEN maintain RPV water level above - 143 in. (TAF). Use one or more of the systems Itsted above (step 2). II APPROVED OCT 311985 i f E 0.C. O. S. R. 3 2/00539 ' 1 I c pe w r -w-m - - -,mv w --m,ww-~,w ,,,_ ~
QGA 500-7 Reeision 1 l~HEiTe~eiscuilig~tEliprocedure:-~-~~~~~~~-~~l IF RPV water level cannot be determined, l l TREN RPV FLOODING IS REQUIRED exit this procedure and l enter QGA 500-6, Reactor Pressure Vessel Flooding l lE all control rods are inserted to or beyond l 5 position 04, l THEN exit this procedure and enter QGA 100-1, Reactor l Pressure Vessel Water Level Control, at step 5. l_____________________________I lH6tTe~eieiuitHgsieis~2tsr6uih'4T~---~~-~~--l ~ lE reactor power is above 37,or cannot be determined. l l g RPV water level is above - 143 in., A A_ND suppression pool temperature is above 110*F. l either an ADS valve is open or opens, or drywell l jA pressure is above 2.0 psig, l THEN return to step I of this procedure. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l l~HhlieexecuIiEg'sieps'2tEr6ughST-~~~~~~--~~l lE Emergency RPV Depressurization is recuired, l THEN exit this procedure and enter QGA-500-2, Emergency l _ _ _ Reactor Pressure Vessel Depressurization. _ _ _ _ _ _l lE a high drywell pressure ECCS automatic initiation signal (+2.0 psig) l occurs or exists while depressurizing the reactor pressure vessel, l THEN before reactor pressure vessel pressure decreases to 325 psig, l prevent injection from those core spray and RHR aumps not requirnd l to assure adequate core cooling. l WHEN the high drywell pressure ECCS automatic initiation l stqnal clears, l THEN restore core spray and RHR to AUTOMATIC /STANOBY. l_________________________________.-____l APPROVED oc n uess g Ol O. C. O. S. R. 2/00539 6- -~ --w -ww -w-- y,. m
QGA 500-7 Revision 1 4. IF RPV water level cannot be maintained above -143 in., I] TIIEN EMERGENCY RPV DEPRESSURIZATION IS REQUIRE 0; exit this procedure and enter QGA 500-2, Emergency RPV Depressurization. ) Continue to terminate and prevent all injection into the RPV, a. as instructed by QGA 500-2, EXCEPT do not terminate injection from boron injection systems and CRO. ' Il I UNTIL RPV pressure is below l that specified in l Nuiiber--l-- RPV --l the table alongside. of Open Pressure i LF less than 2 lAOSvalvesl (PSIG) l l ADS valves can be opened. l- --l-- 215 --l l l THEN continue in this 4 270 procedure at l 3 l 365 l I step 4b. 2 555 l-_-_----_--_l I A rapid increase in injection into the RPV may induce a large power excursion i and result in substantial core damage. b. Commence and slowly increase injection into the RPV with one l or more of the systems listed below to restore and maintain RPV pressure above that specified in tne table in step 4a until RPV water level is a above -143 in. (TAF). Then maintain RPV water level above -143 in. (TAF). l System Procedure for System Operation l----__--__- I-----_1_-_--_-------l l Condensate /Feedwater l 00P 3300-2 l 1350 - O psig l 1 l RCIC - BUT do not lQOP1300-2 l 1150-50 psig I 1 operate turbine l below 2200 rpm l l l l HPCI - But do not l QOP 2300-6 l 1150 - 100 psig l operate turbine l below 2200 rpm l l l unless aux. oil l pump is running l l l l Safe shutdown pump l QOP 2900-2 l 1150 - O psig l 5 l CR0 l QOP 300-16 l 1500 - O psig l l LPCI mode of RHR l 00A 1000-7 l 325 - O psig l APPROVED 2/00539 0. C. O. S. R. l
QGA 500-7 Reetsion 1
l lHElIeexecuitigtElsirocedure:- - - - - -
IF RPV water level cannot be determined, l lTiiENRPVFLOODINGISREQUIRED;exitthisprocedureand l enter QGA 500-6, Reactor Pressure Vessel Flooding l lE all control rods are inserted to or beyond l position 04, l THEN exit this procedure and enter QGA 100-1, Reactor l Pressure Vessel Water Level Control, at step 5. