ML022760540

ASME Inservice Testing Program, Revision 26, Section 4.1 - Summary of Change

ML022760540
Person / Time
Site:	Oconee
Issue date:	07/31/2002
From:	Duke Energy Corp, Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML022760540 (200)

Text

Valve FlowDlingram ASME V'alve Active Vahlit Actuator JFD Test TestType TestDirectlon Test Frequency Relef Clas Catg.

Type Type Type Descriptlm Frequency Description Reqest LPSW Low Pressure Service Water OLPSO001 OFT.124A-01.O) D2 C

B No Gate Luniforque None PI Verify the Valve Remote Closed to Open 2Y Tested once ON-ORV-I5 Position Indication every two years OLPS0002 OFD-124A-O-1.01J2 C

B No Gate Lunitorque None Pl Verify the Valve Remote Closed to Open 2Y Tested once ON-GRV-I 5 Position Indication every two years OLPS0003 OFD-124A-01-O1 G2 C

B No Gate Lnnttorque None PI Verify the Valve Remote Closed to Open 2Y Tested once ON-GRV-I5 Position Indication every two years ILPS0004 OFD-124B-1..

K6 C

B Yes Gate Lmintorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0004 OFD-124B-2.1 K6 C

B Yes Ball Lunitorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0004 OFD-124B-3.1 K6 I C

B Yes Ball Lnniforque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station. -IST Submittal/for I 'alves Interval4. Revision 26 Section 4.1 LPSW-Low Pressure Service Water Page 1 of 14 (07/01/02)

Valve FlowDiagram ASWE

\\'aht Actlie VahW Actuator JFD Test TestType TestDIrectim Test Frequency Rellef Clasi Catg T)pc T)pe T~pe Descrlptlon Frequency Descrlptlon Reqest ILPS0005 OFD-124B-)..

116 C

B Yes Gate Limntorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0005 OFD-124B-2 1 116 C

B Yes Ball Lbmtorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0005 OFD-124B-3 I H6 C

B Yes Ball Ltnitorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1LPS0006 OFD-124B-I 4 L2 B

B Yes Gale Liutorque ON-LPSW-OI ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0006 OFD-124B-2 4 L2 B

B Yes Ball Linutorque ON-LPSW-O1 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPSO006 OFD-124B-3.4 L2 B

B Yes Ball Lirntorque ON-LPSW-0I ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station - IST Submittal for Valves Interval 4. Revision 26 LPSW-Low Pressure Service Water Section 4.1 Page 2 of 14 (07101102)

Valve FlowDiagram ASME Valve Active Valh Actuator JFD Test TestType TestDirection Test Frequency Relief Cl11 Catg.

T~pc T~pc Type Description Frequency Description Reqest ILPS0015 OFD-124B-J 4 G14 B

B Yes Butterflv Ltmttorque ON-LPSW-O1 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0015 OtFD-124B-24 G14 B

B Yes Ball Litnitorque ON-LPSW-O1 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0015 OFD.124B-3.4 G14 B

B Yes Ball Limitorque ON-LPSW-OJ ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years ILPSO016 OFD-124B-O)-02 K3 B

B No Gate Luntorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0016 OFD-124B-02-02 K3 B

B No Ball Linutorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0016 OFD-124B-03-02 KC3 B

B No Gate Llnutorque None PI Verify the Valve Remote Both (Stroke Test) ! 2Y Tested once None Position Indication every two years Ocone Nuclear Station -IST Submittal for 'alves Interval 4. Revision 26 (07/01/02)

LPSW-Low Pressure Service Water Section 4.1 Page 3 of.14

Valve FlowDlvgrmin ASME Vale Active Valhv Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

Type T)pe Type Description Frequency Descrlptim Reqest I LPSOOIs OFD-124B-J 2 D3 B

B Yes Butterfly Ltinttorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0018 OFD-124B-2.2 D3 B

B Yes Butterfly L mutorque ON-LPSff,-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0018 OFD-124B-3 2 C3 B

B Yes Butterfly Lwnutorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown Pl Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years ILPS0019 OFD-124B-0O-02 K7 B

B No Ball Lmnutorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0019 OFD.-24B-O2-02 K7$

B B

No Ball Ltmitorque None P1 Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0019 OFD-124B-03-02 K7 B

B No Ball Linmtorque None P1 Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Ocone Nuclear Station-IST Submtttal for Valves Inte"81 4. Revision 26 (07/01/02)

Section 4.1 Page 4 of/14 LPSIV-Low Pressure Service Water

Valve FlowDlagrumi ASIE

\\'aiw Acthe Valve Actuator JFD Test TestType TestDIrectlon Test Frequency Rdlef Clas Catg.

Type Type Type Description Frequency Description Reqest ILPSO021 OFD-124B-J.2 D8 B

B Yes Butterfly Lmnitorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0021 OFD-124B-2 2 D8 B

B Yes Butterfly Lnnitorque ON-LPSW-5O PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0021 OFD-124B-3.2 C8 B

B Yes Butterfly Lnitorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years lLPS0022 OFD-124B-O1.02 K12 B

B No Ball Limttorque None PI Veritfy the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0022 OFD-124B-02-02 KI B

B No Ball Ltmttorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0022 OFD-124B-03-02 K12 B

B No Ball Ltnmtorque None P1 Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Ocon¢ Nuclear Station - 1ST Submittal for Valves Interval 4. Revirion 26 (07/01/02)

Section 4.1 Page 5 of/14 LPSJV-Low Pressure Service Water

Valve FlowDlirnm ASME

'ahWt Acthe Vall Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Class Catg T)pe Type T)pe Description Frequency Description Reqest ILPS0024 OP"D-)24B-).2 DJ2 B

B Yes Butterfly Limitorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPSO024 OFD.I2JB.2.2 D12 B

B Yes Butterfly, Lhnttorque ON.LPSr V-O5 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0024 OFD-124B-3.2 C12 B

B Yes Butterfly Linitorque ON-LPSW-05 PS Partial-Stroke Exercise Closed to Open M

Tested once None monthly ST Measure Full-Stroke Closed to Open CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years OLPS0025 OFD.l124A-1.I D7 C

C Yes Check Sey/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly OLPS0028 OFD-124A-I.l J7 C

C Yes Check Sed/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None S*

quarterly OLPS0031 OFD-124A-I 1 G7 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly Oconee Nuclear Station - ISTSubmnttal for I alves Interval 4. Revision 26 (07/01102)

LPSW-Low Pressure Service Water Section 4.1 Page 6 of 14

Valve FlowDiigrarn ASME

\\'nai Actiie Vahl Actuator JFD Test TestType TestDirection Test Frequency Relief Chia Catg Type Type Type Description Frequency Description Reqest 3LPS0120 OFD-124A-03-O 3J2 C

B

\\No Gate Lwintorque None PI Verify the Valve Remote Closed to Open 2Y Tested once ON.GRV-15 Position Indication every two years 3LPS0121 OFD-124A-3.1 37 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 3LPS0123 OFD-124A-03-O1 G2 C

B No Gate Linutorque None PI Verify the Valve Remote Closed to Open 2Y Tested once ON-GRV-15 Position Indication every two years 3LPS0124 OFD-124A-3.1 G7 C

C Yes Check SetfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly ILPSO139 OFD-124A-1 I KIO C

B Yes Butterfly Ltnitorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2fPS0139 OFD-124A-. I C8 C

B Yes Butterfly, Limtorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once jqone Position Indication every two years 3LPS0139 OFD-124A-3.1 EIO C

B Yes Butterfly Rotork ON-LPSW-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station - IST Subnuttal for Valves Interval 4. Revision 26 (07/01/02)

LPSW-Low Pressure Service Water Section 4.1 Page 7 of 14

Valve FlowDlagram ASME Valvt Active Valhv Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg Trpe Type Tope Description Frequency Description Reqest ILPS0148 OFD-124B-].1 L4 C

C Yes Check SelfActuated ON-LPSIr-03 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Open to Closed SD Disassem one None vlv per grp ea.

RFO 2LPS0148 OFD.124B.2 1 L7 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 3LPS0148 OFD-124B-3 1 L4 C

C Yes Check SelfActuated ON-LPSW-03 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Open to Closed SD Disassem one None vlv per grp ca.

RFO 1LPS0151 OFD-124B-1 I F3 C

C Yes Check SelfActuated ON-LPSW-03 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Open to Closed SD Disassem one None vlv per grp ea.

RFO ILPS0251 OFD-)I24B-I.I J8 C

B Yes Butterfly Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 2LPS0251 OFD-124B-2 1 J8 C

B Yes BlutterflT Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 3LPS0251 OFD-124B-31 K7 C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly Oconee Nuclear Station - 1ST Submlftal for Valves Interal 4. Revision 26 LPSW-Low Pressure Service Water Section 4.1 Page 8 of.14 (07101102)

Valve FlowDlagram ASME Vaaht Acthe Valht Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg T)pe Type Type Description Frequency Description Reqest 1 LPS02S2 OF'-).

24B-1.J1 18 C

B Yes Butterfly Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 2LPS0252 OFD-)?4B-2.)

18 C

B Yes Butterfly, Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 3LP50252 OFD-124B-3 I 117 C

B Yes Boll Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 1LPS0308 OFD-124B-1.4 17 B

C No Relief SelfActuoted None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2LPS0308 OFD-124B-2 4 17 B

C No Relhef Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3LPS0308 OFD-J24B-3 4 17 B

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0309 OFD-124B-2 4 18 B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0310 01"D-124.-2 4 16 B

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station -IST Submittal for I 'alves Interval 4. Revision 26 (07/01/02)

Section 4.1 Page 9 of 14 LPSfV-Low Pressure Service Water

Valve FlowDiagram ASME Vahir Acthie Valh Actuator JFD Test TestType TestDIrection Test Frequency Relief Class Catg T~pe T)pe Type Description Frequency Description Reqest ILPS0311 OED-124B-1 4 1)0 B

C No Relief Sell/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0311 OE-D-)24B-2.4 110 B

C No Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-1 2 Test valve per OM-l schedule 3LPS0311 OFD-124B-3 4 110 B

C No Relief Sel/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0312 01FD.124B-2 4 112 B

C No Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0313 OED-1 24B-2 4 19 B

C No Relief Self/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 1LPS0314 OF"D-124B-1.4 D7 B

C No Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2LPS0314 OFD.124B.2.4 D7ý B

C No Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3LPS0314 OFD.124B-3 4 D7 B

C No Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule Oconme Nuclear Station.ISTSubmittal for Valves Interaid4. Revisin 26 LPSW-Low Pressure Service Water Section 4.1 Page 10 of 14 (07101102)

Valve Flom Diagram ASME Valh Actlhe Valve Actuator JFD Test TestType TestDirection Test Frequency Relief Class Cotg.

Type Type Type Descrlpion Frequency Description Reqest 2LPS0315 OFD-124B-2.4 D8 B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule 2LPS0316 OFD-124B-2 4 D6 B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 1LPS0317 OFD-124B-1.4 DIO B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0317 OFD-124B-2 4 DIO B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3LPS0317 OFD-124B-3 4 DIO B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2LPS0318 OFD-124.2 4 D12 B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2LPS0319 OFD-124B-2 4 D9ý B

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open I RV Test relief ON-GRV12 Test valve per OM-1 schedule Oconee Nuclear Station-IST Submittal for l'alves Interval 4. Revision 26 (07/01/02)

LPSWV-Low Pressure Service Water Section 4.1 Page II of'14

Valve Fla% Diagram ASME

'Valle Actle Vaahe Actuator JFD Test TestType TestDirection Test Frequency Relief Clas Catg.

Type Type Type Description Frequency Description Reqeit 2LPS0503 OFD-124B-2I1 G3 C

C Yes Check SelfActuated ON-LPSW-03 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Open to Closed SD Dtsassem one None vlv per grp ea RFO 3LPS0503 OFD-124B-3 1 F3 C

C Yes Check SelfActuated ON-LPSW-03 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Open to Closed SD Dtsassem one None vlv per grp ca.

RFO lLPS0516 OFD-124A-1.3 K3 C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 2LPS0516 OFD-124A-.3 K3 C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 3LPS0516 OFD-124A-3 3 KS C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 1LPS0525 OFD-124A-).3 i5 C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 2LPS0525 OFD-124A-2.3 Ji C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly 3LPS0525 OFD-124A-3 3 J5 C

B Yes Ball Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly Oconee Nuclear Station-ISTSubinittal for Valves Intervna4. Revision 26 Section 4.1 LPSW-Low Pressure Service Water Page 12 of 14 (07/01/02)

Valve FlowDlagram ASME Vahlw Active Vali Actuator JFD Test TestT.pe TestDirectlon Test Frequency Relief ClaIs Catg Type Type Type Description Frequency Description Reqest 1LPS056S OFD-124B.1,2

.J8 B

B Yes Gate Rotork None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0565 0ED-I124B-2 2 J8 B

B Yes Gate Rotork None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0565 OFD-124B-3.2 18 B

B Yes Gate Rotork None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1LPS0566 OFD-)24B-.,2 18 B

B No Gate Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2LPS0566 OFD-124B. 2.2 18 B

B No Gate Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3LPS0566 OFD-124B-3 2 18,

B B

No Gate Rotork None SPI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years OconeeNuclear Station -IST Submittal for lalves Interval 4. Revision 26 (07/01/02)

LPSWV-Low Pressure Service Water Section 4.1 Page 13 of.14

Valve FlowDlIwrom ASME Vahlt Actlhe

'alw Actuator JFD Test TestType TestDlrectlon Test Frequency Rellef Class Cvtg.

Type T)pe Type Description Frequency Description Reqest ILPS0931 O-D-124B-1.

)GIO C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly 2LPS0931 OFD-124B-2 111)0 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly 3LPS0931 OFD-124B-3 I KI I C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly Oconee Nuclear Station - ISTSubinittal for Valves Interval 4, Reision 26 (07/01/02)

LPSW-Low Pressure Service Water Section 4.1 Page 14 of 14

Valve FIo% Diaram ASME V'ahe Acthe Vals Actuator JFD Test TestT~pe TestDirectlon Test Frequency Relief CIMI Catg T)pe T)pe T~pe Description Frequency Description Reqest LRT " Leak Rate Test ILRTO017 OFD-I37E.1.1 KIO B

A No Dzaphravm Air None AU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRTO017 O17V-137E-1.J H)0 B

A No Dsaphra~,m Air None BU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0017 OFD-137E-).1 E9 B

A No Diaphragnm Air None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 1LRTM024 OFD-137E-I.1 112 B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0024 OPD-137E-1. 1 G11 B

A No Diaphragmn Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0024 OFD-137E-1.1 CII B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station -. ST Submittal for Valves Interval 4. Revision 26 LRT-Leak Rate Test Section 4.1 Page 1 of 3 (07101102)

Valve FlowDlagram ASME Valve Active Vale Actuator JFD Test TestType TestDirection Test Frequency Reilef Clals Catg T)pe T)pe T~pe Description Frequency Description Reqest ILRT0025 OFD-137E-1.I 112 B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0025 OFD-137E-I.1 GII B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0025 OFD-/37E-1.I CI I B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0036 OFD-137E. II Fl 1 B

A No Globe Manual None LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0036 OFD-137E-).)

CII B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0037 OFD-137E-1.l F11 B

A No Globe Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0037 OFD-137E-).)

Cl),

B A

No Globe Manual None SIU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for I'alhes Interval 4, Revision 26 LRT-Leak Rate Test Section 4.1 Page 2 of 3 (o07101102)

Valve FlowDlagrim ASME

'alws Acthe Vah1¢ Actuator JFD Test TestType TestDirection Test Frequency Relief Class Cotg.

T)pC Typc T~pe Description Frequency Description Reqest ILRT0038 OFD-137E-l.1 J12 B

A No Globe Manual None BU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0038 OFD-137E.l.I 1t)1 B

A No Globe Manual Ntone 1U Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0038 OFD-137E-J.I DI I B

A No Globe Manual None 3lJ Leak-Rate Test Valve to Accident Direction RF Tested every None App 3 Requirement(s) refueling outage ILRT0039 OFD-137E-I.I

.J13 B

A No Globe Manual None BU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LRT0039 OFD-137E-I.I 1-12 B

A No Globe Manual None 2Hl Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LRT0039 OFD-137E-I 1 DII B

A No Globe Manual None BU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - ISTSubmtittal for Valves Inteval 4, Rerislon 26 LRT-Leak Rate Test Section 4.1 Page 3 of 3 1

(07101102)

Valve FIo% Dlagram ASME V'ahw Active Vahl Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

T)pe Type Type Description Frequency Description Reqest L.WD" Liquid Waste Disposal ILWDO00I OFD-107B-1.1 Cll B

A Yes Diaphragin Luntorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2LWD0001 OFD-107B-2.1 CICI B

A Yes Diaphragm Lbntorque None ST Measure Full-Stroke Openjo Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3LWD0001 OFD-107B-3.1 CII B

A Yes Dtaphragm Lwutorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station-ISTSubmittal for i'alves Interval 4. Reviion 26 L WD-Liauid Waste Disposal Section 4.1 Page 1 of 2 I

(07101102)

Valve FlowDlagram ASME

\\'ahr Acthie Vahlr Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Clas Catg.

T)pe Trpe Type Description Frequency Description Reqest ILWD0002 OFD-107B-).J C11 B

A Yes Dtaphrog.m Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2LWDO002 OFD-)OTB-2 I C12 B

A Yes Diaphra,~n Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3LWD0002 OFD-107B-3 I C12 B

A Yes Diaphrain Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Closed to Open 2Y Tested once None Position Indication every two years PI Venfy the Valve Remote

'Open to Closed 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station IST Submwttal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 Page 2 of 2 t

LPWD-Liauid Waste Disposal

Valve FlowDl[agrar ASME Valve Actlhe valh Actuator JFD Test TestType TestDirectlon Test Frequency Relief ClasS Catg Type T)pe Type Description Frequency Descrlption Reqest MS

- Main Steam I MSO001 OFD-122A-).1

.19 B

C Yes Relhe/-

el/ Actuataed None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2MS0001 OFD-)22A-2 1 J9 B

C Yes Relief Sel/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0001 OFD-1224.3.)

.19 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 1MSO002 OFD-122A-I.I

.14 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2MS0002 OFD-)22A-2)I J4 B

C Yes Relief Sel/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3MS0002 OFD-122A-3.1 J4 B

C Yes jelief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule Oconee Nuclear Station - IST Submittal for Valves Interval4. Revision 26 Section 4.1 MS-Main Steam Page 1 of 19 (07/01/02)

Valve FlowDagraxn ASME VahT Active Vahl Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

Type Type T)pe Description Frequency Description Reqest IMS0003 OED-122A-!.J J7 B

C Yes Relhef Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2MS0003 OFD-122A-2)

J 7 B

C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3M50003 OFD-122A.3 1 i7 B

C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule IMS0004 OFV-122A-1.)

i]s B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2M50004 OFD-122A.2) iSd B

C Yes Relief Self Actuataed None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0004 OFD-)22A -3.)

iS C

Yes Relhef SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station -IST Subinittal for Valves Interval4. Revision 26 MS-Main Steam Section 4.1 Page 2 of 19 J

(07101102)

Valve FlowDlagrarn MIME

'athr Actlhe Val Actuator JFD Test TestType TestDirection Test Frequency Relief Class Cstg.

Type Tcpe Type Description Frequency Descrlption Reqest I MSO005 OFD-122A-1 I J8 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON.GRV-12 Test valve per OM-1 schedule 2MS0005 OFD-122A-21 1A8 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS000S OFD-122A-3.1 A8 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule IMS0006 OFD-122A-1 I J5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2MS0006 OFD-122A.2 1

.5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-I schedule 3MS0006 OFD-122A.3)I JS B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-.12 Test valve per OM-1 schedule, OcontE*uclear Station -. ST Submittal for Valves IntJry 4. Revision 26 (07/01/02)

Section 4.1 MS-Main Steam Page 3 of/19 1

Valve FlowDiagram ASME Vahle Actie Voalie Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Cla3s Catg.

Type T)pe T~pe Description Frequency Description Reqest 1MS0007 OFD-122A-J I J7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule 2MS0007 OFD-122A-2.1 J7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0007 OFD-122A-3 I J7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule IMS0008 OFD.122A-I.I J6 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2MS0008 OFD-122A.2 1 J6 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0008 OF7D-122A-3.1 J6 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station-ISTSubmtttal for Ialves Interval 4. Revision 26 (07/01/02)

Section 4.1 Page 4 of 19 t

MS-Main Steam

Valve FlowDlagri ASMIE VWd Arctihe

'aWIT Actuator JFD Test TestType TestDirectmon Test Frequency Relief CI'I CHtg.

T)pe Tcpe Type Description Frequency Descrlption Reqest IMSO009 OFD-122A-lI D9 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2MS0009 OFD-122A-21 D9 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0009 OFD-122A.3 I D9 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule IMS0010 OFD-122A.I.l D4 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2MS0010 OFD-122A-2)I D4 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3MS0010 OFD-122A.3 I D4 B

C les Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule Oconee Nuclear Station. IST Submittal for I blves Interval 4. Revision 26 (07/01/02)

MS-Main Steam Section 4.1 Page 5 of 19

'1 I

Valve FlowDlagrmn ASMIE

\\'abw Acthe Vali%

Actuator JFD Test TestType TestDIrectlon Test Frequency Rdlef Class Catg.

Tnpe Type T~pc Description Frequency Description Reqest IMS0011 OFD-122A-I.1 D7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2MSOO1I1 OFD-122A-2 I D7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule 3MSOO1I OFD.122A-31 D7 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule lMS0012 OFD-122A-I 1 D5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRVo12 Test valve per OM-1 schedule 2MS0012 OFD-122A-2 I DS B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0012 OFD-122A-31 1D5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule Oconee Nuclear Station. IST Submittal for Valves Intuery4. Revirlon 26 MS-Main Steam Section 4.1 Page 6 of"19 (07101102)

Valve Flo% Diagram ASME VaIw Active Vans Actuator JFD Test TestType TestDirection Test Frequency Relief Clas Catg Tppe Tpe T)pe Description Frequency Description Reqest lMS0013 OFD-122A-). 1D8 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2MS0013 OFD-122A-2.1 D8 B

C Yes Relief Sey/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0013 OFD-122A-3 I D8 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule IMS0014 OFD-1224-11 D3 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule 2MS0014 0FD-1224-2I1 D5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 3MS0014 OFD-122A-3I DJ B

C Yes Relief Sel/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station - IST Subnmittal for I 'alves Interva 4. Revision 26 MS-Main Steam Section 4.1 Page 7 of 19 J

(o07101102)

Valve FlowDlagram A.SIE Vnhl Actlie Valle Actuator JFD Test TestType TestDirectlton Test Frequency Rdlef Clais Cntg.

Type T)pe Type Description Frequency Descrlptiou Reqest IMS001S OFD.122A-l I D7 B)

C Yes Relhef SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-l schedule 2MS0015 OFD-122A-2 1 D7 B

C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3MS001S OFD-122A.3 1 D7 B

C Yes Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule IMS0016 OFD-122A.).)

D6 B

C Yes Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule 2MS0016 OFD-122A-21!

