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PART B: PUMPS AND VALVES
PART B: PUMPS AND VALVES l
!                                                                                                                                                                                                                                            l l                                              INSERVICE                                           INSPECTION                                           P R 0 G.R A M j
l INSERVICE INSPECTION P R 0 G.R A M j
l                                                                                                                                                                                                                                           ?
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f LA SALLE COUNTY STATION UNIT 2
f LA SALLE COUNTY STATION UNIT 2
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)
COMM0:lWEALTH EDIS0N COMPANY 9
COMM0:lWEALTH EDIS0N COMPANY 9
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!                                                                                                  AUGUST 31, 1983 1
AUGUST 31, 1983 1
t l
t l
l 1
l 1
l PREPARED BY LA SALLE STATION TECHNICAL STAFF (OPERATIONS)
l PREPARED BY LA SALLE STATION TECHNICAL STAFF (OPERATIONS)
I
I IN CONJUNCTION WITH f
!                                                                                            IN CONJUNCTION WITH f                                                                   LA SALLE PROJECT ENGINEERING GROUP (DESIGN) l I
LA SALLE PROJECT ENGINEERING GROUP (DESIGN) l I
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Commonw=lth Edi2on
@ LaSalleCountyNuclearStationUnit 2 Commonw=lth Edi2on O
  @ LaSalleCountyNuclearStationUnit 2 O
PUMP AND VALVE INSERVICE TESTING PLAN TABLE OF CONTENTS Tab Description Table of Contents 1
PUMP AND VALVE INSERVICE TESTING PLAN TABLE OF CONTENTS Description                             Tab 1
Inservice Testing Plan - Description 2
Table of Contents Inservice Testing Plan - Description     2 Fomat Legend and Notes                   3 Inservice Testing Plan - Pumps           4 Relief Recuests - Pumps                   5 Inservice Testing Plan - Valves           6 Relief Recuests - Valves                 7 O
3 Fomat Legend and Notes 4
Inservice Testing Plan - Pumps Relief Recuests - Pumps 5
Inservice Testing Plan - Valves 6
Relief Recuests - Valves 7
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b                               ~
b Commonwealth Edison
Commonwealth Edison LcSalle County Nuclear Stat 6on Unit 2 INSERVICE TESTING PLAN DESCRIPTION
~
: 1.                                           APPLICABLE ASME CODE INSERVICE TESTING 1.1         The Inservice Testing of equipment in NRC Quality Groups A, B, C, and D+ are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1980 Edition through Winter 1980 Addenda, except where specific written relief from examinations and testings determined to be impractical has been grar.ed by the NRC pursuant to 10 CFR Part 50, Section 50.55 a (g) (6) (i) . Known relief requests from ASME Code Section XI requirements are included in the Inservice Testing Plan.
LcSalle County Nuclear Stat 6on Unit 2 INSERVICE TESTING PLAN DESCRIPTION 1.
: 2.                                     PUMPS AND VALVES TESTED IN ACCORDANCE WITH ASME SECTION XI SUBSECTIONS IWA, IWP, AND IWV 2.1         All ASME Code Class 1, 2, and 3 safety-related pumps that are provided with an emergency power-source are tested in accordance with ASME Section XI IWP-30J0.              .
APPLICABLE ASME CODE INSERVICE TESTING 1.1 The Inservice Testing of equipment in NRC Quality Groups A, B, C, and D+ are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1980 Edition through Winter 1980 Addenda, except where specific written relief from examinations and testings determined to be impractical has been grar.ed by the NRC pursuant to 10 CFR Part 50, Section 50.55 a (g) (6) (i).
2.2         All ASME Code Class 1, 2, and 3 safety-related valves have been reviewed against the exclusion criteria of ASME Section XI IWV-1200.
Known relief requests from ASME Code Section XI requirements are included in the Inservice Testing Plan.
2.3         All ASME Code Class 1, 2, and 3 safety-related valves, which are not excluded by Section 2.2 above, are categorized and tested in accordance witn ASME Section XI IWV- 2200 and IWV-300 0.
2.
2.4         Inservice Testing boundary classifications for pumps and valves are included in the Preservice Inspection Report as the Preservice Inspection Records Index.
PUMPS AND VALVES TESTED IN ACCORDANCE WITH ASME SECTION XI SUBSECTIONS IWA, IWP, AND IWV 2.1 All ASME Code Class 1, 2, and 3 safety-related pumps that are provided with an emergency power-source are tested in accordance with ASME Section XI IWP-30J0.
: 3.                               INSERVICE TESTING 3.1         When a pump or valve is determined to be impractical to test in accordance with respective ASME Section XI IWP-3000 or IWV-3000, a specific written relief request from the ASME Code is submitted to the NRC (in accordance with Section 1.1 above). Each written relief request contains the following information as a minimum.
2.2 All ASME Code Class 1, 2, and 3 safety-related valves have been reviewed against the exclusion criteria of ASME Section XI IWV-1200.
3.1.1         Identification of pump (s) or valve (s) for which 4
2.3 All ASME Code Class 1, 2, and 3 safety-related valves, which are not excluded by Section 2.2 above, are categorized and tested in accordance witn ASME Section XI IWV-2200 and IWV-300 0.
relief is requested.
2.4 Inservice Testing boundary classifications for pumps and valves are included in the Preservice Inspection Report as the Preservice Inspection Records Index.
3.1.2         Function of pump (s) or valve (s) .
3.
3.1.3       ASME Section III Code Class and Category O-                                                                                                                                                                        (valves only) .
INSERVICE TESTING 3.1 When a pump or valve is determined to be impractical to test in accordance with respective ASME Section XI IWP-3000 or IWV-3000, a specific written relief request from the ASME Code is submitted to the NRC (in accordance with Section 1.1 above).
Each written relief request contains the following information as a minimum.
3.1.1 Identification of pump (s) or valve (s) for which relief is requested.
4 3.1.2 Function of pump (s) or valve (s).
O-3.1.3 ASME Section III Code Class and Category (valves only).
1
1
                                                                                                                                                                                                                                          )
)


C mmonw; lth Edison LcSdie County Nucle r St tton Unit 2 3.1.4         The specific ASME Code requirement that is determined to be impractical.
C mmonw; lth Edison LcSdie County Nucle r St tton Unit 2 3.1.4 The specific ASME Code requirement that is determined to be impractical.
3.1.5         LSCS relief justification (s) information fer requesting relief.
3.1.5 LSCS relief justification (s) information fer requesting relief.
3.1.6         Specific alternative test (s) in lieu of ASME Code Section XI requirement (s).
3.1.6 Specific alternative test (s) in lieu of ASME Code Section XI requirement (s).
3.3       All records and reports are prepared in accordance with ASME Section XI IWA-6000.
3.3 All records and reports are prepared in accordance with ASME Section XI IWA-6000.
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Commonwealth Edison
Commonwealth Edison
(                   tcsaue county Nuclear Station Unit 2 i
(
tcsaue county Nuclear Station Unit 2 i
INSERVICE TESTING PLAN FORMAT LEGDO AQ NOTES
INSERVICE TESTING PLAN FORMAT LEGDO AQ NOTES
: 1. AS*E CLASS 1, 2, AND 3 PNS FIELD                                             DESCRIDTION 00         PM tO4EER                               Pump numoer as used on the P&ID.
: 1. AS*E CLASS 1, 2, AND 3 PNS FIELD DESCRIDTION 00 PM tO4EER Pump numoer as used on the P&ID.
01           PM NAE                                 Pump word description and name.
01 PM NAE Pump word description and name.
02          CLASS ASE Section III Code Classification (1, 2, or 3).
ASE Section III Code Classification (1, 2, or 3).
03           P&ID NO.                               Piping and Instrumentation Drawing Nuncer. All drawing nurters are prefixed with "M". Sheet nuncers follow the drawing numoer.
02 CLASS 03 P&ID NO.
04           COORDINATES                             Pump coordinates on P&ID.
Piping and Instrumentation Drawing Nuncer. All drawing nurters are prefixed with "M".
Speed of guno to be measured. N/ A       Not 05            SPEED Applicable. All the CumDs with N/A in the steed colunn are either syncnorous or incuction me ::
Sheet nuncers follow the drawing numoer.
04 COORDINATES Pump coordinates on P&ID.
05 SPEED Speed of guno to be measured. N/ A Not Applicable. All the CumDs with N/A in the steed colunn are either syncnorous or incuction me ::
driven and do not require speed measurements.
driven and do not require speed measurements.
06             IM.ET PRESS                           Inlet pressure of gump to be measured.
06 IM.ET PRESS Inlet pressure of gump to be measured.
07             01FF. PRESS.                         Differential pressure of cump to be measureo, N/A, Not applicable for positive displarement gumps.
07 01FF. PRESS.
08           FLOW RATE                             Flow rate of gump to be measured 09           VIBRATION Vibration amplitude of rump to be measured. - See RP-CA.
Differential pressure of cump to be measureo, N/A, Not applicable for positive displarement gumps.
10             BEARING TEW .                         Bearing temperature of pump to De measured - See RP-Ol.
08 FLOW RATE Flow rate of gump to be measured 09 VIBRATION Vibration amplitude of rump to be measured. - See RP-CA.
11             TEST INTERVAL                         Testing interval of pumps and any Relief Requests. Relief nuncers are prefixed by "RD" for pumps ("RV" for valves).
10 BEARING TEW.
Bearing temperature of pump to De measured - See RP-Ol.
11 TEST INTERVAL Testing interval of pumps and any Relief Requests. Relief nuncers are prefixed by "RD" for pumps ("RV" for valves).
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n)         Commonwealth Edison LcSado County Nuclear Station Unit 2 l                                       II ASE CLASS 1, 2, AND 3 VALVES FIELD                                                       DESCRIPTION f     00     VALVE RMER                       Valve number as used on the P&ID.
n )
01     SIZE                             Nominal size of valve in inches.
Commonwealth Edison LcSado County Nuclear Station Unit 2 l
02     P&ID PO.                         Piping and Instrumentation Drawing Mscer. All drawing nureers are prefixed with "M". Sheet nureers follow the drawing nureer.
II ASE CLASS 1, 2, AND 3 VALVES FIELD DESCRIPTION f
03     COORDINATES                       Valve location on P&ID.
00 VALVE RMER Valve number as used on the P&ID.
04     CLASS CATECORY                   ASE Section III Code Classification (1, 2, or 3) followed by the Valve Category ( A, B, C, 0, OR E). tC is used for valves which do not have an ASE Section III Class.
01 SIZE Nominal size of valve in inches.
05     VALVE TYPE                       AG       Angle BL       Ball EF       Butterfly CNV Control Valve
02 P&ID PO.
Piping and Instrumentation Drawing Mscer. All drawing nureers are prefixed with "M".
Sheet nureers follow the drawing nureer.
03 COORDINATES Valve location on P&ID.
04 CLASS CATECORY ASE Section III Code Classification (1, 2, or 3) followed by the Valve Category ( A, B, C, 0, OR E). tC is used for valves which do not have an ASE Section III Class.
05 VALVE TYPE AG Angle BL Ball EF Butterfly CNV Control Valve 08 Dott:le Block
(
(
08        Dott:le Block i                                                EFC Excess Flow Check FCV Flow Control Valve GB       Globe q                                              GT       Gate WC Manual Flow Control PN       Needle Valve NSC Non-Slam Check P         Plug PG       Packless Globe PRV Pressure Regulator Valve RV       Relief Valve S         Safety SRV Safety Relief Valve SC       Stop Check
EFC Excess Flow Check i
                .                              CV         Check Valve 06     ACTUATOR TYPE                     A0       Air Operator AS       Air Spring Ex       Explosive M         Manual MO       Motor Operated SO         Solenoid Operated SP       Spring 07     VALVE POSITIL"!                   C         Normally Closed 0         Normally Open L.O. Locked Open L.C. Locked Closed O                                                                 Page 2 l
FCV Flow Control Valve GB Globe GT Gate q
WC Manual Flow Control PN Needle Valve NSC Non-Slam Check P
Plug PG Packless Globe PRV Pressure Regulator Valve RV Relief Valve S
Safety SRV Safety Relief Valve SC Stop Check CV Check Valve 06 ACTUATOR TYPE A0 Air Operator AS Air Spring Ex Explosive M
Manual MO Motor Operated SO Solenoid Operated SP Spring 07 VALVE POSITIL"!
C Normally Closed 0
Normally Open L.O. Locked Open L.C. Locked Closed O
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Commonwraith Edison '
Commonwraith Edison '
tcsaise county Nuclear Station Unit 2 II ASE CLASS 1, 2, APO 3 VALVES - CON'T.
tcsaise county Nuclear Station Unit 2 II ASE CLASS 1, 2, APO 3 VALVES - CON'T.
    ]
]
FIELD                                                         DESCRIPTION ,
FIELD DESCRIPTION 08 TEST E
08   TEST                                 E       Exercise FS     Full Stroke PS     Part Str H Exercise ST     Stroke Time LV     Locked Valve (Administrative controls, No Senedule)
Exercise FS Full Stroke PS Part Str H Exercise ST Stroke Time LV Locked Valve (Administrative controls, No Senedule)
RV     Verify set points in accordance with IW-3510 FC     Fire Explosive Charge LT     Leak Test in Accordance with FSAR Table 6.2-21 PIT Position Indiction check FST Fail Safe Test 09   TEST SCHEDLLE                       Q       Quarterly, 92 Days CS     Cold Shutdown (IST), See Note (3)
RV Verify set points in accordance with IW-3510 FC Fire Explosive Charge LT Leak Test in Accordance with FSAR Table 6.2-21 PIT Position Indiction check FST Fail Safe Test 09 TEST SCHEDLLE Q
RR     Reactor Refueling EV     IW-3610 10   Max. STROKE TIE                       The maxinum allowed stroke time for valves requiring stroke time measurement 11   RELIEr REQJEST                       A relief request nuceer when a scecific code requirement is determined to be impractical.
Quarterly, 92 Days CS Cold Shutdown (IST), See Note (3)
Relief recuest numbers for valves are prefixed with "RV". ("RP" for cumps) 12   ACTIVE OR PASSIVE                     Active "A" valves are valves which are recuired to change position to accomplish a specific function. Passive"P" valves are valves which are not recuired to change position to accomclism a specific fmetion.
RR Reactor Refueling EV IW-3610 10 Max. STROKE TIE The maxinum allowed stroke time for valves requiring stroke time measurement 11 RELIEr REQJEST A relief request nuceer when a scecific code requirement is determined to be impractical.
13   REMMKS                               General valve descriptions or comments.
Relief recuest numbers for valves are prefixed with "RV". ("RP" for cumps) 12 ACTIVE OR PASSIVE Active "A" valves are valves which are recuired to change position to accomplish a specific function. Passive"P" valves are valves which are not recuired to change position to accomclism a specific fmetion.
13 REMMKS General valve descriptions or comments.
III NOTES (1) In accordance with AST Section XI IW-3410 (b) (1) and IW-3520 (b) these valves are exercised to the position required to ful'ill their function during Cold Shutcown or Reactor Refueling as apolicaole.
III NOTES (1) In accordance with AST Section XI IW-3410 (b) (1) and IW-3520 (b) these valves are exercised to the position required to ful'ill their function during Cold Shutcown or Reactor Refueling as apolicaole.
(2) Safety valves and relief valves are tested during Reactor Refueling; however, individual valves are scheduled inaccordance witn AS{ Section XI Table IW-3510-1.
(2) Safety valves and relief valves are tested during Reactor Refueling; however, individual valves are scheduled inaccordance witn AS{ Section XI Table IW-3510-1.
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    'I
d Commonw cith Edison
      \
'I
d        Commonw cith Edison Lcs ile county Nuclear Station Unit 2                                           l l
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III NOTES - CON'T O
Lcs ile county Nuclear Station Unit 2 III NOTES - CON'T O
V     (3) Inservice valve testing at cold shutdom is defined as:
V (3) Inservice valve testing at cold shutdom is defined as:
Valve testing unicn conmeces not later than forty eipt (48) hours after cold snutcom mc continues mtil reovired testing is completed or plant start-up, unicnever occurs first. Completim of all reovirac valve                   l testing is not a remisite to pimt start-up. valve testing which is not completed di. iring a cold shutcom will oe performed curing suosecuent cold shutcoms to meet tne code specified testing requiremets. to valve will               :
Valve testing unicn conmeces not later than forty eipt (48) hours after cold snutcom mc continues mtil reovired testing is completed or plant start-up, unicnever occurs first. Completim of all reovirac valve testing is not a remisite to pimt start-up. valve testing which is not completed di. iring a cold shutcom will oe performed curing suosecuent cold shutcoms to meet tne code specified testing requiremets. to valve will De testec more ofte tnm cnce every 90 days.
De testec more ofte tnm cnce every 90 days.
l Also, some valves require entry into the ecntainmot to perform the test, suen valvss will only be testec men the crywell is de-inertec.
l Also, some valves require entry into the ecntainmot to perform the test, suen valvss will only be testec men the crywell is de-inertec.
Note:       It is expected that the required inservice valve testing will normally oe completec in 120 hours following colo snutcom.
Note:
However, congleticn of all valve testing curing colo shutcom is not required if plot operating etnditims will not permit tne testing of specific valves.                                             ;
It is expected that the required inservice valve testing will normally oe completec in 120 hours following colo snutcom.
However, congleticn of all valve testing curing colo shutcom is not required if plot operating etnditims will not permit tne testing of specific valves.
In tne event that a valve must be declared inoperaole as a result of cole snutcom testing ( AS{ Coce, Sectim XI, IW-3410 (g) a,c IW-3520 (c))
In tne event that a valve must be declared inoperaole as a result of cole snutcom testing ( AS{ Coce, Sectim XI, IW-3410 (g) a,c IW-3520 (c))
the applicaole unit start-up limitatims will be as stated in the tecnincal specificaticn, limiting cmcitims for operaticns.
the applicaole unit start-up limitatims will be as stated in the tecnincal specificaticn, limiting cmcitims for operaticns.
(4) 10 CFR 50 Appendix J Type C Test.
(4) 10 CFR 50 Appendix J Type C Test.
G U      (5) Reactor Coolant System Pressure Isolation Valves, leak tested per Tech.
GU (5) Reactor Coolant System Pressure Isolation Valves, leak tested per Tech.
Spec. 4.4.3.2.2.
Spec. 4.4.3.2.2.
(6) Test pressure is not in the same direction as the pressure existing when the valve is required to perform the safety function as required by Appendix J to 10 CFR 50. Either manufacturers' test data, site test results, or justification (e.g. , reverse test pressure tending to lif t disk from seat) will be available on site to verify that testing in the reverse direction will provide either equivalent or more conservative results. (From FSAR Table 6.2-21 Note 20).
(6) Test pressure is not in the same direction as the pressure existing when the valve is required to perform the safety function as required by Appendix J to 10 CFR 50.
(7) These lines have been evaluated to an acceptable alternative design                 '
Either manufacturers' test data, site test results, or justification (e.g., reverse test pressure tending to lif t disk from seat) will be available on site to verify that testing in the reverse direction will provide either equivalent or more conservative results.
I basis other than that specifically listed in GDC 56. This alternate basis is found in SRP 6.2.4.II.3.e, and the evaluation to the criteria specified therein is as follows:
(From FSAR Table 6.2-21 Note 20).
: a. All lines are in engineered safety feature or engineered safety feature-related systems.
(7) These lines have been evaluated to an acceptable alternative design basis other than that specifically listed in GDC 56. This alternate basis is found in SRP 6.2.4.II.3.e, and the evaluation to the criteria specified therein is as follows:
: b. System reliability can readily be seen to be greater when only a single valve is provided, since the addition of another valve in series provides an additional potential point of failure, and, in the case of relief valve discharge lines, the installation of an additional valve is actually prohibited by the ASME Code.
a.
All lines are in engineered safety feature or engineered safety feature-related systems.
b.
System reliability can readily be seen to be greater when only a single valve is provided, since the addition of another valve in series provides an additional potential point of failure, and, in the case of relief valve discharge lines, the installation of an additional valve is actually prohibited by the ASME Code.
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N                                   -
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V
Commonwealth Edison V
: 3)     Commonwealth Edison g           LcSalle County Nuclear Station Unit 2 O                                                                           .
g LcSalle County Nuclear Station Unit 2 O
III NOTES - CON'T i
III NOTES - CON'T i
: c. The systems are closed outside containment.
c.
: d. A single active failure of these ESF systems can be accomodated.
The systems are closed outside containment.
: e. The systems outside containment are protected from missiles consistent with their classification as ESF systems.
d.
: f. The systems are designed to Seismic Category I standards.
A single active failure of these ESF systems can be accomodated.
: g. The systems are classified as Safety Class 2.
The systems outside containment are protected from missiles e.
: h. The design ratings of these systems meet or exceed those specified for the primary containment,
consistent with their classification as ESF systems.
: i. The leaktightness of these systems is assured by normal surveillance, inservice testing and leak detection monitoring.
f.
: j. The single valve on these lines is located outside containment.
The systems are designed to Seismic Category I standards.
g.
The systems are classified as Safety Class 2.
h.
The design ratings of these systems meet or exceed those specified for the primary containment, i.
The leaktightness of these systems is assured by normal surveillance, inservice testing and leak detection monitoring.
j.
The single valve on these lines is located outside containment.
(From FSAR Table 6.2-21, Note 28).
(From FSAR Table 6.2-21, Note 28).
(8) These lines are always filled with water on the outboard side of the containment thereby forming a water seal. They are maintained at a N
(8) These lines are always filled with water on the outboard side of the containment thereby forming a water seal.
pressure that is always higher than primary containment pressure by water leg pumps; thus, precluding any outleakage from primary cantain-ment. However, even if outleakage did occur, it would be into an ESF system which forms a closed loop outside primary containment. Thus, any leakage from primary containment would return to primary contain-ment through this closed loop.
They are maintained at a N
These valves are under continuous leakage test because they are always subjected to a differential pressure acting across the seat.       Leakage through these valves is continuously-monitored by the pressure switches in the pump discharge lines, which have a low alarm setpoint in the main control room.
pressure that is always higher than primary containment pressure by water leg pumps; thus, precluding any outleakage from primary cantain-ment.
However, even if outleakage did occur, it would be into an ESF system which forms a closed loop outside primary containment.
: Thus, any leakage from primary containment would return to primary contain-ment through this closed loop.
These valves are under continuous leakage test because they are always subjected to a differential pressure acting across the seat.
Leakage through these valves is continuously-monitored by the pressure switches in the pump discharge lines, which have a low alarm setpoint in the main control room.
Even though a special leakage test is not merited on these valves for the reasons discussed above, a system leakage test to meet the l
Even though a special leakage test is not merited on these valves for the reasons discussed above, a system leakage test to meet the l
l requirements of Type C testing and as hereinafter described, will be performed to ensure the leak-tightnesses of the ECCS and RCIC systems.
requirements of Type C testing and as hereinafter described, will be l
The systems will be pressurized with water to a minimum pressure of 39.6 psig (peak drywell accident pressure) with the system totally isolated from primary containment. A leakage rate for the entire system will then be determined and compared to an acceptance limit based on site boundary dose considerations (iO CFR 100: ECCS subsystem leakage not to exceed I gpm times number of valves in the subsystem tested).
performed to ensure the leak-tightnesses of the ECCS and RCIC systems.
The systems will be pressurized with water to a minimum pressure of 39.6 psig (peak drywell accident pressure) with the system totally isolated from primary containment. A leakage rate for the entire system will then be determined and compared to an acceptance limit based on site boundary dose considerations (iO CFR 100:
ECCS subsystem leakage not to exceed I gpm times number of valves in the subsystem tested).
(From FSAR Table 6.2-71. Note 29).
(From FSAR Table 6.2-71. Note 29).
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fd } Commonwealth Edison
fd } Commonwealth Edison L-sene county Nuclear Statkm Unit 2 III NOTES - CON'T (9) To satisfy the requirements of General Design Criterion 56 and to l
            .              L-sene county Nuclear Statkm Unit 2 III NOTES - CON'T (9) To satisfy the requirements of General Design Criterion 56 and to l
perform their function, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).
perform their function, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).
These lines are Seismic Category I and terminate in instruments that are Seismic Category I. They are provided with manual isolation valvcs
These lines are Seismic Category I and terminate in instruments that are Seismic Category I.
;                    and excess flow check valves.
They are provided with manual isolation valvcs and excess flow check valves.
The integrity of these lines is to be tested during the Type "A" Test.
The integrity of these lines is to be tested during the Type "A" Test.
These lines and their associated instruments will be pressurized to Pa -
These lines and their associated instruments will be pressurized to P -
Surveillance inspections will be performed to ensure the leaktight integrity of these lines and their associated instrunents. Additional inservice inspection is included in the Technical Specifications. This inservice inspection verifies the function of the excess flow check valves.
a Surveillance inspections will be performed to ensure the leaktight integrity of these lines and their associated instrunents.
Isolation is provided by the excess flow check valve. In the event of a line rupture downstream of the check valve and a containment pressure above 2 psig, this valve would close to limit the amount of leakage.       (From FSAR Table 6.2-21, Jiote 32).
Additional inservice inspection is included in the Technical Specifications.
This inservice inspection verifies the function of the excess flow check valves.
Isolation is provided by the excess flow check valve.
In the event of a line rupture downstream of the check valve and a containment pressure above 2 psig, this valve would close to limit the amount of leakage.
(From FSAR Table 6.2-21, Jiote 32).
The exercise and leak test procedure confirms valve operability through a visual observation of a marked decrease in the instrument lir.e's flow rate.
The exercise and leak test procedure confirms valve operability through a visual observation of a marked decrease in the instrument lir.e's flow rate.
;            (10) To perform their function and to satisfy the requirements of General Design Criterion 55, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).
(10) To perform their function and to satisfy the requirements of General Design Criterion 55, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).
These lines are Seismic Category I and terminate in instruments that are Seismic Category I. They are provided with flow-restricting orifices, manual isolation valves, and excess flow check valves.
These lines are Seismic Category I and terminate in instruments that are Seismic Category I.
They are provided with flow-restricting orifices, manual isolation valves, and excess flow check valves.
The flow-restricting orifice is sized to assure that in the event. of a postulated failure of the piping or component, the potential offsite exposure will be substantially below the guidelines of 10 CFR 100.
The flow-restricting orifice is sized to assure that in the event. of a postulated failure of the piping or component, the potential offsite exposure will be substantially below the guidelines of 10 CFR 100.
Isolation is provided by the excess flow check valve. In the' event of a line rupture downstream of the check valves, this valve would close to limit the amount of leakage.
Isolation is provided by the excess flow check valve.
.                    The-integrity of these lines will be tested during the Type "A" Test. Surveillance inspections will be performed to ensure the leak-tight integrity of.these lines and their associated instruments. Addi-tional inservice inst action is included in' the Technical Specifications.
In the' event of a line rupture downstream of the check valves, this valve would close to limit the amount of leakage.
This inservice inspection verifies the function of the excess flow
The-integrity of these lines will be tested during the Type "A" Test.
.                      check valves (From FSAJ. Table 6.2-21, Note 33).
Surveillance inspections will be performed to ensure the leak-tight integrity of.these lines and their associated instruments.
Addi-tional inservice inst action is included in' the Technical Specifications.
This inservice inspection verifies the function of the excess flow check valves (From FSAJ. Table 6.2-21, Note 33).
The exercise and leak test procedure-confirms valve operability through a visual observation of a marked decrease in the instrument line's flow p
The exercise and leak test procedure-confirms valve operability through a visual observation of a marked decrease in the instrument line's flow p
: o rate.
rate.
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Commonwealth Edison kV e )7   usene     counpudeer smuon unn 2
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:    'V III NOTES - CON'T O (11)   The ECCS and RCIC suction lines are normally filled with water on both the inboard and outboard side cf containment, thereby forming a water seal to the containment environment. The valves are open during post-LOCA conditions to supply a water source for the ECCS pumps. Since a break in an ECCS line need not be considered in conjunction with a DBA, the only possible situation requiring one of these valves to be closed during a DBA is An unacceptable leakage in an ECCS. However, because these ECCS systems are constantly monitored for excessive leakage, this is not a credible event for design.
'V III NOTES - CON'T O (11)
However, at the insistence of the NRC, these valves will receive a leakage test as part of the low pressure system leakage test described in Note 29.     (From FSAR Table 6.2-21, Note 39).
The ECCS and RCIC suction lines are normally filled with water on both the inboard and outboard side cf containment, thereby forming a water seal to the containment environment. The valves are open during post-LOCA conditions to supply a water source for the ECCS pumps.
Since a break in an ECCS line need not be considered in conjunction with a DBA, the only possible situation requiring one of these valves to be closed during a DBA is An unacceptable leakage in an ECCS.
: However, because these ECCS systems are constantly monitored for excessive leakage, this is not a credible event for design.
However, at the insistence of the NRC, these valves will receive a leakage test as part of the low pressure system leakage test described in Note 29.
(From FSAR Table 6.2-21, Note 39).
(12) The leakages through the Main Steamline valves will not be included in establishing the acceptance limits for the combined leakage in accordance with the 10 CFR 50, Appendix J, Type B and C tests.
(12) The leakages through the Main Steamline valves will not be included in establishing the acceptance limits for the combined leakage in accordance with the 10 CFR 50, Appendix J, Type B and C tests.
Because the Mair Steamlines are provided with a leakage control system, the leakage through these valves will not be added into the combined leakage rate. This exclusion is in accordance with Article Ill.C.3 of 10 CFR 50, Appendix J.   (From FSAR Table 6.2-21, Note 30).
Because the Mair Steamlines are provided with a leakage control system, the leakage through these valves will not be added into the combined leakage rate. This exclusion is in accordance with Article Ill.C.3 of 10 CFR 50, Appendix J.
(13) These penetrations are provided with removable spools outboard of the outboard isolation valve. During operation, these lines will be blind flanged using a double 0-ring and type-B leak tested. In addition,
(From FSAR Table 6.2-21, Note 30).
(13) These penetrations are provided with removable spools outboard of the outboard isolation valve.
During operation, these lines will be
(]
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G           the packing of these isolation valves will be soap bubble tested to ensure insignificant or no leakage at containment test pressure each refueling outage.
blind flanged using a double 0-ring and type-B leak tested.
l                                                                                         1 l                                                 Page 7 l
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the packing of these isolation valves will be soap bubble tested to ensure insignificant or no leakage at containment test pressure each refueling outage.
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                                                    +/ LaSalle County Nuclear Station Unit 2 INSERVICE TESTING PLAN                                                      .
[ C INSERVICE TESTING PLAN
Systern DG - Diesel Generator
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      /           Commonwealth Edison INSERVICE TESTING PLAN                                                           .
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Systern D0 - Diesel Oil
Commonwealth Edison INSERVICE TESTING PLAN
      \vN J LaSalle County Nuclear Station Unit 2 v                                                                     P,U MPS                                     Pago 1 of             1 TEST PAHAMETERS TO DE MEASURED PUMP         PUMP                   P&tD NUMBER         PJA M E         CLASS   NO COOH.         INl E T     Dif f i t OW Vitill A . ' UEAf ter4G                   T EST iff illWAL SPE LD PHESS       PitiSS IIA T E IlON             TEMP 00             01               02   03   04   05       06       07       08     09               10                           11 2000lP     Diesel Oil               3 132 6C   N/A   RP-05       RP-05 RP-05   RP-04           RP-01     Quarter.ly Pump 2A                                                                                                                                       3 20002P     HPCS Diesel             3 132 4C   N/A   RP-05       RP-05 RP-05   RP-04           RP-01     Quarterly Oil Pump 28 l
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LaSalle County Nuclear Station Unit 2 INSERVICE TESTING PLAN P, UMPS Systern FC - Fuel Pool Cooling page 1     or       1 TEST PARAMETEllS TO DE MEASURED FuMP                                               Puup                   PalD PJUMilLR                                             PJAME       CLASS           TJO COOH           etai t. :   Die t now     vault A. urAltitui         T EST ite IL HVAt SPELD PHESS     lPaliSS  IIA T E IlOPJ     ILMP 00                                                 01         02           03     04   05       06         0/       08     09       10                     11 2FC03PA                                           Fuel Pool           3       134-2     7E     N/A   YES         YES   YES     RP-04     RP-01   Quarterly Emergency Make-up Pump 2A 4
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                    )                  Commonwealth Edison INSEIWICE TESTING PLAN LaSalle County Nuclear Station Unit 2                                                               Systern HP - High Pressure Core Kj                                                                                             P,U MPS                           Pago j   of     j           Spray
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( 4" )J LaSalle County Nuclear StaticnINSERVICE                    Unit 2 TESTING PLAN Systein RH - Residual Heat Removal v                                                            P,UM PS                       pago   1 of                                         1 PUMP       PUMP             PalD NUMBER       tJA M E   CLASS   14 0   COOft       ritt ti     ti ow v stA- 0 Anirju         T EST irit L HVAL 00           01       02     03       04   05   06   07     08   09       10                     11 2E12-C002A RHR Pump 2A   2     142-1     SA   N/A YES   YES     YES   RP-04   RP-01   Quarterly 2E12-C002B RHR Pump 28   2     142-2     4B   N/A YES   YES     YES   RP-04   RP-01   Quarterly 2E12-C002C   RHR Pump 2C   2     142-3     SB   N/A YES   YES     YES   RP-04   RP-01   Quarterly 2E12-C003   RHR Water     2     142-3     7A   N/A YES   YES     RP-02 RP-04 RP-01   Quarterly Leg Pump 2E12-C300A   RHR Service   3     134-2     7F, N/A YES   YES     YES   RP-04 RP-01   Quarterly Water Pump 2A 2E12-C3008   RHR Servii.e   3     134-2     7C   N/A YES   YES     YES   RP-04 RP-01   Quarterly Water Pump 28 2E12-C3000   RHR Service   3     134-1 . 7E   N/A YES   YES   YES     RP-04 RP-01   Quarterly Water Pump                   l 2C 2E12-C3000   RHR Service     3               7F   N/A YES   YES   YES     RP-04 RP-01   Quarterly Water Pump         l134-1 g
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/
Commonwealth Edison INSERVICE TESTING PLAN Systein RH - Residual Heat Removal P,UM PS pago 1 of 1
v PUMP PUMP PalD NUMBER tJA M E CLASS 14 0 COOft ritt ti ti ow v stA-0 Anirju T EST irit L HVAL 00 01 02 03 04 05 06 07 08 09 10 11 2E12-C002A RHR Pump 2A 2
142-1 SA N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C002B RHR Pump 28 2
142-2 4B N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C002C RHR Pump 2C 2
142-3 SB N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C003 RHR Water 2
142-3 7A N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump 2E12-C300A RHR Service 3
134-2 7F, N/A YES YES YES RP-04 RP-01 Quarterly Water Pump 2A 2E12-C3008 RHR Servii.e 3
134-2 7C N/A YES YES YES RP-04 RP-01 Quarterly Water Pump 28 2E12-C3000 RHR Service 3
134-1.
7E N/A YES YES YES RP-04 RP-01 Quarterly Water Pump l
2C l134-1 2E12-C3000 RHR Service 3
7F N/A YES YES YES RP-04 RP-01 Quarterly Water Pump g
2D l
2D l
                          ..ii
..ii


O                                                                   O                                                         O
O O
    \ ' - ' '
O Q)
Q)                                  Commonwealth Edison LaSane County Nuclear Stauori unit 2 INSERVICE TESTING PLAN                      Systern RI - Reactor Core Isolaticn
Commonwealth Edison INSERVICE TESTING PLAN
(,                                                                                                                           P, UMPS                         Pago   1 of       1       Cooling PUMP                         PUMP                             ?&lD IJUMBLR                                 PJA M E                   CLASS   NO   COOil         een ti pie r   e a ow vaultA. urAsurni           TEST irilLHVAL SPELD PliESS PfliSS   itAIE   IlOrd   TEMP 00                         01               02     03     04   05     06     07       08     09       to                   11 2E51-C001                                             RCIC Pump                       2     147-2 2C   YES   YES     Y:S   YES     RP-04   RP-01   Quarterly 2E51-C003                                           RCIC Water                     2     147-2 4A   N/A   YES     YES     RP-02   RP-04   RP-01   Quarterly Leg Pump i
\\ ' - ' '
LaSane County Nuclear Stauori unit 2 Systern RI - Reactor Core Isolaticn
(,
P, UMPS Pago 1 of 1
Cooling PUMP PUMP
?&lD IJUMBLR PJA M E CLASS NO COOil een ti pie r e a ow vaultA.
urAsurni TEST irilLHVAL SPELD PliESS PfliSS itAIE IlOrd TEMP 00 01 02 03 04 05 06 07 08 09 to 11 2E51-C001 RCIC Pump 2
147-2 2C YES YES Y:S YES RP-04 RP-01 Quarterly 2E51-C003 RCIC Water 2
147-2 4A N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump i
4 A
4 A


O                                                                       O                                                                                     O (r x '2 )
O O
          ~~
O (r x
Commonwealth Edison LaSalle County Nuclear Station Un:t 2 INSERVICE TESTING PLAN P,U MPS SysteHi LP - Low Pressure Core Spray pago   1 or                         1 PLIMP                         PUMP               P&lD PJUMOLR                           PJA M E   CLA:E. NO COOR         ins t.t Ditr   tiow   viust A- ut Asura;                     T EST itJ ILHVAL SPEED PHE SS PHiSS   flAIE     IlON     It MP 00                             01       0? i     03   04   05     06     07     08       09         10                                               11
'2 )
Commonwealth Edison INSERVICE TESTING PLAN LaSalle County Nuclear Station Un:t 2 SysteHi LP - Low Pressure Core Spray
~~
P,U MPS pago 1 or 1
PLIMP PUMP P&lD PJUMOLR PJA M E CLA:E.
NO COOR ins t.t Ditr tiow viust A-ut Asura; T EST itJ ILHVAL SPEED PHE SS PHiSS flAIE IlON It MP 00 01 0? i 03 04 05 06 07 08 09 10 11
__ _4 l
__ _4 l
2E21-C001     LPCS Pump                       2       140   30   N/A   YES     Y.ES   YES     RP-04     RP-01               Quarterly 2E21-0002     LPCS Water                       2       140   3B   N/A   YES     YES     RP-02   RP-04     RP-01               Quarterly Leg Pump 4
2E21-C001 LPCS Pump 2
140 30 N/A YES Y.ES YES RP-04 RP-01 Quarterly 2E21-0002 LPCS Water 2
140 3B N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump 4
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O O
: 2. ,) Commonwealth Edison L'     t asane county Nucesar station unit 2         PUMP & VALVE TESTING                   Page       2                                     of       2 RELIEF REQUESTS Iii                         5                                   ASME
O N
                  -'i 3     PUMPGil         QO                               SECTION XI VALVE NO.                         FUNCTION     TEST REQUlf tEMENT         DASIS FOilItEllEF                                               ALIEftNATIVE IEST o
: 2.,)
00           01             02               03               04                         05                                                               06 RP-01   Continued                                                               not always predict such problems. An increase in bearing temperature most often does not occur until the bearing has 4                                                      I deteriorated to a point where additional pump damage may occur.
Commonwealth Edison L'
Bearing temperatures
t asane county Nucesar station unit 2 PUMP & VALVE TESTING Page 2
!                                                                                              are also affected by the temperatures of the meditm being panped, which could fleid misleading msults.
of 2
RELIEF REQUESTS Iii 5
ASME
-'i 3 PUMPGil QO SECTION XI VALVE NO.
FUNCTION TEST REQUlf tEMENT DASIS FOilItEllEF ALIEftNATIVE IEST o
00 01 02 03 04 05 06 RP-01 Continued not always predict such problems. An increase in bearing temperature most often does not occur until the bearing has I
deteriorated to a point 4
where additional pump damage may occur.
Bearing temperatures are also affected by the temperatures of the meditm being panped, which could fleid misleading msults.
Vibration madings are not affected by tht!
Vibration madings are not affected by tht!
                                                                                                , temperature of the medium being psnped, tius tie readings are more consis-tent.
, temperature of the medium being psnped, tius tie readings are more consis-tent.
a i
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O                                                             O'                                               O N
O O'
SJ   ~
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Commonwealth Edison PUMP & V ALVE TESTING               Page   1     W     l tasane county Nucknar Station Unit 2 j             s\                                                                   RELIEF REQUESTS i
SJ Commonwealth Edison PUMP & V ALVE TESTING Page 1
!                          DE                         N yO ASME SECTION XI 33         PUMP OR ALTERN ATIVE TEST i
W l
                            %g        VALVE NO.         >f O<
~
FUNCTION         TEST REOUIREMENT       BASIS FOR REllEF U
tasane county Nucknar Station Unit 2 j
01             02             03                     04                   05                       06 00 IP-02   WCS water Leg               Pressure             IW-3100           Flow is not a sitfificant   Pressure Maintenance
s\\
!                                  Pump                         Maintenance           Flow Measurement   desigi parameter for the   of ECCS discharge 2E22-C003           2                                               water leg panps. iteir     lines within j
RELIEF REQUESTS i
primary purpose is to       allowable pressure LPCS water Le9                                                       maintain the ECCS pump     limits.
DE N
i Punp                                                                 discharge lines filled 2E21-C002           2                                               and pressurized. The
ASME 33 PUMP OR yO SECTION XI VALVE NO.
* satisfactory performance
>f FUNCTION TEST REOUIREMENT BASIS FOR REllEF ALTERN ATIVE TEST O<
;                                  RitR water Leg                                                       of this function is mani-
i g
;                                  Pung                                                                 fested by the maintenance 2                                               of tie discharge line l                                   2E12-C003 within allowable stanrthy l                                                                                                        pressure limits.
U 00 01 02 03 04 05 06 IP-02 WCS water Leg Pressure IW-3100 Flow is not a sitfificant Pressure Maintenance Pump Maintenance Flow Measurement desigi parameter for the of ECCS discharge 2E22-C003 2
1 RCIC Water           2 1herefore, there is
water leg panps. iteir lines within primary purpose is to allowable pressure j
;                                  Leg Pump 2E51-C003 actually no flow criteria j                                                                                                         on the pump that coulti be i
i LPCS water Le9 maintain the ECCS pump limits.
used to determine wiether the pump is satisfactorily
Punp discharge lines filled 2E21-C002 2
'                                                                                                        performing its safety I                                                                                                         function. Therefore, j
and pressurized.
because the desity basis j                                                    ,
The satisfactory performance RitR water Leg of this function is mani-Pung fested by the maintenance l
of the waterleg panps is i
2E12-C003 2
maintenance of pressure, j                                                                                                         this is the parameter lint is considered for J
of tie discharge line l
4                                                                                                        inservice testlinj.
within allowable stanrthy pressure limits.
I 4
1 RCIC Water 2
1 G8.T3
1herefore, there is Leg Pump actually no flow criteria 2E51-C003 j
on the pump that coulti be i
used to determine wiether the pump is satisfactorily performing its safety I
function.
Therefore, j
because the desity basis of the waterleg panps is j
maintenance of pressure, i
j this is the parameter lint is considered for J
inservice testlinj.
4 I
4 1
G8.T3


O                                                         O                                         O 9,)     Commonwealth Edison
O O
          ''~   LaSane County Nuclear Station Unit 2         PUMP & VALVE TESTING           Page     1 of 1
O 9,)
'    \                                                         RELIEF REQUESTS Ili{0                       mb                                 ASME 73       PUMPOil           "O                               SECTION XI y@      VALVE NO.          $              FUNCTION     TEST IIEOUlFlEMENT BASIS FOIL llELIEF   ALIEflNATiVE IESI a                      o$<
Commonwealth Edison
O 00         01             02               03                 04               05                     06 i
'''~
RP-03     Deleted i
LaSane County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1
of 1
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RELIEF REQUESTS Ili{0 mb ASME 73 PUMPOil "O
SECTION XI FUNCTION TEST IIEOUlFlEMENT BASIS FOIL llELIEF ALIEflNATiVE IESI o$
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VALVE NO.
a O
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[ 73:_ _ ) LaSalle (VA>
U f.
        '7         County Nuclear Station Unit 2         PUMP & VALVE TESTlNG RELIEF REQUESTS Pago I   of   3 Ei                                                               ASME 3 -)       PUMP OR           $O                               SECTION XI VALVE NO.                         FUNCTION     TEST HEOUlilEMENT       BASIS FOR HELIEF         ALIERNATIVE IESI 00           of             02               03                 04                       05                       06 RP-04     All Pumps             --
[ 73:_ _ ) Commonwealth Edison (V '7 LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTlNG Pago I
N/A               Table IWP-3100-2   Depending on the pump type, Computer trending vibration will either be     will use the past measured in mils or in       several vibration inches per second. A more values to determine                                     '
of 3
informative reading is ob- an Alert and a tained using vibration
A>
                                                                                                ,              Required Action Range.
RELIEF REQUESTS Ei ASME 3 -)
velocity equipment, however,The IRD General the limited bearing access-- Machinery Vibration ability on La Salle's ver-   Severity Chart will tically oriented pumps       be used as a further and positive displacement     aid, pumps reduce the accuracy of this relatively bulky equipment. In these cases, a measurement of vibration amplitude will be taken.
PUMP OR
$O SECTION XI VALVE NO.
FUNCTION TEST HEOUlilEMENT BASIS FOR HELIEF ALIERNATIVE IESI 00 of 02 03 04 05 06 RP-04 All Pumps N/A Table IWP-3100-2 Depending on the pump type, Computer trending vibration will either be will use the past measured in mils or in several vibration inches per second. A more values to determine informative reading is ob-an Alert and a tained using vibration Required Action Range.
velocity equipment, however,The IRD General the limited bearing access-- Machinery Vibration ability on La Salle's ver-Severity Chart will tically oriented pumps be used as a further and positive displacement
: aid, pumps reduce the accuracy of this relatively bulky equipment.
In these cases, a measurement of vibration amplitude will be taken.
Whichever method is used, fixed limiting values for the Alert and Required Action Ranges will not be used as a trigger for maintenance operations because each pump operates satisfactorily at a unique vibration level due to variables such as restraid orientation, pump size, pump type, and pump speed.
Whichever method is used, fixed limiting values for the Alert and Required Action Ranges will not be used as a trigger for maintenance operations because each pump operates satisfactorily at a unique vibration level due to variables such as restraid orientation, pump size, pump type, and pump speed.
Alert and Required Action Range limits for any par-ticular pump will be based u ta
Alert and Required Action Range limits for any par-ticular pump will be based u ta


O                                                           O                                                           O N
O O
1-1)                         Commonwealth Edison PUMP & VALVE TESTING                    Page      2 of  3 y '' >] LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS e                                                       >
O N
Ui$                                                     Ed                               ASME 13                             PUMPOlt               $O                           SECTION XI
1-1)
        %g                              VALVE NO.             _sf 04 FUNC110N       T EST IlEOulflEMENT       BASIS F OR REL IEF       ALIEf ttJATIVE ICSI o
Commonwealth Edison y ' >] LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 2
00                                 01                   02         03                   04                       05                       06 RP-04                         All Pumps                 --
of 3
N/A                 TABLE IWP-3100-2     on its past vibration (Continued)                                                             history. As a further aid, the IRD Mechanalysis Chart of vibration           '
RELIEF REQUESTS e
severity wil also be used as a guide in rating pump performance.
Ui$
Ed ASME 13 PUMPOlt
$O SECTION XI VALVE NO.
_sf FUNC110N T EST IlEOulflEMENT BASIS F OR REL IEF ALIEf ttJATIVE ICSI 04 g
o 00 01 02 03 04 05 06 RP-04 All Pumps N/A TABLE IWP-3100-2 on its past vibration (Continued) history. As a further aid, the IRD Mechanalysis Chart of vibration severity wil also be used as a guide in rating pump performance.
I P
I P
4 4.f 13
4 4.f 13


