Text

Addenda to Inservice Insp Program Rept & Instructions for Updating Rept
	ML20071C445
Person / Time
Site:	LaSalle
Issue date:	01/31/1983
From:	; GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20071C439	List: ML20071C438; ML20071C445;
References
	NUDOCS 8303020079
	Download: ML20071C445 (139)
	v • d • e

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LA SALLE COUNTY STATION S UNIT 1 G INSERVICE INSPECTION PROGRAM REPORT INSTRUCTIONS FOR UPDATING Before updating your Inservice Inspection Program Report, please remove from volume 2 Tabs 22 through 30 and 'the material following each of the tabs and place them behind Form GE-Il in Section 21 at the end of Volume 1.

To update your La Salle County Station Unit I Inservice Inspection Report, remove the following pages and insert the following pages:

REMOVE INSERT VOLUME 1 Cover sheet Cover sheet, Tab for Part A, and title sheet for Part A VOLUME __2

/~ \ Cover sheet Cover sheet, Tab for Part A kl (Cont'd) , 'and title sheet for Part A After Page GEL-1103 Tab for Part B, title sheet for Part B , Tab 1, Table .

of Contents, Tab 2, Pages 1 and 2, Tab 3, Pages 1 through 7, Tab 4, Pages DG, DO, FC, HP, SC, RH, RI, LP , Tab 5, RP-01 Pages 1 and 2, RP-02, RP-03, RP-04

Pages 1 and 2, RP-05, RP-06, l RP-07, RP-08, RP-09, Tab 6, CM Pages 1 and 2, DG, DO, FC, FW, HG Pages 1 and 2, HP Pages 1 and 2, IN Pages 1 through 3, LP, MC, MS Pages 1 through 11, NB Pages 1 through 3, PC, RD, RE, RH Pages 1 i through 11, RI Pages 1 8303020079 830218 through 4, RR Pages 1 through PDRADOCK05000fj G 3, RT Pages 1 and 2, SA, SC , VP , VQ Pages 1

through 3, WR, Tab 7, RV-01, s_-

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LA SALLE COUNTY STATION UNIl 1 INSERVICE INSPECTION PROGRAM REPORT INSPRUCTIONS FOR UPDATING (Cont ' d) ~!

l REMOVE INSERT 1 t.

RV-02 Pages 1 and 2, RV-03, RV-04, RV-05, RV-06, RV-07, RV-08, RV-09 Pages.1 and 2, RV-10, RV- ll , RV- 12 , RV- 13 , RV- 14 ,

RV-15, RV-16, RV-17, RV-18, P.V-19, RV-20, RV-21 Pages 1 and 2, RV-22 Pages 1 and 2, RV-23 Pages 1 and 2, RV-24, RV-25 Pages 1 and.2, RV-26, RV-27 pages 1 and 2, i RV-28 Pages 1 through 3, l RV-29, RV-30, RV-31, RV-32, '

RV-33, RV-34, RV-35, RV-36, and RV-37.

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INSERVICE INSPECTION PROGRAM PART A: PIPING SUBSYSTEMS, COMP 0NENTS AND COMPONENT SUPPORTS, AND NRC REQUIRED AUGMENTED INSERVICE INSPECTIONS PART B: PUMPS AND VALVES Q

LA SALLE COUNTY STATION l

UNIT 1 COPNONWEALTH EDISON COMPANY

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. PART A: PIPING SYSTEMS i-I i l s

'IN5ERVICE INSPECTION PR0 GRAM i

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INSERVICE INSPECTION PROGRAM i ,

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! PART A: PIPING SUBSYSTEMS, COMP.0NENTS AND COMPONENT SUPPORTS, AND NRC REQUIRED AUGMENTED INSERVICE INSPECTIONS '-

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j PART B: PUMPS AND VALVES 3 8 4 O 4 I

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PART A: PIPING SYSTEMS INSERVICE INSPECTION PR0 GRAM

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LA SALLE COUNTY STATION.

jUNIT1 j- COMMONWEALTH EDISON COMPANY i

' JANUARY 31, 1983 k

PREPARED BY

{ GENERAL ELECTRIC COMPANY INSTALLATION & SERVICE ENGINEERING DIVISION

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PART B: PlNPS AND VALVES INSERVICE INSPECTION PR0 GRAM

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LA SALLE COUNTY STATION UNIT 1 CDPNONWEALTH EDISON COMPANY JANUARY 31, 1983 4

! PREPARED BY GENERAL ELECTRIC COMPANY INSTALLATION & SERVICE ENGINEERING DIVISION l AND l

LA SALLE STATION TECHNICAL STAFF (OPERATIGE.3)

IN CONJUNCTION WITH s

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LA SALLE PROJECT ENGINEERING GROUP (DESIGN) 1

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g Ccmmonw ahh Edison LcSalk County Nuckw Sttson Unst 1 l O

PIMP AND VALVE INSERVICE TESTING PLAN TABLE OF CONTENTS Description Tab Table of Contents 1 Inservice Testing Plan - Description 2 i Fomat t.egend and Notes 3 I

Inservice Testing Plan - Pumps 4

. Relief Requests - Ptaps 5 Inservice Testing Plan - Valves 6 l

Relief Requests - Valves 7 i

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'" LaSalle County Nuclear Statson Unit 1 l

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 tnrough Winter 1980 Addenda, except where specific written relief from examinations and testings determined to be impractical has been granted by the NRC pursuant to 10 CFR Part 50, Section 50.55 a (g) (6) (1) . Known relief requests from ASME Code Sectien 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-3000.

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.

v 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 with 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 contai'ns the following information as a minimum.

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

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

3.1.3 ASME Section III code Class and Category s (valves only).

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Commonw:ahh Edison i sSalle Coimly Nuc4wer Station Unit 1 O -

3.1.4 The specific ASME Code requirement that is i determined to be impractical.

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

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

i 3.3 All records and reports are prepared in accordance with ASME Section XI IWA-6888.

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Commonw:alth Edison L cSalle Coiuity Nuclw St:Inm Urut 1 INSERVICE TESTitC PLAN FORMAT LEGEND AND NOTES I. ASE CLASS 1, 2. AND 3 P.WS FIELD _ DESCRIPTION 00 PJF NJMEER Pump nuncer as used on the P&ID.

01 PLW NAE Pump word description and name.

02 CLASS ASE Section III Code Classification (1, 2, or 7).

03 P&ID NO. Piping and Instrumentation Drawing Nunter. All drawing numbers are prefixed with "M". Sheet nuncers follow the drawing numoer.

04 COORDINATES Pump coordinates on P&IO.

05 SPEED Speed of pump to be measured. N/A - Not Applicable. All the pumps with N/A in the speed colum are either synchorous or induction motor driven and do not require speed measurements.

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

07 OIFF. PRESS. Differenti'l pressure of pump to be measured, N/A, Not apSiSble for positive displacement gumps.

08 FLOW RATE Flow rate of gump to be measured 09 VIBRATION Vibration amplitude of pump to be measured. - See RP-04.

10 BEARING TE)P. Bearing temperature of pump to be measured - See RP-01.

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

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Commonw:ahh Edb:n L sSW County Nuckar Station Uma 1 II ASE CLASS 1, 2, AND 3 VALVES FIELD DESCRIPTION W VALVE RMER Valve number as used on the P&ID. '

01 SIZE Nominal size of valve in inches.

02 P&ID NO. Piping and Instrumentation Drawing Nuncer. All drawing nunbers are prefixed with "M". Sheet nuncers follow the drawing number.

03 COORDINATES Valve location on P&ID.

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

05 VALVE TYPE AG Angle EL Ball BF Butterfly CNV Control Valve 08 Dottle Block EFC Excess Flow Check FCV Flow Control Valve GB Globe GT Gate WC Manual Flow Control NV 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 l EX Explosive l

M Manual M0 Motor Operated 50 Solenoid Operated SP Spring l

l 07 VALVE POSITION C Normally Closed 0 Normally Open L.O. Locked Open L.C. Locked Closed Page 2 -

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/ c ) Comm:nw:alth Edi=n (v9 ) t esas conniy nucwr swiun una i II ASE CLASS 1, 2, Ato 3 VALVES - CON'T.

(d FIELD DESCRIPTION 08 TEST E Exercise FS Full Stroke PS Part Stroke Exercise ST Stroke Time LV Locked valve (Administrative controls, No Schedule)

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 SCHEDu.E Q Quarterly, 92 Days CS Cold Shutdown (IST), See Note (3)

RR Reactor Refueling EV IW-3610 10 Max. STROKE TIE The maximum allowed stroke time for valves requiring stroke time measurement 11 RELIEF REQJEST A relief Ioquest nunter when a specific code (J requirement is determined to be impractical.

Relief request numbars for valves are prefixed with "RV". ("RP" for pumps) 12 ACTIVE OR PASSIVE Active "A" valves are valves which are recuired to change position to acccmplish a specific function. Passive"P" valves are valves which are not required to change position to accomplish a specific function.

13 REMARKS General valve descriptions or conynents.

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

(2) Safety valves and relief valves are tested during Reactor Refueling; however, individua) valves are scheduled inaccordance with ASE Section XI Table IW-3510-1.

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1eS:lle County Nuclear Sistion Unst 1 J

III NOTES - CCN'T O (3) Inservice valve testing at cold shutdem is defined as:

valve testing wnich comsices not later tnan forty eignt (48) hours after cold snutdoun a,d continues i.ntil required testing is comoleted or plant start-up, wniusever occurs first. Completim of all required valve testing is not a requisite to plant start-up. Valve testing wnich is not completed during a cold shutcom will oe performed during suosecumt cold snutdowls to meet tne code specified testing requiremelts. No valve will De tested more often thai cnce every 90 days.

Also, some valves require entry into the ccntainr. ant to perform the test, sucn valves will only be tested wnsi the drywell is de-inerted.

Note: It is expected that the required inservice valve testing will normally be completed in 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months following cold shutdow1.

However, completicn of all valve testing during cold shutdowl is not required if plant operating conditicns will not permit tne testing of specific valves.

In the evait that a valve must be declared inoperable as a result of cold shutdow1 testing (ASME Code, Secticn XI, IW-3410 (g) and IW-3520 (c))

the applicable ulit start-up limitaticns will be as stated in the tecnincal specification, limiting canditicns for operaticns.

(4) 10 CFR 50 Apper. dix J Type C Test.

(5) Reactor Coolant Systen 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 lift disk from seat) will be available on site to verify that testing in the

! reverse direction will provide either equivalent or more conservative

! results. (From FSAR Table 6.2-21, Note 20).

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

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

b. System reliability.can readily be seen to be greater when only a l 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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x n) Commonwealth Edison (v ? ) ies.no County Nuch Station Uni I O i III NOTES - CON'T

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.

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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.

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

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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 Os pressure that is always higuer than primary containment pressure by water leg pumps; thus, precluding any outleakage from primary contain-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. Leakane 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 i

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 basad on site boundary dose considerations (10 CFR 100: ECCS subsystem leakage not to exceed i gpm times number of valves in the subsystem tested).

(From FSAR Table 6.2-21, Note 29).

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[m3 ) Commonw:alth Edison

( l eSik Coiunty Nochem Stetson Usut i III NOTES - CON'T O- (9) To satisfy the requirements of General Design Criterion 56 and to 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 instrument, that are Seismic Category I. They are provided with manual isolation valves and excess flow check valves.

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

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

Surveillance inspections will be performed to ensure that the leak- 8 tight integrity of these lines and their associated instruments.

Additional inservice inspection is included in the Technical Specifi-cations. This inservice inspection verifies the function of the excess flow check valves and their leakage rates.

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, Note 32).

(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 lintes 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.

Additional inservice inspection is included in the Technical Specifi-cations. This inservice inspection verifies the function of the excess flow check valves and their leakage rates. (From FSAR Table 6.2-21, Note 38).

(11) The ECCS and RCIC suction lines are normally filled with water on both the inboard and outboard side of 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 O

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Lasane county Nuclear Schon Und 1 III NOTES - CON'T !

O V 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 Main Steamlines are proviosd 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 III.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, the packing of these isolation valves will be soap bubble tested to ensure insignificant or no leakage at containt..ent test pressure and refueling outage.

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O O O Commonwealth Edison

@ LaSalle County Nuclear Stalmn Unit 1 INSERVICE TESTING PLAN P, UMPS System DG - DIESEL EfERAT(R Page 1 of g TEST PARAMETERS TO DE MEASURED p PMD NUMBER NAME CLASS NO COOR. INLET DIFF. Ft OW VERA. BEARtNG TESTINTERVAL SPEED PHESS PRESS HATE TION T E MP. ,

00 01 02 03 04 05 06 07 08 09 10 11 00G-01P DG Cooling 3 87-2 7C N/A yes yes yes RP-04 P-01 Quarterly - See F-03 Pump "0A" 1DG-OlP DG Cooling 3 87-1 70 N/A yes yes yes RP-04 RP-01 Quarterly - See RP-03 Pump "1A" til i t

O O O Commenwealth Edison

@ LaSano County Nuclear Station Unit 1 INSERVICE TESTING F LAN p p em 00 - pESEL OIL

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PUMP PUMP PalD NUMBER NAME CLASS NO COOR. INLET DiF F. (LOW VISRA- BEARING TEST INTERVAL SPEED PRFSS PRESS RATE ilON T E MP.

00 01 02 03 04 05 06 07 08 09 to 11 0000lP OG Pump 0 3 85-1 4C WA AP-05 P-05 P-05 W-04 W-01 Quarterly - See W-03 1000lP OG Pump 1A 3 85-1 6C N/A RP-05 P-05 RP-05 RP-04 RP-Ol Quarterly - See F-03 10002P WCS OG 3 85-1 1C WA RP-05 P-05 RP-05 RP-04 W-01 Quarterly - See F-03 011 Transfer Pump l

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O O O Commonwealth Edison

@ LaSalle County Nuclear StatN)O Unit i INSERVICE TESTING PLAN PUMPS System FC - FLEL P00. C00.IE Page 1 of 1 pgg TEST PARAMETERS TO BE MEASURED p

NUMDER NAME CLASS NO COOR. INLET DIF F. FLOW V18HA. BEARING TEST INTERVAL SPEED PHESS PRESS RAIE TION T E MP.

00 01 02 03 04 05 06 07 08 09 10 11 IFC03PA FP-Emerg. 3 87-2 7E N/A yes yes yes W-04 W-01 Quarterly - See W-03 Make-up-I A j IFC03PO FP-Emerg. 3 87-1 7C N/A yes yes yes RP-04 RP-01 Quarterly - See RP-03 Mike-up-10 I

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l O O O Commonweasith Edison INSERVICE TESTING PLAN SystemW-HIQi PfESSLEE CGE SPRAY l LaSalle County Nuclear Stat 6on Unit 1 PUMPS Page 1 of 1 l TEST PARAMETERS TO BE MEASURED l PUMP PUMP PalD N'JMBER NAME CLASS NO COOR. INLET DIF F. FLOW VIBRA- BEAnlNG TEST INTERVAL i SPEED PAESS PHESS RATE TION T E MP.

00 01 02 03 04 05 06 07 08 09 10 11 IE22-C001 iPCS Pump 2 95 2C N/A yes yes yes RP-04 FF-01 Quarterly - See P-03 IE22-C003 HPCS Water 2 95 AD N/A yes yes FP-02 FP-04 RP-01 Quarterly - See IP-03 Leg Pump IE22-C002 HPCS 3 87-1 78 N/A yes yes yes RP-04 RP-01 Quarterly - See RP-03 DG Cooling Water Pump 1A b .. . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _

O O O Lasaise county Nuclew Station Unit 1 INSERVICE TESTING PLAN PUMPS System SC-STMOBY LIQlJID C(NTRG.