D6 B

C Yes Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0016 OF"D-122A-3.l D6 B

C Yes Relief Set/A ctuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station. ISTSubmittal for Valves Interval 4. Revision 26 MS-Main Steam Section 4.1 Page 8 of.19 l

(07101102)

Valve FlowDlagran ASMIE

\\'a1 Active Valle Actuator JFD Test TestType TestDirection Test Frequency Rellef ClasI Catg.

T)pe T)pe T)pe Description Frequency Description Reqest IMS0017 OFD-122A-I 2 153 B

B Yes Gate Limrtorque ON-hS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0017 OFD-122A-2 2 15 B

B Yes Gate L untorque ON-MS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0017 OFD-122A-3 2 15 B

B Yes Gate Lnittorque ON-MS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years lMS0024 OFD-122A-J.2 H3 B

B Yes Gate Lunftorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0024 OFD-122A-2 2 113' B

B Yes Gate Lumitorque None ST Measure Full-Stroke Open to Closed Q

Tested once

,None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0024 OFD-122A-3 2 113 B

B Yes Gate Linutorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years OconeE Nuclear Station - IST Submittal for I'alves Interval 4. Revision 26 (07/01/02)

MS-Main Steam Section 4.1 Page 9 of 19

Valve FlowDIogram ASIE a'Ohr Acthe Vahr Actuator JFD Test TestType TestDirectlon Test Frequency Rellet Ca18 Catg Type Type Type Descriptisn Frequency Description Reqest IMS0026 OFD-122A -1.2 D3 B

B Yes Gate Linuaorque ON-MS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0026 OFD.122A4-22 DJ B

B Yes Gate Lumtorque ON-AIS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0026 OFD-122A-3 2 DJ5 B

B Yes Gate Liuntorque ON-MS-02 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1MS0033 OFD-122A-l.2 E3 B

B Yes Gate Lintorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0033 OFD-122A.2 2 E3 B

B Yes Gate Litrtorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0033 OFD-122A-3 2 E3 B

B Yes Gate Linntorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station -1ST Submittal for Valves Interval4. Revision 26 MS-Main Steam Section 4.1 Page lOof19 (07101102)

Valve FlowDlagram kSME \\dw Actiie

\\'aic Actuator JFD Test TestType TestDirectlon Test Frequency Relief ClaIl Cog.

T)pc T~pe Type Description Frequency Description Reqest IMS0035 OFD-122A-J.3 L2 B

B Yes Gate Linitorque ON-MS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0035 OFD-122A.2 3 L2 B

B Yes Gate Limutorque ON-MS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0035 OFD-122A-3 3 L2 B

B Yes Gate Limitorque ON-MS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1MS0036 OFD-122A-1 3 F2 B

B Yes Gate Ltnitorque ON-MS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0036 OFD-122A-2 3 F2' B

B Yes Gate Llmitorque ON-MS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0036 OFD-122A-3 3 F2 B

B Yes Gate Linatorque ON-AIS-03 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station - ISTSubmuttal for V'alves Interval 4. Revision 26 (07/01/02)

MS-Main Steam Section 4.1 Page 11 of 19

Valve FlowDlagran ASAIE VhWI Active V'alv Actuator JFD Test TestType TestDirection Test Frequency Relief ClaII Catg.

Type T~pe Type Description Frequency Description Reqest 1MS0076 OFD-122A.1 I CIO B

B Yes Gate Ltmttorque ON-MS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0076 OFD.122A.21 110 B

B Yes Gate Lbnitorque ON-MS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0076 OFD-122A-3 1 110 B

B Yes Gate Ltmitorque ON-AMS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1MS0079 OFRD-122A-I 1 110 B

B Yes Gate Lmittorque ON.-AS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0079 OFD-122A-2.1 CIOC B

B Yes Gate Limitorque ON-AIS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown '

PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0079 OFD-122A-3 I CIO B

B Yes Gate Linitorque ON-AfS-04 ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Starton -IST Submittal for Valves Intenval 4. Revision 26 MS-Main Steam Section 4.1 Page 12 of 19 (07101102)

Valve Flo% Diagram ASME

\\'alst Active Vahl Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

Type Typc Type Description Frequency Description Reqest IMS0082 OFD-1221-1.4 12 B

B Yes Gate Liinrtorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0082 OFD-122A-24 12 B

B Yes Gate Linitorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0082 OFD-122A-3 4 12 B

B Yes Gate Lititorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1 MS0084 OFD-122A-l 4 G2 B

B Yes Gate Lnittorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0084 OFD-122A-2 4 G2' B

B Yes Gate Ltintorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0084 OFD-122A.3 4 G2 B

B Yes Gate Lhnttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station - ISTSubmittal for Valves Interval4. Revision 26 (07/01/02)

Section 4.1 Page 13 of 19 MS-Main Steam

Valve FlowDlagrarn ASNIE Valw Actle

'Vale Actuator JFD Test TestType TestDirectlon Test Frequency Rdlef Clams Catg.

Type Type Type Description Frequency Descriptiou Reqest IMS0092 OFD-122?A-I.4 H6 C

C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2MS0092 OFD-122, -2 4 116 C

C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3MS0092 OFD-122A.3 4 116 C

C Yes Relier Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 1MS0093 OFD-122A-14 117 C

B Yes Ball Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly 2MS0093 OFVD.122A -2.4 117 C

B Yes Boll Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly 3MS0093 OFD.122A-3 4 117 C

B Yes Ball Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly Oconee Nuclear Station -IST Submittal for i'alves Interval4. Revilon 26 (07/01/02)

Section 4.1 Page 14 of.19 I

MS-Main Steamt

Valve FIo Diagram ASNIE Valv Active Valle Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg T)pe Type Type Description Frequency Description Reqest I MS0102 OFD-)22B-IlI J3 B

B Yes Stop Hydrauhic ON-MfS-OI PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0102 OFD-122B-2.1 J3 B

B Yes Stop ttydrauhic ON-AfS-0O PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (stroke Test) 2Y Tested once None Position Indication every two years 3MS0102 OFD-122B-3 I J3 B

B Yes Stop Hydrauhc ON-MS-C)

PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station -IST Submittal for I bives Interval 4. Revision 26 MS-Main Steam Section 4.1 Page 15 of 19

'1 (07101102)

Valve FlowDlagram ASMEE Vahr Acthe VaIT Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Cutg.

Type Type Type Description Frequency Description Reqest IMS0103 OFD-122B-).1I 4i B

B Yes Stop Hydraulhc ON-MS-O0 PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0103 OFD-122B-21 J4 B

B Yes Stop Hydraulic ON-MS-01 PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown Pl Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0103 OFD-122B-3 I J4 B

B Yes Stop Hydrauihc ON-MS-Of PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station - 1ST Submittal for I'alves Ir"fev14. Revision 26 (07/01/02)

Section 4.1 MS-Main Steam Page 16 of 19 l

Valve FlowDlagram ASME WaIT Active Vahe Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg Type Type T)pe Description Frequency Description Reqest IMS0104 OFD-122B-l.1 4

B B

Yes Stop Hydraulic ON,-MS-OI PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0104 OFD-122B-2.1 J4 B

B Yes Stop Hydrauhc ON-MS-Cl PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0104 OFD-122B-3 I J4 B

B Yes Stop Hydraulic ON-MS-OI PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station. IST Submittal for Valves Interyal 4. Retvison 26 (07/01/02)

Section 4.1 Page 17oof 19 1

MS-Main Steam

Valve FlowDlagram ASME Vahi Acthe Valis Actuator JFD Test TestType TestDirectlon Test Frequency Relef CIMI Catg.

T~pe Type Type Description Frequency Description Reqest 1MS0105 OFD-122B-I.1 315 B

B Yes Stop Hydraulic ON-MS-OI PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2MS0105 OFD-122B-2

.135 B

B Yes Stop Hydraulic ON-MS-01 PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3MS0105 OFD-122B-3.1 35 B

B Yes Stop Hydrauidc ON-MS-01 PS Partial-Stroke Exercise Open to Closed Q

Tested once None quarterly ST Measure Full-Stroke Open to Closed CS Tested every None Time of Valve cold shutdown PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 1MS0153 OFD-122A-.1 Jl10 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 2MS0153 OFD-122A-2.1 310 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None I

cold shutdown 3MS0153 OFD-122A-3.1 J10 B

B Yes Gate Manual ON-AMS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown OconmeNuclear Station - IST Submittal/for M'alves Int*rnJ4. Re-iion 26 (07101/02)

Section 4.1 Page 18 of/19 MS-Main Steam

Valve FlowDlagram ASME Valle Active Valit Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

T)pe T)pe Type Description Frequency Description Reqest IMSO155 OFD-1224.I.)

DIO B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 2MS0155 OFD-122A-2 1 DIO B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 3MS0155 OFD-122A-3.1 DIO B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown IMS0161 OFD-122A-)..

J9 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 2MS0161 OFD-122A-2 I J9 B

B Yes Gate Manual ON-AIS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 3MS0161 OFD-122A.3.1 J9 B

B Yes Gate Manual ON-AIS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 1MS0163 OFD-122A.l.)

E9 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown 2MS0163 OFD-122A-21 E9 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None

£

'cold shutdown 3MS0163 OFD-1224-3.1 E9 B

B Yes Gate Manual ON-MS-07 FS Full-Stroke Exercise Both (Stroke Test)

CS Tested every None cold shutdown Ocone*Nuclear Station. IST Submittal for l'alves Interval 4. Revision 26 (07/01/02)

MS-Main Steam Section 4.1 Page 19 of 19

Valve Flo% Diagram ASMNIE V%'a Acthe

%ahW%

Actuator JFD Test TestType TestDirection Test Frequency Relief Clai Cotg.

T.pe Type Trpe Description Frequency Description Reqest N

" Nitrogen IN0106 OFD.127B.I 2 E4 B

A No Globe Manual None LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 1N0107 OFD-127B-. 2 1--4 B

A No Globe Manual None lU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 N-Nitrogen Page 1 of 4 I

Valve FIo% Diagran ASIE

\\nih Actl'ie Vahl Actuator JFD Test TestType TestDIrectlon Test Frequency Relief Class Cotg Type Type Type Description Frequency Description Reqest 1N0129 OFD-127B-).2 G7 B

A/C Yes Check Sel/Actuated ON-N-OJ FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2N0129 OFD-I27B-2 2 G7 B

A/C Yes Check SelfActuated ON-N-OI FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open'to Closed RF Tested every None refueling outage UI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3N0129 OFD-127B-3 2 G7 B

A/C Yes Check Sel/Actuated ON-N-01 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 N-Nitrogen Page 2 of 4

Valve Flo-A Diagrati ASME Vaiw Actlie Vahe Actuator JFD Test TestType TestDirection Test Frequency Reilef CIaMI Catg.

T)pc T)pe Type Description Frequency Description Reqest IN0131 OFD-127B-I 2 J7 B

A/C Yes Check SelfActuated ON-N-0J FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2N0131 OFD-127B-22 J7 B

A/C Yes Check SelfActuated ON-0-OI FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Opento Closed RF Tested every None refueling outage UI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3N0131 OFD-127B-3 2 J7 B

A/C Yes Check Sey/Actuated ON-N-OI FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for I'ahves.

Intervl 4. Revision 26 (07/01/02)

N-Nitrogen Section 4.1 Page 3 of 4 I

Valve FlowDiagram ASIE aht rActhie Vaahe Actuator JFD Test TestType TestDIrectlon Test Frequency Rellef Class Catg Type Type Type Description Frequency Description Reqest IN0246 OFD-127B-1.2 EIO B

A/C Yes Check SelfActuated ON-N-02 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2N0246 OFD-127B-2.2 EJO B

A/C Yes Check SelfActuated ON-N.02 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open'to Closed RF Tested every None refueling outage LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3N0246 OFD-127B-3.2 EIO B

A/C Yes Check SelfActuated ON-N-02 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2N0263 OFD-127B-2.2 E7$

B A

No Globe Manual None LJ Leak-Rate Test Valve to Accident Direction, RF Tested every None App J Requirement(s) refueling outage 3N0263 OFD-127B-3.2 E7 B

A No Globe Manual None LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - 1ST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 N-Nitrozen Page 4of4

Valve FlowDilgrmn ASME Vaiit rActive

\\ali Actuator JFD Test TestType TestDirection Test Frequency Relief Cla01 Cotg.

Type Type Type Description Frequency Description Reqest OG " Keowee Governor Oil lOG0013 hCFD-)05A-I.1 1111 C

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 2OG0013 KFD-JOSA-2! 1111l C

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 10G0016 KFD-IOSA-1. 1 118 C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2OG0016 KFD-105-2.l1 1t8 C

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule lOG0019 KFD-IO0,I-1.)

tt5 C

C No Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 20G0019 KFD-05A.2.1 113 C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule Oconme Nuclear Station. ISTSubmittal for V'alves Interval 4. Revision 26 OG-Keowee Governor Oil Section 4.1 Page I of)I (07101102)

Valve FlowDlagram ASME VahIT Active VaI Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Clas Cut.

T)pe T)pc T~pe Description Frequency Description Reqest PR

" Purge IPROO01 OFD-))6A.JIJ F3 B

A No Butterfly Limttorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2PROO01 OFD.116A.2 1 G3 B

A No Butterfly Lumutorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PROO01 OFD.1)64-3 I G3 B

A No Butterfly Lwutorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - 1ST Submittal for I'alves Interva 4. Revision 26 (07/01/02)

Section 4.1 PR-Purze Page 1 of 17 1

Valve FlowDlagram ASNIE Vuh Active Valve Actuator JFD Test TestType TestDirectlon Test Frequency Relief Cla1s Catg Typc T~pe Type Description Frequency Description Reqest 1PROO02 OFD-)164.1.1 FS B

A No Butterfly Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0002 OFD-116A-2.1 G5 B

A No Butterfly Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR0002 OFD-1164-31 G3 B

A No Butterfly Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station -IST Submittal/for Molves Interval 4, Revision 26 Section 4.1 PR-Puree Page 2 of 17 (07/01/02)

I

Valve FlowDlagran AWME Vahl Active U'ase Actuator JFD Test TestType TestDirectlon Test Frequency Relief CaIs Catg.

Type Type T)pe Description Frequency Description Reqest IPROO05 OFD-1)6A-I.

1D5 B

A No Butter/?'

Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PROO05 OFD-116,4.2 1 D5 B

A No

Butterfl, Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction

'RF Tested every None App J Requirement(s) refueling outage 3PR0005 OFD.116A-3. !

D5 B

A No Butterfly Air None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Ui Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage

£ Oconee Nuclear Station. ISTSubmittal for I'alves Int,'er14. Revision 26 (07/01/02)

Section 4.1 PR-Purge Page 3 of 17

Valve FlowDlhram ASME Vaahe Active

\\'aiie Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

T~pe Type Tnpe Description Frequency Description Reqest IPR0006 OFD.-116,-J.1.

D3 B

A No ButterPfl Linaitorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2PR0006 OFD-1)6A -2.1 Di B

A No Butterfly*

Lnnttorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years L3 Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PR0006 OFD-J)6A-3 I Di B

A No Butterfly Lunrtorque None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for Valves Intjeva 4. Reviion 26 Section 4.1 PR-Purge Page 4 of'17 (07/01/02)

Valve FlowDiagram ASME Valv Active Valle Actuator JFD Test TestType TestDlrectlon Test Frequency Relief Class Catg T)pe Type Type Description Frequency Descriptlm Reqest IPROO07 OFD-116C-).1 G3 B

A Yes Dtaphrogim Limttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Reverse Direction RF Tested every None App,J Requirement(s) refueling outage 2PR0007 OFD-116C-2.1 G3 B

A Yes Diaphraogn Llnttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LJ Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PR0007 OFD-116C.3 I G3 B

A Yes Dtaphragm L

tintorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station -1IST Submittal for I bh'es Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purze Page 5 of/17 t

Valve FlowDilagram ASIE Vaiir Acthe r ah Actuator JFD Test TestType TestDirectlon Test Frequency Relief CaIs Catg T)pe T)pe Type Description Frequency Description Reqest 1PR0008 OFD-U 6C-J.I K*3 B

A Yes Dtaphragns Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0008 OFD-11I6C-2.J K:3 B

A Yes Dmaphragm~

Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR0008 OFD-116C-3.1 K3 B

A Yes Djaphra.n Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - ISTSubnuittal for Valves interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purze Page 6 of 17 t

I

Valve FlowDlagram AMIE Vahr Acthe Valve Actuator JFD Test TestType TestDlrectlon Test Frequency Relief Class Catg.

T)pe Type Type Description Frequency Descriptlon Reqest IPROO09 OFD-J)6C-).,

D2 B

A Yes Diaphra1nm Linutorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2PR0009 OFD-116C-2.1 D2 B

A Yes Diaphragm Limitorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PR0009 OFD-)16C-3 1 D2 B

A Yes Diaphragm Limntorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Statton-IST Submittal for I'ahes Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purge Page 7of17

Valve FlowDlagramr ASME V'alw Active Valle Actuator JFD Test TestType TestDirection Test Frequency Rellef Class C4tg.

Type T)pe Type Description Frequency Description Reqest 1PROO10 OFD.IJ6C-I I C4 B

A Yes Diaphrav,,

Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PROO10 OFD-116C-2.1 C4 B

A Yes Diaphragin Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PROO10 OFD-116C-3 I C4 B

A Yes Diaphragm Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for oalves Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purze Page 8 of 17 I

Valve Flo% Dlagram ASME

\\'Whe Acthe Vahw Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg T)pe T)pe Type Description Frequency Description Reqest IPROO15 OFD-I 6B-I.

I111 C

B Yes Butterflv Ltnttorque None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2PR0015 OFD-)16B-2) I III C

B Yes Butterfly Lunitorque Alone ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3PROO15 OFD-116B-3 I 111 C

B Yes Butterfly Lmuntorque None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years IPROO19 OFD-II6B-).I Ell C

B Yes Butterfly Lmtntorque None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2PR0019 OFD-lI6B-2 1 Ell C

B Yes Butterfly Ltnmtorque None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3PR0019 OFD-116B-3 I ElI C

B Yes Butterfly Linntorque None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station-IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purge Page 9 of 17

Valve Flo% Diagram ASME Vahl Active Valit Actuator JFD Test TestType TestDireetlon Test Frequency Relief MaIS Catg.

T)pc T)pe T)pe Description Frequency Description Reqest 1PR0034 0FDJ-I 6B-J.1 111 C

C Yes Check Sell/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2PR0034 OFD-116B-2.1)II1 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 3PR0034 OFD-)J6B-31 I Ell C

C Yes Check Sey/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 1PR003S OFD-I I6B-J I Eli C

C Yes Check Se/A Actua ted None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2PR0035 OFD-1l16B.2 I Eli C

C Yes Check Self/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 3PR0035 OFD-l 1613-3 I Eli C

C Yes Check Self/Actuated None ES Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly Oconee Nuclear Station - 1ST Submittal for Valves Interval 4, Revision 26 Section 4.1 PR-Purze Page 10 of 17 (07/010/2)

I

Valve FlowDlagram ASMIE Vt Acthe Vahl Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Clas Cgtg Tepe Type Type Description Frequency Description Reqest IPROO59 OFD-)16C-J 1 I H2 B

A No Diaphragm Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2PR0059 OFD-1 16C-21I 113 B

A No Diaphrani Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PR0059 OFD-116C-3 1 113 B

A No Diaphragm Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station. IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Puree Page 11 of17 I

Valve FlowDiagram ASME Vahv Active Valiv Actuator JFD Test TestT)pe TestDirectlon Test Frequency Relief Class Catg T)pe Type T.pe Description Frequency Description Reqest 1PROO60 OFD-116C-J I D3 B

A No Diaphragm Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2PR0060 OFD-116C-2 I D3 B

A No Diaphragm Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3PROO60 0FD-116C-3.1 D3 B

A No Diaphragm Rotork None PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage IPR0068 OFD-116C-1.I

.13 B

A No Globe Manual None L

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0068 OFD-Jl6C-2.1

,14 B

A No Globe Manual None LU Leak-Rate Test Valve to Accident Direction RF Tested every iRone App J Requirement(s) refueling outage 3PR0068 OFD-116C.3 I 13 B

A No Globe Manual None LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station-IST Submtttal for I'alves Interval4. Revision 26 (07/01/02)

Section 4.1 PR-Purze Page 12 of 17

Valve FIowDlagram AWME VahW Acthe Volhv Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg Type Type Type Description Frequency Description Reqest IPR0081 OF'D-IIOA-I 3 J6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly Pl Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0081 OP"D-I)IOA-2 3

.16 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR0081 OFD-IJOA -3.3 J6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station.ISTSubnittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purre Page 13 of 17

Valve FlowDlagram ASME Vuali Active Valis Actuator JFD Test TestTylpe TestDirection Test Frequency Relief Class Catg Type Type Type Description Frequency Description Reqest 1PR0084 OFD-) IOA-J 3 K"6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0084 01D.) 10.A.2 3 K6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR0084 OF-D-J IOA -3.3 K6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for Valves Interval 4. RRevision 26 (07/01/02)

Section 4. 1 PR-Purze Page 14 of 17 1

Valve FlowDIagrarn ASME VahT Actlte Valt Actuator JFD Test TestType TestDirection Test Frequency Reflef Clais Catg.

T~pe Type Type Description Frequency Description Reqest 1PR0087 OFD-IIOA-1 3 E6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0087 OFD-IIOA.-2.3 E6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years IJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR0087 OFD-1IOA-3 3 E6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for I Waves Interval 4. Revision 26 (07/01/02)

Section 4.1 PR-Purge Page 15of"17 I

Valve FlowDiaram ASME N'ahW Active VahT Actuator JFD Test TestType TestDirectlon Test Frequency Relief ClaIs Catg.

Type Type Type Description Frequency Description Reqest IPR0090 OFD-JJIOA-l 3 F6 B ~ 4 No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2PR0090 OFD-)IO0,-2 3 F6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3PR009)0 OFD-IJIOA-3 3 F=6 B

A No Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconet Nuclear Station -IST Submittal for Valves Interval 4, Revision 26 Section 4.1 PR-Puree Page 16 of 17 (07/01/02)

J

Valve FlowDlagram ASME VahI Active Val Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

Trpe Type Type Description Frequency Description Reqest 1PRO115 OFD-)16B-J 1 15 C

C Yes Check SelfActuated ON-PR-02 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassem one None vlv per grp ca.

RFO 2PRO115 OFD-116B-2.1 15 C

C Yes Check SelfActuated ON-PR-02 FS Full-Stroke Exercise Closed to Open 0

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassem one None vlv per grp ca.

RFO 3PR0115 OF'D-)I6B-3 1 15 C

C Yes Check SelfActua ted ON-PR-02 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassem one None vlv per grp em.

RFO 1PR0116 OFD-)I6B-J.)

ES C

C Yes Check Self Actuated ON-PR-02 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassem one None vlv per grp ea.

RFO 2PR0116 OFD-116B.2.i ES C

C Yes Check Se/A Actuated ON-PR-02 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassern one None vlv per grp ea.

RFO 3PR01"16 OF'D-I)I6B-3 1 ES C

C Yes Check Set/'Actuated ON-PR-02 FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly SD Sample Disassembly Both (Stroke Test)

SD Disassem one None vlv per grp ea.

