Text

Inservice Insp Program.Part B: Pumps & Valves
	ML20082B912
Person / Time
Site:	LaSalle
Issue date:	08/31/1983
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20082B864	List: ML20082B861; ML20082B873; ML20082B890; ML20082B912;
References
	PROC-830831-02, NUDOCS 8311210368
	Download: ML20082B912 (143)
	v • d • e

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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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! IN CONJUNCTION WITH f LA SALLE PROJECT ENGINEERING GROUP (DESIGN) l I

s 8311210368 831112 l PDR ADOCK 05000373 i.

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

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

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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.

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 4

relief is requested.

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

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

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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

( 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.

02 CLASS 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.

04 COORDINATES Pump coordinates on P&ID.

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 ::

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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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.

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

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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

. 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

Commonwraith Edison '

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

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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 Lcs ile county Nuclear Station Unit 2 l l

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 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 :

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 0.0333 hours 1.984127e-4 weeks 4.566e-5 months 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.

G U (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 '

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:

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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3) Commonwealth Edison 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.

e. The systems outside containment are protected from missiles 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

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

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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 Pa -

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

o rate.

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Commonwealth Edison kV e )7 usene counpudeer smuon unn 2

'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,

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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.

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) Commonwealth Edison

+/ LaSalle County Nuclear Station Unit 2 INSERVICE TESTING PLAN .

Systern DG - Diesel Generator

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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

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/ Commonwealth Edison INSERVICE TESTING PLAN .

Systern D0 - Diesel Oil

\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

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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) 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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TEST PAllAMETEfts TO DE MEASUFtED ic PilMP PUMP P&lD NUMBt.R flA M E CLASS NO COOIl sta Er oil r t o ow vautiA. uEAlutui TEST If4 TLilVAL SPEID PHfSS PttiSS #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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O O O Commonwealth Edison INSERVICE TESTING PLAN LaSalle County Nuclear Staten Unit 2 systern SC - Standby Liquio Control kC'v) P, UMPS page 1 or 1 PilMP PUMP P&lD NUMOLH HAME NO 'COOil INE EI Oli f f l OW VluftA.

CLASS l 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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( 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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Q) Commonwealth Edison LaSane County Nuclear Stauori unit 2 INSERVICE TESTING PLAN 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

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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

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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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2. ,) 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 4 I deteriorated to a point 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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Commonwealth Edison PUMP & V ALVE TESTING Page 1 W l tasane county Nucknar Station Unit 2 j s\ RELIEF REQUESTS i

! DE N yO ASME SECTION XI 33 PUMP OR ALTERN ATIVE TEST i

%g VALVE NO. >f O<

FUNCTION TEST REOUIREMENT BASIS FOR REllEF U

01 02 03 04 05 06 00 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 j

primary purpose is to allowable pressure LPCS water Le9 maintain the ECCS pump limits.

i 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 2 of tie discharge line l 2E12-C003 within allowable stanrthy l pressure limits.

1 RCIC Water 2 1herefore, there is

Leg Pump 2E51-C003 actually no flow criteria 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 j ,

of the waterleg panps is i

maintenance of pressure, j this is the parameter lint is considered for J

4 inservice testlinj.

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

' \ RELIEF REQUESTS Ili{0 mb ASME 73 PUMPOil "O SECTION XI y@ VALVE NO. $ FUNCTION TEST IIEOUlFlEMENT BASIS FOIL llELIEF ALIEflNATiVE IESI a o$<

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'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 --

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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1-1) Commonwealth Edison PUMP & VALVE TESTING Page 2 of 3 y >] LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS e >

Ui$ Ed ASME 13 PUMPOlt $O SECTION XI

%g VALVE NO. _sf 04 FUNC110N T EST IlEOulflEMENT BASIS F OR REL IEF ALIEf ttJATIVE ICSI 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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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.

$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 -

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

\/ RELIEF REQUESTS r >

Ui$ N ASME 33 PUMP Oft VALVE NO.

$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.

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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] 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<

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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

d N ASME SECTION XI 33 PUMPOH VALVE NO.

$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

! 2L12-C0028 accomodate pressure reference value or inlet pressure of the rises of pump l

Remove Decay Heat less. RHR water len pump is RHR Pur.1p C t suction.