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I l HEtIe eiefui1Eg sieds 2 tErdugh 4I - - - - - - - - - -l lE reactor power is above 3% or cannot be determined l AND RPV water level is above - 143 in., lAND suppression pool temperature is above 110*F, l AND either an ADS valve is open or opens, or drywell l pressure is above 2.0 psig, l THEN return to step 1 of this procedure. l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _I I l WEITe execuiiKg steis 2 tEr6 ugh 5I - - - - - - - - - 1 lE Emergency RPV Depressurization is required, l THENexitthisprocedureandenterQGA-500-2. Emergency l___ Reactor Pressure Vessel Depressurization. _ _ _ _ _ _l l I_F a blah drywell pressure ECCS automatic initiation signal (+2.0 psig) l occurs or exists while depressurizing the reactor pressure vessel, l THEN before reactor pressure vessel pressure decreases to 325 psig, l prevent injection from those core spray and RHR pumps not reautred l to assure adequate core cooling. l WHEN the high drywell pressure ECCS automatic initlation l signal clears, l l THEN restore core spray and RHR to AUTOMATIC /STA M BY. l l______________________________________I l While executing step 5:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l* t l I_F reactor power commences and continues to increase l* THEN return to step 1 of this procedure l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l* ppROVED b T 31N l I 2/0053g 8-3.C.O.S R-l ~
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QGA 500-7 Revision 1 CD 4. (Continued) IF RPV water level cannot be restored and maintained above c. - 143 in. (TAF), THEN commence and slowly increase injection into the RPV with one or more of the following systems to restore and maintain RPV water level above -143 in. T 0Ma% I System Procedure l____________1______1 lCS l QOA 1400-2 l lECCSkeepfill l QOP 1400-3 l l CR0 pump from l QOP 300-19 l other unit l___________________l 5. WHEN 340 pounds of boron have been injected into the RPV (a change of 457. in SBLC tank level; refer to QGA 500-T3, Boron I Injection Heights). THEN restore and traintain RPV water level between +8 in. and +48 in. a. IF RPV water level canndt be maintained above +8 in., THEN maint H RPV water level above -143 in. (TAF). l b. IF RPV Mter level cannot be maintained above -143 in., u TREN EMERGElCY RPV OEPRESSURIZATION IS REQUIRE 0, ex1t thi5 l procedure and enter QGA 500-2, Emergency Reactor Pressure Vessel Depressurization. i 6. WHEN QGP 2-3, Reactor Scram, is entered from QGA 100-2, Reactor Pressure Vessel Pressure Control, THEN exit this procedure and proceed in acccrdance with QGA 2-3, Reactor Scram. II II APPROVED OCT 311985 lO, O. C. O. S. R. (final) 2/0053g I I l
QGA 500-8 Revision 1 October 1985 INJECTION OF BORON USING THE REACTOR WATER CLEANUP SYSTEM I A. E, m CO,o m 0,s Entry to this procedure is required as specified in QGA 100-3, Reactor i Power Control. II IIi g I .IIIIO IIiII 'IIII Ig II Ig APPROVED IlO 00T 311985
- 0. C. O. S. R.
2/0054g II I
Isi!$~i i I I THIS PAGE INTENTIONALLY BLANK ( APPRC'ED OCT 31985 = o.c.c 3. R. II 1 Oi 2/00549 2-I w - tew-s- +=-m m------ww_ wwww. ,,y--we w weew
QGA 500-8 Revision 1 B. OPERATOR ACTIONS l 1. IF a Group III isolation exists. MEN bypass the isolation in accordance with QGA 500-T2, Bypassing the Low Reactor Water Level Group III Isolation Signal. 2. Remove the cleanup domins from service in accordance with QOP 1200-3. 3. Backwash the cleanup domins in accordance with QOP 1200-4. 4. IF the boron solution in the SBLC tank is available, THEN a. Verify drain valve 1101-20 is closed and connect a 1-1/2 I inch hose from the drain line to the precoat tank. b. Orain the precoat tank by opening valve 1279-50; close valve 1279-50 when precoat tank is empty. c. OPEN valve 1101-20 to fill the precoat tank with boron solution. 5. IF the boron solution in the SBLC tank is NOT available, W EN prepare boron solution as follows: I a. Fill the large precoat tank 3/4 full of water. b. Start the tank agitator, c. Add 65 pounds of boric acid and 65 pounds of borax alternating between boric acid and corax while making the addition. NOTE l l 65 pounds is 1/5 of a 325 pound drum of borax or boric acid. NOTE This is enough solution to fill one i l domin. 6. Drain a cleanup demin as follows: a. Open valve A0-1279-18 A/B, filter demin vent. b. Open valve RM-1279-28 A/B, filter demin dome vent. c. Open valve RM-1279-22 A/B, filter demin drain. d. Allow the demin to drain for 5 minutes then close valves I RM-1279-22 A/B, A0-1279-18, and RM-1279-22 A/8. OCT 311985 ~
- 0. C. O. S. R.
g I
-.m.. eli 1, Ii _i, 1,-,_z_ _ I
- li II APPROVED OCT 311985 0.c.o. s. n.