RFO Ocon¢eNuclear Station -IST Submittal for Valves Interval 4. Revision 26 Section 4.1 PR-Purge Page 17of17 (07/01/02)

Valve FlowDlagram ASNE

%'WIT Acthie

\\'alW%

Actuator JFD Test TestType TestDirection Test Frequency Rellef Class Catg.

T)pe T)pe T~pe Description Frequency Description Reqest RC " Reactor Coolant 1RC0001 OFD-IOOA-2 1110 A

B No Globe Solenoid ON-RC-02 ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Venfy the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2RC0001 OFD-IOOA-2 2 HIO A

B No Globe Solenoid ON-RC-02 ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3RC0001 OFD-)0a4-3 2 1110 A

B No Globe Solenoid ON-RC-02 ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nucleor Station -IST Submittal for Valves Interval 4. Revision 26 RC-Reactor Coolant Section 4.1 Page I of 11 (o07o01102)

Valve FlomDilagram ASME

\\'ahs Acthe VaaIe Actuator JFD Test TestType TestDlrectlon Test Frequency Relief Class Catg.

Type Type Type Description Frequency Descrlptlon Reqest I RC0004 OFD-IOOA-I 2 J9 A

B Yes Gate Limntforque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2RC0004 OFD-IOOA-2 2 J9 A

B Yes Gate Lbmitorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3RC0004 OFD-)OOA-3 2 J9 A

B Yes Gate Limttorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station. IST Submittal for Ialves Interval 4. Revision 26 RC-Reactor Coolant Section 4.1 Page 2 of 11 1

(07101102)

Valve Flo% Dlagmr ASME Vahr Active Vahw Actuator JFD Test TestType TestDirection Test Frequency Relief CIasi Catg T)pe Type T)pe Description Frequency Description Reqest I RC0005 OFD-I OA-1.1 13 A

A Yes Gate Ltmttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years UI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2RC0005 OFD-IJOA-2 1 13 A

A Yes Globe Lnmttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3RC0005 OFD-IIOA-3.1 13 A

A Yes Gate Llmtorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - IST Submittal for I 'alves Interval4. Revision 26 RC-Reactor Coolant Section 4.1 Page 3 of 11 (07101102)

Valve FlowDiagrami ASME

,'alve Active Valve Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

T~pe T~pe Type Description Frequency Description Reqest 1RC0006 OFD-IIOA-I 1 1H3 A

A Yes Gate Linitorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2RC0006 OFD-I IOA.2 1 113 A

A Yes Globe Ltmttorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years I

Leak-Rate Test Valve to Accident Direction RF Tested every None App I Requirement(s) refueling outage 3RC0006 OFD-IIOA-31 H3 A

A Yes Globe Lnmitorque None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Ocoan" Nuclear Station.IST Submittal for Valves Int!erval4. Revision 26 RC-Reactor Coolant Section 4.1 Page 4 of.11 l

(07101102)

Valve Flo% Diagram ASME Valve Active Vahv Actuator JFD Test TestType TestDirection Test Frequency Relief Clais Catg.

T)pe Type T)pe Description Frequency Description Reqest IRC0007 OFD-IJOA-J.I 16 B

A Yes Globe Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2RC0007 OFD-)JIOA-2 1 16 B

A Yes Globe Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3RC0007 01FV-J IOA -3.)

16 B

A Yes Globe Air None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station - 1ST Submittal for Valves Interval4. Revision 26 (07/01/02)

Section 4.1 Page 5 of 11 RC-Reactor Coolant

Valve FlowDlarun ASMIE Valit Active

\\'alit Actuator JFD Test TestT~pe TestDirectlon Test Frequency Relief CIlI Catg.

Type T)pc Type Description Frequency Description Reqest I RC0066 O"D-I OOA-I.2 J9 A

B Yes Relief Solenoid ON-RC-04 RV Safety and Relief Valve Closed to Open RF Tested every ON-ORV-12 Test refueling outage ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown 2RC0066 OFD-.IOOA-2.2 J9 A

B Yes Relief Solenoid ON-RC.04 RV Safety and Relief Valve Closed to Open RF Tested every ON-GRV-12 Test refueling outage ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown 3RC0066 OD-I OOA.3 2 J9 A

B Yes Relief Solenoid ON-RC-04 RV Safety and Relief Valve Closed to Open RF Tested every ON-ORV-12 Test refueling outage ST Measure Full-Stroke Both (Stroke Test)

CS Tested every None Time of Valve cold shutdown 1RC0067 OFD-IOOA-1.2 J7 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RF Tested every ON-ORV-12 Test refueling outage 2RC0067 OFD-)OOA-2.2 A8 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RF Tested every ON-GRV-12 Test refueling outage 3RC0067 OFD-JOOA-3.2 A 8 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open

, RF Tested every ON-GRV-12 Test refueling outage Oconee Nuclear Station-ISTSubmittal for I'alves Interval 4. Revision 26 (07/01/02)

Section 4.1 RC-Reactor Coolant Page 6 of))

Valve FlowD)agram ASME YahIT Acthe ValT Actuator JFD Test TestT)pe TestDirectlon Test Frequency Relief Class Catg.

T)pe T~pe Type Description Frequency Description Reqest 1RC0068 OFD-1OOA-i 2 J7 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RF Tested every ON-GRV-12 Test refueling outage 2RC0068 OFD-IOOA-2 2 J7 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RF Tested every ON-GRV-12 Test refueling outage 3RC0068 OFD-IOOA-3 2 J7 A

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RF Tested every ON-ORV-12 Test refueling outage 1RC0164 OFD-IIOA-1.4 G4 B

A Yes Solenoid Solenoid None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Open to Closed 2Y Tested once ON-GRV-15 Position Indication every two years LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2RC0164 OFD-IIOA-2.4 G4 B

A Yes Solenoid Solenoid None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Open to Closed 2Y Tested once ON-GRV-15 Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling A

outage 3RC0164 OFD-I)OA-3 4 G4 B

A Yes Globe Manual None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage OconeeNuclear Station - ISTSubinttal for Valves Interval4. Revision 26 (07/01/02)

Section 4.1 Page 7oof 11 RC-Reactor Coolant

Valve FlowDiagram ASME Valve Acthie Valhv Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

Type Type Type Description Frequency Description Reqest IRC016S OFD-J)OA -,.4 G4 C

A Yes Solenoid Solenoid None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Open to Closed 2Y Tested once ON-GRV-15 Position Indication every two years Li Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2RC0165 OE"D-IJIOA-2 4 04 C

A Yes Solenoid Solenoid None ST Measure Full-Stroke Open to Closed Q

Tested once None Time of Valve quarterly PI Verify the Valve Remote Open to Closed 2Y Tested once ON-GRV-1 5 Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3RC016S OFD-IJOA-3 4 04 C

A4 Yes Globe Manual None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly Li Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage IRC01RX NCA NCA NA C

Yes Check Set/ Actuated ON-tRA'-OI FS Full-Stroke Exercise Both (Stroke Test)

RF Tested every None refueling outage S

Oconee Nuclear Station -IST Submittal foro Valves Intupvi1 4. Revision 26 (07/01/02)

RC-Reactor Coolant Section 4.1 Page 8 of))1

ValVe FlowDiagrari ASME

\\'aWr Actihe Vahr Actuator JFD Test TestT)pe TestDirection Test Frequency Relief Clmi Catg Type Type Type Description Frequency Description Reqest 1RC0206 OFD-JJOA-)

J,3 B

A!C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule LU Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2RC0206 OFD-IJIOA-02-Ol 3]4 B

A/C Yes Relief Sed/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-1 2 Test valve per OM-1 schedule LJ Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3RC0206 OF'D-IJIOA.03.0l J4 B

A/C Yes Relhef Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-.GRV-12 Test valve per OM-1 schedule I_

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station.-IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 RC-Reactor Coolant Page 9 ofll I

Valve FlowDlagrwn ASME V'alv Active V'alht Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

Type T)pe T)pe Description Frequency Description Reqest 1RC0207 ORJ-IOa4.J.4 GI B

C

)es Check Self Actuated ON-RC-05 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage 2RC0207 OFD-IIOA-02-04 G2 B

C Yes Check SelfActuated ON-RC-05 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage 3RC0207 OFD-11IOA-03-04 G2 B

C Yes Check SelfActuated ON-RC-05 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage Oconee Nuclear Station.-ISTSubmtttal for I alves Interval 4. Reviswn 26 RC-Reactor Coolant Section 4.1 Page 10 of))

l 1 (07101102)

Valve FlowDlgranm AS*IE Valve Active Valve Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

T~pe Type Type Description Frequency Description Reqest 1 RC0208 OFD-) OA4-J 4 01 B

C Yes Check SelfActuated ON-RC-OS FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage 2RC0208 OFD-I IOA-02-04 G2 B

C Yes Check SelfActuated ON-RC-05 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage 3RC0208 OFD-)IOA-03-04 G2 B

C Yes Check SelfActuated ON-RC-05 FS Full-Stroke Exercise Closed to Open RF Tested every None refueling outage FS Full-Stroke Exercise Open to Closed RF Tested every None refueling outage 2RCO2P.X NA NA M't C

Yes Check Self Actuated ON-R,\\'01 FS Full-Stroke Exercise Both (Stroke Test)

RF Tested every None refueling outage 3RC03RX NA NA NA C

Yes Check SelfActuated ON-R\\'-01 FS Full-Stroke Exercise Both (Stroke Test)

RF Tested every Nqone refueling outage Oconee Nuclear Station - IST Submittal for l'alves Interval 4. Revision 26 (07/01/02)

RC-Reactor Coolant Section 4.1 Page 11 of 11

Valve FlowDiagran AiSME

%'3' Acthe Valhe Actuator JFD Test TestType TestDirectim Test Frequency Relief Class Cztg.

T~pe Type Type Description Frequency Description Reqest SF " Spent Fuel lSF0072 OFD-104A-I.I J3 B

A No Diaphragm Manual None LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SF0072 OFD-IO4A-I.I 1J2 B

A No Ball Manual None LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3SF0072 OFD-IO A-3) 1 J4 B

A No Djaphrooan Manual None U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage ISF0073 OFD-104A-1 I J3 B

A No Diaphravn Manual None LI Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SF0073 OFD-104A-1.1 J12 B

A No Ball Manual None Li Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3SF0073 OFD-104A-3 I JS B

A No ODaphraom Manual None lU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Ocone. Nuclear Station - lST Submittal for Valves Interval 4. Revison 26 (07/01/02)

Section 4.1 Page 1of 7 SF-Spent Fuel

Valve FlowDlagam ASIE VWhT Active Valhe Actuator JFD Test TestType TestDIrectlon Test Frequency Relief Class Catg T)pe T3pe T~pe Description Frequency Description Reqest 1SF0074 OFVD-104A-1 1 13 B

A No Dtaphra~,m Manual None L

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SF0074 OED-104A -1.1 112 B

A No Ball Manual None 2U Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3SF0074 OFD-104A-3 1 15 B

A No Dtaphragmn Manual None AU Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SF0081 OFD-104A-1.J D12 B

A No Gate Manual None 2U Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station IST Submittal for I'alves Interval 4. Reiion 26 (07/01/02)

Section 4.1 Page 2 of 7 I

SF-Sp~ent Fuel

Valve FlowDlogrnm ASME Valht Acthe V'alhs Actuator JFD Test TestType TestDirectlon Test Frequency Relief Class Catg.

T)pe Type T)pe Description Frequency Description Reqest ISF0082SSF OFVD-IOIA-) S P:2 BI A

Yes Globe Lhmtorque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every to years L2 Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SFO082SSF OFD-IOJA.2 S F2 B

A Yes Globe Lnm'torque None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years LJ Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3SFO082SSF OFD-IOIA-3 5 F2 B

A Yes Globe Rotork None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once IRone Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage Oconee Nuclear Station.IST Submittal for Valves IntervalI4. Revision 26 SF-Spent Fuel Section 4.1 Page 3 of/7 (0710110o2)

Valve Flo* Diagrmn ASNIE Valv Acthe

% 'al w Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg T)pe T)pe Type Description Frequency Description Reqest ISFOO97SSF OFDm-O4A-I K3 B

A Yes Gate Rotork None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 2SF0097SSF OFD-104A-1.)

K12 B

A Yes Gate Rotork None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years U

Leak-Rate Test Valve to Accident Direction RF Tested every None App J Requirement(s) refueling outage 3SFOO97SSF OFD-104A-3 1 1K3 B

A Yes Gate Rotork None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly ST Measure Full-Stroke Both (Stroke Test)

RF Tested every None Time of Valve refueling outage P1 Verify the Valve Remote Both (Stroke Test) 2Y Tested once IRJone Position Indication every two years U

Leak-Rate Test Valve to Accident Direction,RF Tested every None App J Requirement(s) refueling outage Oconme Nuclear Station - IST Submittal for I alves InterWl4. Revision 26 SF-Spent Fuel Section 4.1 Page 4 of 7 (0 7101102)

Valve Flow Dlagra m AMIE Valit Acthie Val e Actuator JFD Test TestType TestDlrectlon Test Frequency Relief Class Catg.

Type Type T)pe Description Frequency Description Reqest lSF0125 OFD-104A-OJ-0I K5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule U

Leak-Rate Test Valve to Reverse Direction 2Y Tested once None App J Requirement(s) every two years 2SF0125 OFD-104A-0l-0 E12 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule LI Leak-Rate Test Valve to Reverse Direction 2Y Tested once None App J Requirement(s) every two years 3SF0125 OFD-)04A-03-0I K5 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule U

Leak-Rate Test Valve to Reverse Direction 2Y Tested once None App J Requirement(s) every two years Ocone Nuclear Station - 1ST Submittal for I'alves Interval4. Revision 26 (07/01/02)

Section 4.1 SF-Spent Fuel Page 5 of 7 I

Valve FlowDiagmrn ASME Vaht Actlese Vahr Actuntor JFD Test TestType TestDirection Test Frequency Relief Clasi Catg.

T)pc Type Type Description Frequency Description Reqest 1SF0126 OF-D-1O4A-).I L3 B

A/C Yes Relhef Self Xctuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule LU Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2SF0126 OFD-IOJA.Ol-Ol L12 B

A/VC Yes Relief SelfAetuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule LU Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3SF0126 OF72)-1O4A-03-OI LS B

A/C Yes Relief Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule I2 Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 1SF0127 OFD-104A-I.I D3 B

A/C Yes Relhef Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2SF0127 OFD-104A-01-0. E12 B

AAC Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3SF0127 OFD-1O4A-03-OI E)2 B

A/C Yes Relhef Self Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule Oconee Nuclear Station - IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 Page 6 of 7 SF-Spent Fuel

Valve FlowDlagrun ARNIE Valve Active Vah Actuator JFD Test TestType TestDirection Test Frequency Relef Class Cutg.

Type Type Type Description Frequency Description Reqest ISF0128 OFD-104A-1.1 D3 B

C Yes Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2SF0128 OFD-104A-OI.O) DI3 B

C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 3SF0128 OFD-.04A.03.0) C3 B

C Yes Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule ISF0129 OFD-104A-1.I J3 B

A/C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 2SF0129 OFD-.O4A-OI-0O J12 B

A/C Yes Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule LJ Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage 3SF0129 OFD-.O4A.03-OJ J5 B

AiC Yes Relief Set/Actuated None RV Safety and Relief Valve Closed to Open

• RV Test relief ON-GRV-12 Test valve per OM-1 schedule U

Leak-Rate Test Valve to Reverse Direction RF Tested every None App J Requirement(s) refueling outage Ocorj Nuclear Station - IST Subnmttal for Valves Interval 4. Revhsion 26 (07/01/02)

SF-Spent Fuel Section 4.1 Page 7 of 7

Valve FlowDlogrom AS ME Vah Acthie Valhw Actuator JFD Test TestType TestDirection Test Frequency Relief Cais Cmlg Type Type T)pe Description Frequency Description Reqest 55W" Siphon Seal Water OSSWO003 OFD-129A.I I K'2 C

C Yes Check Set/Actuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly rs Full-Stroke Exercise Open to Closed Q

Tested once None quarterly OSSWO004 OFD-129A-.I J2 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly OSSWO007 OFD-129A-1.)

L2 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly OSSWO008 OFD-129A.-1.I J2 C

C Yes Check Set/Actuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly OSSWO080 OFD-129A-02-02 18 C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule OSSWO081 OFD-129A-I.I 12 C

C No Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule OSSWO082 OFD-129A-1.1 F2 C

C No Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12

.Test valve per OM-1 schedule Oconee Nuclear Station - IST Submittal for Valves Interval 4. Revision 26 SSWV-Siphon Seal Water Section 4.1 Page 1 of 4 (0710110o2)

Valve FIoWDiagram ASNlE V\\ah ActiVe

\\'alh Actuator JFD Test TestType TestDirectlon Test Frequency Relief Cdma Camg T)pe T)pe T~pe Description Frequency Description Reqest 0SSW0083 OFD-129A,.

2 L6 C

C No Relief Sel/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-ORV-12 Test valve per OM-1 schedule ISSW0153 OFD-129A-J.2 KI3 C

C No Relief Set/ Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-l schedule 2SSW0153 OFD-129A-2 2 "1O C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 3SSW0153 OFD.129A-3 2 K2 C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule lSSWO154 OFD.129A.I.2 J13 C

C No Relief Set/Actuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-I schedule 2SSWO154 OFD-129A.-2 2 JJO C

C No Relief SelfActuated None RV Safety and Relief Valve Closed to Open RV Test relief ON-GRV-12 Test valve per OM-1 schedule 3SSW0154 OFD-129A-3 2 K2.

C C

No Relief SelfActuated None RV Safety and Relief Valve Closed to Open

' RV Test relief ON-GRV-12 Test valve per OM-1 schedule Oconee Nuclear Station. ISTSubnittal for Valves Interv l4. Revision 26 (07/01/02)

SSW-Siphon Seal Water Section 4.1 Page 2 of 4

Valve FlowDiagran AME Valw Acthe Valh Actuator JFD Test TestType TestDirection Test Frequency Relief Class Catg.

Type Type Type Description Frequency Description Reqest ISSWO155 OFD-129A.J)1 D4 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2SSWO155 OFD-129A.1 I D8 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3SSWO155 OFD-129A-I1 DII C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years lSSWO156 OFD-129A-l.I D6 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2SSWOI16 OFD.129A.lI D16I C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3SSWO156 OFD-129A-1.I

)D3 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station.ISTSubnittal for Valves Interval 4. Revision 26 (07/01/02)

SSW-Sihhon Seal Water Section 4.1 Page 3 of 4

Valve FlowDiagram ASNIE Vhit Actie Vall Actuator JFD Test TestType TestDirection Test Frequency Relief CIlai Catg T~pe Type Type Description Frequency Description Reqest lSSWO157 OFD-129A-l.I DJ C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Vertfy the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2SSWO157 OFD-.29A-1.]

D9 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 3SSWO157 OFD-129A.) I D12 C

B Yes Solenoid Solenoid None ST Measure Full-Stroke Both (Stroke Test)

Q Tested once None Time of Valve quarterly PI Venfy the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years Oconee Nuclear Station. IST Submittal for Valves Interval 4. Revision 26 (07/01/02)

Section 4.1 Page 4 of 4 SSWV-Siphon Seal Water

Valve FlowDlagram ASME Valhe ActlIe Valhc Actuator JFD Test TestType TestDirectlon Test Frequency Relef Chis Ctg.

Type Tyep Type Description Frequency Description Reqest TS

" Keowee Turbine Sump 1TSO002 KFD.102.-I.I G8 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2TS0002 KFD.-102A.2I G8 C

C Yes Check Set/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly ITSO04 KFD1.)02A -1.1 118 C

C Yes Check Set/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2TS0004 KFD-102A.2 1 118 C

C Yes Check Set/Actuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly ITS0013 KFtD-102A-1.1 1 112 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly 2TS0013 KFD-I02A-*.

2 1112 C

C Yes Check SelfActuated None FS Full-Stroke Exercise Closed to Open Q

Tested once None quarterly FS Full-Stroke Exercise Open to Closed Q

Tested once None quarterly Ocon*, Nuclear Station - IST Submittal for I'alves Interval 4. Revision 26 TS-Keowee Turbine Sump Section 4.1 Page I of)I (07/1012)

Valve FlowDlagrom ASME a'ht Actlh

\\Valle Actuntor JFD Test TestT.pe TestDirection Test Frequency Rellef Class Catg T~pe Type Type Description Frequency Description Reqest WL

" Keowee Turb. Gen. Cooling Wtr IWLOO11 KFD-IOOA.I I JI C

B Yes Globe Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PF Verify the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years 2WL0011 KFD-IOOA-2.1 JI C

B Yes Globe Air None ST Measure Full-Stroke Closed to Open Q

Tested once None Time of Valve quarterly PI Verify'the Valve Remote Both (Stroke Test) 2Y Tested once None Position Indication every two years IWL0040 KFD-IOOA-1. 1 B1)

C C

Yes l'acuum Breaker SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2WL0040 KFD.IOOA-2.1 B11 C

C

)es Vacuum Breaker SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 1WL0077 KFD-IOOA-I.)

FIO C

C Yes V'acuum Breaker SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly 2WL0077 A:FD-1Oa4-2)

FIO C

C

)es l'acu:~m Breaker SelfActuated None FS Full-Stroke Exercise Both (Stroke Test)

Q Tested once None quarterly Oconee Nuclear Station -IST Submittal for Valves Interal 4. Revision 26 (07/01/02)

WL-Keowee Turb. Gen. Coolinz Wtr Section 4.1 Page IJof I

DUKE POWER OCONEE NUCLEAR STATION Relief Request Section 5.0 Revision 26 7/01/02

5.1 PUMP GENERIC RELIEF REQUESTS Relief Request Applicability Status Deleted 1/31/99 Deleted 1/31/99

-Deleted 2/13/95 Deleted 2/13/95 Deleted 9/01/95 Deleted 1/31/99 Rev. 26 07/01/02 Page 1 of 1 ON-GRP-01 ON-GRP-02 ON-GRP-03 ON-GRP-04 ON-GRP-05 ON-GRP-06 N/A N/A N/A N/A N/A N/A

5.2 PUMP SPECIFIC RELIEF REQUESTS Relief Request Applicability Status ON-SRP-HPI-01 ON-SRP-HPI-02 ON-SRP-TS-01 SSF RC Makeup Pumps Unit 3 SSF RC Makeup Pumps Keowee Turbine Sump Pumps Submitted 07/01/02 Submitted 07/01/02 Deleted 07/01/02 Rev. 26 07/01/02 Page I of 1

Oconee Units 1, 2, and 3 Pump Specific Relief Request Item Number:

ON-SRP-HPI-01 Pump(s):

Function:

Test Requirement:

Basis for Relief:

07101/02 Rev. 26 SSF RC Makeup Pumps (positive displacement) 1,2,3HPIPU0005 The SSF RC Makeup pumps shall be capable of delivering sufficient flow to the RC pump seal injection lines during an SSF Event in order to prevent seal failures (seal LOCA).

Per OMa-1996a Subsection ISTB paragraph 5.2.3 (c), the flow rate and pressure shall be determined and compared to their respective reference values where system resistance cannot be varied.