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PUMP PUMP P&lD NUMBER NAME CLASS NO COOR. INLET Dif F. FLOW VIBHA- BEARWG TEST INTERVA L SPEED PRESS PRESS RATE TOON T E MP.

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IC41-C001A RC Pump 1A 2 99 C4 WA RP-06 NR yes HP-04 W-Ol Quarterly (IP46)

IC41-C0018 1C Pump 1B 2 99 B4 WA IP-06 m yes IP-04 RP-01 Quarterly (RP-06) of it

O O O Commonwealth Edison

@ LaSalle County Nucker StaHon Unit 1 INSERVICE TESTING PLAN PUMPS Sys' m R4-ESIDlR. EAT REMNAL Page 1 of 1 TEST PARAMETERS TO DE MEASURED PMD NUMEER NAME CLASS NO COOR. INLET DIFF. FLOW VIDRA- BEARING TEST INTERVAL SPEED PRESS PRESS HATE ilON TEMP.

00 01 02 03 04 05 06 07 08 09 10 11 IE12-C002A RtR Pump 1A 2 96-01 SA N/A yes yes yes RP-04 W-01 Quarterly lE12-C0020 RHR Pump 1B 2 96-02 4B N/A yes yes yes W-04 W-01 Quarterly lE12-C002C RtR Pump IC 2 96-3 SC N/A yes yes yes P-04 P-01 Quarterly LE12-C003 RHR Water 2 96-03 7A N/A yes yes RP-02 RP-04 RP-01 Quarterly Leg Pump IE12-C300A RHR Serv. 3 87-2 7A N/A yes yes yes F-04 RP-01 Quarterly Water Pump 1A lE12-C3000 RHR Serv. 3 87-2 70 N/A yes yes yes P-04 RP-01 Quarterly Water Pump id IE12-C300C RHR Serv. 3 87-1 7E N/A yes yes yes RP-04 RP-01 N arterly Water Pump IC IE12-C3000 RHR Serv. 3 87-1 7F N/A yes yes yes RP-04 RP-OL Quarterly -

Water Pump ID GF fl

O O O Commonwealth Edison

@ LaSalle County Nuclear Station Un6t t INSERVICE TESTING PLAN P PS syg.m RI-REACTOR Cb 5 ISOL-COOL Pe 1 of I p TEST PARAMETERS TO BE MEASURED NUMBER NAME CLASS NO COOR. INLET DIFF. FLOW VIBRA- BEARING TEST INTERVAL SPEED PRESS PRESS RATE TIOf; T E MP.

00 01 02 03 04 05 06 07 08 09 10 11 IE51-C001 RCIC Pump 2 101-02 C2 yes yes yes yes IP-04 FF-01 Quarterly lE51-C003 RCIC 2 101-02 A4 N/A yes yes IP-02 IP-04 RP-01 Quarterly Water Leg Pump 1

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O O O Commonwealth Edison INSERVICE TESTING PLAN LaSalle County Nuclear Station Unig g stem LP-LOW PRESSURE CORE SPRAY PUMP PUMP PalD NUMBER NAME CLASS NO COOR. Im ET DiF F. FLOW VIBRA- BEAIUNG TEST INTERVAL SPEED PRESS PRESS RAIE ilON T EMP.

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

IE21-C001 LPCS Pump 2 94 28 N/A yes yes yes W-04 RP-01 Quarterly lE21-C002 LPCS Water 2 94 3B N/A yes yes RP-02 AP-04 Leg Pump RP-01 Quarterly p}

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@ Commonwealth PUMP t.aSalle County Nucker Station Unit 1 Edison

& VALVE TESTING RELIEF REQUESTS Page 1 of 2 I-~ >. P.

IIi 33 PUMP OR N ASM.2 SECT!'sN XI VALVE NO.

QO FUNCTION TEST REQUIREMENT BASIS FOR RELIEF AtTERNATIVE TEST 00 01 02 03 04 05 lA' IP-01 All Pumps --

N/A Measure Bearing Bearing temperature Vibration velocity Iemperature measuoments will not mea wrements will be Annually provlu significant taken quarterly.

additional information regarding bearing-condition than that already obtained by measuring vibration amplitude. Measurement of vibration amplitude provides more concise and consistent information with respect to pump and bearing condition. The usage of vibration amplitude measurenents can provide information ,

as to a change in the balance of rotating parts, misalignment-

of bearings, worn bearings, changes in ,

internal hydraulic forces and general pump integrity prior to the condition degrading to the point where the conponent is jeopardized, uearing tenperature does OE-13

O O O Commonwealth Edison

@ Lasane County Nuclew PUMP S: anon

& VALVE unit 1 TESTlNG Page 2 of 2 RELIEF REQUESTS e >

b$ Eo ASME i 33 PUMP OR QO SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RP-Ol Continued not always predict such problems. An increase in bearing temperature most often does not occur until the bearing has deteriorated to a point where additional pump damage may occur.

Bearing temperatums are aise affected by the temperatums of the medium being pumped, which could yield misleading msults.

Vibration madings are not affected by the temperature of the medium being pumped, tims the readings are more consis-tent. As described in mller request RP-04, vibration velocity measurements will be made in inches /second rather than in mils. This will provide a mom sensitive detennination of abnormal conditions.

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@ Commonwealth PUMP LaSalle County Nucleat Station Unit 1 Edison

& VALVE TESTlNG RELIEF REQUESTS Page 1 of 1 D E ASME 33 PUMP OR QO SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOP. RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 IP-02 IPCS Water Leg Pressure IM'-3100 Flow is not a sirpificant Pressure Maintenance Pump Maintenance Flow Measurement desity parameter for the of ECCS discharge IE22-C003 2 water leg pumps. Their lines within primary purpose is to allowable pressure LPCS Water Leg maintain the ECCS pump limits.

Pung discharge lines filled 1E21-C002 2 and pressurized. The satisfactory performance RHR Water Leg of this function is mani-Pump fested by the maintenance IE12-C003 2 of the discharge line within allowable stan@y pressure limits.

Iterefore, there is actually no flow criteria on the pump that could be used to determine whether the punp is satisfactorily l

performing its safety function. Therefore, because the design basis of the waterleg pumps is maintenance of pressure, this is the parameter that is considered for inservice testiinj.

GC-T3

O O O Commonwealth Edison

@ LaSalle County Nuclear Station PUMP & VALVE TESTING Unti I Page 1 of 1 RELIEF REQUESTS h33 PUMP OH E

mO ASME SECTION Xi m3 VALVE NO. $ FUNCTION Eg o$< TEST FIEQUIREMENT HASIS FOR FIELIEF ALTEllNATIVE TEST o

00 01 02 03 04 05 06 RP-03 Deleted est 13

O O O Commonwesitt. Edison i

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@ tasane county Nuclear Stalwn Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of 2 5 ASME 33 PUMPOR VALVE NO.

$0 FUNCTION SECTiON XI TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST l

o i 00 01 02 03 04 05 06 W-04 All Pumps --

N/A Requirements of Portable vibratlan The vibratici testing

_ Table IWP-3100-2 monitoring equipmmt data will be malyzed allowing for the in accordance with measuremmt of vibratlai the chart showi in velocity in inches / F-04.The alert rance secoid is available at will be the plant site. This measuremmt gives a more accurate determinatlan .314sec" < V < .6E8s "ec of abnormal vibratiois The required action at frequmcle 9 other than shaft rotaticial range will be speed. The results of V> .628 in/sec.

this testing will be evaluated using the "Gmeral Machinery Severity Chart",

p W lished by IRD Mech-analysis, Inc., as a guide.

tsi 13

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@ Commonwealth Edison LaSaHe County Nuclear Station Unit 1 PUMP & V ALVE TESTlHG RELIEF REQUESTS Page 1 of 1 E ASME 3.3 PUMPOR $O SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST o

00 01 02 03 04 05 06 IP-05 0000lP 3 Transfer Fuel Oil Measure Pump The purpose of these Measure flow by From The Diesel Inlet Pressure, pumps is to move fuel measuring the time it ID00lP 3 Generator Fuel Oil And Differential oil into the day tank takes to increase the Storage Tank To Pressure, And Flow approximately ten times level in the day tank, ID002P 3 The Day Tank. Rate. faster than the diesel ergine consumption rate.

The exact flow characteristic of the pump is not crucial.

Also, there is no definable output pressure requirement. For these reasons, the best method of determining degrada-tion trends in pump performance is to measure the flow rate by measuring the time it takes to increase to a certain level in the day tank.

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O O O .

l Commonwealth Edison tasaim county Nuclear Stauon Unit 1 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS .

E ASME 33 PUMP OR $'J SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVETEST 00 01 02 03 04 05 06 ,

RP-06 1C41-C001A 2 Measure Pump It is igractical to Mnitor pump f Inlet Pressure measure standby 11guld discharge at each IC41-C001B 2 control pump inlet inservice test. !

pressure in accordmce with Section XI require-ments. During pump '

l testing, the pum suction i is from a test tm k '

rather than the main standby 11guld control tank. The only means available to measure inlet pressure is to correlate tank level l to inlet pressure. These ptmps are positive '

displacement, the measure-mmt of inlet pressure is not critical in judging pum performance.

Measuring the discharge pressure and the flow ,

rate is adequate to detect changes in the hydraulic characteristics of the pumps.

86E T3

O O O Commonwealth Edison

@ LaSalle County Nuclew PUMPStation Un611

& V ALVE TESTING Pane 1 of 1 RELIEF REQUESTS 5 ASME 33 PUMP OH $O SECTION X1 '

y VALVE NO. FUNCTION TEST REQUlHEMENT B ASIS FOR RELIEF ALTERNATIVE TEST 00 01 a2 03 04 05 06 RP-07 Deleted a

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k Est 53

O O O

@ Commonwealth PUMP LaSalk County Nucker Station Unit 1 Edison

& VALVE TESTING RELIEF REQUESTS Page 1 of 1

$$ So ASME 33 PUMP OH $O SECTIOH XI VALVE NO. FUNCTION TEST HEOUlHEMENT DASIS FOR HELIEF ALTERNATIVE TEM 00 Ol 02 03 04 05 06 RP-08 RHR Pump A Remove Decay Heat IWP-4120 requires The reference values for Since inlet pressure lE12-C002A 2 that the full scale the inlet pressures of varies on the RHR range of pump in- RHR Pumps A, B and C are pumps, gages with RHR Pump B Remove Decay Heat struments shall be all (Pi>7.5 psig). The larger scale ranges lE12-C0028 2 three times the reference value for the are required to reference value or inlet pressure of the accomodate pressure RHR Pump C Remove Decay Heat less. RHR water lea pump is rises of pump lE12-C002C 2 (Pi>8 psig). The full suction.

scaTe range of the RHR Water Leg Pressure Mainten- inlet pressure gages for Pump 2 ance all four pumps reads 0-250 psig. The inlet pressure for these pumps may attain a maximum pressure of 200 psig and therefore the pumps require a gage with.a larger scale range.

li tI 13

O O O Commonwealth Edison

@ LaSane County Nuckw PUMPStauon

& VALVE TESTINGUnn 1 Page 1 of 1 RELIEF REQUESTS Ui ASME 33 PUMP OR' $O SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF AtTERNATIVE TEST 00 01 02 03 04 OS 06 RP-09 HPCS Pump 2 ECCS Pump IWP 4120 requires The reference value for Due to pressure lE22-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 psig, or about a 115 psig range. The range is necessary due to the configuration of this system. When the HPCS pump is being stopped, 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.

Hence, a suction pressure -

gage with a larger scale is needed to enable the gage to remain in calibration for the measurement of suction -

pressure of the HPCS pump.

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O O O CM-Containment Monitoring symem LaSeNo County Nucteer Stetton Unit .,

INSERVICE TESTING PLAN page 1 or 2

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.5 156-1 F7 2/A GB SO 0 FS, Q 5 RV-02 A (See Note 4,6) 1CM017A LT RR RV-19 1CM017B .5 156-2 F7 2/A GB SO O FS, Q 5 RV-02 A (See Note 4) j LT RR RV-19 ICfl018A .5 156-1 E7 2/A G8 50 0 FS, Q 5 RV-02 A (See Note 4,6)

LT RR RV-19 1CM0188 .5 156-2 F7 2/A GB SO O FS, Q 5 RV-02 A (See Note 4)

LT RR RV-19 1CM019A .5 156-1 B7 2/A GB SO O FS, Q 5 RV-02 A (See Note 4) 4 LT RR RV-19 1CM0198 .5 56-2 B7 2/A f,9 SO O FS, 0 5 RY-02 A (See Note 4)

' LT RR RV-19 1CM020A .5 156-1 B7 2/A GB SO O FS, Q 5 RV-02 A (See Note 4,6)

LT RR PV-19 1CM020B .5 156-2 B7 2/A GB 50 0 FS, Q 5 RV-02 A (See Note 4,6)

, LT RR RV-19 1CM021B .5 156-2 E3 2/B GB S0 C FS 0 5 RV-02 A ICM022A .5 156-1 E3 2/B GB S0 C FS Q 5 RV-02 A GE-T 2 -1180

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@ LaSde County Nucher .

Stanon Unit 1 INSERVICE TESTING PLAN p, 2 g 2 e

00 01 j 02 /03/04 05 08 07 De 09 to 11 12 13

.5 156-2 EL 2/B GB S0 C FS Q 5 RV-02 A 1CM0238 1CM024A .5 156-1 E3 2/B GB S0 C FS Q 5 RV-02 A 1CM025A .5 156-1 A4 2/B GB S0 C FS Q 5 RV-02 A 1CM026B .5 156-2 A4 2/3 GB S0 C FS Q 5 RV-02 A 1CM031 .5 156-4 C6 2/A GB SO 0 FS, Q 5 RV-02 A (See Note 4,6)

LT RR RV-19 1CM032 .5 156-4 C6 2/A GB SO O FS, Q 5 RV-02 A (See Note 4)

LT RR RV-19 1CM033 .5 156-4 87 2/A GB SO O FS, Q 5 RV-02 A (See Note 4)

LT RR RV-19 1CM034 .5 156-4 B7 ?/A GB SO O FS, Q 5 RV-02 A (See Note 4,6)

LT RR RV-19 I

GE-T2 1180

O O O System DG-Olesel Generator INSERVICE TESTING PLAN Pap N ]

@ Commonwealth Edison LaSane County Nuclear Station Unit 1 VALVES

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10 11 / 12 13 00 01 02 /03, 04 05 06 07 08 09 C E Q A Diesel Cooling Water 00G-002 12 87-02 06 3/C NSC -

Pump Discharge Check FS RV-01 A Diesel Cooling Strainer 00G-009 4 87-02 C5 3/8 GT MD C Q Backwash Outlet Stop C RV RR A Diesel Generator Cooler 00G-014 .75 87-02 04 3/C RV -

OR relief (See Note 2) x1.0 A Ofesel Cooling Water 1DG-002 10 87-01 D6 3/C NT - C E Q Pump Discharge Check FS RV-01 A Diesel Cooling Water l 10G-011 4 87-01 06 3/8 GT M0 C Q Strainer 87-01 D4 3/C RV -

C RV RR A Diesel Generator Cooler 1DG-034 . 7.5 la poliof (Coo Nnto @

45 A LPCS Pump Cooler Control 10G-035 1.5 87-02 E4 l 3/8 GB M0 0 FS.ST C A LPCS Pump Motor Cooler 10G-036 1.5 87-02 E2 3/C CV -

C E Q Outlet Check i

I i -

O O O lesel 011 INSERVICE TESTING PLAN gstem La e nty N I a Sta i Unit 1 00

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01 ,.