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

! 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

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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 >

, DO EO ASME

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PUMP OH SECTION XI yO FUNCTION TEST HEOtllHEMENT DASIS FOR REllEF Alif RNATIVE TEST g

VALVE NO.

$[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 '

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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!NSERVICE TESTING VALVES Unit PLAN 2 system CM-Containment Monitoring P8G* 1 2

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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)

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, 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)

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 S0 0 FS, GB 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 rs 0 C 5 RV-02 A GE-T 2 -1180

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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)

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

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00 01 02 03 04 j 05 f 06 07 08 09 10 11 12 13 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 2DG-036 1.5 134-02 E2 3/C CV -

C E Q A LPCS Pump Motor Cooler Outlet Check GE-T 2 -1180

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'V (V V Commonwealth Edison

@ 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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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 -

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

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> 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 -

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 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

Commonwealth Edison

@ LaSalle County Nuclear ,

Station VALVES Unit 2 1NSERVICE TESTlNG PLAN sysi m FW-Feedwater

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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 -

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)

PIT RR IB21-F032B 24 118 C6 1/AC NT A0 0 E RR RV-32 A Rx Feedwater Line Check l

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)

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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@ 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

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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(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

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+' $ g-h 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)

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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

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 .

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 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.

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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 -

C E Q A HPCS Pump Discharge Check 2E22-F007 3/4 141 C4 2/C NSC -

0 E Q A HPCS Water Leg Pump 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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f'1 v U Commonwealth Edison

@ LaSalle County Nuclear Station Unit p 2 pop IN-Drywell Instr. Nitro.

1 of 3 VALVES

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 -

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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system IN - Drywell Instrument Nitrogen OLa e Coun y Nuct a Sta i Unit 2 INSERVICE TESTING PL AN VALVES "*8* '

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)

LT RR RV-19 (M-47)

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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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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

9 oO Y A 3 c,A .O gh 00 01 02 03 04 05 06 07 08 09 11 12 13 iu /

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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Otas e co n y Nu I a Sta o Unit 2 INSERVICE TESTING PLAN VALVES system LP-Low Pres. Core Spray

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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

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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)

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O O O O LaSa eCo n yNucl a Sta o Unit INSERVICE 2 PLAN TESTING VALVES gstem 2 MS-Main team

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(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)

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. (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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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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! 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)

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)

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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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. 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 (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 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

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)

.?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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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 -

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138-1 C5 3/C CV C E RR RV-28 A Vacuum Breakers 2B?l-F037K1 12 -

2B21-F037K2 12 138-1 C5 3/C CV - C E RR RV-28 A Vacutan Breakers 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 2821-F037R1 12 138-1 C5 3/C CV - C E RR RV-28 A Vacuum Breakers 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 2B21-F03752 12 138-1 C5 3/c CV - C E RR RV-28 A Vactaan Breakers I

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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 -

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C E RR RV-28 A Vacuum Breakers 2B21-F037N1 12 138-1 C6 3/C CV -

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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

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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

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

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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

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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)

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)

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)

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)

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.

LT RR (See Note 4)

B4 2/A CNY A0 C FS,ST ] 20 RV-19 A Drywell Floor Sump 2RF013 2 137-4 Suction (M-93) F.C.

LT RR (See Note 4)

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FS,ST Q 100 A R R Heat Exchanger j 2E12-F0038 18 142-4 C8 2/B GT M0 O Outlet Stop.

MO O FS,ST Q 132 RV-19 A RR Oatboard suction

! 2El?-F004A 24 142-1 A7 2/A GT from Suppression Pool LT RR

! (M-70)(See Note 4,6,11)

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)

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)

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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)

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

O O O INSERVICE TESTING PLAN system RH-Residual Heat Removal

@ CommonwealthEdison tasaite county Nuclear Station Unit 2 VALVES Page 2 of j j.

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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)

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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 ,

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M0 C FS,ST Q 88 RV-19 A fHt Containment Spray 2E12-F0178 16 142-2 F6 2/A GT LT

RR Downstream Isolation (M-19) (See flote 4,6) 2/C RV RR A H Pump A Discharge

2E12-F025A lx2 142-1 E3 RV SP C Header Rellef (M-85)

' (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

Header Reller (M-86) i i

(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)

(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

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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)

(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

/3 t

' G Om i system RH-Residual Heat Removal INSERVICE TESTING PLAN of 11 OLa eC n y Nuct a Sta l Unit 2 Page 5 VALVES Ob

) O q.