RP-04 GENER AL MACHINERY VIBR ATION SEVERITY CHART
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              "J LaSalle County Nuclear Station Unit 2                                                   PUMP & VALVE TEST 1NG                 Pago   1   of 1 RELIEF REQUESTS II)                                                                               5                             ASME 33                                                   PUMP OH VALVE NO.
Commonwealth Edison "J LaSalle County Nuclear Station Unit 2 PUMP & VALVE TEST 1NG Pago 1
                                                                                        $0      FUNCTION SECTION XI TEST HEOUlHEMENT         DASIS IOH HEllEF       AliEHNATlVE IESI 00                                                                           01 02         03                 04                       05                     06 RP-05                                 2D00lP                                         3 Transfer Fuel Oil   Measure Pump Inlet These pumps are required From the Diesel Oil Pressure, Differ- to transfer fuel oil from 20002P                                         3 Storage Tanks to   ential Pressure,   the storage tank to the                                           -
of 1
the Day Tanks       and Flow Rate     day tank at a rate of at least 30 gpm, which is approximately ten times the diesel engine's consumption rate. They are not required to pro-vide a reproduceable suction on differential pressure. In fact,
v'
'                                                                                                                                  pressure measurements may vary considerably depend-ing on the suction head in the diesel oil storage tank. The flow rate is verified to be above 30 gpm by measuring the time required for bulk transfer of fuel oil to the day tank.
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RELIEF REQUESTS II) 5 ASME 33 PUMP OH
$0 SECTION XI VALVE NO.
FUNCTION TEST HEOUlHEMENT DASIS IOH HEllEF AliEHNATlVE IESI 00 01 02 03 04 05 06 RP-05 2D00lP 3
Transfer Fuel Oil Measure Pump Inlet These pumps are required From the Diesel Oil Pressure, Differ-to transfer fuel oil from 20002P 3
Storage Tanks to ential Pressure, the storage tank to the the Day Tanks and Flow Rate day tank at a rate of at least 30 gpm, which is approximately ten times the diesel engine's consumption rate.
They are not required to pro-vide a reproduceable suction on differential pressure.
In fact, pressure measurements may vary considerably depend-ing on the suction head in the diesel oil storage tank. The flow rate is verified to be above 30 gpm by measuring the time required for bulk transfer of fuel oil to the day tank.
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          '-f 7 LaSane County Nuclear Stapon Unit 2         PUMP & VALVE TESTlNG               Pago   1   of   1
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      \/                                                       RELIEF REQUESTS r                           >
'-f 7 LaSane County Nuclear Stapon Unit 2 PUMP & VALVE TESTlNG Pago 1
Ui$                           N                               ASME 33         PUMP Oft VALVE NO.
of 1
                                        $0          FUNCTION SECTION XI TEST HEOUlHEMENT       UASIS FOR HEllEF         ALIEHNATIVE lESI 00           01           02             03                 04                     05                       06 RP-06     2C41-C001A           2                       Measure Pump Inlet It is impractical to         Measure pump discharge Pressure           measure standby liquid       pressure and flow 2C41-C001B           2                                         control pump inlet           rate quarterly.                        .
\\/
pressure in accordance with Section XI require-ments. During pump test-ing, the pump suction is from a test tank rather than the main standby liquid control tank.
RELIEF REQUESTS r
Ui$
N ASME 33 PUMP Oft
$0 SECTION XI VALVE NO.
FUNCTION TEST HEOUlHEMENT UASIS FOR HEllEF ALIEHNATIVE lESI 00 01 02 03 04 05 06 RP-06 2C41-C001A 2
Measure Pump Inlet It is impractical to Measure pump discharge Pressure measure standby liquid pressure and flow 2C41-C001B 2
control pump inlet rate quarterly.
pressure in accordance with Section XI require-ments.
During pump test-ing, the pump suction is from a test tank rather than the main standby liquid control tank.
For these positive dis-placement pumps, the measurment of inlet pressure is not cirtical in judging pump perfor-mance. Measuring the discharge pressure and the flow rate is adequate to detect changes in the hydraulic characteristics of the pumps.
For these positive dis-placement pumps, the measurment of inlet pressure is not cirtical in judging pump perfor-mance. Measuring the discharge pressure and the flow rate is adequate to detect changes in the hydraulic characteristics of the pumps.
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L' Commonwealth Edison 3                      LaSalle County Nuclear Station tinit 2         PUMP & VALVE TESTlNG           Pago     1 of   1
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      '']                                                                    RELIEF REQUESTS p                                       >-                                                                  I Ui$                                       bO                                   ASME
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          ~.i 3                   PUMP OFI       $O                               SECTION XI y8                       VALVE NO.       J"O             FUNCTION     TEST flEQUlflEMENT DASIS FOIL FlELIEF     ALIEf1tJATI /E IESI a                                     O<
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LaSalle County Nuclear Station tinit 2 PUMP & VALVE TESTlNG Pago 1
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3 RELIEF REQUESTS p
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J"O FUNCTION TEST flEQUlflEMENT DASIS FOIL FlELIEF ALIEf1tJATI /E IESI a
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                                                                            'N O ,)                             Commonwealth Edison                                                                   Pane 1        0f  1 PUMP & V ALVE TESTlNG q                                                         LaSeHe County Nuclear Station Unit 2 RELIEF REQUESTS 9
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d                                                N                                    ASME SECTION XI 33                            PUMPOH VALVE NO.
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                                                                                                            $0            FUNCTION       TEST flEOUlflEMENT         HASIS F Of1 f1Et IEF     ALTEllNATIVE TEST 03                 04                         05                       06 00                            Ol            02 The reference values for      Since inlet pressure RHR Pump A                   Remove Decay Heat   IWP-4120 requires RP-08                                                                                                                                            varies on the RHR 2E12-C002A           2                           that the full scale   the inlet pressures of pumps, gages with range of pump in-     RHR Pumps A, B and C are all (Pi>7.5 psig). The       larger scale ranges j                                                                                      RHR Pump B                    Remove Decay Heat  struments shall be                                  are required to 2                         three times the       reference value for the
Commonwealth Edison PUMP & V ALVE TESTlNG Pane 1 0f 1
!                                                                                      2L12-C0028                                                                                            accomodate pressure reference value or     inlet pressure of the rises of pump l
q LaSeHe County Nuclear Station Unit 2 RELIEF REQUESTS 9d N
Remove Decay Heat   less.                 RHR water len pump is RHR Pur.1p C t                                                                                        suction.
ASME 33 PUMPOH
2 (Pi>8 psig). The full 2E12-C002C scaTe rance of the RHR Water leg                 Pressure Mainten-                         inlet pressure gaaes for 2      ance                                      all four pumps reads Pump 0-250 psio. The inlet
$0 SECTION XI VALVE NO.
!                                                                                                                                                                pressure for these pumps 2E12-C003     .
FUNCTION TEST flEOUlflEMENT HASIS F Of1 f1Et IEF ALTEllNATIVE TEST 00 Ol 02 03 04 05 06 RP-08 RHR Pump A Remove Decay Heat IWP-4120 requires The reference values for Since inlet pressure 2E12-C002A 2
may attain a maximum pressure of 200 psig and
that the full scale the inlet pressures of varies on the RHR range of pump in-RHR Pumps A, B and C are pumps, gages with j
;                                                                                                                                                                therefore the pumps require a cane with a laraer scale range.
RHR Pump B Remove Decay Heat struments shall be all (Pi>7.5 psig). The larger scale ranges 2L12-C0028 2
three times the reference value for the are required to reference value or inlet pressure of the accomodate pressure l
RHR Pur.1p C t Remove Decay Heat less.
RHR water len pump is rises of pump (Pi>8 psig).
The full suction.
2E12-C002C 2
scaTe rance of the RHR Water leg Pressure Mainten-inlet pressure gaaes for all four pumps reads Pump 2
ance 0-250 psio.
The inlet pressure for these pumps 2E12-C003 may attain a maximum pressure of 200 psig and therefore the pumps require a cane with a laraer scale range.
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S. )                     Commonwealth Edison Page 1        of            1 LaSal% County Nuclear Station Unit 2                     PUMP & V AI.VE TESTING RELIEF REQUESTS s                                                   >
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Commonwealth Edison LaSal% County Nuclear Station Unit 2 PUMP & V AI.VE TESTING Page 1 of 1
      ;                                          PUMP OH                                       SECTION XI yO                                                                      FUNCTION       TEST HEOtllHEMENT       DASIS FOR REllEF                   Alif RNATIVE TEST g
RELIEF REQUESTS s
VALVE NO.
DO EO ASME
                                                          $[05 00                                             01 02                   03                 04                       05                                 OS RP-09                           HPCS Pump             2           ECCS Pump         IWP 4120 requires   The reference value for               Due to pressure IE22-C001                                           that the full scale the inlet pressure of the             spikes, a gage with range of pump in-   HPCS pumps is 8 psig                 a larger scale will struments shall be when drawing water from               be used to measure                     '
$[0 SECTION XI
three times the     the suppression pool and             inlet pressure.
~3 PUMP OH FUNCTION TEST HEOtllHEMENT DASIS FOR REllEF Alif RNATIVE TEST yO VALVE NO.
reference value or 17.5 psig when drawing
g 5
* less,               water from the condensate storage tank. The full scale range of the inlet pressure gage is -30" Hg to 100 psiq, or about a 115 psig range. The ranae is necessary due to the configuration of this system. When the HPCS pump is beino stopped, i                                                                                                               there is a spike in the suction pressure.       Such a pressure spike causes a suction pressure indicator with a smaller range to
00 01 02 03 04 05 OS RP-09 HPCS Pump 2
'                                                                                                              go out of calibration, llence, a suction pressure gage with a larger scale is needed to enable the qaqe to remain in calibration for the
ECCS Pump IWP 4120 requires The reference value for Due to pressure IE22-C001 that the full scale the inlet pressure of the spikes, a gage with range of pump in-HPCS pumps is 8 psig a larger scale will struments shall be when drawing water from be used to measure three times the the suppression pool and inlet pressure.
-                                                                                                              mea;urement of suction pre;sure of the llPCS pump.
reference value or 17.5 psig when drawing
! w ss
: less, water from the condensate storage tank. The full scale range of the inlet pressure gage is -30" Hg to 100 psiq, or about a 115 psig range.
The ranae is necessary due to the configuration of this system. When the HPCS pump is beino stopped, i
there is a spike in the suction pressure.
Such a pressure spike causes a suction pressure indicator with a smaller range to go out of calibration, llence, a suction pressure gage with a larger scale is needed to enable the qaqe to remain in calibration for the mea;urement of suction pre;sure of the llPCS pump.
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Commonwealth Edison O LaSalle County Nucle.v                                                                       Stanon
O LaSalle County Nucle.v Stanon Unit 2 Commonwealth Edison
                                                                                                      !NSERVICE       TESTING VALVES Unit PLAN 2            system CM-Containment Monitoring P8G*   1 2
!NSERVICE TESTING PLAN system CM-Containment Monitoring P8G*
                                                                                                        /
1 2
                                /                                                 9*       oo w
VALVES
                                                                                                                                    }                             -
/
00                                          01 / 02     03,     04     5     06   07       08       09     to         11         12 [           13 2CM017A                                             .5   158-1 F6   2/A     GB     $0     0       FS,     Q       5   RV-02           A   (See Note 4,6)
/
LT       RR           RV-19 2CM017B                                           .5   158-2 F6   2/A     GB     SO   O       FS,     0       5   RV-02           A   (See Note 4)
9*
LT       RR           RV-19 2CM018A                                           .5     158-1 F6   2/A     G8     50   0       FS,       Q       5   RV-02           A   (See Note 4,6)
o
LT       RR           RV-19 2CM018B                                         .5     15G-2 F6   2/A     GB     SO   0       FS,               5   RV-02           A Q                                  (See Note 4)
}
LT       RR           RV-19 2CM019A                                         .5     158-1 B6   2/A     GB     SO   O       FS,               5   RV-02 Q                              A   (See Note 4)
o w
LT       RR           RV-19 2CM019B                                       .5       158-2 66   2/A     GB     SO   O       FS,       0       5   R t.'- 02       A   (See Note 4)
01 / 02 03, 04 5
LT       RR           RV-19 2CM020A                                       .5       158-1 86   2/A           S0     0       FS, GB                            0       5     RV-02           A   (See Note 4,6)
06 07 08 09 to 11 12 [
LT       RR           RV-19 2CM020B                                     .5         158-2 R6   2/A     GB   10     0       FS,       0       5     RV-02           A   (See Note 4,6)
00 13 2CM017A
LT       RR           RV-19 2CM021B                                     .5         158-2 F3   2/3     ca ,l 50     C       FS       n       5     RV-02           A 2CM022A                                     .5         158-1 F3
.5 158-1 F6 2/A GB
* 2/B     GB   50             rs       0 C                        5     RV-02           A GE-T 2 -1180
$0 0
FS, Q
5 RV-02 A
(See Note 4,6)
LT RR RV-19 2CM017B
.5 158-2 F6 2/A GB SO O
FS, 0
5 RV-02 A
(See Note 4)
LT RR RV-19 2CM018A
.5 158-1 F6 2/A G8 50 0
FS, Q
5 RV-02 A
(See Note 4,6)
LT RR RV-19 2CM018B
.5 15G-2 F6 2/A GB SO 0
FS, Q
5 RV-02 A
(See Note 4)
LT RR RV-19 2CM019A
.5 158-1 B6 2/A GB SO O
FS, Q
5 RV-02 A
(See Note 4)
LT RR RV-19 2CM019B
.5 158-2 66 2/A GB SO O
FS, 0
5 R t.'- 02 A
(See Note 4)
LT RR RV-19 2CM020A
.5 158-1 86 2/A GB S0 0
FS, 0
5 RV-02 A
(See Note 4,6)
LT RR RV-19 2CM020B
.5 158-2 R6 2/A GB 10 0
FS, 0
5 RV-02 A
(See Note 4,6)
LT RR RV-19 2CM021B
.5 158-2 F3 2/3 ca,l 50 C
FS n
5 RV-02 A
2CM022A
.5 158-1 F3
* 2/B GB 50 C
rs 0
5 RV-02 A
GE-T 2 -1180


r                                                               p                                                         Q 0                                                         N)
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OLa                           e Co n y Nucl a Stano Unit 2       INSERVICE TESTING PLAN VALVES system CM-Containment Monitoring
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                                                                                                                  "*8*         '
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OLa e Co n y Nucl a Stano Unit 2 INSERVICE TESTING PLAN system CM-Containment Monitoring VALVES
                                                                                                                    $          g.
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0 4
00                   01     02       03     4 / 05   06   07   08     09       10           11           12             13 2CM0238                     .5                         GB S0   C   FS               5         RV-02           A 1SS-2l F2 ' 2/8                            Q 2CM024A                     .5   158-1   E2   2/B     GB S0   C   FS     Q         5         RV-02           A 2CM025A                     .5   158-1   B3   2/B     GB S0   C   FS     Q         5         RY-02           A 2CM026B                     .5   158-2   B3   2/B     GB S0   C   FS     0         5         RV-02           A 2CM031                   1.5     158-4 3 C6   2/A     G8 SO   O   FS,   Q         5         RV-02           A   (See Note 4,6)
h a
LT     RR                 RV-19 2CM032                   1.5     158-4   C6   2/A     GB SO   O   FS,   0         5         RV-02           A   (See Note 4)
4 g.
LT     RR                 RV-19 2CM033                   1.5     158-4   B7   2/A     GB S0   0   FS,   0         5         RV-02           A   (See Note 4)
q.
LT     RR                 RV-19 2CM034                   1.5     158-4   B7   2/A     GB 50   0   FS,   Q         5         RV-02           A   (See Note 4,6)
00 01 02 03 4 / 05 06 07 08 09 10 11 12 13 1SS-2l F2 ' 2/8 2CM0238
LT     RR                 RV-19 I
.5 GB S0 C
FS Q
5 RV-02 A
2CM024A
.5 158-1 E2 2/B GB S0 C
FS Q
5 RV-02 A
2CM025A
.5 158-1 B3 2/B GB S0 C
FS Q
5 RY-02 A
2CM026B
.5 158-2 B3 2/B GB S0 C
FS 0
5 RV-02 A
2CM031 1.5 158-4 3 C6 2/A G8 SO O
FS, Q
5 RV-02 A
(See Note 4,6)
LT RR RV-19 2CM032 1.5 158-4 C6 2/A GB SO O
FS, 0
5 RV-02 A
(See Note 4)
LT RR RV-19 2CM033 1.5 158-4 B7 2/A GB S0 0
FS, 0
5 RV-02 A
(See Note 4)
LT RR RV-19 2CM034 1.5 158-4 B7 2/A GB 50 0
FS, Q
5 RV-02 A
(See Note 4,6)
LT RR RV-19 I
GE-T2 1180
GE-T2 1180


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C  E       Q                           A   Diesel Cooling Water Pump Discharge Check                                                 '
r.O q%.
2DG-011                     4     134-01     C6     3/B   GT     M0     C FS     Q           RV-01         A   Diesel Cooling Water Strainer 2DG-034                     .75   134-01     C4     3/C   RV     -
A 0
C  RV     RR                         A   Diesel Generator Cooler I.                                                                       2A Relief (See Note 2) 2DG-035                     1.5   134-02     E4     3/B   Git   M0     0 FS,ST   Q       45                 A   LPCS Pump Cooler Control 2DG-036                     1.5   134-02     E2     3/C   CV     -
c^
C  E      Q                          A  LPCS Pump Motor Cooler Outlet Check GE-T 2 -1180
a n
s s
00 01 02 03 04 05 06 07 08 09 10 11 12 13 j
f 2DG-002 10 l134-01 D6 3/C NSC C
E Q
A Diesel Cooling Water Pump Discharge Check 2DG-011 4
134-01 C6 3/B GT M0 C
FS Q
RV-01 A
Diesel Cooling Water Strainer 2DG-034
.75 134-01 C4 3/C RV C
RV RR A
Diesel Generator Cooler I.
2A Relief (See Note 2) 2DG-035 1.5 134-02 E4 3/B Git M0 0
FS,ST Q
45 A
LPCS Pump Cooler Control C
E Q
A LPCS Pump Motor Cooler 2DG-036 1.5 134-02 E2 3/C CV Outlet Check GE-T 2 -1180


I    ,                                                            D                                             O
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                                                          'V                                                               (V                                              V Commonwealth Edison
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                                            @                                                                                                            D0 - Diesel Oi1 I.aSal e County Nuclear Station Unit 2           INSERVICE TEST 1NG PL AN           system VALVES                    "*8'     I   'I
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                                                                  #                                0                                       *
I.aSal e County Nuclear Station Unit 2 Commonwealth Edison D0 - Diesel Oi1 INSERVICE TEST 1NG PL AN system
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9              c ps    sY  n   y                 S'       $          g-00           01     02 / 03 / 04             0     06   07   08     09   10     11         12             13 2D0002                 1.5     132     E6     3/C     NSCl-       C     E     Q                       A   Unit 2A DG Fuel Oil Transfer Pump Discharge Check 2D0004                 1.5     132     E6     3/B     GB   S0     C     FS     Q           RV-02       A   Unit 2 Day Tank Inlet Stop Valve 200012                 1.5     132     E4     3/C     NSC -
'I VALVES 9
C    E     Q                       A   Unit 2B DG Fuel Oil l                                                                       Transfer Pump Discharge Check 200014                 1.5     132     E4     3/8     GB   S0     C   FS     Q           RV-02       A   Unit 2B Day Tank Inlet
0 sY p
                                                                                            ;                                                                Stop Valve 200024               2       132     82     3/B     GB   S0     C   FS     Q           RV-02       A   Diesel Fire Fuel Transfer Pump Inlet Stop I
n y
4 S'
g-cs 00 01 02 / 03 / 04 0
06 07 08 09 10 11 12 13 2D0002 1.5 132 E6 3/C NSCl-C E
Q A
Unit 2A DG Fuel Oil Transfer Pump Discharge Check 2D0004 1.5 132 E6 3/B GB S0 C
FS Q
RV-02 A
Unit 2 Day Tank Inlet Stop Valve 200012 1.5 132 E4 3/C NSC C
E Q
A Unit 2B DG Fuel Oil l
Transfer Pump Discharge Check 200014 1.5 132 E4 3/8 GB S0 C
FS Q
RV-02 A
Unit 2B Day Tank Inlet Stop Valve 200024 2
132 82 3/B GB S0 C
FS Q
RV-02 A
Diesel Fire Fuel Transfer Pump Inlet Stop I
GE-T 2 - 1180
GE-T 2 - 1180


m                                                                                               s                                                       A
m s
                      ~./                                                                                                                                               %
A
OLa                       e Co n y Nuct a Sta on!Nt 2                                           INSERVICE TESTING PLAN VALVES system FC-Fuel Pool Cooling
~./
                                                                                                                                          "*9'     I       ' I
OLa e Co n y Nuct a Sta on!Nt 2 INSERVICE TESTING PLAN system FC-Fuel Pool Cooling
                                                                    /
"*9' I
                          #                                            8         oO    *>
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g   A                g,c*      ''
/
                                                                                                                                              >            40            e.4 00             01                               02     03     04     05 [C6        07   08     09     10       11           12             13 2FC-044A                 6                           134-02     E6         3/C   NSC       -
8 O
C    E       Q                             A     Fuel Pool Emergency Make Up Pump 2A Discharge Check 2FC-044B                 6                         134-01       C6         3/C   NSC     -
c*
C    E     Q                             A       Fuel Pool Emergency Make Up Pump 2B Discharge Check 2FC-105A                 1x.75 137-1                               D4       3/C   RV       -
g, 40 4
C    RV     RR                           A       Fuel Pool Cooling Heat Exchanger Relief (See g                                                           Note 2) 2FC-1058                 lx.75 137-1                             D3         3/C   RV       -
o g
C    RV     RR                           A       Fuel Pool Cooling Heat Exchan er Relief (see Note 2 2FC-086                   10                     144-1           C2         2/A   G1       M     C     LT     RR           RV-19           P     Rx well bulkhead drain RV-37                 outboard (M65)(See Note 4) 2FC-113                   2                     144-1           D2         2/A   GB       M           LT C            RR           RV-19           P     Cond. to refuel bellows RV-37                 inboard (M59)(See Note 4,6) 2FC-ll4                   2                   144-1             D2         2/A   GB       M     C     LT     RR           RV-19           P     Cond. to refuel bellows RV-37                 outboard (M59)(See Note 4,6) 2FC-115                   10                   144-1             C2         2/A   GT       M     C     LT     RR           RV-19           P               bulkhead drain RV-37                  Rx   well(M65MSee Note) 4.0 inboard GE-T 2 -1180
A e.
05 [C6 00 01 02 03 04 07 08 09 10 11 12 13 2FC-044A 6
134-02 E6 3/C NSC C
E Q
A Fuel Pool Emergency Make Up Pump 2A Discharge Check 2FC-044B 6
134-01 C6 3/C NSC C
E Q
A Fuel Pool Emergency Make Up Pump 2B Discharge Check 2FC-105A 1x.75 137-1 D4 3/C RV C
RV RR A
Fuel Pool Cooling Heat Exchanger Relief (See g
Note 2) 2FC-1058 lx.75 137-1 D3 3/C RV C
RV RR A
Fuel Pool Cooling Heat Exchan er Relief (see Note 2 2FC-086 10 144-1 C2 2/A G1 M
C LT RR RV-19 P
Rx well bulkhead drain RV-37 outboard (M65)(See Note 4) 2FC-113 2
144-1 D2 2/A GB M
C LT RR RV-19 P
Cond. to refuel bellows RV-37 inboard (M59)(See Note 4,6) 2FC-ll4 2
144-1 D2 2/A GB M
C LT RR RV-19 P
Cond. to refuel bellows RV-37 outboard (M59)(See Note 4,6) 2FC-115 10 144-1 C2 2/A GT M
C LT RR RV-19 P
Rx well(M65MSee Note 4.0 bulkhead drain RV-37 inboard
)
GE-T 2 -1180


Commonwealth Edison
@ LaSalle County Nuclear Station Unit 2 Commonwealth Edison 1NSERVICE TESTlNG PLAN sysi m FW-Feedwater l
  @ LaSalle County Nuclear                                     ,
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                                                                                                                                  '  I g                ''
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qb        go* gs      y     c               gd                            O 98 00                  ot    02    / 03             04 / 05         06   07     08     09   to     11           12 /           13 1821-F010A                 24   118       A6           1/AC     NSC   -    0   E     RR           RV-06           A   Rx Feedwater Line Ovrck LT                 I!V-19               Valve (M-5)(See Note 1,4) 1821-F0108                 24   118       C6           1/AC     HSC   -
9 O
0    E     RR           IN-06           A   Rx Feedwater Line Ch ck i                           LT                 l'V-19               Valve (M-6)(See Note 1,4) 1821-F032A                 24   118       A6           t/AC                 0            RR NSC   A0         E                   FN-32           A   Rx Feedwater Line Dvck LT     RR         ny_g9               Valve (M-5)(See Note 1,4)
8 g
PIT     RR IB21-F032B                 24   118       C6           1/AC     NT   A0   0   E       RR         RV-32           A Rx Feedwater Line Check l
q g
p FN-19               Valve (M-6)(See Hote 1,4) 1021-F065A                 24   118       A5             2/A   GT   K)   O   FS,ST CS           RV-07           A Rx Feedwater Isolatirm LT     RR     132   IN-19               Valve (M-5)(See Note i,4)
g g
:                                          PIT   RR l
/ 03 04 / 05 06 07 08 09 to 11 12 /
IB21-F065B                 24   118       C5             2/A   GT ,MO     O   FS,ST CS           RV-07           A Rx Feedwater Isolattr*
13 00 ot 02 1821-F010A 24 118 A6 1/AC NSC 0
LT     RR     132   IN-19               Valve (M-6)(See Note i 4)
E RR RV-06 A
PIT   RR e
Rx Feedwater Line Ovrck LT I!V-19 Valve (M-5)(See Note 1,4) 1821-F0108 24 118 C6 1/AC HSC 0
E RR IN-06 A
Rx Feedwater Line Ch ck i
LT l'V-19 Valve (M-6)(See Note 1,4) 1821-F032A 24 118 A6 t/AC NSC A0 0
E RR FN-32 A
Rx Feedwater Line Dvck LT RR ny_g9 Valve (M-5)(See Note 1,4)
PIT RR IB21-F032B 24 118 C6 1/AC NT A0 0
E RR RV-32 A
Rx Feedwater Line Check l
FN-19 Valve (M-6)(See Hote 1,4) p 1021-F065A 24 118 A5 2/A GT K)
O FS,ST CS RV-07 A
Rx Feedwater Isolatirm LT RR 132 IN-19 Valve (M-5)(See Note i,4)
PIT RR l
IB21-F065B 24 118 C5 2/A GT
,MO O
FS,ST CS RV-07 A
Rx Feedwater Isolattr*
LT RR 132 IN-19 Valve (M-6)(See Note i 4)
PIT RR e
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NI                                                       O                                                                                     O Commonwealth Edisca
("%
              @ tasaii countyNuclear!NSERVICE                        St;tm.         Unit TESTING VALVES 2PLAN            system liG - Cont. Combustible Gas "80'         l ' 2                                                         Control
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00       01   02     03 / 04         05/06     07     08       09     10     11             12                                           13 2HG001A       4   130-2   F7       2/A   GT   M0   C   FS,ST   Q         22   RV-19         A       Upsteam HG Stop LT       RR                                   (M-53)(See Note 4,6) 2HG001B       4   130-2   E7       2/A   GT   M0   C   FS,ST   Q         22   RV-19         A       Upsteam HG Stop LT       RR                                     (M-33)(See Note 4,6) 2HG002A       4   130-2   F6       2/A   GC   M0   C   FS,ST   Q         66   RV-19         A       Downsteam G Stop LT       A                                     (M-53)(See Note 4) 2HG002B       4   130-2   E6       2/A   GB   M0   C   FS,ST iQ           66   RV-19         A       Downsteam HG Stop LT       RR                                     (M-33)(See Note 4) 2HG003       6   130-2' B6       2/5   GT   M0   0   FS,ST   Q         60   RV-19         A       Unit 2 Outlet to Unit 2 D/W l
' 2 Control VALVES
2HG005A       6   130-2 87       2/A ' GT   M0   C   FS,ST l0';        33   RV-19         A       Unit 2 Recombiner RTN LT                                             Downsteam Stop (M-102)
/-,/
/
/
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ep
.O h
O q.
00 01 02 03 / 04 05/06 07 08 09 10 11 12 13 2HG001A 4
130-2 F7 2/A GT M0 C
FS,ST Q
22 RV-19 A
Upsteam HG Stop LT RR (M-53)(See Note 4,6) 2HG001B 4
130-2 E7 2/A GT M0 C
FS,ST Q
22 RV-19 A
Upsteam HG Stop LT RR (M-33)(See Note 4,6) 2HG002A 4
130-2 F6 2/A GC M0 C
FS,ST Q
66 RV-19 A
Downsteam G Stop LT A
(M-53)(See Note 4) 2HG002B 4
130-2 E6 2/A GB M0 C
FS,ST iQ 66 RV-19 A
Downsteam HG Stop LT RR (M-33)(See Note 4) 2HG003 6
130-2' B6 2/5 GT M0 0
FS,ST Q
60 RV-19 A
Unit 2 Outlet to Unit 2 D/W l
2HG005A 6
130-2 87 2/A
' GT M0 C
FS,ST l0 33 RV-19 A
Unit 2 Recombiner RTN LT Downsteam Stop (M-102)
(See Note 4,6)
(See Note 4,6)
I 2HG005B       6   130-2 A7       2/A   GT   M0   C   FS,ST   Q         33   RV-19         A       Unit 1 Recombiner RTN LT       RR                                     Downstream Stop (M-95)
I 2HG005B 6
(See Note 4,6) 2HG006A         6   130-2 B6 , 2/A         CT   M0   C   FS,ST   Q         33   RV-19         A       Unit 2 Recombiner RTN j                         LT       RR                                     Upstream Stop (M-102)
130-2 A7 2/A GT M0 C
                                                      !                                                                        (See Note 4) 1
FS,ST Q
                                                -                I GE-T 2 -1180
33 RV-19 A
Unit 1 Recombiner RTN LT RR Downstream Stop (M-95)
(See Note 4,6) 2HG006A 6
130-2 B6, 2/A CT M0 C
FS,ST Q
33 RV-19 A
Unit 2 Recombiner RTN j
LT RR Upstream Stop (M-102)
(See Note 4) 1 I
GE-T 2 -1180


                                                                ~'s                                                                                                       ()
~'s
(U                                                           v                                             V OLa                                         I e Coun y Nuct a Ste o. On 12         lNSERVICE TESTING PLAN VALVES gstem iG-Cont. Combustible Gas Control l
()
                                                                    #                                                A    w        g4
(U V
                                                                                                                                          +'         $      g-h 00         01     02           / 04   05 / 06 , 07       08   09   10     11       12             13 I
v OLa lNSERVICE TESTING PLAN iG-Cont. Combustible Gas Control I e Coun y Nuct a Ste o. On 12 gstem VALVES l
i 2HG006B                   6     130-2   A6 i ?/ A     GT   MJ   C   FS,ST Q     33   RV-19         A Unit 1 Recombiner RTN         .
h 4
LT     RR                           Upstream Stop (M-95)
+'
(See Note 4) 2HG009                     6     130-2   C6     2/B   GT   M0   C   FS,ST Q     60                 A Unit 2 Outlet to Unit 1
g-A w
                                                                                                          ,!                                              D/W (See Note 4)
g 00 01 02
I   i i
/ 04 05 / 06, 07 08 09 10 11 12 13 I
GE.T 2 -1180
i 2HG006B 6
130-2 A6 i ?/ A GT MJ C
FS,ST Q
33 RV-19 A
Unit 1 Recombiner RTN LT RR Upstream Stop (M-95)
(See Note 4) 2HG009 6
130-2 C6 2/B GT M0 C
FS,ST Q
60 A
Unit 2 Outlet to Unit 1 D/W (See Note 4)
I i
i GE.T 2 -1180


c                                 .                  . ..          .
c O
O                                                                                 O                                                  O O La a eCoun yNuct a Sta                                                     INSERVICE  ioVALVES Unit   2 PLAN TESTING                gstem lip - tiigh Pressure Core Spr ay 1           2 1
O O
4                                 N                                   $      %                            9           4, 00    01                      02        ,f[0;4_         05 f/ '06       07     08     09   10       11       12               13 2E22-F001     14             141           A4     2/8           GT     MG     0     FS,ST   Q     140                 A   HPCS Pump Suction Stop From CST                   .
O La a eCoun yNuct a Sta io Unit 2 INSERVICE TESTING PLAN gstem lip - tiigh Pressure Core Spr ay VALVES 1
2E22-F002     24             141           A4     2/C           CV     -
2 1
C    E       Q                         A   HPCS Pump Suction Stop         i From CST 2E22-F004     12           141             DS     1/A           GT     M0       C   FS,ST   Q     14   RV-19         A   HPCS Injection Line St< p.
4 N
l LT       RR                             (Mll)(See tiote 5,4)           l l
9 4,
2E22-F005     12           141             D6     1/AC         NSC     A0       C   E       CS         RV-19         A   HPCS Injection Line Tent-PIT     RR         RV-35               able (M-ll)(See Note LT       RR                             5,7) 2E22-F012       4           141             C3     2/A         GT     M0       C   FS,ST   Q     22   RV-19         A   HPCS Pump Minimum flow LT       RR                             bypass line stop (Sec Note 4,6,8) 1 2E22-F014     1x2         141             B5     2/C         RY               C   RV       RR                         A   HPCS Water Leg Dischar,e v                                                        relief (See Note 2,4,F 6) 2E22-F015     18           141             86   2/A           GT     M0       C   FS,ST   Q     99   RV-19         A   HPCS Stop Pump Suction LT       RR                             from Suppression l                                                                   Chamber (See Note 4,6.
,f[0;4_
'06 07 08 09 10 11 12 13 00 01 02 05 /
f 2E22-F001 14 141 A4 2/8 GT MG 0
FS,ST Q
140 A
HPCS Pump Suction Stop From CST 2E22-F002 24 141 A4 2/C CV C
E Q
A HPCS Pump Suction Stop i
From CST 2E22-F004 12 141 DS 1/A GT M0 C
FS,ST Q
14 RV-19 A
HPCS Injection Line St< p l
LT RR (Mll)(See tiote 5,4) l l
2E22-F005 12 141 D6 1/AC NSC A0 C
E CS RV-19 A
HPCS Injection Line Tent-PIT RR RV-35 able (M-ll)(See Note LT RR 5,7) 2E22-F012 4
141 C3 2/A GT M0 C
FS,ST Q
22 RV-19 A
HPCS Pump Minimum flow LT RR bypass line stop (Sec Note 4,6,8) 1 2E22-F014 1x2 141 B5 2/C RY C
RV RR A
HPCS Water Leg Dischar,e relief (See Note 2,4,F v
6) 2E22-F015 18 141 86 2/A GT M0 C
FS,ST Q
99 RV-19 A
HPCS Stop Pump Suction LT RR from Suppression l
Chamber (See Note 4,6.
J ll) l 1
J ll) l 1
l GE-T 2 -1180 I
l GE-T 2 -1180 I


                                                                                                        ''%                                                O
O
()"\
()"\\
                                      \.                                                              (D                                                   LI system 11P - High Pressure Core Spray OLa                e Coun y Nuct a Sta n Unit 2             INSERVICE TESTING PLAN VALVES                        "'8*       '
(D LI
4@                           oO                                        cf                                        99 4             c,       a     s     y                                          4.0 00       01     02     03 / 04                  06   07     08       09   10       11       12             13 2E22-F016         24     141     B5   2/C     CV       -
\\.
C    E         RR         RV-10           A   HPCS Check Pump Suction from Suppression Chamber (See Note 1) 2E22-F024         16   141     C3 I 2/C       NSC     -
OLa INSERVICE TESTING PLAN system 11P - High Pressure Core Spray e Coun y Nuct a Sta n Unit 2
C    E         Q                           A   HPCS Pump Discharge Check 2E22-F007         3/4   141     C4   2/C     NSC     -
"'8*
0    E          Q                          A  HPCS Water Leg Pump 1                                                        Discharge Check l
VALVES 4@
I 2E22-F035         lx2   141     D2   2/C     RV I -         C   RV         RR                         A   HPCS Discharge Line Relief (See Note 2)                     ,
4 o
1 2E22-F028         10   134-01   B6     3/C , NSC       -
c, a
C    E         Q                           A   HPCS DLS Gen Cooling                   l l
s cf 4.0 9
Water Discharge Check                   l l
O 9
2E22-F319         4   134-01   A6     3/B     GT     M0     C   FS         Q           RV-01           A   HPCS Diesel Cooling                     l Water Strainer Bkswash Outlet Stp g
y 03 / 04 00 01 02 06 07 08 09 10 11 12 13 2E22-F016 24 141 B5 2/C CV C
2E22-F345         .75 134-01     B4     3/C     RV     -
E RR RV-10 A
C    RV         RR                         A   HPCS DG Cooler Inlet xl.0                                                                                           Relief (See Note 2)
HPCS Check Pump Suction from Suppression Chamber (See Note 1) 2E22-F024 16 141 C3 I 2/C NSC C
E Q
A HPCS Pump Discharge Check 0
E Q
A HPCS Water Leg Pump 2E22-F007 3/4 141 C4 2/C NSC 1
Discharge Check l
I 2E22-F035 lx2 141 D2 2/C RV I -
C RV RR A
HPCS Discharge Line Relief (See Note 2) 1 2E22-F028 10 134-01 B6 3/C, NSC C
E Q
A HPCS DLS Gen Cooling l
l Water Discharge Check l
l 2E22-F319 4
134-01 A6 3/B GT M0 C
FS Q
RV-01 A
HPCS Diesel Cooling l
Water Strainer Bkswash Outlet Stp g
2E22-F345
.75 134-01 B4 3/C RV C
RV RR A
HPCS DG Cooler Inlet xl.0 Relief (See Note 2)
GE-T 2 - 1180
GE-T 2 - 1180


C
/J^
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f'1 v                                                                                   U Commonwealth Edison
v U
  @ LaSalle                         County Nuclear Station Unit                                     p      2       pop IN-Drywell Instr. Nitro.
@ LaSalle County Nuclear Station Unit 2 Commonwealth Edison IN-Drywell Instr. Nitro.
1 of   3 VALVES
p pop 1
                  #                                    9    /c                      8                  @      d                   .O                                                   p 00                   01   02             03   04     c5     06     07     os     09     to       11       12                     13 21N001A                     2   66-3           F6     2/A   GB     A0     0     FS.ST   RR     40     RV-12       A   Drywell Suction Isolatior                                   -
of 3
LT     RR             RV-19           Fail Close (See Note 1, l                       FST     RR                             4,6) (M-54) 2IN001B                     2   66-3           F7     2/A   GG     A0     0     FS.ST   RR     40     RV-12       A   Drywell Suction Isolatio, i       LT     RR             RV-19           Fail Close (See Note 1, FST     RR                             4) (M-54) 2IN017                     1.5 66-3           B3     2/A   GS     A0     0     FS     RR             RV-12       A   Drywell Pneumatic-To LT     RR             RV-02           Drywell Fail Close (See FST     RR             RV-19           Note 1,4) (M-54) 2IN074                     1.5 66-3           E5     2/A   GB     A0     0     FS     RR             RV-02       A   Dryer Purging Valve Fail LT     RR             RV-12           Close (See Note 1,4,6)
VALVES 8
FST     RR             RV-19           (M-54) 2IN075                     1.5 66-3           E5     2/A   GB     A0     0     FS     RR             RV-02       A   Dryer Purging Valve Fail LT     RR             RV-12           Close (See Note 1,4)
d
FST     RR             RV-19           (M-54) 2Ii4045                     1x2 66-7           E3     3/C   RV     -
.O p
C    'RV     RR                             Ventilation System 21N046                     1x2 66-7           E2     3/C   RV     -
9
C    RV     RR                             Ventilation System GE-12 1180
/c 00 01 02 03 04 c5 06 07 os 09 to 11 12 13 21N001A 2
66-3 F6 2/A GB A0 0
FS.ST RR 40 RV-12 A
Drywell Suction Isolatior LT RR RV-19 Fail Close (See Note 1, l
FST RR 4,6) (M-54) 2IN001B 2
66-3 F7 2/A GG A0 0
FS.ST RR 40 RV-12 A
Drywell Suction Isolatio, i
LT RR RV-19 Fail Close (See Note 1, FST RR
: 4) (M-54) 2IN017 1.5 66-3 B3 2/A GS A0 0
FS RR RV-12 A
Drywell Pneumatic-To LT RR RV-02 Drywell Fail Close (See FST RR RV-19 Note 1,4) (M-54) 2IN074 1.5 66-3 E5 2/A GB A0 0
FS RR RV-02 A
Dryer Purging Valve Fail LT RR RV-12 Close (See Note 1,4,6)
FST RR RV-19 (M-54) 2IN075 1.5 66-3 E5 2/A GB A0 0
FS RR RV-02 A
Dryer Purging Valve Fail LT RR RV-12 Close (See Note 1,4)
FST RR RV-19 (M-54) 2Ii4045 1x2 66-7 E3 3/C RV C
'RV RR Ventilation System 21N046 1x2 66-7 E2 3/C RV C
RV RR Ventilation System GE-12 1180


                                                                                                                                .)                                                   L.
.)
system IN - Drywell Instrument Nitrogen OLa                              e Coun y Nuct a Sta i Unit 2         INSERVICE TESTING PL AN VALVES                          "*8*       '
L.
                                                          #                                9           c,           s     &              c,A      ''        h        r.O          q9 00                      01    02      03    04    05[06       07     08         09     10       11       12             13 2IN031                           .75   66-3   B5     2/A   GB     SO   O   FS       RR             RV-02         A   Tip Indexer Purge-Fail FST       RR             RV-12             Close (See Note 1,4,6)
OLa INSERVICE TESTING PL AN system IN - Drywell Instrument Nitrogen e Coun y Nuct a Sta i Unit 2
LT       RR             RV-19             (M-47)
"*8*
                                                                                                                                      /
VALVES h
2B21-F024A                       .75   66-4   F6     3/C   NSC   -
r.O q9 A
0    E         RR             RV-16         A   11SIV In Check (See Note 1) 2B21-F024B                       .75   66-4   F7     3/C   NSC' -       0   E         RR             RV-16         A   MSIV In Check (See Note
9 c,
                                                                                                            !                                                        1) j 2B21-F024C                       .75   66-4   F4     3/C   NSC   -
s c,
0    E         RR             RV-16         A   MSIV In Check (See Note 1) 2B21-F024D                       .75   66-4   F5     3/C   NSC   -
05[06 07 08 09 10 11 12 13 00 01 02 03 04 2IN031
0    E         RR             RV-16         A   MSIV In Check (See Note 1) 2B21-F040C                       .50   66-4   B2     3/C   NSC   -
.75 66-3 B5 2/A GB SO O
0    E         RR             RV-16         A   ADS In Check (See Note i                                                 1) 2B21-F040D                       .50   66-4   B4     3/C   NSC   -
FS RR RV-02 A
0    E         RR             RV-16         A   ADS In Check (See Note 1) 2B21-F050E                       .50   66-4   B7     3/C   NSC   -    0   E         RR             RV-16         A   ADS In Check (See Note 1)
Tip Indexer Purge-Fail FST RR RV-12 Close (See Note 1,4,6)
J l
LT RR RV-19 (M-47)
i            ,
/
                                                                                                !  -        I.
2B21-F024A
.75 66-4 F6 3/C NSC 0
E RR RV-16 A
11SIV In Check (See Note 1) 2B21-F024B
.75 66-4 F7 3/C NSC' -
0 E
RR RV-16 A
MSIV In Check (See Note 1) j 2B21-F024C
.75 66-4 F4 3/C NSC 0
E RR RV-16 A
MSIV In Check (See Note 1) 2B21-F024D
.75 66-4 F5 3/C NSC 0
E RR RV-16 A
MSIV In Check (See Note 1) 2B21-F040C
.50 66-4 B2 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note i
1) 2B21-F040D
.50 66-4 B4 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1) 2B21-F050E
.50 66-4 B7 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1)
J li I.
GC-T 2 -1180
GC-T 2 -1180


O                                                                                           O                                                   O INSERVICE TESTING PLAN                 system IN - Drywell Instrument Nitrogen OLaS                                                                    e Co n y Nu I a la 10 Unit 2 VALVES                      P898 3   of 3
O O
                                                            #                                    9     oO  ''    Y   A     3         c,A                            .O           gh 00                                             01   02       03   04   05     06   07     08   09               11       12             13 iu /
O OLaS INSERVICE TESTING PLAN system IN - Drywell Instrument Nitrogen e Co n y Nu I a la 10 Unit 2 P898 3
2B21-F040R                                                   .50 66-4   B7   3/C   NSC   -
of 3
0    E     RR             RV-16         A   ADS In Check (See Note
VALVES 9
: 1)                                             >
O Y
2821-F040S                                                   .50 66-4   B6   3/C   NSC   -
A 3
0    E     RR             RV-16         A   ADS In Check (See Note 1) 2821-F0400                                                   .50 66-4   B3   3/C   NSC   -
c,
0    E     RR             RV-16         A   ADS In Check (See Note 1) 2821-F040V                                                   .50 66-4   B5   3/C   NSC -
.O h
0    E     RR             RV-16         A   ADS In Check (See Note 1) 2IN043                                                       1     66-7   D1   3/C   NSC -
A o
0    E     RR             RV-12         A   ADS Supply Check (M-60) 2IN044                                                       1     66-7   04   3/C   NSC -
g 00 01 02 03 04 05 06 07 08 09 iu /
0    E     RR             RV-12         A   ADS Supply Check (M-55)
11 12 13 2B21-F040R
.50 66-4 B7 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1) 2821-F040S
.50 66-4 B6 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1) 2821-F0400
.50 66-4 B3 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1) 2821-F040V
.50 66-4 B5 3/C NSC 0
E RR RV-16 A
ADS In Check (See Note 1) 2IN043 1
66-7 D1 3/C NSC 0
E RR RV-12 A
ADS Supply Check (M-60) 2IN044 1
66-7 04 3/C NSC 0
E RR RV-12 A
ADS Supply Check (M-55)
GE-T2 -1180
GE-T2 -1180


("                                                           C\                                                                                             C V
("
Otas             e co n y Nu I a Sta o Unit 2           INSERVICE TESTING PLAN VALVES system LP-Low Pres. Core Spray
C\\
                                                                                                                                "*8* I       '
C V
I
Otas INSERVICE TESTING PLAN system LP-Low Pres. Core Spray e co n y Nu I a Sta o Unit 2
                                            #                    9      oO  c,'>    4     4    d           c,*                             s.0                                                   $
"*8*
00       01     02       03   04       5     06   07     08 ,    09     10       11         12                                             13 EE21-F001         24     140     B6   2/A   GT     M0   0   FS,ST     Q     132   RV-19           A   LPCS Suction From LT       RR                               Suppression Pool Stop (M-68)(See Note 4,6,11) 2E21-F003         16     140   C2     2/C   NSC     -
I I
C    E         Q                           A   LPCS Pump Discharge Chtck 2E21-F005         12     140   D6     1/A   GT     M0     C   FS,ST     CS     20   RV-04           A   LPCS Injection Line Out-LT       RR           RV-19               board Stop (M-10) (See Note 1,5,4) 2E21-F006         12     140   C6     1/AC   NSC   A0     C   E         CS           RV-35           A   LPCS Injection Line PIT       RR           RV-19               Testable Check Valve LT       RR                               (M-10)(See Note 1,5,7) 2E21-F0ll         4     140   C3     2/A   GT     M0     0   FS,ST     Q         4 RV-19           A   LPCS Min Flow Bypass Stp LT       RR                               (See Note 4,6,8)(M-77) 2E21-F018       3x4       140   DS     2/C   RV     -
VALVES 4
C    RV       RR                           A   LPCS Pump Discharge Relief (See Note 2,4,6.3) 2E21-F031       lx2       140   B4     2/C   RV     -
d c,*
C    RV       RR                           A   LPCS Pump Suction Relief (See Note 2,4,6,8) 2E21-F033       .75       140   C3     L, _' NSC           0   E         Q                           A   LPCS Water Leg Pump Discharge Check GE-T 2 - 1180
s.0 O
c,'>
4 9
o 00 01 02 03 04 5
06 07 08 09 10 11 12 13 EE21-F001 24 140 B6 2/A GT M0 0
FS,ST Q
132 RV-19 A
LPCS Suction From LT RR Suppression Pool Stop (M-68)(See Note 4,6,11) 2E21-F003 16 140 C2 2/C NSC C
E Q
A LPCS Pump Discharge Chtck 2E21-F005 12 140 D6 1/A GT M0 C
FS,ST CS 20 RV-04 A
LPCS Injection Line Out-LT RR RV-19 board Stop (M-10) (See Note 1,5,4) 2E21-F006 12 140 C6 1/AC NSC A0 C
E CS RV-35 A
LPCS Injection Line PIT RR RV-19 Testable Check Valve LT RR (M-10)(See Note 1,5,7) 2E21-F0ll 4
140 C3 2/A GT M0 0
FS,ST Q
4 RV-19 A
LPCS Min Flow Bypass Stp LT RR (See Note 4,6,8)(M-77) 2E21-F018 3x4 140 DS 2/C RV C
RV RR A
LPCS Pump Discharge Relief (See Note 2,4,6.3) 2E21-F031 lx2 140 B4 2/C RV C
RV RR A
LPCS Pump Suction Relief (See Note 2,4,6,8) 2E21-F033
.75 140 C3 L, _'
NSC 0
E Q
A LPCS Water Leg Pump Discharge Check GE-T 2 - 1180


O                                                                     O                                           O INSERVICE TESTING PLAN                  MC-Clean Condens. Storage La a e coun y Nucl a Sta i Unit 2                                                       gstem
O O
                                / % 3 d?:f M , $ ' / / /
O MC-Clean Condens. Storage INSERVICE TESTING PLAN gstem La a e coun y Nucl a Sta i Unit 2
00                               01   02 03   04   05   06   07   08   09   10     11       12             13 2CM027                                     3 75-4 C8 2/A GT   M   LC   LT   RR         RV-19       P (M-37)(See Note 13)               .
/ % 3 d?:f M, $ ' / / /
RV-37 2MC033                                     3 75-4 C8 2/A GT   M   LC   LT   RR         RV-19       P (M-37)(See Note 13)
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2CM027 3
75-4 C8 2/A GT M
LC LT RR RV-19 P
(M-37)(See Note 13)
RV-37 2MC033 3
75-4 C8 2/A GT M
LC LT RR RV-19 P
(M-37)(See Note 13)
RV-37 GE-T 2 -1180
RV-37 GE-T 2 -1180


O                                                                                                 O                                               O Commonwealth Edison O LaSalleCountyNuclearStat6onUnit                                                         INSERVICE TESTlNG PLAN VALVES 2           system MS-MAIN STEM u                     *'                    *
O O
                                                #                      U       0 0
O O LaSalleCountyNuclearStat6onUnit 2 Commonwealth Edison MS-MAIN STEM INSERVICE TESTlNG PLAN system VALVES u
* c,>   q n      y         &                C      g-                          8 9'
C U
00                                                   01   02   03     04   05   06   07     08   09   to     11         12             13 2021-F013A                                               8x10 116-1 D3       1/C   SRV A0   C     RV     RR                         A D m in Steam Line Safety /Reller Valve (See Note 2) 2B21-F0138                                               8x10 116-1 C3       1/C   SRV A0   C     RV     RR                         A A Main Steam Line Safety /Rellef Yalve (See Note 2) 2821-F013C                                               8x10 116-1 E2     1/BC   SRV A0   C     RV     RR         RV-33           A C Main Steam Line E       RR                           Safety / Relief Yalve (A05) (See Note 2) 2021-F0130                                               8x10 116-1 82             SRV A0   C     RV     RR         RV-33           A B Main Steam Line 1/BC E       R"                           Safety / Relief Valve (A05) (See Note 2) 2821 F013E                                               8x10 116-1 E3     1/BC   SRV A0   C     RV     RR         RV-33           A C Main Steam Line E       RR                           Safety / Relief Valve (ADS) (See Note 2)
0 c,>
q y
8 9'
0 n
g-00 01 02 03 04 05 06 07 08 09 to 11 12 13 2021-F013A 8x10 116-1 D3 1/C SRV A0 C
RV RR A
D m in Steam Line Safety /Reller Valve (See Note 2) 2B21-F0138 8x10 116-1 C3 1/C SRV A0 C
RV RR A
A Main Steam Line Safety /Rellef Yalve (See Note 2) 2821-F013C 8x10 116-1 E2 1/BC SRV A0 C
RV RR RV-33 A
C Main Steam Line E
RR Safety / Relief Yalve (A05) (See Note 2) 2021-F0130 8x10 116-1 82 1/BC SRV A0 C
RV RR RV-33 A
B Main Steam Line E
R" Safety / Relief Valve (A05) (See Note 2) 2821 F013E 8x10 116-1 E3 1/BC SRV A0 C
RV RR RV-33 A
C Main Steam Line E
RR Safety / Relief Valve (ADS) (See Note 2)


O                                             O                                                               O O LaSa eCo n yNucl a Sta                                           o Unit INSERVICE      2 PLAN TESTING VALVES gstem 2 MS-Main team
O O
                                                  #              9      0
O O LaSa eCo n yNucl a Sta o Unit 2 MS-Main team INSERVICE TESTING PLAN gstem 2 VALVES 9
* c3>           d           cf   'h                   .O                                   q. 8 00       01   02   03   04     05 06   07   08     09   to   11         12               13 2B21-F013F   8x10 116-1 B3   1/C   SRV   A0 C   RV     RR                       A   B Main Steam Line Safety / Relief Valve                           -
0 c3>
(See Note 2) 2B21-F013G   8x10 116-1 D6   1/C   SRV   A0 C   RV     RR                       A   D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013H     8x10 116-1 D4   1/C   SRV   A0 C   RV     RR                       A   D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013J     8x10 116-1 C4   1/C   SRV   A0 C   RV     RR                       A   A Main Steam Line Safety Relief Valve (See Note 2) 2821-F013K       8x10 116-1 B4   1/C   SRV   A0 C   RV     RR                       A   B Main Steam Line Safety Relief Valve (See Note 2)
d cf
'h
.O 8
q.
00 01 02 03 04 05 06 07 08 09 to 11 12 13 2B21-F013F 8x10 116-1 B3 1/C SRV A0 C
RV RR A
B Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013G 8x10 116-1 D6 1/C SRV A0 C
RV RR A
D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013H 8x10 116-1 D4 1/C SRV A0 C
RV RR A
D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013J 8x10 116-1 C4 1/C SRV A0 C
RV RR A
A Main Steam Line Safety Relief Valve (See Note 2) 2821-F013K 8x10 116-1 B4 1/C SRV A0 C
RV RR A
B Main Steam Line Safety Relief Valve (See Note 2)
GE-T2 - 1180
GE-T2 - 1180


O                                                       O                                                                 O Commonwealth Edison O Lasone county Nuclear                                                                     Station INSERVICE            Unit TESTING VALVES 2
O O
PL AN          sysiem MS-MAIN STEM 4
O O Lasone county Nuclear Station Unit 2 Commonwealth Edison MS-MAIN STEM 4 INSERVICE TESTING PL AN sysiem 3
                                                                                                                                    "*"    3                    'II
'II VALVES O
                                                      #                  9      oO  s'>         8   y              c,*   ''
s'>
Q                            g.
8 c,*
O 00       01   02       03   04 j  05   06   07     08     09       10   11         12                           13 2021-F013L                                           8x10 116-1   E6       1/C   SRV A0   C   RV       RR                           A         C Main Steam Line Safety /Reller valve (See Note 2) 2821-F013M                                           8x10 116-1   B7       1/C   SRV A0   C   RV       RR                           A         B Main Steam Line Safety /Reller Valve
O g.
.                                                                                                                                                      (See flote 2) 2821-F013N                                           8x10 116-1   E7       1/C   SRV A0   C   RV       RR                           A         C Miln Steam Line Safety /Reller Valve (See Note 2) 2021-F013P                                           8x10 116-1   C6       1/C   SRV A0   C   RV       RR                           A         A Main Steam Line Safety / Relief Valve (See Note 2) 2021-F013R                                           8x10 116-1   E5     1/DC   SRV A0   C   RV       RR             RV-33         A         C Main Steam Line E         "R                                     Safety /Reller Valve (ADS)(See Note 2)
9 o
y Q
00 01 02 03 04 05 06 07 08 09 10 11 12 13 j
2021-F013L 8x10 116-1 E6 1/C SRV A0 C
RV RR A
C Main Steam Line Safety /Reller valve (See Note 2) 2821-F013M 8x10 116-1 B7 1/C SRV A0 C
RV RR A
B Main Steam Line Safety /Reller Valve (See flote 2) 2821-F013N 8x10 116-1 E7 1/C SRV A0 C
RV RR A
C Miln Steam Line Safety /Reller Valve (See Note 2) 2021-F013P 8x10 116-1 C6 1/C SRV A0 C
RV RR A
A Main Steam Line Safety / Relief Valve (See Note 2) 2021-F013R 8x10 116-1 E5 1/DC SRV A0 C
RV RR RV-33 A
C Main Steam Line E
"R Safety /Reller Valve (ADS)(See Note 2)


l I
l O
O                                                                                                         O                                                                     O INSERVICE TESTING PLAN                         system Ms. MAIN STEM O CommonwealthEdison LaSalle County Nuclear Station Unit 2 VALVES                            ""'    4 11
O O
                    /                                                                   5     no  e,''           s$                        e,A                                                  $
I O CommonwealthEdison INSERVICE TESTING PLAN system Ms. MAIN STEM LaSalle County Nuclear Station Unit 2 4
Y                                     ''
11 VALVES s$
s .O 00                       01                                         02   03   04     05     06   07     os             09     to     11                                     13 2821-F0135         8x10                                                 116-1 86   1/BC SRV     A0   C   RV               RR           RV-33         A   B Main Steam Line E               RR                               Safety /Reller Valve (ADS)(See Note 2) 2B21-F013U         8x10                                                 116-1 07   1/BC SRV     AD   C   RV               RR           RV-33           A   D Main Steam Line E               RR                               Safety / Relief Ysive (ADS)(See Note 2) 2B21-F013V         8x10                                                 116-1 C7   1/BC SRV     AD   C   RV               RR           RV-33         A   A min Steam Line E               RR                               Safety / Relief Valve (ADS)(See Note 2) 2B21-F016         3                                                   116 7 07       1/A GT   ,
/
KJ   0   FS,ST           Q     15   RV-19           A   Main Steam Inboard LT               RR                               Orain Line Isolation Pli             HR                               Valve (See Note 4,6) 2B21-F019         3                                                   116 7 06       1/A GT     W     0   FS ST           Q     15   RV-19           A   Outboard Orain Line LT               HH                               Nin Steam Isolation PIT             HH                               Valve (See Note 4) l
5 o
e,''
Y A
s.O e,
n 00 01 02 03 04 05 06 07 os 09 to 11 13 2821-F0135 8x10 116-1 86 1/BC SRV A0 C
RV RR RV-33 A
B Main Steam Line E
RR Safety /Reller Valve (ADS)(See Note 2) 2B21-F013U 8x10 116-1 07 1/BC SRV AD C
RV RR RV-33 A
D Main Steam Line E
RR Safety / Relief Ysive (ADS)(See Note 2) 2B21-F013V 8x10 116-1 C7 1/BC SRV AD C
RV RR RV-33 A
A min Steam Line E
RR Safety / Relief Valve (ADS)(See Note 2) 2B21-F016 3
116 7 07 1/A GT
, KJ 0
FS,ST Q
15 RV-19 A
Main Steam Inboard LT RR Orain Line Isolation Pli HR Valve (See Note 4,6) 2B21-F019 3
116 7 06 1/A GT W
0 FS ST Q
15 RV-19 A
Outboard Orain Line LT HH Nin Steam Isolation PIT HH Valve (See Note 4) l