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02 03 04 05 06 07 06 09 10 11 12 A Unit U OG Fuel 011 13

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1.5 85 D4 3/C NSC - C E Q 000002 Transfer Pump Discharge Check FS RV-02 A Unit 0 OG Day Tank 000004 1.5 85 D4 3/B GT T C Q Inlet Stop Valve C E Q A thit IA DG Fuel 011 ,

100002 1.5 85 D6 3/C N5C -

Transfer Pump discharge i

check FS RV-02 A thit 1 Day Tank Inlet 100004 1.5 85 E6 3/8 GB SO C Q Stop Valve NT C E Q A Unit IB OG Fuel 011 100012 1.5 85 D1 3/C -

Transfer Pump Discharge Check 50 FS Q RV-02 A (kilt 18 Day Tank Inlet 100014 1.5 85 El 3/B GB C Stop Valve 85 82 3/D GB 50 C FS Q RV-02 A Diesel Fire fuel 100024 2 Transfer Pump Inlet Stop t 60 l ;* 1IHO _ __ ____ ___ _________

O O O Commonwealth Edison sysiem FC-Fuel Pool Cooling

@ Lasone County Nuclear Station urut 1 INSERVICE TESTING PLAN VALVES

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4* 8 o0 4 A c* -g. g g- +

4a 00 01 02 / 03, 04 / 05 06 07 08 09 10 11 12 13 IFC-044A 6 87-02 E6 3/C NSC - C E .

Q A Fuel Pcol Emergency

- Make Up Pump 1A Discharge Check IFC 0448 6 87-01 C6 3/C NT - C E Q A Fuel Pool Emergency Make Up Purrp IB Discharge Check IFC-105A .75 91- 1 D4 3/C RV -

C RV RR A Fuel Pool Cooling Heat x.75 Exdianger Relief (See Note 2)

IFC-1050 .75 91- 1 D3 3/C RV - C RV RR A Fuel Pool Coollng Ileat

x.75 Exchanger Reller (See Note 2)

IFC-086 10 98- 1 C7 2/A GT M C LT RR RV-19 P Rx well bulkhead drain RV-37 outboard (t165)(See Note 4)

IFC-Il3 2 98- 1 07 2/A GB M C LT RR RV-19 P Cond to refuel bellows RV-37 inboard (MS9) (See Note 4,6) 1FC-ll4 2 98- 1 D7 2/A GB 11 C LT RR RV-19 P Cond. to refuel bellows RV-37 outboard (f159) (See Note 4,6) 1FC-ll5 10 98- 1 C7 2/A GT il C LT RR RV-19 P Rx well bulkhead drain RV-37 inboard (l165)(See Note 4,6) s .1 f .' 19 Bf 3

I INSERVICE TESTING PLAN ter La o e C unty NucI a Sta n Unit 1 gstemFW-F 00

/

01 mp6;66 s Y//

02 03 04 05 06 07 08 [ 09 10 11 12 13

/

1 IB21-F010A 24 57 7A 1/AC NSC - 0 E RR R/-06 A Rx Feedwater Line Che d LT RV-19 Valve (M-5)(See Note 1,4)

IB21-F010B 24 57 7C 1/AC NSC - 0 E RR R/-06 A Rx Feedwater Line Check LT RV-19 Valve (M-6)(See Note 1,4) ;

l IB21-F032A 24 57 6A I/AC NSC A0 0 E RR RV-32 A Rx Feedwater Line Check LT RR RV-19 Valve (M-5)(See Note 1,4) l RR

' PIT IB21-F032B 24 57 6C 1/AC NSC A0 0 E RR RV-32 A Rx Feedwater Line Check RV-19 Valve (M-6)(See Note 1,4) j IB21-F065A 24 57 SA 2/A GT M0 O FS,ST CS RV-07 A Rx Feedwater Isolation LT RR 132 RV-19 Valve (M-5)(See Note 1,4)

PIT RR IB21-F0658 24 57 SC 2/A GI MO O FS,ST CS RV-07 A Rx Feedwater Isolation LT fut 132 RV-19 Valve (M-6)(See Note 1,4)

PIT RR

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O O O Commonwealth Edison INSERVICE TESTING PLAN gsm HG p t. Coabustible Gas

@ LaSaHe County Nuclear Station VALVES Unit t 1 2 Control 5 9 O O c

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s3 -S. s 9 A- h 00 1 0' 03 04 05 06 07 08 / 109 10 a

11 12 13 i

FS,ST Q 22 RV-19 A Upsteam HG Stop 4 130-1 F7 2/A GT M0 C (SS3)(See Note 4,6) f LT RR IH0001A H0 FS, ST Q 22 RV-19 A Upsteam HG Stop

! 4 130-1 E7 2/A GT C (433)(See Note 4,6)

LT RR 16 G 018 FS, ST 66 RV-19 A 4 130-1 F7 2/A G8 M0 C Q Downsteam

(*53)(See NoteG Stop 4 )

< LT RR It G 02A FS, ST Q 66 RV-19 A Downsteam HG St l 4 130-1 E7 2/h G8 M0 C

(*33)(See Note )

LT RR i ItG028 i FS,ST 60 RV-19 A Unit 1 Outlet to Unit 1 IH0003 6 130-1 C6 2/8 GT M0 O Q O/W l

l FS, ST Q 33 HV-19 A Unit 1 Recombiner RIN

! 6 130-1 07 2/A GT M0 C Downsteam stop (*102)

LT HR D G OSA (See Note 4,6) 6 FS,ST 0 33 RV-19 A Unit 2 Recombiner RTN lHG0058 130-1 A7 2/A GT M0 C downstream Stop (M-95)

LT RR (See Note 4,6) 5 130-1 B6 2/A GT "O C FS,ST 0 33 R'.'- 19 A ' Unit 1 Recombiner RTil LT RR Unstm Stop (l:-102) lHG006A (See flote 4)

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O O O

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@ Lesene county Nuclew StatRm Unit 1 INSERVICE TESTING PLAN Pe 2 W 2 00

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01 02

%$R8!/y'// 03 04 05 06 07 06 09 10 11 13

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6 130-1 A6 2/A GT M0 C FS.ST Q 33 RV-19 A Unit 2 Recombiner RTN lHG006B LT RR Upstm Stop (M-95)

(See Note 4) 1HG009 6 130-1 C6 2/B GT M0 C FS,ST Q 60 A Unit 1 Outlet to Unit 2 D/W (See Note 4) i GE-T2 -1180

l HP-High Pressure Core Spray L en. county seu s unsi t INSERVICE TESTING PLAN srswn Pep W 1 2 VALVES

# 00 Y $ c} .O $

/ 00 01 02 03 04 05 os 07 os ce 10 11 12 13 lE22-F001 14 95 A4 2/B GT M0 0 FS,ST Q 140 A HPCS Pump Suction Stop From CST lE22-F002 24 95 B4 2/C CV -

C E Q A HPCS Pump Suction Stop From CST lE22-F004 12 95 D6 1/A GT M0 C FS,ST Q 66 RV-19 A HPCS Injection Line Stop LT RR (Mll)(See Note 5,4) lE22-F005 12 95 D7 1/AC NSC A0 C E CS RV-19 A HPCS Injection Line Test-PIT RR RV-35 able (M-ll) (See Note LT RR 5,7,8) lE22-F012 4 95 C3 2/A GT M0 C FS,ST Q 22 RV-19 A HPCS Pump Minimum flow LT RR bypass line stop (See Note 4,6,8) lE22-F014 lx2 95 B5 2/C RV C RV RR A HPCS Water Leg Disgharge relief (See Note 2,4,8, 6) lE22-F015 18 95 B6 2/A GT M0 C FS,ST Q 99 RV-19 A HPCS Stop Pump Suction LT RR from Suppression Chamber (See Note 4,6, 11) l CE T2-1180

O O O 9 ' '#

INSERVICE TESTING PLAN system

@ LaSeNo County Nuclear Station Unit 1 p, 2 m 2 00

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01 ,

6f:U;h# /}'h*/ /

02 03 04 05 06 07 08 09 10 11 12 13 C RR RV-10 A HPCS Check Pump Su tion lE22-F016 24 95 B5 2/C CV -

E from Suppression Chamber (See Note 1)

A HPCS Pump Discharge lE22-F024 16 95 C3 2/C NSC - C E Q Check 0 A HPCS Water Leg Pump lE22-F007 3/4 95 D4 2/C NSC -

E Q Discharge Check lx2 95 D2 ' 2/C RV C RV RR A HPCS Discharge Line lE22-F035 -

Relief (See Note 2)

A HPCS DLS Gen Cooling lE22-F028 10 87-01 B6 3/C NSC -

C E Q Water Discharge Check 87-01 M0 FS RV-01 A HPCS Diesel Cooling lE22-F319 4 B6 3/B GT C Q Water Strainer Bkswash Outlet Stp IE22-F345 .75 87-01 B4 3/C RV -

C RV RR A HPCS DG Cooler Inlet xl.0 Relief (See Note 2)

GE-T2 -1180

O O O.

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INSERVICE TESTING PLAN systen

@ LeSeNe County Nuclear Station Unit f p, 1 g 3 el # / f' f

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13 00 01 02 03 04 05 06 07 08 09 10 11 IIN001A 2 66-1 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, FST RR 4,6)

IIN001B 2 66-1 F7 2/A GB A0 0 FS ST RR 40 RV-12 A Drywell Suction Isolatiin LT RR RV-19 Fail Close (See Note 1, FST RR 4)

IIN017 1.5 66-1 B3 2/A GB 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)

IIN074 1.5 66-1 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 lIN075 1.5 66-1 E5 2/A GB A0 0 FS RR RV-02 A Dryer P;:rging Valve Fail LT RR RV-12 Close (See Note 1,4)

FST RR RV-19 lIN045 1x2 66-7 E7 3/C P.V -

C RV RR Ventilation System IIN046 1x2 66-7 E6 3/C RV -

C RV RR Ventilation System

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c envy i sta n unit INSERVICE TESTING PLAN getem jN-Drywe 1 I t.a O c $

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

'l'I;O.'1 J.75 G6-1 BG 2/A GB SO O FS ' RR RV-02 A Tip Indexer Purge-Fall FST RR RV-12 Close (See flote 1,4 LT RR RV-19 61

.75 66-2 3/C NT 0 E RR RV-16 A MSIV IN CIECK (See tbte lB21-F024A F6 -

1) 66-2 3/C NT 0 E RR RV-16 A MSIV IN CitECK (See Note IB21-F024B .75 F7 -

1) 66-2 3/C NT 0 E RR RV-16 A MSIV IN CIECK (See Note 1021-F024C .75 F4 -

1) 66-2 3/C NT 0 E RR RV-16 A M51V IN CilECK (See Note IB21-F0240 .75 F5 -

1)

.50 66-2 B2 3/C HT 0 E RR RV-16 A PDS IN CIECK (See Note IB21-F040C -

1)

.50 66-2 64 3/C NT 0 E RR RV-16 A ADS IN CIECK (See Note IB21-F0400 -

1)

.50 66-2 U7 3/C NT 0 E RR RV-16 A ADS IN CllECK (See Note IB21-F040E -

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O O O Commonwealth Edison INSERVICE TESTING PLAN system LP-Low Pres. Core Spray

@ LaSeNe County Nuclear Station Un6t 1 page ] og ]

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04 05 06 07 08 09 10 11 12 13 00 01 02 03 1E21-F001 24 94 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) 1E21-F003 16 94 C2 2/C NSC -

C E Q A LPCS Pump Discharge Check lE21-F005 12 94 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) lE21-F006 12 94 C6 1/AC NSC A0 C E CS RV-21 A LPCS Injection Line PIT RR RV-19 Testable Check Valve f (it-10)(See Note 1,5,7)

LT RR l

i lE21-F0ll 4 94 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) lE21-F018 3x4 94 DS 2/C RV -

C RV RR A LPCS Pump Discharge Relief (See Note 2,4,6,8) 1E21-F031 lx2 94 B4 2/C RV -

C RV RR A LPCS Pump Suction Relief (See Note 2,4,6,8)

GE-T2 -1180

O O O cUy"n= INSERVICE TESTING PLAN MC-Clean Condens. Storage

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00 01 02 03 04 05 06 07 08 09 10 11 12 13 IMC027 3 75-02 B6 2/A GT H LC LT RR (M-37) (See Note 13) g-, P IMC033 3 75-02 B6 2/A GT H LC LT RR RV-19 P (M-37) (See Note 13)

RV-37 GE-T2 -1180

O O O O l.a a eC un y N 1 a Sta o Unit t livSERVICE TESTING PLAN VALVES system f-MAIN Page STEAM of 11 Ob

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09 10 11 12 13 02 03 04 05 / 06 07 08 00 01 8x10 55-1 D3 1/C SRV A0 C RV RR RV-23 A D Main Steam Line IB21-F013A Safety / Relief Valve (See Note 2) 8x10 55-1 C3 1/C SRV A0 C RV RR RV-23 A A Main Steam Line IB21-F0138 Safety / Relief Valve (See Note 2) 8x10 55-1 E2 1/BC SRV A0 C RV RR RV-23 A C Main Steam Line 1821-F013C Safety /Reller Valve E RR RV-33 (ADS) (See Note 2) 8x10 55-1 'B2 SRV AD C RV RR RV-23 A B Main Steam Line 1821-F0130 1/BC Safety /Rellef Valve E RR RV-33 (ADS) (See Note 2)

IB21-F013E 8x10 55-1 E3 SRV AD C RV RR RV-23 A C Main Steam Line 1/BC Safety / Relief Valve E RR RV-23 (ADS) (See Note 2) i 1

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Relief Valve (See Note 2) 8x10 55-1 O!* 1/C SRV AD C RV RR RV-23 A B Maln Stear. Line Safety IB21-F013K Relief Valve (See Note 2) f.F I? 1980

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A0 C RV RR RV-23 A C Main Steam Line IB21-f013N 8x10 55-1 E7 1/C SRV Safety / Relief Valve (See Note 2)

C RV RR RV-23 A A Main Steam Line 1021-F013P 8x10 55-1 C6 1/C SRV AG ' Safety /Reller Valve

('See Note 2)

SRV A0 C RV RR RV-23 A C Main Steam Line

, 1021-F013R 8x10 55-1 E5 1/BC Safety /Reller valve E RR RV-33 (ADS)(See Note 2)

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IB21-F013J 8x10 55-1 D7 1/BC SRV A0 C RV RR RV-23 A 0 Main Steam Line E RR RV-33 Safety / Relief Valve (ADS)(See Note 2)

IB21-F013V 8x10 55-1 C7 1/BC SRV A0 C RV RR RV-23 A A N in Steam Line E RR RV-33 Safety / Relief Valve (ADS)(See Note 2) 1021-F016 3 55-7 B7 1/A GT K) 0 FS,ST Q 15 RV-19 A Main Steam Inboard LT RR Drain Line Isolation PIl RR Valve (See Note 4,6)

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07 08 09 10 11 12 13 00 01 02 03 04 05 06 1/A 08 A0 0 PS Q 3-5 RV-22 A B MSIV Outboard IB21-F0280 26 55-2 B4 (See flote 1,4,12)

FS,ST CS FST CS PIT RR LT RR RV-19 1/A 08 A0 0 PS Q 3-5 RV-22 A C MSIV Outboard 1821-F028C 26 55-2 F4 (Seeflote1,4,12)

FS.ST CS FST CS PIT RR LT RR RV-19 1/A A0 0 PS Q 3-5 RV-22 A 0 MSIV Dutboard IB21-F0280 26 55-2 04 CB (See flote 1,4,12)