9 O e, s e,A s.

o 10 11 12 13 07 08 09 00 01 02 03 04 / 05 06 ,

E CS RV-35 A RR LPCI Testable O*

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)

AG C E CS RV-35 A RR LPCI Testable O*

12 142-3 E7 1/AC NSC Inboard Stop (M-12) 2E12-F041C PII RR RV-19 LT RR (See Note 1,5,7)

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)

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)

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)

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 -

Hypiss chect<

l l

l

- - - _ - _ ~ - . -

O O O system RH-Residual Heat Removal Commonwealth Edison INSERVICE TESTING PLAN Page (, of ]}

LaSaue County Nuclear Station Unit 2 VR ES f # / /,/ C f *'# ,# p# ,$ l j#

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 ,

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)

(See Note 1,S,7)

O O La a e C un y Nuclea Sta i Unit 2 oge et 9

00

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01 uf:%

02 03 04 05 06 07 08 09

,Q'//

to 11 12 13

/

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

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.

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 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 -

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)

GE-T2 t I80

(G 3 a L) p) u.

Commonwealth Edison O LaSalk County NuckarINSERVICE StationVALVES Unit TESTING 2 PLAN system RH-Residual Heat Removal

"* 9 II

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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 -

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

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 ,

4 40 oo e,9 4r 40* c,A k g.O [

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 -

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 2E12-F331C 16 134-1 E6 3/C ilSC -

C E Q A RHR Service Water Pump 2C Discharge Check 2E12-F3310 16 134-1 F6 3/C f1SC -

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 -

C RV RR A RHR Heat Exchanger Relief (See flote 2)

GE T2 It00

O O O Commonwealth Edison INSERVICE TESTING PLAN systam RH-Residual Heat Removal O LaSalleCountyNuclearStationUnit 2 VALVES

"*"* 11 11

4# oO e,> t s y g,e* k gc 4

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 -

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

O O O

@ 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*

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)

(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 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 -

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

@ LaSaile County Nuclear Station y y g Unit 2 Page of

U 4Y 9 oO e*

p>' at A y c

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 -

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

/

' O 4Y 9 oO 4 A yd -

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)

GE 72 1180

O O O Commonwealth Edison ,

O tasanecountyNuclearINSERVICE StauonUnit VALVES 2

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- +

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 -

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

O O O La e C un y Nuct a Sta i Unit 2 y

) on 00

/

01 mf6%4g//

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 Commonwealth Edison Syewm RR-Reactor Recirculation O LaSaue County Nuclear .

Station INSERVICE TESTING PLAN VALVES Unit 2 "*" 2 # 3

9# 00 e,) r$ c,A

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 -

0 E RR RV-34 A See Note 10 LT 2833-F311A .75 2139-2 2/AC EFC -

0 E RR RY-34 A See Note 10 LT 2833-F3118 .75 2139-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 2833-F311C .75 2139-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 2B33-F311D .75 2139-2 2/AC EFC -

0 RR RV-34 A See Note 10

{

.75 2139-3 2/AC EFC -

0 E RR RV-31 A See Note 10 2B33-F315A LT

.75 21 39-3 2/AC EFC - 0 E RR RV-34 A See Note 10 2B33-F3158 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 LT i f 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

9 O sh Y su & sA 4~ .O $

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 0 EFC -

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

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*

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)

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) 2G33-F339A 1.5 137s2 E8 3/C RV - C RV RR A RWCU Hu Peller (See 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 La e Co n y Nuci a Sta l Unit 2 gstem R -Reactor Water Cleanup

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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)

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

"*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)

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 Unit 2 INSERVICE TESTING VALVES PLAN system SC-Standby Liquid Control

"*8' I ' I

# 00 c, s cf '? .O $

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 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

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

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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

(*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)

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)

PIT RR FS ST RR 90 RV-17 A Water Supply 2 VPil30 8 133 82 2/A BF M0 O

(*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)

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)

LT RR 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

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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)

Isolation Damper (M-66)

(See Note 1)

CS 130 RV-09 P Inlet to Suppression C3 2/A BF M0 C FS,ST Chenher Fr. Rx. Bldg.