During an accident the SSF RC Makeup pumps take suction from the spent fuel pool and inject into the reactor coolant pump (RCP) seals. During accident conditions, the SSF RC Makeup pumps would be required to inject flow into the RCP seals at 2350 psig. The SSF RC Makeup pump for each unit is tested during power operation through a recirculation test flow path that takes suction from the spent fuel pool and returns to the spent fuel pool.

The spent fuel level is not capable of providing the 2350 psig of back pressure necessary to sufficiently challenge the SSF RC Makeup pumps during quarterly testing. Therefore, a throttle valve is installed within the recirculation test flow path in order to create resistance within the system.

This resistance increases the discharge pressure of the SSF RC Makeup pump to greater than 2350 psig during quarterly testing through the recirculation test loop.

The flow capability of the pump can then be evaluated at conditions similar to accident conditions. The installed throttle valve is not capable of being adjusted during power operation because it is located within a high dose area of the reactor building.

Thus, the recirculation test loop utilized for quarterly testing of the SSF RC Makeup pump is considered to be a fixed resistance.

The SSF RC Makeup pumps are positive displacement pumps located within the reactor building. Given the utilization of a fixed resistance system, both the discharge pressure and the flow rate of the SSF RC Makeup pumps are monitored against acceptance limits. The flow rate achieved by the SSF RC Makeup pumps is evaluated against IST flow acceptance limits and design basis acceptance limits. The discharge pressure achieved by the SSF RC Makeup pumps is evaluated against the lower range IST pressure acceptance limits and design pressure of the piping.

The discharge pressure achieved by the SSF RC Makeup pumps is not evaluated against the higher range IST pressure acceptance limits. Rather, the discharge pressure achieved by the SSF-RC Makeup pumps is only evaluated against the design pressure of the piping.

The potential exists for increased system resistance to occur within the recirculation test loop (increased filter fouling, etc.) during quarterly testing.

The discharge pressure of the SSF RC Makeup pump would increase with an increase in system resistance. Per IST requirements, if the discharge pressure increased above the IST limit, then, the SSF RC Makeup pump would be declared inoperable and power reductions would be necessary to ON-SRP-HPI-01 Page I of 2 Section 5.2

Test Alternative:

adjust the installed test loop throttle valve. Such corrective actions would be required per IST regardless if the pump were still capable of meeting its flow rate requirements at the higher discharge pressure. Such corrective actions would be deemed impractical given that the design basis of the system at the higher pressure was ensured. Allowing the pump discharge pressure to vary above the IST limit only increases the challenge of the pump.

Degradation of hydraulic performance of a positive displacement pump would be more likely to occur at a higher discharge pressure. Likewise, requiring a positive displacement pump to produce a flow rate at a higher discharge pressure would create higher loading on both the pump and

motor, thereby, increasing any likelihood of reduced vibrational performance.

The discharge pressure limits associated with design pressure limits will ensure that system limits are acceptable with higher pump dischiarge pressures. Therefore, it is concluded that limiting the upper acceptance criteria of discharge pressure for the SSF RC Makeup Pumps to piping design pressure limits, rather than IST limits, will not mask any pump degradation and will ensure that system limits are not violated.

Given the utilization of a fixed resistance system, both the discharge pressure and the flow rate of the SSF RC Makeup pumps are monitored against acceptance limits. The flow rate achieved by the SSF RC Makeup

• pumps is evaluated against IST flow acceptance limits and design basis "

acceptance limits.

The discharge pressure achieved by the SSF RC Makeup pumps is evaluated against the lower range IST pressure acceptance limits and piping design pressure limits.

The discharge pressure achieved by the SSF RC Makeup pumps is not evaluated against the higher range IST pressure acceptance limits. Rather, the discharge pressure achieved by the SSF RC Makeup pumps is only evaluated against piping design pressure limits.

07/01/02 Rev. 26 ON-SRP-HPI-01 Page 2 of 2 Section 5.2

Oconee Unit 3 Pump Specific Relief Request Item Number:

ON-SRP-HPI-02 Pump(s):

SSF RC Makeup Pump (positive displacement) 3HPIPU0005 Function:

The SSF RC Makeup pump shall be capable of delivering sufficient flow to the RC pump seal injection lines during an SSF Event in order to prevent seal failures (seal LOCA).

Test Requirement:

Per OMa-1996 Subsection ISTB 4.7.4 c, one vibration measurement shall be read during each inservice test. On reciprocating pumps, the location shall be on the bearing housing of the crankshaft, approximately perpendicular to both the crankshaft and the line of plunger travel.

Basis for Relief:

During an accident, the SSF RC Makeup pump takes suction from the spent fuel pool and injects into the reactor coolant pump (RCP) seals.

During accident conditions, the SSF RC Makeup pump would be required to inject flow into the RCP seals at 2350 psig. The SSF RC Makeup pump is tested during power operation through a recirculation test flow path that takes suction from the spent fuel pool and returns to the spent fuel pool.

The SSF RC Makeup pump is a positive displacement pump located within the containment building. Quarterly vibration parameters are monitored via permanently installed vibration sensors that are routed through a containment penetration.

Two vibration sensors (accelerometers) are mounted on the pump bearing housings. The pump outboard bearing probe is in the vertical direction (perpendicular to the crankshaft and perpendicular to the line of plunger travel) and the pump inboard probe is in the horizontal direction (perpendicular to the crankshaft and parallel to the line of plunger travel).

Currently, the pump outboard vibration probe is not functioning properly such that valid data is unobtainable from this instrument.

During an extended pump run on 3/8/02, the pump outboard bearing vertical vibration was observed to be responding erratically. After a detailed engineering analysis of the vibration data, it was concluded that there is no known machinery defect that would cause the erratic vibration signature.

In addition, other pump parameters (the inboard bearing horizontal vibration value, discharge pressure, flow) remained steady and consistent with past pump performance. Furthermore, such significant changes in the pump outboard bearing vertical vibration instrument readings would also be observed to some degree in the pump inboard bearing-idrizontal vibration instrument readings if the pump were degrading.

Due to the location of the malfunctioning vibration sensor (inside the containment building biological shield wall), a unit power reduction from 100% to approximately 20% would be required to enter containment and correct the problem.

The power reduction is necessary to reduce the radiation field that makes the equipment inaccessible at full power.

07/01102 ON-SRP-HPI-02 Rev. 26 Page 1 of 2 Section 5.2

Test Alternative:

07/01102 Rev. 26 Monitoring of the pump vibration with only one probe functioning will ensure the health of the pump is sufficiently examined.

For this component, degradation of the pump would be characterized by specific frequencies of vibration corresponding to the shaft speed and plunger cycling. In addition to reviewing acceptability of the overall vibration level at the horizontal sensor, Engineering will evaluate the frequency spectrum for each test. Review of pump failure modes with the manufacturer has determined that increases in vibration amplitude at shaft speed and plunger cycling frequency will give early indication -of a degrading condition. Furthermore, the manufacturer has concluded that there is no credible failure mechanism for the pump that would manifest itself in such a way that this level of monitoring would not detect failure.

Compliance with the OMa-1996 Subsection ISTB 4.7.4 c vibration measurement requirement location would be a hardship without a compensating increase in the level of quality and safety pursuant to 10CFR50.55a(a)3(i*i, with the hardship being the unit power reduction that would be required in order to correct the malfunctioning vibration sensor.

The SSF RC Makeup Pump will be tested in accordance with OMa-1996 Subsection ISTB 4.7.4 c requirements except for the stated location of the vibration measurement point. Rather, vibration will be monitored on the pump inboard bearing in the horizontal direction that is perpendicular to the crankshaft and parallel to the line of plunger travel. This alternative will only be utilized until the next power reduction that would accommodate repair to the pump outboard bearing probe in the vertical direction.

ON-SRP-HPI-02 Page 2 of 2 Section 5.2

5.3 VALVE GENERIC RELIEF REQUESTS Rev. 26 07/01/02 Page I of I Relief Request ON-GRV-01 ON-GRV-02 ON-GRV-03 ON-GRV-04 ON-GRV-05 ON-GRV-06 ON-GRV-07 ON-GRV-08 ON-GRV-09 ON-GRV-10 ON-GRV-11 ON-GRV-12 ON-GRV-13 ON-GRV-14 ON-GRV-15 ON-GRV-16 Applicability N/A N/A Fail-Safe Valves N/A N/A N/A N/A N/A N/A N/A N/A Safety/And Relief Valves Tested Under Ambient Conditions (remove 10 minute hold time) written 10/03/98 N/A N/A Valves with Passive Safety Functions and Remote Position Indications Valves with Passive Safety Functions Status Deleted 02/13/95 Deleted 02/13/95 Revised 07/01/02 Deleted 02/13/95 Deleted 02/13/95 Deleted 02/13/95 Deleted 02/13/95 Deleted 07/01/02 Deleted 02/13/95 Deleted 07/01/02 Deleted 02/13/95 Revised 07/01/02 Deleted 07/01/02 Deleted 07/01/02 Submitted 07/01/02 Submitted 07/01/02

Oconee Units 1, 2, and 3 Generic Relief Request Item Number.

Category Type:

Test Requirement:

Basis for Relief:

Alternate Testing:

07/01/02 Rev. 26 ON-GRV-03 Fail-Safe Valves ISTM 4.2.6: "Valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the exercising frequency of paragraph ISTC 4.2.1."

Testing by loss of actuator power is not practical.

First, loss of actuator power generally involves maintenance action to interrupt power, which must subsequently' be restored and verified. This greatly increases the manpower requirements for testing and increases possibility for human error in returning component to service.

Second, by ISTC 3.4, a subsequent post-maintenance test is required to verify return to acceptable operation.

Third, some components, especially pneumatic valves, have two modes of "loss of actuator power": they can lose pneumatic power by loss of instrument air or they can lose electrical power to control solenoids.

Therefore, to test all modes of failure at least three tests would be required on some valves.

The net result is a significant increase in manpower and time to perform the tests, an increase in radiation exposure for valves in radiation areas, and an increase in the possibility of improper return to service.

Fail safe valves will be tested using normal controls. Where both normal controls and engineered safeguard (ESG) control switches exist, the ESG switches will be used. The action of the switch is the same as if the actuator power is removed.

Fail/Safe valves installed have pneumatic or mechanical devices to fail the valve in the safe direction. Response to I.E. Notice 88-14 and recent analysis has shown all valves installed to fail in the safe direction and/or mechanical means have been provided and incorporated into procedures to reposition the valve.

ON-GRV-03 Page I of I Section 5.3

Oconee Units 1, 2, and 3 Generic Relief Request Item Number:

ON-GRV-12 Category Type (s):

Flow Diagram (s):

Function (s):

Test Requirement:

Basis for Relief:

Code Alternative:

All safety and relief valves set-pressure testing.

All applicable Provide over-pressure protection to associated systems.

ASME OMa-1996, Appendix I Sections I 8.1.1(h), I 8.1.2 (h) and I 8.1.3 (g), Time Between Valve Openings; A minimum of 10 min.

shall elapse between successive openings.

For these valves, the requirement for waiting 10 min. between successive openings has been modified by the ASME Code Committees in conjunction with safety and relief valve industry experts and is reflected in a change made to the ASME O&M 1995 Edition (OMb 1997, Appendix I). Data and research has proven that the effect on thermal equilibrium and set-point is negligible between successive openings.

The impact of waiting 10 minutes between successive openings is an unnecessary increase in manpower and radiation exposure with no increase in level of safety or test accuracy.

For all safety and relief valves, a minimum of 5 min. shall elapse between successive valve openings.

07/01/02 Rev. 26 ON-GRV-12 Page I of 1 Section 5.3

Oconee Units 1, 2, and 3 Generic Relief Request Item Number:

Category Type:

Test Requirement:

Basis for Relief:

Alternate Testing:

07/01/02 Rev. 26 ON-GRV-15 Valves with passive safety functions and remote position indications.

The scope of OMa-1 996 Subsection ISTC includes testing requirements for valves which have a passive safety function and remote position indicators. ISTM 4.1 of Omao1996 Subsection ISTC requires that valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated.

If a valve position indicator of a valve with a.passive safety function is verified to be correctly indicating the actual valve positiorn by other means (flow, pressure, etc.),

observing the valve locally provides little or no value. In general, valves can not be verified locally without cycling in at least one direction in order to obtain a point of reference with respect to direction of travel of the stem. Since the code does not require valves with passive safety functions to be cycled, the local position verification of the valve requires an additional test cycle of the valves to observe the direction of stem travel. Thus, the local valve position verification unnecessarily increases the wear on the valve by requiring valve cycling and requires the positioning of passive valves out of their safety position during cycling. Verification by other means such as flow, pressure, etc. would give as much (if not more) assurance that the actual valve position is correctly indicated. Therefore, utilizing other positive means (flow, pressure, etc.) for verifying passive valve position indication is a viable alternative that eliminates unnecessary cycling of passive valves which is required with local verifications.

Valves with remote position indicators shall be verified at least once every two years to verify that valve operation is accurately indicated. For a valve with a passive safety function in the open position, the open remote position indication is to be verified with plant indications that the valve can pass full accident required flow. For a valve with a passive safety function in the closed position, the closed remote position indication is to be verified with testing that demonstrates the valve is acceptably leak tight with respect to design basis requirements.

ON-GRV-15 Page I of 1 Section 5.3

Oconee Units 1, 2, and 3 Generic Relief Request Item Number:

Category Type:

Test Requirement:

Basis for Relief:

Alternate Testing:

07101102 Rev. 26 ON-GRV-16 Valves which are maintained in one position to satisfy a safety function (i.e.

passive safety function) and then must change position during an event to fulfill another safety function (i.e. active safety function).

Although Table ISTC 3.6-1 of OMa-1996 Subsection ISTC clearly describes testing requirements based on valve function (i.e. active versus passive), Section ISTC 4.2.2 appears to imply that exercise testing of a valve is required for passive functions of active valves.

Per Section ISTC 1.1 of OMa-1 996 Subsection ISTC, the basis of Inservice Testing is to assess the operational readiness of active or passive valves which are required' to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

To this end, a valve which has a single active function to change position is monitored to ensure its operational readiness to fulfill such a function.

Likewise, the position indication of a valve which simply has a passive function to remain in a certain position is monitored. Thus, the code has no requirements or provisions for monitoring the ability of passive valves to change position. As recognized by the code, the degradation of a valve to move to its passive position is inconsequential since the valve is maintained during normal operations in such a position to meet its passive safety function. As previously stated, Section ISTC 4.2.2 does not appear to recognize that certain valves may have a passive function and an active function. For example, Section ISTC 4.2.2 requires that a valve be full stroke exercised during plant operation to the positions required to fulfill its function(s). This would imply that a valve with a passive function in one direction and active function in the other direction would be required to be monitored for degradation during cycling to either position. However, as previously stated and as recognized by the code, any potential degradation of a valve to change position to meet its passive safety function is inconsequential. Obviously, since it is a passive function, there is no necessity for a valve to move to its passive position to perform a specific function in shutting down a reactor to the cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident. Likewise, there should be no requirement to monitor the ability of a valve to move to its passive position.

For valves which are maintained in one position to satisfy a safety function (i.e.

passive safety function) and then must change position during-en event to fulfill another safety function (i.e. active safety function), the following testing is to be performed:

"* Testing of the passive function of the valve will be performed identically to the testing specified within Table ISTC 3.6-1 of OMa-1996 for a passive valve.

"* Testing of the active function of the valve will be performed identically to the testing specified within Table ISTC 3.6-1 of OMa-1 996 for an active valve.

ON-GRV-16 Page 1 of 1 Section 5.3

5A VALVE SPECIFIC RELIEF REQUESTS Relief Request Applicability Status ON-SRV-CF-01 ON-SRV-CF-02 Core Flood Tank "A" and "B" Outlet Checks LPI Header"A" and "B" Check Valves Revised 07/01/02 Revised 07/01/02 Rev. 26 07/01/02 Page 1 of 1

Oconee Units 1,2, and 3 Specific Relief Request Item Number.

ON-SRV-CF-01 Valve(s):

ICF0011, 1 CF0013 2CF0011, 2CF0013 3CF0011, 3CF0013 Valve Category.

A/C Function:

Test Requirement:

Basis for Relief:

07/01/02 Rev. 26 These valves normally prevent backflow from RCS to core flood tanks. In an emergency they open to permit flow from core flood tanks to the Reactor Coolant System.

OMa-1996, Subsection ISTC 3.4 Effect of Valve or Actuator Replacement, Repair, and Maintenance on Reference Values Relief is requested from requirement for post-maintenance flow testing.

ISTC 4.5.8 Corrective Action Relief is requested from requirement to flow test prior to retuming valve to service following corrective action.

Relief from OMa-1996 Subsection ISTC 3.4 requirement for post maintenance testing is requested on the following basis. Any maintenance required on these valves would be scheduled after the full flow test because the valve cannot be removed from the system for maintenance until after the core flood tanks are drained (low-point maintenance).

Full flow testing is concurrent with draining of the tanks, and therefore precedes valve removal.

Revising the outage schedule to provide for valve maintenance prior to full flow testing would create a significant hardship on outage management and would adversely affect shutdown risk as explained below.

ON-SRV-CF-01 Page I of 2 Section 5A

Alternate Testing:

07/01/02 Rev. 26 The maintenance on the valve must be performed during the defueled maintenance window. To fill the CF Tanks after defueled maintenance window and perform the full flow test before fuel is reloaded would take roughly 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> of critical path outage time. Additionally, during that phase of the outage there is no available space to mix water for the CF Tank fill.

There is also no piping system available to refill the tanks. Realignment of the piping necessary to refill the tanks would require extensive procedure revisions and many Block Tagout revisions.

Performing the test just prior to fuel movement as required by the above scenario would cloud the water in the vessel and limit the ability to properly verify fuel assembly locations. This increases the risk of a fuel handling error during the refueling process.

Relief from the retest requirement following corrective action (ISTC 4.5.8) is requested on the same basis as stated above for ISTC 3.4. Corrective action as intended in this context would necessarily require disassembly for these valves. Such corrective action will be scheduled during the defueled maintenance window of each respective refueling outage.

As an alternative to post-maintenance retesting required by ISTC 3.4 and ISTC 4.5.8, all maintenance which can affect the performance of the valve will be performed during refueling. The valves will be exercised by hand following disassembly, prior to returning the valves to service. While not the preferred method, disassembly is recognized within OMa-1996, Subsection ISTC 4.5.4 (c) whereby flow test methods are impractical.

Additionally, Generic Letter 89-04 recognizes disassembly as an acceptable altemate to full flow testing. In some respects, disassembly can be the most effective method of advance detection of deterioration. For example, it can detect wear, corrosion, or other mechanical damage that flow testing may not detect. Therefore, this method will assure an acceptable level of safety. A partial stroke test will be performed during unit startup following disassembly.

ON-SRV-CF-01 Page 2 of 2 Section 5.4

Oconee Units 1, 2, and 3 Specific Relief Request Item Number:

Valve(s):

Valve Category:

ON-SRV-CF-02 ICF0012, lCF0014 2CF0012, 2CF0014 3CF001 2, 3CF001 4 A/C Function:

Test Requirement:

Basis for Relief:

07/01102 Rev. 26 These valves normally prevent backflow from RCS to LPI/CF Systems. In an emergency they open to permit flow from core flood tanks or LPI to the Reactor Coolant System.

OMa-1 996, Subsection ISTC 3.4 Effect of Valve or Actuator Replacement, Repair, and Maintenance on Reference Values Relief is requested from requirement for post-maintenance full-flow testing.

ISTC 4.5.8 Corrective Action Relief is requested from requirement to full-flow test prior to returning valve to service following corrective action.

Relief from OMa-1996, Subsection ISTC 3.4 requirement for post maintenance testing is requested on the following basis. These valves cannot be isolated from the RCS. Therefore, disassembly of these valves for maintenance must be performed when the reactor is defueled and the refueling canal drained. (This is called the "defueled maintenance window" or "low point maintenance windows.) Operability testing of these valves is scheduled immediately following defueling and just prior to draining the canal for maintenance.

Since the operability test requires draining of the core flood tanks, there will be no water source for testing after the completion of maintenance.

Revising the outage schedule to provide for valve maintenance prior to full-flow testing would require either a) isolating the core flood tanks with CF-1 and CF-2 while draining the canal and performing maintenance, or b) draining the core flood tanks prior to the defueled maintenance window. Option a) is a safety risk to maintenance personnel, since the tanks would have only single isolatigri.. Also, it does not allow for maintenance of CF-1 and CF-2, if required. Option b) creates an outage scheduling burden in that the core flood tanks would have to be refilled in order to perform the operability test. During that phase of the outage there is no available space to mix water for the CF Tank fill. There is also no piping system available to refill the tanks. Realignment of the piping necessary to refill the tanks would require extensive procedure revisions and many Block Tagout revisions. Furthermore, any problems discovered during the operability test would require a second draining of the refueling canal for ON-SRV-CF-02 Page I of 2 Section 5.4

Alternate Testing:

repairs. These hardships are not offset by a compensating increase in the level of safety. In fact, both of the above options would adversely affect shutdown risk, as follows.

The water in the canal will be clouded by the operability test. The sequences described above result in reduced time allowed for this cloudiness to clear up prior to refueling. This would make it harder to identify fuel assembly locations correctly, increasing the risk of a fuel handling accident.

Relief from the retest requirement following corrective action (ISTC 4.5.8) is requested on the same basis as stated above for ISTC 3.4. Corrective action as intended in this context would necessarily require disassembly of the valves, as the condition of the valve internals would need to be ascertained. Such corrective action will be scheduled during the defueled maintenance window of each respective refueling outage.

As an alternative to post-maintenance retesting required by ISTC 3.4 and ISTC 4.5.8, all maintenance which can affect the performance of the valve will be performed during refueling. The valves will be exercised by hand following disassembly, prior to returning the valves to service. While not the preferred method, disassembly is recognized within OMa-1996, Subsection ISTC 4.5.4 (c) whereby flow testing is impractical.

Additionally, Generic.

Letter 89-04 recognizes disassembly as an acceptable alternate to full flow, testing. In some respects; disassembly can be the most effective method of advance detection of deterioration.

For example, it can detect wear, corrosion, or other mechanical damage that flow testing may not detect.

Therefore, this method will assure an acceptable level of safety. A partial stroke test will be performed during unit startup following disassembly.

07/01102 Rev. 26 ON-SRV-CF-02 Page 2 of 2 Section 5.4

DUKE POWER OCONEE NUCLEAR STATION Justification For Deferral Section 6.0 Revision 26 7/01/02

6.1 VALVE JUSTIFICATION FOR DEFERRALS Justification for Deferral Applicability Status ON-AS-01 ON-AS-02 ON-BS-01 ON-BS-02 ON-C-01 ON-C-02 ON-C-03 ON-C-04 ON-CC-01 ON-CC-02 ON-CF-01 ON-CF-02 ON-CF-03 ON-CS-01 ON-CS-02 ON-ESV-01 ON-FDW-01 ON-FDW-02 ON-FDW-03 ON-FDW-04 ON-FDW-05 ON-FDW-06 ON-FDW-07 ON-FDW-08 ON-FDW-09 ON-FDW-010 ON-FDW-01 1 ON-FO-01 ON-HP-01 ON-HP-02 ON-HP-03 Deleted 07/01/02 Deleted 09/01/95 A or B RBSP Discharge Checks A or B RBS Containment Isolation Checks MDEFWPs Suction from UST Block MDEFWPs Suction from UST Check MDEFWPs Suction from Hotwell Check Deleted 07/01/02 CC Supply/Return Containment Isol.