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LT RR 1/A C FS,ST Q 23 RV-19 A B MSIV Outboard Drain IB21-F067B 1.5 55-7 E5 PG M1 Isolation (See flote 4,12)

LT RR 1.5 55-7 E7 1/A PG FO C FS,ST Q 23 RV-19 A C MSIV Outboard Drain IB21-F067C Isolation (See flote 4,12)

LT RR 1.5 55-7 E6 1/A PG H) C FS ST Q 23 RV-19 A D MSIV Dutboard Drain IB21-F067D Isolation (See Flote 4,12)

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LT RR RV-19 2.5 55-8 E3 1/A GT Mt) C FS ST CS 13.75 RV-Il A MS Loop B Bleed Valve 1E32-F001E Outboard (See Note 1,4,12)

LT RR RV-19 52-8 C3 1/A GT M0 C FS,ST CS 13.75 RV-11 A MS Loop C Bleed Valve lE32-F001J 2.5 Outboard (See Note 1,4,12)

LT RR RV-19 lE32-F00lN 2.5 55-8 C3 1/A GT M0 C FS,ST CS I3.75 RV-11 A MS Loop D Bleed Valve LT RR RV-19 Outboard (See flote 1.4.12) lE32-F003A 55-8 F4 2/8 GB M0 C FS,ST CS 60 RV-Il A MS Loop A Bypass to 2

Steam tunnel (See Note 1) lE32-F003E 2 55-8 04 2/B GB M0 C FS,ST CS 60 RV-11 A MS Loop B Bypass to Steam tunnel (See Note 1) lE32-F0033 2 55-8 C4 2/8 GB M0 C FS,ST CS 60 RV-Il A HS Loop C Bypass to Steam tunnel.(See Note 1) lE32-F003N 2.5 55-8 84 2/B GT M0 C FS ST CS 25 RV-Il A HS Loop D Bypass to Steam tunnel (See Note 1) 1E32-F002A 2.5 55-8 F3 2/B GT M0 C FS,ST CS 25 RV-11 A MS Loop A Bleed Valve (See Note 1) l sil I? 1Itif t

O O O MS-MAIN STEAM Commonwealth Ed! son

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IE32-F007 2.5 55-8 B4 2/B GT M0 C FS,ST CS 25 RV-Il A Bleed Valve-Steam

' Tumel (See Note 1) lE32-F008 2.0 55-8 A4 2/B GB M0 C FS.ST CS 60 RV-Il A Discha e to Steam Tume1 :2e Note D lE32-F009 2.0 55-8 A4 2/8 GB M0 C FS,ST CS 60 RV-ll A Discharge to Steam fumel (See Note 1) sir i? IIHs

O O O unit 1 INSERVICE TESTING PLAN golem MS-yN TEAM La aic county Nuci a Sta 00

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E CS RV-28 A Vacuum Breakers IB21-F037B1 12 92-1 C4 3/C CV - C .

E CS RV-28 A Vacuum Breakers IB21-F03782 12 92-1 C4 3/C CV - C E CS RV-28 A Vacuum Breakers 1621-F037C1 12 92-1 C4 3/C CV - C C E CS RV-28 A Vacuum Breakers 1821-F037C2 12 92-1 C4 3/C CV -

3/C C E CS RV-28 A Vacuum Breakers IB21-F03701 12 92-1 C4 CV -

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92-1 C4 3/c CV C E CS RV-28 A Vacutmi Breakers IB21-F037F2 12 -

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12 92-1 C5 3/C CV C E CS RV-28 A Vacuum Breakers 1821-F037tJ2 -

12 92-1 C6 3/C CV C E CS RV-28 A Vacuum Breakers 1821-F037H1 -

12 92-1 C6 3/C CV C E CS RV-28 A Vacuum Breakers 1821-F037H2 -

92-1 C6 3/C CV C E CS RV-28 A Vacuum Breakers IB21-F03731 12 -

IB21-F03732 12 92-1 C6 3/C CV - C E CS RV-28 A Vacuum Breakers IB21-F037M1 12 92-1 C6 3/C CV - C E C3 RV-28 A Vacuum Breakers IB21.-F037M2 12 92-1 C6 3/C CV -

C E CS RV-28 A Vacuum Breakers 1821-F037N1 12 92-1 C6 3/C CV - C E CS IN-28 A Vacuum Breakers l

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O O O syemm NB-Nuclear Boiler INSERVICE TESTING PLAN

@ CommonwealthEdison Lesen county Nuckw StatRm Unit t VALVES Page 1 of 3

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07 08 09 10 11 12 13 00 01 02 03 04 05 08 1821-F346 .75 93-3 B6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F348 .75 93-3 A6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F350 .75 93-3 A6 2/AC EFC 0 E,LT RR RV-34 'A See Note 10 1821-F344 .75 93-3 B3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F353 .75 93-4 AS 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F355 .75 93-4 B5 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F357 .75 93-4 05 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F359 .75 93-4 C5 2/AC EFC 0 E,LT R4 RV-34 A See Note 10 1821-F361 .75 93-4 DS 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F363 .75 93-4 C5 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F365 .75 93-4 E5 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F367 .75 93-4 A5 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F370 .75 93-5 A6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F372 .75 93-5 C6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 CE.T2 1180 L.__ _ . _ . _ _ _

O O O INSERVICE TESTING PLAN NB-Nuclear Boiler

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f 03 04 05 06 07 06 09 10 11 12 13 00 01 02 1821-F374 .75 93-5 06 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F376 .75 93-5 B6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F378 .75 93-5 E6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F380 .75 93-5 A6 2/AC EFC 0 E.LT RR RV-34 A See Note 10 IB21-F382 .75 93-5 F6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F437 .75 93-3 E3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F439 .85 93-3 E3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F441 .75 93-3 D3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F443 .75 93-3 D3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F445A .75 93-3 D3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1B21-F4458 .75 93-3 03 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F447 .75 93-3 C3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F449 .75 93-3 C3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F451 .75 93-3 C3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 l

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9 oO *> t A , 4 g- e-08 09 10 11 12 13 00 01 02 f 03 / 04 05 06 07 IB21-F453 .75 93-3 C3 2/AC EFC 0 E.LT RR RV-34 A See Hote 10 IB21-F455A .75 93-3 B3 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F445B .75 93-3 B3 2/AC EFC 0 E.LT RR RV-34 A See Note 10 1821-F457 .75 93-3 E6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F459 .75 93-3 E6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F461 .75 93-3 D6 2/AC EFC 0 E.LT RR RV-34 A See Note 10 IB21-F463 .75 93-3 D6 2/AC EFC 0: E,LT RR RV-34 A See Note 10 1821-F465A .75 93-3 D6 2/AC EFC 0: E,LT RR RV-34 A See Note 10 1B21-F465B .75 93-3 D6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F467 .75 93-3 C6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F469 .75 93-3 C6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F471 .75 93-3 C6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F473 .75 93-3 C6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 IB21-F475A .75 93-3 B6 2/AC EFC 0 E,LT RR RV-34 A See Note 10 1821-F475B .75 93-3 B6 2/AC EFC 0 E.LT RR RV-34 A See Note 10 GE-T 2 -1180 ,

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FS,ST Q 20 RV-19 A (496) Drywell 1RE025 2 91-4 C4 2/A CNV A0 C Equipment Drain se p LT RR suction.(See Note 4)

FS,ST Q 20 RV-19 A (497) Gland Seal 1RE026 1 91-4 05 2/A CNV A0 C Reservoir Drywell LT RR Equipment (See Note 4)

FS,ST Q 20 RV-19 A (M-97) Gland Seal 1RE029 1 91-4 DS 2/A CNV A0 C Reservoir Drywell LT RR Equipment (See Note 4)

FS,ST Q 20 RV-19 A Floor Drain (Drywell) 1RF012 2 91-4 A4 2/A CNV A0 C Sump Suction (M-98) F.C.

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FS,ST 20 RV-19 A Drywell Floor' Sump 1RF013 2 91-4 B4 2/A CNV A0 C Q LT RR Suction (M-98) F.C.

(Sec Note 4) f 4F .17 lifl0

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O O O system RH-RESI0lML HEAT REM [NAL INSERVICE TESTING PLAN '

O Las leCo n y Nuc a Sta i Und t VALVES

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180 A R R Heat Exchanger 96-4 C8 2/B GT MO O FS,ST Q Outlet Stop.

IE12-F0038 18 FS,ST Q 132 RV-19 A R R Outboard suction 96-1 A7 2/A GT MO O from Suppression Pool IE12-r004A 24 LT RR (M-70)(See Note 4,6,11)

FS,ST Q 132 RV-19 A RR Outboard suction 96-2 A7 2/A GT M0 O from Suppression Pool lE12-F004B 24 LT RR (M-72)(See Note 4,6,11)

O FS,ST Q 132 RV-19 A R R Outboard suction 24 96-3 A7 2/A GT M0 from Suppression Pool lE12-F004C LT RR (M-71)(See Note 4,6,11)

C fW RR A R R Shutdown suction 1E12-F005 1x2 96-3 C5 2/C RV SP cooling Suction 10R Relief (See Hote 2,6,4,8)

FS,ST Q 180 A Pump Suction Stop From 18 96-1 A7 2/8 GT M0 C Shutdown Cooling 1E12-F006A FS,ST Q 180 A Pump Suction Stop from IE12-F0068 18 96-2 (M 2/8 GT M0 C Shutdown Cooling h nmn

O O O sy iem RH-Residual Heat Removal ey sia unn i INSERVICE TESTING PLAN La

9 oO Y 8 cf *) .O p 07 08 09 10 11 12 13 00 01 02 03 04 05 06 FS,ST CS 41 RV-04 A RHR Shutdown Cooling lE12-F008 20 96-3 D6 1/A GT M0 C Pump 1A Suction LT RR RV-19 HDR Outboard Isolation (M-7)(See Note 1,5,4)

FS,ST CS Al RV-04 A RHR Shutdown Cooling lE12-F009 20 96-3 C7 1/A GT M0 C LT RR RV-19 HDR Inboard Isolation PIT RR (M-7)(See Note 1,5,4)

FS,ST 22 RV-19 A RHR Heat Exchanger lE12-F0llA 4 96-4 A3 2/A GT M0 C Q Steam Condensing Stop LT RR to Supp. Chamber (See Note 4,8,6)

M0 FS,ST Q 22 RV-19 A RHR Heat Exchanger lE12-F0118 4 96-4 A6 2/A GT C Steam Condensing Stop LT RR to Supp. Chamber (See Note 4,8,6)

FS,ST 88 RV-19 A RHR Containment Spray lE12-F016A 16 96-1 E5 2/A GT M0 C Q Upstream Isolation LT RR (ft-18) (See Note 4)

FS,ST 88 RV-19 A RHR Containment Spray lE12-F016B 16 96-2 F5 2/A ,

GT M0 C Q Upstream Isolation LT RR (fi-19) (See Note 4)

GE-12 -1180

O O O CommonwealthEdison system RH-IESIDUAL EAT EMWAL

@ LaSalle County Nuclear Station UnN I INSERVICE TESTING PLAM VALVES

"*8' 3 *' 1h

Y oO c, Y $ ef '

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10 11 12 13 04 05 06 07 08 09 00 01 02 03 A ftR Containment Spray 96-1 E7 GT M0 C FS,ST Q 88 RV-19 lE12-F017A 16 2/A Downstream Isolation LT RR (M-18)(See fiote 4,6)

A fue Containment Spray 96-2 F6 GT H0 C FS,ST Q 88 RV-19 lE12-F017B 16 2/A Downstream Isolation LT '

RR (M-19) (See Ilote 4,6) f RV RR A IDE Pump A Discharge IE12-F025A lx2 96-1 E3 2/C RV SP C Header Relief (M-85)

(See flote 2,4,6,8)

RV RR A IVE Pump B Discharge lx2 96-2 05 2/C RV SP C IE12-F025B Header Relief (M-86)

(See flote 2,4,6,8)

RV RR A IVR Pump C Discharge lE12-F025C 1x2 96-3 C2 2/C RV SP C Header Relief (M-87)

(See Note 2,4,6,8)

FS,ST 40 A f1R Heat Exchanger IE12-F026A 4 96-4 B4 2/B GT M0 C Q Steam Condensing Outlet Stop to fCIC Planp Suction 1

f6 09 11H0

O O O INSERVICE TESTING PLAN

@ La en cmey mm sia untis (valem RH-Residual Heat Removal 00

/

01

/f$%h h///

02 03 04 05 06 07 08 09

/10 11 12 RHR Heat Exchanger 13

/

lE12-F026B 4 96-4 B6 2/B GT M0 C FS,ST Q 40 A Steam Condensing Outlet Stop to RCIC Pump Suction IE12-F027A 4 96-1 C5 2/A GT M0 C FS,ST Q 30 RV-19 A RHR Suppression Chamber LT RR Spray Isolation (M-73)

(See Note 4,6,8) 1E12-F027B 4 96-2 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) lE12-F030 lx2 96-2 B4 2/C RV SP C RV RR A RHR System Drain Header Relief (ft-91) (See Note 2,4,6,8) lE12-F031A 18 96-1 A4 2/C CV -

C E Q A RHR Pu:np A Discharge Chk lE12-F031B 18 96-2 C3 2/C CV -

C E Q A RHR Pump B Discharge Chk l E12-F031 C 18 96-3 B4 2/C CV -

C E Q A RHR Pump C Discharge Chk lE12-F041A 12 96-1 D7 1/AC NSC A0 C E CS RV-21 A RHR LPCI Testable Chk PIT RR RV-19 Inboard Stop (it-13)

LT RR (See Hote 1,5,7,0)

GE-T2 -1180

O O O EAT REMCWAL INSERV1CE TESTING PLAN golemf-RESI LaS k nty Nucl a Sta Unit 1 VALVES 4 $ gO b O q%.