O                                                                           O                                                 O i
O O
commonwealth Edison                                                                       s sem MS-MAIN TEM LaSalle County Nuclear Station Unit 2             INSERVICE TESTING PLAN i
O i
U
commonwealth Edison MS-MAIN TEM INSERVICE TESTING PLAN s sem LaSalle County Nuclear Station Unit 2 i
* AY                      O O
AY U
p>'c'    sY    n    y           40    +         g)       g-               N I
O n
00                                       01   02   03   04       05   06   07     08     09   10     11       12             13
y 4
!    2821-F022A                                                                       26   116-2 C6     1/A     m     A0   0     PS     Q       3-5 RV-22         A A MSIV Inboard (M-1)
+
FS,ST CS                             (See Note 1,4,6.12)
g) g-N p>'
FST   CS PIT   RR                                                             ,
sY 0
I LT     RR           RV-19 2B21-F022B                                                                       26   116-2 B6     1/A     m     A0   0     PS     Q       3-5 RV-22         A B MSIV Inboard (M-2)
c' O
,                                                                                                                                  FS.ST CS                             (See Note 1.4.12.6) j                                                                                                                                   FST   CS
I 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2821-F022A 26 116-2 C6 1/A m
!                                                                                                                                  PIT   Rit LT     RR           RV-19 2021-F022C                                                                       26   116-2 F6     1/A     m     A0   0     PS     Q       3-5 RV-22         A C MSIV Inboard     (M-3) l                                                                                                                                   FS,ST CS                             (See Note 1.4.12.61
A0 0
;                                                                                                                                  FST   CS
PS Q
,                                                                                                                                  Pli   RR LT     RR           RV-19 i
3-5 RV-22 A A MSIV Inboard (M-1)
2021-F0220                                                                       26   116-2 06     1/A     m     A0   0     PS     Q       3-5 RV-22         A D MSIV Inboard     (M-4)
FS,ST CS (See Note 1,4,6.12)
!                                                                                                                                  FS.ST CS                             (See Note 1,4,12,6) i                                                                                                                                   FST   CS
FST CS PIT RR I
$                                                                                                                                  PIT   RR LT     RR           RV-19 t
LT RR RV-19 2B21-F022B 26 116-2 B6 1/A m
:    2021-FO?tm                                                                       26   116-2 C4     1/A     m     A0   0     PS     Q       3-5   RV-22         A A f1Siv Outboard (M-1)
A0 0
FS,ST CS                             (See Note 1,4,12)
PS Q
FST   CS PIT   llR LT     RR           RV-19 i
3-5 RV-22 A B MSIV Inboard (M-2)
  $ th t               I$Nn
FS.ST CS (See Note 1.4.12.6) j FST CS PIT Rit LT RR RV-19 2021-F022C 26 116-2 F6 1/A m
A0 0
PS Q
3-5 RV-22 A C MSIV Inboard (M-3) l FS,ST CS (See Note 1.4.12.61 FST CS Pli RR LT RR RV-19 i
2021-F0220 26 116-2 06 1/A m
A0 0
PS Q
3-5 RV-22 A D MSIV Inboard (M-4)
FS.ST CS (See Note 1,4,12,6) i FST CS PIT RR LT RR RV-19 t
2021-FO?tm 26 116-2 C4 1/A m
A0 0
PS Q
3-5 RV-22 A A f1Siv Outboard (M-1)
FS,ST CS (See Note 1,4,12)
FST CS PIT llR LT RR RV-19 i
$ th t I$Nn


O                                                     O                                                                                                   O Commonwealth Edison                                                                          *3 O LaSalle County Nuclear                               Station INSERVICE     TESTING VALVES Linit PLAN 2          system Pag,   6     og11
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                  #                9     no e,)           5                  e,A '                            O gC 00       01   02   03   04     05     06   07     08     09       10     11         12                                                           13
O O LaSalle County Nuclear Station Linit 2 Commonwealth Edison
. 2B21-F028B     26   116-2 B4   1/A   W     10   0   PS       Q       3-S   RV-22         A   B MSIV Outboard (M-2)
*3 INSERVICE TESTING PLAN system
FS,ST   CS                                 (See flote 1,4,12)
: Pag, 6
FST     CS PIT     RR LT       RR             RV-l?
og11 VALVES 5
2821-F028C       26   116-2 F4   1/A   08     10   0   PS       Q       3-5   RV-22         A   C MSIV Dutboard (M-3)
e, '
FS,ST   CS                                 (See flote 1,4,12)
A O
FST     CS PIT     RR LT     RR             RV-19 2821-F0280       26   116-2 04   1/A   W     A0   0   PS       Q       3-5   RV-22         A   D MSIV Outtx)ard (M-4)
C 9
FS,ST   CS                                 (See flote 1,4,12)
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FST     CS PIT     llR LT     RR             RV-19 2821-F067A       1.5   116-7 E6   1/A   PG   M1     C   FS,ST   Q       '23     RV-19         A   A MSIV Outboard Drain Li     RR                                 Isolation (See flote 4.12) 2821-F0670       1.5   116-7 E5   1/A   PG   H1     C   FS,ST   Q       23     RV-19         A   0 MSIV Dutboard Drain LT     IIR                                 isolation (S''e flote 4,12) 2821-F067C       1.5   116-7 E7   1/A   PG   t11   C   FS.ST   Q       ?3     RV-19         A   C MSIV Outboard Drain LT     ltR                                 Isolation (See flote 4,12) 2B21-F0670       1.5   116-7 E6   1/A   PG   HI     C   FS,ST   U       ?3     liv-19         A   D MSIV Otilboard Drain LT     RR                                 Isolation (See flote 4,12)
g n
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2B21-F028B 26 116-2 B4 1/A W
10 0
PS Q
3-S RV-22 A
B MSIV Outboard (M-2)
FS,ST CS (See flote 1,4,12)
FST CS PIT RR LT RR RV-l?
2821-F028C 26 116-2 F4 1/A 08 10 0
PS Q
3-5 RV-22 A
C MSIV Dutboard (M-3)
FS,ST CS (See flote 1,4,12)
FST CS PIT RR LT RR RV-19 2821-F0280 26 116-2 04 1/A W
A0 0
PS Q
3-5 RV-22 A
D MSIV Outtx)ard (M-4)
FS,ST CS (See flote 1,4,12)
FST CS PIT llR LT RR RV-19 2821-F067A 1.5 116-7 E6 1/A PG M1 C
FS,ST Q
'23 RV-19 A
A MSIV Outboard Drain Li RR Isolation (See flote 4.12) 2821-F0670 1.5 116-7 E5 1/A PG H1 C
FS,ST Q
23 RV-19 A
0 MSIV Dutboard Drain LT IIR isolation (S''e flote 4,12) 2821-F067C 1.5 116-7 E7 1/A PG t11 C
FS.ST Q
?3 RV-19 A
C MSIV Outboard Drain LT ltR Isolation (See flote 4,12) 2B21-F0670 1.5 116-7 E6 1/A PG HI C
FS,ST U
?3 liv-19 A
D MSIV Otilboard Drain LT RR Isolation (See flote 4,12)


O                                                             O                                                       O Commonwealth Edison O LaSalleCountyNuclearStationUnit                                                INSERVICE TESTING PLAN 2              system MS - Main Steam Page   j   of    y)
O O
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O O LaSalleCountyNuclearStationUnit 2 Commonwealth Edison INSERVICE TESTING PLAN system MS - Main Steam Page j
y             3                             .O            #
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00             01     02     03   04     05     06   07       08     09       to     11         12             13 2E32-F001A                           2.5     116-8 F3       1/A                     FS,ST         13.75 GT    M0    C            CS              RV-Il         A     MS Loop A Bleed Valve LT       RR             RV-19               Outboard (See Note 1.4.12) 2E32-F001E                           2.5     116-8   E3     1/A GT   M0     C   FS,ST   CS     13.75   RV-Il         A     MS Loop B Bleed Valve LT       RR             RV-19               Outboard (See Note 1,4,12) 2E32-F001]                             2.5     116-8 C3       1/A GT   M)     C     FS,ST   CS     13.75   RV-Il         A     MS Loop C Bleed Valve LT       RR             RV-19               Outboard (See flote 1,4,12) 2E32-F00lN                             2.5     116-8 C3       1/A GT   M0     C     FS,ST   CS     I3.75   W-Il         A   MS toop D Bleed valve LT       RR             RV-19               Outboard (See flote 1.4.12) 2E32-F003A                               2'   116-8 F4       2/B   GB   M0     C     FS,ST             60
O e,6 Y
:                                                                                                                                            CS              RV-Il         A   MS Loop A Bypass to Steam tmnel (See Note 1) 2E 32-F003E                               2     116-8   04     2/B   GB   M0     C     FS,ST   CS       60     RV-Il         A   MS Loop B Bypass to Steam tmoel (See Note 1) 2E 32-F003]                               2     116-8   C4     2/B   GB   HO     C     FS,ST             60 CS              RV-Il         A   MS Loop C Byruss to Steam tmnel (See Note 1) 2E 32-F003N                                 3     116-8   B4     2/0   GT   MO     C     FS,ST   CS       30     RV-Il         A   MS Loop D Dypass to Stearn tmnel (See Note 1)
O c*
                                        .?E 32-F00/A                               2.5     116-8   F3     2/0   GI   HO     C     FS,ST   CS     25     RV-Il         A   MS Loop A niced valve (See tht e I)
.O o
y 3
00 01 02 03 04 05 06 07 08 09 to 11 12 13 2E32-F001A 2.5 116-8 F3 1/A GT M0 C
FS,ST CS 13.75 RV-Il A
MS Loop A Bleed Valve LT RR RV-19 Outboard (See Note 1.4.12) 2E32-F001E 2.5 116-8 E3 1/A GT M0 C
FS,ST CS 13.75 RV-Il A
MS Loop B Bleed Valve LT RR RV-19 Outboard (See Note 1,4,12) 2E32-F001]
2.5 116-8 C3 1/A GT M)
C FS,ST CS 13.75 RV-Il A
MS Loop C Bleed Valve LT RR RV-19 Outboard (See flote 1,4,12) 2E32-F00lN 2.5 116-8 C3 1/A GT M0 C
FS,ST CS I3.75 W-Il A
MS toop D Bleed valve LT RR RV-19 Outboard (See flote 1.4.12) 2E32-F003A 2'
116-8 F4 2/B GB M0 C
FS,ST CS 60 RV-Il A
MS Loop A Bypass to Steam tmnel (See Note 1) 2E 32-F003E 2
116-8 04 2/B GB M0 C
FS,ST CS 60 RV-Il A
MS Loop B Bypass to Steam tmoel (See Note 1) 2E 32-F003]
2 116-8 C4 2/B GB HO C
FS,ST CS 60 RV-Il A
MS Loop C Byruss to Steam tmnel (See Note 1) 2E 32-F003N 3
116-8 B4 2/0 GT MO C
FS,ST CS 30 RV-Il A
MS Loop D Dypass to Stearn tmnel (See Note 1)
.?E 32-F00/A 2.5 116-8 F3 2/0 GI HO C
FS,ST CS 25 RV-Il A
MS Loop A niced valve (See tht e I)


O                                                                                             O                                                                     O l
O O
INSERVICE TESTING PLAN               sysieni         1 aS e Co n y Nu I a Sta o Unit 2                                                                   ,
O l
l
INSERVICE TESTING PLAN sysieni 1
                                          #                              U    0 0          t    8               ef     'h         c           O
aS e Co n y Nu I a Sta o Unit 2 l
                                                                                                                                                .                              p 00                                   01   02                   03   04     05   08   07     08   09     10     11         12                                   13 2E32-F002E                               2.5   116-8 E3                   2/B   GT   MD   C   FS,ST CS     25   RV-ll         A M5 Loop R Bleed Valve (See N0ce 1) 2E32-F002]                               2.5   116-8 D3                   2/B   GT   HD   C   FS,ST CS     25   RV-Il         A M5 Loop C Bleed Valve (See Note 1) 2E32-F002N                               2.5   116-8 C3                   2/B   GT   M0   C   FS,ST CS     25   RV-ll         A MS Loop D Blet.d Yalve (See Note 1) 2E32-F006                                 2.5   116-8 B3                   2/B   GT   m     C   FS,ST CS     25   RV-Il         A Bleed Valve-Steam Tunnel (See Note 1) 2E32-F007                                 2.5   116-8 84                   2/B   GT   m     C   FS,ST CS     25   RV-Il         A Bleed Valve-Steam Tunne1 (See Note 1) 2E32-F008                                 2.0   116-8 A4                   2/B   GB   M0   C   FS,ST CS     60   RV-Il         A Discharge to Steam Tunnel (See Hate 1) 2E32-F009                                 2.0   116-8 A4                   2/8   GB   M0   C   FS,ST CS     60   RV-Il         A Discharge to Steam Tunnel (See Note 1)
8 ef
'h U
0 t
O c
p 0
00 01 02 03 04 05 08 07 08 09 10 11 12 13 2E32-F002E 2.5 116-8 E3 2/B GT MD C
FS,ST CS 25 RV-ll A
M5 Loop R Bleed Valve (See N0ce 1) 2E32-F002]
2.5 116-8 D3 2/B GT HD C
FS,ST CS 25 RV-Il A
M5 Loop C Bleed Valve (See Note 1) 2E32-F002N 2.5 116-8 C3 2/B GT M0 C
FS,ST CS 25 RV-ll A
MS Loop D Blet.d Yalve (See Note 1) 2E32-F006 2.5 116-8 B3 2/B GT m
C FS,ST CS 25 RV-Il A
Bleed Valve-Steam Tunnel (See Note 1) 2E32-F007 2.5 116-8 84 2/B GT m
C FS,ST CS 25 RV-Il A
Bleed Valve-Steam Tunne1 (See Note 1) 2E32-F008 2.0 116-8 A4 2/B GB M0 C
FS,ST CS 60 RV-Il A
Discharge to Steam Tunnel (See Hate 1) 2E32-F009 2.0 116-8 A4 2/8 GB M0 C
FS,ST CS 60 RV-Il A
Discharge to Steam Tunnel (See Note 1)


O                                                             O                                               O                               .
O O
                                                                                                          ^                   P 11
O OLa
,  OLa                                  e Co n y Nucles Sta   Unit 2
^
                                                                        ,                  VALVES ge 9
P e Co n y Nucles Sta Unit 2 ge 9
Y     00  s'*                                          $                                    +
11 VALVES sY Y
sY 7      sY        y            4s~                   A-00                         01       02     03   04     05   06   07     08       09   10     11     12             13 2B21-F037Al                       12         138-1 C4     3/C   CV   -    C    E        RR          RV-28      A  Vacuum Breakers                                i 2B21-F037A2                       12         138-1 C4     3/C   CV   -     C   E       RR           RV-28       A Vacuum Breakers 2B21-F037B1                       12         138-1 C4     3/C   CV   -    C    E        RR          RV-28      A  Vacuum Breakers                                  '
0 s'
2B21-F03rB2                       12         138-1 C4     3/C   CV   -
sY s~
C    E       RR           RV-29       A Vacuum Breakers 2B21-F037C1                       12         138-1 C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers
A-
,      2B21-F037C2                       12         138-1 C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers 2821-F03701                       12         138-1 C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers 2B21-F03702                       12         138-1 C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers 2B21-F037El                       12         138-1 C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers 2B21-F037E2                       12         138-1 C4     3/C   CV   -    C   E       RP,         RV-28       A Vacuum Breakers 2B21-F037F1                       12         138-l C4     3/C   CV   -    C   E       RR           RV-28       A Vacuum Breakers 2B 21-F037F2                       12         138-1 C4     3/c   CV   -
+
C    E       RR           RV-28       A Vacimwn Breakers
0 y
    ,,e i s n o. .
4 7
00 01 02 03 04 05 06 07 08 09 10 11 12 13 C
E RR RV-28 A
Vacuum Breakers i
2B21-F037Al 12 138-1 C4 3/C CV 2B21-F037A2 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers C
E RR RV-28 A
Vacuum Breakers 2B21-F037B1 12 138-1 C4 3/C CV 2B21-F03rB2 12 138-1 C4 3/C CV C
E RR RV-29 A
Vacuum Breakers 2B21-F037C1 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037C2 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2821-F03701 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F03702 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037El 12 138-1 C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037E2 12 138-1 C4 3/C CV C
E RP, RV-28 A
Vacuum Breakers 2B21-F037F1 12 138-l C4 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B 21-F037F2 12 138-1 C4 3/c CV C
E RR RV-28 A
Vacimwn Breakers
,,e i s n o..


                                                                                                                                                                ~
~
O                                                                       O                                                                     O .
O O
E,.
O E,.
* t       en. oun y                   i   u nit 2                                                                               g
t en. oun y i
                                /                      **                                                                                    l , e**              /
u nit 2 g
00                            01  02
/ls[$''$**hh"'//
                                                              /ls[$''$**hh"'//
l e** /
03     04 05   06   07 OS   09 to     11                               12             13 12  138-1  C4      3/C CV  -    C    E     RR       RV-28                                 A Vacutse Breakers 2Br21-F037G1 138-1   C4       3/C CV       C    E      RR      RV-28                                A  Vacuum Breakers
/
.,    2B21-F037G2                             12                           -
00 01 02 03 04 05 06 07 OS 09 to 11 12 13 C
138-1   C5      3/C CV       C   E     RR       RV-28                                 A Vacuum Breakers 2B?l-F037K1                             12                            -
E RR RV-28 A
2B21-F037K2                            12   138-1   C5       3/C CV -    C   E     RR       RV-28                                 A Vacutan Breakers i
Vacutse Breakers 2Br21-F037G1 12 138-1 C4 3/C CV 2B21-F037G2 12 138-1 C4 3/C CV C
2B21-F037L1                             12   138-1   C5       3/C CV -    C   E     RR       RV-28                                 A Vacuum Breakers 2B21-F037L2                             12   138-1   C5       3/C CV -    C   E     RR       RV-28                                 A Vacuum Breakers 2B21-F037P1                             12   138-1   C5       3/C CV -    C   E     RR       RV-28                                 A Vacuum Breakers 2B21-F037P2                             12   138-1   C5       3/C CV -     C   E     RR       RV-28                                 A Vacuum Breakers 2821-F037R1                             12   138-1   C5       3/C CV   -    C    E      RR      RV-28                                  A  Vacuum Breakers 4
E RR RV-28 A
2B21-F037R2                           12   138-1   C5       3/C CV   -    C   E     RR       RV-28                                 A Vacuum Breakers 2B 21-F03751                           12   138-1   C5       3/C CV   -   C   E     RR       RV-28                                 A Vacuum Breakers 2B21-F03752                           12   138-1   C5       3/c CV   -    C    E      RR      RV-28                                  A Vactaan Breakers I
Vacuum Breakers C
E RR RV-28 A
Vacuum Breakers 2B?l-F037K1 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacutan Breakers 2B21-F037K2 12 138-1 C5 3/C CV i
2B21-F037L1 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037L2 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037P1 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037P2 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers C
E RR RV-28 A
Vacuum Breakers 2821-F037R1 12 138-1 C5 3/C CV 4
2B21-F037R2 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B 21-F03751 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers C
E RR RV-28 A Vactaan Breakers 2B21-F03752 12 138-1 C5 3/c CV I
j i
j i
r;s . s p s o m i                                                                                                         _ _ _ - - _ _ _ _ _ _ _ - _ _ _ -
r;s. s p s o m i


o                                                               o                                         b La       ey       is           unii 2                                           he      d  g 00
o o
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b he d
Of
La ey is unii 2 g
                                                          / /pf:,$**h,$h'*'"$
pf:,$**h,$h'*'"$f.?l
02     03           04   05     06   07   08   09 f.?l 10     11 12
,f'
                                                                                                                                    ,f' /      13 28:21-F037VI                 12       138-1 C5             3/C   CV     -    C     E   RR       RV-28     A   Vacuum Breakers 2821-F037V2                 12       138-1 C5             3/C CV     -    C     E   RR       RV-28     A   Vacuum Breakers 2B21-F037UI                 12       138-1 C5           3/C   CV     -
/
C    E     RR       RV-28     A   Vacuta Breakers 1
/
2B21-F03702                 12       138-1 C5           3/C   CV     -
/ /
C    E     RR       RV-28     A   Vacuum Breakers 2821-F037H1                 12       138-1 C6           3/C   CV     -    C     E     RR       RV-28     A   Vacuum Breakers 2821-F037H2                 12       138-1 C6             3/C   CV     -
00 Of 02 03 04 05 06 07 08 09 10 11 12 13 28:21-F037VI 12 138-1 C5 3/C CV C
C    E     RR       RV-28     A   Vacuum Breakers 2B21-F037]l                 12       138-1 C6             3/C   CV     -
E RR RV-28 A
C    E     RR       RV-28     A   Vacuta Breakers j               2821.F03732                 12       138-1 C6             3/C   CV   -      C     E     RR       RV-28     A   Vacuum Breakers
Vacuum Breakers 2821-F037V2 12 138-1 C5 3/C CV C
;              2E21-F037M1                 12       138-1 C6             3/C   CV   -
E RR RV-28 A
C    E     RR       RV-28     A   Vacula Breakers 2821-F037M2                 12       138-1 C6             3/C   CV   -
Vacuum Breakers 2B21-F037UI 12 138-1 C5 3/C CV C
C    E     RR       RV-28     A   Vacuum Breakers 2B21-F037N1                 12       138-1 C6             3/C   CV   -
E RR RV-28 A
C    E     RR       RV-28     A   Vacuum Breakers 2B?l-F037N2                 12       138-1 C6             3/c   CV   -      C     E     RR       RV-28     A   Vactam Breakers fil I ,* $ f Met
Vacuta Breakers 1
2B21-F03702 12 138-1 C5 3/C CV C
E RR RV-28 A
Vacuum Breakers 2821-F037H1 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuum Breakers 2821-F037H2 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037]l 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuta Breakers j
2821.F03732 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuum Breakers 2E21-F037M1 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacula Breakers 2821-F037M2 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B21-F037N1 12 138-1 C6 3/C CV C
E RR RV-28 A
Vacuum Breakers 2B?l-F037N2 12 138-1 C6 3/c CV C
E RR RV-28 A
Vactam Breakers fil I,* $ f Met


O                                                       O                                                                                           O O La a ec un yNuct a Sta                                   i n Unit INSERVICE           2 PLAN TESTING                    system NB - Nuclear Boiler VALVES
O O
                $                  9       oO    e,'' s       4    &          c,A                  h          r.
O O La a ec un yNuct a Sta i n Unit 2 INSERVICE TESTING PLAN system NB - Nuclear Boiler VALVES 4
00       01     02   03     04       05   06   07     08     09     10         11         12                                     13 2B21-F346         .75   139-3 86   2/AC     EFC         0   E LT   RR           RV-34           A     See Note 10 2821-F348       .75   139-3 A6   2/AC     EFC         0   E,LT   RR           RV-34           A     See Note 10 2821-F350       .75   139-3 A6   2/AC     EFC         0   E LT   RR           RV-34           A     See Note 10 r
c,A h
2B21-F344       .75   139-3 B3   2/AC     EFC         0   E.LT   RR           RV-34           A     See Note 10 2821-F353       .75   139-4 A5   2/AC   EFC           0   E,LT   RR           RV-34           A     See Note 10 2821-F355       .75   139-4 B5   2/AC     EFC         0   E.Li     RR           RV-34           A   See Note 10 2B21-F357       .75     139-4 05   2/AC     EFC         0   E.LT     RR           RV-34           A   See Note 10 2821-F359       .75   139-4 C5   2/AC     EFC         0   E LT   RR           RV-34           A     See Note 10 2B21-F361       .75   139-4 DS   2/AC     EFC         0   E LT   RR           RV-34           A   See Note 10 2B21-F363       .75     139-4 C5   2/AC     EFC         0   E,LT   RR           RV-34           A     See Note 10 2B21-F365       .75     139-4 ES   2/AC   EFC           0   F,LT   RR           RV- 34         A     See Note 9 2B21-F367       .75     139-4 A5   2/AC   EFC           0   F,LT   RR           RV-34           A     See Note 9 2B 21-f 370     .75     139-5 A6   2/AC   rrC           0   F,LT   PR           RV-31           A     See Note 10 2B El-F372     .75     139-5 C6   2/AC   IFC         0     F,LT   PR           R '.' u         A     sen note in GE f ? -IIRO
9 O
e,''
s r.
o 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2B21-F346
.75 139-3 86 2/AC EFC 0
E LT RR RV-34 A
See Note 10 2821-F348
.75 139-3 A6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F350
.75 139-3 A6 2/AC EFC 0
E LT RR RV-34 A
See Note 10 r
2B21-F344
.75 139-3 B3 2/AC EFC 0
E.LT RR RV-34 A
See Note 10 2821-F353
.75 139-4 A5 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F355
.75 139-4 B5 2/AC EFC 0
E.Li RR RV-34 A
See Note 10 2B21-F357
.75 139-4 05 2/AC EFC 0
E.LT RR RV-34 A
See Note 10 2821-F359
.75 139-4 C5 2/AC EFC 0
E LT RR RV-34 A
See Note 10 2B21-F361
.75 139-4 DS 2/AC EFC 0
E LT RR RV-34 A
See Note 10 2B21-F363
.75 139-4 C5 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F365
.75 139-4 ES 2/AC EFC 0
F,LT RR RV-34 A
See Note 9 2B21-F367
.75 139-4 A5 2/AC EFC 0
F,LT RR RV-34 A
See Note 9 2B 21-f 370
.75 139-5 A6 2/AC rrC 0
F,LT PR RV-31 A
See Note 10 2B El-F372
.75 139-5 C6 2/AC IFC 0
F,LT PR R '.' u A
sen note in GE f ? -IIRO


Q                                                     O
Q O
[
[
                                                                                                                                                            \
\\
INSERVICE TESTING PLAN             gstem NB - Nuclear Boiler La e coun y Nuct a Sta on Unit 2 00
INSERVICE TESTING PLAN NB - Nuclear Boiler La e coun y Nuct a Sta on Unit 2 gstem
                                                            /
/ mp6%%,Q'// /
01 mp6%%,Q'//
00 01 2
2       03   04   05 06 07     08   09 10       11         12             13
03 04 05 06 07 08 09 10 11 12 13 2821-F374
                                                                                                                                                            /
.75 139-5 D6 2/AC EFC 0
2821-F374                                             .75   139-5     D6   2/AC EFC       0 E LT   RR       RV-34           A   See Note 10 2B21-F376                                             .75   139-5     B6   2/AC EFC       0 E.LT   RR       RV-34           A   See Note 10 2B 21-F378                                           .75   139-5     E6   2/AC EFC       0 E,LT   RR       RV-34           A   See Note 10 2B 21-F380                                           .75   139-5     A6   2/AC EFC       0 E,LT   RR       RY-34           A   See Note 9 2B21-F382                                           .75   139-5     F6   2/AC EFC       0 E.LT   RR       RV-34           A   See Note 9 2B21-F437                                           .75   139-3     E3   2/AC EFC       0 E.LT   RR       RV-34           A   See Note 10 2B21-F439                                             .85   139-3     E3   2/AC EFC       0 E,LT   RR       RV-34           A   See Note 10 2B21-F441                                           .75   139-3     D3   2/AC   EFC       0 E,LT   RR       RV-34           A   See Note 10 2821-F443                                             .75   139-3     D3   2/AC   EFC       0 E,LT   RR       RV-34           A   See Note 10 2B21-F445A                                           .75   139-3     03 2/AC     EFC       0 E,LT   RR       RV-34           A   See Note 10 2B21-F4458                                           .75   139-3     D3   2/AC   EFC       0 E ,LT RR       RV-34           A   See Note 10 2B21- F447                                           .75   139-3     C3   2/AC   EFC       0 E,LT   RR       RV-34           A   See Note 10 2821-F449                                           .75   139-3     C3   2/AC   EFC       0 f,LT   RR       RV-14           A   See Note 10 2821-F451                                           .75   139-3     C3   2/AC   FFC       0 I ,LT RR       RV- 14         A   See Note 10 C E- T 7 -1180
E LT RR RV-34 A
See Note 10 2B21-F376
.75 139-5 B6 2/AC EFC 0
E.LT RR RV-34 A
See Note 10 2B 21-F378
.75 139-5 E6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B 21-F380
.75 139-5 A6 2/AC EFC 0
E,LT RR RY-34 A
See Note 9 2B21-F382
.75 139-5 F6 2/AC EFC 0
E.LT RR RV-34 A
See Note 9 2B21-F437
.75 139-3 E3 2/AC EFC 0
E.LT RR RV-34 A
See Note 10 2B21-F439
.85 139-3 E3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F441
.75 139-3 D3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F443
.75 139-3 D3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F445A
.75 139-3 03 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F4458
.75 139-3 D3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F447
.75 139-3 C3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F449
.75 139-3 C3 2/AC EFC 0
f,LT RR RV-14 A
See Note 10 2821-F451
.75 139-3 C3 2/AC FFC 0
I,LT RR RV-14 A
See Note 10 C E-T 7 -1180


O                                                                                 O                                                   O system NB - Nuclear Boiler OLa            e co n y Nuct a Sta l Unit 2                                     INSERVICE TESTING PLAN VALVES Page 3 of     3
O O
                                                                                                  /
O OLa INSERVICE TESTING PLAN system NB - Nuclear Boiler e co n y Nuct a Sta l Unit 2 Page 3
              #                                                  &      00  c,6     s                 A co
of 3
                                                                                                              ''                s.O                    f 00                                               02 03     04     05 06 07 [ 08      09   10     11       12             13 2B21-F453         .75                                 139-3   C3 2/AC   EFC       0 E,LT   RR         RV-34       A dee Hot.e IU 2B21-F455A       .75                                 139-3   B3 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F445B       .75                                 139-3   B3 2/AC   EFC       0 E,LT   RR'         RV-34       A See Note 10 2821-F457         .75                                 139-3   E6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F459         .75                                 139-3   E6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F461         .75                                 139-3   D6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F463         .75                                 139-3   D6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F465A       .75                                 139-3   D6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note W 2B21-F465B       .75                                 139-3   D6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F467         .75                                 139-3   C6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2821-F469         .75                                 139-3   C6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F471         .75                               139-3     C6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F473         .75                                 139-3   C6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2B21-F475A       .75                                 139-3   B6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 2821-F475B       .75                                 139-3   B6 2/AC   EFC       0 E,LT   RR         RV-34       A See Note 10 GE-T2 -1180
VALVES
/
A s.O f
0 c,6 s
co 0
07 [ 08 00 02 03 04 05 06 09 10 11 12 13 2B21-F453
.75 139-3 C3 2/AC EFC 0
E,LT RR RV-34 A
dee Hot.e IU 2B21-F455A
.75 139-3 B3 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F445B
.75 139-3 B3 2/AC EFC 0
E,LT RR' RV-34 A
See Note 10 2821-F457
.75 139-3 E6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F459
.75 139-3 E6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F461
.75 139-3 D6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F463
.75 139-3 D6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F465A
.75 139-3 D6 2/AC EFC 0
E,LT RR RV-34 A
See Note W 2B21-F465B
.75 139-3 D6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F467
.75 139-3 C6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F469
.75 139-3 C6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F471
.75 139-3 C6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F473
.75 139-3 C6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2B21-F475A
.75 139-3 B6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 2821-F475B
.75 139-3 B6 2/AC EFC 0
E,LT RR RV-34 A
See Note 10 GE-T2 -1180


7                                               q                                                   p (d                                               V O La a eCo n yNuct a Sta                                                   lo VALVES INSERVICE  Unit   2 PLAN TESTING                system PC-Primary Containment Vent Purge
l 7
                                                                                                                            "*8' I       '    I
q p
                                                      #            &      oO    c,''   sr   $ &            cf   *)~
(d V
z.O         gh 00   01   02   03   04     05     08 07   08     09   10     11         12             13 2PC001A                     24 138-2 D6   2/C   CV       -
O La a eCo n yNuct a Sta lo Unit 2 INSERVICE TESTING PLAN system PC-Primary Containment Vent Purge VALVES
C  E       Q                         A   Vacuum Breakers
"*8' I
!                          2PC001B                     24 138-2 E6   2/C   CV       -
I O
C  E       Q                         A   Vacuum Breakers IPC001C                     24 138-2 D3   2/C   CV     -
c,''
C  E       Q                         A   Vacuum Breakers 2PC001D                       24 138-2 E3   2/C   CV     -
sr cf
C  E       Q                         A   Vacuum Breakers GE-T2 1180
*)~
z.O h
o g
00 01 02 03 04 05 08 07 08 09 10 11 12 13 2PC001A 24 138-2 D6 2/C CV C
E Q
A Vacuum Breakers 2PC001B 24 138-2 E6 2/C CV C
E Q
A Vacuum Breakers IPC001C 24 138-2 D3 2/C CV C
E Q
A Vacuum Breakers 2PC001D 24 138-2 E3 2/C CV C
E Q
A Vacuum Breakers GE-T2 1180


O                                                   O                                                   O O Las eCo n yNuc a StaINSERVICE                    io Unit     2 TESTING VALVES PLAN           System RD-Control Rod Drive
O O
                                                                                          "*8*   I   '    I
O O Las eCo n yNuc a Sta io Unit 2 INSERVICE TESTING PLAN System RD-Control Rod Drive
                                                                                              &b
"*8*
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CO     01   02   03     04     05   06   07   08     09     10     11         12             13 2Cll-0001-126       146-3 D6   NC/B   GT           0   FS       RV-30       RV-30         A   Scram Testing (185)                                                   FST     RV-30 2Cll-0001-127       146-3 E3   NC/B   GT           0   FS       RV-30       RV-30         A   Scram Testing (185)                                                   FST     RV-30 2Cll-D001-ll 4       146-3 E3   NC/C   CV           0   E       RV-30         RV-30         A   Scram Testing (185) 2Cll-F380       2   146-2     2/B   CNV   A0     0   FS     Q             RV-26         A   CRD Scram Discharge FST                                     Instrument Volume Vent 2Cll-F381       2   146-2     2/B   CNV   A0     0   FS     Q             RV-26         A   CRD Scram Discharge FST                                     Instrument Volume Drain 2C11-F388       2   146-2     2/B   CNV   A0     0   FS     Q             RV-26         A   CRD Scram Discharge FST                                     Instrument Volume Vent 2C11-F389       2   146-4     2/B   CNV   A0     0   FS     Q             RV-26         A   CRD Scram Discharge FST                                     Instrument Volume Drain i
Y cf r.
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0 CO 01 02 03 04 05 06 07 08 09 10 11 12 13 2Cll-0001-126 146-3 D6 NC/B GT 0
FS RV-30 RV-30 A
Scram Testing (185)
FST RV-30 2Cll-0001-127 146-3 E3 NC/B GT 0
FS RV-30 RV-30 A
Scram Testing (185)
FST RV-30 2Cll-D001-ll 4 146-3 E3 NC/C CV 0
E RV-30 RV-30 A
Scram Testing (185) 2Cll-F380 2
146-2 2/B CNV A0 0
FS Q
RV-26 A
CRD Scram Discharge FST Instrument Volume Vent 2Cll-F381 2
146-2 2/B CNV A0 0
FS Q
RV-26 A
CRD Scram Discharge FST Instrument Volume Drain 2C11-F388 2
146-2 2/B CNV A0 0
FS Q
RV-26 A
CRD Scram Discharge FST Instrument Volume Vent 2C11-F389 2
146-4 2/B CNV A0 0
FS Q
RV-26 A
CRD Scram Discharge FST Instrument Volume Drain i
GE-T2 -1180
GE-T2 -1180


O                                                     O                                                                 O RF-React. Bldg Floor Drn.
O O
RE-React. Bldg Equip Drn.
O RF-React. Bldg Floor Drn.
O            Commo    en         n             INSERVICE TESTING PL AN VALVES system Page 1               of   I g                9 9     o*   g6    y     8              gU    6                                      O e0 10                  11            12              13 04     05   06   07     08     09 00      01    02    03 FS,ST Q     20   RV-19                       A     (M-96) Drywell 2RE024        2    137-4  84    2/A  CNY  A0    C Equipnent Drain stanp LT    RR suctlon.(See Note 4,6)
O Commo RE-React. Bldg Equip Drn.
A0         FS,ST Q     20   py_19                         A   (g_96) Drywell 2RE025        2    137-4  C4    2/A    HV        C Equipnent Drsin sump LT    RR suction.(See Note 4)
en n
FS,ST Q     20   RV-19                         A   (M-97) Gland Seal 2RE026        1     137-4 05    2/A   CNV   A0   C Reservolt Drywell LT    RR Equipnent (See Note 4)
INSERVICE TESTING PL AN system Page 1 of I
FS,ST Q     20   py_19                         A     (M-97) Gland Seal 2RE029        1    137-4 DS    2/A   CNV   A0   C Reservoir Drywell LT      RR Equipnent (See Note 4)
VALVES O
A0          FS.ST       20   RV-19                         A   Floor Drain (Drywell) 2RF012        2      137-4 A4    2/A  CNV        C            Q Sump Suction (M-98) F.C.
0 8
LT    RR (See Note 4)
U 6
B4     2/A   CNY   A0   C   FS,ST ]       20   RV-19                           A   Drywell Floor Sump 2RF013        2    137-4                                                                                        Suction (M-93) F.C.
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LT    RR (See Note 4)
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9 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2RE024 2
137-4 84 2/A CNY A0 C
FS,ST Q
20 RV-19 A
(M-96) Drywell LT RR Equipnent Drain stanp suctlon.(See Note 4,6) 2RE025 2
137-4 C4 2/A HV A0 C
FS,ST Q
20 py_19 A
(g_96) Drywell LT RR Equipnent Drsin sump suction.(See Note 4) 2RE026 1
137-4 05 2/A CNV A0 C
FS,ST Q
20 RV-19 A
(M-97) Gland Seal LT RR Reservolt Drywell Equipnent (See Note 4) 2RE029 1
137-4 DS 2/A CNV A0 C
FS,ST Q
20 py_19 A
(M-97) Gland Seal LT RR Reservoir Drywell Equipnent (See Note 4) 2RF012 2
137-4 A4 2/A CNV A0 C
FS.ST Q
20 RV-19 A
Floor Drain (Drywell)
LT RR Sump Suction (M-98) F.C.
(See Note 4) 2RF013 2
137-4 B4 2/A CNY A0 C
FS,ST
]
20 RV-19 A
Drywell Floor Sump LT RR Suction (M-93) F.C.
(See Note 4)
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o 00 01 02 03 04 05 06 / 07 08 09 to 11 12 13 2E12-F003A 18 142-4 C1 2/B GT MO O
!                                                                                                      (M-70)(See Note 4,6,11)
FS,ST Q
M0     O   FS,ST Q       132 RV-19         A R R Outboard suction 2E12-F0048      24    142-I. 87      2/A GT from Suppression Pool LT    RR (M-72)(See Note 4,6,11)
100 A
M0     O   FS,ST Q       132 RV-19         A R R Outboard suction 2E12-F004C    24    142-3    A7      2/A GT from Suppression Pool LT    RR (M-71)(See Note 4,6,11)
RR Heat Exchanger Outlet Stop.
j 2E12-F0038 18 142-4 C8 2/B GT M0 O
FS,ST Q
100 A
R R Heat Exchanger Outlet Stop.
2El?-F004A 24 142-1 A7 2/A GT MO O
FS,ST Q
132 RV-19 A
RR Oatboard suction from Suppression Pool LT RR (M-70)(See Note 4,6,11) 2E12-F0048 24 142-I.
87 2/A GT M0 O
FS,ST Q
132 RV-19 A
R R Outboard suction LT RR from Suppression Pool (M-72)(See Note 4,6,11) 2E12-F004C 24 142-3 A7 2/A GT M0 O
FS,ST Q
132 RV-19 A
R R Outboard suction LT RR from Suppression Pool (M-71)(See Note 4,6,11)
(
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2/C       SP     C     RV   RR                         A RR Shutdown suction lx2  142-3    C5            RV 2E12-F005                                                                                          cooling Suction il1R Relief (See Note 2,6,4,8)
2E12-F005 lx2 142-3 C5 2/C RV SP C
FS,ST          180                A  Pump Ssction Stop From f   2E12-F0064     18   142-1     A7     2/B GT   MO     C           Q Slust:10wn Cooling FS,Si          180                A  Rsmp Section Stop from 2E12-F0060       18   142-2     in     2/B GT   M0     C           Q Shot:10wn Coolliul
RV RR A
RR Shutdown suction cooling Suction il1R Relief (See Note 2,6,4,8) f 2E12-F0064 18 142-1 A7 2/B GT MO C
FS,ST Q
180 A
Pump Ssction Stop From Slust:10wn Cooling 2E12-F0060 18 142-2 in 2/B GT M0 C
FS,Si Q
180 A
Rsmp Section Stop from Shot:10wn Coolliul


O                                                                                               O                                                 O INSERVICE TESTING PLAN               system RH-Residual Heat Removal
O O
      @ CommonwealthEdison tasaite county Nuclear Station Unit 2 VALVES Page 2   of     j j.
O
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@ CommonwealthEdison INSERVICE TESTING PLAN system RH-Residual Heat Removal tasaite county Nuclear Station Unit 2 Page 2
g3 40        5-           e.4 00                                                   01     02   03   04   05   06   07     08     09     10     11         12             13 2E12-F008                                       20               142-3 D6   1/A   GT M0   C   FS,ST   CS     41   RV-04       A   RHR Shutdown Cooling LT     RR           RV-19             Pump 2A Suction HDR Outboard Isolation (ft-7)(See Note 1,5,4) 2E12-F009                                       20               142-3 D7   1/A   GT M0   C   FS,ST   CS     41   RV-04       A   RHR Shutdown Cooling LT     RR           RV-19             HDR Inboard Isolation PIT     RR                             (ll-7)(See Note 1,5,4) 2E12-F0llA                                     4               142-4 A3   2/A   GT M0   C   FS.ST   Q       22   RV-19       A   RHR Heat Exchanger LT     RR                             Steam Condensing Stop to Supp. Chamber (See Note 4,8,6) 2El2-F0llB                                     4                 142-4 A6   2/A   GT M0   C   FS,ST   Q       22   RV-19       A   RHR Heat Exchanger LT     RR                             Steam Condensino Stop to Supp. Chamber (See Note 4,8,6) 2E12-F016A                                     16               142-1 E5   2/A   GT f10   C   FS.ST   Q       88   RV-19       A   RHR Containment Spray LT     RR                             Upstream isolation (ft-18) (See Note 4) 2E12-F016B                                     16               142-2 F5   2/A   GT M0   C   FS,ST   Q       08   PV-19       A   RHR Containment Spray LT     RR                             Upstream isolation (M-19) (See Note 4)
of j j.
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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E12-F008 20 142-3 D6 1/A GT M0 C
FS,ST CS 41 RV-04 A
RHR Shutdown Cooling LT RR RV-19 Pump 2A Suction HDR Outboard Isolation (ft-7)(See Note 1,5,4) 2E12-F009 20 142-3 D7 1/A GT M0 C
FS,ST CS 41 RV-04 A
RHR Shutdown Cooling LT RR RV-19 HDR Inboard Isolation PIT RR (ll-7)(See Note 1,5,4) 2E12-F0llA 4
142-4 A3 2/A GT M0 C
FS.ST Q
22 RV-19 A
RHR Heat Exchanger LT RR Steam Condensing Stop to Supp. Chamber (See Note 4,8,6) 2El2-F0llB 4
142-4 A6 2/A GT M0 C
FS,ST Q
22 RV-19 A
RHR Heat Exchanger LT RR Steam Condensino Stop to Supp. Chamber (See Note 4,8,6) 2E12-F016A 16 142-1 E5 2/A GT f10 C
FS.ST Q
88 RV-19 A
RHR Containment Spray LT RR Upstream isolation (ft-18) (See Note 4) 2E12-F016B 16 142-2 F5 2/A GT M0 C
FS,ST Q
08 PV-19 A
RHR Containment Spray LT RR Upstream isolation (M-19) (See Note 4)
N CE 72-It90 1
N CE 72-It90 1


O                                                                                                               O                                           O INSERVICE TESTING PLAN                m RH-Residu     Heat Remvoal Unit 2
O O
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O m RH-Residu Heat Remvoal INSERVICE TESTING PLAN
4 O             4
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                                                          #                              9                      oO  '
aS Coun y Nu a la Unit 2 l
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00                                               01   02           03                 04   05   06   07 GT   M0   C   FS,ST   Q     88   RV-19     A H Containment Spray             ,
d C
2E12-F017A                                        16    142 2 E7                          2/A                                                    Downstream Isolation LT       RR (M-18)(See iiote 4,6)
A-O 9
M0   C   FS,ST   Q     88   RV-19     A fHt Containment Spray 2E12-F0178                                          16    142-2 F6                          2/A  GT LT
o c3' 00 01 02 03 04 05 06 07 08 09 to If 12 13 d
* RR                        Downstream Isolation (M-19) (See flote 4,6) 2/C                  RV      RR                    A  H Pump A Discharge
2E12-F017A 16 142 2 E7 2/A GT M0 C
:                  2E12-F025A                                         lx2   142-1   E3                             RV   SP   C Header Rellef (M-85)
FS,ST Q
'                                                                                                                                                                        (See flote 2,4,6,8) lx2   142-2                             2/C RV   SP   C   RV       RR                     A iHt Pop B Discharge 2E12-F025B                                                        C5 1
88 RV-19 A
Header Reller (M-86) i i
H Containment Spray Downstream Isolation LT RR (M-18)(See iiote 4,6) 2E12-F0178 16 142-2 F6 2/A GT M0 C
(See Note 2,4,6,8) 2/C             C   RV       RR                     A fMt Pmp C Discharge l                2E12-F025C                                          lx2  142-3 C2                                RV  SP Header Relief (M-87)
FS,ST Q
(See Note 2,4,6,8) 142-4                             2/B       M0   C   FS,ST   Q     40               A INR Heat Exchanger l                  2E12-F026A                                          4            B4                              GT Steam Condensing Outlet
88 RV-19 A
'                                                                                                                                                                        Stop to RCIC Pinnp Suctton I
fHt Containment Spray Downstream Isolation RR LT (M-19) (See flote 4,6) 2E12-F025A lx2 142-1 E3 2/C RV SP C
RV RR A
H Pump A Discharge Header Rellef (M-85)
(See flote 2,4,6,8) 1 2E12-F025B lx2 142-2 C5 2/C RV SP C
RV RR A
iHt Pop B Discharge Header Reller (M-86) i (See Note 2,4,6,8) i l
2E12-F025C lx2 142-3 C2 2/C RV SP C
RV RR A
fMt Pmp C Discharge Header Relief (M-87)
(See Note 2,4,6,8) l l
2E12-F026A 4
142-4 B4 2/B GT M0 C
FS,ST Q
40 A
INR Heat Exchanger Steam Condensing Outlet Stop to RCIC Pinnp Suctton I


O                                                         O                                                                                       O.
O O
INSERVICE TESTING PLAN             gstem RH-Residual Heat Removal La a e Coun y Nuct a Sta l Unit 2 f                    90      oo e,>  t    48            c*,     k                   .O                                                 p 00         01     02     03     04     05   06   07     06   09     10     11       12                                                   13 2E12-F026B       4     142-4   B6     2/B   GT   M0   C   FS,ST Q     40                 A   RHR Heat Exchanger Steam Condensing Outlet Stop to RCIC Pump Suction 2E12-F027A       4     142-1   CS     2/A   GT   M0   C   FS,ST Q     30   RV-19         A   RHR Suppression Chamber LT     RP                           Spray Isolation (M-73)
O.
(See Note 4,6,8) 2E12-F0278       4   142-2   C4     2/A   GT   M0   C   FS,ST Q     30   RV-19         A   RHR Suppression Chamber LT     RR                           Spray isolation (M-74)
INSERVICE TESTING PLAN gstem RH-Residual Heat Removal La a e Coun y Nuct a Sta l Unit 2 8
(See Note 4,6,8) 2E12-F030         1x2 142-2     B4     2/C   RV   SP   C   RV     RR                       A   RHR System Drain Header Relief (ft-91) (See Note 2,4,6,8) t 2E12-F031A         18   142-1   A4     2/C   CV   -
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C    E     Q                         A   RHR Pump A Discharge Chk 2E12-F0318         18   142-2   C3     2/C   CV   -
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C    E     O                         A   RHR Pump B Discharge Chk 2E12-F031 C       18   142-3   B4     2/C   CV   -
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C    E     O                         A   RHR Pump C Discharge Chk 2E12-F041A         12   142-1   07   '/AC   flSC A0   C   E     CS         RV-35         A   RHR LPCI Testable Chk PIT   RR         RV-19             Inboard sten (if-13)
0 f
LT     RR                           (See Note 1,5,7)
9 o
e,>
t 4
o 00 01 02 03 04 05 06 07 06 09 10 11 12 13 2E12-F026B 4
142-4 B6 2/B GT M0 C
FS,ST Q
40 A
RHR Heat Exchanger Steam Condensing Outlet Stop to RCIC Pump Suction 2E12-F027A 4
142-1 CS 2/A GT M0 C
FS,ST Q
30 RV-19 A
RHR Suppression Chamber LT RP Spray Isolation (M-73)
(See Note 4,6,8) 2E12-F0278 4
142-2 C4 2/A GT M0 C
FS,ST Q
30 RV-19 A
RHR Suppression Chamber LT RR Spray isolation (M-74)
(See Note 4,6,8) 2E12-F030 1x2 142-2 B4 2/C RV SP C
RV RR A
RHR System Drain Header Relief (ft-91) (See Note 2,4,6,8) t 2E12-F031A 18 142-1 A4 2/C CV C
E Q
A RHR Pump A Discharge Chk 2E12-F0318 18 142-2 C3 2/C CV C
E O
A RHR Pump B Discharge Chk 2E12-F031 C 18 142-3 B4 2/C CV C
E O
A RHR Pump C Discharge Chk 2E12-F041A 12 142-1 07
'/AC flSC A0 C
E CS RV-35 A
RHR LPCI Testable Chk PIT RR RV-19 Inboard sten (if-13)
LT RR (See Note 1,5,7)
GE.TF ftAG
GE.TF ftAG


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                      #                          o 10     11         12               13 07    08      09 00       01   02       03   04 / 05       06              ,
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E       CS           RV-35         A RR LPCI Testable O*
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NSC    A0    C                                              Inboard Stop (M-14) 2E12-F0410    12    142-2 E7      1/AC PIT      RR          RV-19 LT      RR (See Note 1,5,7)
O s.
AG     C     E       CS           RV-35         A   RR LPCI Testable O*
q.
12    142-3  E7    1/AC  NSC                                                          Inboard Stop (M-12) 2E12-F041C                                                    PII      RR          RV-19 LT       RR                             (See Note 1,5,7)
e,A O
FS,ST   CS           RV-27         A   RR LPCI injection Line 12    142-1 05      1/A    GT    MO    C                                              Outboard Stop (M-13) 2E 12-F042A                                                    LT      RR    20    RV-19 (See Note 1.5,4)
e,''
C    FS,ST   CS   20     RV-27         A   RR LPCI injection Line   l 1/A    GT    M0                                                    Outboard stop (M-14) 2E12-F0428  12    142-2 E6                                          RR          RV-19 LT (See hote 1,5,4)
s 9
C      FS,ST   CS   20     FN-27           A RR I.PCI Injection Line 1/A    GT    M0                                                    Outboard Stop (M-12) 2E12-F042C    12    142-3 E6                                          RR          RV-19 LT (See Note 1,5,4)
o 06 07 08 09 10 11 12 13 00 01 02 03 04 / 05 2E12-F0410 12 142-2 E7 1/AC NSC A0 C
Q                          A  RR Pump Miniman 2/C    CV    -      C    E 2E12-F046A   8       142-1   BS                                                                         Byrnss Check Q                          A  FDIR Pirnp Mininan Flow CV           C     E 2E12-F0460   8     142-2   C2   2/C           -
E CS RV-35 A
Hypiss chect<
RR LPCI Testable O*
PIT RR RV-19 Inboard Stop (M-14)
(See Note 1,5,7)
LT RR 2E12-F041C 12 142-3 E7 1/AC NSC AG C
E CS RV-35 A
RR LPCI Testable O*
PII RR RV-19 Inboard Stop (M-12)
LT RR (See Note 1,5,7) 2E 12-F042A 12 142-1 05 1/A GT MO C
FS,ST CS RV-27 A
RR LPCI injection Line LT RR 20 RV-19 Outboard Stop (M-13)
(See Note 1.5,4) 2E12-F0428 12 142-2 E6 1/A GT M0 C
FS,ST CS 20 RV-27 A
RR LPCI injection Line l
LT RR RV-19 Outboard stop (M-14)
(See hote 1,5,4) 2E12-F042C 12 142-3 E6 1/A GT M0 C
FS,ST CS 20 FN-27 A
RR I.PCI Injection Line LT RR RV-19 Outboard Stop (M-12)
(See Note 1,5,4) 2E12-F046A 8
142-1 BS 2/C CV C
E Q
A RR Pump Miniman Byrnss Check 2E12-F0460 8
142-2 C2 2/C CV C
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LaSaue County Nuclear Station Unit 2                       VR ES f              # / /,/                        C    f      *'#                                                               ,#     p# ,$                l              j#
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08                                                                09    10    11          12/              13 00         01       02       03     04   05   06   07                                                                                                                             l 2/C             C     E                                                     g                                         A H Pump Minista Flow 2E12-F046C      8      142-3    B3            CV  -
(,
Bypass Check 142-4     E4       2/B   GT   MG   0     FS,ST                                                 Q                   180                 A H Heat Exchanger         l 2El?-F047A      18 Inlet Stop              ,
of
142-4     ES       2/B   GT   MO   O     FS.ST                                                   Q                 180                 A H Heat Exchanger 2E12-F0478      18 Inlet Stop              j 142-4 01           2/B   CB   MO   0     rS,ST                                                 Q                   270                 A H Heat Exctanger 2E12-F0484      18 Bypass Stop 142-4 08           2/B   CB   M0   O     FS,ST                                                   Q                 270                 A R m Heat Exchanger       l 2E12-F0488      18 Bypass Stop 2E12-F049A     3       142-4     C1       2/B   GT   M0   C     FS,ST                                                   Q                 30                   A H Heat Exchanger Blowdown Upstream Isolation to RB EDT 2E12-F0498     }       142-4 C8           2/B   GT   M0   C     FS,ST                                                   Q                 30                   A Upstream isolation to RB EDI 142-1     07             t4T A0     0   E                                                       CS                     RV 04           A Rm Stutdown Cooling 2E12-F050A      12                          1/AC LT                                                             RR             RV-19               Ter. table theck (M-ti)
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C f 00 01 02 03 04 05 06 07 08 09 10 11 12/
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A H Pump Minista Flow Bypass Check 2El?-F047A 18 142-4 E4 2/B GT MG 0
FS,ST Q
180 A
H Heat Exchanger l
Inlet Stop 2E12-F0478 18 142-4 ES 2/B GT MO O
FS.ST Q
180 A
H Heat Exchanger Inlet Stop j
2E12-F0484 18 142-4 01 2/B CB MO 0
rS,ST Q
270 A
H Heat Exctanger Bypass Stop 2E12-F0488 18 142-4 08 2/B CB M0 O
FS,ST Q
270 A
R m Heat Exchanger l
Bypass Stop 2E12-F049A 3
142-4 C1 2/B GT M0 C
FS,ST Q
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}
142-4 C8 2/B GT M0 C
FS,ST Q
30 A
Upstream isolation to RB EDI 2E12-F050A 12 142-1 07 1/AC t4T A0 0
E CS RV 04 A
Rm Stutdown Cooling LT RR RV-19 Ter. table theck (M-ti)
(See Note 1,S,7)
(See Note 1,S,7)