CC Supply Containment Isol. Check CFT A and B Outlet Checks LPI/CF Header Checks CFT A and B Inlet Checks Quench Tank Recirc. Containment Isolation Check Thermal Reverse Flow Check Valves Deleted 07/01/02 OTSG Startup Block and Control TDEFWP Discharge Checks, EFW to OTSG A or B, and OTSG Emergency Header Checks A or B OTSG Main Flow Control Normal FDW to Emergency Checks Deleted 07/01/02 Steam Generator Isolation Check Valves Emergency Feedwater Header Check Valves Emergency Feedwater Inside Containment Penetration Check Valves MDEFWP Normal Discharge Header Check Valves MDEFWP Minimum Flow Check Valves Emergency Feedwater Outside Containment Penetration Check Valves SSF Diesel Engine Fuel Oil Transfer Pump Discharge Check Valves Letdown Containment Isolation RCP Seal Return Containment Isol.

HPI Loop A Emergency Injection Control Submitted 07/01/02 Deleted 09/01/95 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Rev. 26 07/01/02 Page 1 of 3

6.1 VALVE JUSTIFICATION FOR DEFERRALS Justification for Deferral Applicability Status ON-HP-04 ON-HP-05 ON-HP-06 ON-HP-07 ON-HP-08 ON-HP-09 ON-HP-10 ON-HP-11 ON-HP-12 ON-HP-13 ON-HP-14 ON-HP-15 ON-HP-16 ON-HP-17 ON-HP-1 8 ON-HP-19 ON-HP-20 ON-HP-21 ON-HP-22 ON-LP-01 ON-LP-02 ON-LP-03 ON-LP-04 ON-LP-05 ON-LP-06 ON-LP-07 ON-LP-08 ON-LP-09 ON-LP-1 0 ON-LPSW-01 ON-LPSW-02 HPI A or B Crossover Valves LDST Outlet Checks HPI Pump Min. Recirculation Block Letdown Containment Isolation RC Seal Return Line Check Deleted 07101102 HPI Pump Emergency Suction Checks HPI Pump Discharge Checks Al or A2 Loop Injection Stop Checks B1 or B2 Loop Injection Stop Checks HPI Loop B Emergency Injection Checks HPI Loop A Emergency/Normal Injection Checks HPI Pump Min. Recirculation Stop Checks RCP Seal Supply Containment Isol. Checks Cancelled Tempering Supply Inside Containment Isolation Check Valve HPI Tempering Line RCS Boundary Check Valve Inlet Stop Check Valve HPI Pump Min. Flow Line Stop/Check Valve Decay Heat Drop Line Isolation A or B LPI Header Containment Isol. Checks Post-LOCA Boron Dilution Valves LPI Pump A Discharge Check Valve Deleted 07/01/02 LPI Supply to HPI Isolation A or B LPI Header Isolation LPI Post Boron Dilution Valves BWST to LPI Pump Check Valves Reactor Building Sump Section Isolation Valve RCP Cooler Supply and Discharge Block U3 MTOT Cooler Supply Block Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Cancelled 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/01/02 Submitted 07/61/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Submitted 07/01/02 Revised 07/01102 Revised 07/01102 Rev. 26 07/01/02 Page 2 of 3

6.1 VALVE JUSTIFICATION FOR DEFERRALS Justification for Deferral Applicability Status ON-LPSW-03 ON-LPSW-04 ON-LPSW-05 ON-LWD-01 ON-MS-01 ON-MS-02 ON-MS-03 ON-MS-04 ON-MS-05 ON-MS-06 ON-MS-07 ON-N-01 ON-N-02 ON-PR-01 ON-PR-02 ON-RC-01 ON-RC-02 ON-RC-03 ON-RC-04 ON-RC-05 ON-RX-01 ON-SSF-01 ON-SSF-02 ON-SSF-03 ON-SSF-04 ON-SSF-05 Normal/Emergency Supply Checks to HPIP Motor Deleted 3126/96 RBCU Cooling Coil Outlet Valves Reactor Building Sump Containment Isolation Valves Turbine Stop Main Steam Turbine Bypass MS Supply to FDWPTs Block MS Supply to SSRH Block Deleted 09/01/95 Deleted 07/01/02 Main Atmospheric Dump Block/Equalization Valves CFT A and B Inlet Containment Isol. Checks Low Pressure Nitrogen Header Supply Check Valves Deleted 01/31/99 Penetration Room Filter Train Inlet Check Valves Deleted 3/26/96 Pressurizer Spray Control Deleted 01/31/99 Pressurizer Power Operated Relief Valves Reverse Flow Check Valves RX Vessel Inlet Vent Valves SSF ASW Supply to A OTSG SSF RC Makeup Supply to RCP Seals SSF RC Makeup to RCP Seals Block Letdown to Spent Fuel Vent SSF AFW Supply to B OTSG Control Revised 07/01/02 Deleted 3/26/96 Revised 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Deleted 09/01/95 Submitted 07/01/02 Submitted 07/01/02 Revised 07/01/02 Submitted 07/01/02 Deleted 01/31/99 Submitted 07/01/02 Deleted 3/26/96 Revised 07/01/02 Deleted 01/31/99 Revised 07/01/02 Submitted 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Revised 07/01/02 Deleted 07/01/02 Rev. 26 07/01/02 Page 3 of 3

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-BS-01 Reactor Building Spray Pump Discharge Check Valves 1 BS001 1, 2BS001 1, 3BS001 1, 1 BS001 6, 2BS001 6, 3BS001 6 C

These valves shall be capable of opening to pass flow from the Reactor Building Spray Pumps.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be full stroke exercised open at power conditions, cold shutdown conditions, or refueling conditions. The present piping size configuration prevents recirculation flow from the pumps and through these check valves from equaling reactor building spray design flow. Normal recirculation flow is approximately 1250 gpm and design flow for the system is 1500 gpm. Quarterly testing in the open direction is impractical.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are stroked to the closed position and partially stroked to the open position every three months.

ON-BS-01 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-BS-02 Reactor Building Spray Header Isolation Check Valves 1BS0014, 2BS0014, 3BS0014, 1BS0019, 2BS0019, 3BS0019 C

These Yalves shall be capable of opening to provide spray to containment atmosphere.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996 Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be tested to the open position at power conditions, cold shutdown conditions, or refueling conditions. Full flow testing of the valves with system flow would spray down the containment building, which is unacceptable.

Full flow testing of the valves with air is not possible due to the pipe size and available volume of air.

These are the last valves prior to reaching the spray nozzles. Testing these valves to the closed position is not practical given the system design.

Quarterly testing of these valves is impractical.

In addition, frequent testing of these valves is not deemed necessary because of the following:

There are two independent RB spray trains.

These valves are not subjected to liquid or a corrosive atmosphere.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are partially stroked using air to the open position every refueling outage.

ON-BS-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-C-01 Motor Driven Emergency Feedwater (MDEFW) Pump Suction from Upper Surge Tank Isolation Valve 1C0573, 2C0573, 3C0573 B

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves are required to be locked open to provide suction to both of the MDEFW pumps from the Upper Surge Tank (UST).

When transferring MDEFW pump suction from the upper surge tanks to the hotwell, this valve is unlocked and shall be closed to provide a system boundary.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

These valves cannot be full stroke exercised at power conditions.

Stroking these valves at power operation would require removing both trains of the MDEFW system from service, which is not allowed by Technical Specifications.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed. The valves are tested closed during cold shutdown.

ON-C-0l Page 1 of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral ON-C-02 Motor Driven Emergency Feedwater (MDEFW) Pump Suction from Upper Surge Tank (UST) Check Valve 1 C0572, 2C0572, 3C0572 IST Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101/02 Rev. 26 This valve shall open to allow water to flow from the upper surge tanks to the MDEFW pumps.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996 Subsection ISTC. Open and close tests are not required to be performed at the same time if performed within the same interval.

Both MDEFW Pumps must be operated simultaneously in order to full' stroke the valve. Both MDEFW Pumps must be taken out of service in order to simultaneously operate the pumps. During power operation, Technical Specifications does not allow both MDEFW Pumps to be taken out of service simultaneously. Additionally, necessary test connections do not exist to support performance of a closure test.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Per OMa-1996 Subsection ISTC 4.5.2 (b), the valves are full stroked to the open position during cold shutdown to assure the safety function to open.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the capability to close.

Additionally, the valves are partially stroked to the open position every three months during power operation.

ON-C-02 Page 1 of 1 Section 6.1 Item Number:

Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Code Category:

ON-C-03 Motor Driven Emergency Feedwater (MDEFW) Pump Suction from Hotwell Check Valve 1 C0850, 2C0850, 3C0850, 1C0852, 2C0852, 3C0852 -

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 The valves shall open to allow water to flow from the condenser hotwell to the MDEFW pumps.

The valves shall be closed as a system boundary when the MDEFW pumps take suction from the Upper Surge Tank.

Verify proper valve movement to the open and closed position every three months as required per Oma-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing cannot be performed during normal unit operation since condenser vacuum must be broken to stroke these valves.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1 996 Subsection ISTC 4.5, the valves are fully stroked to the open and closed positions to verify the safety functions during cold shutdown conditions when condenser vacuum is broken or at refueling conditions.

ON-C-03 Page 1 of I Section 6.1 Item Number:

Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 ON-CC-01 Component Cooling Return Penetration Block Valves 1CC0007, 2CC0007, 3CC0007, 1CC0008, 2CC0008, 3CC0008 A

These valves shall be capable of closing to perform their Containment Isolation function.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Exercising these valves during power operation would isolate cooling water to the control rod drive mechanism and to the reactor coolant pumps which could potentially result in damage to thermal barriers and pump seals. In addition, closing these valves would cause over heating of the letdown fluid, which could lead to an automatic isolation of letdown flow, resulting in a loss of pressurizer level control and/or damage to the purification demineralizers.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown conditions, when the component cooling system is isolated.

ON-CC-01 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-CC-02 Component Cooling Penetration Check Valve 1 CCO020, 2CC0020, 3CC0020, 1 CC0024, 2CC0024, 3CC0024 1 CC0076, 2CC0076, 3CC0076, 1 CC0077, 2CC0077, 3CC0077 Code Category:

NC Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves shall be capable of closing to perform their Containment Isolation function.

Verify proper valve movement to the oper) and closed position every three months as required per OMa-1996 Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed position during power operation would isolate cooling water to the control rod drive mechanism, letdown coolers, and reactor coolant pumps which could potentially result in damage to thermal barriers and pump seals. Testing at each cold shutdown would require personnel to drain portions of the component cooling system and install test equipment. This would unnecessarily expose personnel to hazardous chemicals as well as generate excessive radioactive waste since the component cooling water contains chromates.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This altemative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON-CC-02 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-CF-01 Core Flood Tank Discharge Line Check Valve 1CF0011, 2CF0011, 3CF0011, 1CF0013, 2CF0013, 3CF0013 C

These valves normally prevent backflow from the RCS to the core flood tanks. These valves shall be capable of opening when RCS pressure drops below the pressure in the core flood tank so that the tank contents can be injected into the reactor vessel.

Verify proper valve movement to the open and closed position every three months as required per Oma-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the open position during power operation is not possible since the core flood tank pressure cannot be increased above RCS pressure during normal operation. The valves cannot be tested to the open position during cold shutdown due to the possibility of over pressurization and hydraulic shock to the reactor coolant system.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1996, Subsection ISTC is followed.

During each refueling outage, testing is performed at a lower than accident pressure. The test method utilizes nitrogen overpressure on the core flood tanks which are filled to normal Technical Specification level with the core flood tank outlet block valves closed. The outlet valves are opened while tank level and pressure data are recorded versus time.

This data is utilized to calculate a flow rate through the check valves and to determine the flow coefficient (Cv) of the check valves. This Cv is then compared to the required accident Cv to ensure that the valves are capable of passing the design basis accident flow and to ensure acceptable valve performance. Qualification of the calculations of the data is provided by independent review in accordance with the owner's Quality Assurance Program.

The full stroke close test will be performed by a leak test each refueling outage in accordance with OMa-1996 Subsection ISTC 4.5 which states that open and close tests need only be performed at an interval when it is practical to perform both tests.

ON-CF-01 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101/02 Rev. 26 ON-CF-02 Core Flood Tank and Low Pressure Injection Header Check Valve 1CF0012, 2CF0012, 3CF0012, 1CF0014, 2CF0014, 3CF0014 NC These valves normally prevent backf low from the RCS to the core flood tanks and the Low Pressure Injection System. In an emergency these valves 6pen to permit flow from the core flood tanks or the Low Pressure Injection System to the RCS.

Verify proper valve movement to the open and closed position every three months as required per Oma-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the open position during power operation is not possible since the core flood tank pressure cannot be increased above RCS pressure during normal operation. The valves cannot be tested to the open position during cold shutdown due to the possibility of over pressurization and hydraulic shock to the reactor coolant system.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1 996, Subsection ISTC is followed.

During each refueling outage, testing is performed at a lower than accident pressure. The test method utilizes nitrogen overpressure on the core flood tanks which are filled to normal Technical Specification level with the core flood tank outlet block valves closed. The outlet valves are opened while tank level and pressure data are recorded versus time.

This data is utilized to calculate a flow rate through the check valves and to determine the flow coefficient (Cv) of the check valves. This Cv is then compared to the required accident Cv to ensure that the valves are capable of passing the design basis accident flow and to ensure acceptable valve performance. Qualification of the calculations of the data is provided by independent review in accordance with the owner's Quality Assurance Program.

The full stroke close test will be performed by a leak test each refueling outage in accordance with OMa-1996 Subsection ISTC 4.5 which states that open and close tests need only be performed at an interval when it is practical to perform both tests.

ON-CF-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-CF-03 Core Flood Tank Nitrogen/Makeup Header Check Valve 1CF0042, 2CF0042, 3CF0042, 1CF0044, 2CF0044, 3CF0044 Code Category:

A/C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves shall be capable of closing to perform their containment isolation function.

Verify proper valve movement to the open and closed position every three months'as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same Interval.

Testing these valves to the closed position can only be accomplished by local leak rate testing. The only available pressurization path is inside the reactor building.

Making a reactor building entry at power exposes personnel to excessive risk to their safety as well as potentially excessive radiation exposure. Testing at each cold shutdown would require personnel to drain portions of the system and install test equipment.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON-CF-03 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 ON-CS-01 Quench Tank Recirculation Check Valve 1CS0011, 2CS0011, 3CS0011, 1CS0012, 2CS0012, 3CS0012 A/C These valves shall be capable of closing to perform their containment isolation function.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed position can only be accomplished by local leak rate testing since there is no means to simulate reverse flow in the line.

An altemative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "if no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON-CS-01 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

ON-CS-02 Pen 29 Thermal Overpressurization Reverse Flow Check Valve 1CS0197, 2CS01 97, 3CS0197 A/C This valve shall be capable of opening and relieving to prevent thermal overpressurization of Penetration #29 during a LOCA event. This valve shall be capable of closing to provide containment isolation for Penetration #29.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed position can only be accomplished by local leak rate testing since there is no means to simulate reverse flow in the line.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

7/01102 ON-CS-02 Rev. 26 Page 1 ofIl Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-01 OTSG Startup Control Valves 1 FDW0035, 2FDW0035, 3FDW0035 1 FDWO044, 2FDW0044, 3FDW0044 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These normally open valves close to provide feedwater isolation after a Main Steam Line Break in which overcooling is a concern.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

These valves are normally open to allow feedwater flow to continue through the startup line. Testing these valves would result in a feedwater transient, which could cause a reactor trip.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown conditions.

ON-FDW-01 Page 1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-FDW-02 Valve:

TDEFWP Discharge Header Check Valves 1FDW0311, 2FDW0311, 3FDWO311 1 FDW0312, 2FDW0312, 3FDW0312 Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 These valves close to preclude diversion of flow when the TDEFDW pump is not running and MDEFDW pumps are running.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater pumps must supply water to the steam generators in order to test these valves to their proper position. The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, testing these valves at power would create undue thermal stresses on the steam generator tubes and nozzles. In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.5 is followed.

Per OMa-1996 Subsection ISTC, the valves will be tested to their required open and closed safety positions during cold shutdown.

ON-FDW-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-03 Steam Generator Main Feedwater Control Valve 1 FDWO032, 2FDW0032, 3FDW0032 1 FDWO041, 2FDWO041, 3FDW0041 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101102 Rev. 26 These normally open valves must close to provide feedwater isolation after a Main Steam Line Break where overcooling is a concern.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves at power would disrupt the normal feedwater flow and steam generator level causing a plant transient and possible reactor trip.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown conditions.

ON-FDW-03 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-04 Main Feedwater Return to Emergency Feedwater Header Check Valve 1 FDW0039, 2FDW0039, 3FDW0039 1 FDW0432, 2FDW0432, 3FDW0432 Code Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 During an accident, these valves shall close or remain closed to preclude a diversion of emergency feedwater.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Due to system constraints, there is no means to verify these valves close upon cessation or reversal of flow. A test of the opening function can only be performed during a refueling outage. Testing these valves at power would disrupt the normal feedwater flow and steam generator level causing a plant transient and possible reactor trip. Testing at cold shutdown is not practicable as chemistry requirements are met just prior to plant start-up.

Therefore performing and restoring from this test becomes critical path and causes unnecessary delays to plant start-up.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every refueling outage.

ON-FDW-04 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-FDW-06 Valve:

Steam Generator Isolation Check Valves 1 FDW0232, 2FDW0232, 3FDW0232 1 FDW0233, 2FDW0233, 3FDW0233 Valve Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 C

These valves are normally closed and must open to supply emergency feedwater to the steam generators.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater pumps must supply water to the steam generators in order to test these valves to their proper open position.

The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, exercising these valves at power would create undue thermal stresses on the steam generator tubes and nozzles.

In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

Due to system design, no practical means exists for testing these valves to the closed position.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every cold shutdown.

ON-FDW-06 Page I of I Section 6.1 Item Number:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-07 Emergency Feedwater Header Check Valves 1FDW0317, 2FDW0317, 3FDW0317 1FDW0318, 2FDW0318, 3FDW0318 Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves are normally closed preventing backflow from the feedwater line to the emergency feedwater pump. In an accident, they open to allow flow from the emergency feedwater pump to the normal and emergency feedwater nozzles.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater pumps must supply water to the steam generators in order to test these valves to their proper open position.

The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, exercising these valves at power would create undue thermal stresses on the steam generator tubes and nozzles.

In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

Due to system design, no practical means exists for testing these valves to the closed position.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every cold shutdown.

ON-FDW-07 Page I of 1 Section 6.1

Oconee Units 1,2, and 3 Justification for Deferral Item Number:

ON-FDW-08 Valve:

Valve Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 Emergency Feedwater Inside Containment Penetration Check Valves 1 FDW0345, 2FDW0345, 3FDW0345 1 FDW0346, 2FDW0346, 3FDW0346 C

These valves are normally closed preventing backflow from the feedwater line to the emergency feedwater pump. in an accident, they open to allow flow from the emergency feedwater pump to the normal and emergency feedwater nozzles.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater pumps must supply water to the steam generators in order to test these valves to their proper open position.

The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, testing these valves at power would create undue thermal stresses on the steam generator tubes and nozzles. In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

Due to system design, no practical means exists for testing these valves to the closed position.

Per OMa-1 996 Subsection ISTM 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every cold shutdown.

ON-FDW-08 Page 1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-09 MDEFWP Normal Discharge Header Check Valves 1 FDW0373, 2FDW0373, 3FDW0373 1 FDW0383, 2FDW0383, 3FDW0383 Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves are normally closed preventing backflow from the feedwater line to the emergency feedwater pump. In an accident, they open to allow flow from the emergency feedwater pump to the normal and emergency feedwater nozzles.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater pumps must supply water to the steam generators in order to test these valves to their proper position. The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, testing these valves at power would create undue thermal stresses on the steam generator tubes and nozzles. In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

An alternative test frequency based on the guidelines the requirements within OMa-1 996 Subsection ISTC 4.5 is followed.

Per OMa-1996 Subsection ISTC, the valves will be tested to their required open and closed safety positions during cold shutdown.

ON-FDW-09 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-FDW-10 MDEFWP Minimum Flow Check Valves 1FDW0378, 2FDW0378, 3FDW0378 1FDW0388, 2FDW0388, 3FDW0388 Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves shall open when their respective pump's minimum flow path is opened by the pump's auto-recirculation control valve and flow is passing through the line.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Due to system design, no practical means exists for testing these valves to the closed position.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every quarter.

ON-FDW-10 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Valve Category:

ON-FDW-11 Emergency Feedwater Outside Containment Penetration Check Valves 1 FDW0442, 2FDW0442, 3FDW0442 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves are normally closed preventing backflow from the feedwater line to the emergency feedwater pump. In an accident, they open to allow flow from the emergency feedwater pump to the normal and emergency feedwater nozzles.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The Emergency Feedwater purfips must supply water to the steam generators in order to test these valves to their proper open position.

The Emergency feedwater pumps supply unheated condensate to the steam generators. Therefore, testing these valves at power would create undue thermal stresses on the steam generator tubes and nozzles. In addition, testing these valves by supplying the steam generators with unheated condensate would place the plant in a feedwater transient which could cause a reactor trip.

Due to system design, no practical means exists for testing these valves to the closed position.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every cold shutdown.

ON-FDW-1 I Page 1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 ON-FO-01 SSF Diesel Engine Fuel Oil Transfer Pump Discharge Check Valve OFO-50 C

This valve shall open to allow transfer of fuel oil from the Fuel Oil Storage Tank to the Fuel Oil Day Tank when the Fuel Oil Transfer Pump operates.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

This valve cannot be tested to the closed position at power conditions, cold shutdown conditions, or refueling conditions. The present piping configuration does not allow verification that the valve moves to the closed position. There are on test vents or drains to allow testing to the closed position. Testing to the closed position is impractical.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valve is sample disassembled once every refueling interval to assure the safety function to open as well as to assure the capability to close.

Additionally, the valve is stroked to the open position every three months.

ON-FO-01 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-HP-01 Letdown Line Outside Containment Isolation Valve 1HP0005, 2HP0005, 3HP0005 A

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves are open during normal unit power operation to allow letdown flow from the Reactor Coolant System. The valves shall close for containment isolation.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves at power operation will isolate letdown flow from the Reactor Coolant System. The resulting transient due to loss of volume and chemistry control could cause a reactor trip.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1 996 Subsection ISTC, the valves will be tested to the closed position during cold shutdown.

ON-HP-01 Page 1 of 1 Section 6.1 Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101/02 Rev. 26 ON-HP-02 Reactor Coolant Pump Seal Return Line Containment Isolation Valve 1HP0020, 2HP0020, 3HP0020, 1HP0021,2HP0021,3HP0021 A

These valves are open during normal unit power operation to align a flow path to return water that passes through the Reactor Coolant Pumps seals to the Letdown Storage Tank. The valves shall close for containment isolation.