2VQ027 26 138-1 RR RV-19 LT Inboard (PCIS)

Isolation Damper (M-66)

/

(See Note 1)

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)

(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)

! (M-20)(See Hote-1.4.6)

CS 130 RV-09 A Suction Fr Rx. Bldg.

2/A HF M0 C FS,ST l 2VQO31 26 138-1 C1 LT RR RV-19 inboard Isolatinn l

Damper (PCIS) (M-67) l (See Note 1)

$ h *$ h hh'

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

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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)

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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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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)

(See Note 1,4) 2VQ041 26 138-1 A8 2/B BF M0 C FS,ST 90 Q 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 23 RV-19 Q 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 FS.ST 90 C CS RV-09 (See Note 1,4)

LT RR RV-19 l

2VQ043 8 138-1 C2 2/A BF M0 FS.ST 90 C CS RV-09 (See Note 1.4)

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( P)/ LaSalle CountyNuclearStation Unit Commonwealth Edison PUMP2& 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

13 O J n

/ o ) Commonwealth Edison

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

'v RELIEF REQUESTS Iii ASME 13 PUMP OH $0 SECTION XI NE VALVE NO.

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.

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

O O O

/' N

/ R) Commonwealth Edison (A/V"/ LaSalle County Nuc' ear Station Unit 2 PUMP & VALVE TESTING RELIEF REQUESTS Pago 2 of 2 e >

IiiO EO ASME 33 PUMPOft "O SECTION XI y@

e VALVE NO. M 04 FUNCTION TEST REQUlllEMENT BASIS FOR HELIEF AL TEllNAllVE IESI 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

\

2CM031 2/A ' i 2CM032 2/A 1 N

2CM033 2/A 'N 2CM034 2/A t al (3

l O O O 7m i

/

c) Commonwealth Edison

\ ' "J LaSalle County Nuclear Station Unit 2 i

PUMP & VALVE TESTING Pago 1 of 1 RELIEF REQUESTS Ili 5 ASME 33 PUMP OH VALVE NO.

$0 FUNCTION SECTION XI 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.

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l O O O n

[ C) Commonwealth Edison

(' '"

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.

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

O O O E _) Commonwealth Edison s LaSalle County Nuclear Station Unit 2 N-RELIEF REQUESTS s >

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

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

l O O O j [ c1 ; ,% Commonwealth Edison

/ LaSaNo County Nuclear StaHon Unit 2 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REOUESTS s

i M 33 PUMP OH SO WO ASME SECTION XI

wo VALVE NO. $ FUNCTION TEST HEOUlHEMENT BASIS F OR REllEF Al.iERNATIVE IES T t Ky o!

, 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 ,

i n e st lJ

O O o

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

' RELIEF REQUESTS Eb ASME

$$ SECTION XI P PUMP OR $0 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE. TEST i 8 VALVE NO.-

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.

Exercising them would deprive tie flow of feedwater to the vessel

tius putting tim plant in a less safe condition.

1 GF-t3

O O O l Commonwealth Edison s VJ LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 of I b/ RELIEF REQUESTS F

$$ 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

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.

2 i

t .I l 's

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

33 PUMP OR yO TEST REQUIREMENT HASIS FOR REllEF ALTERNATIVE TEST V ALVE NO. ; FUNCTION u 05 06 03 04 00 01 02 ,

~n i

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.

Warterly operation. These valves Chamber Fr. Rx 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 Inlet to Drywel: opened in an operating 2VQ029 2/A or hot shutdown mode, Fr. Rx. Oldg.

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

@utdown. Valve

" 2V0035 does not have 2VQ030 this restriction, and 2/A toction Fr. hence is not contained 2VQO31 on this relief request.

S"lipression I:hanber Inhoarti isolation lunper 9

O o O i Oh Commonwealth Edison PUMP & V ALVE TESTlNG Pat 2 2 of 2 LaSalle County Nuclear Station Urtil 2

'\~ %

RELIEF REQUESTS E ASME I SECTION XI 33 PUMP OR $O FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE TEST

us o VALVE NO. J$

EE O<

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 '

shutdown.

' Isolation DarMier PCIS 2VQO36 2/A Suction Fr.