& o0 s y 09 11 12 13 02 03 04 05 06 07 08 to 00 01 A0 C E CS RV-21 A RE LPCI Testable Chk IE12-F0418 12 96-2 E7 1/AC NSC Inboard Stop (M-14)

PIT RR RV-19 LT RR (See Note 1,5,7,8)

A0 C E CS RV-21 A RR LPCI Testable Chk lE12-F041C 12 96-3 E7 1/AC NSC Inboard Stop (M-12)

PIT RR RV-19 LT RR (See Note 1.5.7,8)

C FS,ST CS RV-27 A RR LPCI Injection Line lE12-F042A 12 96-1 DS 1/A GT M0 Outboard Stop (M-13)

LT RR 20 RV-19 (See Note 1,5.4)

C FS,ST CS 20 RV-27 A RIE LPCI Injection Line lE12-F042B 12 96-2 E6 1/A GT M0 Outboard Stop (H-14)

LT RR RV-19 (See fiote 1,5,4)

C FS,ST CS 20 RV-27 A RHR LPCI Injection Line lE12-F042C 12 96-3 E6 1/A GT M0 Outboard Stop (M-12)

LT RR RV-19 (See Note 1,5,4)

C E Q A. RIE Pump Minitum lE12-F046A 8 96-1 BS 2/C CV -

Bypass Check C E Q A RHR Pump Mininun Flow 1E12-F0468 8 96-2 C2 2/C CV -

Byrass Check Gi f2 11H0

O O O INSERVICE TESTING PLAN gs m RH-REjli1JAL EAT EMNAL La e County Nuct a Sta o Unit t f

4 O e, y 4 y c,A Q 4.0 4,

9 o 11 12 13 03 04 05 06 07 08 09 f 10 00 01 02 A RE Pump Minimum Flow 96-3 83 2/C CV - C E Q lE12-F046C 8 Bypass Check Q 180 A RR Heat Exchanger lE12-F047A 18 96-4 E4 2/B GT MO O FS.ST Inlet Stop FS,ST Q 180 A R E Heat Exchanger lE12-F0478 18 96-4 E5 2/B GT M0 O Inlet Stop FS,ST Q 270 A RIE Heat Exchanger IE12-F048A 18 96-4 01 2/B GB M0 C Bypass Stop FS,ST 270 A RIE Heat Exchanger IE12-F048B 18 96-4 08 2/B GB M0 C Q Bypass Stop 30 A RHR Heat Exchanger 3 96-4 C1 2/B GT M0 C FS,ST Q IE12-F049A Blowdown Umtream Isolation to RB EDT 3 96-4 C8 2/B GT M0 C FS,ST Q 30 A Umtream Isolation to lE12-F049B RB EDT CS RV-04 A RiR Shutdown Cooling lE12-F050A 12 96-1 07 1/AC t4SC A0 0 E LT RR RV-19 Testable Check (M-8)

(See flote 1,5,7) en 11.1 TAO

O O O 1

l l

syst m RH-Residu Heat Removal ty N low ta km unit t INSERVICE TESTING PLAN La VALVES l

l su 4 94 9 .O g.M

/ qb oo g6 4 06 09 10 11 12 13 00 01 02 03 04 05 06 07 A0 0 CS RV-04 A RHR Shutdown Cooling 1E12-F050B 12 96-2 D7 1/AC NSC E LT RR RV-19 Testable Chk (M-9) (See Note 1,5,7)

FS ST 300 A RHR Heat Exchanger 1E12-F052A 10 96-4 C4 2/B GB M0 C Q Steam Inlet Stop FS,ST 300 A RHR Heat Exchanger lE12-F052B 10 96-4 C5 2/B GB M0 C Q Steam Inlet Stop FS.ST CS 29 RV-04 A RHR Shutdown Cooling 1E12-F053A 12 96-1 D5 1/A GB M0 C LT RR RV-19 Discharge Isolation (M-8) (See Note 1,5,4) 96-2 M0 FS,ST CS 29 RV-04 A RHR Shutdown Cooling lE12-F053B 12 D6 1/A GB C LT RR RV-19 Discharge Isolation (M-9) (See Note 1.5,4) 96-4 RR A RHR Heat Exchanger lE12-F055A 4x6 D3 2/C RV SP C RV Steam Inlet Header Relief (M-88) (See Note 2,4,6,8) 96-4 M0 LT RR RV-19 P RHR Heat Exchanger Vent lE12-F073A .75 E3 2/A GB C (See Note 4,3,6)

LT RR RV-19 P RHR Heat Exchanger Vent lE12-F073B .75 96-4 E6 2/A GS M0 C (See Note 4,8,6)

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

@ Commonwealth Edison Lesene County Nuch Stauon Unit 1 Page g of j]

$ 9 oO c',' sY cf +' <$ h- +

n y 4 08 09 10 11 12 13 00 01 02 03 04 05 06 07 lE12-F055B 4x6 96-4 05 2/C RV SP C RV RR A RHR Heat Exchanger Steam Inlet Header Relief (ft-88) (See Note 2,4,6, 8) lE12-F087A 10 96-4 C4 2/B GB M0 C FS.ST Q 300 A RHR Heat Exchanger Steam Inlet PCV Bypass Stop IE12-F087B 10 96-4 C5 2/B GB M0 C FS.ST Q 300 A RHR Heat Exchanger Steam Inlet PCV Bypass Stop lE12-F088A lx2 96-1 A6 2/C RV -

C RV RR A RHR Pump Suction HDR Relief (See Note 2,4,8) 1E12-F088B 1x2 96-2 B5 2/C RV -

C RV RR A RHR Pump Suction HDR Relief (See Note 2,4,8) lE12-F088C lx2 96-3 B6 2/C RV -

C RV RR A RHR Pump Suction HDR Relief (See Note 2,4,8, 6) lE12-F311A .75 96-4 D2 2/C RV SP C RV RR A RHR Heat Exchanger Shell x1 Side Relief (M-88, it89)

(See Note 2,4,6,8) lE12-F311B .75 96-4 D6 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 1180

O O O RH-Resi al Heat Removal

@f.

sye s mi INSERVICE Tr 3 TING PLAN , g

. VALVES sY & 00 c*'

s 4Y A y 4$ $ g- +%

04 05 06 07 08 09 10 11 12 13 00 01 02 03 lE12-F312A 1.5 96-1 D2 2/B GB M0 C FS.ST Q 45 A RHR Heat Exchanger t0 H2 Recombiner #1 lE12-F3128 1.5 96-2 E2 2/B GB M0 C FS,ST Q 45 A RHR Heat Exchanger to H2 Recombiner #2 lE12-F064A 4 96-1 B5 2/A GT MO 0 FS,ST Q 22 RV-19 A RHR Pump 1 A Main Flow LT RR Bypass (See Note 4,6,8) lE12-F064B 4 96-2 C3 2/A GT M0 0 FS,ST Q 22 RV,19 A RHR Pump IB Main Flow LT RR Bypass (See Note 4,6,8) lE12-F064C 4 96-3 B4 2/A GT M0 0 FS,ST Q 22 RV-19 A RHR Pump 1C Main Flow LT RR Bypass (See Note 4,6,8) lE12-F084A .75 96-1 B3 2/C CV -

C E Q A From LPCS Water leg Pump to RHR 1 A Discharge lE12-F084B .75 96-4 E5 2/C CV -

C E Q A From RHR Water Leg Pump to RHR 18 Discharge lE12-F084C .75 96-3 A7 2/C CV -

C E Q A From RHR Water Leg Pump to RHR IC Discharge 1E12-F068A 20 87-02 B3 3/B GT M0 C FS,ST Q 200 A RHR Heat Exchanger Service Water Outlet Stop GE-72 -1180

O O O INSERVICE TESTING PLAN spi.m -Resido Heat Removal

@ta typuc w sia unis t 00

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

/

lE12-F068B 20 87-01 F2 3/8 GT M0 C FS,ST Q 200 A RHR Heat Exchanger Service Water Outlet Stop lE12-F331A 16 87-02 B6 3/C NSC -

C E Q A RHR Service Water Pump 1A Discharge Check lE12-F331B 16 87-02 B6 3/C NSC -

C E Q A RHR Service Water Pump 18 Discharge Check lE12-F331C 16 87-01 E6 3/C ilSC -

C E Q A RHR Service Water Pump IC Discharge Check lE12-F331 D 16 87-01 F6 3/C NSC -

C E Q A RHR Service Water Pump 10 Discharge Check lE12-F336A 4 87-02 A5 3/8 GT M0 C FS Q RV-01 A RHR Service Water Pump Strainer IA Backwash Outlet Stop lE12-F336B 4 87-01 ES 3/B GT f10 C FS Q RV-01 A RHR Service Water Pump Strainer 1B Backwash Outlet Stop l E12-F313A 3x4 91-3 C4 2/C RV -

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

GE-T2 -1180

O O O

" " system RH-Residual Heat Removal INSERVICE TESTING PLAN

@ Lase #e County Nuclear Station Unit 1 ,

p.g. jj og jj 02 03 04 05 08 07 08 09 10 11 12 13 00 01 1E12-F3138 3x4 91-3 C3 2/C RV -

C RV RR A RHR Heat Exchange Relief (See Note 2) lE12-F023 6 96-1 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) lE12-F024A 18 96-1 E2 2/A GB M0 C FS,ST Q 297 RV-19 A RHR Test Line for D2 LT RR Suppression Fool Cooling (See Note 4,6,8) lE12-F042B 18 96-2 E2 2/A GB M0 C FS,ST Q 297 RV-19 A RHR Test Line for LT RR Suppression Pool Cooling (See Hote 4,6,8)

GE 72-1180

O O O INSERVICE TESTING PLAN

@L. i. ty m s until VALVES gm RI-Re ctor Core Isolation Coolant 1 4

# 00 p' c*

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03 04 05 06 07 08 09 10 11 12 13 00 01 02 lE51-F010 8 101-2 A4 2/B GT M0 O FS,ST Q 80 A Suction from CST Downstream Stop lE51-F0ll 8 101-2 B3 2/C CV -

C E Q A Suction from CST Downstream Check l E51-F008 4 101-1 E7 1/A GT MO 0 FS,ST CS 20 RV-31 A Steam Supply Outboard LT RR RV-19 Isolation (M-15)

(See Note 1,4) lE51-F013 6 101-2 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) lE51-F017 .75 101-2 B2 2/C RV SP C RV RR A Pump Suction Relief x1.0 (See Note 2) 1E51-F018 1.5 101-2 F3 2/C RV SP C RV RR A Turbine Lube Oil Cooler x3.0 Inlet Relief (See Note 2) l E51-F019 2 101-2 BS 2/A GB M0 C FS,ST Q 7 RV-19 A Minimum Flow B'ypass t

LT RR Stop (See Note 4,6,8)

I i lE51-F028 1.25 101-1 B6 2/C NSC -

C E Q A Barometric Condenser Vacuum Pump Discharge (ft-81)(See Note 4) l E51-F030 8 101-2 B6 2/C CV -

C PS Q RV-36 A Pump Suction From E R.1 Suppression Chamber GE-T2 -1180

O O O to we ey er sia unist INSERVICE TESTING PLAN gaiem RI-Rejetor Core Isolation Coolant U

4h 9 oO at A y 44 4 g- d 00 01 02 03 04 05 06 07 08 09 10 11 12 13 lE51-F031 8 101-2 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) lE12-F036A 4x6 101-2 C6 2/C RV SP C RV RR A RCIC Safety Relief Valve Discharge Condensate (M-101) (See Note 2) 1E12-F0368 4x6 101-2 B3 2/C RV SP C RV RR A RCIC Safety Relief Valve Discharge Condensate l (M-92) (See flote 2) lE51-F040 10 101-1 B7 2/C CV -

C E Q A Turbine Exhaust Check (M-76) (See Note 4) lE51-F045 4 101-1 D5 2/B GB M0 C FS,ST Q 120 A Turbine Exhaust Supply Stop lE51-F046 2 101 -2 D3 2/B GB f10 C FS,ST Q 60 A Turbine Lube Oil Cooler Supply Stop _

1E51-F047 2 101-1 B6 2/C CV -

C E Q A RHR Condensate Pump Discharge Check lE51-F061 .75 101-2 A3 2/C CV -

C E Q A Water Leg Pump Discharge Check u

GE-T 2 -118s

O O O

@ se us INSERVICE TESTING PLAN VALVES (ystem RI-Reactor Core Isolation Coolant I

$ 9 O q A cf *' .O O

00 01 02 03 04 05 06 07 08 09 10 f 11 12 13 1E51-F063 10 101-1 E8 1/A GT M0 0 FS,ST CS 15 RV-31 A Steam Supply Inboard LT RR RV-19 Isolation (M-15)

PIT RR (See Note 1,4,6) 1E51-F064 10 101-1 E7 1/A GT M0 C FS,ST CS 15 RV-15 A Steam Supply Inboard LT RR RV-19 Isolation (To RHR)

(M-15) (See Note 1,4) 1E51-F065 6 101-2 C7 1/C CV A0 C E Q RV-19 A RCIC Injection Outboard PIT RR Testable Check (M-29)

LT RR (See Note 5,7) l E51-F066 6 101-2 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) lE51-F068 10 101-1 B7 2/A GT MO 0 FS,ST Q 55 RV-19 A Turbine Exhaust Isolation LT RR (M-76) (See Note 4,6) 1E51-F069 1.25 101-1 B7 2/A GB M0 0 FS,ST Q 20.6 RV-19 A Barometric Condenser LT RR Vacuum Pump Discharge Stop (M-81)

(See Note 4,6) lE51-F076 1 101-1 E8 1/A GB M0 C FS,ST Q 15 RV-19 A Steam Supply Inboard LT RR Isolation Valve Warm-Up PIT RR Bypass (M-15)

(See Note 4,61 GE-T2 1180

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O O O INSERVICE TESTING PLAN syemm RR Reactor Recirculation La own sia uniti #

VALVES 1 3 8

00 01 02 03 04 05 06 07 08 09 10 11 12 13 IB33-F019 .75 93-02 E6 2/A GB A0 0 FS Q RV-02 A Process Sampling LT RR RV-19 (See Note 4)

PIT RR IB33-F020 .75 93-02 E8 2/A GB A0 0 FS Q RV-02 A Process Sampling LT RR RV-19 (See Note 4)

IB33-F319A .75 2093-8 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F319B .75 2093-8 2/AC EFC -

0 E RR RV-34 A See Note 10 LT .

1B33-F317A .75 2093-8 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F317B .75 2093-8 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F313A .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F3138 .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F313C .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT GE-T 2 -1180

I Oa ey is i uni 1 INSERVICE TESTING PLAN **m RR-Reactor Recirculation 4 A O O C) A Cy Q x. f 00 01 02 03 04 05 06 07 08 09 10 11 12 13 IB33-F313D .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT IB33-F311A .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F311B .75 2093-2 2/AC EFC - 0 E RR RV-34 A See Note 10 LT 1833-F311C .75 2093-2 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1B33-F311D .75 2093-2 2/AC EFC -

0 RR RV-34 A See Note 10

{

.75 2093-3 2/AC EFC 0 E RR RV-34 A See Note 10 1833 r315A -

LT

.75 2093-3 2/AC EFC - 0 E RR RV-34 A See Note 10 1833-F315B LT

.75 2093-4 2/AC EFC 0 E RR RV-34 A See Note 10 1B33-F315C -

LT 1B33-F3150 .75 2093-4 EFC 0 E RR RV-34 A See Note 10 2/AC -

LT 1833-F301A .75 93-1 08 2/AC EFC -

0 E RR RV-34 A See Note 10 LT GE-T2 -1180

O O O Commonwealth Edison RR-Reactor Recirculation O Lesene County Nucteer Stetton VALVEJ Unit t INSERVICE TESTING PLAN system Pege 3 or 3

# oO t 4 y cf 0 p 00 01 02 03 04 05 06 07 08 09 10 11 12 13 1833-F3018 .75 93-2 D8 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F307A .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F307B .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F307C .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F307D .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT IB33-F305A .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10

! LT 1833-F305B .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT ,

1B33-F305C .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT 1833-F305D .75 2093-1 2/AC EFC -

0 E RR RV-34 A See Note 10 LT GE-T2 1180

l 0 .

o o f Commonwealth Edison INSERVICE TESTING PLAN syaiem RT-4EACTOR WRTER CLEAMP tasane county Nuclear Stanon Unit 1 P898 1 of 2 VALVES u b

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07 08 09 10 11 12 13 CD 01 02 03 05 06 l

6 97-1 E8 1/A GT M0 O FS,ST CS 30 RV-06 A C.U. Suetical Inboard l 1G33-F001 LT RR RV-19 Isolation (M-30)

PIT RR (See Note 1.4.6) 6 97-1 E7 1/A GT M0 O FS,ST CS 30 RV-08 A C.U. Outboard 1G33-F004 LT RR RV-19 Isolation (M-30)

Pli RR (See Note 1,4) 1.5 91-2 E8 3/C RV - C RV RR A RWCU Hx Relief (See 1G33-F339A Note 2),

X2.5 1.5 91-2 C8 3/C RV C RV RR A RWCU Hx Relief (See IG33-F3390 -

x2.5 Note 2).

1G33-F340A 1.5 91-2 E8 3/C RV - C RV RR A RWCU Hx Relief (See x2.5 Note 2).

1G33-F3400 1.5 91-2 C8 3/C RV -

C RV RR A RWCU Hx Relief (See x2.5 Note 2).