O                                                         O La a e C un y Nuclea Sta i Unit 2                                                             oge                                                                             et 9
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02     03     04   05 06   07   08       09
00 01 02 03 04 05 06 07 08 09 to 11 12 13 2E12-F050B 12 142-2 D7 1/AC NSC A0 0
                                                                                                              ,Q'//
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to                 11                                                           12                                 13
RHR Shutdown Cooling LT P.R RV-19 Testable Chk (M-9) (See Note 1,5,7) 2E12-F052A 10 142-4 C4 2/B GB M0 C
                                                                                                                                                                                                                                        /
FS.ST 0
2E12-F050B     12     142-2   D7   1/AC NSC   A0 0   E       CS                           RY-04                                                         A                         RHR Shutdown Cooling LT     P.R                         RV-19                                                                                   Testable Chk (M-9) (See Note 1,5,7) 2E12-F052A     10     142-4   C4   2/B   GB   M0 C   FS.ST   0         300                                                                             A                       RHR Heat Exchanger Steam inlet Stop l
300 A
2E12-F0528     10     142-4   C5   2/B   GB   M0 C   FS,ST   Q         300                                                                               A                       RHR Heat Exchanger Steam Inlet Stop 2E12-F053A     12     142-1   05   1/A   GB   M0 C   FS,ST   CS         29               RV-04                                                           A                       RHR Shutdown Cooling LT     RR                           RV-19                                                                                   Discharge Isolation (M-8) (See Note 1,5,4) 2E12-F053B     12     142-2   D6   1/A   GB   P10 C   FS,ST   CS         29               RV-04                                                           A                       RHR Shutdown Cooling LT     RR                           RV-19                                                                                   Discharge Isolation (M-9) (See Note 1,5,4) 2E12-F055A     4xG   142-4   D3   2/C   RV   SP C   RV     RR                                                                                           A                     RHR Heat Exchanger Steam Inlet Header Relief (M-88) (See Note 2,4,6,3) 2E12-F073A     .75   142-4   E3   2/A   GB   MO C   LT     RR                           RV-19                                                             P                     RHR Heat Exchancer Vent (See Note 4.3,6) 2E12-F073B     .75   142-4   E5   2/A   GB   M0 C   LT     RR                           RV-19                                                             P                     RHR Heat Exchanaer Vent (See Note 4,8,6)
RHR Heat Exchanger Steam inlet Stop l
2E12-F0528 10 142-4 C5 2/B GB M0 C
FS,ST Q
300 A
RHR Heat Exchanger Steam Inlet Stop 2E12-F053A 12 142-1 05 1/A GB M0 C
FS,ST CS 29 RV-04 A
RHR Shutdown Cooling LT RR RV-19 Discharge Isolation (M-8) (See Note 1,5,4) 2E12-F053B 12 142-2 D6 1/A GB P10 C
FS,ST CS 29 RV-04 A
RHR Shutdown Cooling LT RR RV-19 Discharge Isolation (M-9) (See Note 1,5,4) 2E12-F055A 4xG 142-4 D3 2/C RV SP C
RV RR A
RHR Heat Exchanger Steam Inlet Header Relief (M-88) (See Note 2,4,6,3) 2E12-F073A
.75 142-4 E3 2/A GB MO C
LT RR RV-19 P
RHR Heat Exchancer Vent (See Note 4.3,6) 2E12-F073B
.75 142-4 E5 2/A GB M0 C
LT RR RV-19 P
RHR Heat Exchanaer Vent (See Note 4,8,6)


O                                                                                                                               O                                               O Commonwealth Edison                                                                                     INSERVICE TESTING PLAN                     sy iem RH-Residual Heat Removal O LaSalle County Nuclear Stationg Unit 2                                                                                                                          Page g     of   jj 4Y                                                                                   9       O   e,   4V           4   y                                     A-O                                            .g.
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00         01                                         02                                 03   04     05   06         07     08   09   10     11         12             13 2E12-F055B       4x6             142-4                                                           D5   2/C   RV     SP         C     RV     RR                       A   RHR Heat Exchanger Steam Inlet Header Relief
O O LaSalle County Nuclear Station Unit 2 Commonwealth Edison INSERVICE TESTING PLAN sy iem RH-Residual Heat Removal Page g of jj g
(!!-88) (See Note 2,4,6, 8) 2E12-F087A       10             142-4                                                           C4   2/B   GB     M0         C     FS.ST       300 Q                        A   RHR Heat Exchanger Steam inlet PCV Bypass Stop 2E12-F0878       10             142-4                                                           C5 2/B     GB   M0         C     FS ST       300 Q                        A RHR Heat Exchanger Steam Inlet PCV Bypass Stop 2E12-F088A       lx2           142-1                                                           A6   2/C   RV     -
4Y 9
C. RV     RR                       A   RHR Pump Suction HDR Relief (See Note 2,4,8) 2E12-F088B       lx2           142-2                                                           B5   2/C   RV     -
O e,
C    RV     RR                       A   RHR Pump Suction HOR Relief (See Note 2,4,8) 2E12-F088C       lx2             142-3                                                           B6   2/C   RV     -
4V 4
C    RV     RR                       A   RHR Pump Suction HDR Relief (See Note 2,4,8, 6) 2E12-F311 A     .75           142-4                                                           D2   2/C   RV     SP         C     RV     RR                       A   RHR Heat Exchanger Shell x1                                                                                                                                                       Side Relief (M-88, M89)
y
(See Note 2,4,6,8) 2E12-F3118       .75           142-4                                                             06   2/C   RV     SP       C       RV     RR                       A   RHR Heat Exchanger Shell x1                                                                                                                                                       Side Relief (M-88, M89)
.g.
A-O 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E12-F055B 4x6 142-4 D5 2/C RV SP C
RV RR A
RHR Heat Exchanger Steam Inlet Header Relief
(!!-88) (See Note 2,4,6, 8) 2E12-F087A 10 142-4 C4 2/B GB M0 C
FS.ST Q
300 A
RHR Heat Exchanger Steam inlet PCV Bypass Stop 2E12-F0878 10 142-4 C5 2/B GB M0 C
FS ST Q
300 A
RHR Heat Exchanger Steam Inlet PCV Bypass Stop 2E12-F088A lx2 142-1 A6 2/C RV C.
RV RR A
RHR Pump Suction HDR Relief (See Note 2,4,8) 2E12-F088B lx2 142-2 B5 2/C RV C
RV RR A
RHR Pump Suction HOR Relief (See Note 2,4,8) 2E12-F088C lx2 142-3 B6 2/C RV C
RV RR A
RHR Pump Suction HDR Relief (See Note 2,4,8, 6) 2E12-F311 A
.75 142-4 D2 2/C RV SP C
RV RR A
RHR Heat Exchanger Shell x1 Side Relief (M-88, M89)
(See Note 2,4,6,8) 2E12-F3118
.75 142-4 06 2/C RV SP C
RV RR A
RHR Heat Exchanger Shell x1 Side Relief (M-88, M89)
(See Note 2,4,6,8)
(See Note 2,4,6,8)
GE-T2 t I80
GE-T2 t I80


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O LaSalk County Nuckar Station Unit 2 Commonwealth Edison INSERVICE TESTING PLAN system RH-Residual Heat Removal 9
4Y               h     00        sY     A   y           44    -s.         $          g-h 00  [o1     02     03   G4     05   os   or     os     os     to       11         12               13 2E12-F312A     1.5 142-1 D2   2/B   GB     M0   C   FS.ST   Q     45                   A   RHR Heat Exchanger to H2 Recombiner #1 2E12-F312B     1.5 142-2 E2   2/B   GB     M0   C   FS,ST   Q     45                   A   RHR Heat Exchanger to H2 Recombiner #2 2E12-F064A     4   142-1 B5   2/A   GT   MO     0   FS.ST   Q     22     RV-19         A   RHR Pump 2A Main Flcw LT       RR                               Bypass (See Note 4,6,8) 2E12-F0648     4   142-2 C3   2/A   GT   M0     O   FS,ST   Q     22     RV,19         A   RHR Pump 2B Main Flow LT       RR                               Bypass (See Note 4,6,8) 2E12-F064C     4   142-3 B4   2/A   GT   MO     0   FS,ST   Q     22     RV-19         A   RHR Pump 2C Main Flow LT       RR                               Bypass (See Note 4,6,8) 2E12-F084A     .75 142-1 83   2/C   CV   -
II VALVES
C    E       Q                           A   from LPCS Water leg Pump to RHR 2A Discharge 2E12-F0848     .75 142-4 E5   2/C   CV   -
/
C    E       Q                           A   From RHR Water Leg Pump to RilR 2B Discharge 2E12-F084C     .75 142-3 A7   2/C   CV   -
4Y h
C    E       Q                           A   From RHR Water Leg Pump to RilR 2C Discharge 2E12-F068A     20   134-2 B2   3/B   GT   M0     C   FS.ST   Q     200                   A   RilR lleat Exchanger Service Water Outlet Stop C E-72 1180
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[o1 00 02 03 G4 05 os or os os to 11 12 13 2E12-F312A 1.5 142-1 D2 2/B GB M0 C
FS.ST Q
45 A
RHR Heat Exchanger to H2 Recombiner #1 2E12-F312B 1.5 142-2 E2 2/B GB M0 C
FS,ST Q
45 A
RHR Heat Exchanger to H2 Recombiner #2 2E12-F064A 4
142-1 B5 2/A GT MO 0
FS.ST Q
22 RV-19 A
RHR Pump 2A Main Flcw LT RR Bypass (See Note 4,6,8) 2E12-F0648 4
142-2 C3 2/A GT M0 O
FS,ST Q
22 RV,19 A
RHR Pump 2B Main Flow LT RR Bypass (See Note 4,6,8) 2E12-F064C 4
142-3 B4 2/A GT MO 0
FS,ST Q
22 RV-19 A
RHR Pump 2C Main Flow LT RR Bypass (See Note 4,6,8) 2E12-F084A
.75 142-1 83 2/C CV C
E Q
A from LPCS Water leg Pump to RHR 2A Discharge 2E12-F0848
.75 142-4 E5 2/C CV C
E Q
A From RHR Water Leg Pump to RilR 2B Discharge 2E12-F084C
.75 142-3 A7 2/C CV C
E Q
A From RHR Water Leg Pump to RilR 2C Discharge 2E12-F068A 20 134-2 B2 3/B GT M0 C
FS.ST Q
200 A
RilR lleat Exchanger Service Water Outlet Stop C E-72 1180 1


O                                                   O                                               O Commonwealth Edison                                                    syas m RH-Residoal Heat Remtval O t.aSalle County Nuclear                             Stauon VALVES Unit 2 INSERVICE TESTINO PLAN               Pep   10 m       11           ,
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O O t.aSalle County Nuclear Stauon Unit 2 Commonwealth Edison INSERVICE TESTINO PLAN syas m RH-Residoal Heat Remtval Pep 10 m 11 VALVES k
02   03   04     05   06   07     08   09     10   11       12             13 00      01 2E12-F0688   20   134-1   F2 3/B   GT     M0   C     FS,ST 0     200                 A RHR Heat Exchanger Service Water Outlet Stop 2E12-F331A   16   134-2   B6 3/C   NSC     -
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C    E     O                         A RHR Service Water Pump 2A Discharge Check 2E12-F331B   16   134-2   C6 3/C   f4SC   -
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C    E     Q                         A RHR Service Water Pump 2B Discharge Check 2E12-F331C   16   134-1   E6 3/C   ilSC   -
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C    E     Q                         A RHR Service Water Pump 2C Discharge Check 2E12-F3310   16   134-1   F6 3/C   f1SC   -
0*
C    E    Q A  RHR Service Water Pump 2D Discharge Check 2E12-F336A     4   134-2   A5 3/B   GT     M0   C     FS   0           RV-01         A RHR Service Water Pump Strainer 2A Backwash Outlet Stop 2E 12-F336B   4   134-1 .E5 3/B   GT     f10 C     FS   Q           RV-01         A RHR Service Water Pump Strainer 2B Backwash Outlet Stop 2E 12-F313A   3x4 137-3   C4 2/C   RV     -
A 0
C    RV   RR                         A RHR Heat Exchanger Relief (See flote 2)
4 4
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c, 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E12-F0688 20 134-1 F2 3/B GT M0 C
FS,ST 0
200 A
RHR Heat Exchanger Service Water Outlet Stop 2E12-F331A 16 134-2 B6 3/C NSC C
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A RHR Service Water Pump 2A Discharge Check 2E12-F331B 16 134-2 C6 3/C f4SC C
E Q
A RHR Service Water Pump 2B Discharge Check C
E Q
A RHR Service Water Pump 2E12-F331C 16 134-1 E6 3/C ilSC 2C Discharge Check C
E Q
A RHR Service Water Pump 2E12-F3310 16 134-1 F6 3/C f1SC 2D Discharge Check 2E12-F336A 4
134-2 A5 3/B GT M0 C
FS 0
RV-01 A
RHR Service Water Pump Strainer 2A Backwash Outlet Stop 2E 12-F336B 4
134-1
.E5 3/B GT f10 C
FS Q
RV-01 A
RHR Service Water Pump Strainer 2B Backwash Outlet Stop 2E 12-F313A 3x4 137-3 C4 2/C RV C
RV RR A
RHR Heat Exchanger Relief (See flote 2)
GE T2 It00
GE T2 It00


O                                                 O                                                   O Commonwealth Edison             INSERVICE TESTING PLAN               systam RH-Residual Heat Removal O LaSalleCountyNuclearStationUnit 2                      VALVES
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                                                                                                "*"*  11 11
O O LaSalleCountyNuclearStationUnit 2 Commonwealth Edison INSERVICE TESTING PLAN systam RH-Residual Heat Removal VALVES 11 11 e*
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4.0                                  e4 00       01   02   03   04     05   06   07     08   09     10   11       12               13 2E12-F313B   3x4 137-3   C3 2/C   RV   -
4.0 4
C    RV     RR                         A   RHR Heat Exchange Relief (See Note 2) 2E12-F023   6   142-1   F6 1/A   GB   M0   C     FS,ST CS     90     RV-04       A   RHR to Head Spray (See LT     RR           RV-19             Note 1,4) 2E12-F024A   18   142-1   02 2/A   GB   M0   C     FS.ST Q     297     RV-19       A   RHR Test Line for LT     RR                             Suporession Pool Cooling (See Note 4,6.S) 2E12-F024B   18   142-2   E2 2/A   GB   M0   C     FS,ST Q     297     RV-19       A   RHR Test Line for LT     RR                             Suppression Pool Cooling 1                                        (See Note 4,6,8) 1 C4.T7-1100
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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E12-F313B 3x4 137-3 C3 2/C RV C
RV RR A
RHR Heat Exchange Relief (See Note 2) 2E12-F023 6
142-1 F6 1/A GB M0 C
FS,ST CS 90 RV-04 A
RHR to Head Spray (See LT RR RV-19 Note 1,4) 2E12-F024A 18 142-1 02 2/A GB M0 C
FS.ST Q
297 RV-19 A
RHR Test Line for LT RR Suporession Pool Cooling (See Note 4,6.S) 2E12-F024B 18 142-2 E2 2/A GB M0 C
FS,ST Q
297 RV-19 A
RHR Test Line for LT RR Suppression Pool Cooling (See Note 4,6,8) 1 1
C4.T7-1100


O                                                                       O                                                                   O
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@ La a eCoun yNuct a INSERVICE                                                   Unit 2              Sta toVALVES  TESTING PLAN             g   RI-Re ctor Core Isolation Coolant 1       4 at                   U         00 c3>     at     A     y           gc*
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40        A-                           44 00             01       02     03     04       05     06   07     08     09     10     11       12               13 2 E51-F010                                             8       147-2 A4       2/B     GT     M0     O     FS,ST   Q     80                 A   Suction from CST Downstream Stop 2 E51-F0ll                                             8       147-2 B3       2/C     CV             C                                           Suction from CST E        Q                        A Downstream Check 2 E51-F008                                             4       147-1 E7       1/A     GT     MO     0     FS ST         20 CS          RV-31       A   Steam Supply Outboard LT       RR           RV-19           Isolation (M-15)
@ La a eCoun yNuct a Sta to INSERVICE TESTING PLAN g
(See Note 1,4) 2 E51-F013                                             6       147-2 C7       1/A     GT     M0     C     FS,ST   CS     15     RV-05       A   Injection Stop (M-29)
RI-Re ctor Core Isolation Coolant Unit 2 VALVES 1
LT       RR           RV-19           (See Note 1,4) 2 E51-F017                                             .75     147-2 82       2/C     RV     SP     C     RV       RR                       A   Pump Suction Relief xl.0 (See Note 2) 2 E51-F018                                               1.5     147-2 F3       2/C     RV     SP           RV       RR x3.0 C                                        A   Turbine tube Oil Cooler Inlet Relief (See Note 2) 2 E51-F019                                             2       147-2 B5       2/A     GB     M0     C     FS.ST   Q       7     RV-19       A   Minimum Flow Bypass LT       RR                           Stop (See Note 4,6,8) 2 E51-F028                                             1.25   147-1 B6       2/C     fl5C   -
4 at U
C    E       Q                         A   Barometric Condenser Vacuum Pump Discharge (ft-81)(See Note 4) 2 E51-F030                                             8   l 147 86       2/C     CV     -
0 c3>
C    PS       Q             RV-36       A   Pump Suction from i                                               I       RR                           Suppression Thamber CE T2 -1180
at A
c*
0 4
0 y
g 4
A-4 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2 E51-F010 8
147-2 A4 2/B GT M0 O
FS,ST Q
80 A
Suction from CST Downstream Stop 2 E51-F0ll 8
147-2 B3 2/C CV C
E Q
A Suction from CST Downstream Check 2 E51-F008 4
147-1 E7 1/A GT MO 0
FS ST CS 20 RV-31 A
Steam Supply Outboard LT RR RV-19 Isolation (M-15)
(See Note 1,4) 2 E51-F013 6
147-2 C7 1/A GT M0 C
FS,ST CS 15 RV-05 A
Injection Stop (M-29)
LT RR RV-19 (See Note 1,4) 2 E51-F017
.75 147-2 82 2/C RV SP C
RV RR A
Pump Suction Relief xl.0 (See Note 2) 2 E51-F018 1.5 147-2 F3 2/C RV SP C
RV RR A
Turbine tube Oil Cooler x3.0 Inlet Relief (See Note 2) 2 E51-F019 2
147-2 B5 2/A GB M0 C
FS.ST Q
7 RV-19 A
Minimum Flow Bypass LT RR Stop (See Note 4,6,8) 2 E51-F028 1.25 147-1 B6 2/C fl5C C
E Q
A Barometric Condenser Vacuum Pump Discharge (ft-81)(See Note 4) 2 E51-F030 8
l 147 86 2/C CV C
PS Q
RV-36 A
Pump Suction from i
I RR Suppression Thamber CE T2 -1180


O                                                                                                     O                                                                               O Commonwealth Edison                                                               INSERVICE TESTING PL AN                   system RI-Reactor Core Isolation Coolant l
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                      @ LaSaile County Nuclear                                                                                    Station y    y g Unit 2              Page                of
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g2     4'       g@                                     A-                   44 00                                     01   02                     03/04       05   06   07     06       09   10       11               12                                   13 2E51-F031                               8           147-2                   B7 2/A   GT     M0   C   FS,ST     Q     44       RV-19             A     Pump Suction from LT       RR                                     Suppression Chamber (See Note 4,6,11) 2E12-F036A                             4x6         147-2                   C6 2/C   RV     SP   C   RV       RR                               A   RCIC Safety Relief Valve Discharge Condensate (M-101) (See Note 2) 2E12-F036B                             4x6         147-2                   B3 2/C   RV     SP   C   RV       RR                               A   RCIC Safety Relief Valve Discharge Condensate (M-92) (See flote 2) 2E51-F040                               10           147-1                   B6 2/C   CV     -
4 e*
C    E         Q                                 A   Turbine Exhaust Check (M-76) (See Note 4) 2E51-F045                             4             147-1                   D5 2/B   GB     M0   C   rS,ST     Q     120                         A   Turbine Exhaust Supply Stop 2E51-F046                             2             147-2                   D3 2/8   GB     f10   C   FS,ST     Q     60                         A   Turbine Lube Oil Cooler Supply Stop 2E51-F047                             2             147-1                   B6 2/C   CV     -
4Y 9
C    E         Q                                 A   RHR Condensate Pump Discharge Check 2E51-F061                               .75         147-2                   A3 2/C   CV     -
oO p>'
C    E         Q                                 A   Water Leg pump Discharge Check GE t 180
at A
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A-4 c
y 00 01 02 03/04 05 06 07 06 09 10 11 12 13 2E51-F031 8
147-2 B7 2/A GT M0 C
FS,ST Q
44 RV-19 A
Pump Suction from LT RR Suppression Chamber (See Note 4,6,11) 2E12-F036A 4x6 147-2 C6 2/C RV SP C
RV RR A
RCIC Safety Relief Valve Discharge Condensate (M-101) (See Note 2) 2E12-F036B 4x6 147-2 B3 2/C RV SP C
RV RR A
RCIC Safety Relief Valve Discharge Condensate (M-92) (See flote 2) 2E51-F040 10 147-1 B6 2/C CV C
E Q
A Turbine Exhaust Check (M-76) (See Note 4) 2E51-F045 4
147-1 D5 2/B GB M0 C
rS,ST Q
120 A
Turbine Exhaust Supply Stop 2E51-F046 2
147-2 D3 2/8 GB f10 C
FS,ST Q
60 A
Turbine Lube Oil Cooler Supply Stop 2E51-F047 2
147-1 B6 2/C CV C
E Q
A RHR Condensate Pump Discharge Check 2E51-F061
.75 147-2 A3 2/C CV C
E Q
A Water Leg pump Discharge Check GE t 180


O                                                                                               O                                                                                                                                   O syaw RI-Reactor Core Isolation Coolant O La a ecoun yNuci                                                         Unit 2    a Sta       l VALVES INSERVICE TESTING     PLAN Page                           3                                         of                     4
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                                                                                                                                                              /
O O La a ecoun yNuci a Sta l INSERVICE TESTING PLAN syaw RI-Reactor Core Isolation Coolant Unit 2 Page 3
                                                                                                                          #'                                                                                                                                          O 4Y                                                         9     oO          4     A   yd                    ''                                                                                                    -
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00       01                                   02               03   04     05   06   07   08     09     10       11                                           12                                                       13 2E51-F063   10                                 147-1               E8 1/A     GT     M0 O   FS ST   CS     15     RV-31                                           A                             Steam Supply Inboard LT     RR             RV-19                                                                           Isolation (M-15)
VALVES
PIT     RR                                                                                             (See Note 1,4,6) 2E51-F064   10                                 147-1               E7 1/A     GT     M0 C   FS.ST   CS     15     RV-15                                           A                             Steam Supply Outboard LT     RR             RV-19                                                                           Isolation (To RHR)
/
(M-15) (See Note 1,4) 2E51-F065   6                                 147-2               C7 1/C     CV     A0 C   E       CS             RV-19                                           A                             RCIC Injection Outboard PIT     RR             RV-35                                                                         Testable Check (M-29)
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LT     RR                                                                                               (See Note 5,7) 2E51-F066   6                                 147-2               CB 1/C     CV     A0 C   E       CS             RV-19                                           A                             RCIC Injection Inboard PIT     RR             RV-35                                                                           Testable Check (M-29)
4Y 9
LT     RR                                                                                               (See Note 5,7) 2E51-F068   10                                 147-1               B7 2/A     GT     MO 0   FS,ST   Q       55     RV-19                                             A                             Turbine Exhaust Isolatim LT     RR                                                                                               (M-76) (See Note 4,6)
o 4
                                    '2E51-F069     1.25 147-1                                             B7 2/A     GB     M0 O   FS,ST   Q       20.6   RV-19                                           A                             Barometric Condenser LT     RR                                                                                               Vacuum Pump Discharge Stop (M-81)
A d
(See Note 4,6) 2 E51-F076   1                                 147-1                 E8 1/A     GB     M0 C   FS,ST   Q       15     RV-19                                             A                             Steam Supply Inboard LT     RR                                                                                               lsolation Valve Wann-Up PIT     RR                                                                                             Bypass (M-15)
y 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E51-F063 10 147-1 E8 1/A GT M0 O
FS ST CS 15 RV-31 A
Steam Supply Inboard LT RR RV-19 Isolation (M-15)
PIT RR (See Note 1,4,6) 2E51-F064 10 147-1 E7 1/A GT M0 C
FS.ST CS 15 RV-15 A
Steam Supply Outboard LT RR RV-19 Isolation (To RHR)
(M-15) (See Note 1,4) 2E51-F065 6
147-2 C7 1/C CV A0 C
E CS RV-19 A
RCIC Injection Outboard PIT RR RV-35 Testable Check (M-29)
LT RR (See Note 5,7) 2E51-F066 6
147-2 CB 1/C CV A0 C
E CS RV-19 A
RCIC Injection Inboard PIT RR RV-35 Testable Check (M-29)
LT RR (See Note 5,7) 2E51-F068 10 147-1 B7 2/A GT MO 0
FS,ST Q
55 RV-19 A
Turbine Exhaust Isolatim LT RR (M-76) (See Note 4,6)
'2E51-F069 1.25 147-1 B7 2/A GB M0 O
FS,ST Q
20.6 RV-19 A
Barometric Condenser LT RR Vacuum Pump Discharge Stop (M-81)
(See Note 4,6) 2 E51-F076 1
147-1 E8 1/A GB M0 C
FS,ST Q
15 RV-19 A
Steam Supply Inboard LT RR lsolation Valve Wann-Up PIT RR Bypass (M-15)
(See Note 4,6)
(See Note 4,6)
GE 72 1180
GE 72 1180


O                                                                   O                                                 O Commonwealth Edison                                                                                                            ,
O O
O tasanecountyNuclearINSERVICE                                        StauonUnit VALVES 2
O O tasanecountyNuclear StauonUnit 2 Commonwealth Edison INSERVICE TESTING PLAN system RI-Reactor Core Isolation Coolant Page 4
TESTING PLAN           system RI-Reactor Core Isolation Coolant Page   4   of   4 4             9   oO  c''           d                  ''                    O a   4   A   p           gcf              g         s-             +
of 4
00                               01   02   03 04   05   06 07   08     09     10     11       12             13 2E51-F080                             2   147-1 C7   2/A GB   M0   0   FS,ST         33   RV-19 Q                        A   RCIC Turbine Exhaust                                           -
VALVES 4
LT     RR                           Vacuum Breaker Inlet Stop (M-101) (See Note 4) 2E51-F086                             2.0 147-1 C7   2/A GB   M0   0   FS,ST   Q     33   RV-19       A   RCIC Turbine Exhaust LT     RR                           Vacuum Breaker Outlet Stop (M-101) (See Note 4,6) 2E51-E091                             1   147-1 D7   1/A GB   M0   C   FS,ST   CS     15   RV-15       A   Warm-Up Bypass (M-15)
9 O
LT     RR           RV-19           (See Note 1,4)
c''
o a
4 A
d cf O
p g
g s-
+
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E51-F080 2
147-1 C7 2/A GB M0 0
FS,ST Q
33 RV-19 A
RCIC Turbine Exhaust LT RR Vacuum Breaker Inlet Stop (M-101) (See Note 4) 2E51-F086 2.0 147-1 C7 2/A GB M0 0
FS,ST Q
33 RV-19 A
RCIC Turbine Exhaust LT RR Vacuum Breaker Outlet Stop (M-101) (See Note 4,6) 2E51-E091 1
147-1 D7 1/A GB M0 C
FS,ST CS 15 RV-15 A
Warm-Up Bypass (M-15)
LT RR RV-19 (See Note 1,4)
GE-T2 -1180
GE-T2 -1180


O                                                                                                     O                                                   O La e C un y Nuct a Sta i Unit 2                                                                                         y
O O
                                                                                                                                          )                                          on 00
O
              /
)
01 mf6%4g//
on La e C un y Nuct a Sta i Unit 2 y
02   03   04     05   06   07     08     09 10     11   12             13
/ mf6%4g//
                                                                                                                                                                            /
/
2833-F019     .75                                         139-2           E6   2/A   GB     A0   0     FS   Q         RV-02   A   Process Sampling LT     RR       RV-19       (See Note 4)
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2833-F019
PIT   RR 2B33-F020     .75                                         139-2           E8   2/A   GB     A0   0   FS     Q         RV-02   A   Process Sampling LT     RR       RV-19       (See Note 4) 2B33-F319A     .75 2139-8                                                       2/AC EFC     -
.75 139-2 E6 2/A GB A0 0
0    E     RR       RV-34   A   See Note 10 LT 2B33-F3198     .75 2139-8                                                       2/AC EFC   -
FS Q
0    E     RR       RV-34   A   See Note 10 LT 2833-F317A   .75                             2139-8                           2/AC EFC   -
RV-02 A
0    E     RR       RV-34   A   See Note 10 LT 2B33-F3178   .75                             2139-8                           2/AC EFC   -
Process Sampling LT RR RV-19 (See Note 4)
0    E     RP,       RV-34   A   See Note 10 LT 2833-F313A   .75                             2139-2                           2/AC EFC   -
PIT RR 2B33-F020
0    E     RR       9V-34   A   See Note 10 LT 2833-F3138   .75                             2139-2                             2/AC EFC   -
.75 139-2 E8 2/A GB A0 0
0    E     RR       RV-34   A   See Note 10 LT 2 833-F313C   .75                           2139-2                             2/AC EFC   -
FS Q
0    F     PR       RV-34   A   See Note 10 LT
RV-02 A
Process Sampling LT RR RV-19 (See Note 4) 2B33-F319A
.75 2139-8 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F3198
.75 2139-8 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2833-F317A
.75 2139-8 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F3178
.75 2139-8 2/AC EFC 0
E RP, RV-34 A
See Note 10 LT 2833-F313A
.75 2139-2 2/AC EFC 0
E RR 9V-34 A
See Note 10 LT 2833-F3138
.75 2139-2 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2 833-F313C
.75 2139-2 2/AC EFC 0
F PR RV-34 A
See Note 10 LT


O                                                   O                                                 O Commonwealth Edison                                                        Syewm RR-Reactor Recirculation O LaSaue County Nuclear                   .
O O
Station INSERVICE TESTING PLAN VALVES Unit 2           "*"  2  #    3
O O LaSaue County Nuclear Station Unit 2 Commonwealth Edison INSERVICE TESTING PLAN Syewm RR-Reactor Recirculation 2
                  #                9#    00 e,)         r$                 c,A   ''
3 VALVES b
Ob      s.O           gh 00       01   02     03   04     05   06   07   08     09 j    10     11       12             13 2B33-F313D     .75 2139-2       2/AC   EFC   -
h 9
0   E       RR             RV-34       A See Note 10 LT 2833-F311A     .75 2139-2       2/AC   EFC   -
0 e,)
0    E       RR             RY-34       A See Note 10 LT 2833-F3118     .75 2139-2       2/AC   EFC   -
r$
0    E       RR             RV-34       A See Note 10 LT 2833-F311C     .75 2139-2       2/AC   EFC   -
c,A O
0    E      RR             RV-34       A See Note 10 LT 2B33-F311D     .75 2139-2       2/AC   EFC   -
s.O g
0            RR            RV-34        A  See Note 10
0 00 01 02 03 04 05 06 07 08 09 10 11 12 13 j
2B33-F313D
.75 2139-2 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 0
E RR RY-34 A
See Note 10 2833-F311A
.75 2139-2 2/AC EFC LT 0
E RR RV-34 A
See Note 10 2833-F3118
.75 2139-2 2/AC EFC LT 0
E RR RV-34 A
See Note 10 2833-F311C
.75 2139-2 2/AC EFC LT RR RV-34 A
See Note 10 2B33-F311D
.75 2139-2 2/AC EFC
{
{
                    .75 2139-3        2/AC  EFC  -
0 0
0    E       RR             RV-31       A See Note 10 2B33-F315A LT
E RR RV-31 A
                    .75 21 39-3       2/AC   EFC   -    0   E       RR             RV-34       A See Note 10 2B33-F3158 LT l
See Note 10 2B33-F315A
2833-F315C     .75 2139-4       2/AC   EFC   -
.75 2139-3 2/AC EFC LT 0
0    E       RR             RV-34       A See Note 10 LT 2B33-F315D     .75 2139-4       2/AC   EFC   -
E RR RV-34 A
0    E       RR             RV-14       A See Note 10 LT 2B33-F301A     .75 139-l   08 2/AC   EFC   -
See Note 10 2B33-F3158
0    E       RR             RV-34       A See Note 10 LT i                                                                                                     f CE- ? 2 - 1180
.75 21 39-3 2/AC EFC LT l
2833-F315C
.75 2139-4 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F315D
.75 2139-4 2/AC EFC 0
E RR RV-14 A
See Note 10 LT 2B33-F301A
.75 139-l 08 2/AC EFC 0
E RR RV-34 A
See Note 10 f
LT i
CE- ? 2 - 1180


O                                                                                           O                                                 O O                                           as eco n yNu I a Sta o Unit 2             INSERVICE TESTING PLAN VALVES sy i.m RR-Reactor Recirculation Ob
O O
                                                      #                  9       O   sh      Y     su   &          sA    4~                  .O         $
O O
00                                         01     02     03     04     05     06   07     08     09   10     11         12             13 2833-F3018                                     .75   139-2   DB   2/AC   EFC     -
as eco n yNu I a Sta o Unit 2 INSERVICE TESTING PLAN sy i.m RR-Reactor Recirculation VALVES A
0    E     RR         RV-34         A   See Note 10 LT 2B33-F307A                                     .75 2139-1         2/AC   EFC   -
4~
0    E       RR         RV-34         A   See Note 10 LT 2833-F307B                                     .75 2139-1         2/AC   EFC     -
b 9
0    E       RR         RV-34         A   See Note 10 LT 2B33-F307C                                     .75   2139-1         2/AC                 0 EFC    -
O h
E       RR         RV-34         A   See Note 10 LT 2833-F3070                                     .75   2139-1         2/AC   EFC   -
Y su s
0    E       RR         RV-34         A   See Note 10 LT 2833-F305A                                     .75   2139-1         2/AC   EFC   -
O
0    E       RR         RV-34         A   See Note 10 LT 2833-F3058                                     .75   2139-1         2/AC   EFC   -
.O s
0    E       RR         RV-34         A   See Note 10 LT 2B33-F305C                                     .75   2139-1         2/AC   EFC   -
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2833-F3018
0    E       RR         RV-34         A   See Note 10 LT 2B33-F305D                                     .75   2139-1         2/AC   LFC   -
.75 139-2 DB 2/AC EFC 0
0    E       RR         RV-34         A   See flote 10 LT GE T2 It80
E RR RV-34 A
See Note 10 LT 2B33-F307A
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2833-F307B
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F307C
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2833-F3070
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2833-F305A
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2833-F3058
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F305C
.75 2139-1 2/AC EFC 0
E RR RV-34 A
See Note 10 LT 2B33-F305D
.75 2139-1 2/AC LFC 0
E RR RV-34 A
See flote 10 LT GE T2 It80


O                                                                                   O                                                                                 O t
O O
Commonwealth Edison                             1NSERV1CE TESTlNG PLAN                                                                   system RT-EACT(R WATER CLEAMP LaSalle County Nuclear Station Unit 2                                                                                                    Pa9e  1    of 2 VALVES 4                       9       O O  ''          A                                                                  p*)                 N          A*
O t
02       03     04     05   06   07                         08                                   09     10     11           12             13 00            01 2G33-F001         6       143-1   E8       1/A   GT   MO   O                 FS,ST         CS                                   30   R/-06             A C.U. Suction Ittoard LT             RR                                         RV-19               Isolation (M-30)
Commonwealth Edison 1NSERV1CE TESTlNG PLAN system RT-EACT(R WATER CLEAMP Pa9e 1
PIT           RR                                                             (See Note 1.4.6) 2G33-F004         6       143-1   E7       1/A   GT   M0   O                 FS,ST         CS                                   30   RV-08             A C.U. Outboerd LT           RR                                         RV-19               Isolation (M-30)
of 2 LaSalle County Nuclear Station Unit 2 VALVES N
PIT           RR                                                             (See Note 1,4) 2G33-F339A         1.5     137s2   E8       3/C   RV   -    C                RV              RR                                                          A  RWCU Hu Peller (See X2.5                                                                                                                                         Note 2).
A*
2 G33-F3398         1.5     137-2 C8         3/C   RV   -    C                 RV             RR                                                         A RWCU Hx Relief (See x2.5'                                                                                                                                       Note 2).
O A
2 G33-F340A         1.5     137-2 E8         3/C   RV   -    C               RV             RR                                                           A RWCU Hz Reller (See x2.5                                                                                                                                         Nr,te 2).
4 9
2 G33-F3408         1.5     137-2 C8         3/C   RV   -    C               RV             RR                                                           A RWCU Hx Relief (See x2.5                                                                                                                                         Mate 2).
O p*)
1 2 G33-F341 A       1.5     137-2   E5       3/C   RV   -
00 01 02 03 04 05 06 07 08 09 10 11 12 13 2G33-F001 6
C                RV             RR                                                           A RWCU Hz Reller (See x2.5                                                                                                                                         Rite 2).
143-1 E8 1/A GT MO O
2 G33-F 341B       1.5     137-2   C5       3/C   RV   -
FS,ST CS 30 R/-06 A
C                RV             RR                                                           A RWCU Hx Rellef (See x2.5                                                                                                                                         Mite 2).
C.U. Suction Ittoard LT RR RV-19 Isolation (M-30)
PIT RR (See Note 1.4.6) 2G33-F004 6
143-1 E7 1/A GT M0 O
FS,ST CS 30 RV-08 A
C.U. Outboerd LT RR RV-19 Isolation (M-30)
PIT RR (See Note 1,4)
C RV RR A
RWCU Hu Peller (See 2G33-F339A 1.5 137s2 E8 3/C RV X2.5 Note 2).
2 G33-F3398 1.5 137-2 C8 3/C RV C
RV RR A
RWCU Hx Relief (See x2.5' Note 2).
2 G33-F340A 1.5 137-2 E8 3/C RV C
RV RR A
RWCU Hz Reller (See x2.5 Nr,te 2).
2 G33-F3408 1.5 137-2 C8 3/C RV C
RV RR A
RWCU Hx Relief (See x2.5 Mate 2).
1 2 G33-F341 A 1.5 137-2 E5 3/C RV C
RV RR A
RWCU Hz Reller (See x2.5 Rite 2).
2 G33-F 341B 1.5 137-2 C5 3/C RV C
RV RR A
RWCU Hx Rellef (See x2.5 Mite 2).
I
I
  ,,, ,,,,,,n
,,,,,,n


INSERVICE TESTING PLAN La e Co n y Nuci a Sta l Unit 2                                         gstem R -Reactor Water Cleanup
INSERVICE TESTING PLAN gstem R -Reactor Water Cleanup La e Co n y Nuci a Sta l Unit 2
                                                      /
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00         01     02     03     04   5 06   07   08   09   10     11         12             13 2G33-F040       4     143-1   F4     2/A GT   M0     0 FS,ST CS   22   RV-08       A     RWCU Isolation LT   RR         RV-19             (See Note 1,4)
/
s o
v o
o 00 01 02 03 04 5
06 07 08 09 10 11 12 13 2G33-F040 4
143-1 F4 2/A GT M0 0
FS,ST CS 22 RV-08 A
RWCU Isolation LT RR RV-19 (See Note 1,4)
GE-T2 1180
GE-T2 1180


O                                                       O                                                                                                             O O           La a e Coun y Nuct a Sta l n Unit 2       INSERVICE TESTING PLAN VALVES system SA-Service Air
O O
                                                                                                                    "*9'   I   '      I at                     9       oO  e*> 4r   su            cf   'S 4.0                                                                        ed 00         01     02       03     04   05   06 07   08   09   10     11       12                                                                 13 2SA042             3     82-05     B7     2/A   GT   M   C LT   RR         RV-19       P   (M-38) (See Note 13)
O O
RV-37 2SA046             3     82-05     B7     2/A   GT   M   C LT   RR         RV-19       P   (M-38) (See Note 13)
La a e Coun y Nuct a Sta l n Unit 2 INSERVICE TESTING PLAN system SA-Service Air
"*9' I
I VALVES u
4.0 d
at 9
O e*>
4r s
cf
'S e
o 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2SA042 3
82-05 B7 2/A GT M
C LT RR RV-19 P
(M-38) (See Note 13)
RV-37 2SA046 3
82-05 B7 2/A GT M
C LT RR RV-19 P
(M-38) (See Note 13)
RV-37 GE-T 2 -1180
RV-37 GE-T 2 -1180


r-                                                                   p N]x O La a eC un yNuct a Sta                         Unit 2        INSERVICE TESTING VALVES PLAN         system SC-Standby Liquid Control
r-p N]x O La a eC un yNuct a Sta INSERVICE TESTING PLAN system SC-Standby Liquid Control Unit 2
                                                                                                                                  "*8' I     '    I
"*8' I
                                                            #            #      00  c,''       s                   cf   '?                   .O                                     $
I VALVES 0
00         01   02 03   04   05   06   07 f    08     09     10   11         12               13 2C41-F001A   :. 145 C2   2/B   PG   M0   C     FS,ST RR     15   RV-13       A   A SBLC Pump Suction Stop (See Note 1) 2C41-F001B   3     145 B2   2/B   PG   M0   C     FS,ST RR     15   RV-13       A   B SBLC Pump Suction Stop (See Note 1) 2C41-F004A   1.5   145 C5   1/A, GT   EX   C     CC     EV           RV-19     A     Pump Injection Squib D                       LT     RR                             Valve (M-34)(See Note 4) 2C41-F004B   1.5   145 B5   1/A, GT   EX   C     FC     EV           RV-19       A   Pump Injection Squib D                       LT     RR                             Valve (M-34)(See Note 4) 2C41-F006   1.5   145 D6   1/C   NSC   -
c,''
C      E     RR           RV-14       A   Outboard Check (M-34) 2C41-F007     1.5   145 D7   1/A, NSC   -
s cf
C      E     RR           RV-14       A   Inboard Check (M-34)
'?
C                       LT     RR           RV-19           (See Note 4) 2C41-F029A   .75   145 D4   2/C   RV   SP   C     RV     RR                       A   Pump Discharge Relief x1                                                                           (See Note 2) 2041-F029B     .75   145 C4   2/C   RV   SP   C     RV     RR                       A   Pump Discharge Relief x1                                                                           (See Note 2) 2C41-F033A     1.5   145 C4   2/C   NSC   -
.O 0
C      E     Q                         A   Pump Discharge Check 2C41-F033B   1.5   145 B4   2/C   NSC   -
00 01 02 03 04 05 06 07 08 09 10 11 12 13 f
C      E     Q                         A   Pump Discharge Check I.
2C41-F001A 145 C2 2/B PG M0 C
FS,ST RR 15 RV-13 A
A SBLC Pump Suction Stop (See Note 1) 2C41-F001B 3
145 B2 2/B PG M0 C
FS,ST RR 15 RV-13 A
B SBLC Pump Suction Stop (See Note 1) 2C41-F004A 1.5 145 C5 1/A, GT EX C
CC EV RV-19 A
Pump Injection Squib D
LT RR Valve (M-34)(See Note 4) 2C41-F004B 1.5 145 B5 1/A, GT EX C
FC EV RV-19 A
Pump Injection Squib D
LT RR Valve (M-34)(See Note 4) 2C41-F006 1.5 145 D6 1/C NSC C
E RR RV-14 A
Outboard Check (M-34) 2C41-F007 1.5 145 D7 1/A, NSC C
E RR RV-14 A
Inboard Check (M-34)
C LT RR RV-19 (See Note 4) 2C41-F029A
.75 145 D4 2/C RV SP C
RV RR A
Pump Discharge Relief x1 (See Note 2) 2041-F029B
.75 145 C4 2/C RV SP C
RV RR A
Pump Discharge Relief x1 (See Note 2) 2C41-F033A 1.5 145 C4 2/C NSC C
E Q
A Pump Discharge Check 2C41-F033B 1.5 145 B4 2/C NSC C
E Q
A Pump Discharge Check I.
GE-T2 1180
GE-T2 1180


O                                                                               O                                                                                                                 O system VP-PRIMRY CCHTAlp6ENT INSERVICE TESTING PL AN                                                                        of          I VENTILATIIN O Commonwcalth Edison LaSalle County Nuclear Station Unit 2                                                                                                         Psee   1
O O
                                              /
O O Commonwcalth Edison INSERVICE TESTING PL AN system VP-PRIMRY CCHTAlp6ENT LaSalle County Nuclear Station Unit 2 Psee 1
f                       &        oo  e, sef'                    ?          sh            gP                              &
of I VENTILATIIN
09                              11        12                                    13 02       03     04       05                 06   07     08                                   to i        00            01 FS,ST                         RR     40               RV-17                 A     Chilled Water Return 8        133      E2      2/A    GT                  MO    O 2VP053A LT                             RR                       RV-19                       (*27) (See Note i.4) 2/A   GT                   M0   C     FS,ST                         RR     40               RV-17                 A     Chilled Water Return 2VP0538          8        133      C2                                                                                                                                    (428) (See Note 1,4)
/
LT                            RR                        RV-19 O     FS,ST                         RR     40                 RV-17               A     Water Supply 2VP063A          8      133      D2      2/A  GT                  MO
ef'
(*25) (See Note 1,4)
?
LT                            RR                        RV-19 FS,ST                         RR       40                 RV-17               A     Water Supply 2VP063B          8      133      82      2/A  GT                  MD    C i                                                                                    LT                             RR                         RV-19                     (64-26) (See Note i 4)
h P
FS,ST                         RR     90                   RV-17               A     Water Supply 2 VPil3A          8      133      02      2/A  EF                  M0    O LT                             RR                           RV-19                     (14-25) (See Note 1.4.6)
f o
PIT                           RR FS ST                          RR       90                  RV-17              A    Water Supply 2 VPil30         8       133       82       2/A   BF                   M0   O
e, s
s g
o i
00 01 02 03 04 05 06 07 08 09 to 11 12 13 2VP053A 8
133 E2 2/A GT MO O
FS,ST RR 40 RV-17 A
Chilled Water Return LT RR RV-19
(*27) (See Note i.4) 2VP0538 8
133 C2 2/A GT M0 C
FS,ST RR 40 RV-17 A
Chilled Water Return LT RR RV-19 (428) (See Note 1,4) 2VP063A 8
133 D2 2/A GT MO O
FS,ST RR 40 RV-17 A
Water Supply LT RR RV-19
(*25) (See Note 1,4) i 2VP063B 8
133 82 2/A GT MD C
FS,ST RR 40 RV-17 A
Water Supply LT RR RV-19 (64-26) (See Note i 4) 2 VPil3A 8
133 02 2/A EF M0 O
FS,ST RR 90 RV-17 A
Water Supply LT RR RV-19 (14-25) (See Note 1.4.6)
PIT RR 2 VPil30 8
133 82 2/A BF M0 O
FS ST RR 90 RV-17 A
Water Supply LT RR RV-19
(*26) (See Note 1,4,6)
(*26) (See Note 1,4,6)
LT                            RR                            RV-19 PIT                           RR 2/A   IF                   MO   O     FS,ST                         RR     90                   RV-17             A   Ch111ed Water Return 2 VPll4A          8      133      E2                                                                                                                                    (427) (See Hote 1,4,6)
PIT RR 2 VPll4A 8
LT                            RR                            RV-19 PIT                           RR C2       2/A   (F                   MO   O     FS,ST                         RR     90                     TN-17               A   Chilled Water Return 2 VPil4B          8      133                                                                                                                      IN-19                 (M-28) (5cc Note 1,4,6)
133 E2 2/A IF MO O
LT                            RR Pli                           RR
FS,ST RR 90 RV-17 A
Ch111ed Water Return LT RR RV-19 (427) (See Hote 1,4,6)
PIT RR 2 VPil4B 8
133 C2 2/A (F
MO O
FS,ST RR 90 TN-17 A
Chilled Water Return LT RR IN-19 (M-28) (5cc Note 1,4,6)
Pli RR


O                                                                   O                                                       O system VQ#RIWWlY C(NTAlt#ENT Commonwealth Edison                               INSERVICE TESTING PLAN                     pag. 1     og 3           m LaSalk County Nuclear StationiUnit 2
O O
                                                                            /
O system VQ#RIWWlY C(NTAlt#ENT Commonwealth Edison INSERVICE TESTING PLAN pag.
* q$
1 og 3 m
O c*'             $                c,A
LaSalk County Nuclear StationiUnit 2
                                                                                                                      ''        O          v 5                      9               o 11        12                13 07    06      09      10 02     03           04   05     06 00          01 130    RV-09         P  Outboerd to Suppression C    FS,ST  CS 2VQO26                         26         138-1 C2       2/A       0F   MD RR               RV-19             chenber Fr. Rx. Bldg.     '
/
LT Inhoard (PCIS)
q$
O v
O c*'
c,A 5
9 o
00 01 02 03 04 05 06 07 06 09 10 11 12 13 2VQO26 26 138-1 C2 2/A 0F MD C
FS,ST CS 130 RV-09 P
Outboerd to Suppression LT RR RV-19 chenber Fr. Rx. Bldg.
Inhoard (PCIS)
Isolation Damper (M-66)
Isolation Damper (M-66)
(See Note 1)
(See Note 1) 2VQ027 26 138-1 C3 2/A BF M0 C
CS        130    RV-09        P    Inlet to Suppression C3         2/A     BF   M0     C     FS,ST                                     Chenher Fr. Rx. Bldg.
FS,ST CS 130 RV-09 P
2VQ027                          26        138-1                                                  RR              RV-19 LT Inboard (PCIS)
Inlet to Suppression LT RR RV-19 Chenher Fr. Rx. Bldg.
Inboard (PCIS)
Isolation Damper (M-66)
Isolation Damper (M-66)
/
/
(See Note 1)
(See Note 1) 2VQ029 26 138-1 02 2/A 0F M0 C
FS,ST CS       130   RV-09         A   Inlet to Drywell Fr 02            2/A    0F    M0    C                                                Rx. Bldg. Outboard 2VQ029                          26        138-1                                                  RR              RV-19 LT                                          Isolation Damper (PCIS)
FS,ST CS 130 RV-09 A
(M-20)fSee Note 1,d) 130    RV-09        A    Inlet to Drywell Fr 2/A         MD     C     FS,ST CS 2VQ030                          26        138-1  03                    BF RR               RV-19             Rx. Bldg. Inboard LT l                                                                                                                                         Isolation Damrer (PCIS)
Inlet to Drywell Fr LT RR RV-19 Rx. Bldg. Outboard Isolation Damper (PCIS)
!                                                                                                                                        (M-20)(See Hote-1.4.6)
(M-20)fSee Note 1,d) 2VQ030 26 138-1 03 2/A BF MD C
CS       130   RV-09         A   Suction Fr Rx. Bldg.
FS,ST CS 130 RV-09 A
2/A  HF    M0    C    FS,ST l  2VQO31                          26      138-1  C1 LT     RR               RV-19               inboard Isolatinn l
Inlet to Drywell Fr LT RR RV-19 Rx. Bldg. Inboard l
Damper (PCIS) (M-67) l (See Note 1)
Isolation Damrer (PCIS)
    $            h *$ h hh'
(M-20)(See Hote-1.4.6) l 2VQO31 26 138-1 C1 2/A HF M0 C
* O                                                                       O                                                     O Commonwealth Edison                                     INSERVICE TESTING PLAN                 sye'em VQ-Primary Containment Purge O tasaii county Nuclear Station Unit 2                                                                            yg(ygg                      f>ege 2   of     3
FS,ST CS 130 RV-09 A
                                                #                                        9    oo    ''  s      5,               c 4,A sh        -
Suction Fr Rx. Bldg.
00                             01   02       03   04     05   06   07   08     09     to     11         12               13 2VQO32                                               2                       138-1   C7   2/A   GB   M0   C   FS.ST   CS       10   RV-09         P   Bypass Suction LT     PR           RV-19             (See Note 1,4,6) 2VQO34                                               26                     138-1   E6   2/A   BF   M0   C   FS.ST   CS     130   RV-09         A   Sitction Fr. Drywell LT     RR           RV-19             Inboard Isolation Damper (PCIS) (M-21)
LT RR RV-19 inboard Isolatinn l
(See Note 1,4,6) 2VQO35                                               2                       138-1   E6   2/A   GB   M0   C   FS,ST   Q         5   RV-19         P   Suction Fr. Drywell LT     RR                               Inboard Isolation Damper Bypass Inboard (ll-21)
Damper (PCIS) (M-67)
(See Note 4,6) 2VQO36                                               26                     138-1   E7   2/A   BF   M0   C   FS,ST   CS     130   RV-09         A   Suction Fr. Drywell LT     RR           RV-19             Outboard Isolation Damper Bypass (M-21)
(See Note 1) l h *$
(See Note 4) 2VQO37                                             26                       138-1   B8   2/B   BF   M0   C   FS,ST   0       90                 A   Prime Cont. Ventilation Secondary Containment Inboard Isolation Damper (PCIS) 2V0038                                             26                       138-1   B7   2/B   BF   tto C   FS,ST   0       90                 A   Prime Cont. Ventilation Secondary Containment Outboard Isolation Damper (PCIS)
h hh'
 
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s 00 01 02 03 04 05 06 07 08 09 to 11 12 13 2VQO32 2
138-1 C7 2/A GB M0 C
FS.ST CS 10 RV-09 P
Bypass Suction LT PR RV-19 (See Note 1,4,6) 2VQO34 26 138-1 E6 2/A BF M0 C
FS.ST CS 130 RV-09 A
Sitction Fr. Drywell LT RR RV-19 Inboard Isolation Damper (PCIS) (M-21)
(See Note 1,4,6) 2VQO35 2
138-1 E6 2/A GB M0 C
FS,ST Q
5 RV-19 P
Suction Fr. Drywell LT RR Inboard Isolation Damper Bypass Inboard (ll-21)
(See Note 4,6) 2VQO36 26 138-1 E7 2/A BF M0 C
FS,ST CS 130 RV-09 A
Suction Fr. Drywell LT RR RV-19 Outboard Isolation Damper Bypass (M-21)
(See Note 4) 2VQO37 26 138-1 B8 2/B BF M0 C
FS,ST 0
90 A
Prime Cont. Ventilation Secondary Containment Inboard Isolation Damper (PCIS) 2V0038 26 138-1 B7 2/B BF tto C
FS,ST 0
90 A
Prime Cont. Ventilation Secondary Containment Outboard Isolation Damper (PCIS)
GE T2 tI80
GE T2 tI80