Verify proper valve movement to the closed position every three months as required per Oma-1 996 Subsection ISTC 4.2.

These valves are containment isolation valves in a non-redundant flow path. Testing these valves to the closed position will result in an isolation of the RCP seal water return system. Such transients on the RCP seals should not be performed in order to maintain the long term health of the RCP seals.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1996 Subsection ISTC, the valves will be tested to the closed position during cold shutdown.

ON-HP-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-HP-03 HPI Train A Discharge Header Isolation Valve 1 HP0026, 2HP0026, 3HP0026 Valve:

Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07101/02 Rev. 26 The valves shall open to align the HPI Pump discharge header to the reactor vessel. The valve shall be capable of being throttled from the control room to limit HPI flow. This may be required to prevent runout of the HPI Pumps, assure adequate NPSHa during piggyback operation, or maintain the RCS pressure/temperature within subcooling limits to prevent Pressurized Thermal Shock of the RCS.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Valve alignments necessary to perform this testing would remove the warming flow from the reactor coolant system normal makeup flow nozzles. This would increase the number of thermal stress cycles on the makeup nozzles, which are restrictive over plant life.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1996 Subsection ISTC, the valves will be tested to the open and closed position during cold shutdown.

ON-HP-03 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-HP-04 HPI Pumps Discharge Line Crossover Header Valve 1HP0409, 2HP0409, 3HP0409, 1HP0410, 2HP0410, 3HP0410 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

01/31/99 Rev. 25 The valves shall open for HPI flow to be cross-connected in the event of a single failure during an accident. The valves shall be capable of being throttled from the control room to limit HPI flow. This may be required to prevent runout of the HPI Pumps, assure adequate NPSHa during piggyback operation, or maintain the RCS pressure/temperature within subcooling limits to prevent Pressurized Thermal Shock of the RCS.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

The testing of HP0409 would result in a thermal transient on the B Loop.

Likewise, if leakage occurred through HP0409 during testing of HP0410, a similar thermal transient would occur. This would increase the number of thermal stress cycles on the B Loop injection nozzles which are restricted over plant life.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1996 Subsection ISTC, the valves will be tested to the open and closed position during cold shutdown.

ON-HP-04 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-05 Letdown Storage Tank Outlet Header Check Valve 1 HP0097, 2HP0097, 3HP0097 A/C These valves shall be capable of opening to align the Letdown Storage Tank (LDST) to the suction header of the HPI Pumps after an accident.

This allows HPI Pump minimum flow to be recirculated through the LDST rather than being diverted to the radwaste system. These valves shall close to prevent backflow from HPI pump suction to the LDST during LPI to HPI "piggyback" operation.

Verify proper valve movement to the open and closed position every three months as required per Oma-1996 Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

The LDST provides the normal suction for the HPI pumps such that HP 97 is normally open. These valves are tested closed with the LPI to HPI "piggyback" operation.

'Piggyback" alignment to HPI can only be accomplished during cold shutdown due to reactivity concems at power operation associated with injecting highly borated water to the RCS.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5, the valves are tested to the open and closed positions during cold shutdown.

Additionally, the valves are tested to the open position every three months.

ON-HP-05 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-06 HPI Pump Recirculation Block Valve 1 HP0247, 2HP0247, 3HP0247 1HP0249, 2HP0249, 3HP0249 1 HP0251, 2HP0251, 3HP0251 A

The valves shall close to isolate HPI pump minimum flow recirculation lines during LPI to HPI "piggyback" operation to prevent excessive flow to the LDST during an accident.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves during power operation would remove minimum flow protection from the HPI pumps. Pump damage could occur if an idle pump started without adequate discharge flow or on loss of discharge flow to a running pump.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-HP-06 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 ON-HP-07 Letdown Cooler Outlet and Inside Containment Isolation Valve 1 HP0003, 2HP0003, 3HP0003, 1 HP0004, 2HP0004, 3HP0004 A

Valves shall close to isolate the letdown cooler for containment isolation.

Verify proper valve movement to the closed position every three months as required per OMa-1996 Subsection ISTC 4.2.

Testing these valves during power operation induces undesirable transients within the letdown coolers which could compromise integrity of the reactor coolant system pressure boundary.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves will be tested to the closed position during cold shutdown.

ON-HP-07 Pagel of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-HP-08 HPI Pumps Minimum Flow to the LDST Header Isolation Check Valve 1 HP0189, 2HP0189, 3HP0189 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 Normally, these valves are at least partially open during power operation since at least one HPI Pump's minimum flow, RCP seal return flow and RCS letdown flow is passing through the valve.

Assuming an accident and LOOP, the valves would likely close and have to reopen after emergency power is aligned to allow HPI minimum flow to be recirculated to the pump suction piping via the LDST.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

There is no existing flow instrumentation to monitor flow or cessation of flow through these valves.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the partially open position every refueling.

ON-HP-08 Page 1 of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-10 HPI Pump Emergency Supply (From the BWST) Check Valve 1HP0101, 2HP0101, 3HP0101, 1HP0102, 2HP0102, 3HP0102 NC These valves are closed during normal unit power operation since there is no flow from the BWST to the HPI Pump suction. The valves shall open to supply the HPI Pumps from the BWST whenever its associated isolation valve opens. The valves shall close to prevent reverse flow from the suction header to the BWST when HPI is aligned for piggyback operation.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Quarterly HPI pump tests utilize suction from the letdown storage tank.

These valves are located in piping, which contains highly borated water from the BWST. Testing these valves open would cause injection of highly borated water into the RCS, necessitating extensive cleanup. Late in core life injecting BWST water (>1800 ppm boron) would cause a rapid power transient and consequent reactor trip. Testing these valves open at cold shutdown could prevent reactor startup due to a relatively high boron concentration. In addition, testing these valves open at power or cold shutdown could cause overpressurization of the RCS.

Testing of these valves in the closed position is performed by leak rate testing of the valves. Adequate differential pressure is achieved during the LPI to HPI "piggyback" operation.

The LPI to HPI "piggyback" operation is limited to cold shutdown conditions.

Per OMa-1 996 Subsection ISTC 4.5. open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are tested to the open and closed position each refueling.

Additionally the valves are tested to the closed position and partially open position each cold shutdown.

ON-HP-10 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-11 HPI Pump Discharge Check Valve 1HP01 05, 2HP01 05, 3HP0105 1HP01 09, 2HP01 09, 3HP0109 1HP0113, 2HP0113, 3HP0113 C

These valves shall open as a result of its pump starting and delivering flow. The valves shall close to prevent reverse flow.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be tested at power or at cold shutdown due to the possibility of RCS overpressurization.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1 996 Subsection ISTC 4.5, the valves are full stroke exercised to the closed position every three months.

Additionally, the valves are tested to the partially open position every three months during quarterly pump testing.

ON-HP-1I Page1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

ON-HP-12 HPI Injection Line RCS Boundary Check Valve 1HP0486, 2HP0486, 3HP0486, 1HP0487, 2HP0487, 3HP0487 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 This valve shall open to pass flow in the forward direction to allow emergency HPI injection into the RCS as required. This valve shall close to limit the total RCS leakage into the HPI Injection and Tempering lines during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be tested open at power or during cold shutdown due to the possibility of RCS overpressurization.

Due to system design, testing to the closed position can only be accomplished by use of an extemal test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open and close.

Additionally, the valves are tested to the partially open position during cold shutdown. The valves are tested to the open position each refueling outage. During a refueling outage, the capability to adequately vent the RCS prevents the overpressurization of the RCS when full flow testing these valves.

ON-HP-12 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101102 Rev. 26 ON-HP-13 HPI Injection Line RCS Boundary Check Valve 1HP0488, 2HP0488, 3HP0488, 1HP0489, 2HP0489, 3HP0489 C

This valve shall open to pass flow in the forward direction to allow emergency HPI injection into the RCS as required.

In addition, the valves shall close to limit the total RCS leakage into the HPI Injection and Tempering lines during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tdsts are not required to be performed at the same'time if performed within the same interval.

These valves cannot be tested to the open position at power or during cold shutdown due to the possibility of RCS overpressurization.

Due to system design, testing to the closed position can only be accomplished by use of an extemal test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1 996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open and close.

Additionally, the valves are tested to the partially open position during cold shutdown. The valves are tested to the open position each refueling outage. During a refueling outage, the capability to adequately vent the RCS prevents the overpressurization of the RCS when full flow testing these valves.

ON-HP-13 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-HP-14 HPI Train B Injection Line Containment Isolation Check Valve 1HP01 88, 2HP01 88, 3HP0188 Valve:

Code Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101102 Rev. 26 These valves are closed during normal operation. In an accident, the valves shall open to provide emergency high pressure injection.

In addition, the valves shall close to limit the RCS leakage into the HPI Injection and Tempering lines during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves at power would result in a thermal transient on the B Loop. This would increase the number of thermal stress cycles on the B Loop injection nozzles which are restricted over plant life. Testing these valves to the open position at cold shutdown could overpressurize the RCS.

Due to system design, testing to the closed position can only be accomplished by use of an external test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open and close.

Additionally, the valves are tested to the partially open position during cold shutdown. The valves are tested to the open position each refueling outage. During a refueling outage, the capability to adequately vent the RCS prevents the overpressurization of the RCS when full flow testing these valves.

ON-HP-14 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-HP-15 HPI Train A Injection Line Containment Isolation Check Valve 1HP0194, 2HP0194, 3HP0194 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 In an accident, the valves shall open to provide high pressure injection.

In addition, the valve shall close to limit the RCS leakage into the HPI Injection and Tempering lines during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be tested open at power or during cold shutdown due to the possibility of RCS overpressurization.

Due to system design, testing to the closed position can only be accomplished by use of an external test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open and close.

Additionally, the valves are tested to the partially open position quarterly.

The valves are tested to the open position each Tefueling outage. During a refueling outage, the capability to adequately vent the RCS prevents the overpressurization of the RCS when full flow testing these valves.

ON-HP-15 Page 1 of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-HP-16 HPI Pump Minimum Flow Line Stop/Check Valve 1 HP0248, 1HP0250 2HP0248, 2HP0250 3HP0248, 3HP0250 Code Category:

A/C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 The valves shall open to pass HPI pump minimum recirculation flow.

The valves shall be substantially leak tight and capable of being closed during the piggyback alignment.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests* are not required to be performed at the same time if performed within the same interval.

No permanently installed flow insirumentation exists to measure pump recirculation flow.

Testing these valves closed during power operation would remove minimum flow protection from the HPI pumps. Pump damage could occur if an idle pump started without adequate discharge flow or on loss of discharge flow to a running pump.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC 4.5 is followed.

The valves are tested to the open position during each refueling outage via ultrasonic measurement techniques. This frequency is based on the guideline provided in NUREG-1482, section 4.1.4 which states that the "NRC has determined that the need to set up test equipment is adequate justification to defer testing until a refueling outage."

Although this section of the NUREG is specifically addressing the verification of closed check valves by leak testing, it is reasonable that the same justification would apply to installation of ultrasonic test equipment to verify forward flow testing.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests. The valves are tested to the open and closed position during each refueling outage.

Additionally, the valves are tested to the closed position during each cold shutdown.

ON-HP-16 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 ON-HP-17 Reactor Coolant Pump Seal Injection Line Inside Containment Isolation Check Valve 1HP0144, 2HP0144, 3HP0144, 1HP0145, 2HP0145, 3HP0145 1HP0146, 2HP0146, 3HP0146, 1HP0147, 2HP0147, 3HP0147 Reactor Coolant Pump Seal Injection Line Outside Containment Isolatiorn Check Valve 1HP0390, 2HP0454, 3HP0390, 1 HP0454, 2HP0457, 3HP0454 1HP0457, 2HP0389, 3HP0393, 1 HP0393, 2HP0390, 3HP0457 A/C These valves shall open to establish seal injection. These valves shall close for containment isolation.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed position during power operation will isolate reactor coolant pump seal injection which could result in RCP seal degradation.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC 4.5 is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "if no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

Additionally, these valves are tested to the open position every three months.

ON-HP-17 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-HP-19 Normal Charging Line, Tempering Supply Inside Containment Isolation Check Valve 1HP0254, 2HP0494, 3HP0254 Code Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07101102 Rev. 26 This vaive shall close to limit the total RCS leakage into the HPI Injection and Tempering lines during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Due to system design, testing to the closed position can only be accomplished by use of an external test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the full opening and closing functions of the valves.

ON-HP-19 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01102 Rev. 26 ON-HP-20 HPI Tempering line AL/A2 RCS Boundary Check Valve 1 HP0451, 2HP0451, 3HP0451 1 HP0453, 2HP0453, 3HP0453 C

This valve shall close to limit the total RCS leakage into the respective HPI Tempering line during an SSF event.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Due to system design, testing to the closed position can only be accomplished by use of an external test pump. Due to the hardship of installing such test equipment, ALARA concerns and complexity, it is not deemed practical to perform such a test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the full opening and closing functions of the valves.

ON-HP-20 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-21 Letdown Storage Tank Inlet Stop Check Valve 1HP0078, 2HP0078, 3HP0078 C

Normally, these valves are at least partially open during power operation since at least one HPI Pump's minimum flow, RCP seal return flow and RCS letdown flow is passing through the valve.

Assuming an accident and LOOP, the valves would likely close and have to reopen after emergency power is aligned to allow HPI minimum flow to be recirculated to the pump suction piping via the LDST.

Verify proper valve movement to the open and closed position every' three months as required per Oma-1996 Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves cannot be closed during power operation.

Closing the valves would isolate the operating HPI Pump's minimum flow, RCP seal return flow and RCS letdown flow to the LDST.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.5 is followed for the closed test.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests. The valves are tested to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every three months.

ON-HP-21 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 ON-HP-22 HPI Pump Minimum Flow Line Stop/Check Valve 1 HP0252 2HP0252 3HP0252 A/C The valves shall be substantially leak tight and capable of being closed during the piggyback alignment.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

No permanently installed flow instrumentation exists to measure pump recirculation flow.

Testing these valves closed during power operation would remove minimum flow protection from the HPI pumps. Pump damage could occur if an idle pump started without adequate discharge flow or on loss of discharge flow to a running pump.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1 996 Subsection ISTC 4.5 is followed.

The valves are verified to be tested to the open position during each refueling outage via ultrasonic measurement techniques. This frequency is based on the guideline provided in NUREG-1482, section 4.1.4 which states that the "NRC has determined that the need to set up test equipment is adequate justification to defer testing until a refueling outage." Although this section of the NUREG is specifically addressing the verification of closed check valves by leak testing, it is reasonable that the same justification would apply to installation of ultrasonic test equipment to verify forward flow testing.

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests. The valves are tested to the open and closed position during each refueling outage.

Additionally, the valves are tested to the closed position during each cold shutdown.

ON-HP-22 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-LP-01 Reactor Coolant System/Low Pressure Injection Isolation Valve 1LP0001, 2LP0001, 3LP0001 Low Pressure Injection Hot Leg Suction Isolation 1LP0002, 2LP0002, 3LP0002 B

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 The valve shall be capable of being opened after any LOCA to pass flow from the RCS hot leg to the containment sump or the suction of an operating LPI pump.

This flow prevents the formation of an unacceptably high concentration of boric acid in the reactor vessel for certain LOCAs.

Verify proper valve movement to the open position every three months as required per Oma-1 996 Subsection ISTC 4.2.

These valves are redundant pressure boundary isolation valves for the RCS. They open to permit flow from RCS decay heat drop line through LPI system for cooling, and back into RCS. The motor operators on these valves are not adequately sized to open the valves against the full RCS pressure differential. Any attempt to do so could result in damage to the motor operators since the protective torque switches are bypassed on the opening stroke. There is also risk of damage to LP0002 for the same reason, since there is no way to be certain that LP0001 has not leaked by enough to pressurize the upstream side of LP0002.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open position during cold shutdown.

ON-LP-01 Page 1 of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 ON-LP-02 Low Pressure Injection Header Check Valve 1LP0047, 2LP0047, 3LP0047, 1LP0048, 2LP0048, 3LP0048 NC The valve shall open when the LPI pumps are started and the LPI header isolation valves open so that LPI injection can occur.

As pressure isolation valves (PIVs), maximum allowable leakage for this valve is established within Technical Specifications. The valves are containment isolation valves for the LPI injection headers.

Verify propei valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

These valves open to permit flow from LPI system into RCS. During plant operation, aligning LPI pumps' suction headers to the RCS would result in overpressurization of LPI system. When taking suction from the BWST, the discharge pressure of the LPI pumps is insufficient to pass flow into the RCS through these valves. No alternate pressure source or flow path exists through which flow can be passed through these valves at power. Testing the valves in the closed position is limited to leak rate testing of the valves.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1996 Subsection ISTC 4.5 is followed.

The valves will be tested closed on a frequency consistent with Technical Specifications. Technical Specifications requires the valves to be leak rate tested each cold shutdown if the test has not been performed within the last nine months. This alternative is more conservative than the alternative documented within Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage".

The valves will be tested to the open position during cold shutdown in accordance with OMa-1996 Subsection IST-C 4.5 whichT states that open and close tests need only be performed at an interval when it is practical to perform both tests.

ON-LP-02 Page 1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

ON-LP-03 Post LOCA Boron Dilution Isolation 1LP0103, 2LP0103, 3LP0103, 1LP0104, 2LP0104, 3LP0104 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 The valves shall be capable of opening after any LOCA to align a flow path to direct fluid from the RCS hot leg to the containment sump. This prevents the formation of an unacceptably high concentration of boric acid in the reactor vessel for certain LOCAs.

Verify proper valve movement to the open position every three months as required per OMa-1996 Subsection ISTM 4.2.

These valves are redundant pressure boundary isolation valves for the RCS. They open to permit flow from RCS decay heat drop line into the RB emergency sump. LP0103 cannot be opened at power, since the motor operator is not designed to handle full RCS differential pressure.

Attempting to open LP01 03 at power would result in damage to the motor operators, since the protective torque switches are bypassed on the opening stroke. There is also risk of damage to LP0104 for the same reason, since there is no way to be certain that LP01 03 has not leaked by enough to pressurize the upstream side of LP0104.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTM 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves will be tested to the open position during cold shutdown.

ON-LP-03 Page 1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-LP-04 LPI Pump A Discharge Check Valve 1 LP0031, 2LP0031, 3LP0031 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07101/02 Rev. 26 The valve shall open so that the Low Pressure Injection pump can supply flow to the reactor vessel. The valve shall close to prevent back flow through the pump when the pump is not running and the LPI discharge headers are cross-connected.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed in the same interval.

To test the "A" Low Pressure Injection (LPI) Header at power, it must be recirculated to the BWST. The flow rate that can be obtained under test conditions is approximately 1000 GPM. Since there is no direct, external indication of valve position, there is no means for determining if the valves are tested to the full open position when using the test loop.

An alternative test frequency basbd on the requirements within OMa 1996 Subsection ISTC 4.5.4 is followed.

Per OMa-1 996 Subsection ISTC 4.5.4, the valves are tested to the open position during cold shutdown.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the closed position will be performed during cold shutdown.

Additionally, the valves are tested to the partially open position every three months. The valves are also tested to the closed position every three months.

ON-LP-04 Page I of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 ON-LP-06 LPI Cooler To HPI Pump Suction Header Check Valve 1LP0055, 2LP0055, 3LP0055, 1LP0057, 2LP0057, 3LP0057 C

The valhe shall be capable of opening when aligning the HPI pumps in piggyback mode to allow flow from LPI discharge header to the suction of the HPI pumps.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the open position during power operation would cause injection of highly borated water into the RCS, necessitating extensive cleanup. Late in core life, injecting highly borated water from the BWST would cause a rapid power transient and consequent reactor trip. Likewise, testing these valves open at cold shutdown could prevent reactor startup due to the injection of relatively high borated water. In addrtion, testing these valves to the open position at power or cold shutdown could cause overpressurization of the RCS.

Testing these valves to the closed position can only be accomplished by local leak rate testing since there is no other means to simulate reverse flow in the line.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.5 is followed.

Per OMa-1996 Subsection ISTC 4.5, the valves are tested to the open position each refueling. During refueling outages, adequate venting of the RCS is established to prevent overpressurization.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the closed position will be performed during refueling by performance of a leak rate test.

Addtionally, the valves are tested to the partially open position during cold shutdown.

ON-LP-06 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 ON-LP-07 LPI Header Isolation Valve 1LP0017, 2LP0017, 3LP0017, 1LP0018, 2LP0018, 3LP0018 B

These valves shall open and/or throttle to align the Low Pressure Injection Headers for emergency injection to the RCS.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTM 4.2.

These valves are a part of pressure boundary isolation between the RCS and LPI systems. Thus, the valves are kept normally closed as an additional measure to protect the LPI system from overpressurization (i.e. intersystem LOCA).

An altemative test frequency based or6 the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the open and closed position during cold shutdown.

ON-LP-07 Page 1 of 1 Section 6.1

Oconee Unit I Justification for Deferral ON-LP-08 Post-LOCA Alternate Boron Dilution Isolation Valve 1LP0105 Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 01/31199 Rev. 25 B

The valve shall be capable of being opened after any LOCA to align a flow path to direct fluid from the RCS hot leg to the containment sump.

This prevents the formation of an unacceptably high concentration of boric acid in the reactor vessel for certain LOCAs.

Verify proper valve movement to the open position every three months as required per OMa-1996 Subsection ISTC 4.2.

The valve and piping arrangement is unique to Unit-i. The LPI suction from the Reactor Coolant System (RCS) has a high point that may get vapor locked if used as a gravity ilo*, path (to mitigate boron precipitation concern post accident). Opening this valve will drain this portion of the LPI suction and introduce air into the system. Due to this system constraint, this valve must be kept closed in order to avoid damaging the LPI pump(s). Thid valve must only be opened when the system can be replenished properly and vented to ensure that the LPI suction from the RCS is maintained water solid. The RCS cannot replenish this line at power due to system pressure/temperature design limitations.

An altemative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valve is tested to the open position during cold shutdowin.

ON-LP-08 Page I of I Section 6.1 Item Number:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 ON-LP-09 BWST Supply to LPI Pump Check Valve 1LP0029, 2LP0029, 3LP0029, 1LP0030, 2LP0030, 3LP0030 NC These valves shall open to supply water from the BWST to the suction of the LPI and RBS pumps. These valves shall be capable of closing when swapping the suction of LPI Pumps from the BWST to the sump following an accident. This isolates flow from the Reactor Building Emergency Sump to the BWST.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed -position can only be accomplished by local leak rate testing since there is no means to simulate reverse flow in the line.

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration.

This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1 996 Subsection ISTC 4.5, open and -lose tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

Additionally, the valves are tested to the open position every three months.

ON-LP-09 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-LP-10 Reactor Building Sump Suction Isolation Valve 1 LP001 9, 2LP001 9, 3LP001 9, 1 LP0020, 2LP0020, 3LP0020 B

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 During an accident, these valves are remotely operated from the control room and shall open to align the suction of the LPI pumps to the containment recirculation sump. The valves shall be capable of being closed to mitigate the effect of a postulated passive failure in the downstream piping after it has been opened.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing valves LP-1 9 and LP-20 quarterly at power operation requires manual operator action should an ES signal occur, entry into 3 separate Tech Spec Action Statements affecting three systems, racking out pump breakers and opening valve breakers.