1G33-F341A 1.5 91-2 ES 3/C RV -

C RV RR A RWCU Hx Rell'r e (See x2.5 Note 2).

IG33-F 341B 1.5 91-2 C5 3/C RV - C RV RR A RG Hx Reller (See x2.5 Note 2).

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m, INSERVICE TESTING PLAN SA-Service Air

, 3 AN 9* o0 c,83 4y 4 ys e,A *s cd ,0 94 00 01 02 03 04 05 06 07 08 09 to 11 13 ISA042 3 82-03 B7 2/A GT t1 C LT RR RV-19 P (l1-38) (See Note 13)

RV-37 15A046 3 82-03 87 2/A GT T1 C LT RR RV-19 P (!1-38) (See Note 13)

RY-37 GE-T2 -1180

O O O sysam SC-STN(181f LIQUID CONTROL INSERVICE TESTING PLAN O Las e oun y les siei unit i VALVES

'> O g.4 c,U 40 0 *> t- g 9

10 11 12 13 08 09 00 01 02 04 05 06 / 07 I iS,ST RR 15 RV-13 A A SS.C Ptsap Suction 99 C2 2/8 PG M3 C l IC41-F001A 3 Stop (See Note 1) 1 15 RV-13 A B SELC Pump Suction 3 99 82 2/8 PG MO C FS,ST 11R IC41-F0018 Stop (See Note 1)

EV FN-19 A Ptsap Injection Squib IC41-F004A 1.5 99 C5 1/A, GT EX C FC D LT RR I Valve (M-34)(See Note 4)

EX C FC EV RV-19 A Ptsap Injection Squib IC41-FOC'.B 1.5 99 85 'l/A, GT D LT RR Valve (M-34)(See Note 4)

C E RR RV-14 A Dutboard Check (M-34)

IC41-F006 1.5 99 06 1/C NSC -

1/A, C E RR RV-14 A Itboard Check (M-34)

IC41-F007 1.5 99 07 NSC -

LT RR RV-19 (See Note 4)

C R/ A Pump Discharge Relief IC41-F029A .75 99 D4 2/C R/ SP C RR (See Note 2) x1 RV SP C RV RR A Pump Discharge Reller IC41-F029B .75 99 C4 7; ;

(See tbte 2) l x1 Q A Pump Discharge Chttk IC41-F033A 1.5 99 C4 2/C NSC - C E 1.5 99 Ba 2/C !!SC -

,C E Q A Pumo Discharge Check IC41-F033B l

i I

O O O Commonwealth Edison sysm WP-PRIAN CSfTAlteENT INSERVICE TESTlNG PLAN

@ Lesene county Nucieer Station Unit i

VALVES P*9* 1 of 1 VENTILATION

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11 12 13 03 04 05 06 07 06 09 to 00 01 02 M 0 FS,ST RR 40 RV-17 A Chilled Water Return IVP0534 8 86 E2 2/A GT (M-27) (See Note 1,4)

LT RR RV-19 FS,ST RR 40 RV-17 A Chilled Water Return 1VPO538 8 86 C2 2/A GT M0 C (H-28) (See Note 1.4)

LT RR RV-19 .

FS,ST RR 40 RV-17 A Water Supply IVP063A 8 86 02 2/A GT MO O (M-25) (See Note 1,4)

LT RR RV-19 FS ST RR 40 RV-17 A Water Supply lVP063B 8 86 B2 2/A GT MD C RV-19 (M-26) (See Note 1,4)

LT RR FS,ST RR 90 RV-17 A Water Supply IVPil3A 8 86 02 2/A BF HQ O (M-25) (See Note 1,4,6)

LT RR RV-19 PIT RR FS,ST RR 90 RV-17 A Water Supply IVPil38 8 86 82 2/A BF MO O (M-26) (See Note 1,4,6)

LT AR RV-19 PIT RR 2/A 0F MO O FS,ST RR 90 cv-17 A Dillied Water Return IVPil4A 8 86 E2 (M-27) (See flote 1,4,6)

LT RR RV-19 PIT RR FS,ST RR 90 RV-17 A Chilled Water Return IVPil4B 8 86 C2 2/A 0F MO O (M-28) (See flote 1,4,6)

LT RR RV-19 PIT RR

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O o O i system VQ-PRINIRY C(NTAlf0ENT N 0" INSERVlCE TESTING PLAN '

VALVES I -

N f 9# 00 sY s y & & 6-11 12 13 05 06 07 08 09 to 01 02 03, 04 00 FS,ST CS 130 W-09 P Outboard to 9 --wssion 92-1 2/A EF MD C chenber Fr. Rx. Bldg. !

IVQO26 26 C2 LT m RV-19 inboard (PCIS)

Isolstion Damper (M-66)

(See Note 1) 130 RV-09 P Inlet to Suppression ;

2/A BF MD C FS,ST CS Chenher Fr. Rx. Bldg.

IVQO27 26 92-1 C3 m RV-19 LT Inboard (PCIS)

Isolation Damper (M-66) j (See Note 1)

CS 130 HV-09 A Inlet to Drywell Fr 2/A BF MD C FS,ST Rx. Bldg. Datboard IVQO29 26 92-1 D2 RR RV-19 LT Isolation Damper (PCIS) i (M-20)f See Not.e 1,41 CS 130 RV-09 A Inlet to Drywell Fr -

2/A BF M0 C FS,ST Rx. Bldg. Inboard IVQO30 26 92-1 D3 hR RV-19 LT Isolation Demper (PCIS)

(M-20)(See Note 1,4,6) 130 RV-09 A Suction Fr Rx. Bldg.

C FS,ST CS IVQO31 26 92-1 C7 2/A EF M0 RV-19 Inboard Isolation LT RR Damper (PCIS) (M-67)

(See Note 1) 1 a aw axn - __________._~

O O O yN Sta Unit 1 INSERVICE TESTING PLAN w VQ-Pyimary Containment Purge t.a 00

/

01 my:Wg//

02 03 04 05 06 07 i

08 09 10 11 2 13

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IVQ032 2 92-1 C7 2/A GB M0 C FS,ST CS 10 RV-09 P Bypass Suction LT RR RV-19 (See Note 1,4,6) lVQO34 26 92-1 E6 2/A BF M0 C FS,ST CS 130 RV-09 A Suction Fr. Drywell LT RR RV-19 Inboard Isolation Damper (PCIS) (M-21)

(See Note 1,4,6) 1VQO35 2 92-1 E6 2/A GB M0 C FS,ST Q 5 RV-19 P Suction Fr. Drywell LT RR Inboard Isolation Damper Bypass Inboard (M-21)

(See Note 4,6)

IVQO36 26 92-1 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) 1VQ037 26 92-1 88 2/B BF M0 C FS,ST Q 90 A Pritre Cont. Ventilation Secondary Containment Inboard Isolation Damper (PCIS) lVQO38 26 92-1 B7 2/8 BF F10 C FS,ST Q 90 A Prime Cont. Ventilation Secondary Containment Outboard Isolation Damper (PCIS)

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02 03 04 05 08 07 08 09 10 11 12 13 00 01 IVQ040 26 92-1 C8 2/A BF M0 C FS,ST CS 130 RV-09 A Suction from Suppression LT RR RV-19 Chamber Outboard Isolation Damper (PCIS)

(See Note 1,4) lVQ041 26 92-1 A8 2/B BF M0 C FS,ST Q 90 A Suction Fr Rx Bldg.

Return Air Riser IVQ068 2 92-01 E7 2/A GB M0 C FS,ST Q 5 RV-19 A (See Note 4)

LT RR IVQ047 1.5 92-01 D3 2/A GB M0 0 FS,ST Q 23 RV-19 A (See Note 4,6)

LT RR

! IVQ048 1.5 92-01 D3 2/A GB M0 0 FS,ST Q 23 RV-19 A (See Note 4)

LT RR IVQ050 1.5 92-01 C3 2/A GB M0 O FS,ST Q 23 RV-19 A (See Note 4,6)

LT RR IVQ051 1.5 92-01 C3 2/A GB M0 0 FS ,P Q 23 RV-19 A (See Note 4)

LT RR IVQ042 8 92-01 02 2/A BF M0 C FS,ST CS 90 RV-09 (See Note 1,4)

LT RR RV-19 IVQ043 8 92-01 C2 2/A BF M0 C FS.ST CS 90 RV-09 (See Note 1,4)

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@ Commonwealth Edison t Salle County Nuclear Station Unit i PUMP & V ALVE TESTING RELIEF REQUESTS Page 1 of 1 r

E ASME P PUMPOR yO SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE TEST o

00 01 02 03 04 05 06 RV-01 ODG-009 3/B Cooling Water Full stroke and These valves open in Perform a full stroke 1

Discharge stroke time quarter- response to an auto- exercise once per ly backwash logic signal pro- quarter duced by an abnormally 1DG-Oll 3/B Strainer Backwash high differential pressure Valves across the CSCS service water strainers. These 1E12-F336A 3/B RHR Service Water valves stroke very quick-Pump Strainer 1A ly, and because they are Backwash Outlet not manually controlled, Stop an accurate stroke time measurement is very 1E12-F336B 3/B RHR Service Water difficult to obtain.

Pump Strainer 1B Furthermore, the initia-Backwash Outlet tion time of this back-Stop wash feature is not considered a meaningfel lE12-F319 3/8 HPCS Diesel indicator of operational Cooling Water readiness. The ability Strainer Backwash of this valve to open Outlet Stop upon receipt of a back-wash signal is confirmed quarterly.

t al 13

O O O Commonwealth Edison

@ LaSaHe County Nuclear PUMP &Station VALVE TESTING RELIEF REQUESTS Unil l Page 1 of 2 ASME 33 PUMPOH QO SECTION XI go VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTEFiNATIVE TEST U

00 01 02 03 04 05 06 RV-02 IINU17 2/A Drywell Pneumatic Full Stroke and These valves are designed Perform a full stroke to Drywell - Stroke Time to stroke rapidly with- exercise quarterly.

Fail Close Quarterly in a specified time range. Verification lIN074 2/B Dryer Purging Vahe that the valve strokes

- "Fail Close within the time range is IIN075 2/B essential, but due to the inaccuracies involved IINO31 2/A TIP Indexer Purge with measuring short time intervals, stroke 1833-F019 2/A Process Sampling time trending provides Valve no useful information 1833-F020 2/A and may evel lead to useless and unnecessary 000004 3/B Diesel Oil Transfer maintenance operations.

Pump Stop Valve Therefore, the stroke 1D0004 3/B " "

times of these valves will not be trended, 100014 3/B but will be verified to not exceed 5 seconds.

100024 3/B 1CM017A 2/A 1CM0178 2/A 1CM018A 2/A 1CM018B 2/A .

ICM019A 2/A wn

O O O

@ Commonwealth PUMP tasan county Nuclear Statson Unit 1 Edison

& VALVE TESTING RELIEF REQUESTS Page 2 of 2 S ASME 33 PUMP OH QO SECTION XI gO VALVE NO. FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF ALTERNATIVE TEST o

00 01 02 03 04 05 06 RV-02 1CM019B 2/A Diesel Oil Transfer (cont'd) Pump Stop Valve ICM020A 2/A 1CM020B 2/A 1CM021B 2/B 1CM022A 2/B 1CM023B 2/B 1CM024A 2/B 1CM025A 2/B 1CM0268 2/B 1CM031 2/A 1CM032 2/.A 1CM033 2/A 1CM034 2/A e,I f3

O O O Commonwealth Edison

@ LaSaHe County Nuclear PUMP &Stauon V ALVE TESTING RELIEF REQUESTS Unit 1 Page i of g ASME 33 PUMP OR $O SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TdST 01 02 03 04 05 06 00 j RV-03 LWR-029 2/A Drywell Equipment Full Stroke Reactor recirculation Perfo11n a full stroke RECCW lsolation Exercise Quarterly pump operation Exercise during cold requires a continuous shutdown.

LWR-040 2/A " " cooling water flow from the reactor 1

LWR-179 2/A " " tx111 ding closed cooling water system.

LWR-180 2/A " " Exercising these valves during operation interupts this flow from the i reactor building closed cooling wai.er system.

f This could result in i

dama0e to these pumps and thus place the

, plant in a less safe

mode of operation.

G E.13

O O O

@ CommonwealthEdisc,n t.aSaHe County Nuclear Station Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of 1

$33 PUMP OR E

$O ASME SECTION XI TEST F1EQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST VALVE NO. FUNCTION o 06 02 03 04 05 00 01 RV-04 lE21-F005 1/8 LPCS Injection Full Stroke These valves cannot be Perform a full stmke Line Outboard Exercise exercised during normal exercise during cold stop Quarterly operation because they shutdown, are electrically inter-1E12-F008 1/A RtB Shutdown locked shut by nonnal Cooling Pump operating differential 1/A Suction IDR pmssure to protect the Isolation low pressure piping outside the drywell.

IE12-F009 1/A 1E12-F050A 1/C RtB Shutdown Cooling Testable Check lE12-F0500 1/C lE12-F053A 1/8 RER Shutdown Cooling Discharge Isolation IE12-F053B 1/B RlR Shutdown Cooling Discharge Isolation IE12-F023 1/B RIH to llead Spr:iy G E .13

O O O Commonwealth Edison g/ LaSaue County Nuclear Station Unit 1 PUMP & V ALVE TESTING Page 1 of 1 RELIEF REQUESTS s >

b@ So ASME 33 PUMP OR $O SECTION XI VALVE NO. FUNCTION TEST REQUIREMENT DASIS FOR RELIEF ALTERNATIVE TEST o

01 02 03 04 05 06 00 RV-05 l E51-F013 1/B RCIC Outboard In- Full Stroke Exer- During power operation, Perform 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.

The valve may be exer-cised during cold shutdowns when reactor ,

~

pressure has been sub-stantially reduced.

bl 13

O O O

@ Commonwealth PUMP tasan. county Nuclear Station Unit 1 Edison

& VALVE TESTING RELIEF REQUESTS Page 1 of 1 9 *

$$ 5O ASME 33 PUMPOR VALVE NO.

$0 FUNCTION SECTION XI TEST REQUlHEMENT BASIS FOR RELIEF ALTERNATIVE TESI 00 01 02 03 04 05 06 RV-06 IB21-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 1821-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 valves will be exercised at each refueling outage when the feed-water flow is interrupted ,

tal 13

O O O Page 1 of

@ Commonwealth Edison LaSWh County Nuclear Station Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS 1

> I EO ASME SECTION XI 33 PUMP OR QO FUNCTION TEST REQUIREMENT BASIS FOR DEllEF ALTERNATIVE. TEST VALVE NO.

o 06 02 03 04 05 00 01 RV-07 1821-F065A 2/A Rx Feedwater Full Stroke It is impractical to Perform a full stroke Isolation Valve Exercise Quarterly exercise these valves exercise during cold 1821-F0658 2/A " " during normal operation shutdown.

because the feedwater system is needed to maintain primary coolant inventory.

Exercising them would deprive the flow of I feedwater to the vessel thus putting the plant in a less safe condition. ,

1 GE- T3

O O O Commonwealth Edison

@ LaSaHe County Nuclear Station Unit 1 PUMP & VALVE TESTlNG RELIEF REQUESTS Page 1 of 1 5 ASME 33 PUMP OH MO SECTION X1 VALVE NO. FUNCTION TEST FIEQUlHEMENT BASIS FOR RELIEF ALTERNATIVE TES T o

00 01 02 03 04 05 06 HV-UU 1G33-F001 Inboard Suction Full Stroke Exer- The entire RWCU system 1/A Perform a full stroke Isolation cise Quarterly must be inoperable exercise during cold before any of these shutdown 1G33-F004 1/A Outboard Suction -

valves can be closed.