O                                                             O                                                                                         O a   e Co n y Nu I a Sta l Unit 2         INSERVICE TESTING PLAN                                        VQ-P imary Containment Pruge 00
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                                                %9?:?86,$'// /
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02     03   04       05     os   07       os     os     to /    11                     12                     13 2VQ040       26     138-1   C8     2/A     BF     M0     C     FS,ST         130   RV-09 CS                                      A     Suction from Suppression LT       RR           RV-19                           Chamber Outboard Isolation Damper (PCIS)
to /
(See Note 1,4) 2VQ041       26   138-1   A8     2/B     BF   M0     C     FS,ST           90 Q                                      A     Suction Fr Rx Bldg.
00 01 02 03 04 05 os 07 os os 11 12 13 2VQ040 26 138-1 C8 2/A BF M0 C
Return Air Riser 2VQ068         2     138-1   E7     2/A     GB   ft0     C     FS,ST   Q       5   RV-19                     A     (See Note 4)
FS,ST CS 130 RV-09 A
LT       RR 2VQ047         1.5   138-1   D3   2/A     GB     MO     0     FS ST   Q     23     RV-19                     A     (See Note 4,6)
Suction from Suppression LT RR RV-19 Chamber Outboard Isolation Damper (PCIS)
LT     RR 2VQ048         1.5   138-1   D3   2/A     GB   fiO     O     FS,ST         23     RV-19 Q                                        A   (See Note 4)
(See Note 1,4) 2VQ041 26 138-1 A8 2/B BF M0 C
LT       RR 2VQ050       1.5   138-1   C3     2/A     GB   M0     O     FS,ST   Q     23     RV-19                     A     (See Note 4,6)
FS,ST Q
LT       RR 2VQOSI       1.5   138-1   C3     2/A     GB   f10     0     FS,ST   Q     23     RV-19                   A     (See Note 4)
90 A
LT       RR 2VQ042       8     138-1   02     2/A     BF   M0           FS.ST           90 C              CS            RV-09                           (See Note 1,4)
Suction Fr Rx Bldg.
LT       RR           RV-19 l
Return Air Riser 2VQ068 2
2VQ043         8     138-1   C2     2/A     BF   M0           FS.ST           90 C              CS            RV-09                           (See Note 1.4)
138-1 E7 2/A GB ft0 C
LT       RR           RV-19 GE T2-I t90
FS,ST Q
5 RV-19 A
(See Note 4)
LT RR 2VQ047 1.5 138-1 D3 2/A GB MO 0
FS ST Q
23 RV-19 A
(See Note 4,6)
LT RR 2VQ048 1.5 138-1 D3 2/A GB fiO O
FS,ST Q
23 RV-19 A
(See Note 4)
LT RR 2VQ050 1.5 138-1 C3 2/A GB M0 O
FS,ST Q
23 RV-19 A
(See Note 4,6)
LT RR 2VQOSI 1.5 138-1 C3 2/A GB f10 0
FS,ST Q
23 RV-19 A
(See Note 4)
LT RR 2VQ042 8
138-1 02 2/A BF M0 C
FS.ST CS 90 RV-09 (See Note 1,4)
LT RR RV-19 l
2VQ043 8
138-1 C2 2/A BF M0 C
FS.ST CS 90 RV-09 (See Note 1.4)
LT RR RV-19 GE T2-I t90


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( P)/ LaSalle CountyNuclearStation Unit Commonwealth Edison PUMP2& VALVE TEST 1NG Page   1   of           1
( P)/ LaSalle CountyNuclearStation Unit 2 C
  \d                                                                                         RELIEF REQUESTS IIi                                                                                                 ASME 33                                                   PUMP OR   "O                               SECTION XI VALVE NO.               FUNCTION       TEST REQUIREMENT       BASIS FOR RELIEF       ALTERNATIVE IESI 00                                                 01       02             03                   04                   05                         06 RV-01                                             2DG-Oli     3/B   Strainer Backwash   Full stroke and   These valves open in       Perform a full stroke Valves             stroke time       response to an autoback-   exercise once per quarterly         wash logic signal produced quarter by an abnormally high 2E12-F336A   3/B   RHR Service Water                     differential pressure Pump Strainer 2A                     across the CSCS service Backwash Outlet                       water strainers. These Stop                                 fast acting, automatically controlled valves only 2E12-F336B   3/B   RHR Service Water                     open to 10% of full stroke Pump Strainer 2B                     making an accurate stroke Backwash Outlet                       time measurement very Stop                                 difficult to obtain.
Commonwealth Edison PUMP & VALVE TEST 1NG Page 1
Furthermore, the stroke 2E22-F319   3/B   HPCS Diesel                           time of these valves is Cooling Water                         not considered a meaning-Strainer Backwash                     ful indicator of oper-Outlet Stop                           ational readiness.
of 1
\\d RELIEF REQUESTS IIi ASME 33 PUMP OR "O
SECTION XI VALVE NO.
FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE IESI 00 01 02 03 04 05 06 RV-01 2DG-Oli 3/B Strainer Backwash Full stroke and These valves open in Perform a full stroke Valves stroke time response to an autoback-exercise once per quarterly wash logic signal produced quarter by an abnormally high 2E12-F336A 3/B RHR Service Water differential pressure Pump Strainer 2A across the CSCS service Backwash Outlet water strainers. These Stop fast acting, automatically controlled valves only 2E12-F336B 3/B RHR Service Water open to 10% of full stroke Pump Strainer 2B making an accurate stroke Backwash Outlet time measurement very Stop difficult to obtain.
Furthermore, the stroke 2E22-F319 3/B HPCS Diesel time of these valves is Cooling Water not considered a meaning-Strainer Backwash ful indicator of oper-Outlet Stop ational readiness.
un
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( C# J tassisecountyNuclearStationUnit 2                   PUMP & VALVE TESTING               Pago   1   of   2
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Commonwealth Edison
Uy JN         FUNCTION       TEST REQUlHEMENT       BASIS FOR RELIEF       ALIEHNATIVE IESI oo             of                 02             03                   04                   05                               06 RV-02     2IN017         2/A           Drywell Pneumatic   Full Stroke and   These valves are designed   Perform a full stroke to Drywell -         Stroke Time       to stroke rapidly within   exercise quarterly.
( C# J tassisecountyNuclearStationUnit 2 PUMP & VALVE TESTING Pago 1
Fail Close           Quarterly         a specified time range.
of 2
Verification that the 2IN074         2/B           Dryer Purging Valve                   valve strokes within the
'v RELIEF REQUESTS Iii ASME 13 PUMP OH
                                              - Fail Close                           time range is essential, i
$0 SECTION XI N
VALVE NO.
JN FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF ALIEHNATIVE IESI Uy E
oo of 02 03 04 05 06 RV-02 2IN017 2/A Drywell Pneumatic Full Stroke and These valves are designed Perform a full stroke to Drywell -
Stroke Time to stroke rapidly within exercise quarterly.
Fail Close Quarterly a specified time range.
Verification that the 2IN074 2/B Dryer Purging Valve valve strokes within the
- Fail Close time range is essential, i
but due to the inaccuracie.
but due to the inaccuracie.
2IN075         2/B
2IN075 2/B involved with measuring short time intervals, 2IN031 2/A TIP Indexer Purge stroke time trending pro-vides no useful informa-2B33-F019 2/A Process Sampling tion and may even lead to Valve unnecessary maintenance operations. Therefore, 2B33-F020 2/A the stroke times of these valves will not be 2D0004 3/B Diesel Oil Transfer trended, but will be Pump Stop Valve verified to not exceed 5 seconds.
                                              "        "                            involved with measuring short time intervals, 2IN031         2/A           TIP Indexer Purge                       stroke time trending pro-vides no useful informa-2B33-F019       2/A           Process Sampling                       tion and may even lead to Valve                                   unnecessary maintenance operations. Therefore, 2B33-F020       2/A the stroke times of these valves will not be 2D0004         3/B           Diesel Oil Transfer                     trended, but will be
200014 3/B 2D0024 3/B t
,                                            Pump Stop Valve                         verified to not exceed 5 seconds.
2CM017A 2/A Containment Monitor-ing Valve 2CM017B 2/A 2CM018A 2/A 2CM0188 2/A uo
200014         3/B 2D0024         3/B t
2CM017A       2/A           Containment Monitor-ing Valve 2CM017B       2/A 2CM018A       2/A 2CM0188       2/A uo


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IiiO                                                         EO                                 ASME 33                                       PUMPOft             "O                             SECTION XI y@
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00                                           01               02               03               04               05                   06 RV-02                                   2CM019A             2/A     Containment Monitor-(cont'd)                                                                 ing Valve 2CM019B             2/A 2CM020A             2/A 2CM020B             2/A 2CM021B             2/B 2CM022A             2/B 2CM023B             2/B 2CM024A             2/B 2CM025A             2/B
Commonwealth Edison
                                                                                                                                                        \
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2CM026B             2/B                                                                                 N
LaSalle County Nuc' ear Station Unit 2 PUMP & VALVE TESTING Pago 2
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RELIEF REQUESTS e
IiiO EO ASME 33 PUMPOft "O
SECTION XI y@
VALVE NO.
M FUNCTION TEST REQUlllEMENT BASIS FOR HELIEF AL TEllNAllVE IESI 04 e
0 00 01 02 03 04 05 06 RV-02 2CM019A 2/A Containment Monitor-(cont'd) ing Valve 2CM019B 2/A 2CM020A 2/A 2CM020B 2/A 2CM021B 2/B 2CM022A 2/B 2CM023B 2/B 2CM024A 2/B 2CM025A 2/B
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2CM026B 2/B N
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2CM031 2/A i
2CM032 2/A 1
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    \ '' ' "J LaSalle County Nuclear Station Unit 2 i
Commonwealth Edison
PUMP & VALVE TESTING                 Pago   1   of     1 RELIEF REQUESTS Ili                         5                                               ASME 33           PUMP OH VALVE NO.
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                                      $0                          FUNCTION SECTION XI TEST HEOUlHEMENT         BASIS FOR HELIEF         ALIEHNATIVE IESI o
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00             01           02                           03                 04                     05                       06 RV-03       2WR-029         2/A     Drywell Equipment                 Full Stroke       Reactor recirculation         Perform a full stroke RBCCW Isolation                   Exercise Quarterly pump operation requires a     exercise during cold continuous cooling water     shutdown 2WR-040         2/A                                                         flow from the reactor building closed cooling 2WR-179         2/A                                                         water system. Exercising these valves during oper-2WR-180         2/A                                                         ation interupts this flow from the reactor building closed cooling water system. This could result in damage to these pumps and thus place the plant in a less safe mode of operation.
\\ '' ' "J LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 1
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RELIEF REQUESTS Ili 5
ASME 33 PUMP OH
$0 SECTION XI VALVE NO.
FUNCTION TEST HEOUlHEMENT BASIS FOR HELIEF ALIEHNATIVE IESI o
00 01 02 03 04 05 06 RV-03 2WR-029 2/A Drywell Equipment Full Stroke Reactor recirculation Perform a full stroke RBCCW Isolation Exercise Quarterly pump operation requires a exercise during cold continuous cooling water shutdown 2WR-040 2/A flow from the reactor building closed cooling 2WR-179 2/A water system.
Exercising these valves during oper-2WR-180 2/A ation interupts this flow from the reactor building closed cooling water system. This could result in damage to these pumps and thus place the plant in a less safe mode of operation.
t al 13
t al 13


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LaSaHe County Nucker Station Unit 2                                         PUMP & VALVE TESTING RELIEF REQUESTS Pago   I   of I Ei                                                             E                             ASME 33       PUMPOH                                               $O                           SECTION XI da      VALVE NO.                                             Jf       FUNCTION     TEST HEOulitEMENT       BASIS FOR HEllEF       ALTEHNATIVE IESI og Go         of                                                 02         03                 04                   05                       06 RV-04 2E21-F005                                               1/B LPCS Injection     Full Stroke       These valves cannot be     Perform a full stroir Line Outboard       Exercise Quarterly exercised during normal   exercise during cold Stop                                   operation because they     shutdown.
Commonwealth Edison
are electrically inter-2E12-F008                                               1/A RHR Shutdown                           locked shut by normal Cooling Pump 2A                       operating differential Suction HDR                           pressure to protect the Isolation Outboard                     low pressure piping outside the drywell.
('
2E12-F009                                               1/A RHR Shutdown Cooling Inboard Isolation 2E12-F050A                                             1/C RHR Shutdown Cooling Testable Check 2E12-F050B                                             1/C           ,"
LaSaHe County Nucker Station Unit 2 PUMP & VALVE TESTING Pago I
2E12-F053A                                             1/B RHR Shutdown Cooling Discharge Isolation 2E12-F053B                                             1/B RHR Shutdown Cooling Discharge Isolation 2E12-F023                                               1/B RHR te Head Spray L
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RELIEF REQUESTS Ei E
ASME 33 PUMPOH
$O SECTION XI d
VALVE NO.
Jf FUNCTION TEST HEOulitEMENT BASIS FOR HEllEF ALTEHNATIVE IESI og a
Go of 02 03 04 05 06 RV-04 2E21-F005 1/B LPCS Injection Full Stroke These valves cannot be Perform a full stroir Line Outboard Exercise Quarterly exercised during normal exercise during cold Stop operation because they shutdown.
are electrically inter-2E12-F008 1/A RHR Shutdown locked shut by normal Cooling Pump 2A operating differential Suction HDR pressure to protect the Isolation Outboard low pressure piping outside the drywell.
2E12-F009 1/A RHR Shutdown Cooling Inboard Isolation 2E12-F050A 1/C RHR Shutdown Cooling Testable Check 2E12-F050B 1/C 2E12-F053A 1/B RHR Shutdown Cooling Discharge Isolation 2E12-F053B 1/B RHR Shutdown Cooling Discharge Isolation 2E12-F023 1/B RHR te Head Spray L
t el 83
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O                                                                 O                                               O E _) Commonwealth Edison s        LaSalle County Nuclear Station Unit 2 N-RELIEF REQUESTS s                                   >
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5 i0                                   50                             ASME 33     PUMP OH                       "O                           SECTION XI VALVE NO.                             FUNCTION       TEST FIEOulitEMENT     DASIS F OR FIEt IEF ALTEFINATIVE TEST 00           Of                       02         03                   04                     05                   06 2
O E _)
RV-05 2E51-F013                       1/8 RCIC Outboard in-   Full Stroke Exer-   During power operation, Pc? form a full jection Stop Valve cise Quarterly     the RCIC piping is       stroke exercise normally pressurized at during cold shutdown.
Commonwealth Edison LaSalle County Nuclear Station Unit 2 sN-RELIEF REQUESTS s
i0 50 ASME 5
33 PUMP OH "O
SECTION XI VALVE NO.
FUNCTION TEST FIEOulitEMENT DASIS F OR FIEt IEF ALTEFINATIVE TEST 00 Of 02 03 04 05 06 2
RV-05 2E51-F013 1/8 RCIC Outboard in-Full Stroke Exer-During power operation, Pc? form a full jection Stop Valve cise Quarterly the RCIC piping is stroke exercise normally pressurized at during cold shutdown.
60 psig. One purpose of valve F013 is to isolate reactor pressure from the RCIC system.
60 psig. One purpose of valve F013 is to isolate reactor pressure from the RCIC system.
Opening the valve would result in a water hammer of the RCIC piping, and the high reactor water pressure would cause damage to the low pressure piping on the suction side of the RCIC pump, which is designed for a maximum pressure of 100 psig.
Opening the valve would result in a water hammer of the RCIC piping, and the high reactor water pressure would cause damage to the low pressure piping on the suction side of the RCIC pump, which is designed for a maximum pressure of 100 psig.
l                                                                                         The valve may be exer-I cised during cold shutdowns when reactor pressure has been sub-stantially reduced.
l The valve may be exer-I cised during cold shutdowns when reactor pressure has been sub-stantially reduced.
1 ftl IIS
1 ftl IIS


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                              / LaSaNo County Nuclear StaHon Unit 2 PUMP & V ALVE TESTING                   Page 1 of 1 RELIEF REOUESTS s
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:                        wo          VALVE NO.        $                FUNCTION         TEST HEOUlHEMENT         BASIS F OR REllEF       Al.iERNATIVE IES T t                       Ky                             o!
PUMP & V ALVE TESTING Page 1 of 1
,                                                        o l                       00               01           02                 03                   04                       05                       06 RV-06         2B21-F010A         1/AC   Feedwater Inboard           Exercise Quarterly   A leak rate test must be   Perfonn a full stroke Check Valve                                     conducted in order to       exercise each verify the closure of       refueling outage 2B21-F010B         1/AC   Feedwater Inboard                               these normally open Check Valve                                     check valves. This test is not possible during power operation
/ LaSaNo County Nuclear StaHon Unit 2 RELIEF REOUESTS s
:                                                                                                            or cold shutdown because a steady flow rate of coolant is passing through the feedwater lines. These t
i M
valves will be exercised at each refueling outage when the feed-water flow is interrupted ,
SO ASME 33 PUMP OH WO SECTION XI FUNCTION TEST HEOUlHEMENT BASIS F OR REllEF Al.iERNATIVE IES T o!
i                 n e st lJ
wo VALVE NO.
t Ky o
l 00 01 02 03 04 05 06 RV-06 2B21-F010A 1/AC Feedwater Inboard Exercise Quarterly A leak rate test must be Perfonn a full stroke Check Valve conducted in order to exercise each verify the closure of refueling outage 2B21-F010B 1/AC Feedwater Inboard these normally open Check Valve check valves.
This test is not possible during power operation or cold shutdown because a steady flow rate of coolant is passing through the feedwater lines.
These t
valves will be exercised at each refueling outage when the feed-water flow is interrupted n
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    ;i   Commonwealth Edison                                                                   Page 1    W Lassile County Nuclear Station Unit 2             PUMP & VALVE TESTING                               1
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  '                                                          RELIEF REQUESTS Eb                                 ASME
;i Commonwealth Edison Lassile County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 W
    $$                                                                SECTION XI P      PUMP OR               $0           FUNCTION       TEST REQUIREMENT       BASIS FOR RELIEF     ALTERNATIVE. TEST i 8    VALVE NO.-
1 RELIEF REQUESTS Eb ASME P
04                    05                    06 00           01                 02             03                                                                           i 2B21-F065A                 2/A     Rx Feedwater       Full Stroke       It is impractical to     Perfom a full stroke RV-07                                                                           exercise these valves     exercise during cold Isolation avalve  Exercise Quarterly 2/A        "                                during nonnal operation   shutdown, 2821-F0658                                                               because tim feedwater system is needed to maintain primary coolant inventory.
PUMP OR
Exercising them would deprive tie flow of feedwater to the vessel
$0 SECTION XI 8
;                                                                                  tius putting tim plant in a less safe condition.
VALVE NO.-
FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE. TEST i
00 01 02 03 04 05 06 i
2B21-F065A 2/A Rx Feedwater Full Stroke It is impractical to Perfom a full stroke RV-07 Isolation valve Exercise Quarterly exercise these valves exercise during cold during nonnal operation
: shutdown, a
2821-F0658 2/A because tim feedwater system is needed to maintain primary coolant inventory.
Exercising them would deprive tie flow of feedwater to the vessel tius putting tim plant in a less safe condition.
1 GF-t3
1 GF-t3


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        $$                        So                                 ASME 33      PUMPOF4                                          SECilON XI At.TEFINAYlVE TEST N"      VALVE NO.        y[O         F UNCilON       TEST f1EOUlHEMENT         B ASIS F OR f1Et IEF 5
O l
00         ol           02             03                   04                         05                                                                             06 RV-08 2G33-F001         1/A     Inboard Suction     full Stroke Exer-   The entire RWCU system                                                               Perfonn a full stroke Isolation           cise Quarterly       must be inoperable                                                                   exercise during cold before any of these                                                                 shutdown 2G33-F004         1/A     Outboard Suction                       -
Commonwealth Edison VJ LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 of I sb/
valves can be closed.
RELIEF REQUESTS F
Isolation                                 This system maintains reactor water chemistry 2G33-F040         2/A     Discharge to Feed-                       and prevents thermal water Isolation                           stratification of the water in the bottom head section of the vessel.
So ASME y[O SECilON XI 33 PUMPOF4 F UNCilON TEST f1EOUlHEMENT B ASIS F OR f1Et IEF At.TEFINAYlVE TEST N
The systems operability is required during power operation to prevent fuel cladding reactions and to prevent thermal stresses in the vessel's bottom head section. There fore, 1
VALVE NO.
these valves will be
5 00 ol 02 03 04 05 06 RV-08 2G33-F001 1/A Inboard Suction full Stroke Exer-The entire RWCU system Perfonn a full stroke Isolation cise Quarterly must be inoperable exercise during cold before any of these shutdown 2G33-F004 1/A Outboard Suction valves can be closed.
,                                                                                  full stroke exercised durinq each cold shut-down.
Isolation This system maintains reactor water chemistry 2G33-F040 2/A Discharge to Feed-and prevents thermal water Isolation stratification of the water in the bottom head section of the vessel.
The systems operability is required during power operation to prevent fuel cladding reactions and to prevent thermal stresses in the vessel's bottom head section.
There fore, 1
these valves will be full stroke exercised durinq each cold shut-down.
2 i
2 i
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O                                                     O                                               O l-         Commonwealth Edison                                                           Page g    of  2 PUMP & V ALVE TESTING (dO N  "/ Lasalle County   Nuclear   Station   Unit 2   RELIEF REQUESTS ASME SECTION XI d
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33       PUMP OR       yO                           TEST REQUIREMENT       HASIS FOR REllEF       ALTERNATIVE TEST V ALVE NO.         ;      FUNCTION u                                                        05                     06 03                  04 00           01         02 ,
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of (dO "/ Lasalle County Nuclear Station Unit 2 RELIEF REQUESTS N
Full Stroke       These valves cannot be     Perform a full stroke RV-09  2VQO26            2/M Outboard to                              exercised during normal   exercise during cold R4pression          Exercise                                    shutdown.
ASME SECTION XI 33 PUMP OR yO TEST REQUIREMENT HASIS FOR REllEF ALTERNATIVE TEST d
Warterly         operation. These valves Chamber Fr. Rx                        are required to remain Oldg. Inboard                         administratively shut                           ,
FUNCTION V ALVE NO.
(PCIS) Isolation                       during power operation, Damper in accordance with the Final Safety Analysis 2VQ027             2/A   Inlet to                               lleport and the Suppression                           Technical Specifications.
04 05 06 u
Chantler Fr. Rx                         The response to FSAR Oldg. Inboard (PCIS) Isolation                       Question 021.54 further explains that Danper valve 2V0032 cannot be Inlet to Drywel:                     opened in an operating 2VQ029              2/A                                          or hot shutdown mode, Fr. Rx. Oldg.
00 01 02 03
i                                                                             and hence can only be Isolation Damper (PCIS) tested while in cold
~n i
                                                                              @utdown. Valve
RV-09 2VQO26 2/M Outboard to Full Stroke These valves cannot be Perform a full stroke R4pression Exercise exercised during normal exercise during cold Chamber Fr. Rx Warterly operation. These valves shutdown.
                                              "                                2V0035 does not have 2VQ030                                                         this restriction, and 2/A   toction Fr.                           hence is not contained 2VQO31                                                          on this relief request.
are required to remain Oldg. Inboard administratively shut (PCIS) Isolation during power operation, Damper in accordance with the Final Safety Analysis 2VQ027 2/A Inlet to lleport and the Suppression Technical Specifications.
S"lipression I:hanber Inhoarti isolation lunper 9
Chantler Fr. Rx The response to FSAR Oldg. Inboard (PCIS) Isolation Question 021.54 further explains that Danper valve 2V0032 cannot be 2VQ029 2/A Inlet to Drywel:
opened in an operating or hot shutdown mode, Fr. Rx. Oldg.
i and hence can only be Isolation Damper tested while in cold (PCIS)
@utdown.
Valve 2V0035 does not have 2VQ030 this restriction, and 2VQO31 2/A toction Fr.
hence is not contained S"lipression on this relief request.
I:hanber Inhoarti isolation lunper 9


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RELIEF REQUESTS E                                     ASME I                                                                                            SECTION XI 33       PUMP OR           $O               FUNCTION       TEST REQUIREMENT BASIS FOR REllEF     ALTERNATIVE TEST
O h Commonwealth Edison PUMP & V ALVE TESTlNG Pat 2 2 of 2
:                            us o    VALVE NO.          J$
LaSalle County Nuclear Station Urtil 2
EE                         O<
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u                                                     05                    06 02                 03                 04 00            01 Full Stroke                            Perform a full stmke RV-09   2VQO34                 2/A     Suction Fr.                                                 exercise during cold Drywell Inboard     Exercise Quarterly                                                                 '
RELIEF REQUESTS I
shutdown.
E ASME 33 PUMP OR
'                                                                    Isolation DarMier PCIS 2VQO36                 2/A   Suction Fr.
$O SECTION XI us o VALVE NO.
Drywell Outboard Isolation Damper Oypass 2v0042                 2/0 2VQ043                 2/0 l
J$
I                                    2VQO32                 2/A   Oypass Suction l
FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE TEST EE O<u 00 01 02 03 04 05 06 Perform a full stmke RV-09 2VQO34 2/A Suction Fr.
2VQ040                 2/A     Suction From Suppression Chairhe Outboard Isolation Dargler (PCIS) til-IT
Full Stroke Drywell Inboard Exercise Quarterly exercise during cold shutdown.
Isolation DarMier PCIS 2VQO36 2/A Suction Fr.
Drywell Outboard Isolation Damper Oypass 2v0042 2/0 l
2VQ043 2/0 I
2VQO32 2/A Oypass Suction l
2VQ040 2/A Suction From Suppression Chairhe Outboard Isolation Dargler (PCIS) til-IT


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RELIEF REQUESTS s
RELIEF REQUESTS s
* Iu,                                                                                                                               ASME SECTION XI 33 us O PUMPOH VALVE NO.
Iu, ASME 33 PUMPOH
                                                                                                $0 s "'                   FUNCTION           TEST HEOUlHEMENT                       HASIS FOR REtIEF               At.TERNATWE TEST o<
$0 SECTION XI us O VALVE NO.
Ey                                                                          o 02                         03                             04                               05                         06 00                                                        01 4
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RV-10                                                                 2E22-F016         2/C   Suppression Pool                     Exercise Quarterly               The llPCS system is demon-     Exercise each refuel-Suction Check                                                         strated to be operable         ing outage during each quarter by taking a       HPCS alternate flow suction from, and dis-         path test.
FUNCTION TEST HEOUlHEMENT HASIS FOR REtIEF At.TERNATWE TEST Ey o<o 00 01 02 03 04 05 06 RV-10 2E22-F016 2/C Suppression Pool Exercise Quarterly The llPCS system is demon-Exercise each refuel-4 Suction Check strated to be operable ing outage during each quarter by taking a HPCS alternate flow suction from, and dis-path test.
charging back to the cycled condensate storage tank. Cycled condensate is reactor grade water, however, this is not necessarily true of suppression pool water.
charging back to the cycled condensate storage tank. Cycled condensate is reactor grade water, however, this is not necessarily true of suppression pool water.
Valve F016 can be exer-cised by aligning the llPCS pump suction to the suppression pool. Allow-ing suppression pool water to enter the 11PCS system permits the possibility of cycled condensate con-tamination which would cause many of the units' systems to become contami-nated. This situation is undesirable at all times, but may be quarded aqainst if tested during refueling notages.
Valve F016 can be exer-cised by aligning the llPCS pump suction to the suppression pool.
Allow-ing suppression pool water to enter the 11PCS system permits the possibility of cycled condensate con-tamination which would cause many of the units' systems to become contami-nated.
This situation is undesirable at all times, but may be quarded aqainst if tested during refueling notages.
Therefnre, it is requested that this valve be full st rok e evert ised durinq ear.h refuelinq outaqc.
Therefnre, it is requested that this valve be full st rok e evert ised durinq ear.h refuelinq outaqc.
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O                                                           o                                                   o Commonwealth Edison
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('''                     LaSane County Nuclear Station Unit 2         PUMP & V ALVE TESTING RELIEF REQUESTS Page 1      of    1 r
o Commonwealth Edison PUMP & V ALVE TESTING Page 1 of 1
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                                                    $$                                                        SECilON XI 33           PUMP OR   $0             FUNCTION       TEST HEOUIREMENT         BASIS FOR RELIEF       ALTERNATIVE TEST 3          VALVE NO.
LaSane County Nuclear Station Unit 2 RELIEF REQUESTS r
04                      05                      06 00             01       02               03 1/A     MS Bleed Valve     Full Stroke Exercise These valves camot be       Perform a full stroke RV-11      2E32-F001A                                                          exercised durirg normal     exercise during cold 2E32-F001E        1/A    M5 Bleed Valve      Quarterly 1/A     MS Bleed Valve                           operation. These valves     shutdown.
EO ASME 33 PUMP OR
2E32-F00lJ                                                          are desityled to operate 2E32-F00lN       1/A     MS Bleed Valve 2/B    MS Loop Oypass                          when the main steam line 2E32-F003A                                                         pressure is near 2E32-F003E       2/b to Steam       Tunnel
$0 SECilON XI 3
                                                                                                    "                          atmospheric. Testing 2E32-F003J       2/8 " "
VALVE NO.
2E32-F003N       2/6     "    "    "                          of these valves at 2E32-F002A       2/8 MS Loop Bleed                               normal steam line pressure has tre 2E32-F00?E       2/8 Valve           "                          potential for 2E32-F002J       2/8 a "
FUNCTION TEST HEOUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RV-11 2E32-F001A 1/A MS Bleed Valve Full Stroke Exercise These valves camot be Perform a full stroke 2E32-F001E 1/A M5 Bleed Valve Quarterly exercised durirg normal exercise during cold 2E32-F00lJ 1/A MS Bleed Valve operation. These valves shutdown.
2/8      "    "    "                          dischargirg live steam 2E32-F002N 2E32 F006       2/U Oleed Valve-                                 into the Heactor 2/B     Steam Tunnel                             building Atmosphere.
2E32-F00lN 1/A MS Bleed Valve are desityled to operate when the main steam line 2E32-F003A 2/B MS Loop Oypass 2E32-F003E 2/b to Steam Tunnel pressure is near atmospheric.
2E32-F007                        "
Testing 2E32-F003J 2/8 of these valves at 2E32-F003N 2/6 normal steam line 2E32-F002A 2/8 MS Loop Bleed 2E32-F00?E 2/8 Valve pressure has tre potential for a
2E32-F008       2/U 2E32-F009       2/U GL13
2E32-F002J 2/8 dischargirg live steam 2E32-F002N 2/8 2E32 F006 2/U Oleed Valve-into the Heactor 2E32-F007 2/B Steam Tunnel building Atmosphere.
2E32-F008 2/U 2E32-F009 2/U l
GL13


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( '] LaSalle County Nuclear Station Unit 2         PUMP & V ALVE TESTING                 Page 1 of 1 RELIEF REQUESTS s-                     >
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Commonwealth Edison
        -3s          PUMP OR   QO                             SECTION XI yO          VALVE NO.               FUNCTION       TEST REQUlHEMENT         BASIS FOR ret IEF     AtTERNATIVE TEST 00             01     02             03                 04                     05                     06 RV-12       2IN017       2/A   Drywell Pneumatic   Full Stroke Exer-   As these valves cut off   Perform full stroke to Drywell -       cise Quarterly     the supply and discharge   exercise coincident Fail Close                             side of the compressor     with fail safe oper- -
( '] LaSalle County Nuclear Station Unit 2 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS s-
from the drywell, they     ation at each refuel-2II1001A     2/A   Drywell Suction                         may be stroked closed     ing outage. Valves Isolations - Fail                       only when the nitrogen     21N043 and 2IN044 Close                                   compressor is shutdown. are not fail safe Normally, this occurs only tested.
'M Eo ASME
2IN001B       2/A   Drywell Suction                         during refueling outages Isolations - Fail                       because instrument nitro-Close                                   gen is needed for control of the MSRV's, the in-21N074       2/A   Dryer Purging       Check the Fail Safe board isolation valves on Valve - Fail Close Operation of the   MS, HPCS, LPCS, RHR, and
-3 PUMP OR QO SECTION XI syO VALVE NO.
                                      .                  Valve upon loss of RCIC, and the process 2IN075       2/A   Dryer Purging       actuator power each sampling line on RR. The Valve. - Fail Close quarter,           instrument air alternate emergency supply cannot 4
FUNCTION TEST REQUlHEMENT BASIS FOR ret IEF AtTERNATIVE TEST 00 01 02 03 04 05 06 RV-12 2IN017 2/A Drywell Pneumatic Full Stroke Exer-As these valves cut off Perform full stroke to Drywell -
ZINO31       2/A   Tip indexer Purge                       be used during power Valve                                   operation or cold shut-down as it would contami-2IN043       3/C   ADS Supply Check                       nate the drywell nitrogen Valve                                   atmosphere. Therefore, these val,e wiD be 2IN044       3/C   ADS Supply Check                       stroked at each refueling Valve                                   outage when the drywell is de-inerted and the instrument nitrogen system is shutdown.
cise Quarterly the supply and discharge exercise coincident Fail Close side of the compressor with fail safe oper-from the drywell, they ation at each refuel-2II1001A 2/A Drywell Suction may be stroked closed ing outage.
Valves Isolations - Fail only when the nitrogen 21N043 and 2IN044 Close compressor is shutdown.
are not fail safe Normally, this occurs only tested.
2IN001B 2/A Drywell Suction during refueling outages Isolations - Fail because instrument nitro-Close gen is needed for control of the MSRV's, the in-21N074 2/A Dryer Purging Check the Fail Safe board isolation valves on Valve - Fail Close Operation of the MS, HPCS, LPCS, RHR, and Valve upon loss of RCIC, and the process 2IN075 2/A Dryer Purging actuator power each sampling line on RR.
The Valve. - Fail Close
: quarter, instrument air alternate emergency supply cannot ZINO31 2/A Tip indexer Purge be used during power 4
Valve operation or cold shut-down as it would contami-2IN043 3/C ADS Supply Check nate the drywell nitrogen Valve atmosphere.
Therefore, these val,e wiD be 2IN044 3/C ADS Supply Check stroked at each refueling Valve outage when the drywell is de-inerted and the instrument nitrogen system is shutdown.


O                                                         O                                                                   O Commonwealth Edison LaSalle County Nuclear Stauon unit 2         PUMP & V ALVE TESTING                 Page 1 of 1
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    '                                                                                            REllEF REQUESTS
O Commonwealth Edison LaSalle County Nuclear Stauon unit 2 PUMP & V ALVE TESTING Page 1 of 1 REllEF REQUESTS N
                          $$                                            N
ASME 33 PUMP OH
                                                                        *O ASME SECilON XI 33                        PUMP OH                                                                                        ALTERNA11VE TEST gO               g g
*O SECilON XI gO VALVE NO.
VALVE NO.           M o4 FUNCTION       TEST REQUlHEMENT       DASIS FOR REllEF o                                                                                                   06 02             03                 04                     05 00                        01 SBLC Pump Suction   Full Stroke Exer- During the test'.nq of       Perform a full stroke RV-13                                  2C41-F001A            2/B                                          these valves, the system     exercise during Stop Valve          cise Quarterly is aligned so that a         reactor refueling.
M FUNCTION TEST REQUlHEMENT DASIS FOR REllEF ALTERNA11VE TEST g
2/B     SBLC Pump Suction                     greater pressure exists 2 C41-F001B Stop Valve                            on the downstream side of
o4 g
o 00 01 02 03 04 05 06 RV-13 2C41-F001A 2/B SBLC Pump Suction Full Stroke Exer-During the test'.nq of Perform a full stroke Stop Valve cise Quarterly these valves, the system exercise during is aligned so that a reactor refueling.
2 C41-F001B 2/B SBLC Pump Suction greater pressure exists on the downstream side of Stop Valve
~
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the F001 valves than on the upstream side.
the F001 valves than on the upstream side.
Opening the valves causes dilution of the sodium pentaborate solution in the SBLC solution tank.
Opening the valves causes dilution of the sodium pentaborate solution in the SBLC solution tank.
Therefore, a chemical analysis of the solution will need to be performed, as required by the tech-i nical specifications, to ensure that the concen-tration of boron in solution is within the required limits. It is undesirable to perform
Therefore, a chemical analysis of the solution will need to be performed, as required by the tech-nical specifications, to i
;                                                                                                                      this test during cold shutdowns due to the considerable length of time the testing pro-cedure and chemical analysis requires. It is requested that the test-ing frequency for these valves be every refueling outano.
ensure that the concen-tration of boron in solution is within the required limits.
It is undesirable to perform this test during cold shutdowns due to the considerable length of time the testing pro-cedure and chemical analysis requires.
It is requested that the test-ing frequency for these valves be every refueling outano.
4
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( JL)       Commonwealth Edison                                                                 Page 1                 of   1 PUMP & VALVE TESTING
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Commonwealth Edison PUMP & VALVE TESTING Page 1 of 1
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LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS t                         r EO                                 ASME
LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS t
                          $$                                                                SECTION XI i3                 PUMP OR     QO             FUNCTION     TEST REQUIREMENT       B ASIS FOR RELIEF                   AllERNATIVE TEST VALVE NO.
r EO ASME i3 PUMP OR QO SECTION XI VALVE NO.
o                                                                                            06 02               03                 04                     05 00                    01                                                                                                                                    -.
FUNCTION TEST REQUIREMENT B ASIS FOR RELIEF AllERNATIVE TEST o
1 Exercise Quarterly These valves cannot be                 Exe mise during RV-14              ?C41-F006        1/C    Sa_C Outboard Check                                 exercised during                       reactor refueling.
00 01 02 03 04 05 06 RV-14
?C41-F006 1/C Sa_C Outboard Exercise Quarterly These valves cannot be Exe mise during 1
Check exercised during reactor refueling.
reactor operation i
reactor operation i
1/C   Inboard Check                         nor durng cold shutdown.
2C41-F007 1/C Inboard Check nor durng cold shutdown.
2C41-F007 To exercise these l
To exercise these l
valves open, tte system post inject into tie vessel.
valves open, tte system post inject into tie vessel.
A system injection is not practical i
A system injection is not practical during nonnal operation i
during nonnal operation or cold shutdown;
or cold shutdown; the explosive charges would have to be detonated and tim f
'                                                                                                        the explosive charges would have to be detonated and tim system taken out of fI                                                                                                        service.
system taken out of I
service.
1 i
1 i
f 3
f 0t 13 3
0t 13


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[ g)         Commonwealth Edison LaSalle County Nuclear Station Unit 2         PUMP & VALVE TESTING                 Page       I of           I f
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Commonwealth Edison
RELIEF REQUESTS Ili                                                               ASME 33         PUMP OH           QO                               SECTION XI
('
                          @@        VALVE NO.                          FUNCTION      TEST REQUIREMENT      UASIS FOR RELIEF                ALTERNATlVE IESI
LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page I
of I
f RELIEF REQUESTS Ili ASME 33 PUMP OH QO SECTION XI
[$
[$
00           01             02                 03               04                     05                                 06 RV-15   2E51-F064           1/A     High Energy Line   Full Stroke Exer- These valves are located             Perform a full stroke Break Safeguard     cise Quarterly   at the interface of high             exercise during RCIC Steam Outboard                   and low pressure piping.             cold shutdown.
VALVE NO.
Isolation                             Opening either valve during power operation 2E51-F091           1/A     Warm-Up Bypass                         could result in pressure Valve                                 line damage. The valves may be opened when reactor pressure is reduced during cold shutdown.
FUNCTION TEST REQUIREMENT UASIS FOR RELIEF ALTERNATlVE IESI 00 01 02 03 04 05 06 RV-15 2E51-F064 1/A High Energy Line Full Stroke Exer-These valves are located Perform a full stroke Break Safeguard cise Quarterly at the interface of high exercise during RCIC Steam Outboard and low pressure piping.
cold shutdown.
Isolation Opening either valve during power operation 2E51-F091 1/A Warm-Up Bypass could result in pressure Valve line damage. The valves may be opened when reactor pressure is reduced during cold shutdown.
t al 13 '
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s Commonwealth Edison 7 Lesene County Nuclear Stetton Unit 2          PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of I L/                 .
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b$                           So                               ASME 33           PUMP OH         mo                             SECilON XI AliERNAlfvE TEST us O       VALVE NO.                       FUNCTION     TEST HEOtllHLMENT                       D ASIS F OR REllEF Eg                           u u                                                                                                                                     OS 01           02               03               04                                       05 00 RV-16       2821-FU24A         3/C     M51V Accumulator   Exercise Quarterly             Entry into the drywell                                             Exercise during Check Valves                                       is reqitired to confirm                                           reactor refueling the closure of these                                               outage.
Commonwealth Edison PUMP & VALVE TESTING Page 1 of I 7 Lesene County Nuclear Stetton Unit 2 sL/
2821-F024B         3/C check valves. Since the drywell atmosphere is 2821-F024C         3/C nonnally inerted with nitrogen gas at all 2821-F024D         3/C times except refueling outages, these valves 2821-F040C         3/C     ADS Accumulator                                 may be exercised only Check Valves                                     during refueling outages when drywell 2821-F040D         3/C                                                       entry is possible.
RELIEF REQUESTS b$
2821-F040E         3/C 2821-F040R         3/C 2821-F040 S         3/C 2821-F040U         3/C 2B21-F040V         3/C l
So ASME 33 PUMP OH mo SECilON XI us O VALVE NO.
. .. n
FUNCTION TEST HEOtllHLMENT D ASIS F OR REllEF AliERNAlfvE TEST Eg u u 00 01 02 03 04 05 OS RV-16 2821-FU24A 3/C M51V Accumulator Exercise Quarterly Entry into the drywell Exercise during Check Valves is reqitired to confirm reactor refueling the closure of these outage.
_________ ___________                  _ _ _ _ _ _ _ _ _ _ . _                                          _  J
2821-F024B 3/C check valves.
Since the drywell atmosphere is 2821-F024C 3/C nonnally inerted with nitrogen gas at all 2821-F024D 3/C times except refueling outages, these valves 2821-F040C 3/C ADS Accumulator may be exercised only Check Valves during refueling outages when drywell 2821-F040D 3/C entry is possible.
2821-F040E 3/C 2821-F040R 3/C 2821-F040 S 3/C 2821-F040U 3/C 2B21-F040V 3/C l
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['( 'v']) LaSalleCountyNuclear PUMP            StationUnit
[' 'v']) LaSalleCountyNuclear StationUnit 2 Commonwealth Edison 1
                                                                      & V ALVE TESTING2                  Page 1 of 1 RELIEF REQUESTS b$                   So                                 ASME 33       PUMPOH     $O                             SECTION XI FUNCTION       T EST IlEOutflEMENT       DASIS F OR IV.tlEF               ALTERNATIVE TEST 8    VALVE NO.
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u 01     02           03                   04                       05                                   06 00 RV-17   2VP053A       2/A   Chilled Water Return Full Stroke Exer-   Closing any one of these     Perform a full stroke cise Quarterly     isolation valves would       exercise during 2VP053B       2/A prevent chilled water         refueling outages.
PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS b$
from reaching the primary 2VP114A       2/A
So ASME 33 PUMPOH
                                                "        "                              containment cooling i                                                                                         units. The systems 2VPil48       2/A
$O SECTION XI 8
                                                "        "                              operation is essential during power operation 2VP063A       2/A   Chilled Water                           and is also necessary Supply                                   during cold chutdowns to maintait, acceptable 2 VP063B       2/A
VALVE NO.
                                                "        "                              condition <, in the drywell for equipment and main-2 VPil3A       2/A
FUNCTION T EST IlEOutflEMENT DASIS F OR IV.tlEF ALTERNATIVE TEST u
                                                "        "                              tenance personnel.     These
00 01 02 03 04 05 06 RV-17 2VP053A 2/A Chilled Water Return Full Stroke Exer-Closing any one of these Perform a full stroke cise Quarterly isolation valves would exercise during 2VP053B 2/A prevent chilled water refueling outages.
:                                                                                        valves will be exercised 2 VPil38       2/A at refueling outages 4
from reaching the primary 2VP114A 2/A containment cooling i
when the heat input to the drywell atmosphere is substantially reduced.
units. The systems 2VPil48 2/A operation is essential during power operation 2VP063A 2/A Chilled Water and is also necessary Supply during cold chutdowns to maintait, acceptable 2 VP063B 2/A condition <, in the drywell for equipment and main-2 VPil3A 2/A tenance personnel.
These valves will be exercised 2 VPil38 2/A at refueling outages when the heat input to 4
the drywell atmosphere is substantially reduced.
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a O                                                           O                                                                         O E     Commonwealth Edison                                                               Page 1   of     I D    LaSalle County Nuclear Station Unit 2         PUMP & VALVE TESTING l
O O
RELIEF REQUESTS i
O a
.                    p EO                                 ASME
E Commonwealth Edison PUMP & VALVE TESTING Page 1 of I
                  $$                                                            SECTION XI
LaSalle County Nuclear Station Unit 2 D
                  ~13     PUMP OR           $0             FUNCTION     TEST REQUIREMENT     BASIS FOR REtlEF         ALTERNATIVE TE ST VALVE NO.
l l
04                    05                                              08 i                  00         01             02               03 2/C     CRD Fk v CVA     Exercise         Since these lines form     NA RV-18  2033-F017A                                                          part of the reactor Dutlet          Quarterly coolant pressure 2/C     CRD Flow CVB boundary, the conse-
RELIEF REQUESTS
,                        2033-F0170                                                          quences of line l                                                        Outlet                            failure was carefully 2/C    CRD Flow CVA                      evaluated. It was
)
:                        2 833-F013A                                                         determined that conse-Outlet                            quences of failure would
i p
EO ASME
~13 PUMP OR
$0 SECTION XI VALVE NO.
FUNCTION TEST REQUIREMENT BASIS FOR REtlEF ALTERNATIVE TE ST i
00 01 02 03 04 05 08 RV-18 2033-F017A 2/C CRD Fk v CVA Exercise Since these lines form NA Dutlet Quarterly part of the reactor coolant pressure 2033-F0170 2/C CRD Flow CVB boundary, the conse-l Outlet quences of line failure was carefully evaluated.
It was 2 833-F013A 2/C CRD Flow CVA determined that conse-
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2/C    CRD Flow CVO                      be less severe than an                                             ',
Outlet quences of failure would be less severe than an l
'                        2 B33-F0138                                                         instrument line failure, Outlet thereby exempting these valves from Inservice Testing. (Ref. IWV-1300) i i
2 B33-F0138 2/C CRD Flow CVO instrument line failure, Outlet thereby exempting these valves from Inservice Testing. (Ref. IWV-1300) i i
i i
i i
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O                                                                                     O                                                   O Commonwealth Edison LaSane County Nuclear Station Unit 2                                  pyyp & V ALViE TESTING                      Page 1 of 1
O O
O Commonwealth Edison
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RELIEF REQUESTS DO                                                         SO                                   ASME 33           PUMP OH                                     $O                               SECTION XI E8     g VALVE NO.                                     M o<
LaSane County Nuclear Station Unit 2 pyyp & V ALViE TESTING Page 1 of 1 RELIEF REQUESTS DO SO ASME 33 PUMP OH
FUNCTION       T EST i1EOUlflEMENT       BASIS F OFI FIELIEF     ALTEHNATIVE TEST o
$O SECTION XI E8 VALVE NO.
00               01                                     02         03                   04                       05                     06 Perform a Seat       Primary containment         Seat leak test in RV-19                      All Cateoory A                                      --
M FUNCTION T EST i1EOUlflEMENT BASIS F OFI FIELIEF ALTEHNATIVE TEST o<
N/A Category A isolation         accordance with primary con-                                                                  leakage Test Per IWV-3420             valves will be seat         10CFR50 Appendix J.
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tainment iso-                                                                                     leak tested and the lation' valves                                                                                     results analyzed in accordance with Appendix J requirements of 10CFR50.
00 01 02 03 04 05 06 RV-19 All Cateoory A N/A Perform a Seat Primary containment Seat leak test in primary con-leakage Test Per Category A isolation accordance with IWV-3420 valves will be seat 10CFR50 Appendix J.
I s .t                       13
tainment iso-leak tested and the lation' valves results analyzed in accordance with Appendix J requirements of 10CFR50.
I s.t 13


O                                                 O                                                                                   O Commonwealth Edison
O O
    @ LaSalle County Nuclear                                                               PUMP Station
O
                                                                                                & VALVE TESTING Unit 2        Pago 1       of 1 RELIEF REQUESTS IIi                                                         5                                 ASME
@ LaSalle County Nuclear Station Unit 2 Commonwealth Edison PUMP & VALVE TESTING Pago 1 of 1
          ~i 3 -
RELIEF REQUESTS IIi 5
PUMP Oil   *O                             SECTION XI y@                                               VALVE NO. b'O         FUNCTION     T EST flEQUlllEMEN T   UASIS f Oil flEt IEF   ALIEf tNATlVE IESI e                                               04 O
ASME
00                                             01               02   03                 04                   05                                                       06 RV-20                                           Deleted t al I:s
~i 3 PUMP Oil
*O SECTION XI y@
VALVE NO.
b'O FUNCTION T EST flEQUlllEMEN T UASIS f Oil flEt IEF ALIEf tNATlVE IESI 04 e
O 00 01 02 03 04 05 06 RV-20 Deleted i
i t al I:s


O                                                                                           O                                           O Commonwealth Edison V'   LaSelle County Nuclear Station Unit 2 PUMP & VALVE TESTING               Pago   1 or   1 RELIEF REQUESTS s                         >
O O
        $$                          SO                                                                   ASME
O Commonwealth Edison V'
        ~i 3     PUMP Oft           "O                                                               SECTION XI y@     VALVE NO.           If                                           FUNCTION       TEST F1EOuif1EMENT BASIS FOft flEllEF     ALIEilNATIVE IESI a                       O<
LaSelle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 1
O 00         G1             02                                             03                   04                 05                     06 RV-21 Deleted k
or 1
RELIEF REQUESTS s
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~i 3 PUMP Oft "O
SECTION XI y@
VALVE NO.
If FUNCTION TEST F1EOuif1EMENT BASIS FOft flEllEF ALIEilNATIVE IESI a
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Commonwealth Edison O tasaneCountyNuclearStationUnit                                  PUMP & VALVE TESTING 2                Pago 1     of   2 RELIEF REQUESTS IIi                                                                       ASME 13       PUMP OH VALVE NO.
%.;)
                                              $0        FUNCTION SECTION XI TEST REQUIREMENT         BASIS FOR REllEF       ALIERNATIVE IESI O
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00         ol                         02           03                   04                     05                     06 RV-22   2821-F022A                       1/A Primary Containment   Full stroke and     Full stroke testing these   Part stroke exercise Isolation for Main   stroke time       valves during normal         quarterly, perform a Steam Inboard         quarterly. Check reactor operation requires full stroke exercise the fail-safe     isolating one of the four and stroke time during 2B21-F022B                       1/A Primary Containment   operation of the   main steam lines. Isola- cold shutdown. The Isolation for Main   valve upon loss   tion of these lines         fail-safe operation Steam Inboard       of actuator power   results in primary system   of these valves will quarterly.         pressure spikes, reactor     also be checked 2B21-F022C                       1/A Primary Containment                     power decrease, and in-     during cold shutdown Isolation for Main                       creased flow in the un-     since this is done Steam Inboard                           isolated steam lines.       coincident with full This unsymctrical oper-     stroke exercising.
O tasaneCountyNuclearStationUnit 2 Commonwealth Edison PUMP & VALVE TESTING Pago 1 of 2
2B21-F022D                       1/A Primary Containment                     ation can lead to a         The fail-safe Isolation for Main                       reactor scram, and as       testing of valves Steam Inboard                           discussed in NUREG-0626     2B21-F022A, B, C, and pressure transients         D, however, will be 2821-F028A                       1/A Primary Containment                     resulting from full stroke   completed only at Isolation for Main                       te'. ting MSIV's increase   cold shutdowns in Steam Outboard                           the :hanges of actuating     which the primary primary system relief       containment is 2B21-F028B                       1/A Primary Containment                     valves. It is proposed       deinerted since access Isolation for Main                       that only partial stroke     to the valves to Steam Outboard                           testing be performed         perform this testing during power operation       requires entry into 2B21-F028C                       1/A Primary Containment                     and that the valve be       the drywell .
RELIEF REQUESTS IIi ASME 13 PUMP OH
Isolation for Main                       full stroked and stroke Steam Outboard                           timed during cold shut-downs. This partial stroke exercising provides an acceptable means of verifying valve performanc2 i
$0 SECTION XI VALVE NO.
FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALIERNATIVE IESI O
00 ol 02 03 04 05 06 RV-22 2821-F022A 1/A Primary Containment Full stroke and Full stroke testing these Part stroke exercise Isolation for Main stroke time valves during normal quarterly, perform a Steam Inboard quarterly.
Check reactor operation requires full stroke exercise the fail-safe isolating one of the four and stroke time during 2B21-F022B 1/A Primary Containment operation of the main steam lines.
Isola-cold shutdown.
The Isolation for Main valve upon loss tion of these lines fail-safe operation Steam Inboard of actuator power results in primary system of these valves will quarterly.
pressure spikes, reactor also be checked 2B21-F022C 1/A Primary Containment power decrease, and in-during cold shutdown Isolation for Main creased flow in the un-since this is done Steam Inboard isolated steam lines.
coincident with full This unsymctrical oper-stroke exercising.
2B21-F022D 1/A Primary Containment ation can lead to a The fail-safe Isolation for Main reactor scram, and as testing of valves Steam Inboard discussed in NUREG-0626 2B21-F022A, B, C, and pressure transients D, however, will be 2821-F028A 1/A Primary Containment resulting from full stroke completed only at Isolation for Main te'. ting MSIV's increase cold shutdowns in Steam Outboard the :hanges of actuating which the primary primary system relief containment is 2B21-F028B 1/A Primary Containment valves.
It is proposed deinerted since access Isolation for Main that only partial stroke to the valves to Steam Outboard testing be performed perform this testing during power operation requires entry into 2B21-F028C 1/A Primary Containment and that the valve be the drywell.
Isolation for Main full stroked and stroke Steam Outboard timed during cold shut-downs.
This partial stroke exercising provides an acceptable means of verifying valve performanc2 i
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1 O                                                                   O                                             O I   O.C       Commonwealth Edison
O O
  /
O 1
(O) j              LaSalle County Nuclear Station Unit 2                     PUMP & VALVE TESTING               Pago   2   of   2 N
I O
i                                                                           RELIEF REQUESTS IIi                                 E                                     ASME 33         PUMP OH                   *O                                   SECTION XI gO       VALVE NO.                                   FUNCTION       TEST REQUlHEMENT       BASIS FOR REllEF     ALIEHNATlVE IESI 00           01                     02                 03                 04                     05                   06 RV-22   2B21-F028D                   1/A         Primary Containment                   during plant operation
(O)
(. ant'd)                                           Isolation for Main                   without affecting safety Steam Outboard                       margins. This request also contributes to the
/
;                                                                                              reduction of the relief valves challenge rate as recommended in NUREG-0626.
.C Commonwealth Edison LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 2
of 2
j N
i RELIEF REQUESTS IIi E
ASME 33 PUMP OH
*O SECTION XI gO VALVE NO.
FUNCTION TEST REQUlHEMENT BASIS FOR REllEF ALIEHNATlVE IESI 00 01 02 03 04 05 06 RV-22 2B21-F028D 1/A Primary Containment during plant operation
(. ant'd)
Isolation for Main without affecting safety Steam Outboard margins.
This request also contributes to the reduction of the relief valves challenge rate as recommended in NUREG-0626.
a
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O                                       O                                                     O                           .
O O
i Commonwealth Edison O LaSalleCountyNuclearStationUnit                          PUMP & VALVE TESTING   2        Pago 1   of   1 RELIEF REQUESTS r                     >
O O LaSalleCountyNuclearStationUnit 2 i
                                                                  $$                  50                         ASME
Commonwealth Edison PUMP & VALVE TESTING Pago 1 of 1
                                                                  ~.i ')   PUMP OH VALVE NO.
RELIEF REQUESTS r
                                                                                        $0    FUNCTION SECTION XI TEST HEQUlitEMENT   BASIS FOR REllEF     ALTEf tNATIVE lESI O
50 ASME
00           01       02       03               04                 05                               06 RV-23           Deleted i.e n
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PUMP OH
$0 SECTION XI VALVE NO.
FUNCTION TEST HEQUlitEMENT BASIS FOR REllEF ALTEf tNATIVE lESI O
00 01 02 03 04 05 06 RV-23 Deleted i.e n


O                                                         O                                                                             O O        Commonwealth Edison
O O
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Las sie county Nuclear Station Unit 2         PUMP & VALVE TESTING RELIEF REQUESTS Pago     1                       of 1
O Commonwealth Edison Las sie county Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 1
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of 1
RELIEF REQUESTS Ei$
EO ASME "3 3 PUMP Oft "O
SECTIOf1 XI y@
VALVE NO.
FUNCTION TEST IlEOUlFlEMENT BASIS FOIlIlELIEF AL T EFINATIVE 1 ES I 00 01 02 03 04 05 06 RV-24 Deleted I
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[ 9 ,)         Commonwealth Edison PUMP & V ALVE TESTING                     Page 1 of 2 LaSalle County Nuclear Station i at 2 RELIEF REQUESTS w                                                                                               ASME 33     PUMP OH           *O                                                                   SECilON XI FUNCilON         TEST HEOUlHEMENT           D ASIS F OR ret IEF       AL TERNATIVE TEST g   VALVE NO.
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o                                                                                                                       06 01           02                                             03                       04                     05 00 RV-25   All valves in       NA       NA                                                   IWV 3417(b) and     Specific relief is request-   Evaluate the condition the program for                                                                     IWV 3523             ed from the requirements     of each valve with which IWV                                                                                               of paragraphs IWV 3417(b)     respect to its safety 3417(b) and/or                                                                                           and IWV 3523 of Section       related function and IWV 3523                                                                                               XI of the 1980 Edition       take appropriate apply.                                                                                                   of the ASME Boiler and       corrective action Pressure Vessel Code in-     as stated in the
[ 9,)
-                                                                                                                                    ciuding the Addenda           Technical Specifica-through Winter 1980.         tion - Limiting
Commonwealth Edison LaSalle County Nuclear Station i at 2 PUMP & V ALVE TESTING Page 1 of 2 RELIEF REQUESTS ASME w
,                                                                                                                                    These paragraphs state       Condition for the corrective actions to operation.
33 PUMP OH
be taken when valves fail to exhibit a required 3
*O SECilON XI VALVE NO.
change of disk position.
FUNCilON TEST HEOUlHEMENT D ASIS F OR ret IEF AL TERNATIVE TEST g
l                                                                                                                                     These actions include requirements to take corrective action prior to plant startup should a failure occur during cold shutdown testing.       Also stated are requirements to declare valves in-operable if corrective action is unsuccessful within a 24 hour period.
o 00 01 02 03 04 05 06 RV-25 All valves in NA NA IWV 3417(b) and Specific relief is request-Evaluate the condition the program for IWV 3523 ed from the requirements of each valve with which IWV of paragraphs IWV 3417(b) respect to its safety 3417(b) and/or and IWV 3523 of Section related function and IWV 3523 XI of the 1980 Edition take appropriate apply.
These paragraphs do not take into account the plant Technical Specifica-tion requirements for limitinq conditions for aperation which state the t .I 13
of the ASME Boiler and corrective action Pressure Vessel Code in-as stated in the ciuding the Addenda Technical Specifica-through Winter 1980.
tion - Limiting These paragraphs state Condition for the corrective actions to operation.
be taken when valves fail to exhibit a required change of disk position.
3 l
These actions include requirements to take corrective action prior to plant startup should a failure occur during cold shutdown testing.
Also stated are requirements to declare valves in-operable if corrective action is unsuccessful within a 24 hour period.
These paragraphs do not take into account the plant Technical Specifica-tion requirements for limitinq conditions for aperation which state the t.I 13


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Commonwealth Edison Lasaii. county Nuclear Station Unit 2                             PUMP & V ALVE TESTING                                         page 2 of 2
Commonwealth Edison
    '~                                                                             RELIEF REQUESTS e                                                                                             ASME M                             Eo                                                               SECTION XI 33         PUMPOH             mo                                                                                               BASIS F OFI FIEllEF ALTEFINATIVE TESI w0 Ey VALVE NO.          M o<
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FUNCTION            TEST flEOulitEMENT u                                                                04                                 05                 06 01           02                             03 00 minimum conditions RY-25     Continued                                                                                                     necessary for safe opera-tion of the plant. The failure of a particular i
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valve may not necessarily require a plant shutdown or prevent a startup. In addition, valves not
Lasaii. county Nuclear Station Unit 2 PUMP & V ALVE TESTING page 2 of 2 RELIEF REQUESTS
'                                                                                                                              capable of perfonning their safety-related function are declared inoperable as soon as that condition has been verified, not after a 24-hour period has elapsed.
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Eo ASME 33 PUMPOH mo SECTION XI w0 VALVE NO.
M FUNCTION TEST flEOulitEMENT BASIS F OFI FIEllEF ALTEFINATIVE TESI Ey o<
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00 01 02 03 minimum conditions RY-25 Continued necessary for safe opera-tion of the plant.
The failure of a particular valve may not necessarily i
require a plant shutdown or prevent a startup.
In addition, valves not capable of perfonning their safety-related function are declared inoperable as soon as that condition has been verified, not after a 24-hour period has elapsed.
For the above reasons, l.a Salle County Station will evaluate the condition of each valve With respect to its safety-related function and take the appropriate cnrrective action as stated in the Technical specificatinn - Limitinq Condition for Operation.
For the above reasons, l.a Salle County Station will evaluate the condition of each valve With respect to its safety-related function and take the appropriate cnrrective action as stated in the Technical specificatinn - Limitinq Condition for Operation.