Drywell Outboard Isolation Damper Oypass 2v0042 2/0 2VQ043 2/0 l

I 2VQO32 2/A Oypass Suction l

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

O O C D) O

[\ U 7 LaSalle County Nuclear Station Unit Commonwealth Edison PUMP2 & VALVE TESTING Page 1 of I

\ ,

RELIEF REQUESTS s

Iu, ASME SECTION XI 33 us O PUMPOH VALVE NO.

$0 s "' FUNCTION TEST HEOUlHEMENT HASIS FOR REtIEF At.TERNATWE TEST o<

Ey o 02 03 04 05 06 00 01 4

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.

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.

. ..i,

O o o Commonwealth Edison

( LaSane County Nuclear Station Unit 2 PUMP & V ALVE TESTING RELIEF REQUESTS Page 1 of 1 r

EO ASME

$$ SECilON XI 33 PUMP OR $0 FUNCTION TEST HEOUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 3 VALVE NO.

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.

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

" atmospheric. Testing 2E32-F003J 2/8 " "

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 "

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

2E32-F007 "

2E32-F008 2/U 2E32-F009 2/U GL13

O O O

/ Commonwealth Edison

( '] LaSalle County Nuclear Station Unit 2 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS s- >

'M Eo ASME

-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- -

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 4

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.

O O O Commonwealth Edison LaSalle County Nuclear Stauon unit 2 PUMP & V ALVE TESTING Page 1 of 1

' REllEF REQUESTS

$$ N

O ASME SECilON XI 33 PUMP OH ALTERNA11VE TEST gO g g

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.

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

~

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-i nical specifications, to 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

. . . ei

,D O O o

( JL) Commonwealth Edison Page 1 of 1 PUMP & VALVE TESTING

( ' #"

LaSalle County Nuclear Station Unit 2 RELIEF REQUESTS t r EO ASME

$$ SECTION XI i3 PUMP OR QO FUNCTION TEST REQUIREMENT B ASIS FOR RELIEF AllERNATIVE TEST VALVE NO.

o 06 02 03 04 05 00 01 -.

1 Exercise Quarterly These valves cannot be Exe mise during RV-14 ?C41-F006 1/C Sa_C Outboard Check exercised during reactor refueling.

reactor operation i

1/C Inboard Check nor durng cold shutdown.

2C41-F007 To exercise these l

valves open, tte system post inject into tie vessel.

A system injection is not practical i

during nonnal operation or cold shutdown;

' the explosive charges would have to be detonated and tim system taken out of fI service.

1 i

f 3

0t 13

O O O

[h

[ g) Commonwealth Edison LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Page I of I f

(' %

RELIEF REQUESTS Ili ASME 33 PUMP OH QO SECTION XI

@@ 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.

t al 13 '

O O b (7

s Commonwealth Edison 7 Lesene County Nuclear Stetton Unit 2 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of I L/ .

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.

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

. .. n

_________ ___________ _ _ _ _ _ _ _ _ _ _ . _ _ J

O O O -

1 Commonwealth Edison

['( 'v']) LaSalleCountyNuclear PUMP StationUnit

& 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.

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.

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 4

when the heat input to the drywell atmosphere is substantially reduced.

t el f:s

a O O O E Commonwealth Edison Page 1 of I D LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING l

RELIEF REQUESTS i

. p EO ASME

$$ SECTION XI

~13 PUMP OR $0 FUNCTION TEST REQUIREMENT BASIS FOR REtlEF ALTERNATIVE TE ST VALVE NO.

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-

, 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

[

2/C CRD Flow CVO be less severe than an ',

' 2 B33-F0138 instrument line failure, Outlet thereby exempting these valves from Inservice Testing. (Ref. IWV-1300) i i

i i

1 1

I c.w ss

O O O Commonwealth Edison 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 g VALVE NO. M o<

FUNCTION T EST i1EOUlflEMENT BASIS F OFI FIELIEF ALTEHNATIVE TEST o

00 01 02 03 04 05 06 Perform a Seat Primary containment Seat leak test in RV-19 All Cateoory A --

N/A Category A isolation accordance with primary con- leakage Test Per 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.