2/0054g I'
l QGA 500-8 Revision 1 7. F111 a cleanup domin with boron solution as follows: a. OPEN valve A0 1279-18 A/B; filter domin vent b. Open valve RH 1279-40 A/B; precoat inlet l c. Verify open valve RM 1279-12; precoat tank to precoat pump d. Verify closed valve RM 1279-38 A/B; filter demin precoat return e. Verify closed valve RM 1279-26 A/B; filter demin outlet f. Verify closed valve RM 1279-30 A/B; filter demin dome drain g. Verify closed valve RM 1279-13 A/B; filter demin inlet h. Verify closed valve RM 1279-22 A/B; filter demin drain 1. Close valve 1201-85; service air to filter demin j. Start the precoat pump k. Open A0 12379-41 A/B; precoat pump discharge valve 1. Open RM 1279-28 A/B; filter demin dome vent I m. Fill the demin until solution can be seen through the dome vent sightglass n. Close A0 1279-41 A/B; precoat pump discharge valve o. Stop the precoat pump p. Close A0 1279-18 A/B; filter demin vent 8. Return the demin to hold by pressing the recycle reset button, i 9. Pressurize the demin by opening the needle valve between PI 1279-68 and PI 1279-79 A/B until the pressure indicators are equalized. I Then close the needle valve.
- 10. Slowly open RM 1279-26 A/B; filter demin outlet l
- 11. Close RM 1279-28 A/B; filter demin dome vent
- 12. Close RM 1279-40 A/B; precoat tank inlet
- 13. Place the demin in service in accordance with QOP 1200-6 14.
Repeat steps 4 to 12 for the otner demin APPROVED OCT 311985 2/0054g 0. C. O. S. R. 1
is on 1 e i 0 THIS PAGE INTENTIONALLY BLANK 4 l iPPROVED l JCT 311985
- 0. C. O. S. R.
Ss 1 E
QGA 500-8 Revisten 1
- 15. Repeat steps 2 to 12 (with the exception of step 3) alternating domins until either:
All rods have been inserted to or beyond position 04, or a. I b. 537 pounds of boron have been injected into the RPV (refer to i QGA 500-T3 for determining amount of boron injected) II II II II II10 I II II II II I ' I I APPROVED OCT 311985 gg I 0.c.u a. <,,n,,, 2/0054g I
I QGA 500-9 Revision 2 January 1987 I STANDBY LIQUID CONTROL TEST TANK INJECTION I A. ENTRY CONDITIONS Entry to this procedure is required as specified in QGA 500-1, Level I Restoration. I I I I I APPROVED JAN 171987 2/0055g Q.C.O.S.R. l
QGA 500-9 Revision 2 I I I I THIS PAGE INTENTIONALLY BLANK I I E I l AP. PROVED JAN171987 I Q.C.O.S.R. I 2/0055g :
GGA 500-9 Revision 2 B. OPERATOR ACTIONS 1. Fill the test tank about 3/4 full of water using valve 1101-7 to run domineralized water into the test tank. 2. CLOSE VALVE 1101-4, S8LC tank suction valve. 3. CLOSE VALVE 1199-104, SBLC tank suction valve. (UNIT TWO ONLY) 4. OPEN VALVE 1101-8, SBLC test tank suction valve. 5. Obtain the key for the standby liquid control switch from the Shift Engineer. 6. From the control room, start either A or B SBLC pump and fire the squib valve by turning the standby 11guld control switch to SYS 1 or SYS 2. On Unit Two, turn the switch to the two pump operation position. 7. Verify that the squib continuity light goes out for the squib valve (s) fired. I 8. Verify that the SBLC flow light comes on. I 9. Monitor the test tank locally and maintain level between 1/4 and 3/4 full by adding water. 10. If water cannot be added to the test tank, the SBLC pump should be I stopped before the test tank is empty.
- 11. When test tank injection is no longer required, stop the running SBLC pumps.
- 12. CLOSE and lock VALVE 1101-8, SBLC test tank suction valve.
- 13. OPEN and lock VALVE 1101-4, SBLC tank suction valve.
- 14. OPEN and lock VALVE 1199-104, SBLC tank suction valve.