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( ' ' ' LaSane County Nuclear Station Unit 2           PUMP & VALVE TESTING                   Page   1   of               1 RELIEF REQUESTS IIi                                                           ASME 33           PUMP OR     $O                                 SECTION XI
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                                    %"          VALVE NO.                 FUNCTION       TEST HEOUlHEMENT         DASIS FOR HELIEF           ALTERNATlVE 1ESI 00
( ' ' ' LaSane County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1
[$                                    04 01         02             03                                           05                                                                                 06 RV-26     2Cll-F380       2/B     CRD Scram Discharge Full Stroke and       The system is designed       Full stroke exercise Instrument Volume   Stroke Time Quarterly such that the test           quarterly.
of 1
Vent                                       circuit bleeds air from these air operated valves 2Cll-F381       2/B     CRD Scram Discharge                       at a very slow rate, Instrument Volume                         much slower than during Drain                                     normal operation of the valve. Thus, timing 2Cll-F388       2/B     CRD Scram Discharge                       these valves during test-Instrument Volume                         ing has no relevance, and Vent                                       because of the slow bleed rate, the test time 2Cll-F389       2/B     CRD Scram Discharge                       repeatibility is poor.
RELIEF REQUESTS IIi ASME 33 PUMP OR
Instrument Volume Drain s .t f3
$O SECTION XI VALVE NO.
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FUNCTION TEST HEOUlHEMENT DASIS FOR HELIEF ALTERNATlVE 1ESI 00 01 02 03 04 05 06 RV-26 2Cll-F380 2/B CRD Scram Discharge Full Stroke and The system is designed Full stroke exercise Instrument Volume Stroke Time Quarterly such that the test quarterly.
Vent circuit bleeds air from these air operated valves 2Cll-F381 2/B CRD Scram Discharge at a very slow rate, Instrument Volume much slower than during Drain normal operation of the valve.
Thus, timing 2Cll-F388 2/B CRD Scram Discharge these valves during test-Instrument Volume ing has no relevance, and Vent because of the slow bleed rate, the test time 2Cll-F389 2/B CRD Scram Discharge repeatibility is poor.
Instrument Volume Drain s.t f3


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00         01             02               03                 04                       05                       06 RV-27 2E12-F042A         1/B       LPCI Injection     Full Stroke         Relief is requested from     Perform a full stroke Valves             Exercise Quarterly   full stroke exercising       exercise during cold 2E12-F042B                                                             these valves during         shutdown.
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O LaSaneCountyNuclearStationUnit 2 Commonwealth Edison PUMP & VALVE TESTING Page 1 of 2
RELIEF REQU ESTS Ui ASME 33 PUMP OR
$O SECTION X1 VALVE NO.
FUNCTION TEST REQUIREMENT BASIS FOR REL IEF AL TERNATlVE 1ESI O
00 01 02 03 04 05 06 RV-27 2E12-F042A 1/B LPCI Injection Full Stroke Relief is requested from Perform a full stroke Valves Exercise Quarterly full stroke exercising exercise during cold 2E12-F042B these valves during shutdown.
normal reactor operation.
normal reactor operation.
2E12-F042C                                                           The valves are interlocked closed with greater than 729 psid across them, which would require the LPCI pumps to be running to cycle the valves.     If the valve was opened (pump running) in this manner and the inboard testable check valve was to fail or leak, the low pressure piping would be subjected to reactor pressure. This would lift the low pressure piping relief valve (500#) and provide a flow path for reactor pressure to the suppression pool. The relief line is only of 1 inch diameter, and depending on the amount of check valve leakage there exists the potential to severly overpressurize the low pressure piping.
2E12-F042C The valves are interlocked closed with greater than 729 psid across them, which would require the LPCI pumps to be running to cycle the valves.
If the valve was opened (pump running) in this manner and the inboard testable check valve was to fail or leak, the low pressure piping would be subjected to reactor pressure.
This would lift the low pressure piping relief valve (500#) and provide a flow path for reactor pressure to the suppression pool. The relief line is only of 1 inch diameter, and depending on the amount of check valve leakage there exists the potential to severly overpressurize the low pressure piping.
Exercising these valves un
Exercising these valves un


O                                       O                                             O Commonwealth Edison O LaSalle County Nuclear                                               PUMPStation
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                                                                                & VALVE TESTlNGUnit 2        Pago   2   of   2 RELIEF REQUESTS III                               E                         ASME
O O LaSalle County Nuclear Station Unit 2 Commonwealth Edison PUMP & VALVE TESTlNG Pago 2
                            ~i 3                 PUMP OH                           SECTION XI y@                   VALVE NO.
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[$0  FUNCTION     TEST REQUlHEMENT       BASIS FOR RELIEF     AL TERNATIVE 1ESI n
RELIEF REQUESTS III E
00                 01       02     03               04                     05                   06 RV-27 (Cont'd)                                                                                     provides single valve protection to the low
ASME
.,                                                                                                pressure piping for the duration of the test, thus placing the plant in a less safe condition.
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~i 3 PUMP OH SECTION XI y@
VALVE NO.
FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF AL TERNATIVE 1ESI n
00 01 02 03 04 05 06 RV-27 (Cont'd) provides single valve protection to the low pressure piping for the duration of the test, thus placing the plant in a less safe condition.
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                                                                                                  & V ALVE
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                        \, d     '                                                            RELIEF REQUESTS e
SECTlON XI 33 PUMP OR
DE                     N                                   ASME SECTlON XI 33       PUMP OR     $0             FUNCTION      TEST REQUIREMENT           BASIS FOR RELIEF       ALTERNATIVE TEST S       VALVE NO.
$0 TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST S
04                       05                     08 00           01       02               03 The vacuum breaker system     Exercise during allows MSRV downcomer refueling outages.
VALVE NO.
Exercise Quarterly pressure to equalize with RV-28   2821-F037Al     3/C       Vacuum Breakers                     drywell pressure as down-for The V.aln c omer   steam is condensed 2821-F037A2       3/C     Ste:3 r.elief                       in the suppression pool.
FUNCTION 04 05 08 00 01 02 03 The vacuum breaker system Exercise during allows MSRV downcomer refueling outages.
Valve 01scharge                     The 36 normally closed 2821-F037B1       3/C     Lines.                               check valves (2 on each downcomer) which comprise 2821-F03782       3/C                                           this system are not equipped with an automatic 2B21-F037C1       3/C                                           neans of actuation. Exer-tising these valves is 2821-F037C2     3/C                                           achieved by manually push-ing the valve disc to its 2B21-F03701     3/C                                           apen position with a small diameter rud. This testing 2821-F03702     3/C                                             requires the removal of drywell floor grating in 2821-F037El     3/C                                             arder to provide access to l                                                                                                                     these valves. The radi-2B21-F037E2       3/C                                           ation field in this area
RV-28 2821-F037Al 3/C Vacuum Breakers Exercise Quarterly pressure to equalize with drywell pressure as down-for The V.aln omer steam is condensed c
!                                                                                                                      has a high dose rate, and 2821-F037F1       3/C                                           the time required to test the 36 valves is substan-2 021-F037F2     3/C                                             ti al . Considering the interests of the ALARA j                                                     2021-r05/G1       3/c                                             3rinciple, Edison feels that adequate testing of 2 tul-F0 57t;2     5/l:                                           this system is achieved at l
2821-F037A2 3/C Ste:3 r.elief in the suppression pool.
i refueling frequency.
Valve 01scharge The 36 normally closed 2821-F037B1 3/C Lines.
check valves (2 on each downcomer) which comprise 2821-F03782 3/C this system are not equipped with an automatic 2B21-F037C1 3/C neans of actuation. Exer-tising these valves is 2821-F037C2 3/C achieved by manually push-ing the valve disc to its 2B21-F03701 3/C apen position with a small diameter rud. This testing 2821-F03702 3/C requires the removal of drywell floor grating in 2821-F037El 3/C arder to provide access to l
these valves. The radi-2B21-F037E2 3/C ation field in this area has a high dose rate, and 2821-F037F1 3/C the time required to test the 36 valves is substan-2 021-F037F2 3/C ti al.
Considering the interests of the ALARA j
2021-r05/G1 3/c 3rinciple, Edison feels that adequate testing of l
2 tul-F0 57t;2 5/l:
this system is achieved at i refueling frequency.
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Lasone county Nuclear Station Unit 2           PUMP & VALVE TESTING        Pa98 2      3
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                  \-                                                                               RELIEF REQUESTS u$                             E                                 ASME l                                         b             yAty                            FUNCTION       TEST E U RE ENT BASIS FOR RELIEF   ALTERNATIVE TEST zw                        .
Commonwealth Edison PUMP & VALVE TESTING Pa98 2 d
o<o t                                             E 01             02               03               04             05                 #
Lasone county Nuclear Station Unit 2 3
00 l                            HV-28                 Caitinued 2.821-F037K1           3/C 2 021-F037K2           3/C 2 821-F037L1           3/C 2 821-F037L2           3/C 2 821-F037P1           3/C 2 6J1-F037P2           3/C i
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2 B21-F037R1           3/C l                                                   2 B21-F037R2           3/C 2 B21-F037S1           3/C 2 B21-F037S2           3/C 2 B21-F037VI           3/C
RELIEF REQUESTS u$
,                                                  2 821-F037V2           3/C 2 ti/1-F0 5 /tli       3/C 2 021-FOiltIl         3/C Gt r3
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HV-28 Caitinued 2.821-F037K1 3/C 2 021-F037K2 3/C 2 821-F037L1 3/C 2 821-F037L2 3/C 2 821-F037P1 3/C 2 6J1-F037P2 3/C i
2 B21-F037R1 3/C l
2 B21-F037R2 3/C 2 B21-F037S1 3/C 2 B21-F037S2 3/C 2 B21-F037VI 3/C 2 821-F037V2 3/C 2 ti/1-F0 5 /tli 3/C 2 021-FOiltIl 3/C Gt r3


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            '#        LaSalle County Nuclear Station Unit 2
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l                                                                              RELIEF REQUESTS Ei$                                         So                               ASME 33                               PUMP Oft   "O                           SECTION XI y@                           VALVE NO. If         FUNCTION     T EST IlEQUtilEMENT DASIS FOflIlEllEF     ALTEFINATIVE IESI e                                   o<o 00                               01       02           03                 04               05                     06 RV-29     Deleted I
LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Paoo 1
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RELIEF REQUESTS Ei$
So ASME 33 PUMP Oft "O
SECTION XI y@
VALVE NO.
If FUNCTION T EST IlEQUtilEMENT DASIS FOflIlEllEF ALTEFINATIVE IESI e
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O                                             O                                                   O i                                                               Commonwealth Edison
O O
( L' } LasaHe County Nucker Stenon Unit 2                                                                   PUMP & VALVE TESTlNG                 Page     1 of   l b
O i
RELIEF REQUESTS Uib                                                                             b                         ASME 33                                                                 PUMP OH     QO                     SECTION XI y8 a
Commonwealth Edison
VALVE NO. 4 O<
( L' } LasaHe County Nucker Stenon Unit 2 PUMP & VALVE TESTlNG Page 1
FUNCTION     TEST REQUIREMENT         BASIS FOR RELIEF       ALTERNATIVE IESI O
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00                                                               01       02     03                 04                     05                       06 RV-30                                                                 2Cll-D001-126 NC/B             Full stroke and       There are 185 of each of   Individual scram stroke time quarterly the valves listed, i.e.,   insertion tests will 2Cll-D001-127 NC/B             check the fail-safe   one for each of the 185 be performed per the operation of         control rod drives. The Technical Specifi-2C11-D001-114 NC/C             2Cll-D001-126 and     proper operation of each cation frequency.
b RELIEF REQUESTS Uib b
2Cll-D001-127 upon   of these valves is demon-                           t loss of actuator     strated during scram power quarterly       testing. During scram testing each control rod insertion time is measured. The Technical Specifications limit individual scram inser-tion times to specific values. The CRD Scram Test ensures that the above mentioned valves are functioning properly.
ASME 33 PUMP OH QO SECTION XI y8 VALVE NO.
4 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE IESI a
O<O 00 01 02 03 04 05 06 RV-30 2Cll-D001-126 NC/B Full stroke and There are 185 of each of Individual scram stroke time quarterly the valves listed, i.e.,
insertion tests will 2Cll-D001-127 NC/B check the fail-safe one for each of the 185 be performed per the operation of control rod drives. The Technical Specifi-2C11-D001-114 NC/C 2Cll-D001-126 and proper operation of each cation frequency.
2Cll-D001-127 upon of these valves is demon-t loss of actuator strated during scram power quarterly testing.
During scram testing each control rod insertion time is measured.
The Technical Specifications limit individual scram inser-tion times to specific values. The CRD Scram Test ensures that the above mentioned valves are functioning properly.
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O                                                     O                                               O Commonwealth Edison
O O
O Commonwealth Edison
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J LesesleCountyNuclearStationUnit 2         PUMP & VALVE TESTlNG RELIEF REQUESTS Page   1   of       1 II)                                                           ASME 33           PUMPOH         "3 0                           SECTION XI
J LesesleCountyNuclearStationUnit 2 PUMP & VALVE TESTlNG Page 1
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oo           01           02             03                 04                   05                       06 RV-31     2E51-F008         1/A   RCIC Steam Supply   Full stroke and   The RCIC valves are on a   Full stroke exercise Outboard Isolation   stroke time       line which provides steam   and measure stroke quarterly         to the turbine driven RCIC time during cold pump. They are designed     shutdowns.
RELIEF REQUESTS II)
2E51-F063         1/A   RCIC Steam Supply                     to provide a containment Inboard Isolation                     isolation function in the event of a downstream line break. Normally, however, they are left in the open position so that the line will be filled with steam up to the RCIC Turbine Steam Supply Stop Valve E51-F045. Maintaining the turbine supply line in this condition prevents the occurrence of a high pressura water hammer and assure s that the steam can be readily supplied to the turbine when the RCIC system is 1eeded.
ASME 33 PUMPOH "3 0 SECTION XI VALVE NO.
M FUNCTION TEST HEQUIREMENT BASIS FOR HELIEF ALTERNATIVE 1ESI e
04O oo 01 02 03 04 05 06 RV-31 2E51-F008 1/A RCIC Steam Supply Full stroke and The RCIC valves are on a Full stroke exercise Outboard Isolation stroke time line which provides steam and measure stroke quarterly to the turbine driven RCIC time during cold pump. They are designed shutdowns.
2E51-F063 1/A RCIC Steam Supply to provide a containment Inboard Isolation isolation function in the event of a downstream line break. Normally, however, they are left in the open position so that the line will be filled with steam up to the RCIC Turbine Steam Supply Stop Valve E51-F045. Maintaining the turbine supply line in this condition prevents the occurrence of a high pressura water hammer and assure s that the steam can be readily supplied to the turbine when the RCIC system is 1eeded.
Closing these t ntainment isolation valve during reactor power operation renders the RCIC system inoperable during this testing and introduces thc possibility that one, or both of the valves may stick in the closed position.
Closing these t ntainment isolation valve during reactor power operation renders the RCIC system inoperable during this testing and introduces thc possibility that one, or both of the valves may stick in the closed position.
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O                                                         O                                                               O 1   Commonwealth Edison k'C'         LaSaRe County Nucsoar Stauon Unit 2         PUMP & V ALVE TESTING                   Page 1 of 1 RELIEF REQUESTS g                         m $,
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WO ASME 3     PUMP OH                                           SECTION XI idO     VALVE NO.                       FUNCTION     TEST REOUlHEMENT       B ASIS F OR RELIEF                 ALTERNATIVE TEST cp                         u o
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i o0         01             02             03               04                       05                               06 RV-32 2 B21-F032A           1/AC   Feeddater Outboard Exercise Quarterly A test operator is incor-             An attempt will be porated into the design of made to partially Testable Check Valve                                 these valves which is                 stroke these valves capable of closing the               quarterly. A full 2 B21-F0328           1/AC valve through an angle               stroke exercise will of 15*, and the valve is             be perfonned each equipped with two posi-               refueling outage.
Commonwealth Edison k C' LaSaRe County Nucsoar Stauon Unit 2 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS g
m $,
ASME 3
PUMP OH WO SECTION XI idO VALVE NO.
FUNCTION TEST REOUlHEMENT B ASIS F OR RELIEF ALTERNATIVE TEST cp u o o0 01 02 03 04 05 06 i
RV-32 2 B21-F032A 1/AC Feeddater Outboard Exercise Quarterly A test operator is incor-An attempt will be Testable Check porated into the design of made to partially Valve these valves which is stroke these valves capable of closing the quarterly. A full 2 B21-F0328 1/AC valve through an angle stroke exercise will of 15*, and the valve is be perfonned each equipped with two posi-refueling outage.
tion indication lights for reporting disk positions of approximately 85% and 100~. of full open. These valves can be opened by feedwater flow only so a partial stroke exercise is possible only when the reactor is at high power and the feedwater flow has completely opened the disk. A full stroke exercise of these valves may be performed when feedwater flow increases from a no-flow condition to a maximum flow condi-tions following each refueling outage.
tion indication lights for reporting disk positions of approximately 85% and 100~. of full open. These valves can be opened by feedwater flow only so a partial stroke exercise is possible only when the reactor is at high power and the feedwater flow has completely opened the disk. A full stroke exercise of these valves may be performed when feedwater flow increases from a no-flow condition to a maximum flow condi-tions following each refueling outage.
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              ,      O                                                                         O                                                     O g
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Commonwealth Edison Lasalle County Nuclear Station Uni 2
,d Commonwealth Edison V
            '                                                                    PUMP & VALVE TESTING                     Page 1 of 1 RELIEF REQUESTS DO                                             So                             ASME 33     PUMP OH                               $0                           SECilON XI E3ot VALVE NO.                               >U     FUNCilON       TEST f1EOUIIIEMENT       l1 ASIS I OR helle F     ALTERNATIVE TEST Ug 00           01                               02             03               04                         05                       06 RV-33 2821-F013C                               1/8C ADS Relief Valve   Exertise Quarterly Vendor specifications for Perform an 'in place' 2821-F0130                                    "        "                              these ADS safety relief     exercise at each 1/BC                                           valves require steam         refueling outage.
g Lasalle County Nuclear Station Uni 2 PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS DO So ASME 33 PUMP OH
pressure behind the 2821-F013E                               1/BC                                         disk before cycling.
$0 SECilON XI E3 VALVE NO.
Thus, the plant must be 2821-F013R                               1/BC                                         in an operating or
>U FUNCilON TEST f1EOUIIIEMENT l1 ASIS I OR helle F ALTERNATIVE TEST l
                                                                  "                                      startup condition with 2821-F0135                               1/8C           "
Ug ot 00 01 02 03 04 05 06 RV-33 2821-F013C 1/8C ADS Relief Valve Exertise Quarterly Vendor specifications for Perform an 'in place' these ADS safety relief exercise at each 2821-F0130 1/BC valves require steam refueling outage.
the required steam pressure in the main 2B21-F013tl                             1/BC steam lines. These valves 2821-F013V                               1/BC
pressure behind the 2821-F013E 1/BC disk before cycling.
                                                                  "        "                              are located inside the drywell and considering the possibility of a stuck open valve, it is preferable that they be exercised either preceeding or fr r  .owing each refueline 'utage                       '
Thus, the plant must be 2821-F013R 1/BC in an operating or startup condition with 2821-F0135 1/8C the required steam pressure in the main 2B21-F013tl 1/BC steam lines. These valves are located inside the 2821-F013V 1/BC drywell and considering the possibility of a stuck open valve, it is preferable that they be exercised either preceeding or fr.owing r
when the containment atmosphere is de-inerted.
each refueline 'utage when the containment atmosphere is de-inerted.
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O                                                                 O                                                   b 2   Commomwealth Edison LaSane Couny Nucteer Statkm Unn 2                   PUMP & VALVE TESTING                   Page 1 of 1 RELIEF REQUESTS t                                                                       .
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DO                                           N                                     ASME SECilON XI 33                   PUMPOf4                 $O
b 2
Commomwealth Edison LaSane Couny Nucteer Statkm Unn 2 PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS t
DO N
ASME 33 PUMPOf4
$O SECilON XI VALVE NO.
FUNCTION TEST REOUlHEMENT BASIS FOR REL IEF ALTERNATIVE TEST
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VALVE NO.                                FUNCTION        TEST REOUlHEMENT          BASIS FOR REL IEF      ALTERNATIVE TEST 00                               01       02               03               04                       05                       OS RV-34                           All Nuclear               2/AC         Excess Flow Check   Exercise Quarterly, These excess flow check     Full Stroke Exercise Boiler and                             Valves             Leak Test During   valves are designed to       and Leak Test During Reactor Recir-                                             Reactor Refueling automatically close           Reactor Refueling culation Excess                                                               in the event of a down-Flow Check                                                                     stream line rupture in Valves Indi-                                                                   which flow exceeds 6.5 cated in the                                                                   gpm, or if drywell Program                                                                       pressure exceeds 1.69 psig. Upon closing, these valves are designed to allow a controlled leakage of approximately 0.5 gpm. The lines are also provided with flow restricting orifices which would limit the potential offsite exposure to well below the guidelines of 10CFR100. Because                                 ,
00 01 02 03 04 05 OS RV-34 All Nuclear 2/AC Excess Flow Check Exercise Quarterly, These excess flow check Full Stroke Exercise Boiler and Valves Leak Test During valves are designed to and Leak Test During Reactor Recir-Reactor Refueling automatically close Reactor Refueling culation Excess in the event of a down-Flow Check stream line rupture in Valves Indi-which flow exceeds 6.5 cated in the gpm, or if drywell Program pressure exceeds 1.69 psig. Upon closing, these valves are designed to allow a controlled leakage of approximately 0.5 gpm.
exercising these valves requires that recircula-tion flow instrumentation and nuetron monitoring instrumentation be tempor-arily taken out of service ,
The lines are also provided with flow restricting orifices which would limit the potential offsite exposure to well below the guidelines of 10CFR100. Because exercising these valves requires that recircula-tion flow instrumentation and nuetron monitoring instrumentation be tempor-arily taken out of service the optimum time for functional testing these valves is during the routine vessel pressure test performed during each refueling outage.
the optimum time for functional testing these valves is during the routine vessel pressure test performed during each refueling outage.
ea n.
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O                                                                             O                                                                                       O rm
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[ 2_)       Commonwealth Edison PUMP & V ALVE TESTING                 Pago                             1             of 1
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( ] LesonecountyNuclearStationUnit 2 b                                                                             RELIEF REQUESTS Ui                                                                                 ASME 33       PUMP OH                                                                 SECTION XI d"      VALVE NO.
[ 2_)
[$O                        FUNCTION                     TEST HEQUlHEMENT         DASIS FOR HELIEF                                           AliERNATlVE IESI' 5
Commonwealth Edison
00         01       02                                           03               04                       05                                                           06 RV-35 2E22-F005   1/C   HPCS Inboard                                       Exercise           During reactor power                                           Exercise during Testable Check                                     Quarterly           operation, a differential                                     cold shutdowns.
( ] LesonecountyNuclearStationUnit 2 PUMP & V ALVE TESTING Pago 1
pressure of approximately 2E51-F066   1/C   RCIC Inboard                                                           1000 psi exists across Testable Check                                                         these inboard testable check valves. The 2E21-F006   1/C   LPCS Inboard                                                           check valves are Testable Check                                                         equipped with test operators, however, the i                 2E12-F041A   1/C   RHR LPCI Inboard                                                       operators are not able Testable Check                                                         to function with such a high op across the                                                               l' 2E12-F041B   1/C valve. The valves will be exercised against 2E12-F041C   1/C a reduced reactor pressure during cold 2E51-F065     1/C   RCIC Injection                                                         shutdowns.
of 1
b RELIEF REQUESTS Ui ASME
[$O 33 PUMP OH SECTION XI d
VALVE NO.
FUNCTION TEST HEQUlHEMENT DASIS FOR HELIEF AliERNATlVE IESI' 5
00 01 02 03 04 05 06 RV-35 2E22-F005 1/C HPCS Inboard Exercise During reactor power Exercise during Testable Check Quarterly operation, a differential cold shutdowns.
pressure of approximately 2E51-F066 1/C RCIC Inboard 1000 psi exists across Testable Check these inboard testable check valves. The 2E21-F006 1/C LPCS Inboard check valves are Testable Check equipped with test operators, however, the i
2E12-F041A 1/C RHR LPCI Inboard operators are not able Testable Check to function with such a high op across the l
2E12-F041B 1/C valve. The valves will be exercised against 2E12-F041C 1/C a reduced reactor pressure during cold 2E51-F065 1/C RCIC Injection shutdowns.
Outobard Testable Check i st l 's
Outobard Testable Check i st l 's


                                                                                                                                                                                              ~
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O                                                           O                                                                                       O
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: 4)               Commonwealth Edison LaSalle County Nuclear Station Unit 2         PUMP & VALVE TESTING                     Page 1 of 1 RELIEF REQUESTS O                                                                 ASME E$       PUMP OR           MO                               SECTION XI AliERNATIVE TEST dO     VALVE NO.                         FUNCTION       TEST REQUlHEMENT         D ASIS FOR RELIEF Ey                         o o
/ 4)
02               03                 04                       05                                         06 00          01 RV-36                         2E51-F030             2/C     RCIC Suppression   Exercise Quarterly The check valve is partial Perform a full stroke Pool Suction Check                     stroke exercised each       exercise during the Valve                                   quarter by the perfor-       RCIC alternate flow mance of a reduced flow     path   test at each test of the RCIC system     refueling outage and alternate flow path,         partial stroke the The opening of this valve valve each quarter.
Commonwealth Edison LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS O
ASME E$
PUMP OR MO SECTION XI dO VALVE NO.
FUNCTION TEST REQUlHEMENT D ASIS FOR RELIEF AliERNATIVE TEST Ey o o 00 01 02 03 04 05 06 RV-36 2E51-F030 2/C RCIC Suppression Exercise Quarterly The check valve is partial Perform a full stroke Pool Suction Check stroke exercised each exercise during the Valve quarter by the perfor-RCIC alternate flow mance of a reduced flow path test at each test of the RCIC system refueling outage and alternate flow path, partial stroke the The opening of this valve valve each quarter.
is confirmed by the sus-tainence of suction pressure at the RCIC pump.
is confirmed by the sus-tainence of suction pressure at the RCIC pump.
A quarterly full flow test           -
A quarterly full flow test is not performed for the alternate flow path because suppression pool water could potentially contaminate the cycled condensate system.
is not performed for the alternate flow path because suppression pool water could potentially contaminate the cycled condensate system.     Each refueling outage a full flow test of the alternate flow path is conducted at which
Each refueling outage a full flow test of the alternate flow path is conducted at which
                                                                                                              ' time this check valve is full-stroke exer-cised.
' time this check valve is full-stroke exer-cised.
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[( ::: )7 LaSalle County Nuclear Station
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        - ' '                                      Unit PUMP & 2VALVE    TESTING             Pago   1             of   1
[ ::: )7 LaSalle County Nuclear Station Unit 2 Commonwealth Edison
  \/                                               RELIEF REQUESTS IIi                                                     ASME iD       PUMP OH   $O                             SECTION XI VALVE NO.             FUNCTION       TEST HEOUlHEMENT         BASIS FOR HELIEF                 ALTERNAllVE IESI 00           01       02           03                   04                     05                                 06 RV-37   2FC-086       2/A   Rx Well Bulkhead   Full Stroke and     These valves are passive             Leak test during Drain Outboard     Stroke Time         and iocked closed. They               refueling outages.
(
Quarterly, Leak     do perform a containment 2FC-ll3       2/A   Cond. to Refuel     Test During Reactor isolation function and Bellows Inboard     Refueling           will be leak tested.
PUMP & VALVE TESTING Pago 1
However, these valves are 2FC-ll4       2/A   Cond. to Refuel                         not required to change Bellows Outboard                       position during power operation or during an 2FC-ll5       2/A   Rx Head Bulkhead                       emergency situation and Drain Inboard                           therefore, their ability to stroke will not be 2MC027       2/A                                           tested.
of 1
2MC033       2/A 2SA042       2/A 2SA046       2/A t al f3
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_ _ _ _ _ _              _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}
RELIEF REQUESTS IIi ASME iD PUMP OH
$O SECTION XI VALVE NO.
FUNCTION TEST HEOUlHEMENT BASIS FOR HELIEF ALTERNAllVE IESI 00 01 02 03 04 05 06 RV-37 2FC-086 2/A Rx Well Bulkhead Full Stroke and These valves are passive Leak test during Drain Outboard Stroke Time and iocked closed. They refueling outages.
Quarterly, Leak do perform a containment 2FC-ll3 2/A Cond. to Refuel Test During Reactor isolation function and Bellows Inboard Refueling will be leak tested.
However, these valves are 2FC-ll4 2/A Cond. to Refuel not required to change Bellows Outboard position during power operation or during an 2FC-ll5 2/A Rx Head Bulkhead emergency situation and Drain Inboard therefore, their ability to stroke will not be 2MC027 2/A tested.
2MC033 2/A 2SA042 2/A 2SA046 2/A t al f3}}

Latest revision as of 07:25, 14 December 2024

Inservice Insp Program.Part B: Pumps & Valves
ML20082B912
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1983
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20082B864 List:
References
PROC-830831-02, NUDOCS 8311210368
Download: ML20082B912 (143)
v • d • e


Text

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PART B: PUMPS AND VALVES l

l INSERVICE INSPECTION P R 0 G.R A M j

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f LA SALLE COUNTY STATION UNIT 2

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COMM0:lWEALTH EDIS0N COMPANY 9

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AUGUST 31, 1983 1

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l PREPARED BY LA SALLE STATION TECHNICAL STAFF (OPERATIONS)

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LA SALLE PROJECT ENGINEERING GROUP (DESIGN) l I

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PUMP AND VALVE INSERVICE TESTING PLAN TABLE OF CONTENTS Tab Description Table of Contents 1

Inservice Testing Plan - Description 2

3 Fomat Legend and Notes 4

Inservice Testing Plan - Pumps Relief Recuests - Pumps 5

Inservice Testing Plan - Valves 6

Relief Recuests - Valves 7

O

b Commonwealth Edison

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LcSalle County Nuclear Stat 6on Unit 2 INSERVICE TESTING PLAN DESCRIPTION 1.

APPLICABLE ASME CODE INSERVICE TESTING 1.1 The Inservice Testing of equipment in NRC Quality Groups A, B, C, and D+ are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1980 Edition through Winter 1980 Addenda, except where specific written relief from examinations and testings determined to be impractical has been grar.ed by the NRC pursuant to 10 CFR Part 50, Section 50.55 a (g) (6) (i).

Known relief requests from ASME Code Section XI requirements are included in the Inservice Testing Plan.

2.

PUMPS AND VALVES TESTED IN ACCORDANCE WITH ASME SECTION XI SUBSECTIONS IWA, IWP, AND IWV 2.1 All ASME Code Class 1, 2, and 3 safety-related pumps that are provided with an emergency power-source are tested in accordance with ASME Section XI IWP-30J0.

2.2 All ASME Code Class 1, 2, and 3 safety-related valves have been reviewed against the exclusion criteria of ASME Section XI IWV-1200.

2.3 All ASME Code Class 1, 2, and 3 safety-related valves, which are not excluded by Section 2.2 above, are categorized and tested in accordance witn ASME Section XI IWV-2200 and IWV-300 0.

2.4 Inservice Testing boundary classifications for pumps and valves are included in the Preservice Inspection Report as the Preservice Inspection Records Index.

3.

INSERVICE TESTING 3.1 When a pump or valve is determined to be impractical to test in accordance with respective ASME Section XI IWP-3000 or IWV-3000, a specific written relief request from the ASME Code is submitted to the NRC (in accordance with Section 1.1 above).

Each written relief request contains the following information as a minimum.

3.1.1 Identification of pump (s) or valve (s) for which relief is requested.

4 3.1.2 Function of pump (s) or valve (s).

O-3.1.3 ASME Section III Code Class and Category (valves only).

1

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C mmonw; lth Edison LcSdie County Nucle r St tton Unit 2 3.1.4 The specific ASME Code requirement that is determined to be impractical.

3.1.5 LSCS relief justification (s) information fer requesting relief.

3.1.6 Specific alternative test (s) in lieu of ASME Code Section XI requirement (s).

3.3 All records and reports are prepared in accordance with ASME Section XI IWA-6000.

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Commonwealth Edison

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tcsaue county Nuclear Station Unit 2 i

INSERVICE TESTING PLAN FORMAT LEGDO AQ NOTES

1. AS*E CLASS 1, 2, AND 3 PNS FIELD DESCRIDTION 00 PM tO4EER Pump numoer as used on the P&ID.

01 PM NAE Pump word description and name.

ASE Section III Code Classification (1, 2, or 3).

02 CLASS 03 P&ID NO.

Piping and Instrumentation Drawing Nuncer. All drawing nurters are prefixed with "M".

Sheet nuncers follow the drawing numoer.

04 COORDINATES Pump coordinates on P&ID.

05 SPEED Speed of guno to be measured. N/ A Not Applicable. All the CumDs with N/A in the steed colunn are either syncnorous or incuction me ::

driven and do not require speed measurements.

06 IM.ET PRESS Inlet pressure of gump to be measured.

07 01FF. PRESS.

Differential pressure of cump to be measureo, N/A, Not applicable for positive displarement gumps.

08 FLOW RATE Flow rate of gump to be measured 09 VIBRATION Vibration amplitude of rump to be measured. - See RP-CA.

10 BEARING TEW.

Bearing temperature of pump to De measured - See RP-Ol.

11 TEST INTERVAL Testing interval of pumps and any Relief Requests. Relief nuncers are prefixed by "RD" for pumps ("RV" for valves).

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Commonwealth Edison LcSado County Nuclear Station Unit 2 l

II ASE CLASS 1, 2, AND 3 VALVES FIELD DESCRIPTION f

00 VALVE RMER Valve number as used on the P&ID.

01 SIZE Nominal size of valve in inches.

02 P&ID PO.

Piping and Instrumentation Drawing Mscer. All drawing nureers are prefixed with "M".

Sheet nureers follow the drawing nureer.

03 COORDINATES Valve location on P&ID.

04 CLASS CATECORY ASE Section III Code Classification (1, 2, or 3) followed by the Valve Category ( A, B, C, 0, OR E). tC is used for valves which do not have an ASE Section III Class.

05 VALVE TYPE AG Angle BL Ball EF Butterfly CNV Control Valve 08 Dott:le Block

(

EFC Excess Flow Check i

FCV Flow Control Valve GB Globe GT Gate q

WC Manual Flow Control PN Needle Valve NSC Non-Slam Check P

Plug PG Packless Globe PRV Pressure Regulator Valve RV Relief Valve S

Safety SRV Safety Relief Valve SC Stop Check CV Check Valve 06 ACTUATOR TYPE A0 Air Operator AS Air Spring Ex Explosive M

Manual MO Motor Operated SO Solenoid Operated SP Spring 07 VALVE POSITIL"!

C Normally Closed 0

Normally Open L.O. Locked Open L.C. Locked Closed O

l Page 2

Commonwraith Edison '

tcsaise county Nuclear Station Unit 2 II ASE CLASS 1, 2, APO 3 VALVES - CON'T.

]

FIELD DESCRIPTION 08 TEST E

Exercise FS Full Stroke PS Part Str H Exercise ST Stroke Time LV Locked Valve (Administrative controls, No Senedule)

RV Verify set points in accordance with IW-3510 FC Fire Explosive Charge LT Leak Test in Accordance with FSAR Table 6.2-21 PIT Position Indiction check FST Fail Safe Test 09 TEST SCHEDLLE Q

Quarterly, 92 Days CS Cold Shutdown (IST), See Note (3)

RR Reactor Refueling EV IW-3610 10 Max. STROKE TIE The maxinum allowed stroke time for valves requiring stroke time measurement 11 RELIEr REQJEST A relief request nuceer when a scecific code requirement is determined to be impractical.

Relief recuest numbers for valves are prefixed with "RV". ("RP" for cumps) 12 ACTIVE OR PASSIVE Active "A" valves are valves which are recuired to change position to accomplish a specific function. Passive"P" valves are valves which are not recuired to change position to accomclism a specific fmetion.

13 REMMKS General valve descriptions or comments.

III NOTES (1) In accordance with AST Section XI IW-3410 (b) (1) and IW-3520 (b) these valves are exercised to the position required to ful'ill their function during Cold Shutcown or Reactor Refueling as apolicaole.

(2) Safety valves and relief valves are tested during Reactor Refueling; however, individual valves are scheduled inaccordance witn AS{ Section XI Table IW-3510-1.

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d Commonw cith Edison

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Lcs ile county Nuclear Station Unit 2 III NOTES - CON'T O

V (3) Inservice valve testing at cold shutdom is defined as:

Valve testing unicn conmeces not later than forty eipt (48) hours after cold snutcom mc continues mtil reovired testing is completed or plant start-up, unicnever occurs first. Completim of all reovirac valve testing is not a remisite to pimt start-up. valve testing which is not completed di. iring a cold shutcom will oe performed curing suosecuent cold shutcoms to meet tne code specified testing requiremets. to valve will De testec more ofte tnm cnce every 90 days.

l Also, some valves require entry into the ecntainmot to perform the test, suen valvss will only be testec men the crywell is de-inertec.

Note:

It is expected that the required inservice valve testing will normally oe completec in 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> following colo snutcom.

However, congleticn of all valve testing curing colo shutcom is not required if plot operating etnditims will not permit tne testing of specific valves.

In tne event that a valve must be declared inoperaole as a result of cole snutcom testing ( AS{ Coce, Sectim XI, IW-3410 (g) a,c IW-3520 (c))

the applicaole unit start-up limitatims will be as stated in the tecnincal specificaticn, limiting cmcitims for operaticns.

(4) 10 CFR 50 Appendix J Type C Test.

GU (5) Reactor Coolant System Pressure Isolation Valves, leak tested per Tech.

Spec. 4.4.3.2.2.

(6) Test pressure is not in the same direction as the pressure existing when the valve is required to perform the safety function as required by Appendix J to 10 CFR 50.

Either manufacturers' test data, site test results, or justification (e.g., reverse test pressure tending to lif t disk from seat) will be available on site to verify that testing in the reverse direction will provide either equivalent or more conservative results.

(From FSAR Table 6.2-21 Note 20).

(7) These lines have been evaluated to an acceptable alternative design basis other than that specifically listed in GDC 56. This alternate basis is found in SRP 6.2.4.II.3.e, and the evaluation to the criteria specified therein is as follows:

a.

All lines are in engineered safety feature or engineered safety feature-related systems.

b.

System reliability can readily be seen to be greater when only a single valve is provided, since the addition of another valve in series provides an additional potential point of failure, and, in the case of relief valve discharge lines, the installation of an additional valve is actually prohibited by the ASME Code.

O Page 4

N 3)

Commonwealth Edison V

g LcSalle County Nuclear Station Unit 2 O

III NOTES - CON'T i

c.

The systems are closed outside containment.

d.

A single active failure of these ESF systems can be accomodated.

The systems outside containment are protected from missiles e.

consistent with their classification as ESF systems.

f.

The systems are designed to Seismic Category I standards.

g.

The systems are classified as Safety Class 2.

h.

The design ratings of these systems meet or exceed those specified for the primary containment, i.

The leaktightness of these systems is assured by normal surveillance, inservice testing and leak detection monitoring.

j.

The single valve on these lines is located outside containment.

(From FSAR Table 6.2-21, Note 28).

(8) These lines are always filled with water on the outboard side of the containment thereby forming a water seal.

They are maintained at a N

pressure that is always higher than primary containment pressure by water leg pumps; thus, precluding any outleakage from primary cantain-ment.

However, even if outleakage did occur, it would be into an ESF system which forms a closed loop outside primary containment.

Thus, any leakage from primary containment would return to primary contain-ment through this closed loop.

These valves are under continuous leakage test because they are always subjected to a differential pressure acting across the seat.

Leakage through these valves is continuously-monitored by the pressure switches in the pump discharge lines, which have a low alarm setpoint in the main control room.

Even though a special leakage test is not merited on these valves for the reasons discussed above, a system leakage test to meet the l

requirements of Type C testing and as hereinafter described, will be l

performed to ensure the leak-tightnesses of the ECCS and RCIC systems.

The systems will be pressurized with water to a minimum pressure of 39.6 psig (peak drywell accident pressure) with the system totally isolated from primary containment. A leakage rate for the entire system will then be determined and compared to an acceptance limit based on site boundary dose considerations (iO CFR 100:

ECCS subsystem leakage not to exceed I gpm times number of valves in the subsystem tested).

(From FSAR Table 6.2-71. Note 29).

Page 5

fd } Commonwealth Edison L-sene county Nuclear Statkm Unit 2 III NOTES - CON'T (9) To satisfy the requirements of General Design Criterion 56 and to l

perform their function, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).

These lines are Seismic Category I and terminate in instruments that are Seismic Category I.

They are provided with manual isolation valvcs and excess flow check valves.

The integrity of these lines is to be tested during the Type "A" Test.

These lines and their associated instruments will be pressurized to P -

a Surveillance inspections will be performed to ensure the leaktight integrity of these lines and their associated instrunents.

Additional inservice inspection is included in the Technical Specifications.

This inservice inspection verifies the function of the excess flow check valves.

Isolation is provided by the excess flow check valve.

In the event of a line rupture downstream of the check valve and a containment pressure above 2 psig, this valve would close to limit the amount of leakage.

(From FSAR Table 6.2-21, Jiote 32).

The exercise and leak test procedure confirms valve operability through a visual observation of a marked decrease in the instrument lir.e's flow rate.

(10) To perform their function and to satisfy the requirements of General Design Criterion 55, these instrument lines have been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11).

These lines are Seismic Category I and terminate in instruments that are Seismic Category I.

They are provided with flow-restricting orifices, manual isolation valves, and excess flow check valves.

The flow-restricting orifice is sized to assure that in the event. of a postulated failure of the piping or component, the potential offsite exposure will be substantially below the guidelines of 10 CFR 100.

Isolation is provided by the excess flow check valve.

In the' event of a line rupture downstream of the check valves, this valve would close to limit the amount of leakage.

The-integrity of these lines will be tested during the Type "A" Test.

Surveillance inspections will be performed to ensure the leak-tight integrity of.these lines and their associated instruments.

Addi-tional inservice inst action is included in' the Technical Specifications.

This inservice inspection verifies the function of the excess flow check valves (From FSAJ. Table 6.2-21, Note 33).

The exercise and leak test procedure-confirms valve operability through a visual observation of a marked decrease in the instrument line's flow p

rate.

o Page 6

e )7 usene counpudeer smuon unn 2 Commonwealth Edison kV

'V III NOTES - CON'T O (11)

The ECCS and RCIC suction lines are normally filled with water on both the inboard and outboard side cf containment, thereby forming a water seal to the containment environment. The valves are open during post-LOCA conditions to supply a water source for the ECCS pumps.

Since a break in an ECCS line need not be considered in conjunction with a DBA, the only possible situation requiring one of these valves to be closed during a DBA is An unacceptable leakage in an ECCS.

However, because these ECCS systems are constantly monitored for excessive leakage, this is not a credible event for design.

However, at the insistence of the NRC, these valves will receive a leakage test as part of the low pressure system leakage test described in Note 29.

(From FSAR Table 6.2-21, Note 39).

(12) The leakages through the Main Steamline valves will not be included in establishing the acceptance limits for the combined leakage in accordance with the 10 CFR 50, Appendix J, Type B and C tests.

Because the Mair Steamlines are provided with a leakage control system, the leakage through these valves will not be added into the combined leakage rate. This exclusion is in accordance with Article Ill.C.3 of 10 CFR 50, Appendix J.

(From FSAR Table 6.2-21, Note 30).

(13) These penetrations are provided with removable spools outboard of the outboard isolation valve.

During operation, these lines will be

(]

blind flanged using a double 0-ring and type-B leak tested.

In addition, G

the packing of these isolation valves will be soap bubble tested to ensure insignificant or no leakage at containment test pressure each refueling outage.

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Commonwealth Edison

[ C INSERVICE TESTING PLAN

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t +/ LaSalle County Nuclear Station Unit 2 Systern DG - Diesel Generator 2

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P,U MPS Pago 1 of 1

l PUMP PUMP P&lD NUMOLR tJAME CLASS NO COOR itai t r oir r e a ow viustA-orAlitt40 T EST lit iLilVAL SPELD Pfif SS PliiSS IIAI E 1807J IE MP 00 01 02 03 04 05 06 07 08 09 10 11 2DG-OlP DG Cooling 3

134-1 7D N/A YES Y.ES YES RP-04 RP-01 Quarterly Pump "2A" 4

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\\v J LaSalle County Nuclear Station Unit 2 Systern D0 - Diesel Oil v

P,U MPS Pago 1 of 1

N TEST PAHAMETERS TO DE MEASURED PUMP PUMP P&tD NUMBER PJA M E CLASS NO COOH.

INl E T Dif f i t OW Vitill A. ' UEAf ter4G T EST iff illWAL SPE LD PHESS PitiSS IIA T E IlON TEMP 00 01 02 03 04 05 06 07 08 09 10 11 2000lP Diesel Oil 3

132 6C N/A RP-05 RP-05 RP-05 RP-04 RP-01 Quarter.ly Pump 2A 3

20002P HPCS Diesel 3

132 4C N/A RP-05 RP-05 RP-05 RP-04 RP-01 Quarterly Oil Pump 28 l

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LaSalle County Nuclear Station Unit 2 Systern FC - Fuel Pool Cooling sL/

P, UMPS page 1 or 1

TEST PARAMETEllS TO DE MEASURED FuMP Puup PalD lPaliSS PJUMilLR PJAME CLASS TJO COOH etai t. :

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urAltitui T EST ite IL HVAt SPELD PHESS IIA T E IlOPJ ILMP 00 01 02 03 04 05 06 0/

08 09 10 11 2FC03PA Fuel Pool 3

134-2 7E N/A YES YES YES RP-04 RP-01 Quarterly Emergency Make-up Pump 2A 4

2FC03PB Fuel Pool 3

134-1 7C N/A YES YES YES RP-04 RP-01 Quarterly Emergency Make-up Pump 2B N

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uEAlutui TEST If4 TLilVAL SPEID PHfSS PttiSS

  1. 1AIE Ilott il MP 00 01 02 03 04 05 06 07 08 09 10 1I 2E22-C001 HPCS Pump 2

141 2B N/A RP-09 YES YES RP-04 RP-01 Quarterly 2E22-C003 HPCS Water 2

141 4D N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump 2E22-C002 HPCS DG 3

134-1 78 N/A YES YES YES RP-04 RP-01 Quarterly Pump 2A 1

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PilMP PUMP P&lD NUMOLH HAME CLASS l NO

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ulAlutui T EST itJ ILi4 VAL SPELD Pfit SS PitLSS IIAIF IlON TE MP 00 01 02 OJ 01 05 06 07 08 09 10 11 2C41-C001A SBLC Pump 2

145 4C N/A RP-06 RP-06 YES PR-04 RP-01 Quarterly 2A 2C41-C001B SBLC Pump 2

145 4B N/A RP-06 RP-06 Yes RP-04 RP-01 Quarterly 2B 4

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v PUMP PUMP PalD NUMBER tJA M E CLASS 14 0 COOft ritt ti ti ow v stA-0 Anirju T EST irit L HVAL 00 01 02 03 04 05 06 07 08 09 10 11 2E12-C002A RHR Pump 2A 2

142-1 SA N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C002B RHR Pump 28 2

142-2 4B N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C002C RHR Pump 2C 2

142-3 SB N/A YES YES YES RP-04 RP-01 Quarterly 2E12-C003 RHR Water 2

142-3 7A N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump 2E12-C300A RHR Service 3

134-2 7F, N/A YES YES YES RP-04 RP-01 Quarterly Water Pump 2A 2E12-C3008 RHR Servii.e 3

134-2 7C N/A YES YES YES RP-04 RP-01 Quarterly Water Pump 28 2E12-C3000 RHR Service 3

134-1.