Additionally, quarterly testing of these valves results in draining inventory from the LPI and RBS suction from the BWST.

Consequently, this introduces air into the suction piping creating the potential for water hammers to occur on pump start-up (PIP-96-2347).

Therefore, an additional sequence of steps is prescribed to remove air from the system after valve stroking is complete but prior to exiting the applicable Tech Spec Action Statements. These steps include opening a vent valve, a drain valve, installing drain hose and manually operating either LP-21 or LP-22. These actions result in a significant increase in the length of time spent in the Tech Spec Action Statements.

With the exception of No Mode, opening these valves during shutdown has the ability to introduce air into the suction of ECCS pumps and increases risks of draining the RCS to the RBES.

Based on the hardship and risks incurred with quarterly stroking, testing of these valves is to be deferred to a refueling outage frequency such that testing can be performed in No Mode.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open and closed positions during refueling with the system drained during No Mode.

ON-LP-10 Page I of I Section 6.1 Item Number:

Valve:

Code Category:

Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 Oconee Units 1, 2, and 3 Justification for Deferral ON-LPSW-01 RCP Motor Bearing and Air Coolers Isolation Valve 1 LPS0006, 2LPS0006, 3LPS0006 1LPS0015, 2LPS0015, 3LPS0015 B

Valves shall close to provide containment isolation.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

These valves isolate flow to the reactor coolant pump motor coolers.

Closure of these valves during power operation would result in overheating and consequent damage to the reactor coolant pumps.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-LPSW-01 Page1 of 1 Section 6.1

Oconee Unit 3 Justification for Deferral Item Number:

ON-LPSW-02 Valve:

Non-Essential Header Isolation Valve 3LPS0139 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 Valve shall close prior to aligning LPSW to the LPI Coolers to ensure adequate LPSW pump NPSH and sufficient LPSW flow to the safety related loads.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Closure of this valve at power would interrupt cooling water to the main turbine oil tank. This would incease turbine oil temperature, which could lead to high vibrations, manual turbine trip, and/or turbine damage.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valve is tested to the closed position during cold shutdown.

ON-LPSW-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-LPSW-03 Valve:

LPSW Header to the HPI Pump Motor Bearing Cooling Jacket Supply Check Valve 1 LPSO1 48, 1 LPS01 51, 2LPS0503, 3LPS01 48, 3LPS0503 Code Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 These valves shall open to allow LPSW cooling water to the HPI pump motor bearing coolers.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Current system design does not provide adequate test connections to allow a closure test to be performed.

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTC 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position every three months.

ON-LPSW-03 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-LPSW-05 Valve:

RBCU Cooling Coil Outlet Isolation Valves 1LPS0018, 2LPS0018, 3LPS0018 1 LPS0021, 2LPS0021, 3LPS0021 1 LPS0024, 2LPS0024, 3LPS0024 IST Valve Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency B

These valves shall open to allow LPSW flow through the RBCU cooling coils.

Verify proper valve movement to the open position every three months as required per OMa-1 996 Subsection ISTC 4.2.

From a system review performed to meet the concerns addressed within Generic Letter 96-06, the potential for a water hammer within the LPSW piping with the outlet isolation valves closed was identified.

The operability evaluation performed to address the potential water hammer concluded that closing these valves at power operation is not allowed by Technical Specifications. Since these valves can not be (fully) closed, it is not possible to test these valves at power operation.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open position during cold shutdown.

ON-LPSW-05 Page 1 of 1 Section 6.1 Item Number:

07101102 Rev. 26

Oconee Units 1, 2, and 3 Justification for Deferral Code Category:

ON-MS-01 Main Turbine Stop Valves 1MS0102, 2MS0102, 3MS0102, 1MS0103, 2MS0103, 3MS0103 1MS0104, 2MS0104, 3MS0104, 1MS0105, 2MS0105,3MS0105 B

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 These hydraulically operated valves shall close to isolate the unaffected steam generator during a main steam line break. The main turbine stop valves limit the Reactor Coolant System cool down rate and resultant reactivity insertion following a main steam line break accident. The valves shall also close to isolate the affected steam generator following a steam generator tube rupture. For a number of events, failure to close could result in an uncontrolled cool down (and is unanalyzed). "

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Stroke time testing of these valves is performed by opening links, tripping the Control Rod Drive breakers and installation of a digital timer. These actions represent a unit trip hazard.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-MS-01 Page I of 1 Section 6.1 Item Number:

Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 ON-MS-02 Main Steam Bypass Valves 1MS0017, 2MS0017, 3MS0017, 1MS0026, 2MS0026, 3MS0026 B

These valves shall close to isolate the affected steam generator in the event of a Steam Generator Tube Rupture.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

These valves are not adequately sized to close at the Main Steam system conditions present at power operation.

Imposing this differential pressure on the valve would inhibit full closure based on the torque setting and damage the operator on the open stroke due to the torque switch being bypassed during opening.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-MS-02 Page 1 of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-MS-03 Main Steam to the Main Feedwater Pump Turbine Isolation Valve 1 MS0035, 2MS0035, 3MS0035, 1 MS0036, 2MS0036, 3MS0036 B

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 This valve shall close to isolate the affected steam generator in the event of a Steam Generator Tube Rupture.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves at power operation could cause a swing of main feedwater flow and a possible reactor runback or trip.

An altemative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1 996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-MS-03 Page I of 1 Section 6.1 Item Number:

Valve:

Code Category:

Oconee Units 1, 2, and 3 Justification for Deferral ON-MS-04 Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 Main Steam Supply to 2nd Stage Reheaters Isolation Valve 1 MS0076, 2MS0076, 3MS0076, 1 MS0079, 2MS0079, 3MS0079 B

These valves shall close to isolate the affected steam generator in the event of a Steam Generator Tube Rupture.

Verify proper valve movement to the closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves at power operation isolates the second stage reheater allowing lower temperature, higher moisture content steam to the Low Pressure Turbines. Unit response would be a loss of power generation, a secondary transient and increased thermal differences across the low pressure turbines steam inlet, possibly beyond the manufacturer recommendations.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-MS-04 Page 1 of I Section 6.1 Item Number:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-MS-07 Main Atmospheric Dump Block / Equalization Valves 1 MS01 53, 2MS0153, 3MS0153 1 MS01 55, 2MS01 55, 3MS0155 1 MS0161, 2MS0161, 3MS0161 1MS0163, 2MS0163, 3MS0163 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

.Test Alternative & Frequency 07101/02 Rev. 26 These chain wheel operated valves shall be opened when secondary side cooling is to be accomplished using the atmospheric dump valves.

Verify proper valve movement to th6 open position every three months as required per OMa-1 996 Subsection ISTC 4.2.

Testing these valves at power operation could cause a transient in main steam flow to the turbine resulting in a reactor runback or trip.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the closed position during cold shutdown.

ON-MS-07 Page I of I Section 6.1 Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

Valve:

Code Category:

Function:

ON-N-01 Core Flood Tank Nitrogen Supply Check Valve 1 N0129, 2N0129, 3N0129, 1 N0131, 2N0131, 3N0131 A/C These valves shall close for containment isolation.

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTM 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves to the closed position can only be accomplished by.

local leak rate testing since there is no other means to simulate reverse flow in the line.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa:1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration. This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON-N-01 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-N-02 Low Pressure Nitrogen Header Supply Check Valve 1N0246, 2N0246, 3N0246 Code Category:

NC These valves shall close for containment isolation.

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Exercising these valves to the closed safety position can only be accomplished by local leak rate testing since there is no other means to simulate reverse flow in the line.

An altemative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration. This alternative is consistent with Section 4.1.4 of NUREG-1 482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON4--02 Page I of 1 Section 6.1 Item Number:

Valve:

Function:

Item Number:

Valve:

Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 Oconee Units 1, 2, and 3 Justification for Deferral ON-PR-02 Penetration Room Filter Train Inlet Check Valve 1PRO115, 2PR0115, 3PR0115 1PRO116, 2PR0116, 3PR0116 C

These valves shall open when their respective PRVS fan starts.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

System design prohibits testing these valves in the closed direction.

Per OMa-11996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Per OMa-1996 Subsection ISTM 4.5.4 (c), the valves are sample disassembled during refueling to assure the safety function to open as well as to assure the capability to close.

Additionally, the valves are tested to the open position quarterly.

ON-PR-01 Page1 of I Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-RC-02 Pressurizer Spray 1 RC0001, 2RC0001, 3RC0001 Code Category:

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 B

These valves shall be capable of opening and closing as one means of reducing RCS pressure following a Steam Generator Tube Rupture.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTM 4.2.

Testing these valves open above cold shutdown conditions will cause unnecessary reactor coolant system pressure transients.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open and closed positions during cold shutdown.

ON-RC-02 Page 1 of 1 Section 6.1 Item Number:

Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-RC-04 Pressurizer Power Operated Relief Valve (PORV) 1 RC0066, 2RC0066, 3RC0066 Valve:

IST Valve Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 These valves shall be capable of opening and closing to provide one train of LTOP Protection.

These valves shall be capable of being opened and closed from the control room to provide an RCS vent path.

These valves shall be capable of being closed during a design basis event. These valves could be opened following a design basis event and reclosure could be required to isolate the RCS pressure boundary.

These valves shall be capable of opening and closing as one means of reducing RCS pressure following a Steam Generator Tube Rupture.

Verify proper valve movement to the open and closed positions every three months as required per OMa-1 996 Subsection ISTC 4.2.

Per NUREG-1482 Section 4.4.1, the NRC recognized that the PORVs have shown a high probability of sticking open and are not needed for overpressure protection during power operation. The NRC has deemed therefore, quarterly testing at power operation "not practical".

An alternative test frequency based on the guidelines within NUREG 1482 and the requirements within OMa-1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open and closed positions during cold shutdown.

ON-FRC-04 Page 1 of 1 Section 6.1

Oconee Units 1,2, and 3 Justification for Deferral Item Number:

Valve:

Code'Category:

ON-RC-05 Pen 5b Thermal Overpressurization Reverse Flow Check Valves 1 RC0207; 2RC0207; 3RC0207 1 RC0208; 2RC0208; 3RC0208 C

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency:

07/01/02 Rev. 26 These valves shall be capable of opening and relieving back to the RCS to prevent thermal overpressurization of Penetration #5b during a Loss of Coolant Accident.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing these valves in the open and close direction is performed during local leak rate testing of Penetration 5b since there is no means to simulate forward or reverse flow in the line.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration. This alternative is consistent with Section 4.1.4 of NUREG-1482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage."

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

ON-RC-05 Page I of I Section 6.1

Oconee Units 1, 2, and 3 Item Number:

Valve:

Justification for Deferral ON-RX-01 Reactor Vessel Internal Vent Valves 1 RC01 RX, 2RC02RX, 3RC03RX IST Valve Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 1

07101102 Rev. 26 These valves shall open when the pressure in the core exit plenum is above the pressure in the core downcomer region. This function reduces the pressure in the core exit plenum during postulated cold leg breaks and is required to assure an adequate amount of ECCS water reaches the fuel. There are eight 14" diameter check valves mounted in the Core Support Shield that effectively separates the core outlet plenum from the inlet nozzles and downcomer.

These valves are normally closed and required to remain closed during normal operation and for postulated hot leg breaks since reverse flow during these modes would bypass the core.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

During power operation or cold shutdown conditions, there are no means to test these valves. The reactor vessel head must be removed in order to test these valves to the open and closed positions.

Per NUREG-1482 guidelines and OMa-1996 Subsection ISTC 4.5 requirements, the valves are tested to the open and close positions each refueling outage.

Each refueling outage the reactor vessel head is removed allowing the valves to be tested. The valves are tested by measuring the forces required to open the valves. Acceptance criteria for the forces required to open the valves is based on accident analyses.

ON-RX-01 Page I of 1 Section 6.1

Oconee Units 1, 2, and 3 Justification for Deferral ON-SSF-01 SSF Steam Generator Feedwater Control Valve SSF-1CCW0269, SSF-2CCW0269, SSF-3CCW0269 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 In an SSF emergency these valves can be throttled open from SSF Control Room to allow Auxiliary Feedwater from several sources to feed the "A" Steam Generator.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996 Subsection ISTC 4.2.

During power operation, Technical Specifications require emergency, feedwater train separation. Testing these valves at power would violate Technical Specifications.

An alternative test frequency based on the requirements within OMa 1996 Subsection ISTC 4.2 is followed.

Per OMa-1996 Subsection ISTC 4.2, the valves are tested to the open and closed positions during cold shutdown.

ON-SSF-01 Page I of I Section 6.1 Item Number:

Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-SSF-02 RC Makeup to RCP, HPI Boundary Check SSF-1 HP0399, SSF-2HP0399, SSF-3HP0399 SSF-1 HP0400, SSF-2HP0400, SSF-3HP0400 SSF-1 HP0401, SSF-2HP0401, SSF-3HP0401 SSF-1 HP0402, SSF-2HP0402, SSF-3HP0402 Code Category:

C Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01/02 Rev. 26 In an SSF emergency these valves open to allow flow from the RC Makeup System to the RC Pump Seal Supply.

Verify proper valve movement to the open and closed position every three months as required per OMa-1996, Subsection ISTC 4.5. Open and close tests are not required to be performed at the same time if performed within the same interval.

Testing of these valves at Power Operation would result in injecting Spent Fuel Pool Water into the RC Pump Seals. This could result in Power Transients, Uncontrolled Reactivity Changes, Reactor Trips or Extensive Cleanup Requirements, particularly near the end of cycle.

Testing these valves to the closed position can only be accomplished by local leak rate testing since there is no other means to simulate reverse flow in the line.

An alternative test method based on the guidelines within NUREG-1482 and the requirements within OMa-1996 Subsection ISTC is followed for the closure test. The valves are tested in the closed position each refueling outage during the local leak rate test for each penetration. This alternative is consistent with Section 4.1.4 of NUREG-1 482 which states, "If no other practical means is available, it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each reactor refueling outage...The NRC has determined that the need to set up [leak rate] test equipment is adequate justification to defer backf low testing of a check valve until a refueling outage."

Per OMa-1 996 Subsection ISTC 4.5, open and close tests need only be performed at an interval when it is practical to perform both tests.

Therefore, the test to the open position will be performed each refueling outage.

Additionally, the valves are tested to the open position each cold shutdown.

ON-SSF-02 Page 1 of I Section 6.1 Valve:

Oconee Units 1, 2, and 3 Justification for Deferral Item Number:

ON-SSF-03 RC Make Up Discharge to RC Pump Seals Block SSF-1 HP0398, SSF-2HP0398, SSF-3HP0398 Code Category:

B Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 These valves are normally closed to prevent Spent Fuel Pool Flow from the RC Makeup System to the RC Pump Seals. In an SSF emergency, they open on command from the SSF to allow the RC Makeup System to supply emergency RC Pump seal water.

Verify proper valve movement to the open position every three months as required per OMa-1 996, Subsection ISTC 4.2.

Testing these valves could result in overpressurization of the SSF RC Makeup pump suction piping should leakage from the HPI system exist past the downstream check valves.

An alternative test frequency based on the requirements within OMa 1996, Subsection ISTC 4.2 is followed.

Per OMa-1996, Subsection ISTC 4.2, the valves are tested to the open position during cold shutdown.

ON-SSF-03 Page I of 1 Section 6.1 Valve:

Oconee Units 1, 2, and 3 Justification for Deferral ON-SSF-04 RCS Letdown to Spent Fuel Pool Inside Containment Isolation SSF-1HP0426, SSF-2HP0426, SSF-3HP0426 A

Function:

Test Requirement:

Basis for Deferral:

Test Alternative & Frequency 07/01102 Rev. 26 During an SSF Event, these valves shall be capable of opening, and closing as needed to control flow through their corresponding Unit's SSF RC letdown line so that pressurizer level is maintained within an acceptable range.

Verify proper valve movement to the open and closed position every three months as required per OMa-1 996, Subsection ISTC 4.2.

This valve is the first normally closed valve from the reactor coolant system. While this valve is open, any leakage past the second boundary would result in a loss of reactor coolant to the Spent Fuel Pool.

An alternative test frequency based on the requirements within OMa 1996, Subsection ISTC 4.2.

Per OMa-1996, Subsection ISTM 4.2, the valves are tested to the open and closed positions during cold shutdown.

ON-SSF-04 Page I of 1 Section 6.1 Item Number:

Valve:

Code Category:

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ACTIVITY DESCRIPTION Revision 26 to the ASME Section XI Inservice Testing Program for Oconee Nuclear Station Units 1, 2, and 3, is hereby submitted.

Oconee Nuclear Station is currently beginning its Fourth Ten Year Interval effective July 1, 2002. Program updates are made as dictated by additions, deletions, andldr revisions to design basis documents (DBDs), design calculations, and physical modifications to the plant. In addition to the required 120 month update, the Pump and Valve Inservice Test Program Manual is updated and submitted to the NRC when a sufficient number of changes to the IST Program have been made. Since the IST Program is constantly updated, this submittal represents a snapshot in time, on the date it was printed.

The effective date for this submittal is July 1, 2002. This submittal documents the ONS upgrade to the ASME Boiler and Pressure Vessel Code 1995 edition including the 1996 addenda. Oconee Units 1, 2, and 3 ASME Inservice Testing Program includes both format and content changes. Several format changes are being made to align with recommendations in NUREG 1482 (Guidelines for Inservice Testing at Nuclear Power Plants). The changes made since the last submittal are summarized as follows:

General and/or Editorial Changes Pump Changes Valve Changes Detailed Description of Changes Relief Requests Justification for Deferrals VALVE INSERVICE TESTING GENERAL DATA SAll Justifications for Deferral and Relief Requests have been revised to reflect the new ASME Code editions. Where content of the Deferrals or Relief Requests have been significantly modified, the information is captured under the appropriate sections within this document.

Page I of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ABBREVIATION CHANGES None PUMPS - ADDED TO OCONEE INSERVICE TESING PROGRAM The following pumps have been added to the Oconee Inservice Testing Program:

Pump System Change Document No revisions PUMPS - REMOVED FROM OCONEE INSERVICE TESTING PROGRAM The following pumps have been deleted from the Oconee Inservice Testing Program:

Pump System Change Document No revisions PUMPS - TRANSFERRED TO OCONEE INSERVICE TESING PROGRAM The following pumps have been transferred from Oconee Supplemental Appendix B Program and are now tested in the Oconee Inservice Testing Program:

Pump System Change Document No revisions PUMPS - TRANSFERRED TO OCONEE SUPPLEMENTAL APPENDIX B PROGRAM The following pumps have been transferred from Oconee Inservice Testing Program and are now tested in the Supplemental Appendix B Program:

Pump 2ESVPU0001 2ESVPU0002 2ESVPU0003 3ESVPU0001 3ESVPU0002 3ESVPU0003 System Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Change Document NRC Correspondence NRC Correspondence NRC Correspondence NRC Correspondence NRC Correspondence NRC Correspondence Page 2 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 VALVES - ADDED TO OCONEE INSERVICE TESING PROGRAM The following valves have been added to the Oconee Inservice Testing Program:

Valve 2SF0125 3SF0125 ISF0125 IC0152 2C0152 3C0152 1C0153 2C0153 3C0153 IC0158 2CO158 3C0158 IC0160 2C0160 3CO 160 I HP0023 2HP0023 3HP0023 ICCO168 2CCO 168 3CCO168 ILP0006 2LP0006 3LP0006 ILP0007 2LP0007 3LP0007 ILP0008 2LP0008 3LP0008 ILP001 I 2LP001I 1LP0013 2LP0013 System SSF RC Makeup SSF RC Makeup SSF RC Makeup Condensate Condensate Condensate Condensate Condensate Condensate Condensate Condensate Condensate Condensate Condensate Condensate High Pressure Injection High Pressure Injection High Pressure Injection Component Cooling Component Cooling Component Cooling Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Page 3 of 23 Effective 7/01/02 Change Document ONOE-10017 ONOE-10932 ONOE-10714 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ILP0069 2LP0069 3LP0092 3LP0093 1CF0005 2CF0005 3CF0005 1CF0006 2CF0006 3CF0006 ISF0127 2SF0127 3SF0127 ISF0128 2SF0128 3SF0128 1SF0126 2SF0126 3SF0126 ISF0129 2SF0129 3SF0129 IHP0935 2HP0935 3HP0935 1HP0934 2HP0934 3HP0934 I

HP0936 2HP0936 3HP0936 ICF0061 2CF0061 3CF0061 1CS0197 2CS0197 3CS0197 IFDW0582 Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Core Flood Core Flood Core Flood Core Flood Core Flood Core Flood Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel Spent Fuel High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection Core Flood Core Flood Core Flood Coolant Storage Coolant Storage Coolant Storage Feedwater PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 Page 4 of 23 Effective 7/0!02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 2FDW0582 3FDW0582 1FDW0583 2FDW0583 3FDW0583 IFDW0584 2FDW0584 3FDW0584 1FDW0585 2FDW0585 3FDW0585 1RC0207 2RC0207 3RC0207 1RC0208 2RC0208 3RC0208 I RC0206 2RC0206 3RC0206 ILPS0016 2LPS0016 3LPS0016 ILPS0019 2LPS0019 3LPS0019 ILPS0022 2LPS0022 3LPS0022 OLPS0001 OLPS0002 OLPS0003 3LPS0120 3LPS0123 IBS0003 2BS0003 3BS0003 IBS0004 Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Building Spray Building Spray Building Spray Building Spray Page 5 of 23 Effective 7/01/02 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 NSM-ON-x3043 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 2BS0004 3BS0004 1HP0098 2HP0098 3HP0098 1HP01 15 2HPO115 3HPO0115 IESV0001 IESV0002 IESV0018 IESV0019 1ESV0026 1ESV0027 1ESV0028 1ESV0029 ISSWO155 1SSWO156 ISSW0157 2HP0457 IAG0006 2AG0006 I AGO007 2AG0007 2CF0034 2CF0035 2CF0036 2CF0037 3CF0034 3CF0035 3CF0036 3CF0037 I HP0254 3HP0254 2HP0494 IHP0451 2HP0451 3HP0451 Building Spray Building Spray High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Essential Siphon Vacuum Siphon Seal Water Siphon Seal Water Siphon Seal Water High Pressure Injection Governor Air Governor Air Governor Air Governor Air Core Flood Core Flood Core Flood Core Flood Core Flood Core Flood Core Flood Core Flood High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection Page 6 of 23 Effective 7/01/02 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-12932 NSM-ON-12932 NSM-ON-12932 ONOE-14392 ONOE-8820 ONOE-8819 ONOE-8820 ONOE-8819 ONOE-13628 ONOE-13628 ONOE-13628 ONOE-13628 ONOE-13629 ONOE-1 3629 ONOE-1 3629 ONOE-13629 ONOE-10590 ONOE-10590 ONOE-10590 ONOE-10590 ONOE-10590 ONOE-10590