(UNIT TWO ONLY) 15. Initiate a work request to replace any squib valves fired during this procedure. I I APPROVED JAN 171987 (final) 2/0055g Q.C.O.S.R. I
I QGA 500-T1 Q BYPASSING LOW LOW REACTOR WATER Revision 1 LEVEL GROUP I ISOLATION SIGNAL October 1985 This checklist provides the necessary jumpers to bypass the Group I isolation from low low reactor water level. This should only be performed when required by an emergency operating procedure. 1. Procedure requiring installation 2. Installation approved by I (OE) NOTE I Approval need not be obtained if an Operating Engineer is not available. 3. In panel 901-15 (902-15): a. Install a jumper between terminals 3 and 4 on relay 595-100A. I Jumper # b. Install a jumper between terminals 3 and 4 on relay 595-100C. Jumper # 4. In panel 901-17 (902-17): a. Install a jumper between terminals 3 and 4 on relay 595-1008. Jumper # b. Install a jumper between terminals 3 and 4 on relay 595-1000. Jumper # (I 5. Above jumpers installed by (SRO) (Date/ Time) 6. This sheet should be placed in the jumper log as a record of installation. 7. When removal of the interlock bypass is required: a. In panel 901-15 (902-15) remove: (1) Jumper # _ between terminals 3 and 4 on relay 595-100A (2) Jumper # _ between terminals 3 and 4 on relay 595-100C I IO ^ee" v' OCT 311985 1/0033g 0. C. O. S. R. II l
QGA 500-71 1 Revision 1 i b. In panel 901-17 (902-17) remove: (1) Jumper # between terminals 3 and 4 on relay 595-1008 (2) Jumper # between terminals 3 and 4 on relay 595-1000 8. Jumpers removed by (SRO) (Date/ Time) 9. Removal verified by (SR0) (Date/ Time) I I I O I I I I I I. iI APPROVED OCT 311985 O.C.O.S.R. l 1/00339 I
QGA 500-T2 Revision 1 October 1985 IO BYPASSING THE LOW REACTOR WATER LEVEL GROUP III ISOLATION SIGNAL This checklist provides the necessary jumpers to bypass the Group III isolation from low reactor water level. This should only be performed when required by an emergency operating procedure. 1. Procedure requiring installation 2. Installation approved by NOTE Approval need not be obtained if an Operating Engineer is not available. l 3. In panel 901-17 (902-17): a. Install a jumper between A-41 and A-42 Jumper # NOTE This maintains relay 595-124 in the I energized position. b. Install a jumper between 0-58 and 0-59 Jumper # NOTE This maintains relay 595-123 in the energized position. 4. Above jumpers installed by (SRO) (Date/ Time) 5. This sheet should be placed in the jumper log as a record of installation. 6. When removal of the interlock bypass is required: a. In panel 901-17 (902-17) remove: (1) Jumper # between A-41 and A-42. I (2) Jumper # between 0-58 and 0-59. 7. Jumpers removed by I (SR0) (0 ate / Time) g 8. Removal vertfled by APPROVED (SRO) (Oate/ Time) OCT 311985 (finai> ' ' ** 4 ~ Il o.c. o. s. n. I
l OGA 500-T3 IO Revision 1 October 1985 BORON INJECTION WEIGHT This checklist provides the necessary information to ccepute tank levels or chemical weights for a given boron injection weight. A. Boron injection using standby liquid control 1. Change in tank level .01328 (boron injection weight) (SBLC tank concentration) 2. Boron injection weight (A) pounds 3. SBLC tank concentration (B) - 4. Change in tank level .01328 ( lb) ( %) (A) (B) 8. Boron injection using cleanup system 1. Weight of borax (1b) - 3.53 (boron injection weight) 2. Weight of boric acid (Ib)- 3.53 (boron injection weight) I 3. Hot shutdown weight - 340 pounds O* Weight of borax needed - 1200.2 pounds Weight of boric acid needed - 1200.2 pounds 4. Cold shutdown weight - 537 pounds Weight of borax needed - 1895.6 pounds Weight of boric acid needed - 1895.6 pounds I I I I l APPROVED OCT 311985
- o. c. o. S. R.
(final) I 1/0035g _1 a
QGA 500-T4 I Revision 1 I ,U BYPASSING THE GROUP II ISOLATION AND REACTOR BUILDING VENTILATION ISOLATION This checklist provides the necessary jumpers to bypass the Group II isolation to the containment vent valves, SBGT auto start, the reactor building vent isolation. 1. Procedure requiring installation I 2. Installation approved by (OE) NOTE Approval need not be obtained if an Operating Engineer is not available. 3. In panel 901-15 (902-15): a. Install a jumper between B-49 and 8-50 Jumper # NOTE This maintains relay 595-134 in the energized position. b. Install a jumper between E-38 and E-39 Jumper # NOTE t This maintains relay 595-133 in the energized position. 4. Above jumpers installed by 5. This sheet should be placed in the jumper log as a record of installation. 6. When removal of the interlock bypass is required: APPROVED a. In panel 901-15 (902-15) remove: OCT 311985 l (1) Jumper # between B-49 and B-50. O. C. O. S. R. _ 2) Jumper # between E-38 and E-39. ( 7. Jumpers removed by (SRO) (Date/Ttme) 8. Removal vertfled by (SRO) (Oate/ Time) (final) 1/00349 ' I
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