7E N/A YES YES YES RP-04 RP-01 Quarterly Water Pump l

2C l134-1 2E12-C3000 RHR Service 3

7F N/A YES YES YES RP-04 RP-01 Quarterly Water Pump g

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urAsurni TEST irilLHVAL SPELD PliESS PfliSS itAIE IlOrd TEMP 00 01 02 03 04 05 06 07 08 09 to 11 2E51-C001 RCIC Pump 2

147-2 2C YES YES Y:S YES RP-04 RP-01 Quarterly 2E51-C003 RCIC Water 2

147-2 4A N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump i

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140 30 N/A YES Y.ES YES RP-04 RP-01 Quarterly 2E21-0002 LPCS Water 2

140 3B N/A YES YES RP-02 RP-04 RP-01 Quarterly Leg Pump 4

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Commonwealth Edison L'

t asane county Nucesar station unit 2 PUMP & VALVE TESTING Page 2

of 2

RELIEF REQUESTS Iii 5

ASME

-'i 3 PUMPGil QO SECTION XI VALVE NO.

FUNCTION TEST REQUlf tEMENT DASIS FOilItEllEF ALIEftNATIVE IEST o

00 01 02 03 04 05 06 RP-01 Continued not always predict such problems. An increase in bearing temperature most often does not occur until the bearing has I

deteriorated to a point 4

where additional pump damage may occur.

Bearing temperatures are also affected by the temperatures of the meditm being panped, which could fleid misleading msults.

Vibration madings are not affected by tht!

, temperature of the medium being psnped, tius tie readings are more consis-tent.

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SJ Commonwealth Edison PUMP & V ALVE TESTING Page 1

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tasane county Nucknar Station Unit 2 j

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RELIEF REQUESTS i

DE N

ASME 33 PUMP OR yO SECTION XI VALVE NO.

>f FUNCTION TEST REOUIREMENT BASIS FOR REllEF ALTERN ATIVE TEST O<

i g

U 00 01 02 03 04 05 06 IP-02 WCS water Leg Pressure IW-3100 Flow is not a sitfificant Pressure Maintenance Pump Maintenance Flow Measurement desigi parameter for the of ECCS discharge 2E22-C003 2

water leg panps. iteir lines within primary purpose is to allowable pressure j

i LPCS water Le9 maintain the ECCS pump limits.

Punp discharge lines filled 2E21-C002 2

and pressurized.

The satisfactory performance RitR water Leg of this function is mani-Pung fested by the maintenance l

2E12-C003 2

of tie discharge line l

within allowable stanrthy pressure limits.

1 RCIC Water 2

1herefore, there is Leg Pump actually no flow criteria 2E51-C003 j

on the pump that coulti be i

used to determine wiether the pump is satisfactorily performing its safety I

function.

Therefore, j

because the desity basis of the waterleg panps is j

maintenance of pressure, i

j this is the parameter lint is considered for J

inservice testlinj.

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Commonwealth Edison

~

LaSane County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1

of 1

\\

RELIEF REQUESTS Ili{0 mb ASME 73 PUMPOil "O

SECTION XI FUNCTION TEST IIEOUlFlEMENT BASIS FOIL llELIEF ALIEflNATiVE IESI o$

y@

VALVE NO.

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00 01 02 03 04 05 06 i

RP-03 Deleted i

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[ 73:_ _ ) Commonwealth Edison (V '7 LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTlNG Pago I

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A>

RELIEF REQUESTS Ei ASME 3 -)

PUMP OR

$O SECTION XI VALVE NO.

FUNCTION TEST HEOUlilEMENT BASIS FOR HELIEF ALIERNATIVE IESI 00 of 02 03 04 05 06 RP-04 All Pumps N/A Table IWP-3100-2 Depending on the pump type, Computer trending vibration will either be will use the past measured in mils or in several vibration inches per second. A more values to determine informative reading is ob-an Alert and a tained using vibration Required Action Range.

velocity equipment, however,The IRD General the limited bearing access-- Machinery Vibration ability on La Salle's ver-Severity Chart will tically oriented pumps be used as a further and positive displacement

aid, pumps reduce the accuracy of this relatively bulky equipment.

In these cases, a measurement of vibration amplitude will be taken.

Whichever method is used, fixed limiting values for the Alert and Required Action Ranges will not be used as a trigger for maintenance operations because each pump operates satisfactorily at a unique vibration level due to variables such as restraid orientation, pump size, pump type, and pump speed.

Alert and Required Action Range limits for any par-ticular pump will be based u ta

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Commonwealth Edison y ' >] LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 2

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RELIEF REQUESTS e

Ui$

Ed ASME 13 PUMPOlt

$O SECTION XI VALVE NO.

_sf FUNC110N T EST IlEOulflEMENT BASIS F OR REL IEF ALIEf ttJATIVE ICSI 04 g

o 00 01 02 03 04 05 06 RP-04 All Pumps N/A TABLE IWP-3100-2 on its past vibration (Continued) history. As a further aid, the IRD Mechanalysis Chart of vibration severity wil also be used as a guide in rating pump performance.

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Commonwealth Edison "J LaSalle County Nuclear Station Unit 2 PUMP & VALVE TEST 1NG Pago 1

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RELIEF REQUESTS II) 5 ASME 33 PUMP OH

$0 SECTION XI VALVE NO.

FUNCTION TEST HEOUlHEMENT DASIS IOH HEllEF AliEHNATlVE IESI 00 01 02 03 04 05 06 RP-05 2D00lP 3

Transfer Fuel Oil Measure Pump Inlet These pumps are required From the Diesel Oil Pressure, Differ-to transfer fuel oil from 20002P 3

Storage Tanks to ential Pressure, the storage tank to the the Day Tanks and Flow Rate day tank at a rate of at least 30 gpm, which is approximately ten times the diesel engine's consumption rate.

They are not required to pro-vide a reproduceable suction on differential pressure.

In fact, pressure measurements may vary considerably depend-ing on the suction head in the diesel oil storage tank. The flow rate is verified to be above 30 gpm by measuring the time required for bulk transfer of fuel oil to the day tank.

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[mSD) Commonwealth Edison t

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'-f 7 LaSane County Nuclear Stapon Unit 2 PUMP & VALVE TESTlNG Pago 1

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RELIEF REQUESTS r

Ui$

N ASME 33 PUMP Oft

$0 SECTION XI VALVE NO.

FUNCTION TEST HEOUlHEMENT UASIS FOR HEllEF ALIEHNATIVE lESI 00 01 02 03 04 05 06 RP-06 2C41-C001A 2

Measure Pump Inlet It is impractical to Measure pump discharge Pressure measure standby liquid pressure and flow 2C41-C001B 2

control pump inlet rate quarterly.

pressure in accordance with Section XI require-ments.

During pump test-ing, the pump suction is from a test tank rather than the main standby liquid control tank.

For these positive dis-placement pumps, the measurment of inlet pressure is not cirtical in judging pump perfor-mance. Measuring the discharge pressure and the flow rate is adequate to detect changes in the hydraulic characteristics of the pumps.

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Commonwealth Edison L'

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LaSalle County Nuclear Station tinit 2 PUMP & VALVE TESTlNG Pago 1

of 1

3 RELIEF REQUESTS p

I Ui$

bO ASME

~.i 3 PUMP OFI

$O SECTION XI y8 VALVE NO.

J"O FUNCTION TEST flEQUlflEMENT DASIS FOIL FlELIEF ALIEf1tJATI /E IESI a

O<O 00 01 02 03 04 05 66 RP-07 Deleted t

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Commonwealth Edison PUMP & V ALVE TESTlNG Pane 1 0f 1

q LaSeHe County Nuclear Station Unit 2 RELIEF REQUESTS 9d N

ASME 33 PUMPOH

$0 SECTION XI VALVE NO.

FUNCTION TEST flEOUlflEMENT HASIS F Of1 f1Et IEF ALTEllNATIVE TEST 00 Ol 02 03 04 05 06 RP-08 RHR Pump A Remove Decay Heat IWP-4120 requires The reference values for Since inlet pressure 2E12-C002A 2

that the full scale the inlet pressures of varies on the RHR range of pump in-RHR Pumps A, B and C are pumps, gages with j

RHR Pump B Remove Decay Heat struments shall be all (Pi>7.5 psig). The larger scale ranges 2L12-C0028 2

three times the reference value for the are required to reference value or inlet pressure of the accomodate pressure l

RHR Pur.1p C t Remove Decay Heat less.

RHR water len pump is rises of pump (Pi>8 psig).

The full suction.

2E12-C002C 2

scaTe rance of the RHR Water leg Pressure Mainten-inlet pressure gaaes for all four pumps reads Pump 2

ance 0-250 psio.

The inlet pressure for these pumps 2E12-C003 may attain a maximum pressure of 200 psig and therefore the pumps require a cane with a laraer scale range.

4 I

i s.1 13

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Commonwealth Edison LaSal% County Nuclear Station Unit 2 PUMP & V AI.VE TESTING Page 1 of 1

RELIEF REQUESTS s

DO EO ASME

$[0 SECTION XI

~3 PUMP OH FUNCTION TEST HEOtllHEMENT DASIS FOR REllEF Alif RNATIVE TEST yO VALVE NO.

g 5

00 01 02 03 04 05 OS RP-09 HPCS Pump 2

ECCS Pump IWP 4120 requires The reference value for Due to pressure IE22-C001 that the full scale the inlet pressure of the spikes, a gage with range of pump in-HPCS pumps is 8 psig a larger scale will struments shall be when drawing water from be used to measure three times the the suppression pool and inlet pressure.

reference value or 17.5 psig when drawing

less, water from the condensate storage tank. The full scale range of the inlet pressure gage is -30" Hg to 100 psiq, or about a 115 psig range.

The ranae is necessary due to the configuration of this system. When the HPCS pump is beino stopped, i

there is a spike in the suction pressure.

Such a pressure spike causes a suction pressure indicator with a smaller range to go out of calibration, llence, a suction pressure gage with a larger scale is needed to enable the qaqe to remain in calibration for the mea;urement of suction pre;sure of the llPCS pump.

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O LaSalle County Nucle.v Stanon Unit 2 Commonwealth Edison

!NSERVICE TESTING PLAN system CM-Containment Monitoring P8G*

1 2

VALVES

/

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01 / 02 03, 04 5

06 07 08 09 to 11 12 [

00 13 2CM017A

.5 158-1 F6 2/A GB

$0 0

FS, Q

5 RV-02 A

(See Note 4,6)

LT RR RV-19 2CM017B

.5 158-2 F6 2/A GB SO O

FS, 0

5 RV-02 A

(See Note 4)

LT RR RV-19 2CM018A

.5 158-1 F6 2/A G8 50 0

FS, Q

5 RV-02 A

(See Note 4,6)

LT RR RV-19 2CM018B

.5 15G-2 F6 2/A GB SO 0

FS, Q

5 RV-02 A

(See Note 4)

LT RR RV-19 2CM019A

.5 158-1 B6 2/A GB SO O

FS, Q

5 RV-02 A

(See Note 4)

LT RR RV-19 2CM019B

.5 158-2 66 2/A GB SO O

FS, 0

5 R t.'- 02 A

(See Note 4)

LT RR RV-19 2CM020A

.5 158-1 86 2/A GB S0 0

FS, 0

5 RV-02 A

(See Note 4,6)

LT RR RV-19 2CM020B

.5 158-2 R6 2/A GB 10 0

FS, 0

5 RV-02 A

(See Note 4,6)

LT RR RV-19 2CM021B

.5 158-2 F3 2/3 ca,l 50 C

FS n

5 RV-02 A

2CM022A

.5 158-1 F3

  • 2/B GB 50 C

rs 0

5 RV-02 A

GE-T 2 -1180

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OLa e Co n y Nucl a Stano Unit 2 INSERVICE TESTING PLAN system CM-Containment Monitoring VALVES

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00 01 02 03 4 / 05 06 07 08 09 10 11 12 13 1SS-2l F2 ' 2/8 2CM0238

.5 GB S0 C

FS Q

5 RV-02 A

2CM024A

.5 158-1 E2 2/B GB S0 C

FS Q

5 RV-02 A

2CM025A

.5 158-1 B3 2/B GB S0 C

FS Q

5 RY-02 A

2CM026B

.5 158-2 B3 2/B GB S0 C

FS 0

5 RV-02 A

2CM031 1.5 158-4 3 C6 2/A G8 SO O

FS, Q

5 RV-02 A

(See Note 4,6)

LT RR RV-19 2CM032 1.5 158-4 C6 2/A GB SO O

FS, 0

5 RV-02 A

(See Note 4)

LT RR RV-19 2CM033 1.5 158-4 B7 2/A GB S0 0

FS, 0

5 RV-02 A

(See Note 4)

LT RR RV-19 2CM034 1.5 158-4 B7 2/A GB 50 0

FS, Q

5 RV-02 A

(See Note 4,6)

LT RR RV-19 I

GE-T2 1180

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or 1 VALVES h

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A 0

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 j

f 2DG-002 10 l134-01 D6 3/C NSC C

E Q

A Diesel Cooling Water Pump Discharge Check 2DG-011 4

134-01 C6 3/B GT M0 C

FS Q

RV-01 A

Diesel Cooling Water Strainer 2DG-034

.75 134-01 C4 3/C RV C

RV RR A

Diesel Generator Cooler I.

2A Relief (See Note 2) 2DG-035 1.5 134-02 E4 3/B Git M0 0

FS,ST Q

45 A

LPCS Pump Cooler Control C

E Q

A LPCS Pump Motor Cooler 2DG-036 1.5 134-02 E2 3/C CV Outlet Check GE-T 2 -1180

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I.aSal e County Nuclear Station Unit 2 Commonwealth Edison D0 - Diesel Oi1 INSERVICE TEST 1NG PL AN system

"*8' I

'I VALVES 9

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g-cs 00 01 02 / 03 / 04 0

06 07 08 09 10 11 12 13 2D0002 1.5 132 E6 3/C NSCl-C E

Q A

Unit 2A DG Fuel Oil Transfer Pump Discharge Check 2D0004 1.5 132 E6 3/B GB S0 C

FS Q

RV-02 A

Unit 2 Day Tank Inlet Stop Valve 200012 1.5 132 E4 3/C NSC C

E Q

A Unit 2B DG Fuel Oil l

Transfer Pump Discharge Check 200014 1.5 132 E4 3/8 GB S0 C

FS Q

RV-02 A

Unit 2B Day Tank Inlet Stop Valve 200024 2

132 82 3/B GB S0 C

FS Q

RV-02 A

Diesel Fire Fuel Transfer Pump Inlet Stop I

GE-T 2 - 1180

m s

A

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OLa e Co n y Nuct a Sta on!Nt 2 INSERVICE TESTING PLAN system FC-Fuel Pool Cooling

"*9' I

' I VALVES

/

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c*

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o g

A e.

05 [C6 00 01 02 03 04 07 08 09 10 11 12 13 2FC-044A 6

134-02 E6 3/C NSC C

E Q

A Fuel Pool Emergency Make Up Pump 2A Discharge Check 2FC-044B 6

134-01 C6 3/C NSC C

E Q

A Fuel Pool Emergency Make Up Pump 2B Discharge Check 2FC-105A 1x.75 137-1 D4 3/C RV C

RV RR A

Fuel Pool Cooling Heat Exchanger Relief (See g

Note 2) 2FC-1058 lx.75 137-1 D3 3/C RV C

RV RR A

Fuel Pool Cooling Heat Exchan er Relief (see Note 2 2FC-086 10 144-1 C2 2/A G1 M

C LT RR RV-19 P

Rx well bulkhead drain RV-37 outboard (M65)(See Note 4) 2FC-113 2

144-1 D2 2/A GB M

C LT RR RV-19 P

Cond. to refuel bellows RV-37 inboard (M59)(See Note 4,6) 2FC-ll4 2

144-1 D2 2/A GB M

C LT RR RV-19 P

Cond. to refuel bellows RV-37 outboard (M59)(See Note 4,6) 2FC-115 10 144-1 C2 2/A GT M

C LT RR RV-19 P

Rx well(M65MSee Note 4.0 bulkhead drain RV-37 inboard

)

GE-T 2 -1180

@ LaSalle County Nuclear Station Unit 2 Commonwealth Edison 1NSERVICE TESTlNG PLAN sysi m FW-Feedwater l

I VALVES b

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c d

9 O

8 g

q g

g g

/ 03 04 / 05 06 07 08 09 to 11 12 /

13 00 ot 02 1821-F010A 24 118 A6 1/AC NSC 0

E RR RV-06 A

Rx Feedwater Line Ovrck LT I!V-19 Valve (M-5)(See Note 1,4) 1821-F0108 24 118 C6 1/AC HSC 0

E RR IN-06 A

Rx Feedwater Line Ch ck i

LT l'V-19 Valve (M-6)(See Note 1,4) 1821-F032A 24 118 A6 t/AC NSC A0 0

E RR FN-32 A

Rx Feedwater Line Dvck LT RR ny_g9 Valve (M-5)(See Note 1,4)

PIT RR IB21-F032B 24 118 C6 1/AC NT A0 0

E RR RV-32 A

Rx Feedwater Line Check l

FN-19 Valve (M-6)(See Hote 1,4) p 1021-F065A 24 118 A5 2/A GT K)

O FS,ST CS RV-07 A

Rx Feedwater Isolatirm LT RR 132 IN-19 Valve (M-5)(See Note i,4)

PIT RR l

IB21-F065B 24 118 C5 2/A GT

,MO O

FS,ST CS RV-07 A

Rx Feedwater Isolattr*

LT RR 132 IN-19 Valve (M-6)(See Note i 4)

PIT RR e

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!NSERVICE TESTING PLAN system liG - Cont. Combustible Gas "80' l

' 2 Control VALVES

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00 01 02 03 / 04 05/06 07 08 09 10 11 12 13 2HG001A 4

130-2 F7 2/A GT M0 C

FS,ST Q

22 RV-19 A

Upsteam HG Stop LT RR (M-53)(See Note 4,6) 2HG001B 4

130-2 E7 2/A GT M0 C

FS,ST Q

22 RV-19 A

Upsteam HG Stop LT RR (M-33)(See Note 4,6) 2HG002A 4

130-2 F6 2/A GC M0 C

FS,ST Q

66 RV-19 A

Downsteam G Stop LT A

(M-53)(See Note 4) 2HG002B 4

130-2 E6 2/A GB M0 C

FS,ST iQ 66 RV-19 A

Downsteam HG Stop LT RR (M-33)(See Note 4) 2HG003 6

130-2' B6 2/5 GT M0 0

FS,ST Q

60 RV-19 A

Unit 2 Outlet to Unit 2 D/W l

2HG005A 6

130-2 87 2/A

' GT M0 C

FS,ST l0 33 RV-19 A

Unit 2 Recombiner RTN LT Downsteam Stop (M-102)

(See Note 4,6)

I 2HG005B 6

130-2 A7 2/A GT M0 C

FS,ST Q

33 RV-19 A

Unit 1 Recombiner RTN LT RR Downstream Stop (M-95)

(See Note 4,6) 2HG006A 6

130-2 B6, 2/A CT M0 C

FS,ST Q

33 RV-19 A

Unit 2 Recombiner RTN j

LT RR Upstream Stop (M-102)

(See Note 4) 1 I

GE-T 2 -1180

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v OLa lNSERVICE TESTING PLAN iG-Cont. Combustible Gas Control I e Coun y Nuct a Ste o. On 12 gstem VALVES l

h 4

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g 00 01 02

/ 04 05 / 06, 07 08 09 10 11 12 13 I

i 2HG006B 6

130-2 A6 i ?/ A GT MJ C

FS,ST Q

33 RV-19 A

Unit 1 Recombiner RTN LT RR Upstream Stop (M-95)

(See Note 4) 2HG009 6

130-2 C6 2/B GT M0 C

FS,ST Q

60 A

Unit 2 Outlet to Unit 1 D/W (See Note 4)

I i

i GE.T 2 -1180

c O

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O La a eCoun yNuct a Sta io Unit 2 INSERVICE TESTING PLAN gstem lip - tiigh Pressure Core Spr ay VALVES 1

2 1

4 N

9 4,

,f[0;4_

'06 07 08 09 10 11 12 13 00 01 02 05 /

f 2E22-F001 14 141 A4 2/8 GT MG 0

FS,ST Q

140 A

HPCS Pump Suction Stop From CST 2E22-F002 24 141 A4 2/C CV C

E Q

A HPCS Pump Suction Stop i

From CST 2E22-F004 12 141 DS 1/A GT M0 C

FS,ST Q

14 RV-19 A

HPCS Injection Line St< p l

LT RR (Mll)(See tiote 5,4) l l

2E22-F005 12 141 D6 1/AC NSC A0 C

E CS RV-19 A

HPCS Injection Line Tent-PIT RR RV-35 able (M-ll)(See Note LT RR 5,7) 2E22-F012 4

141 C3 2/A GT M0 C

FS,ST Q

22 RV-19 A

HPCS Pump Minimum flow LT RR bypass line stop (Sec Note 4,6,8) 1 2E22-F014 1x2 141 B5 2/C RY C

RV RR A

HPCS Water Leg Dischar,e relief (See Note 2,4,F v

6) 2E22-F015 18 141 86 2/A GT M0 C

FS,ST Q

99 RV-19 A

HPCS Stop Pump Suction LT RR from Suppression l

Chamber (See Note 4,6.

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HPCS Check Pump Suction from Suppression Chamber (See Note 1) 2E22-F024 16 141 C3 I 2/C NSC C

E Q

A HPCS Pump Discharge Check 0

E Q

A HPCS Water Leg Pump 2E22-F007 3/4 141 C4 2/C NSC 1

Discharge Check l

I 2E22-F035 lx2 141 D2 2/C RV I -

C RV RR A

HPCS Discharge Line Relief (See Note 2) 1 2E22-F028 10 134-01 B6 3/C, NSC C

E Q

A HPCS DLS Gen Cooling l

l Water Discharge Check l

l 2E22-F319 4

134-01 A6 3/B GT M0 C

FS Q

RV-01 A

HPCS Diesel Cooling l

Water Strainer Bkswash Outlet Stp g

2E22-F345

.75 134-01 B4 3/C RV C

RV RR A

HPCS DG Cooler Inlet xl.0 Relief (See Note 2)

GE-T 2 - 1180

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66-3 F6 2/A GB A0 0

FS.ST RR 40 RV-12 A

Drywell Suction Isolatior LT RR RV-19 Fail Close (See Note 1, l

FST RR 4,6) (M-54) 2IN001B 2

66-3 F7 2/A GG A0 0

FS.ST RR 40 RV-12 A

Drywell Suction Isolatio, i

LT RR RV-19 Fail Close (See Note 1, FST RR

4) (M-54) 2IN017 1.5 66-3 B3 2/A GS A0 0

FS RR RV-12 A

Drywell Pneumatic-To LT RR RV-02 Drywell Fail Close (See FST RR RV-19 Note 1,4) (M-54) 2IN074 1.5 66-3 E5 2/A GB A0 0

FS RR RV-02 A

Dryer Purging Valve Fail LT RR RV-12 Close (See Note 1,4,6)

FST RR RV-19 (M-54) 2IN075 1.5 66-3 E5 2/A GB A0 0

FS RR RV-02 A

Dryer Purging Valve Fail LT RR RV-12 Close (See Note 1,4)

FST RR RV-19 (M-54) 2Ii4045 1x2 66-7 E3 3/C RV C

'RV RR Ventilation System 21N046 1x2 66-7 E2 3/C RV C

RV RR Ventilation System GE-12 1180

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.75 66-3 B5 2/A GB SO O

FS RR RV-02 A

Tip Indexer Purge-Fail FST RR RV-12 Close (See Note 1,4,6)

LT RR RV-19 (M-47)

/

2B21-F024A

.75 66-4 F6 3/C NSC 0

E RR RV-16 A

11SIV In Check (See Note 1) 2B21-F024B

.75 66-4 F7 3/C NSC' -

0 E

RR RV-16 A

MSIV In Check (See Note 1) j 2B21-F024C

.75 66-4 F4 3/C NSC 0

E RR RV-16 A

MSIV In Check (See Note 1) 2B21-F024D

.75 66-4 F5 3/C NSC 0

E RR RV-16 A

MSIV In Check (See Note 1) 2B21-F040C

.50 66-4 B2 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note i

1) 2B21-F040D

.50 66-4 B4 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1) 2B21-F050E

.50 66-4 B7 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1)

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11 12 13 2B21-F040R

.50 66-4 B7 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1) 2821-F040S

.50 66-4 B6 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1) 2821-F0400

.50 66-4 B3 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1) 2821-F040V

.50 66-4 B5 3/C NSC 0

E RR RV-16 A

ADS In Check (See Note 1) 2IN043 1

66-7 D1 3/C NSC 0

E RR RV-12 A

ADS Supply Check (M-60) 2IN044 1

66-7 04 3/C NSC 0

E RR RV-12 A

ADS Supply Check (M-55)

GE-T2 -1180

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06 07 08 09 10 11 12 13 EE21-F001 24 140 B6 2/A GT M0 0

FS,ST Q

132 RV-19 A

LPCS Suction From LT RR Suppression Pool Stop (M-68)(See Note 4,6,11) 2E21-F003 16 140 C2 2/C NSC C

E Q

A LPCS Pump Discharge Chtck 2E21-F005 12 140 D6 1/A GT M0 C

FS,ST CS 20 RV-04 A

LPCS Injection Line Out-LT RR RV-19 board Stop (M-10) (See Note 1,5,4) 2E21-F006 12 140 C6 1/AC NSC A0 C

E CS RV-35 A

LPCS Injection Line PIT RR RV-19 Testable Check Valve LT RR (M-10)(See Note 1,5,7) 2E21-F0ll 4

140 C3 2/A GT M0 0

FS,ST Q

4 RV-19 A

LPCS Min Flow Bypass Stp LT RR (See Note 4,6,8)(M-77) 2E21-F018 3x4 140 DS 2/C RV C

RV RR A

LPCS Pump Discharge Relief (See Note 2,4,6.3) 2E21-F031 lx2 140 B4 2/C RV C

RV RR A

LPCS Pump Suction Relief (See Note 2,4,6,8) 2E21-F033

.75 140 C3 L, _'

NSC 0

E Q

A LPCS Water Leg Pump Discharge Check GE-T 2 - 1180

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2CM027 3

75-4 C8 2/A GT M

LC LT RR RV-19 P

(M-37)(See Note 13)

RV-37 2MC033 3

75-4 C8 2/A GT M

LC LT RR RV-19 P

(M-37)(See Note 13)

RV-37 GE-T 2 -1180

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RV RR A

D m in Steam Line Safety /Reller Valve (See Note 2) 2B21-F0138 8x10 116-1 C3 1/C SRV A0 C

RV RR A

A Main Steam Line Safety /Rellef Yalve (See Note 2) 2821-F013C 8x10 116-1 E2 1/BC SRV A0 C

RV RR RV-33 A

C Main Steam Line E

RR Safety / Relief Yalve (A05) (See Note 2) 2021-F0130 8x10 116-1 82 1/BC SRV A0 C

RV RR RV-33 A

B Main Steam Line E

R" Safety / Relief Valve (A05) (See Note 2) 2821 F013E 8x10 116-1 E3 1/BC SRV A0 C

RV RR RV-33 A

C Main Steam Line E

RR Safety / Relief Valve (ADS) (See Note 2)

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RV RR A

B Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013G 8x10 116-1 D6 1/C SRV A0 C

RV RR A

D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013H 8x10 116-1 D4 1/C SRV A0 C

RV RR A

D Main Steam Line Safety / Relief Valve (See Note 2) 2B21-F013J 8x10 116-1 C4 1/C SRV A0 C

RV RR A

A Main Steam Line Safety Relief Valve (See Note 2) 2821-F013K 8x10 116-1 B4 1/C SRV A0 C

RV RR A

B Main Steam Line Safety Relief Valve (See Note 2)

GE-T2 - 1180

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2021-F013L 8x10 116-1 E6 1/C SRV A0 C

RV RR A

C Main Steam Line Safety /Reller valve (See Note 2) 2821-F013M 8x10 116-1 B7 1/C SRV A0 C

RV RR A

B Main Steam Line Safety /Reller Valve (See flote 2) 2821-F013N 8x10 116-1 E7 1/C SRV A0 C

RV RR A

C Miln Steam Line Safety /Reller Valve (See Note 2) 2021-F013P 8x10 116-1 C6 1/C SRV A0 C

RV RR A

A Main Steam Line Safety / Relief Valve (See Note 2) 2021-F013R 8x10 116-1 E5 1/DC SRV A0 C

RV RR RV-33 A

C Main Steam Line E

"R Safety /Reller Valve (ADS)(See Note 2)

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n 00 01 02 03 04 05 06 07 os 09 to 11 13 2821-F0135 8x10 116-1 86 1/BC SRV A0 C

RV RR RV-33 A

B Main Steam Line E

RR Safety /Reller Valve (ADS)(See Note 2) 2B21-F013U 8x10 116-1 07 1/BC SRV AD C

RV RR RV-33 A

D Main Steam Line E

RR Safety / Relief Ysive (ADS)(See Note 2) 2B21-F013V 8x10 116-1 C7 1/BC SRV AD C

RV RR RV-33 A

A min Steam Line E

RR Safety / Relief Valve (ADS)(See Note 2) 2B21-F016 3

116 7 07 1/A GT

, KJ 0

FS,ST Q

15 RV-19 A

Main Steam Inboard LT RR Orain Line Isolation Pli HR Valve (See Note 4,6) 2B21-F019 3

116 7 06 1/A GT W

0 FS ST Q

15 RV-19 A

Outboard Orain Line LT HH Nin Steam Isolation PIT HH Valve (See Note 4) l

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A0 0

PS Q

3-5 RV-22 A A MSIV Inboard (M-1)

FS,ST CS (See Note 1,4,6.12)

FST CS PIT RR I

LT RR RV-19 2B21-F022B 26 116-2 B6 1/A m

A0 0

PS Q

3-5 RV-22 A B MSIV Inboard (M-2)

FS.ST CS (See Note 1.4.12.6) j FST CS PIT Rit LT RR RV-19 2021-F022C 26 116-2 F6 1/A m

A0 0

PS Q

3-5 RV-22 A C MSIV Inboard (M-3) l FS,ST CS (See Note 1.4.12.61 FST CS Pli RR LT RR RV-19 i

2021-F0220 26 116-2 06 1/A m

A0 0

PS Q

3-5 RV-22 A D MSIV Inboard (M-4)

FS.ST CS (See Note 1,4,12,6) i FST CS PIT RR LT RR RV-19 t

2021-FO?tm 26 116-2 C4 1/A m

A0 0

PS Q

3-5 RV-22 A A f1Siv Outboard (M-1)

FS,ST CS (See Note 1,4,12)

FST CS PIT llR LT RR RV-19 i

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10 0

PS Q

3-S RV-22 A

B MSIV Outboard (M-2)

FS,ST CS (See flote 1,4,12)

FST CS PIT RR LT RR RV-l?

2821-F028C 26 116-2 F4 1/A 08 10 0

PS Q

3-5 RV-22 A

C MSIV Dutboard (M-3)

FS,ST CS (See flote 1,4,12)

FST CS PIT RR LT RR RV-19 2821-F0280 26 116-2 04 1/A W

A0 0

PS Q

3-5 RV-22 A

D MSIV Outtx)ard (M-4)

FS,ST CS (See flote 1,4,12)

FST CS PIT llR LT RR RV-19 2821-F067A 1.5 116-7 E6 1/A PG M1 C

FS,ST Q

'23 RV-19 A

A MSIV Outboard Drain Li RR Isolation (See flote 4.12) 2821-F0670 1.5 116-7 E5 1/A PG H1 C

FS,ST Q

23 RV-19 A

0 MSIV Dutboard Drain LT IIR isolation (Se flote 4,12) 2821-F067C 1.5 116-7 E7 1/A PG t11 C

FS.ST Q

?3 RV-19 A

C MSIV Outboard Drain LT ltR Isolation (See flote 4,12) 2B21-F0670 1.5 116-7 E6 1/A PG HI C

FS,ST U

?3 liv-19 A

D MSIV Otilboard Drain LT RR Isolation (See flote 4,12)

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00 01 02 03 04 05 06 07 08 09 to 11 12 13 2E32-F001A 2.5 116-8 F3 1/A GT M0 C

FS,ST CS 13.75 RV-Il A

MS Loop A Bleed Valve LT RR RV-19 Outboard (See Note 1.4.12) 2E32-F001E 2.5 116-8 E3 1/A GT M0 C

FS,ST CS 13.75 RV-Il A

MS Loop B Bleed Valve LT RR RV-19 Outboard (See Note 1,4,12) 2E32-F001]

2.5 116-8 C3 1/A GT M)

C FS,ST CS 13.75 RV-Il A

MS Loop C Bleed Valve LT RR RV-19 Outboard (See flote 1,4,12) 2E32-F00lN 2.5 116-8 C3 1/A GT M0 C

FS,ST CS I3.75 W-Il A

MS toop D Bleed valve LT RR RV-19 Outboard (See flote 1.4.12) 2E32-F003A 2'

116-8 F4 2/B GB M0 C

FS,ST CS 60 RV-Il A

MS Loop A Bypass to Steam tmnel (See Note 1) 2E 32-F003E 2

116-8 04 2/B GB M0 C

FS,ST CS 60 RV-Il A

MS Loop B Bypass to Steam tmoel (See Note 1) 2E 32-F003]

2 116-8 C4 2/B GB HO C

FS,ST CS 60 RV-Il A

MS Loop C Byruss to Steam tmnel (See Note 1) 2E 32-F003N 3

116-8 B4 2/0 GT MO C

FS,ST CS 30 RV-Il A

MS Loop D Dypass to Stearn tmnel (See Note 1)

.?E 32-F00/A 2.5 116-8 F3 2/0 GI HO C

FS,ST CS 25 RV-Il A

MS Loop A niced valve (See tht e I)

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00 01 02 03 04 05 08 07 08 09 10 11 12 13 2E32-F002E 2.5 116-8 E3 2/B GT MD C

FS,ST CS 25 RV-ll A

M5 Loop R Bleed Valve (See N0ce 1) 2E32-F002]

2.5 116-8 D3 2/B GT HD C

FS,ST CS 25 RV-Il A

M5 Loop C Bleed Valve (See Note 1) 2E32-F002N 2.5 116-8 C3 2/B GT M0 C

FS,ST CS 25 RV-ll A

MS Loop D Blet.d Yalve (See Note 1) 2E32-F006 2.5 116-8 B3 2/B GT m

C FS,ST CS 25 RV-Il A

Bleed Valve-Steam Tunnel (See Note 1) 2E32-F007 2.5 116-8 84 2/B GT m

C FS,ST CS 25 RV-Il A

Bleed Valve-Steam Tunne1 (See Note 1) 2E32-F008 2.0 116-8 A4 2/B GB M0 C

FS,ST CS 60 RV-Il A

Discharge to Steam Tunnel (See Hate 1) 2E32-F009 2.0 116-8 A4 2/8 GB M0 C

FS,ST CS 60 RV-Il A

Discharge to Steam Tunnel (See Note 1)

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E RR RV-28 A

Vacuum Breakers i

2B21-F037Al 12 138-1 C4 3/C CV 2B21-F037A2 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers C

E RR RV-28 A

Vacuum Breakers 2B21-F037B1 12 138-1 C4 3/C CV 2B21-F03rB2 12 138-1 C4 3/C CV C

E RR RV-29 A

Vacuum Breakers 2B21-F037C1 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037C2 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2821-F03701 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F03702 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037El 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037E2 12 138-1 C4 3/C CV C

E RP, RV-28 A

Vacuum Breakers 2B21-F037F1 12 138-l C4 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B 21-F037F2 12 138-1 C4 3/c CV C

E RR RV-28 A

Vacimwn Breakers

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Vacutse Breakers 2Br21-F037G1 12 138-1 C4 3/C CV 2B21-F037G2 12 138-1 C4 3/C CV C

E RR RV-28 A

Vacuum Breakers C

E RR RV-28 A

Vacuum Breakers 2B?l-F037K1 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacutan Breakers 2B21-F037K2 12 138-1 C5 3/C CV i

2B21-F037L1 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037L2 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037P1 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037P2 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers C

E RR RV-28 A

Vacuum Breakers 2821-F037R1 12 138-1 C5 3/C CV 4

2B21-F037R2 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B 21-F03751 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers C

E RR RV-28 A Vactaan Breakers 2B21-F03752 12 138-1 C5 3/c CV I

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Vacuum Breakers 2821-F037V2 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037UI 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuta Breakers 1

2B21-F03702 12 138-1 C5 3/C CV C

E RR RV-28 A

Vacuum Breakers 2821-F037H1 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuum Breakers 2821-F037H2 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037]l 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuta Breakers j

2821.F03732 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuum Breakers 2E21-F037M1 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacula Breakers 2821-F037M2 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B21-F037N1 12 138-1 C6 3/C CV C

E RR RV-28 A

Vacuum Breakers 2B?l-F037N2 12 138-1 C6 3/c CV C

E RR RV-28 A

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.75 139-3 86 2/AC EFC 0

E LT RR RV-34 A

See Note 10 2821-F348

.75 139-3 A6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F350

.75 139-3 A6 2/AC EFC 0

E LT RR RV-34 A

See Note 10 r

2B21-F344

.75 139-3 B3 2/AC EFC 0

E.LT RR RV-34 A

See Note 10 2821-F353

.75 139-4 A5 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F355

.75 139-4 B5 2/AC EFC 0

E.Li RR RV-34 A

See Note 10 2B21-F357

.75 139-4 05 2/AC EFC 0

E.LT RR RV-34 A

See Note 10 2821-F359

.75 139-4 C5 2/AC EFC 0

E LT RR RV-34 A

See Note 10 2B21-F361

.75 139-4 DS 2/AC EFC 0

E LT RR RV-34 A

See Note 10 2B21-F363

.75 139-4 C5 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F365

.75 139-4 ES 2/AC EFC 0

F,LT RR RV-34 A

See Note 9 2B21-F367

.75 139-4 A5 2/AC EFC 0

F,LT RR RV-34 A

See Note 9 2B 21-f 370

.75 139-5 A6 2/AC rrC 0

F,LT PR RV-31 A

See Note 10 2B El-F372

.75 139-5 C6 2/AC IFC 0

F,LT PR R '.' u A

sen note in GE f ? -IIRO

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00 01 2

03 04 05 06 07 08 09 10 11 12 13 2821-F374

.75 139-5 D6 2/AC EFC 0

E LT RR RV-34 A

See Note 10 2B21-F376

.75 139-5 B6 2/AC EFC 0

E.LT RR RV-34 A

See Note 10 2B 21-F378

.75 139-5 E6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B 21-F380

.75 139-5 A6 2/AC EFC 0

E,LT RR RY-34 A

See Note 9 2B21-F382

.75 139-5 F6 2/AC EFC 0

E.LT RR RV-34 A

See Note 9 2B21-F437

.75 139-3 E3 2/AC EFC 0

E.LT RR RV-34 A

See Note 10 2B21-F439

.85 139-3 E3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F441

.75 139-3 D3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F443

.75 139-3 D3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F445A

.75 139-3 03 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F4458

.75 139-3 D3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F447

.75 139-3 C3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F449

.75 139-3 C3 2/AC EFC 0

f,LT RR RV-14 A

See Note 10 2821-F451

.75 139-3 C3 2/AC FFC 0

I,LT RR RV-14 A

See Note 10 C E-T 7 -1180

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VALVES

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07 [ 08 00 02 03 04 05 06 09 10 11 12 13 2B21-F453

.75 139-3 C3 2/AC EFC 0

E,LT RR RV-34 A

dee Hot.e IU 2B21-F455A

.75 139-3 B3 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F445B

.75 139-3 B3 2/AC EFC 0

E,LT RR' RV-34 A

See Note 10 2821-F457

.75 139-3 E6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F459

.75 139-3 E6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F461

.75 139-3 D6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F463

.75 139-3 D6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F465A

.75 139-3 D6 2/AC EFC 0

E,LT RR RV-34 A

See Note W 2B21-F465B

.75 139-3 D6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F467

.75 139-3 C6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F469

.75 139-3 C6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F471

.75 139-3 C6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F473

.75 139-3 C6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2B21-F475A

.75 139-3 B6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 2821-F475B

.75 139-3 B6 2/AC EFC 0

E,LT RR RV-34 A

See Note 10 GE-T2 -1180

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E Q

A Vacuum Breakers IPC001C 24 138-2 D3 2/C CV C

E Q

A Vacuum Breakers 2PC001D 24 138-2 E3 2/C CV C

E Q

A Vacuum Breakers GE-T2 1180

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Scram Testing (185)

FST RV-30 2Cll-0001-127 146-3 E3 NC/B GT 0

FS RV-30 RV-30 A

Scram Testing (185)

FST RV-30 2Cll-D001-ll 4 146-3 E3 NC/C CV 0

E RV-30 RV-30 A

Scram Testing (185) 2Cll-F380 2

146-2 2/B CNV A0 0

FS Q

RV-26 A

CRD Scram Discharge FST Instrument Volume Vent 2Cll-F381 2

146-2 2/B CNV A0 0

FS Q

RV-26 A

CRD Scram Discharge FST Instrument Volume Drain 2C11-F388 2

146-2 2/B CNV A0 0

FS Q

RV-26 A

CRD Scram Discharge FST Instrument Volume Vent 2C11-F389 2

146-4 2/B CNV A0 0

FS Q

RV-26 A

CRD Scram Discharge FST Instrument Volume Drain i

GE-T2 -1180

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137-4 84 2/A CNY A0 C

FS,ST Q

20 RV-19 A

(M-96) Drywell LT RR Equipnent Drain stanp suctlon.(See Note 4,6) 2RE025 2

137-4 C4 2/A HV A0 C

FS,ST Q

20 py_19 A

(g_96) Drywell LT RR Equipnent Drsin sump suction.(See Note 4) 2RE026 1

137-4 05 2/A CNV A0 C

FS,ST Q

20 RV-19 A

(M-97) Gland Seal LT RR Reservolt Drywell Equipnent (See Note 4) 2RE029 1

137-4 DS 2/A CNV A0 C

FS,ST Q

20 py_19 A

(M-97) Gland Seal LT RR Reservoir Drywell Equipnent (See Note 4) 2RF012 2

137-4 A4 2/A CNV A0 C

FS.ST Q

20 RV-19 A

Floor Drain (Drywell)

LT RR Sump Suction (M-98) F.C.

(See Note 4) 2RF013 2

137-4 B4 2/A CNY A0 C

FS,ST

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20 RV-19 A

Drywell Floor Sump LT RR Suction (M-93) F.C.

(See Note 4)

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FS,ST Q

100 A

RR Heat Exchanger Outlet Stop.

j 2E12-F0038 18 142-4 C8 2/B GT M0 O

FS,ST Q

100 A

R R Heat Exchanger Outlet Stop.

2El?-F004A 24 142-1 A7 2/A GT MO O

FS,ST Q

132 RV-19 A

RR Oatboard suction from Suppression Pool LT RR (M-70)(See Note 4,6,11) 2E12-F0048 24 142-I.

87 2/A GT M0 O

FS,ST Q

132 RV-19 A

R R Outboard suction LT RR from Suppression Pool (M-72)(See Note 4,6,11) 2E12-F004C 24 142-3 A7 2/A GT M0 O

FS,ST Q

132 RV-19 A

R R Outboard suction LT RR from Suppression Pool (M-71)(See Note 4,6,11)

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2E12-F005 lx2 142-3 C5 2/C RV SP C

RV RR A

RR Shutdown suction cooling Suction il1R Relief (See Note 2,6,4,8) f 2E12-F0064 18 142-1 A7 2/B GT MO C

FS,ST Q

180 A

Pump Ssction Stop From Slust:10wn Cooling 2E12-F0060 18 142-2 in 2/B GT M0 C

FS,Si Q

180 A

Rsmp Section Stop from Shot:10wn Coolliul

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FS,ST CS 41 RV-04 A

RHR Shutdown Cooling LT RR RV-19 Pump 2A Suction HDR Outboard Isolation (ft-7)(See Note 1,5,4) 2E12-F009 20 142-3 D7 1/A GT M0 C

FS,ST CS 41 RV-04 A

RHR Shutdown Cooling LT RR RV-19 HDR Inboard Isolation PIT RR (ll-7)(See Note 1,5,4) 2E12-F0llA 4

142-4 A3 2/A GT M0 C

FS.ST Q

22 RV-19 A

RHR Heat Exchanger LT RR Steam Condensing Stop to Supp. Chamber (See Note 4,8,6) 2El2-F0llB 4

142-4 A6 2/A GT M0 C

FS,ST Q

22 RV-19 A

RHR Heat Exchanger LT RR Steam Condensino Stop to Supp. Chamber (See Note 4,8,6) 2E12-F016A 16 142-1 E5 2/A GT f10 C

FS.ST Q

88 RV-19 A

RHR Containment Spray LT RR Upstream isolation (ft-18) (See Note 4) 2E12-F016B 16 142-2 F5 2/A GT M0 C

FS,ST Q

08 PV-19 A

RHR Containment Spray LT RR Upstream isolation (M-19) (See Note 4)

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2E12-F017A 16 142 2 E7 2/A GT M0 C

FS,ST Q

88 RV-19 A

H Containment Spray Downstream Isolation LT RR (M-18)(See iiote 4,6) 2E12-F0178 16 142-2 F6 2/A GT M0 C

FS,ST Q

88 RV-19 A

fHt Containment Spray Downstream Isolation RR LT (M-19) (See flote 4,6) 2E12-F025A lx2 142-1 E3 2/C RV SP C

RV RR A

H Pump A Discharge Header Rellef (M-85)

(See flote 2,4,6,8) 1 2E12-F025B lx2 142-2 C5 2/C RV SP C

RV RR A

iHt Pop B Discharge Header Reller (M-86) i (See Note 2,4,6,8) i l

2E12-F025C lx2 142-3 C2 2/C RV SP C

RV RR A

fMt Pmp C Discharge Header Relief (M-87)

(See Note 2,4,6,8) l l

2E12-F026A 4

142-4 B4 2/B GT M0 C

FS,ST Q

40 A

INR Heat Exchanger Steam Condensing Outlet Stop to RCIC Pinnp Suctton I

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142-4 B6 2/B GT M0 C

FS,ST Q

40 A

RHR Heat Exchanger Steam Condensing Outlet Stop to RCIC Pump Suction 2E12-F027A 4

142-1 CS 2/A GT M0 C

FS,ST Q

30 RV-19 A

RHR Suppression Chamber LT RP Spray Isolation (M-73)

(See Note 4,6,8) 2E12-F0278 4

142-2 C4 2/A GT M0 C

FS,ST Q

30 RV-19 A

RHR Suppression Chamber LT RR Spray isolation (M-74)

(See Note 4,6,8) 2E12-F030 1x2 142-2 B4 2/C RV SP C

RV RR A

RHR System Drain Header Relief (ft-91) (See Note 2,4,6,8) t 2E12-F031A 18 142-1 A4 2/C CV C

E Q

A RHR Pump A Discharge Chk 2E12-F0318 18 142-2 C3 2/C CV C

E O

A RHR Pump B Discharge Chk 2E12-F031 C 18 142-3 B4 2/C CV C

E O

A RHR Pump C Discharge Chk 2E12-F041A 12 142-1 07

'/AC flSC A0 C

E CS RV-35 A

RHR LPCI Testable Chk PIT RR RV-19 Inboard sten (if-13)

LT RR (See Note 1,5,7)

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E CS RV-35 A

RR LPCI Testable O*

PIT RR RV-19 Inboard Stop (M-14)

(See Note 1,5,7)

LT RR 2E12-F041C 12 142-3 E7 1/AC NSC AG C

E CS RV-35 A

RR LPCI Testable O*

PII RR RV-19 Inboard Stop (M-12)

LT RR (See Note 1,5,7) 2E 12-F042A 12 142-1 05 1/A GT MO C

FS,ST CS RV-27 A

RR LPCI injection Line LT RR 20 RV-19 Outboard Stop (M-13)

(See Note 1.5,4) 2E12-F0428 12 142-2 E6 1/A GT M0 C

FS,ST CS 20 RV-27 A

RR LPCI injection Line l

LT RR RV-19 Outboard stop (M-14)

(See hote 1,5,4) 2E12-F042C 12 142-3 E6 1/A GT M0 C

FS,ST CS 20 FN-27 A

RR I.PCI Injection Line LT RR RV-19 Outboard Stop (M-12)

(See Note 1,5,4) 2E12-F046A 8

142-1 BS 2/C CV C

E Q

A RR Pump Miniman Byrnss Check 2E12-F0460 8

142-2 C2 2/C CV C

E Q

A FDIR Pirnp Mininan Flow Hypiss chect<

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FS,ST Q

180 A

H Heat Exchanger l

Inlet Stop 2E12-F0478 18 142-4 ES 2/B GT MO O

FS.ST Q

180 A

H Heat Exchanger Inlet Stop j

2E12-F0484 18 142-4 01 2/B CB MO 0

rS,ST Q

270 A

H Heat Exctanger Bypass Stop 2E12-F0488 18 142-4 08 2/B CB M0 O

FS,ST Q

270 A

R m Heat Exchanger l

Bypass Stop 2E12-F049A 3

142-4 C1 2/B GT M0 C

FS,ST Q

30 A

H Heat Exchanger Blowdown Upstream Isolation to RB EDT 2E12-F0498

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142-4 C8 2/B GT M0 C

FS,ST Q

30 A

Upstream isolation to RB EDI 2E12-F050A 12 142-1 07 1/AC t4T A0 0

E CS RV 04 A

Rm Stutdown Cooling LT RR RV-19 Ter. table theck (M-ti)

(See Note 1,S,7)

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E CS RY-04 A

RHR Shutdown Cooling LT P.R RV-19 Testable Chk (M-9) (See Note 1,5,7) 2E12-F052A 10 142-4 C4 2/B GB M0 C

FS.ST 0

300 A

RHR Heat Exchanger Steam inlet Stop l

2E12-F0528 10 142-4 C5 2/B GB M0 C

FS,ST Q

300 A

RHR Heat Exchanger Steam Inlet Stop 2E12-F053A 12 142-1 05 1/A GB M0 C

FS,ST CS 29 RV-04 A

RHR Shutdown Cooling LT RR RV-19 Discharge Isolation (M-8) (See Note 1,5,4) 2E12-F053B 12 142-2 D6 1/A GB P10 C

FS,ST CS 29 RV-04 A

RHR Shutdown Cooling LT RR RV-19 Discharge Isolation (M-9) (See Note 1,5,4) 2E12-F055A 4xG 142-4 D3 2/C RV SP C

RV RR A

RHR Heat Exchanger Steam Inlet Header Relief (M-88) (See Note 2,4,6,3) 2E12-F073A

.75 142-4 E3 2/A GB MO C

LT RR RV-19 P

RHR Heat Exchancer Vent (See Note 4.3,6) 2E12-F073B

.75 142-4 E5 2/A GB M0 C

LT RR RV-19 P

RHR Heat Exchanaer Vent (See Note 4,8,6)

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RV RR A

RHR Heat Exchanger Steam Inlet Header Relief

(!!-88) (See Note 2,4,6, 8) 2E12-F087A 10 142-4 C4 2/B GB M0 C

FS.ST Q

300 A

RHR Heat Exchanger Steam inlet PCV Bypass Stop 2E12-F0878 10 142-4 C5 2/B GB M0 C

FS ST Q

300 A

RHR Heat Exchanger Steam Inlet PCV Bypass Stop 2E12-F088A lx2 142-1 A6 2/C RV C.