Isolation This system maintains reactor water chemistry 1G33-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. Therefore, these valves will be full stroke exercised during each cold shut-down.

i. 3

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@ Commonwealth Edison LaSaHe County Nucleer Stauen Unit 1 PUMP & VAf.VE TESTING RELIEF REQUESTS 2

E ASME SECTION XI i3 PUMP OR QO FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST VALVE NO.

03 04 05 06 00 01 02 RV-09 1YQO26 2/A Outboard to Full Stroke These valves cannot be Perfom a full stroke Suppression Exercise exercised durin0 normal exercise during cold Chamber Fr. Rx Quarterly operation. These valves shutdown.

Bldg. Inboard are required to remain (PCIS) Isolation administratively shut Damper during power operation, in accordance with the IVQ027 2/A Inlet to Final Safety Analysis Suppression Report arnt the Chamber Fr. Rx Technical Specifications.

Oldg. Inboard The response to FSAR (PCIS) Isolation Question 021.54 Danper further explains that valve IVQO32 canrrot ce IVQO29 2/A Inlet to Drywell opened in an operating Fr. Rx. Oldg. or hot shutdown mode, Isolation Damper and hence can only be testad while in cold (PCIS) t hutJown. Valye IVQO30 IV0035 does not havt t.iis restriction, ar.d IVQO31 2/A 50ction Fr. h3nce is not contair.ed suppression aa this relief requtst.

Chanber Inboard Isolation llanper GL 73

_~

O O O of 2

@ CommonwealthEdison LaSane County Nuclear Stauon Unit 1 PUMP & VALVE TESTING Page 2 RELIEF REQUESTS So ASME SECTION XI 33 PUMP OR QO TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST y VALVE NO. FUNCTION o 06 01 02 03 04 05 00 RV-09 IVQO34 2/A Suction Fr. Full Stroke Perform a full stroke Drywell Inboard Exercise Quarterly exercise during cold Isolation Damoer shutdown.

PCIS IVQO36 2/A Suction Fr.

Drywell Oatboard Isolation Damper Oypass IVQ042 2/0 IVQ043 2/0 IVQO32 2/A Dypass Suction IVQ040 2/A %ction From Suppression Chamber Outboard Isolation Damper (PC15)

GL-I3

O O O Page 1 of 1

@ Commonwealth Edison LaSaHe County Nucks Station Unit t PUMP & VALVE TESTING RELIEF REQUES7S li)

PUMP OR N ASME SECTION XI 33 VALVE NO.

QO FUNCllON TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST o

00 of 02 03 04 05 06 RV-10 lE22-F016 2/C Suppression Pool Exercise Quarterly The HPCS 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 e.est.

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 HPCS pump suction to the suppression pool. Allow-ing suppression pool water to enter the HPCS system permits the passibility of cycled condensate con-tamination wnich would cause many of the units' systems to become contami-nated. This situation is undesirable at all times, but may be guarded against if tested during refueling outages.

Therefore, it is requested that this valve be full stroke exercised during each refueling outage, i.i n

O O O Page 1 of

@ CommonwealthEdison PUMP & VALVE TESTING LaSaHe County Nucker Stanon Unit 1 1 RELIEF REQUESTS I

E ASME 33 PUMP OR $O SECTION Xi FUNCTION TEST REQUIREMENT DASIS FOR RELIEF ALTERNATIVE TEST V ALVE NO.

03 04 05 06 00 01 02 RV-Il IE32-F001A 1/A MS Oleed Valve Full Stroke Exercise These valves cannot be Perform a full. stroke IE32-F001E 1/A MS Bleed Valve Quarterly exercised during normal exercise during cold IE32-F001J 1/A MS Bleed Valve operation. These valves shutdown.

lE32-F00lN 1/A MS Oleed Valve are designed to operate lE32-F003A 2/O HS Loop Bypass when the main steam line IE32-F003E 2/8 to Steam Tunnel pressure is near IE32-F0033 2/8 " " " atmospheric. Testing IE32-F003N 2/8 " " " of these valves at 1E32-F002A 2/8 MS Loop Bleed nonnal steam line lE32-F002E 2/B Valve pressure has the

" " " potential for lE32-F002J 2/8 1E32-F002N 2/8 " " " discharging live steam lE32-F006 2/0 Bleed valve- into the Reactor IE32-F007 2/8 Steam Tunnel Building Atmosphere.

IE32-F008 2/U 1E32-F009 2/U i

l

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GE-13

1 O O O i

l Commonwealth Edison LaSalle County Nuclear Station Unit i PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS ,

e-

b$ N ASME SECTION XI 33 PUMP OR $O gO VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE TEST 00 Ol 02 03 04 05 06 RV-12 IIN017 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 Fall Close side of the compressor with fail safe oper-from the drywell, they ation. Test each llN001A 2/A Drywell Suction may be stroked closed refueling outage Isolations - Fail only when the nitrogen except IIN043 Close compressor is shutdown. and IIN044 will not Normally, this occurs only be fail safe tested.

IIN001B 2/A Drywell Suction during refueling outages Isolations - Fail because instrument nitro-Close gen is needed for control of the MSRV's, the in-11N074 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 lIN075 2/A Dryer Purging actuator power each sampling line on RR. The Valve. - Fail Close quarter, instrument air alternate emergency supply cannot IINO31 2/A Tip Indexer Purge be used during power Valve operation or cold shut-down as it would contami-IIN043 3/C ADS Supply Check nate the drywell nitrogen Valve atmosphere. Therefore, these valves will be lIN044 3/C ADS Supply Check stroked at each refueling Valve outage when the drywell is de-inerted and the instrument nitrogen system is shutdown.

l

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@ Commonwealth Edison LaSaHe County Nucles: Station Unit 1 PUMP & V ALVE TESTING RELIEF REQUESTS Page 1 of 1 r >

$$ 50 ASME 33 PUMPOR QC SECTION X1 V At.V E NO. TUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERN ATlVE TEST g

00 01 02 03 04 05 06 RV-13 1C41-F001A 2/B SBLC Pump Suction Full Stroke Exer- During the testing of Perform a full stroke Stop Valve cise Quarterly these valves, the system exercise durbg is aligned so that a reactor refueling.

1C41-F001B 2/B SBLC Pump Suction greater pressure exists 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-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 l

considerable length of time the testing pro-( cedure and chemical l analysis requires. It is requested that the test-ing frequency for these valves be every refueling outage.

t el f3

O O O Page 1 of

@ Commonwealth Edison 1

LaSalle County Nuclear Station Unit 1 PUMP & V ALVE TESTING RELIEF REQUESTS

(

l 5 ASME SECTION XI l 53 PUMP OR VALVE NO.

$0 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 03 04 05 06 l 00 01 02 1/C Sa_C Outboard Exercise Quarterly These valves camot be Exercise during RV-14 1C41-F006 Check exercised during reactor refueling.

reactor operation IC41-F007 1/C Inboard Check nor durng cold shutdown.

To exercise these valves open, the system nust inject into tte vessel.

A system injection is not practical during nonnal operation or cold shutdown; the explosive charges would have to be detonated and ttm system taken out of service.

It GE-T3

O O O

@ Commonwealth Edison LaSalle C ,unty Nuclear Station Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of 1 bd 50 ASME 33 PUMP OR VALVE NO.

$0 FUNCTION SECTION XI TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RV-15 1E51-F064 1/A High Energy Line Full Stroke Exer- This valve is located at Perform a full stroke Break Safeguard cise Quarterly the interface of high exercise during and low pressure piping. cold shutdown.

Opening.the valve during power operation would result in severe water hamer and thermal shock to the low pressure piping. This valve may be stroked at each cold shutdown when reactor water pressure and temperature have both been reduced.

i.e s a

O P O V C) V

@ Commonwealth PUMP LaSaHe County Nuclear Station Unit 1 Edison

& VALVE TESTING RELIEF REQUESTS Page 1 of 1 5 ASME 13 PUMPOR $O SECTION X1 gO VALVE NO. FUNCTION TEST REQUIREMENT DASIS FOR RELIEF ALTERNATIVE TESI' o

00 0t 02 03 04 05 06 RV-16 IB21-F024A 3/C MSIV Accumulator Exercise Quarterly Entry into the drywell Exercise during Check Valves is required to confirm reactor refueling the closure of these outage.

IB21-F024B 3/C check valves. Since the drywell atmosphere is 1821-F024C 3/C normally inerted with nitrogen gas at all 1821-F024D 3/C times except refueling outages, these valves IB21-F040C 3/C ADS Accumulator may be exercised only Check Valves during refueling outages when drywell 1821-F040D 3/C entry is possible.

1821-F040E 3/C 1821-F040R 3/C 1821-F040S 3/C 1821-F040V 3/C 1821-F040V 3/C t.1 f3

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Coni nonwealth Edison LaSane County Nuclear Station Unit 1 PUMP & VALVE TESTING P e 1 of 1 RELIEF REQUESTS e- >

$$ SO ASME SECTION XI 33 PUMPOH $O gO VALVE NO. FUNCTION TEST REQUlHEMENT BASIS FOR RELIEF AliERNATIVE TEST 00 01 02 03 04 05 06 RV-17 IVPUd3A 2/A Chilled Water Return Full Stroke Exer- Closing any one of these Perform a full stroke cise Quarterly isolation valves would exercise during IVP053B 2/A prevent chilled water refuelt: ' outages.

from reaching the primary IVP114A 2/A containment cooling units. The systems IVPil4B 2/A operation is essential during power operation IVP063A 2/A Chilled Water and is also necessary Supply during cold shutdowns to maintain acceptable IVP063B 2/A conditions in the drywell for equipment and main-l IVP113A 2/A tenance personnel. These valves will be exercised IVPil3B 2/A at refueling outages

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

l l

I l

l l

t t ot f3

O O O Page 1 of 1

@ Commonwealth Edison LaSane County Nuclew Station Unit 1 PUMP & VALVE TESTING REllEF REQUESTS

$ 5 ASME SECTION XI 33 PUMP OR $0 FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TE ST VALVE NO.

04 05 06 00 01 02 03 RV-18 IB33-F017A 2/C CRD Flow CVA Exercise Since these lines form NA Outlet Quarterly part of the reactor coolant pressure IB33-F017B 2/C CRD Flow CVB boundary, the conse-Outlet quences of line failure was carefully IB33-F013A 2/C CRD Flow CVA evaluated. It is Outlet determined that conse-quences of failure would IB33-F0138 2/C CRD Flow CVB be less severe than an Outlet instrument line failure, and thereby exempting thes3 valves from Inservice Testing. (Ref. IWV-1300) l GE-T3

O O O CommonwesHh Edison

@ LaSane County Nuclear PUMP &Station VALVE TESTING Unit i Page 1 of 1 RELIEF REQUESTS

$ 5 ASME 33 PUMP OR $O SECTION XI VALVE NO. FUNCTION TEST REQUnREMENT BASIS FOR RELIEF ALTERNATIVE TES T 00 01 02 03 04 05 06 RV-19 All Cateaory A --

N/A Perform a Seat Primary containment Seat leak test in primary con- Leakage Test Per Category A isolation accordance with tainment iso- IWV-3420 valves will be seat 10CFR50 Appendix J.

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

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O O O Commonwealth Edison

@ LaSalle County Nuclew PUMP Station

& VALVE TESTING RELIEF REQUESTS Unit 1 Page 1 of 1

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$0 FUNCTION SECTION XI TEST nEOUlf1EMENT DASIS FOR RELIEF ALTEF1HATIVE TESI o

00 01 02 03 04 05 06 RV-20 Deleted 1

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@ CommonwealthEdison tasane county Nuclear Station Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS n

ACME 33 PUMP OR $O SECilONXI TEST REQt'!REMENT BASIS FOR RELIEF ALTERNATIVE. TEST VALVE NO. FUNCTION t.

U 03 04 05 06 00 01 02 -

] .

1E21-F006 1/C Primary Containment Exettise Quarterly Exercising these valves Exercise during cold '- -

RV-21 Inboard Isolation ducire reactor operation stutdown.

I valves requires opening the equal! zing'valvo around lE12-F041A 1/C Primary Contairrtent the valve and then Inboard Isolation opening the valve. If Valves a system initiation were received at this point, lE21-F041B 21/C Primary Containment the ptsnps would start and '

Inboard Isolation the injection valve Vabes would open. The injection valve requires lE12-F041C 1/C Prim;mj Contalimnt 6 7292 dp across it to Inboard Isolatfoa open, and the pump .

Valver, head would casily give' I that. When the injection ' -

valve opens, should the check val a fall ,

to close, or if it leaked, it would supply a path for Reactor Pmssure to Llw low pmssure pipi:aj of the e low pressure ECCS sy st. ems. A one inch relief valve set at 500# 69t;d rulleve to tie d.g "tussion pool and provicie a loss nt I

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O O O Page 2 of 2

@ Commonwealth Edison LaSalle County Nuclear Station Unit 1 PUMP & VALVE TEST 3NG RELIEF REQUESTS E ASME SECTION XI 3D PUMP OR $0 BASIS FOR RELIEF ALTERNATIVE TEST g VALVE NO. g* FUNCTION TEST REQUIREMENT 04 05 08 00 01 02 03 RV-21 Cmtinued coolant flow from the reactor to the suppressim pool, pcssitsly over-pressurizing the low pressure piping with an initiatim already presmt. Also, opming the valve during Reactor operatim gives mly me valve protectim to the

. low pressure piping.

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@ Commonwealth Edison LaSans County Nuclear Station unit 1 PUMP & VALVE TESTING RELIEF REQUESTS ASME I. SECTION XI 33 PUMP OR QO FUNCTION TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE. TEST VALVE NO.

04 05 08 00 01 02 03 1821-F022A 1/A Primar'; Contain- Full Stroke And Full stroke testing Part struke exercise RV-22 these valves during quarterly, perfora a ment Isolation Stroke Time For oin n Steam Quarterly. Check normal reactor operatinn full stroke exercise The Fall-Safe requires isolating one and stroke time durin ;

1/A Primary Contain- Operation Of The of the four main steam cold shutdown. Tte 1821-F0228 ment Isolation valve Upon Loss lines. Isolation of fail-safe operation for Main Steam Of Actuator Power these lines results in of these valves will l Quarterly. primary system pressure also be checked .

1/A Primary Contain- spikes, reactor power during cold shutdown IB21-F022C ment Isolation fluctuations, and in- sirce this is done For Main Steam creased flow in the coincident with full unisolated steam lines. stroke exercising.

IB21-F022D 1/A Primary Contain- l This unstable operation The fall-safe ment Isolation can lead to a reactor testing of valves For Main Steam scram, and as discussed IU21-F022A, B, C, and in ifJREG-0626 pressure D, however, will be ID21 F028A 1/A Primary Contain- transients resulting completed only at ment Isolation frcm full stroke testing cold shutdowns in For Main Steam W,IV's increase the which the primary chwces of actuatiog containment is 1021-F028B 1/A Primary Contain- deinerted since acces ,

nent Isolation f valves.

prtaary Itsystem is proposed relief to the valves to For Main Steam inat only partial perform this testing stroke testing be required entry into IO21-F02HC 1/A Primary Contain- perfomed duriag the drywell.

ment Isolation power opt >r.liion and for M. sin Steam that tle valve be full strokcu wn! stroke lined 03-10 _ . .

O O O Commonwealth Edison

@ LaSane County Nucker PUMP Station & VALVE TESTUnit RELIEF REQUESTS 4NG 1 Page 2 of 2

!!i 5 ASME SECTION XI 3D PUMP OR QO FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE. TEST VALVE NO.