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 High Pressure Injection High Pressure Injection High Pressure Injection Demineralized Water Demineralized Water Demnineralized Water Siphon Sealing Water ONOE-10590 ONOE-10590 ONOE-10590 ONOE-14486 ONOE-14487 ONOE-14488 ONOE-12932 Page 7 of 23 Effective 7101/02 1HP0453 2HP0453 3HP0453 1DW0539 2DW0539 3DW0539 0SSW0080

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 VALVES - REMOVED FROM OCONEE INSERVICE TESTING PROGRAM The following valves have been deleted from the Oconee Inservice Testing Program:

Valve 1FW0064 2FW0064 3FW0064 1FW0065 2FW0065 3FW0065 IDWO155 IDWO156 1PROO61 2PR0061 3PR0061 2HP0286 1FDWO105 2FDWO105 3FDWO105 1FDWO107 2FDWO107 3FDWO107 IAG-0004 2AG-0004 1 HP-304 I CF0007 2CF0007 3CF0007 IPR0069 2PR0069 3PR0069 IPROO70 2PR0070 3PR0070 1 HP0363 2HP0363 3HP0363 System Filtered Water Filtered Water Filtered Water Filtered Water Filtered Water Filtered Water Demin Water Demin Water Purge Purge Purge High Pressure Injection Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Governor Air Governor Air High Pressure Injection Core Flood Core Flood Core Flood Purge Purge Purge Purge Purge Purge High Pressure Injection High Pressure Injection High Pressure Injection Page 8 of 23 Effective 7/01/02 Change Document ONOE-1 1283 ONOE-1 1275 ONOE-10972 ONOE-1 1283 ONOE-1 1275 ONOE-10972 NSM-ON-13043 NSM-ON-13043 PIP 99-3533 PIP 99-3533 PIP 99-3533 ONOE-14392 ONOE-10146 ONOE-10146 ONOE-10146 ONOE-10146 ONOE-10146 ONOE-10146 ONOE-8820 ONOE-8819 NSM-ON-13066 SLC 16.6.1 (Change 2000-08); ONOE-16493 SLC 16.6.1 (Change 2000-08); ONOE-16493 SLC 16.6.1 (Change 2000-08); ONOE-16493 SLC 16.6.10 (Change 2001-12); ONOE-16548 SLC 16.6.10 (Change 2001-12); ONOE-16548 SLC 16.6.10 (Change 2001-12); ONOE-.1.6548 SLC 16.6.10 (Change 2001-12); ONOE-16548 SLC 16.6.10 (Change 2001-12); ONOE-16548 SLC 16.6.10 (Change 2001-12); ONOE-16548 ONOE-16502 ONOE-16502 ONOE-16502

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 I HP0364 2HP0364 3HP0364 1LPS0309 3LPS0309 ILPS0310 3LPS0310 ILPS0312 3LPS0312 1LPS0313 3LPS0313 1LPS0315 3LPS0315 1LPS0316 3LPS0316 1LPS0318 3LPS0318 1LPS0319 3LPS0319 1PRO121 1 PRO 127 IPR0136 IPRO137 I

PRO 123 IPRO 124 1PRO129 IPRO130 2PRO121 2PRO127 2PR0136 2PRO1 37 2PR0123 2PRO124 2PR0129 2PR0130 3PRO121 3PR0127 3PRO136 High Pressure Injection High Pressure Injection High Pressure Injection Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Watet:

Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Purge Page 9 of 23 Effective 7/01/02 ONOE-16502 ONOE-16502 ONOE-16502 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-16293 ONOE-16034 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-1 6548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548 ONOE-17007 / ONOE-16548

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 3PR0137 Purge ONOE-17007 / ONOE-16548 3PR0123 Purge ONOE-17007 / ONOE-16548 3PR0124 Purge ONOE-17007 / ONOE-16548 3PR0129 Purge ONOE-17007 / ONOE-16548 3PR0130 Purge ONOE-17007 / ONOE-16548 VALVES - TRANSFERRED TO OCONEE INSERVICE TESING PROGRAM The following valves have been transferred from Oconee Supplemental Appendix B Program and are now tested in the Oconee Inservice Testing Program:

System Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Low Pressure Service Water Core Flood Core Flood Core Flood Core Flood Core Flood Core Flood Condensate Condensate Condensate Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Change Document ONOE-10903 ONOE-10904 ONOE-12417 ONOE-12419 ONOE-1 1440 ONOE-11441 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 Page 10 of 23 Effective 7/01/02 Valve 3LPS0516 3LPS0525 1LPS0516 I LPS0525 2LPS0516 2LPS0525 I CFOOO I 2CF0001 3CFOOOI I CF0002 2CF0002 3CF0002 IC0156 2C0156 3C0156 1FDW0368 2FDW0368 3FDW0368 IFDW0369 2FDW0369 3FDW0369 IFDW0372 2FDW0372 3FDW0372

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 IFDW0382 2FDW0382 3FDW0382 ILP0005 2LP0005 3LP0005 1LP0003 1MS0153 2MS0153 3MS0153 1MS0155 2MS0155 3MS0155 1MS0161 2MS0161 3MS0161 1MS0163 2MS0163 3MS0163 Feedwater Feedwater Feedwater Low Pressure Injection Low Pressure Injection Low Pressure Injection Low Pressure Injection Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam VALVES - TRANSFERRED TO OCONEE SUPPLEMENTAL APPENDIX B PROGRAM The following valves have been transferred from Oconee Inservice testing program and are now tested in the Oconee Supplemental Appendix B Program:

System Change Document Main Steam Main Steam Main Steam Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater ONOE-12546 ONOE-12546 ONOE-12546 ONOE-12882 ONOE-12882 ONOE-12882 ONOE-12882 ONOE-12882 ONOE-12882 Page I 1 of 23 Effective 7/01/02 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 PIP 98-3826 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 Valve 1 MS0094 2MS0094 3MS0094 IFDWO033 2FDW0033 3FDW0033 1FDWO042 2FDW0042 3FDW0042

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 1CCWO001o ICCWO002 1CCWO003 1CCW0004 1CCWO005 1CCWO006 2CCW0007 3CCW0093 1FDW0037 2FDW0037 3FDW0037 IFDWO046 2FDW0046 3FDW0046 1MS0083 2MS0083 3MS0083 1MS0085 2MS0085 3MS0085 IMS0087 2MS0087 3MS0087 1MS0091 2MS0091 3MS0091 IAS0039 2AS0039 3AS0039 IHP0043 2HP0043 3HP0043 1HP0055 2HP0055 3HP0055 IHP0056 2HP0056 3HP0056 Condenser Circulating Water Condenser Circulating Water Condenser Circulating Water Condenser Circulating Water Condenser Circulating Water Condenser Circulating Water Condenser Circulating Watei" Condenser Circulating Water Feedwater Feedwater Feedwater Feedwater Feedwater Feedwater Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Main Steam Aux Steam Aux Steam Aux Steam High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection Page 12 of 23 Effective 7101/02 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 NSM-ON-13000 ONOE-13940 ONOE-13940 ONOE-13940 ONOE-13940 ONOE-13940 ONOE-13940 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16325 ONOE-16326 ONOE-16326 ONOE-16326 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 1HP0071 2HP0071 3HP0071 1HP0073 2HP0073 3HP0073 1HP0076 2HP0076 3HP0076 IHP0302 2HP0302 3HP0302 ODA0003 ODA0008 ODA0013 ODA0018 0DA0025 0DA0026 0DA0027 0DA0028 ODA003 1 0DA0032 0DA0033 0DA0034 0DA0037 0DA0038 0DA0039 ODA0040 0DA0043 0DA0044 0DA0045 0DA0046 0DJW0001 ODJW0003 ODJW0005 ODJW0006 0DLO.0001 ODLOO002 High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection High Pressure Injection Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Starting Air Diesel Jacket Water Diesel Jacket Water Diesel Jacket Water Diesel Jacket Water Diesel Lube Oil Diesel Lube Oil ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 ONOE-16412 Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Page 13 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ODLOO006 0DLO0007 ODLOO008 ODLOO009 0DLO0010 ODLOO014 ODLOO015 ODLOO016 0F00078 0F00079 OF00080 0F00081 0F00082 0F00083 0F00084 0F00089 0F00090 0F00091 0F00092 0F00093 0F00094 0F00095 IOGO011 20G0011 10GO014 20G0014 10GO017 20G0017 1LP0028 2LP0028 3LP0028 1LWD0099 2LWD0099 3LWD0099 ILWD0103 2LWD0103 3LWD0103 ISF0060 Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Lube Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Diesel Fuel Oil Keowee Governor Oil Keowee Governor Oil Keowee Governor Oil Keowee Governor Oil Keowee Governor Oil Keowee Governor Oil Low Pressure Injection Low Pressure Injection Low Pressure Injection Liquid Waste Disposal Liquid Waste Disposal Liquid Waste Disposal Liquid Waste Disposal Liquid Waste Disposal Liquid Waste Disposal Spent Fuel System Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Upgrade to OMa-1996; skid mounted component Per OSS-0254.00-00-1028 Per OSS-0254.00-00-1028 Per OSS-0254.00-00-1028 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS4)254.00-00-4001 Page 14 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 Spent Fuel System Spent Fuel System Spent Fuel System Spent Fuel System Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 Per OSS-0254.00-00-4001 VALVES - EDITORIAL CHANGES System Change Document No revisions DETAILED DESCRIPTION OF CHANGES Change Document NSM-ON-x3043 NSM-ON-13000 NSM-ON-12932 NSM-ON-13066 Description of Change Various penetrations were modified in order to provide thermal overpressure relief protection based on Generic Letter 96-06.

The Oconee Service Water Project modified the service water system by the addition of safety related equipment to ensure that siphon flow is maintained during a design basis accident. With this modification, the current design basis function for various service water equipment was revised.

Replaced CCW Pumps seal and bearing lubrication and motor oil cooler supply water piping.

Replaced Unit I Westinghouse RCP Seals with Bingham cartridge seals. This modification eliminated the need for IHP-304.

Page IS of 23 Effective 7/01/02 3SF0060 1SF0061 2SF0061 3SF0061 Valve

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ONOE-10714 ONOE-10017 ONOE-10932 ONOE-10903 ONOE-10904 ONOE-1 1440 ONOE-1 1441 ONOE-1 1283 ONOE-l 1275 ONOE-10972 ONOE-8819 ONOE-8820 ONOE-12417 ONOE-12419 ONOE-12546 ONOE-12882 ONOE-14392 ONOE-10146 ONOE-13628 ONOE-13629 ONOE-10590 ONOE-14486 ONOE-14487 Relief Valve 1SF-125 was added to provide pressure locking protection to the bonnet of RC Makeup pump suction valve 1 SF-97.

Relief Valve 2SF-125 was added to provide pressure locking protection to the bonnet of RC Makeup pump suction valve 2SF-97.

Relief Valve 3SF-125 was added to provide pressure locking protection to the bonnet of RC Makeup pump suction valve 3SF-97.

Valve 3LPS-516 was upgraded from non-ISI to ISI Class C. Therefore, the valve met the scope of the IST program.

Valve 3LPS-525 was upgraded from non-ISI to ISI Class C. Therefore, the valve met the scope of the IST program.

Valve 2LPS-525 was upgraded from non-ISI to ISI Class C. Therefore, the valve met the scope of the IST program.

Valve 2LPS-516 was upgraded from non-ISI to ISI Class C.. Therefore, the valve met the scope of the IST program.

Remove the Filtered Water connection in Unit I Reactor Building by cutting and capping pipe at Pen #46.

Remove the Filtered Water connection in Unit 2 Reactor Building by cutting and capping pipe at Pen #46.

Remove the Filtered Water connection in Unit 3 Reactor Building by cutting and capping pipe at Pen #46.

Replaced 2AG0004 Relief Valve with Relief Valves 2AG0006 and 2AG0007 for redundancy to allow testing of relief valves during unit operation.

Replaced IAGO004 Relief Valve with Relief Valves IAGO006 and IAGO007 for redundancy to allow testing of relief valves during unit operation.

Replace ILPSVA0516. Piping will be upgraded to class F by minor modification ONOE-12107.

ReplaceILPSVA0525. Piping will be upgraded to class F by minor modification ONOE-12107.

The modification revised design basis documents to reflect that MS-94 does not have an active function for accident mitigation.

The modification revised the design basis documents to refl6ct that FDW-33 and FDW-42 do not have an active accident mitigation function.

Modification replaced 2HP-286 with 2HP-457.

Modification documented that 1/2/3FDW-105 and 1/2/3FDW-107 are not active and not required for containment isolation.

Modification added test connections to allow leak rate testing of Unit 2 Penetration 39a.

Modification added test connections to allow leak rate testing ofiflit 3 Penetration 39a.

Modification revised the SSF DBD and the HPI DBD to specify an active to close function for valves 1/2/3HP0451 and 1/2/3HP0453.

Modification added relief valve 1 DW0539 for thermal overpressure protection for Penetration 55..

Modification added relief valve 2DW0539 for thermal overpressure protection for Penetration 55.

Page 16 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ONOE-14488 ONOE-16493 ONOE-16502 ONOE-16034 ONOE-16325 ONOE-13940 ONOE-16326 ONOE-16412 ONOE-17007 ONOE-16548 ONOE-16293 PIP 98-3826 PIP 99-3533 OSS-0254.00-00-xxxx Modification added relief valve 3DW0539 for thermal overpressure protection for Penetration 55.

Modification revised the SLC to no longer require Appendix J leak rate testing on Penetrations 2 and 58b.

Modification revised the DBD delete requirement for closing 1/2/3HP0363 and added closing requirement for 1/213HP0247, 1/2/3HP0249 and 1/2/3HP025 1.

Modification deleted relief valves 3LPS-0309, 0310, 0312, 0313, 0315, 0316, 0318 and 0319.

Modification revised the MS DBD to clarify the design basis for multiple components.

Modification revised the FDW DBD to change the active status for valves 1/2/3FDW0037 and l/2/3FDW0046 from "Yes" to "No."

Modification revised the AS DBD to clarify the design basis for multiple components Modification revised the HPI DBD and associated TAC sheets to move certain relief valves from the IST program to the Supplemental test program.

OSSW-80 (need to find mod number)

Modification revised the Containment Isolation DBD to remove the containment isolation function for valves 1/2/3PR-121, 127, 136, 137. These valves no longer meet the scope of IST.

Modification to delete the Hydrogen Recombiner DBD. SLC 16.6.10 (Change 2000-08) deleted the function of the Hydrogen Recombiner from the ONS licensing basis.

Modification deleted relief valves ILPS-0309, 0310, 0312, 0313, 0315, 0316, 0318 and 0319.

This item within the ONS corrective action program identified a weakness in the IST program in that certain valves, which had a passive safety function and remote position indication, were not included within the test program. Corrective actions included valves with passive safety functions and remote position indication within the testing program.

• PR-61 was determined to not have an active function since this valve is normally in its safety position.

Based on information within the System Design Basis Document, the identified equipment was determined to be outside the scope of the IST Program.

Page 17 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 RELIEF REQUESTS PUMPS - SPECIFIC RELIEF REQUEST - ADDED The following Relief Requests have been added to the Oconee Inservice Testing Program:

SRP ON-SRP-HPI-01 ON-SRP-HPI-02 Pumps SSF RC Makeup Pumps 1,2,3HPIPU0005 (written 2/26/00)

Unit 3 SSF RC Makeup Pump (written 3/10/02)

PUMPS - SPECIFIC RELIEF REQUEST - DELETED The following Relief Requests have been deleted from the Oconee Inservice Testing Program:

SRP ON-SRP-LPI-06 ON-SRP-TS-05 Pumps Low Pressure Injection Pumps IA, 2A, 3A Keowee Turbine Sump Pumps PUMPS - GENERIC RELIEF REQUEST - DELETED The following Relief Requests have been deleted from the Oconee Inservice Testing Program:

GRP Pumps No revisions VALVES - GENERIC RELIEF REQUEST - ADDED The following Relief Requests have been added to the Oconee Inservice Testing Program:

GRV ON-GRV-15 ON-GRV-16 Valves 1/2/3HP0405, 1/2/3HP0417, 1/2LP00 11, I/2LP0013, OLPSOOO1, OLPS0002, OLPS0003, 3LPS0120, 3LPS0123 1/2RC0164, 1/2RC0165 Programmatic Page 18 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 VALVES - GENERIC RELIEF REOUEST - DELETED The following Relief Requests have been deleted from the Oconee Inservice Testing Program:

GRV ON-GRV-08 ON-GRV-10 ON-GRV-13 ON-GRV-14 Valves Multiple valves Multiple relief valves.

Multiple relief valves Multiple relief valves VALVES - SPECIFIC RELIEF REQUEST - ADDED The following Relief Requests have been added from the Oconee Inservice Testing Program:

SRV Valves No revisions VALVES - SPECIFIC RELIEF REOUEST - DELETED The following Relief Requests have been deleted from the Oconee Inservice Testing Program:

SRV Valves No revisions Page 19 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 JUSTIFICATION FOR DEFERRAL-NEW The following Justification for Deferrals have been added to the Oconee Inservice Testing Program:

JFD ON-LP-10 ON-HP-19 ON-HP-20 ON-MS-07 ON-N-02 ON-HP-21 ON-LWD-01 ON-FDW-06 ON-FDW-07 ON-FDW-08 ON-FDW-09 ON-FDW-10 ON-FDW-1 I ON-CS-02 ON-RC-05 ON-PR-02 ON-HP-22 ON-FO-01 Valves Valves 1/2/3LP-19 and 1/2/3LP-20 Valves 1HP0254, 2HP0494, 3HP0254 Valves 1/2/3HP0451 and 1/2/3HP0453 Valves 1/2/3MS0153, 1/2/3MS0155, 1/2/3MS0161, 1/2/3MS0163 Valves 1/2/3N0246 Valve 1/2/3HP0078 Valves 1/2/3LWD0099, 1/2/3LWD0103 Valves 1/2/3FDW0232, 1/2/3FDW0233 Valves 1/2/3FDW0317, 1/2/3FDW0318 Valves 1/2/3FDW0345, 1/2/3FDW0346 Valves 1/213FDW0373, 1/2/3FDW0383 Valves l/2/3FDW0378, 1/2/3FDW0388 Valves 1/2/3FDW0442 Valves 1/2/3CS0197 Valves 1/2/3RC0207; 1/2/3RC0208 Valves 1/2/3PR0115, 1/2/3PR0116 Valves 1/2/3HP0252 Valve OFO-50 JUSTIFICATION FOR DEFERRAL-DELETED The following Justification for Deferrals have been deleted from the Oconee Inservice T6sting Program:

JFD ON-ESV-01 ON-MS-06 ON-HP-09 ON-FDW-05 ON-LP-05 ON-AS-01 ON-LWD-01 ON-C-04 ON-SSF-05 Valves 2ESV0001, 2ESVO002 1,2,3MS0083, 1,2,3MS0085 1,2,3HP0364 1,2,3FDW0037, 1,2,3FDW0046 1,2,3LP0028 1,2,3AS0039 1,2,3LWD0099, 1,2,3LWD0103 1/2/3C0391 I/2/3FDW0347 Page 20 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 JUSTIFICATION FOR DEFERRAL -REVISIONS The following changes have been made to Justification for Deferrals contained within Oconee Inservice Testing Program:

JFD ON-C-02 Valve Number(s)

C0572 ON-CC-02 CCO020,CC0024,CC0076,CC0077 ON-CF-01 ON-CF-02 ON-CF-03 ON-CS-01 ON-FDW-01 ON-FDW-02 ON-HP-05 ON-HP-06 ON-HP-08 ON-HP-12 ON-HP-13 ON-HP-14 CFOO11, CFOO12 CF0012, CF0014 CF0042, CF0044 CS001 1, CS0012 FDWO033, FDWO042 FDW03 11, FDW0312, FDW0317, FDW0318, FDW0373, FDW0383, FDW0345, FDW0346, FDW0442, FDW0232, FDW0233 HP0097 HP0247, HP0249, HP0251 HP0189 HP0486, HP0487 HP0488, HP0489 HP0188 Change Revised to state the valves are included in the sample disassembly program.

Revised to state the valves will be tested to the open position during each refueling outage.

Revised code category from A/C to C and stated the valves will be tested to the closed position during each refueling outage.

Revised to state the valves will be tested to the closed position during each refueling outage.

Revised to state the open test will be performed during each refueling outage.

Revised to state the open test will be performed during each refueling outage.

Eliminated information concerning FDW-33 and FDW-42 since the valves are no longer within the scope of the IST program.

Revised to include only valves FDW0311 and FDW0312.

New JFDs were created for the remaining valves.

Revised to state both opening and closing tests will be performed during each refueling outage.

Revised code category from B to A.

Revised to state the valves are included in the sample disassembly program to verify both the opening and closing function.

Revised function to include closing during an SSF event. Revised to state the valves are included in the sample disassembly program to verify both the opening and closing functions.

Revised function to include closing during an SSF event. Revised to state the valves are included in the sample disassembly program to-rerify both the opening and closing functions.

Revised function to include closing during an SSF event. Revised to state the valves are included in the sample disassembly program to verify both the opening and closing functions.

Page 21 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 ON-HP-15 ON-HP-16 ON-HP-17 ON-LP-06 ON-LPSW-01 ON-LPSW-03 ON-LPSW-05 ON-N-01 ON-SSF-02 HP0194 HP0248, HP0250 HP0144, HP0145, HP0146, HP0147, HP0390, HP0454, 2HP0286 1/3HP0457, 2HP0389, 1/3HP0393 LP0055, LP0057 LPS0006, LPS0015 1/3LPS0148, 1LPS0151, 2/3LPS0503 LPS-566 N0129, N0131 HP0399, HP0400, HP0401, HP0402 Revised function to include closing during an SSF event. Revised to state the valves are included in the sample disassembly program to verify both the opening and closing functions.

Revised function for valves HP0248 and HP0250.

Deleted valve HP0252 (included in a new JFD).

Revised Code Category from B/C to A/C. Revised to state that the test open and close will be performed during refueling.

Revised to delete valve 2HP286 and include valve 2HP0457.

Revised to state valves are tested to the open and closed positions during each refueling outage.

Changed Code Category from A to B Revised function to delete closing requirement during a tornado event.

Eliminated information concerning LPS-566 since the valve is no longer active.

Revised to state the open test will be performed during each refueling outage.

Revised to state the valves are tested closed during each refueling outage.

Page 22 of 23 Effective 7/01/02

SUMMARY

OF CHANGES INSERVICE TESTING PROGRAM Revision 26 Submitted Oconee Nuclear Station Units 1, 2, and 3 The following PUMP GENERIC RELIEF REQUESTS for Oconee Units 1, 2, and 3 have been renumbered as follows:

Present Number New Number No revisions The following PUMP SPECIFIC RELIEF REQUESTS for Oconee Units 1, 2, and 3 have been renumbered as follows:

Present Number New Number No revisions The following VALVE GENERIC RELIEF REQUESTS for Oconee Units 1, 2, and 3 have been renumbered as follows:

Present Number New Number No revisions The following VALVE SPECIFIC RELIEF REQUESTS for Oconee Units 1, 2, and 3 have been renumbered as follows:

Present Number ON-SRV-CF-10 ON-SRV-CF-17 New Number ON-SRV-CF-01 ON-SRV-CF-02 Page 23 of 23 Effective 7/01/02