RV RR A

RHR Pump Suction HDR Relief (See Note 2,4,8) 2E12-F088B lx2 142-2 B5 2/C RV C

RV RR A

RHR Pump Suction HOR Relief (See Note 2,4,8) 2E12-F088C lx2 142-3 B6 2/C RV C

RV RR A

RHR Pump Suction HDR Relief (See Note 2,4,8, 6) 2E12-F311 A

.75 142-4 D2 2/C RV SP C

RV RR A

RHR Heat Exchanger Shell x1 Side Relief (M-88, M89)

(See Note 2,4,6,8) 2E12-F3118

.75 142-4 06 2/C RV SP C

RV RR A

RHR Heat Exchanger Shell x1 Side Relief (M-88, M89)

(See Note 2,4,6,8)

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II VALVES

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[o1 00 02 03 G4 05 os or os os to 11 12 13 2E12-F312A 1.5 142-1 D2 2/B GB M0 C

FS.ST Q

45 A

RHR Heat Exchanger to H2 Recombiner #1 2E12-F312B 1.5 142-2 E2 2/B GB M0 C

FS,ST Q

45 A

RHR Heat Exchanger to H2 Recombiner #2 2E12-F064A 4

142-1 B5 2/A GT MO 0

FS.ST Q

22 RV-19 A

RHR Pump 2A Main Flcw LT RR Bypass (See Note 4,6,8) 2E12-F0648 4

142-2 C3 2/A GT M0 O

FS,ST Q

22 RV,19 A

RHR Pump 2B Main Flow LT RR Bypass (See Note 4,6,8) 2E12-F064C 4

142-3 B4 2/A GT MO 0

FS,ST Q

22 RV-19 A

RHR Pump 2C Main Flow LT RR Bypass (See Note 4,6,8) 2E12-F084A

.75 142-1 83 2/C CV C

E Q

A from LPCS Water leg Pump to RHR 2A Discharge 2E12-F0848

.75 142-4 E5 2/C CV C

E Q

A From RHR Water Leg Pump to RilR 2B Discharge 2E12-F084C

.75 142-3 A7 2/C CV C

E Q

A From RHR Water Leg Pump to RilR 2C Discharge 2E12-F068A 20 134-2 B2 3/B GT M0 C

FS.ST Q

200 A

RilR lleat Exchanger Service Water Outlet Stop C E-72 1180 1

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FS,ST 0

200 A

RHR Heat Exchanger Service Water Outlet Stop 2E12-F331A 16 134-2 B6 3/C NSC C

E O

A RHR Service Water Pump 2A Discharge Check 2E12-F331B 16 134-2 C6 3/C f4SC C

E Q

A RHR Service Water Pump 2B Discharge Check C

E Q

A RHR Service Water Pump 2E12-F331C 16 134-1 E6 3/C ilSC 2C Discharge Check C

E Q

A RHR Service Water Pump 2E12-F3310 16 134-1 F6 3/C f1SC 2D Discharge Check 2E12-F336A 4

134-2 A5 3/B GT M0 C

FS 0

RV-01 A

RHR Service Water Pump Strainer 2A Backwash Outlet Stop 2E 12-F336B 4

134-1

.E5 3/B GT f10 C

FS Q

RV-01 A

RHR Service Water Pump Strainer 2B Backwash Outlet Stop 2E 12-F313A 3x4 137-3 C4 2/C RV C

RV RR A

RHR Heat Exchanger Relief (See flote 2)

GE T2 It00

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RV RR A

RHR Heat Exchange Relief (See Note 2) 2E12-F023 6

142-1 F6 1/A GB M0 C

FS,ST CS 90 RV-04 A

RHR to Head Spray (See LT RR RV-19 Note 1,4) 2E12-F024A 18 142-1 02 2/A GB M0 C

FS.ST Q

297 RV-19 A

RHR Test Line for LT RR Suporession Pool Cooling (See Note 4,6.S) 2E12-F024B 18 142-2 E2 2/A GB M0 C

FS,ST Q

297 RV-19 A

RHR Test Line for LT RR Suppression Pool Cooling (See Note 4,6,8) 1 1

C4.T7-1100

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RI-Re ctor Core Isolation Coolant Unit 2 VALVES 1

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A-4 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2 E51-F010 8

147-2 A4 2/B GT M0 O

FS,ST Q

80 A

Suction from CST Downstream Stop 2 E51-F0ll 8

147-2 B3 2/C CV C

E Q

A Suction from CST Downstream Check 2 E51-F008 4

147-1 E7 1/A GT MO 0

FS ST CS 20 RV-31 A

Steam Supply Outboard LT RR RV-19 Isolation (M-15)

(See Note 1,4) 2 E51-F013 6

147-2 C7 1/A GT M0 C

FS,ST CS 15 RV-05 A

Injection Stop (M-29)

LT RR RV-19 (See Note 1,4) 2 E51-F017

.75 147-2 82 2/C RV SP C

RV RR A

Pump Suction Relief xl.0 (See Note 2) 2 E51-F018 1.5 147-2 F3 2/C RV SP C

RV RR A

Turbine tube Oil Cooler x3.0 Inlet Relief (See Note 2) 2 E51-F019 2

147-2 B5 2/A GB M0 C

FS.ST Q

7 RV-19 A

Minimum Flow Bypass LT RR Stop (See Note 4,6,8) 2 E51-F028 1.25 147-1 B6 2/C fl5C C

E Q

A Barometric Condenser Vacuum Pump Discharge (ft-81)(See Note 4) 2 E51-F030 8

l 147 86 2/C CV C

PS Q

RV-36 A

Pump Suction from i

I RR Suppression Thamber CE T2 -1180

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147-2 B7 2/A GT M0 C

FS,ST Q

44 RV-19 A

Pump Suction from LT RR Suppression Chamber (See Note 4,6,11) 2E12-F036A 4x6 147-2 C6 2/C RV SP C

RV RR A

RCIC Safety Relief Valve Discharge Condensate (M-101) (See Note 2) 2E12-F036B 4x6 147-2 B3 2/C RV SP C

RV RR A

RCIC Safety Relief Valve Discharge Condensate (M-92) (See flote 2) 2E51-F040 10 147-1 B6 2/C CV C

E Q

A Turbine Exhaust Check (M-76) (See Note 4) 2E51-F045 4

147-1 D5 2/B GB M0 C

rS,ST Q

120 A

Turbine Exhaust Supply Stop 2E51-F046 2

147-2 D3 2/8 GB f10 C

FS,ST Q

60 A

Turbine Lube Oil Cooler Supply Stop 2E51-F047 2

147-1 B6 2/C CV C

E Q

A RHR Condensate Pump Discharge Check 2E51-F061

.75 147-2 A3 2/C CV C

E Q

A Water Leg pump Discharge Check GE t 180

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O O La a ecoun yNuci a Sta l INSERVICE TESTING PLAN syaw RI-Reactor Core Isolation Coolant Unit 2 Page 3

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VALVES

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FS ST CS 15 RV-31 A

Steam Supply Inboard LT RR RV-19 Isolation (M-15)

PIT RR (See Note 1,4,6) 2E51-F064 10 147-1 E7 1/A GT M0 C

FS.ST CS 15 RV-15 A

Steam Supply Outboard LT RR RV-19 Isolation (To RHR)

(M-15) (See Note 1,4) 2E51-F065 6

147-2 C7 1/C CV A0 C

E CS RV-19 A

RCIC Injection Outboard PIT RR RV-35 Testable Check (M-29)

LT RR (See Note 5,7) 2E51-F066 6

147-2 CB 1/C CV A0 C

E CS RV-19 A

RCIC Injection Inboard PIT RR RV-35 Testable Check (M-29)

LT RR (See Note 5,7) 2E51-F068 10 147-1 B7 2/A GT MO 0

FS,ST Q

55 RV-19 A

Turbine Exhaust Isolatim LT RR (M-76) (See Note 4,6)

'2E51-F069 1.25 147-1 B7 2/A GB M0 O

FS,ST Q

20.6 RV-19 A

Barometric Condenser LT RR Vacuum Pump Discharge Stop (M-81)

(See Note 4,6) 2 E51-F076 1

147-1 E8 1/A GB M0 C

FS,ST Q

15 RV-19 A

Steam Supply Inboard LT RR lsolation Valve Wann-Up PIT RR Bypass (M-15)

(See Note 4,6)

GE 72 1180

O O

O O tasanecountyNuclear StauonUnit 2 Commonwealth Edison INSERVICE TESTING PLAN system RI-Reactor Core Isolation Coolant Page 4

of 4

VALVES 4

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2E51-F080 2

147-1 C7 2/A GB M0 0

FS,ST Q

33 RV-19 A

RCIC Turbine Exhaust LT RR Vacuum Breaker Inlet Stop (M-101) (See Note 4) 2E51-F086 2.0 147-1 C7 2/A GB M0 0

FS,ST Q

33 RV-19 A

RCIC Turbine Exhaust LT RR Vacuum Breaker Outlet Stop (M-101) (See Note 4,6) 2E51-E091 1

147-1 D7 1/A GB M0 C

FS,ST CS 15 RV-15 A

Warm-Up Bypass (M-15)

LT RR RV-19 (See Note 1,4)

GE-T2 -1180

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2833-F019

.75 139-2 E6 2/A GB A0 0

FS Q

RV-02 A

Process Sampling LT RR RV-19 (See Note 4)

PIT RR 2B33-F020

.75 139-2 E8 2/A GB A0 0

FS Q

RV-02 A

Process Sampling LT RR RV-19 (See Note 4) 2B33-F319A

.75 2139-8 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F3198

.75 2139-8 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2833-F317A

.75 2139-8 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F3178

.75 2139-8 2/AC EFC 0

E RP, RV-34 A

See Note 10 LT 2833-F313A

.75 2139-2 2/AC EFC 0

E RR 9V-34 A

See Note 10 LT 2833-F3138

.75 2139-2 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2 833-F313C

.75 2139-2 2/AC EFC 0

F PR RV-34 A

See Note 10 LT

O O

O O LaSaue County Nuclear Station Unit 2 Commonwealth Edison INSERVICE TESTING PLAN Syewm RR-Reactor Recirculation 2

3 VALVES b

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0 00 01 02 03 04 05 06 07 08 09 10 11 12 13 j

2B33-F313D

.75 2139-2 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 0

E RR RY-34 A

See Note 10 2833-F311A

.75 2139-2 2/AC EFC LT 0

E RR RV-34 A

See Note 10 2833-F3118

.75 2139-2 2/AC EFC LT 0

E RR RV-34 A

See Note 10 2833-F311C

.75 2139-2 2/AC EFC LT RR RV-34 A

See Note 10 2B33-F311D

.75 2139-2 2/AC EFC

{

0 0

E RR RV-31 A

See Note 10 2B33-F315A

.75 2139-3 2/AC EFC LT 0

E RR RV-34 A

See Note 10 2B33-F3158

.75 21 39-3 2/AC EFC LT l

2833-F315C

.75 2139-4 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F315D

.75 2139-4 2/AC EFC 0

E RR RV-14 A

See Note 10 LT 2B33-F301A

.75 139-l 08 2/AC EFC 0

E RR RV-34 A

See Note 10 f

LT i

CE- ? 2 - 1180

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as eco n yNu I a Sta o Unit 2 INSERVICE TESTING PLAN sy i.m RR-Reactor Recirculation VALVES A

4~

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2833-F3018

.75 139-2 DB 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F307A

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2833-F307B

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F307C

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2833-F3070

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2833-F305A

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2833-F3058

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F305C

.75 2139-1 2/AC EFC 0

E RR RV-34 A

See Note 10 LT 2B33-F305D

.75 2139-1 2/AC LFC 0

E RR RV-34 A

See flote 10 LT GE T2 It80

O O

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Commonwealth Edison 1NSERV1CE TESTlNG PLAN system RT-EACT(R WATER CLEAMP Pa9e 1

of 2 LaSalle County Nuclear Station Unit 2 VALVES N

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 2G33-F001 6

143-1 E8 1/A GT MO O

FS,ST CS 30 R/-06 A

C.U. Suction Ittoard LT RR RV-19 Isolation (M-30)

PIT RR (See Note 1.4.6) 2G33-F004 6

143-1 E7 1/A GT M0 O

FS,ST CS 30 RV-08 A

C.U. Outboerd LT RR RV-19 Isolation (M-30)

PIT RR (See Note 1,4)

C RV RR A

RWCU Hu Peller (See 2G33-F339A 1.5 137s2 E8 3/C RV X2.5 Note 2).

2 G33-F3398 1.5 137-2 C8 3/C RV C

RV RR A

RWCU Hx Relief (See x2.5' Note 2).

2 G33-F340A 1.5 137-2 E8 3/C RV C

RV RR A

RWCU Hz Reller (See x2.5 Nr,te 2).

2 G33-F3408 1.5 137-2 C8 3/C RV C

RV RR A

RWCU Hx Relief (See x2.5 Mate 2).

1 2 G33-F341 A 1.5 137-2 E5 3/C RV C

RV RR A

RWCU Hz Reller (See x2.5 Rite 2).

2 G33-F 341B 1.5 137-2 C5 3/C RV C

RV RR A

RWCU Hx Rellef (See x2.5 Mite 2).

I

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INSERVICE TESTING PLAN gstem R -Reactor Water Cleanup La e Co n y Nuci a Sta l Unit 2

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143-1 F4 2/A GT M0 0

FS,ST CS 22 RV-08 A

RWCU Isolation LT RR RV-19 (See Note 1,4)

GE-T2 1180

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o 00 01 02 03 04 05 06 07 08 09 10 11 12 13 2SA042 3

82-05 B7 2/A GT M

C LT RR RV-19 P

(M-38) (See Note 13)

RV-37 2SA046 3

82-05 B7 2/A GT M

C LT RR RV-19 P

(M-38) (See Note 13)

RV-37 GE-T 2 -1180

r-p N]x O La a eC un yNuct a Sta INSERVICE TESTING PLAN system SC-Standby Liquid Control Unit 2

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 f

2C41-F001A 145 C2 2/B PG M0 C

FS,ST RR 15 RV-13 A

A SBLC Pump Suction Stop (See Note 1) 2C41-F001B 3

145 B2 2/B PG M0 C

FS,ST RR 15 RV-13 A

B SBLC Pump Suction Stop (See Note 1) 2C41-F004A 1.5 145 C5 1/A, GT EX C

CC EV RV-19 A

Pump Injection Squib D

LT RR Valve (M-34)(See Note 4) 2C41-F004B 1.5 145 B5 1/A, GT EX C

FC EV RV-19 A

Pump Injection Squib D

LT RR Valve (M-34)(See Note 4) 2C41-F006 1.5 145 D6 1/C NSC C

E RR RV-14 A

Outboard Check (M-34) 2C41-F007 1.5 145 D7 1/A, NSC C

E RR RV-14 A

Inboard Check (M-34)

C LT RR RV-19 (See Note 4) 2C41-F029A

.75 145 D4 2/C RV SP C

RV RR A

Pump Discharge Relief x1 (See Note 2) 2041-F029B

.75 145 C4 2/C RV SP C

RV RR A

Pump Discharge Relief x1 (See Note 2) 2C41-F033A 1.5 145 C4 2/C NSC C

E Q

A Pump Discharge Check 2C41-F033B 1.5 145 B4 2/C NSC C

E Q

A Pump Discharge Check I.

GE-T2 1180

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O O Commonwcalth Edison INSERVICE TESTING PL AN system VP-PRIMRY CCHTAlp6ENT LaSalle County Nuclear Station Unit 2 Psee 1

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00 01 02 03 04 05 06 07 08 09 to 11 12 13 2VP053A 8

133 E2 2/A GT MO O

FS,ST RR 40 RV-17 A

Chilled Water Return LT RR RV-19

(*27) (See Note i.4) 2VP0538 8

133 C2 2/A GT M0 C

FS,ST RR 40 RV-17 A

Chilled Water Return LT RR RV-19 (428) (See Note 1,4) 2VP063A 8

133 D2 2/A GT MO O

FS,ST RR 40 RV-17 A

Water Supply LT RR RV-19

(*25) (See Note 1,4) i 2VP063B 8

133 82 2/A GT MD C

FS,ST RR 40 RV-17 A

Water Supply LT RR RV-19 (64-26) (See Note i 4) 2 VPil3A 8

133 02 2/A EF M0 O

FS,ST RR 90 RV-17 A

Water Supply LT RR RV-19 (14-25) (See Note 1.4.6)

PIT RR 2 VPil30 8

133 82 2/A BF M0 O

FS ST RR 90 RV-17 A

Water Supply LT RR RV-19

(*26) (See Note 1,4,6)

PIT RR 2 VPll4A 8

133 E2 2/A IF MO O

FS,ST RR 90 RV-17 A

Ch111ed Water Return LT RR RV-19 (427) (See Hote 1,4,6)

PIT RR 2 VPil4B 8

133 C2 2/A (F

MO O

FS,ST RR 90 TN-17 A

Chilled Water Return LT RR IN-19 (M-28) (5cc Note 1,4,6)

Pli RR

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1 og 3 m

LaSalk County Nuclear StationiUnit 2

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00 01 02 03 04 05 06 07 06 09 10 11 12 13 2VQO26 26 138-1 C2 2/A 0F MD C

FS,ST CS 130 RV-09 P

Outboerd to Suppression LT RR RV-19 chenber Fr. Rx. Bldg.

Inhoard (PCIS)

Isolation Damper (M-66)

(See Note 1) 2VQ027 26 138-1 C3 2/A BF M0 C

FS,ST CS 130 RV-09 P

Inlet to Suppression LT RR RV-19 Chenher Fr. Rx. Bldg.

Inboard (PCIS)

Isolation Damper (M-66)

/

(See Note 1) 2VQ029 26 138-1 02 2/A 0F M0 C

FS,ST CS 130 RV-09 A

Inlet to Drywell Fr LT RR RV-19 Rx. Bldg. Outboard Isolation Damper (PCIS)

(M-20)fSee Note 1,d) 2VQ030 26 138-1 03 2/A BF MD C

FS,ST CS 130 RV-09 A

Inlet to Drywell Fr LT RR RV-19 Rx. Bldg. Inboard l

Isolation Damrer (PCIS)

(M-20)(See Hote-1.4.6) l 2VQO31 26 138-1 C1 2/A HF M0 C

FS,ST CS 130 RV-09 A

Suction Fr Rx. Bldg.

LT RR RV-19 inboard Isolatinn l

Damper (PCIS) (M-67)

(See Note 1) l h *$

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s 00 01 02 03 04 05 06 07 08 09 to 11 12 13 2VQO32 2

138-1 C7 2/A GB M0 C

FS.ST CS 10 RV-09 P

Bypass Suction LT PR RV-19 (See Note 1,4,6) 2VQO34 26 138-1 E6 2/A BF M0 C

FS.ST CS 130 RV-09 A

Sitction Fr. Drywell LT RR RV-19 Inboard Isolation Damper (PCIS) (M-21)

(See Note 1,4,6) 2VQO35 2

138-1 E6 2/A GB M0 C

FS,ST Q

5 RV-19 P

Suction Fr. Drywell LT RR Inboard Isolation Damper Bypass Inboard (ll-21)

(See Note 4,6) 2VQO36 26 138-1 E7 2/A BF M0 C

FS,ST CS 130 RV-09 A

Suction Fr. Drywell LT RR RV-19 Outboard Isolation Damper Bypass (M-21)

(See Note 4) 2VQO37 26 138-1 B8 2/B BF M0 C

FS,ST 0

90 A

Prime Cont. Ventilation Secondary Containment Inboard Isolation Damper (PCIS) 2V0038 26 138-1 B7 2/B BF tto C

FS,ST 0

90 A

Prime Cont. Ventilation Secondary Containment Outboard Isolation Damper (PCIS)

GE T2 tI80

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00 01 02 03 04 05 os 07 os os 11 12 13 2VQ040 26 138-1 C8 2/A BF M0 C

FS,ST CS 130 RV-09 A

Suction from Suppression LT RR RV-19 Chamber Outboard Isolation Damper (PCIS)

(See Note 1,4) 2VQ041 26 138-1 A8 2/B BF M0 C

FS,ST Q

90 A

Suction Fr Rx Bldg.

Return Air Riser 2VQ068 2

138-1 E7 2/A GB ft0 C

FS,ST Q

5 RV-19 A

(See Note 4)

LT RR 2VQ047 1.5 138-1 D3 2/A GB MO 0

FS ST Q

23 RV-19 A

(See Note 4,6)

LT RR 2VQ048 1.5 138-1 D3 2/A GB fiO O

FS,ST Q

23 RV-19 A

(See Note 4)

LT RR 2VQ050 1.5 138-1 C3 2/A GB M0 O

FS,ST Q

23 RV-19 A

(See Note 4,6)

LT RR 2VQOSI 1.5 138-1 C3 2/A GB f10 0

FS,ST Q

23 RV-19 A

(See Note 4)

LT RR 2VQ042 8

138-1 02 2/A BF M0 C

FS.ST CS 90 RV-09 (See Note 1,4)

LT RR RV-19 l

2VQ043 8

138-1 C2 2/A BF M0 C

FS.ST CS 90 RV-09 (See Note 1.4)

LT RR RV-19 GE T2-I t90

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( P)/ LaSalle CountyNuclearStation Unit 2 C

Commonwealth Edison PUMP & VALVE TEST 1NG Page 1

of 1

\\d RELIEF REQUESTS IIi ASME 33 PUMP OR "O

SECTION XI VALVE NO.

FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE IESI 00 01 02 03 04 05 06 RV-01 2DG-Oli 3/B Strainer Backwash Full stroke and These valves open in Perform a full stroke Valves stroke time response to an autoback-exercise once per quarterly wash logic signal produced quarter by an abnormally high 2E12-F336A 3/B RHR Service Water differential pressure Pump Strainer 2A across the CSCS service Backwash Outlet water strainers. These Stop fast acting, automatically controlled valves only 2E12-F336B 3/B RHR Service Water open to 10% of full stroke Pump Strainer 2B making an accurate stroke Backwash Outlet time measurement very Stop difficult to obtain.

Furthermore, the stroke 2E22-F319 3/B HPCS Diesel time of these valves is Cooling Water not considered a meaning-Strainer Backwash ful indicator of oper-Outlet Stop ational readiness.

un

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Commonwealth Edison

( C# J tassisecountyNuclearStationUnit 2 PUMP & VALVE TESTING Pago 1

of 2

'v RELIEF REQUESTS Iii ASME 13 PUMP OH

$0 SECTION XI N

VALVE NO.

JN FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF ALIEHNATIVE IESI Uy E

oo of 02 03 04 05 06 RV-02 2IN017 2/A Drywell Pneumatic Full Stroke and These valves are designed Perform a full stroke to Drywell -

Stroke Time to stroke rapidly within exercise quarterly.

Fail Close Quarterly a specified time range.

Verification that the 2IN074 2/B Dryer Purging Valve valve strokes within the

- Fail Close time range is essential, i

but due to the inaccuracie.

2IN075 2/B involved with measuring short time intervals, 2IN031 2/A TIP Indexer Purge stroke time trending pro-vides no useful informa-2B33-F019 2/A Process Sampling tion and may even lead to Valve unnecessary maintenance operations. Therefore, 2B33-F020 2/A the stroke times of these valves will not be 2D0004 3/B Diesel Oil Transfer trended, but will be Pump Stop Valve verified to not exceed 5 seconds.

200014 3/B 2D0024 3/B t

2CM017A 2/A Containment Monitor-ing Valve 2CM017B 2/A 2CM018A 2/A 2CM0188 2/A uo

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Commonwealth Edison

( V"/

LaSalle County Nuc' ear Station Unit 2 PUMP & VALVE TESTING Pago 2

of 2

A/

RELIEF REQUESTS e

IiiO EO ASME 33 PUMPOft "O

SECTION XI y@

VALVE NO.

M FUNCTION TEST REQUlllEMENT BASIS FOR HELIEF AL TEllNAllVE IESI 04 e

0 00 01 02 03 04 05 06 RV-02 2CM019A 2/A Containment Monitor-(cont'd) ing Valve 2CM019B 2/A 2CM020A 2/A 2CM020B 2/A 2CM021B 2/B 2CM022A 2/B 2CM023B 2/B 2CM024A 2/B 2CM025A 2/B

\\

2CM026B 2/B N

1

\\

2CM031 2/A i

2CM032 2/A 1

N 2CM033 2/A

'N 2CM034 2/A t al (3

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Commonwealth Edison

/

i

\\ ' "J LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 1

of 1

RELIEF REQUESTS Ili 5

ASME 33 PUMP OH

$0 SECTION XI VALVE NO.

FUNCTION TEST HEOUlHEMENT BASIS FOR HELIEF ALIEHNATIVE IESI o

00 01 02 03 04 05 06 RV-03 2WR-029 2/A Drywell Equipment Full Stroke Reactor recirculation Perform a full stroke RBCCW Isolation Exercise Quarterly pump operation requires a exercise during cold continuous cooling water shutdown 2WR-040 2/A flow from the reactor building closed cooling 2WR-179 2/A water system.

Exercising these valves during oper-2WR-180 2/A ation interupts this flow from the reactor building closed cooling water system. This could result in damage to these pumps and thus place the plant in a less safe mode of operation.

t al 13

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Commonwealth Edison

('

LaSaHe County Nucker Station Unit 2 PUMP & VALVE TESTING Pago I

of I

RELIEF REQUESTS Ei E

ASME 33 PUMPOH

$O SECTION XI d

VALVE NO.

Jf FUNCTION TEST HEOulitEMENT BASIS FOR HEllEF ALTEHNATIVE IESI og a

Go of 02 03 04 05 06 RV-04 2E21-F005 1/B LPCS Injection Full Stroke These valves cannot be Perform a full stroir Line Outboard Exercise Quarterly exercised during normal exercise during cold Stop operation because they shutdown.

are electrically inter-2E12-F008 1/A RHR Shutdown locked shut by normal Cooling Pump 2A operating differential Suction HDR pressure to protect the Isolation Outboard low pressure piping outside the drywell.

2E12-F009 1/A RHR Shutdown Cooling Inboard Isolation 2E12-F050A 1/C RHR Shutdown Cooling Testable Check 2E12-F050B 1/C 2E12-F053A 1/B RHR Shutdown Cooling Discharge Isolation 2E12-F053B 1/B RHR Shutdown Cooling Discharge Isolation 2E12-F023 1/B RHR te Head Spray L

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Commonwealth Edison LaSalle County Nuclear Station Unit 2 sN-RELIEF REQUESTS s

i0 50 ASME 5

33 PUMP OH "O

SECTION XI VALVE NO.

FUNCTION TEST FIEOulitEMENT DASIS F OR FIEt IEF ALTEFINATIVE TEST 00 Of 02 03 04 05 06 2

RV-05 2E51-F013 1/8 RCIC Outboard in-Full Stroke Exer-During power operation, Pc? form a full jection Stop Valve cise Quarterly the RCIC piping is stroke exercise normally pressurized at during cold shutdown.

60 psig. One purpose of valve F013 is to isolate reactor pressure from the RCIC system.

Opening the valve would result in a water hammer of the RCIC piping, and the high reactor water pressure would cause damage to the low pressure piping on the suction side of the RCIC pump, which is designed for a maximum pressure of 100 psig.

l The valve may be exer-I cised during cold shutdowns when reactor pressure has been sub-stantially reduced.

1 ftl IIS

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j [ c Commonwealth Edison 1

PUMP & V ALVE TESTING Page 1 of 1

/ LaSaNo County Nuclear StaHon Unit 2 RELIEF REOUESTS s

i M

SO ASME 33 PUMP OH WO SECTION XI FUNCTION TEST HEOUlHEMENT BASIS F OR REllEF Al.iERNATIVE IES T o!

wo VALVE NO.

t Ky o

l 00 01 02 03 04 05 06 RV-06 2B21-F010A 1/AC Feedwater Inboard Exercise Quarterly A leak rate test must be Perfonn a full stroke Check Valve conducted in order to exercise each verify the closure of refueling outage 2B21-F010B 1/AC Feedwater Inboard these normally open Check Valve check valves.

This test is not possible during power operation or cold shutdown because a steady flow rate of coolant is passing through the feedwater lines.

These t

valves will be exercised at each refueling outage when the feed-water flow is interrupted n

i e st lJ

O O

o

i Commonwealth Edison Lassile County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 W

1 RELIEF REQUESTS Eb ASME P

PUMP OR

$0 SECTION XI 8

VALVE NO.-

FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE. TEST i

00 01 02 03 04 05 06 i

2B21-F065A 2/A Rx Feedwater Full Stroke It is impractical to Perfom a full stroke RV-07 Isolation valve Exercise Quarterly exercise these valves exercise during cold during nonnal operation

shutdown, a

2821-F0658 2/A because tim feedwater system is needed to maintain primary coolant inventory.

Exercising them would deprive tie flow of feedwater to the vessel tius putting tim plant in a less safe condition.

1 GF-t3

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Commonwealth Edison VJ LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 of I sb/

RELIEF REQUESTS F

So ASME y[O SECilON XI 33 PUMPOF4 F UNCilON TEST f1EOUlHEMENT B ASIS F OR f1Et IEF At.TEFINAYlVE TEST N

VALVE NO.

5 00 ol 02 03 04 05 06 RV-08 2G33-F001 1/A Inboard Suction full Stroke Exer-The entire RWCU system Perfonn a full stroke Isolation cise Quarterly must be inoperable exercise during cold before any of these shutdown 2G33-F004 1/A Outboard Suction valves can be closed.

Isolation This system maintains reactor water chemistry 2G33-F040 2/A Discharge to Feed-and prevents thermal water Isolation stratification of the water in the bottom head section of the vessel.

The systems operability is required during power operation to prevent fuel cladding reactions and to prevent thermal stresses in the vessel's bottom head section.

There fore, 1

these valves will be full stroke exercised durinq each cold shut-down.

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ASME SECTION XI 33 PUMP OR yO TEST REQUIREMENT HASIS FOR REllEF ALTERNATIVE TEST d

FUNCTION V ALVE NO.

04 05 06 u

00 01 02 03

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RV-09 2VQO26 2/M Outboard to Full Stroke These valves cannot be Perform a full stroke R4pression Exercise exercised during normal exercise during cold Chamber Fr. Rx Warterly operation. These valves shutdown.

are required to remain Oldg. Inboard administratively shut (PCIS) Isolation during power operation, Damper in accordance with the Final Safety Analysis 2VQ027 2/A Inlet to lleport and the Suppression Technical Specifications.

Chantler Fr. Rx The response to FSAR Oldg. Inboard (PCIS) Isolation Question 021.54 further explains that Danper valve 2V0032 cannot be 2VQ029 2/A Inlet to Drywel:

opened in an operating or hot shutdown mode, Fr. Rx. Oldg.

i and hence can only be Isolation Damper tested while in cold (PCIS)

@utdown.

Valve 2V0035 does not have 2VQ030 this restriction, and 2VQO31 2/A toction Fr.

hence is not contained S"lipression on this relief request.

I:hanber Inhoarti isolation lunper 9

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RELIEF REQUESTS I

E ASME 33 PUMP OR

$O SECTION XI us o VALVE NO.

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FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE TEST EE O<u 00 01 02 03 04 05 06 Perform a full stmke RV-09 2VQO34 2/A Suction Fr.

Full Stroke Drywell Inboard Exercise Quarterly exercise during cold shutdown.

Isolation DarMier PCIS 2VQO36 2/A Suction Fr.

Drywell Outboard Isolation Damper Oypass 2v0042 2/0 l

2VQ043 2/0 I

2VQO32 2/A Oypass Suction l

2VQ040 2/A Suction From Suppression Chairhe Outboard Isolation Dargler (PCIS) til-IT

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$0 SECTION XI us O VALVE NO.

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FUNCTION TEST HEOUlHEMENT HASIS FOR REtIEF At.TERNATWE TEST Ey o<o 00 01 02 03 04 05 06 RV-10 2E22-F016 2/C Suppression Pool Exercise Quarterly The llPCS system is demon-Exercise each refuel-4 Suction Check strated to be operable ing outage during each quarter by taking a HPCS alternate flow suction from, and dis-path test.

charging back to the cycled condensate storage tank. Cycled condensate is reactor grade water, however, this is not necessarily true of suppression pool water.

Valve F016 can be exer-cised by aligning the llPCS pump suction to the suppression pool.

Allow-ing suppression pool water to enter the 11PCS system permits the possibility of cycled condensate con-tamination which would cause many of the units' systems to become contami-nated.

This situation is undesirable at all times, but may be quarded aqainst if tested during refueling notages.

Therefnre, it is requested that this valve be full st rok e evert ised durinq ear.h refuelinq outaqc.

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LaSane County Nuclear Station Unit 2 RELIEF REQUESTS r

EO ASME 33 PUMP OR

$0 SECilON XI 3

VALVE NO.

FUNCTION TEST HEOUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RV-11 2E32-F001A 1/A MS Bleed Valve Full Stroke Exercise These valves camot be Perform a full stroke 2E32-F001E 1/A M5 Bleed Valve Quarterly exercised durirg normal exercise during cold 2E32-F00lJ 1/A MS Bleed Valve operation. These valves shutdown.

2E32-F00lN 1/A MS Bleed Valve are desityled to operate when the main steam line 2E32-F003A 2/B MS Loop Oypass 2E32-F003E 2/b to Steam Tunnel pressure is near atmospheric.

Testing 2E32-F003J 2/8 of these valves at 2E32-F003N 2/6 normal steam line 2E32-F002A 2/8 MS Loop Bleed 2E32-F00?E 2/8 Valve pressure has tre potential for a

2E32-F002J 2/8 dischargirg live steam 2E32-F002N 2/8 2E32 F006 2/U Oleed Valve-into the Heactor 2E32-F007 2/B Steam Tunnel building Atmosphere.

2E32-F008 2/U 2E32-F009 2/U l

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-3 PUMP OR QO SECTION XI syO VALVE NO.

FUNCTION TEST REQUlHEMENT BASIS FOR ret IEF AtTERNATIVE TEST 00 01 02 03 04 05 06 RV-12 2IN017 2/A Drywell Pneumatic Full Stroke Exer-As these valves cut off Perform full stroke to Drywell -

cise Quarterly the supply and discharge exercise coincident Fail Close side of the compressor with fail safe oper-from the drywell, they ation at each refuel-2II1001A 2/A Drywell Suction may be stroked closed ing outage.

Valves Isolations - Fail only when the nitrogen 21N043 and 2IN044 Close compressor is shutdown.

are not fail safe Normally, this occurs only tested.

2IN001B 2/A Drywell Suction during refueling outages Isolations - Fail because instrument nitro-Close gen is needed for control of the MSRV's, the in-21N074 2/A Dryer Purging Check the Fail Safe board isolation valves on Valve - Fail Close Operation of the MS, HPCS, LPCS, RHR, and Valve upon loss of RCIC, and the process 2IN075 2/A Dryer Purging actuator power each sampling line on RR.

The Valve. - Fail Close

quarter, instrument air alternate emergency supply cannot ZINO31 2/A Tip indexer Purge be used during power 4

Valve operation or cold shut-down as it would contami-2IN043 3/C ADS Supply Check nate the drywell nitrogen Valve atmosphere.

Therefore, these val,e wiD be 2IN044 3/C ADS Supply Check stroked at each refueling Valve outage when the drywell is de-inerted and the instrument nitrogen system is shutdown.

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ASME 33 PUMP OH

  • O SECilON XI gO VALVE NO.

M FUNCTION TEST REQUlHEMENT DASIS FOR REllEF ALTERNA11VE TEST g

o4 g

o 00 01 02 03 04 05 06 RV-13 2C41-F001A 2/B SBLC Pump Suction Full Stroke Exer-During the test'.nq of Perform a full stroke Stop Valve cise Quarterly these valves, the system exercise during is aligned so that a reactor refueling.

2 C41-F001B 2/B SBLC Pump Suction greater pressure exists on the downstream side of Stop Valve

~

the F001 valves than on the upstream side.

Opening the valves causes dilution of the sodium pentaborate solution in the SBLC solution tank.

Therefore, a chemical analysis of the solution will need to be performed, as required by the tech-nical specifications, to i

ensure that the concen-tration of boron in solution is within the required limits.

It is undesirable to perform this test during cold shutdowns due to the considerable length of time the testing pro-cedure and chemical analysis requires.

It is requested that the test-ing frequency for these valves be every refueling outano.

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LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS t

r EO ASME i3 PUMP OR QO SECTION XI VALVE NO.

FUNCTION TEST REQUIREMENT B ASIS FOR RELIEF AllERNATIVE TEST o

00 01 02 03 04 05 06 RV-14

?C41-F006 1/C Sa_C Outboard Exercise Quarterly These valves cannot be Exe mise during 1

Check exercised during reactor refueling.

reactor operation i

2C41-F007 1/C Inboard Check nor durng cold shutdown.

To exercise these l

valves open, tte system post inject into tie vessel.

A system injection is not practical during nonnal operation i

or cold shutdown; the explosive charges would have to be detonated and tim f

system taken out of I

service.

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LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page I

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VALVE NO.

FUNCTION TEST REQUIREMENT UASIS FOR RELIEF ALTERNATlVE IESI 00 01 02 03 04 05 06 RV-15 2E51-F064 1/A High Energy Line Full Stroke Exer-These valves are located Perform a full stroke Break Safeguard cise Quarterly at the interface of high exercise during RCIC Steam Outboard and low pressure piping.

cold shutdown.

Isolation Opening either valve during power operation 2E51-F091 1/A Warm-Up Bypass could result in pressure Valve line damage. The valves may be opened when reactor pressure is reduced during cold shutdown.

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So ASME 33 PUMP OH mo SECilON XI us O VALVE NO.

FUNCTION TEST HEOtllHLMENT D ASIS F OR REllEF AliERNAlfvE TEST Eg u u 00 01 02 03 04 05 OS RV-16 2821-FU24A 3/C M51V Accumulator Exercise Quarterly Entry into the drywell Exercise during Check Valves is reqitired to confirm reactor refueling the closure of these outage.

2821-F024B 3/C check valves.

Since the drywell atmosphere is 2821-F024C 3/C nonnally inerted with nitrogen gas at all 2821-F024D 3/C times except refueling outages, these valves 2821-F040C 3/C ADS Accumulator may be exercised only Check Valves during refueling outages when drywell 2821-F040D 3/C entry is possible.

2821-F040E 3/C 2821-F040R 3/C 2821-F040 S 3/C 2821-F040U 3/C 2B21-F040V 3/C l

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PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS b$

So ASME 33 PUMPOH

$O SECTION XI 8

VALVE NO.

FUNCTION T EST IlEOutflEMENT DASIS F OR IV.tlEF ALTERNATIVE TEST u

00 01 02 03 04 05 06 RV-17 2VP053A 2/A Chilled Water Return Full Stroke Exer-Closing any one of these Perform a full stroke cise Quarterly isolation valves would exercise during 2VP053B 2/A prevent chilled water refueling outages.

from reaching the primary 2VP114A 2/A containment cooling i

units. The systems 2VPil48 2/A operation is essential during power operation 2VP063A 2/A Chilled Water and is also necessary Supply during cold chutdowns to maintait, acceptable 2 VP063B 2/A condition <, in the drywell for equipment and main-2 VPil3A 2/A tenance personnel.

These valves will be exercised 2 VPil38 2/A at refueling outages when the heat input to 4

the drywell atmosphere is substantially reduced.

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RELIEF REQUESTS

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EO ASME

~13 PUMP OR

$0 SECTION XI VALVE NO.

FUNCTION TEST REQUIREMENT BASIS FOR REtlEF ALTERNATIVE TE ST i

00 01 02 03 04 05 08 RV-18 2033-F017A 2/C CRD Fk v CVA Exercise Since these lines form NA Dutlet Quarterly part of the reactor coolant pressure 2033-F0170 2/C CRD Flow CVB boundary, the conse-l Outlet quences of line failure was carefully evaluated.

It was 2 833-F013A 2/C CRD Flow CVA determined that conse-

[

Outlet quences of failure would be less severe than an l

2 B33-F0138 2/C CRD Flow CVO instrument line failure, Outlet thereby exempting these valves from Inservice Testing. (Ref. IWV-1300) i i

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LaSane County Nuclear Station Unit 2 pyyp & V ALViE TESTING Page 1 of 1 RELIEF REQUESTS DO SO ASME 33 PUMP OH

$O SECTION XI E8 VALVE NO.

M FUNCTION T EST i1EOUlflEMENT BASIS F OFI FIELIEF ALTEHNATIVE TEST o<

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00 01 02 03 04 05 06 RV-19 All Cateoory A N/A Perform a Seat Primary containment Seat leak test in primary con-leakage Test Per Category A isolation accordance with IWV-3420 valves will be seat 10CFR50 Appendix J.

tainment iso-leak tested and the lation' valves results analyzed in accordance with Appendix J requirements of 10CFR50.

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RELIEF REQUESTS IIi 5

ASME

~i 3 PUMP Oil

  • O SECTION XI y@

VALVE NO.

b'O FUNCTION T EST flEQUlllEMEN T UASIS f Oil flEt IEF ALIEf tNATlVE IESI 04 e

O 00 01 02 03 04 05 06 RV-20 Deleted i

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LaSelle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 1

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RELIEF REQUESTS s

SO ASME

~i 3 PUMP Oft "O

SECTION XI y@

VALVE NO.

If FUNCTION TEST F1EOuif1EMENT BASIS FOft flEllEF ALIEilNATIVE IESI a

O<O 00 G1 02 03 04 05 06 RV-21 Deleted k

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RELIEF REQUESTS IIi ASME 13 PUMP OH

$0 SECTION XI VALVE NO.

FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALIERNATIVE IESI O

00 ol 02 03 04 05 06 RV-22 2821-F022A 1/A Primary Containment Full stroke and Full stroke testing these Part stroke exercise Isolation for Main stroke time valves during normal quarterly, perform a Steam Inboard quarterly.

Check reactor operation requires full stroke exercise the fail-safe isolating one of the four and stroke time during 2B21-F022B 1/A Primary Containment operation of the main steam lines.

Isola-cold shutdown.

The Isolation for Main valve upon loss tion of these lines fail-safe operation Steam Inboard of actuator power results in primary system of these valves will quarterly.

pressure spikes, reactor also be checked 2B21-F022C 1/A Primary Containment power decrease, and in-during cold shutdown Isolation for Main creased flow in the un-since this is done Steam Inboard isolated steam lines.

coincident with full This unsymctrical oper-stroke exercising.

2B21-F022D 1/A Primary Containment ation can lead to a The fail-safe Isolation for Main reactor scram, and as testing of valves Steam Inboard discussed in NUREG-0626 2B21-F022A, B, C, and pressure transients D, however, will be 2821-F028A 1/A Primary Containment resulting from full stroke completed only at Isolation for Main te'. ting MSIV's increase cold shutdowns in Steam Outboard the :hanges of actuating which the primary primary system relief containment is 2B21-F028B 1/A Primary Containment valves.

It is proposed deinerted since access Isolation for Main that only partial stroke to the valves to Steam Outboard testing be performed perform this testing during power operation requires entry into 2B21-F028C 1/A Primary Containment and that the valve be the drywell.

Isolation for Main full stroked and stroke Steam Outboard timed during cold shut-downs.

This partial stroke exercising provides an acceptable means of verifying valve performanc2 i

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ASME 33 PUMP OH

  • O SECTION XI gO VALVE NO.

FUNCTION TEST REQUlHEMENT BASIS FOR REllEF ALIEHNATlVE IESI 00 01 02 03 04 05 06 RV-22 2B21-F028D 1/A Primary Containment during plant operation

(. ant'd)

Isolation for Main without affecting safety Steam Outboard margins.

This request also contributes to the reduction of the relief valves challenge rate as recommended in NUREG-0626.

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Commonwealth Edison PUMP & VALVE TESTING Pago 1 of 1

RELIEF REQUESTS r

50 ASME

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PUMP OH

$0 SECTION XI VALVE NO.

FUNCTION TEST HEQUlitEMENT BASIS FOR REllEF ALTEf tNATIVE lESI O

00 01 02 03 04 05 06 RV-23 Deleted i.e n

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RELIEF REQUESTS Ei$

EO ASME "3 3 PUMP Oft "O

SECTIOf1 XI y@

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FUNCTION TEST IlEOUlFlEMENT BASIS FOIlIlELIEF AL T EFINATIVE 1 ES I 00 01 02 03 04 05 06 RV-24 Deleted I

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Commonwealth Edison LaSalle County Nuclear Station i at 2 PUMP & V ALVE TESTING Page 1 of 2 RELIEF REQUESTS ASME w

33 PUMP OH

  • O SECilON XI VALVE NO.

FUNCilON TEST HEOUlHEMENT D ASIS F OR ret IEF AL TERNATIVE TEST g

o 00 01 02 03 04 05 06 RV-25 All valves in NA NA IWV 3417(b) and Specific relief is request-Evaluate the condition the program for IWV 3523 ed from the requirements of each valve with which IWV of paragraphs IWV 3417(b) respect to its safety 3417(b) and/or and IWV 3523 of Section related function and IWV 3523 XI of the 1980 Edition take appropriate apply.

of the ASME Boiler and corrective action Pressure Vessel Code in-as stated in the ciuding the Addenda Technical Specifica-through Winter 1980.

tion - Limiting These paragraphs state Condition for the corrective actions to operation.

be taken when valves fail to exhibit a required change of disk position.

3 l

These actions include requirements to take corrective action prior to plant startup should a failure occur during cold shutdown testing.

Also stated are requirements to declare valves in-operable if corrective action is unsuccessful within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

These paragraphs do not take into account the plant Technical Specifica-tion requirements for limitinq conditions for aperation which state the t.I 13

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Eo ASME 33 PUMPOH mo SECTION XI w0 VALVE NO.

M FUNCTION TEST flEOulitEMENT BASIS F OFI FIEllEF ALTEFINATIVE TESI Ey o<

04 05 06 u

00 01 02 03 minimum conditions RY-25 Continued necessary for safe opera-tion of the plant.

The failure of a particular valve may not necessarily i

require a plant shutdown or prevent a startup.

In addition, valves not capable of perfonning their safety-related function are declared inoperable as soon as that condition has been verified, not after a 24-hour period has elapsed.

For the above reasons, l.a Salle County Station will evaluate the condition of each valve With respect to its safety-related function and take the appropriate cnrrective action as stated in the Technical specificatinn - Limitinq Condition for Operation.

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RELIEF REQUESTS IIi ASME 33 PUMP OR

$O SECTION XI VALVE NO.

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FUNCTION TEST HEOUlHEMENT DASIS FOR HELIEF ALTERNATlVE 1ESI 00 01 02 03 04 05 06 RV-26 2Cll-F380 2/B CRD Scram Discharge Full Stroke and The system is designed Full stroke exercise Instrument Volume Stroke Time Quarterly such that the test quarterly.

Vent circuit bleeds air from these air operated valves 2Cll-F381 2/B CRD Scram Discharge at a very slow rate, Instrument Volume much slower than during Drain normal operation of the valve.

Thus, timing 2Cll-F388 2/B CRD Scram Discharge these valves during test-Instrument Volume ing has no relevance, and Vent because of the slow bleed rate, the test time 2Cll-F389 2/B CRD Scram Discharge repeatibility is poor.

Instrument Volume Drain s.t f3

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O LaSaneCountyNuclearStationUnit 2 Commonwealth Edison PUMP & VALVE TESTING Page 1 of 2

RELIEF REQU ESTS Ui ASME 33 PUMP OR

$O SECTION X1 VALVE NO.

FUNCTION TEST REQUIREMENT BASIS FOR REL IEF AL TERNATlVE 1ESI O

00 01 02 03 04 05 06 RV-27 2E12-F042A 1/B LPCI Injection Full Stroke Relief is requested from Perform a full stroke Valves Exercise Quarterly full stroke exercising exercise during cold 2E12-F042B these valves during shutdown.

normal reactor operation.

2E12-F042C The valves are interlocked closed with greater than 729 psid across them, which would require the LPCI pumps to be running to cycle the valves.

If the valve was opened (pump running) in this manner and the inboard testable check valve was to fail or leak, the low pressure piping would be subjected to reactor pressure.

This would lift the low pressure piping relief valve (500#) and provide a flow path for reactor pressure to the suppression pool. The relief line is only of 1 inch diameter, and depending on the amount of check valve leakage there exists the potential to severly overpressurize the low pressure piping.

Exercising these valves un

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RELIEF REQUESTS III E

ASME

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VALVE NO.

FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF AL TERNATIVE 1ESI n

00 01 02 03 04 05 06 RV-27 (Cont'd) provides single valve protection to the low pressure piping for the duration of the test, thus placing the plant in a less safe condition.

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ASME e

SECTlON XI 33 PUMP OR

$0 TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST S

VALVE NO.

FUNCTION 04 05 08 00 01 02 03 The vacuum breaker system Exercise during allows MSRV downcomer refueling outages.

RV-28 2821-F037Al 3/C Vacuum Breakers Exercise Quarterly pressure to equalize with drywell pressure as down-for The V.aln omer steam is condensed c

2821-F037A2 3/C Ste:3 r.elief in the suppression pool.

Valve 01scharge The 36 normally closed 2821-F037B1 3/C Lines.

check valves (2 on each downcomer) which comprise 2821-F03782 3/C this system are not equipped with an automatic 2B21-F037C1 3/C neans of actuation. Exer-tising these valves is 2821-F037C2 3/C achieved by manually push-ing the valve disc to its 2B21-F03701 3/C apen position with a small diameter rud. This testing 2821-F03702 3/C requires the removal of drywell floor grating in 2821-F037El 3/C arder to provide access to l

these valves. The radi-2B21-F037E2 3/C ation field in this area has a high dose rate, and 2821-F037F1 3/C the time required to test the 36 valves is substan-2 021-F037F2 3/C ti al.

Considering the interests of the ALARA j

2021-r05/G1 3/c 3rinciple, Edison feels that adequate testing of l

2 tul-F0 57t;2 5/l:

this system is achieved at i refueling frequency.

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00 01 02 03 04 05 l

HV-28 Caitinued 2.821-F037K1 3/C 2 021-F037K2 3/C 2 821-F037L1 3/C 2 821-F037L2 3/C 2 821-F037P1 3/C 2 6J1-F037P2 3/C i

2 B21-F037R1 3/C l

2 B21-F037R2 3/C 2 B21-F037S1 3/C 2 B21-F037S2 3/C 2 B21-F037VI 3/C 2 821-F037V2 3/C 2 ti/1-F0 5 /tli 3/C 2 021-FOiltIl 3/C Gt r3

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o<o 00 01 02 03 04 05 06 RV-29 Deleted I

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ASME 33 PUMP OH QO SECTION XI y8 VALVE NO.

4 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE IESI a

O<O 00 01 02 03 04 05 06 RV-30 2Cll-D001-126 NC/B Full stroke and There are 185 of each of Individual scram stroke time quarterly the valves listed, i.e.,

insertion tests will 2Cll-D001-127 NC/B check the fail-safe one for each of the 185 be performed per the operation of control rod drives. The Technical Specifi-2C11-D001-114 NC/C 2Cll-D001-126 and proper operation of each cation frequency.

2Cll-D001-127 upon of these valves is demon-t loss of actuator strated during scram power quarterly testing.

During scram testing each control rod insertion time is measured.

The Technical Specifications limit individual scram inser-tion times to specific values. The CRD Scram Test ensures that the above mentioned valves are functioning properly.

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ASME 33 PUMPOH "3 0 SECTION XI VALVE NO.

M FUNCTION TEST HEQUIREMENT BASIS FOR HELIEF ALTERNATIVE 1ESI e

04O oo 01 02 03 04 05 06 RV-31 2E51-F008 1/A RCIC Steam Supply Full stroke and The RCIC valves are on a Full stroke exercise Outboard Isolation stroke time line which provides steam and measure stroke quarterly to the turbine driven RCIC time during cold pump. They are designed shutdowns.

2E51-F063 1/A RCIC Steam Supply to provide a containment Inboard Isolation isolation function in the event of a downstream line break. Normally, however, they are left in the open position so that the line will be filled with steam up to the RCIC Turbine Steam Supply Stop Valve E51-F045. Maintaining the turbine supply line in this condition prevents the occurrence of a high pressura water hammer and assure s that the steam can be readily supplied to the turbine when the RCIC system is 1eeded.

Closing these t ntainment isolation valve during reactor power operation renders the RCIC system inoperable during this testing and introduces thc possibility that one, or both of the valves may stick in the closed position.

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ASME 3

PUMP OH WO SECTION XI idO VALVE NO.

FUNCTION TEST REOUlHEMENT B ASIS F OR RELIEF ALTERNATIVE TEST cp u o o0 01 02 03 04 05 06 i

RV-32 2 B21-F032A 1/AC Feeddater Outboard Exercise Quarterly A test operator is incor-An attempt will be Testable Check porated into the design of made to partially Valve these valves which is stroke these valves capable of closing the quarterly. A full 2 B21-F0328 1/AC valve through an angle stroke exercise will of 15*, and the valve is be perfonned each equipped with two posi-refueling outage.

tion indication lights for reporting disk positions of approximately 85% and 100~. of full open. These valves can be opened by feedwater flow only so a partial stroke exercise is possible only when the reactor is at high power and the feedwater flow has completely opened the disk. A full stroke exercise of these valves may be performed when feedwater flow increases from a no-flow condition to a maximum flow condi-tions following each refueling outage.

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$0 SECilON XI E3 VALVE NO.

>U FUNCilON TEST f1EOUIIIEMENT l1 ASIS I OR helle F ALTERNATIVE TEST l

Ug ot 00 01 02 03 04 05 06 RV-33 2821-F013C 1/8C ADS Relief Valve Exertise Quarterly Vendor specifications for Perform an 'in place' these ADS safety relief exercise at each 2821-F0130 1/BC valves require steam refueling outage.

pressure behind the 2821-F013E 1/BC disk before cycling.

Thus, the plant must be 2821-F013R 1/BC in an operating or startup condition with 2821-F0135 1/8C the required steam pressure in the main 2B21-F013tl 1/BC steam lines. These valves are located inside the 2821-F013V 1/BC drywell and considering the possibility of a stuck open valve, it is preferable that they be exercised either preceeding or fr.owing r

each refueline 'utage when the containment atmosphere is de-inerted.

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FUNCTION TEST REOUlHEMENT BASIS FOR REL IEF ALTERNATIVE TEST

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00 01 02 03 04 05 OS RV-34 All Nuclear 2/AC Excess Flow Check Exercise Quarterly, These excess flow check Full Stroke Exercise Boiler and Valves Leak Test During valves are designed to and Leak Test During Reactor Recir-Reactor Refueling automatically close Reactor Refueling culation Excess in the event of a down-Flow Check stream line rupture in Valves Indi-which flow exceeds 6.5 cated in the gpm, or if drywell Program pressure exceeds 1.69 psig. Upon closing, these valves are designed to allow a controlled leakage of approximately 0.5 gpm.

The lines are also provided with flow restricting orifices which would limit the potential offsite exposure to well below the guidelines of 10CFR100. Because exercising these valves requires that recircula-tion flow instrumentation and nuetron monitoring instrumentation be tempor-arily taken out of service the optimum time for functional testing these valves is during the routine vessel pressure test performed during each refueling outage.

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VALVE NO.

FUNCTION TEST HEQUlHEMENT DASIS FOR HELIEF AliERNATlVE IESI' 5

00 01 02 03 04 05 06 RV-35 2E22-F005 1/C HPCS Inboard Exercise During reactor power Exercise during Testable Check Quarterly operation, a differential cold shutdowns.

pressure of approximately 2E51-F066 1/C RCIC Inboard 1000 psi exists across Testable Check these inboard testable check valves. The 2E21-F006 1/C LPCS Inboard check valves are Testable Check equipped with test operators, however, the i

2E12-F041A 1/C RHR LPCI Inboard operators are not able Testable Check to function with such a high op across the l

2E12-F041B 1/C valve. The valves will be exercised against 2E12-F041C 1/C a reduced reactor pressure during cold 2E51-F065 1/C RCIC Injection shutdowns.

Outobard Testable Check i st l 's

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ASME E$

PUMP OR MO SECTION XI dO VALVE NO.

FUNCTION TEST REQUlHEMENT D ASIS FOR RELIEF AliERNATIVE TEST Ey o o 00 01 02 03 04 05 06 RV-36 2E51-F030 2/C RCIC Suppression Exercise Quarterly The check valve is partial Perform a full stroke Pool Suction Check stroke exercised each exercise during the Valve quarter by the perfor-RCIC alternate flow mance of a reduced flow path test at each test of the RCIC system refueling outage and alternate flow path, partial stroke the The opening of this valve valve each quarter.

is confirmed by the sus-tainence of suction pressure at the RCIC pump.

A quarterly full flow test is not performed for the alternate flow path because suppression pool water could potentially contaminate the cycled condensate system.

Each refueling outage a full flow test of the alternate flow path is conducted at which

' time this check valve is full-stroke exer-cised.

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RELIEF REQUESTS IIi ASME iD PUMP OH

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FUNCTION TEST HEOUlHEMENT BASIS FOR HELIEF ALTERNAllVE IESI 00 01 02 03 04 05 06 RV-37 2FC-086 2/A Rx Well Bulkhead Full Stroke and These valves are passive Leak test during Drain Outboard Stroke Time and iocked closed. They refueling outages.

Quarterly, Leak do perform a containment 2FC-ll3 2/A Cond. to Refuel Test During Reactor isolation function and Bellows Inboard Refueling will be leak tested.

However, these valves are 2FC-ll4 2/A Cond. to Refuel not required to change Bellows Outboard position during power operation or during an 2FC-ll5 2/A Rx Head Bulkhead emergency situation and Drain Inboard therefore, their ability to stroke will not be 2MC027 2/A tested.

2MC033 2/A 2SA042 2/A 2SA046 2/A t al f3

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