03 04 05 06 00 01 02 RV-22 Cbntirmed during cold stutdowns.

IB21-F0280 1/A Primary Contain- This partial stroke ment Isolation exercising provides an for Main Steam acceptable meaqs of verifyirg valve perfonnance during plant operation without affectinj safety margins. This request also contributes to the reduction of the relief valves challenge rate as recommended in NUREG-0626.

GL 13

O O O Commonwealth Edison LaSalle County Nuclear Station Unit 1 PUMP & VALVE TESTlNG Page 1 of 2 RELIEF REQUESTS ASME 33 PUMP OR QO SECTION XI FUNCTION TEST REQUIREMENT DASIS FOR ELIEF ALTERNATIVE. TEST VALVE NO.

02 03 04 05 06 00 01 RV-23 IB21-F013A 1/C Safety Relief Verify Valve Set It is impractical for The safety relief Valves For The Point LaSalle County Station valves will be remove <l 1821-F0138 1/C Primary Coolant tn meet the require- and replaced with Pressure Boundary ments of IWV-3510, in valves, that have had IB21-F013C 1/C that as-found set points their set point for these safety relief verified. The nunber IB21-F0130 1/C valves cannot be of valves removed and determined. The replaced during IB21-F013E 1/C station has no on-site refueling outages wil facility for testing be determined by the IB21-F013F 1/C safety valve set points, schedule in IWV-3510.

Our plans are to

1821-F013G 1/C remove them from the system, and ship them 1021-F013H 1/C off site.

They will be rebuilt 1821-F013J 1/C off site and then the set point will be tested IB21-F013K 1/C before lley are sent back on site. There fore, 1021-F013L 1/C IwV-3510(c) cannot be applied because "as found" 1821-F013M 1/C set points are not veri fied.

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@ Commonwealth PUMP LaSaHe County Nuclear StaHon Unit 1 Edison RELIEF REQUESTS

& VALVE TESTING Page 1 of 2 4 ASME 33 PUMP OR mO SECTION XI w0 "E

VALVE NO. M U

FUNCTION TEST HEOUlHEMENT DASis FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RV-25 All valves in NA NA IWV 3417(b) and Specific relief is request- Evaluate the condition the program for IWV 3523 ed from the requirements of each valve with which IWV of paragraphs IWV 3417(b) respect to its safety 3417(b) and/or and IWV.3523 of Section related function and IWV 3523 XI of the 1980 Edision take appropriate apply. of the ASME Boiler and corrective action Pressure Vessel Code in- as stated in the cluding the Addenda Technical Specifica-through Winter 1980. tion - Limiting these paragraphs state Condition for the corrective actions to operation.

be taken when valves fail to exhibit a required change of disk position.

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 I 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 limiting ccnditions for aperation which state the t al 13

(d h v v) l Page 2 of 2 l

@ Commonwealth Edison LaSaHe County Nuclear Stauon Umt 1 PUMP & V ALVE TESTING RELIEF REQUESTS ASME M

33 PUMP OR Eso 50 SECTION XI ALTERNATIVE TEST ui O VALVE NO. M O<

FUNCTION TEST REQUlHEMENT BASIS FOR REllEF EE O 04 05 06 00 01 02 03 RV-25 Cnntinued minimum conditions necessary for safe opera-tion of the plant. The failure of a particular valve may not necessarily require a plant shutdown or prevent a startup. In addition, valves not capable of performing 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, La Salle County Station will evaluate the condition of each valve With respect to its safety-related function and take the appropriate corrective action as stated in the Technical Specification - Limiting Condition for Operation.

t al 13

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@ Commonwealth Edison LaSalk County Nuclew Stat 6on Unit 1 PUMP & V ALVE TESTING RELIEF HEGUESTS Page 1 1 So ASME 33 PUMP OR QO SECTION XI FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE. TEST VALVE NO.

o 02 03 04 05 06 00 01 RV-26 1C11-F010 2/0 CRD Scram Discharge Full Strol<e And The system is designed Full stroke exercise Instrument Volume Stroke Time such that the test quarterly vent valve Quarterly circuit bleeds air from these ICll-F0ll 2/8 CRD Scram Discharge air operated Instrument Volume valves at a very Orain slow rate, much slower than durirv) nonnal ope.ation of the valve. Thus timing these valves during testing tus no relevance, and because of the slow bleed rate the test time repeatibility is reor.

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@ Commonwealth Edison LaSalk County Nucker Stetton Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of 2 E ASME 33 PUMP OR QO SECTION X4 VALVE NO. FUNCTION TEST REQUIREMENT BASIS FOR RELIEF ALTERNATIVE TEST 00 01 02 03 04 05 06 RV-27 IE12-F042A 1/El LPCI Injection Full Stroke Relief is requested Perform a full stroke Valves Exercise Quarterly from full stroke exercise during cold IE12-F0428 1/El exercising these valves shutdown.

during normal reactor lE12-F042C 1/El operation. The valves are interlocked closed with greater than 729 psid across them, which would require the (PCI purms to be tunning to cycle the valves. If the valva was opened (pump tunning) 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 l relief valve (500#)

and provide a flow path j for reactor pressure to the suppression pool.

Ihc relief line is only a 1 loch line which, cE-T 3

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@ Conunonwealth Edison LaSaHe County Nuclew Station Unit 1 PUMP & VALVE YESTlNG RELIEF REQUESTS Page 2 of 2 EO ASME 33 PUMP OR $O SECTION XI FUNCTION TEST PEOUIREMENT BASIS FOR HELIEF ALTERNATIVE. TEST g VALVE NO.

o 01 02 03 04 05 06 00 RV-27 Continued depending on the amount of cleck valve leakage, has tie potential to severely overpressurize the low pressure piping.

Exercising these valves provides single valve protection to the low pressure piping for the duration of tte test. Such exercising puts the plant in a less safe condition.

GE13

O O O 1 3 M

@ CommonwealthEdison t.aSalle County Nuclear Station Unit 1 PUMP & VALVE TEETl>sG RELIEF REQUESTS Page IIi ASME 33 PUMP OR $0 SECTION XI FUNCTION TEST REQUIREMFNT BASIS FOR REllEF ALTERNATIVE TEST VALVE NO.

01 02 03 04 05 06 00 _

RV-28 IB21-F037Al 3/C Vacuum Breakers Exercise Quarterb/ These check valves Verify that these For The Main j have no extemal means check valves freely IB21-F037A2 3/C Steam Relief of actuatim for swing to their full valve Discharge exercising. The opm positim at IB21-F037B1 3/C Lines. mly practical cold shutdow1.

mei. hod for exercising g

IB21-F03782 3/C these valves opm is by manually pushing 1821-F037Cl 3/C the disc from its seat using a small diameter IB21-F037C2 3/C rod. Siace this

requires access to the 1021-F03701 3/C valves which are locat:J within primary 1821-F037D2 3/C cmtainment, the test must be deferred IB21-F037El 3/C to cold shutdowis whm the primary IB21-F037E2 3/C coltahimait is de-Inerteri.

IB21-F037F1 3/C IB21-F037F2 3/C IB21-F031G1 3/C IU21-F037G2 3/C i

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@ Commonwealth Edison t.sSalle County Nuclost Station Unit 1 PUMP & V AL*/E YESTING RELIEF REQUESTS

$.2 3 PUMP OR E$

QO ASME SECTION XI TEST REQUIREMENT BASIS FOR REllEF ALTERNATIVE JEST VALVE NO. FUNCTION o 05 06 02 03 04 00 01 __

NC/d Full Stroke And There are 185 of Individual scram RV-30 IC11-D001-126 insertion tests will Stroke Time each af tha vavics Quarterly Check Tt.e listed, J.e., one be performed per the IC11-D001-127 tC/B Technical Fail-Safe Operation for each of the of 1011-0001-126 185 control red Specification 1C11-D001-114 NC/: frequency.

and ICll-D00i-127 drives. The Upon toss of proper operation of Actuator POW r each of these valves Quarterly is detrcastrated during scra.7 testing. During scrara testina each drive's iterari insertion time is neasured. The Technical Specifications limit individual scram insertion Lines to i.pecific v lves.

This insuras that the above ocotitwed valves are funct ionirg properly.

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O O O of

@ Commonwealth Edison tasatie county Nuclear Station Unit 1 PUMP 1 V ALVE TESTlMG Page 1 1 RELIEF REQUESTS ASME SEC TION XI 33 PUMP OR $O FUNCTION TEST HEQUIREMENT DASIS FOWSEllEF ALTERNATIVE TEST gO VALVE NO.

03 08- e5 06 00 01 02 RV-31 lE51F008 1/A RCIC Steam Supply full St mku And These valves are Perform a full stroke Supply Outboard Stroke Tine riartrially open to supply exercise during cold Isolation (Nart erly steam tc the turbine shutdown.

drivien RCIC injection IE51F063 1/A FCIC Steam Supply pmp. Conservatively Inboard Isolation these valves are left in the open position to insure that driving steam can be stoplied to these turbines at ali times Odrino operation.

These valves also serve as a primay containment isolation function.

LaSalls County Station feels that to close tiiese valves during operation would place the operation or the system in an untenable condition.

Further, if either were to fail l close:1, it would render the 14'IL Sytem inoperable.

GL f 3

O O O o Commonwealth Edison C7 LaSane County Nuclear C;4t6on Unit 1 PUMP & VALVE TESTING RELIEF REQUESTS Page 1 of 1 y, So ASME 33 PUMP OR yO SECTION Xi ALTERNATIVE TEST VALVE NO. FUNCTION TEST REQUlHEMENT BA313 FOR RELIEF o

00 01 02 03 04 , 05 06 RV-32 1821-F032A 1/AC Feedwater Outboard Exercise Quarterly IA test operator is incor- An attempt will be Testable Check pcrated into the design of made to partially Valve these valves which is stroke these valves capable of closing the quarterly. A full

.lB21-F032B 1/AC valve through an angle stroke exercise will of 15*, and the valve is be performed each equipped with two posi- refueling cutage.

tian indication lights for reporting disk positions of approximately 85% and 100% of fuli open. These valves can be opened by feedwater ' low only so a partial strcke exercise

~

is possible only when ithe reactor is at high power and the feedwater flow has corrpletely opened ne disk. A full stroke r:xercist of 'bese valves may be performed when

,feenwatre flow increases from a nu-flow condition to a maximum flow condi-tiens following each

,rebteling outage.

tal 13

(' ( >

Commonwealth Edison

@ tasain county NuclearPUMP Stat 6on unit i

& VALVE TESTING Page 1 of 1

. , RELIEF REQUESTS E

33 PUMP OH ASME

%" VALVE NO.

[QO FUNCTION SECilON XI TEST REQU!3FMENT HASIS FOR HELIEF

$ ALTERNATIVE TES T 00 01 02 03 08 05 06 RV-33 IB21-F013C 1/BC ADS Relief Valve Exercise Quarterly Vendor specifications for Perform an 'in place' 1821-F01:.0 1/BC

" " these ADS safety relief exercise at each valves require steam refueling outage, IB21-F013E 1/BC

" " pressure behind the disk before cycling.

1821-F013R 1/BC

" " Thus, the plant must be in an operating or IB21-F013S 1/BC

" " startup condition with the required steam IB21-F0130 " " pressure in the main 1/BC steam lines. Since the 1821-F013V 1/BC

" " valves are located inside the drywell, it is preferable that

! they be exercised either preceeding or following each refueling outage when the contain-ment atmosphere is de-inerted.

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Commonwealth Edison

@ LaSaHe County Nuclear PUMP &Station VALVE TESTING Umt 1 Page 1 of 1 RELIEF REQUESTS II) ASME

, 33 PUMP OR QC SECTION XI VALVE NO. FUNCTION TEST BEOU!!iEMENT CASIS FOR REllEF ALTERNATIVE TEST 00 o1 02 03 04 05 06 RV-34 All Nuclear 2/AC Excess Flow Check Exercise Quarterly. These excess flow check Boiler and Valves Full Stroke Exercise Leak Test During valves are designed to and Leak Test During Reactor Recir- Reactor Refueling automatically close culation Excess Reactor Refueling Flow Check in the event of a down-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 recirculd-tion flow instrumentation l and nuetron monitoring t

l instrumentation be tempor-arily taken out of service ,

the optimum time for the functionability testing of these valves is during the routine vesscl pressura I test perforined during each refueling outage.

tel 13

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@ Commonwealth PUMP LaSaHe County Nuclear Stahon Unit t Edison

& VALVE TESTING RELIEF REQUESTS Page 1 of 1 N PUMPOH EO ASME SECTION XI 33 QO FUNCTION TEST P.EQUlHEMENT DASIS FOR REllEr A1.TERNATIVE TEST VALVE NO.

00 ol 02 03 04 05 06 RV-35 lE22-F005 1/C HPCS Injection Exercise Quarterly These ally closed Perform a full stroke Inboard Testable testabic Geck valves exercise during each Check Valve serve as the first isola- cold shutdown.

tion valves in the event 1E51-F066 1/C RCIC Injection of a system line break.

Inboard Testable Testing could he performed Check Valve 'during power operation, hcm ver, a real possibility etia a that these valves, cr their oypass test valve:, w.y not properly rescat, rendering them incapabic of cerfonning their isolation function.

Since the drywell is inaccesMble during power operatie, the affected l penetration would .ieed to be isolated, cousing the lsystemtobeunavailable

, for its mergency function .

l1he risk invr,1ved with the cycliig of these e

valves during power oper-f ation ir, much greater lthan the a nurance of l cperability gaine:i by l .

quarterly testing. The valves will be exercised at cold shutdown when thei -

isolation function is act requTreo.

i. ia

O O O

@ Commonwealth PUMP LaSalle County Nuclear Station unit 1 Edison& VALVE TESTING RELIEF REQUESTS Page 1 of 1 b$ So ASME

'3 3 PUMP OH $O SECTION XI VALVE NO. FUNCTION TEST REQUlHEUSNT BA5!S Fort RELIEF ALTERNATIVE TES T 00 01 02 03 04 03 06 RV-36 lE51-F030 2/C RCIC Suppression Exercise Guarterly The check valve is partial Perfonn a full stroke Pool Suction Check stroke exercised each exercise during the Valve quarter by the perfcr- RCIC alternate flow mar.ce 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-i lainence 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 polentially contaminate the cycled condensate system. Each refueling outsge a full flow test of the alternate flow rath is

[canductedatwhich time this check valve is full-stroke exer-cised.

I t,t I3

O O O Commonwealth Edison 0;'d- ~

LaSalle County Nuclear Station Unit 1 PUMP & VALVE TESTING Page 1 of 1 RELIEF REQUESTS e >

$$ So ASME 33 VALVE NO.

PUMP OR $0 FUNCTION SECTION XI TEST REQUIREMENT BASIS FOP. RELIEF ALTERNATIVE TES T 00 01 02 03 04 05 06 MV-37 IFC-086 2/A Rx Well Bulkhead Full Stroke and These valves cre passive Leak test during Drain Outboard Stroka Time Quar- and locked closed. They refueling outages.

terly, Leak Test dc perfor;ii a containment 1FC-113 2/A Cond. to Refuel During Reactor isolation function and Bellows Inboard Refueling will be leak tested, i:owever, these valves are 1FC-114 2/A Cond. to Refuel not required to change Bellows Outboard position during power operat. ion or during an 1FC-ll5 2/A Rx Head Bulkhead emergency situation and Drain Inboard therefore, their ability to stroke will not be 1MC027 2/A tested.

1MC033 2/A ISA042 2/A ISA046 2/A bl I3

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ML20071C445

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