I s .t 13

O O O Commonwealth Edison

@ LaSalle County Nuclear PUMP Station

& VALVE TESTING Unit 2 Pago 1 of 1 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 e 04 O

00 01 02 03 04 05 06 RV-20 Deleted 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 >

$$ 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

e,f 13

(v) (

%.) %.;)

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

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

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(O) j LaSalle County Nuclear Station Unit 2 PUMP & VALVE TESTING Pago 2 of 2 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.

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i Commonwealth Edison O LaSalleCountyNuclearStationUnit PUMP & VALVE TESTING 2 Pago 1 of 1 RELIEF REQUESTS r >

$$ 50 ASME

~.i ') PUMP OH VALVE NO.

$0 FUNCTION SECTION XI 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

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Las sie county Nuclear Station Unit 2 PUMP & VALVE TESTING RELIEF REQUESTS Pago 1 of 1

. 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.

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

- 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 3

change of disk position.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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

'~ RELIEF REQUESTS e ASME M Eo SECTION XI 33 PUMPOH mo BASIS F OFI FIEllEF ALTEFINATIVE TESI w0 Ey VALVE NO. M o<

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

valve may not necessarily 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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( ' ' ' LaSane County Nuclear Station Unit 2 PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS IIi ASME 33 PUMP OR $O SECTION XI

%" VALVE NO. FUNCTION TEST HEOUlHEMENT DASIS FOR HELIEF ALTERNATlVE 1ESI 00

[$ 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.

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.

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O f] ^s L) U (O Commonwealth Edison O LaSaneCountyNuclearStationUnit PUMP & VALVE TESTING 2 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

O O O Commonwealth Edison O LaSalle County Nuclear PUMPStation

& VALVE TESTlNGUnit 2 Pago 2 of 2 RELIEF REQUESTS III E ASME

~i 3 PUMP OH SECTION XI y@ VALVE NO.

[$0 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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Commonwealth Edison Page of I

P)J LassNeCounty Nuclear Stanon Unit PUMP 2 TESTING

& V ALVE

\, d ' RELIEF REQUESTS e

DE N ASME SECTlON XI 33 PUMP OR $0 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST S VALVE NO.

04 05 08 00 01 02 03 The vacuum breaker system Exercise during allows MSRV downcomer refueling outages.

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.

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 2 tul-F0 57t;2 5/l: this system is achieved at l

i refueling frequency.

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, O O O 2,,,) Commonwealth Edison d

Lasone county Nuclear Station Unit 2 PUMP & VALVE TESTING Pa98 2 3

\- RELIEF REQUESTS u$ E ASME l b yAty FUNCTION TEST E U RE ENT BASIS FOR RELIEF ALTERNATIVE TEST zw .

o<o t E 01 02 03 04 05 #

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

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

( PUMP & VALVE TESTING Paoo 1 of 1

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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

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O O O i Commonwealth Edison

( L' } LasaHe County Nucker Stenon Unit 2 PUMP & VALVE TESTlNG Page 1 of l b

RELIEF REQUESTS Uib b ASME 33 PUMP OH QO SECTION XI y8 a

VALVE NO. 4 O<

FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE IESI 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

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J LesesleCountyNuclearStationUnit 2 PUMP & VALVE TESTlNG RELIEF REQUESTS Page 1 of 1 II) ASME 33 PUMPOH "3 0 SECTION XI

%e VALVE NO. M 04 FUNCTION TEST HEQUIREMENT BASIS FOR HELIEF ALTERNATIVE 1ESI O

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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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 $,

WO ASME 3 PUMP OH SECTION XI idO VALVE NO. FUNCTION TEST REOUlHEMENT B ASIS F OR RELIEF ALTERNATIVE TEST cp u o

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.

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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Commonwealth Edison Lasalle County Nuclear Station Uni 2

' 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.

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 2821-F013V 1/BC

" " 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 '

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 .

DO N ASME SECilON XI 33 PUMPOf4 $O

^

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 ,

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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[ 2_) Commonwealth Edison PUMP & V ALVE TESTING Pago 1 of 1

( ] LesonecountyNuclearStationUnit 2 b RELIEF REQUESTS Ui ASME 33 PUMP OH SECTION XI d" VALVE NO.

[$O 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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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

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.

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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O O O rh Commonwealth Edison

[( ::: )7 LaSalle County Nuclear Station

- ' ' Unit PUMP & 2VALVE TESTING Pago 1 of 1

\/ 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

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ML20082B912

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